ML20059K179
| ML20059K179 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 12/14/1993 |
| From: | POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | |
| References | |
| NUDOCS 9402020003 | |
| Download: ML20059K179 (295) | |
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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK-NUCLEAR POWER PLANT O PARTTAL PARTICIPATION EXERCISE ' OBJECTIVES
-- December 14, 1993 g .2em os p#q 1-1
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p) OBJECTIVES j xj DRILL RULES AND GUIDES 2 SCENARIO OVERVIEW 3 MEETINGS 4 TIMELINE 5
O DRILL / CONTINGENCY MESSAGES O DATA 7 METHOD OF EVALUATION b 9
O 10 cc' M. Cardinar s_
SECTION 1
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'N James A. FitzPatrick Nuclear Power Plant 1993 Partial Participation Emergency Exercise December 14, 1993 OBJECTIVES [
A. PURPOSE This document provides guidance for the announced 1993 1 Emergency Plan Partial Participation Exercise. It will be -
used by James A. FitzPatrick Nuclear Power Plant (JAFNPP) personnel and by all participating local agencies.
b This exercise will demonstrate that the various emergency preparedness functions described below can be performed. The exercise will occur on December 14, 1993.
At no time will the exercise be permitted to interfere with the safe operation of JAFNPP. To ensure this goal is achieved, plant management may suspend the exercise or any part of it for any period of time to avoid operational conflict.
B. NEW YORK STATE OBJECTIVES 1.0 Demonstrate the emergency notifications capabilities through the use of the Radiological Emergency Communications System (RECS) hotline.
C. OSWEGO COUNTY OBJECTIVES ,
1.0 Dcaor. strate the emergency notifications capabilities through the use of the Radiological Emergency
- Communications System (RECS) hotline.
2.0 Demonstrate the activities of the nuclear facility liaison officer at the NYPA EOF. >
i 3.0 Demonstrate the ability to make command and control decisions regarding protective actions. r D. POWER AUTHORITY OBJECTIVES 1.0 Accident Detection and Assessment 1.1 Demonstrate the ability of NYPA staff to identify plant system and effluent parameter values characteristic of off-normal conditions.
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1.2 Demonstrate the capability of NYPA staff to perform-n/
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accident assessment based on.information obtained from samples, radiation and effluent monitors, in-plant iodine. instrumentation and containment radiation monitors.
l 2.0 Empraency Classification System i 2.1 Demonstrate the ability of the plant staff to .t classify actual or potential emergencies in l accordance with NYPA Emergency Plan Implementing
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Procedures.
i 3.0 Notification Methods and Procedures !
3.1 Demonstrate the ability of NYPA staff to provide emergency notifications to the NRC, New York State !
and Oswego County in accordance with established procedures.
3.2 Demonstrate the ability of NYPA staff to fully !
alert, mobilize and activate emergency personnel '
for both facility and field-based emergency functions.
4.0 Emeraency Communications !
4.1 Demonstrate the communication capabilities betwaen NYPA, New York State ari Oswego County via the- !
Radiological Emergency Communications System (RECS) dedicated hotline.
4.2 Demonstrate the communication capabilities between l
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NYPA and the NRC via the Emergency Notification System (ENS). l 4.3 Demonstrate the ability of NYPA staff to coordinate, deploy, and control radiological monitoring teams using the field communications system.
t 4.4 Demonstrate the emergency communication capabilities among the emergency response ~
facilities.
4.5 Demonstrate the ability of NYPA staff to provide technical information to the NRC, New York State and Oswego County.
5.0 Radioloaical Exposure Control 5.1 Demonstrate the capability for continuously O monitoring and controlling exposures and contamination of emergency workers.
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() Demonstrate the methods and resources for
.5.2 distributing dosimetry to emergency workers and >
keeping records of individual radiation exposures.
t 5.3 Demonstrate the ability to correlate effluent monitor readings with onsite and offsite exposures. I 5.4 Demonstrate the capability to acquire and evaluate onsite meteorological information and the provisions to obtain representative current !
meteorological information from other sources.
6.0 Protective Response 6.1 Demonstrate the ability to implement protective ;
actions for site personnel up to and including site evacuation. l 6.2 Demonstrate the capability to account for all ;
individua?.s onsite in accordance with procedures.
6.3 De;cnc; rate the ability of NYPA personnel to recommend protective actions to the State and ,
Oswego County.
6.4 Demonstrate the capability of NYPA staff to O determine the source term of any release of radioactive material from the plant. <
6.5 Demonstrate the ability for using default source terms for release rate and dose projections.
6.6 Demonstrate the ability of NYPA personnel to project field data and to determine appropriate protective measures, based on protective. action guidelines (PAGs), available shelter, evacuation time estimates and all other appropriate factors.
7.0 Staff Auamentation 7.1 Demonstrate the ability of staff to be augmented to handle emergencies at the JAFNPP.
7.2 Demonstrate the ability to identify the need for and to call upon outside support agencies for assistance.
7.3 Demonstrate the ability to direct, coordinate and control emergency activities.
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7.4 Demonstrate the ability of NYPA'to designate an
( individual who is in charge of the emergency response and who makes decisions and coordinates emergency activities.
8.0 Shift Staffina 8.1 Demonstrate personnel availability for 24-hour per day emergency response and continuous emergency activities.
8.2 Provide for a line of succession for the emergency director position.
8.3 Demonstrate the Emergency Director's knowledge of and approval of all notifications and protective action recommendations made to offsite authorities.
8.4 Demonstrate NYPA and/or contractor personnel availability for logistics support, technical support, interface with governmental. authorities and release of information to the news media.
9.0 Emercency News Center (Joint News Center) 9.1 Demonstrate the ability to brief the media in an accurate, coordinated and timely manner.
9.2 Demonstrate the ability to coordinate the formulation and dissemination of accurate information to the public in a timely fashion, including press releases.
10.0 Fire Bricade 10.1 Demonstrate the ability of the fire brigade to respond to a simulated fire onsite.
11.0 Headauarters Support Personnel 11.1 Demonstrate the use.of the New York Power Authority's Emergency Response Center in the White Plains Office.
12.0 Field Monitorina 12.1 Demonstrate the capability to acquire and evaluate air, liquid or solid samples (as appropriate) to assist in assessing the magnitude of any release.
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13.0 Release Maanitude O
A' 13.1 Demonstrate the use of appropriate equipment and procedures for the measurement of airbogne radiciodine concentrations as low as 10 -
microcuries per cc in the presence of noble gases.
13.2 Demonstrate the ability to obtain samples of particulate activity in the airborne plume and ..
perform laboratory analysis promptly, as appropriate. ;
14.0 Post Accident Samplina System (PASS)
- t 14.1 Demonstrate the capability to acquire and analyze ;
PASS sample during a specified time period.
15.0 Potassium Iodide (KI) 15.1 Demonstrate the ability to consider the use of KI '
in an emergency situation.
16.0 Assembly and Accountability 16.1 Demonstrate the ability to assemble and account for personnel within the protected area. ;
17.0 Emeraency Facilities and Eauipment 17.1 Demonstrate the capability of the Technical Support ,
Center facilities, displays and equipment to support emergency operations.
17.2 Demonstrate the capability of the Operational l~
Support Center facilities, displays and equipment to support emergency operations.
17.3 Demonstrate the capability of the (EOF) facilities, displays and equipment to support emergency operations.
17.4 Demonstrate the ability to use onsite monitoring ,
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systems to initiate emergency measures and conduct assessments.
I 17.5 Demonstrate the use of appropriate equipment and procedures for determining field radiation measurements.
18.0 Emeroency Plan Improvement 18.1 Demonstrate press releases can be written
() adequately.
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'I 18.2 Demonstrate Protective Action Recommendations O' (PARS) are'not modified solely to match offsite agencies-PARS.
18.3 Demonstrate the prioritization of work and the I ability to dispatch work teams in a timely fashion l to respond to important events.
18.4 This exercise will allow and include response by individuals designated to assume positions in the .
JAFNPP Emergency Organization. This exercise will
- serve as practical-based training for individuals that are assigned to the Emergency Plan Organization. These individuals will be coordinated by the JAFNPP Emergency Plan trainer ,
and documented on a training addendum.
18.5 Demonstrate the ability for self-critique and identification of areas requiring improvement.
E. INTENT OF THE FITZPATRICK EXERCISE SCENARIO This exercise is intended to demonstrate many, but not all, of the Authority's capabilities to respond to emergency conditions. This scenario simulates operating cor,?_itions and j provides a sequence of events as a basis to demonstrate the fs ability to exercise the emergency plans and procedures. Free play is encouraged, and the referees will interfere only if operator / player action prematurely terminates the exercise or excessively deviates from the schedule.
F. CONDUCT OF OPERATIONS AND CONTROL OF THE EXERCISE The Authority will supply official controllers / evaluators for .
locations where an emergency response is being demonstrated.
Prior to the exercise, the controllers and evaluators will be provided with locations, maps, time periods, guidelines (such as training in equipment use and procedures), and an evaluation checklist for their exercise assignments.
The exercise initiating events and information will be controlled by the lead controller at the JAFNPP. The lead controller will have the responsibility to control and coordinate the time sequence of initiating events.
As the initiating events are provided to the JAFNPP staff, ,
they will determine the nature of the emergency and implement '
appropriate emergency response procedures. These procedures
- include a determination of the emergency classification and notification of appropriate Federal, State and local authorities.
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The simulated accident will continue to develop based on data O and information provided to personnel by a controller.
Certain inconsistencies (such as technical reasons for equipment failures) may be intentional. Such inconsistencies '
may be necessary due to the difficulties of simulating an accident that has never occurred, and the requirement to 7 provide a exercise basis which tests the site capabilities to e
'the maximum exterc feasible in a limited time. The lead controller. shall have the authority to resolve cnr explain any inconsistencies or problems that may occur during the. .
exercise. With the exception of such potential inconsisten-cies, the internal operation of the site facilities shall be identical with their intended operation in a real emergency.
G. MAINTAINING EMERGENCY READINESS Actions taken by the participants will not reduce plant or -l public safety. The potential for creating real radiological or other emergencies shall be specifically avoided. All '
messages about real events will be clearly identified.
i During the exercise, the ability to recognize real emergency conditions will be maintained. The exercise will be termi- ,
nated in the event a real emergency condition exists. The '
exercise scenario will not result in degradation of systems, equipment or supplies, nor will it affect the detection, assessment or emergency response capability of the plant.
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SECTION 2 James A. FitzPatrick Nuclear Power Plant' 1993 Partial Participation Emergency Exercise December 14, 1993 '
i EXERCISE RULES AND GUIDES I. Ground Rules II. Scope III. Safety Precautions IV. Exercise Conduct V. Exercise Report j VI. Special Information VII. Simulator Pre-Exercise Preparations
() VIII. Simulator Communications ;
IX. Simulator Malfunctions l X. EPIC Screens Available .
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. SECTION 2 i k/ James A. Fit', Patrick Nuclear Power Plant 1993 Partial Participation Emergency Exercise December 14, 1993 GROUND RULES i
The 1993 NRC observed emergency exercise will be conducted on December 14, 1993. The purpose of this exercise is to demonstrate that various emergency preparedness functions can be performed. '
Since this exercise is not full-scale, limited participation by ;
Oswego County and New York State is expected.
All exercise participants are required to cbserve the following !
exercise Ground Rules for the entire duration of the exercise:
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- 1. Ensure that all communications indicate that this is only an j exercise. Make a positive statement that this is an exer-cise-related message at the beginning and end of all mes-sages or conversations. If communication lines are kept O open for extended periods, periodically repeat the caution.
This is especially critical when transmitting messages over communications facilities that are monitored by non-Power ,
Authority personnel.
- 2. Take no actions that affect plant or non-exercise related operations. Communications to or from'the simulator must be prefaced with "This is a drill. This is a drill. "
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- 3. Take immediate action (s) to restore safe operation, if an unsafe condition exists. Ignore exercise situation if actual safety becomes a concern.
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- 4. Use only the information provided in accordance with the i exercise ground rules or derived from approved procedures. !
Do not improvise information.
- 5. Be sure that the observer / controller is aware of your actions (actual or simulated).
- 6. Make all required notifications.
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- 7. If samples inside or outside the site are deemed necessary, l they will actually be collected, if possible, and their analysis conducted or simulated, as directed. Observer / ] l
-[~' Controllers will accompany the survey teams and repair teams, both onsite and offsite.
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N- James A. FitzPatrick Nuclear Power Plant 1993 Partial Participation Emergency Exercise December 14, 1993 f
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GROUND RULES (continued)- l
- 8. NRC personnel will be evaluating the performance of the :
participants at each location. .
- 9. This exercise is conducted to evaluate our plans and procedures. This exercise is also a training vehicle for members of the JAFNPP Emergency Response Organization to i
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practice working together and with outside organizations.
Please make note of any improvements in any' area that you !
observe as a participant and submit them to the Observer /
Controllers at the conclusion of the exercise.
- 10. Controllers will provide appropriate information at the :
location where that information would normally be available (e.g., Reactor status at the Control Room, dose rate read-ings with field teams, etc.).
- 11. Only parameters and readings available to the simulator will be provided. The selected information will be sufficient to make decisions in accordance with JAFNPP plans and procedures.
- 12. DO NOT BECOME OVERLY CONCERNED WITH THE MECHANICS OF THE REACTOR OR THE CAUSE OF THE ACCIDENT. THIS EXERCISE IS i DESIGNED TO TEST JAFNPP PLANS AND PROCEDURES AND IS NOT CONCERNED WITH ESTABLISHING THE PROBABILITY, FEASIBILITY OR DETAILED MECHANICS OF THE SIMULATED ACCIDENT. 1
- 13. .There will be one or more Observer / Controller at each important location. Controllers will provide information and clarification on which actions are to be simulated or are outside the scope of this exercise in order to keep the excrcise progressing in accordance with the scenario.
Observer / Controllers will also observe all aspects of the exercise to prepare an in-house evaluation of plans, procedures and training.
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SECTION 2 ;
.O James A. FitzPatrick Nuclear Power Plant 1993 Partial Participation Emergency Exercise December 14, 1993 Y
- 14. If, during any part of this exercise, you are having trouble accomplishing your required duties, confusion arises, or ,
clarification is necessary, ask your Controller. Controller assistance or clarification does not necessarily imply ,
failure on your part. Your Controller will know the limita- l tions of information he can provide you, and will assist you' -
only to the extent necessary.
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-l SECTION 2 i i
James A. FitzPatrick Nuclear Power Plant 1993 Partial Participation Emergency Exercise ;
i December 14, 1993 SCOPE {
, The following is a list of the JAF emergency facilities and f' functions to be demonstrated or simulated during the exercise.
l' I. Functions and Facilities to be Demonstrated Simulator Usage Operational Support Center .i Technical Support Center. {
Emergency Operations Facility l Dose Assessment i Restricted Area Evacuation and Assembly -[
Offsite Radiological Monitoring ;
Onsite Communications 1 :
Offsite Communications f O Onsite Radiological Measuring Onsite Repair and Corrective Actions l
Accident Assessment i Notifications l Communications Systems !
Accountability '
Facility Ventilation Isolation Post Accident Sampling System !
Fire Brigade
- II. Eunctions and Facilities to be Simulated Protective Action Recommendations Security Access Control to Site Site Evacuation ,
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>l SECTION 2 James A. FitzPatrick Nuclear Power Plant !
1993 Partial Participation Emergency Exercise
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December 14, 1993 ,
I SAFETY PRECAUTIONS ,
During the performance of an exercise, the ability to recognize a real emergency, terminate the drill, and respond to the new
- situation must be maintained. Therefore, the drill scenario ;
shall not include any actions which degrade the condition of r
systems, equipment or supplies, or affect the detection, assessment or response capability to radiological or other ,
emergencies at JAFNPP. ?
Actions taken by the participants shall also avoid actually reducing plant or public safety. The potential for creating real radiological or other emergencies shall be specifically avoided.
If a local emergency occurs during a training drill requiring the local agency to terminate its participation in the drill, the agency should notify the State and Oswego County Emergency O
Operations Centers of the situation. All messages about real !
events shall be clearly identified as such. For example, precede l a real message with "This is NOT, repeat, NOT an exercise !
message".
The following JAFNPP personnel may cancel or stop the training
- drill at any time that plant or public safety is jeopardized by l the conduct of this exercise.
- 1. Resident Manager !
- 2. General Manager - Operations
- 3. (On Shift) Shift Supervisor
- 4. Emergency Planning Coordinator '
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SECTION 2 ,
O James A. FitzPatrick Nuclear Power Plant 1993 Partial Participation Emergency Exercise .
December 14, 1993 EXERCISE CONDUCT ,
i Exercises at JAFNPP are conducted under the guidance of Emergency '
Plan Procedure SAP-1 " Maintaining Emergency Preparedness" (attached). This procedure lists the. specific requirements for drills and exercises, and includes the requirements for the development of scenarios for drills and exercises. 3 Please review the following procedure for specific information concerning the conduct of this exercise.
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NEW YORK POWER AUTHORITY O
JAMES A. FITZPATRICK NUCLEAR POWER PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE EMERGENCY PLAN VOLUME 3 I
PROCEDURE NO.: SAP-1 i *
- i INFORMATIONAL USE j TIPLE: MAINTAINING EMERGENCY PREPAREDNESS
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APPROVED BY:
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7 Resident Managerd e
APPROVED BY: . .
T "Enfriency J Planning Coorhtnr )
PAGE NO. 1 2 3 4 5 6 7 8 9 10 11 REV. NO. 9 9 9 9 9 9 9 9 9 9 9 PAGE NO. 12 13 14 15 16 17 18 19 REV. NO. 9 9 9 9 9 9 9 9 ,
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. EMERGENCY PLAN IMPLEMENTING PROCEDURE
~~- SAP-1 MAINTAINING EMERGENCY PREPAREDNESS
- 1.0 PURPOSE This procedure details the actions to be taken to maintain f emergency preparedness at the JAFNPP site. The procedure establishes a method for the conduct and evaluation of a drill or exercise at the JAFNPP. This procedure also outlines the management controls used to ensure that ;
corrective actions are implemented. l
2.0 REFERENCES
t' 2.1 NUREG-0654 -
" Criteria for the Preparation and i Evaluation of Radiological Emergency Response Plans and l Preparedness in support of Nuclear Power Plants" ;
2.2 JAFNPP Emergency Plan, Volume #1 l
2.3 ITP-1 MANAGEMENT OF TRAINING GROUP RECORDS 2.4 ITP-3 GENERAL EMPLOYEE TRAINING ,
) 2.5 ITP-12 EMERGENCY RESPONSE TRAINING.
2.6 AP-02.03 CONTROL AND DISTRIBUTION OF EMERGENCY PLAN AND PROCEDURES 6 f
2.7 QA-18.1 OUALITY ASSURANCE AUDIT PROGRAM-PLANT 2.8 SAP-6 DRILL / EXERCISE CONDUCT 2.9 SAP-3 EMERGENCY COMMUNICATIONS TESTING 2.10 IAP-2 CLASSIFICATION OF EMERGENCY CONDITIONS i
2.11 JAFNPP EMERGENCY PLAN IMPLEMENTING PROCEDURES, i I
VOLUMES 2 and 3 2.12 NRC Generic Letter 82-23 2.13 Volume 10 Code of Federal Regulations, Part 50.55
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3.0 INITIATING EVENTS Not Applicable i Rev. No. 9 Page 1 of SAP-1 m_ __.-__ _ _ _ __ _ _ _ _ _ _ _ _ _ . - - -r
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4.0 PROCEDURE V 4.1 General - Emergency preparedness at JAFNPP is maintained through an integrated program of training, 7 drills, exercises, plan and procedure maintenance, and ,
audits. j 4.1.1 Training - Plant staff and outside support ,
agencies are given formal classroom training in accordance with ITP EMERGENCY PREPAREDNESS TRAINING. Formal training consists of classroom instruction and written quizzes and
- examinations. Drills and exercises are utilized to evaluate emergency preparedness, and the results of these are input to subsequent i
training.
4.1.2 Drills - A drill is a hands on, supervised instruction period aimed at testing, developing-and maintaining skills in a particular ;
operation. Drills at JAFNPP are conducted in accordance with the schedule and guidelines of section 4.3 of this procedure. l 4.1.3 Exercises - As defined in NUREG-0654, an exercise is an event that tests the integrated capability and a major portion of the basic elements existing within emergency plans and ,
organizations. Exercises at JAFNPP are conducted in accordance with the schedule and guidelines of section 4.4 of this procedure.
4.1.4 Plan and Procedure Maintenance - Maintenance of ;
the JAFNPP Emergency Plan and Implementing procedures consists of document control i~
activities including distribution control, change control, procedure review, and cross reference review. Plan and procedure maintenance is in accordance with AP-02.03 '
CONTROL AND DISTRIBUTION OF EMERGENCY PLAN AND .
IMPLEMENTING PROCEDURES.
4.1.5 Audits - The JAFNPP emergency preparedness program (in accordance with reference 2.12) is audited at least once every 12 months in accordance with Quality Assurance Manual Procedure 18.1 - OUALITY ASSURANCE AUDIT PROGRAM
- PLANT. Findings and corrective action records shall be maintained by the QA department in accordance with their procedures.
4.1.6 Drill / Exercise Documentation - Documentation for O drills and exercises shall be maintained by the Training Manager. Documentation shall be developed in accordance with section 4.5.
Rev. No. 9 Page 2 of SAP-1
4.1.7 Drill / Exercise Conduct, Observation, Critiqyes fx) l
(, and Deficiencies - A formalized method for evaluating a drill or exercise has been established. SAP DRILL / EXERCISE CONDUCT
- details the method for conducting the 3 Drill / Exercise Observation Program, ' Critique, i and Deficiency action. l 4.2 Trainina - The responsibility for training is shared by ,
the Training Manager and the Emergency Planning :
Coordinator. !
4.2.1 Training Manager - The Training Manager is .
responsible for the formal classroom training of. l onsite and offsite individuals who have duties l in the emergency organization. The Training i Manager is also responsible for specialized training services such as fire fighting and [
emergency medical services. The Training ,
Manager is responsible for fire brigade drills. ;
i 4.2.2 Emergency Planning Coordinator - The Emergency ,,
Planning Coordinator is responsible for ,
communications, medical emergency (contaminated f injury), radiological monitoring and radiation protection drills.
Initial training and periodic retraining shall I 4.2.3 be conducted in accordance with ITP-1, ITP-3, :
and ITP-12. ,
l 4.2.4 Formal training shall be documented using a. l Training Report (as defined by Training procedures).
4.2.5 The Training Manager shall be responsible for r maintaining all Emergency Plan. training records. l This shall include records of all formal l training sessions, drills and exercises.
4.3 Drills - Responsibility for the conduct of drills is divided between the Emergency Planning Coordinator !
(EPC) and the Fire Protection Supervisor (FPS)/ Fire Protection Training Specialist. There are five drill areas: ;
i A. Communication Drills - Emergency Planning coordinator.
Communications with Federal, State and local governments within the Emergency Planning Zones shall be tested monthly. Communications between O the nuclear facility, State and local emergency operations centers, and field assessment teams i
shall be tested annually. Communication drills Rev. No. 9 Page 3 of SAP-1 ,
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f-' shall also include the aspect of understanding the
( content of messages via the observer evaluation.
Documentation for communication drills shall be in accordance with procedure SAP EMERGENCY COMMUNICATIONS TESTING. Communication drills shall be reviewed by the Emergency Planning Coordinator.
B. Fire Drills - Fire Protection Supervisor / Fire Protection Training Specialist.
Fire drills shall be conducted in accordance with the plant technical specifications, Fire Protection Procedures and Training Procedures. Response to an actual fire may be counted as a drill.
Documentation of Fire' Drills shall be done by the Training Manager in accordance with ITP-13.
C. Medical Emercency Drills - Emergency Planning Coordinator.
A medical emergency drill involving a simulated contaminated individual which contains provisions for participation by the local support services agencies (i.e., Oswego Hospital, SUNY Health Science Center and the Oswego Fire Department Ambulance) shall be conducted annually. The
[] medical drill may be performed as part of the
\m/ required annual exercise. Response to an actual medical emergency may be counted as a drill.
Documentation of Medical Emergency Drills shall be done by completing Form SAP-1.13' Drill Report" and a drill scenario and providing a completed copy to the Training Manager. >
D. Radiolocical Monitorina Drills - Emergency Planning j Coordinator.
Plant environs and radiological monitoring drills (onsite and offsite) shall be conducted annually.
These drills shall include collection and analysis of all sample media (e.g., water, vegetation, soil and air), and provisions for communications and -
record keeping. This drill may be conducted as part of the JAFNPP Annual Exercise. Documentation l for Radiological Monitoring Drills shall be done by completing Form SAP-1.1 " Drill Report" and a drill scenario and providing a completed copy to the Training Manager. .
E. Radiation Protection Drills - Emergency Planning Coordinator.
( (1) Radiation Protection drills shall be conducted semi-annually which involve response to, and i analysis of, simulated elevated airborne and Rev. No. 9 Page 4 of SAP-1 i
liquid samples and direct radiation O
measurements in the environment.
(2) Analysis of in-plant liquid samples with actual or simulated elevated radiation levels ,
including use of the post-accident sampling system shall be included in Radiation ,
Protection drills. This drill may be conducted as part of the JAFNPP Annual Exercise. Documentation of Radiation r Protection Drills shall be done by completing Form SAP-1.1 " Drill Report" and drill scenario ,
and providing a completed copy to the Training Manager. Response to an incident involving elevated airborne or liquid activity or elevated radiation levels may be counted as a drill. !
4.3.1 Drill Scheduling - The Emergency Planning Coordinator shall be responsible for the ,
scheduling of all drills with the exception of Fire Drills, which is the responsibility of the '
Fire Protection Supervisor / Fire Protection Training Specialist. To the greatest extent possible drills should be scheduled in :
conjunction with each other to minimize interference with plant operating schedules.
O (Examp'e: Exercising fire, medical and communications aspects of the emergency plan in '
conjunction with the JAFNPP Annual Exercise.) ,
6 4.4 Exercises An emergency response exercise is an event that tests ,
the integrated capability of a major portion of the basic elements contained in the JAFNPP Emergency Plan.
An exercise can be comprised of numerous drills conducted simultaneously.
The purpose of the annual exercise, as described in NUREG-0654 is to test a full scale response '
capabilities of the Plant, State, Local and Federal agencies. The Plant is directly involved and is ;
evaluated on its response to the simulated emergency situation.
The JAFNPP is required to conduct an exercise annually.-
The exercise shall either be a full scale exercise which will include full participation by State and Local agencies or a small scale exercise that shall include only limited participation of State and Local agencies.
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l 4.4.1 All personnel at'JAFNPP may participate in an emergency exercise. (Note: Only Fire Brigade personnel may participate in a fire drill.)
4.4.2 An exercise shall be developed and should include the Alert, Site' Area or General Emergency.
4.4.3 The scenario should be varied from year.-to year such that all major elements of the plans and preparedness organizations are tested within a five year period. Once every six-years an l exercise shall be off-hours. Some exercises should be unannounced. The EPC shall maintain a five year schedule of all major elements to be tested. ,
4.4.4 offsite support agencies should be contacted and included in the development of a JAFNPP Exercise, and requested to supply observers. -
t 4.4.5 Exercises of emergency preparedness should -
simulate an emergency that results in offsite radiological releases which would require .
responses by offsite authorities.
4.4.6 Exercises should be conducted under various O weather conditions. To facilitate this, since the Emergency Planning Coordinator cannot reliably schedule drills'in advance to coincide with adverse weather, it is advisable not to cancel or postpone drills based on unexpected inclemencies unless continuation would constitute undue risk to the-participants or to the plant.
4.4.7 The annual exercises shall be planned in advance via a formal scenario incorporating simulated plant, environmental, and personnel related events (input by controllers) to guide the action and allow for free play.
4.4.8 Documentation of the exercise shall be conducted in a manner consistent with section 4.5 of this procedure.
4.5 Drill and Exercise Development and Documentation 4.5.1 Development Responsibilities - The Emergency Planning Coordinator shall insure the 1 development, planning, scheduling and _
coordination of all drills / exercises involving O the JAFNPP Emergency Plan. ;
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4.5.1.1 The Training Manager shall be 7- responsible for the maintenance of it
\~- copies of all approved drill / exercise scenarios and associated documents in accordance with approved Training Department procedures.
4.5.1.2 The Fire Protection Supervisor shall assist the Emergency Planning.
Coordinator in preparing drill / exercise scenarios.
4.5.1.3 The Operations Manager shall provide assistance to the Emergency Planning Coordinator in preparing drill / exercise scenarios.
4.5.1.4 The Radiological and Environmental Services Manager shall provide assistance to the Emergency Planning coordinator in preparing drill / exercise scenarios.
4.5.1.5 The General Manager - Operations, General Manager - Maintenance and the General Manager - Support Services
(~ shall provide assistance to the
( Emergency Planning. Coordinator in preparing drill / exercise scenarios.
4.5.1.6 The Vice President of Public' Relations shall provide assistance-to the Emergency. Planning Coordinator in preparing the drill / exercise scenarios.
4.5.1.7 A representative of the PORC with a senior reactor operator's license shall review drill / exercise scenarios.
4.5.2 Drill Scenario Development and Documentation -As a minimum, a drill scenario shall be organized to include the following (See Form SAP-1.4):
(1) Drill
Title:
(e.g., Refueling accident, loss of. coolant accident, etc.). Refer to IAP-2, CLASSIFICATION OF EMERGENCY CONDITIONS for information.
(2) Obiectives: The basic objective of the drill.
(3) Scope: Date, time, duration, location, and
() participating onsite and offsite organizations.
Rev. No. 9 Page 7 of SAP-1
M' i
. (4) Safetv Precautions:. Safety precautions.to l
,( )
be followed. '
(5) Time Schedule: A time schedule of initiating events including expected or simulated plant alarms, indications, or .
emergency classifications.
^
(6) Summarv: A narrative summary describing
~
the conduct of the events to include such things as simulated casualties,-offsite department assistance, rescue of personnel, evacuation required, use of-protective.
clothing, deployment of radiological monitoring teams, and.public information activities.
(7) Data: Data related to drill in question.
(8) Drill Report: (With arrangements for qualified observers.) This report.
describes information pertinent to the understanding of the drill intent. A sign-off sheet for PORC representative, and a list of. observers and controllers.
EPIC Screens:
O (9) An accurate list of EPIC screens will be developed and displayed on the EPIC terminals.
4.5.3 Exercise Scenario Development and Documentation - An exercise scenario'shall be organized to. include-(See Form SAP-1.4): l (1) Exercise
Title:
(e.g., Refueling accident, loss of coolant accident, etc. ) . Refer . to IAP-2, CLASSIFICATION OF EMERGENCY CONDITIONS for information.
(2) Obiectives: State basic objectives of the proposed exercise and which portions of the Emergency Plan will be tested.
(3) Rules and Guidelines: Date, time, duration, location, and participating onsite and offsite organizations. Also to include, date, time,'and location of observer briefings and critique. Includes all ground rules, scope, safety precautions and procedure for exercise conduct.
(4) Event Summary: Includes scenario overview, O reactor vessel level and pressure graphs, dose assessment displays and meteorological forecasts. ,
Rev. No. 9 Page 8 of SAP-1
x . (5) 'Meetinas: A time schedule for training,
.g , )- badging, briefings, plant tours and critiques.
(6) Timeline: A time schedule of major events and emergency classifications.
(7) Messaces: Includes completed sheets for '
use in the exercise detailing activities, events, time, and sequence. See Forms SAP--
1.2 and SAP-1.3.
(8) Data: Includes Emergency and Plant Information Computer (EPIC), ARM's and_In-plant Rad Maps, PASS data, Environmental Sample Data, and Offsite Rad Data.
P (9) Anticipated Actions: A timeline of anticipated actions that should~be taken by emergency facilities.
(10) Method of Evaluation: Contents should include the standard to which evaluation shall be made and supporting documentation.
(11) EPIC Screens: An accurate list of EPIC '
,Q screens will be developed and displayed on
-(d the EPIC terminals.
5.0 FIGURES. FORMS AND ATTACHMENTS 5.1 FORM SAP-1.1, Drill Report 5.2 FORM SAP-1.2, Summary Information 5.3 FORM SAP-1.3, Message Sheet 5.4 FORM SAP-1.4, Drill and Exercise Scenario Development Checklist t
V Rev. No. 9 Page 9 of SAP-1
- FORM-SAP-1.1 Page 1 of 7
_[ JAMES A. FITZPATRICK NUCLEAR POWER PLANT EMERGENCY PLAN DRILL REPORT Drill / Exercise
Title:
_.1_993 Partial Participation Emercency Exercise '
December 14, 1993 Drill / Exercise Date:
Reviewed By: -
ID!? 3 Emergency Planning C h inator/ D a t'e /
Fire Protection Supervisor Reviewed By: k - # /d 93 PORC Rspresentative Date/ i O '
4 Copies to:
- 1. JAFNPP EMERGENCY PLANNING COORDINATOR
- 2. JAFNPP TRAINING MANAGER O
Rev. No. 9 Page 10 of SAP-1
.- . . = - . .
FORM SAP-1.1' Page 2 of.7 ,
DRILL REPORT
- 1. Time Frame December 14, 1993
- a. Drill / Exercise date
- b. Date of last similar drill / exercise September 1, 1993
- c. Real time span of drill 4h hours, days
- d. Drill / Exercise time frame 4h hours, days ,
- e. Season (circle one)
Winter Spring Summer Fall -
- f. Period of the week (circle one)
Weekend Holiday
- g. What shift shall the drill begin on?
.-3 3 p.m. - 11 p.m. 11 p.m. -7 a.m. -
- 2. Maximum level of emeraency classification durina the drill / exercise (check one).
Notification of Unusual Event s
Alert ,
Site Area Emergency .
X General Emergency i l
Does not apply- l l
- 3. Oraanization Involvement (Circle anolicable) ]
I
- a. NYPA Control Room Staff / No Technical Support Center (TSC) es No i
Emergency Operations Facility (EOF) p No l
l I
O l Rev. No. 9 Page 11 of' SAP-1 ;
l
FORM SAP-1.1 Page 3 of 7 I DRILL REPORT
- 3. Orcanization Involve 1 tent (Circle acclicable) (Continued)
Site Security / No Fire Brigade / No White Plains Office (WPO) /.No Joint News Center (JNC) h / No Operational Support Center (OSC) h / No Alternate Operational Support Center (AOSC) Yer /
> First Aid Team Yes /
- b. Non NYPA NY State Emergency Management Office / No NY State Department of Health Yes / '
NY State Office of Disaster Preparedness Yes /
NY State Bureau of Radiological Health Yes/h US Nuclear Regulatory Commission Yes /
US Department of Energy Yes /
US Coast Guard Yes /
Niagara Mohawk Yes/h Oswego County Emergency Management Office / No Oswego County Sheriff Yes /
Oswego Hospital Yes /
SUNY Health Science Center at Syracuse Yes / >
Oswego Fire Department Ambulance Yes/h). ,
General Electric Yes/h L Other (Soecifv)
O 5
Rev. No. 9 Page 12 of SAP-1 t
' FORM SAP-1.1 Page 4 of 7 DRILL REPORT
- 4. Communications
- a. S all the JAFNPP Radio System be used for communications? ,
es / No
- b. Should a news release be prepared?
/ No
- c. Activation of Joint News Center? :
/ No
- d. Activation of Public Notification System /EBS?
Yes/f}[)
- 5. Drill / Exercise Elements
- a. Will key emergency response positions be relieved by shift change?
Yes /
- b. Is a contaminated medical injury to be involved?
Yes/{N{)
If yes, (1) Onsite response by First Aid Team Yes / No O (2) Offsite response Yes / No (Circle Agencies Involved) oswego Hospital SUNY Health Science Center at Syracuse Oswego Fire Department Ambulance Other
- c. Wi 1 the exercise involve a simulated f.
es / No (1) Onsite response es /
(2) Offsite response es /
(Circle Agencies Involved)
Oswego Fire Department Scriba volunteer Fire Department Volney Volunteer Fire Corporation Alcan Fire Department Minetto Volunteer Fire Department i
I Rev. No. 9 Page 13 of sap-1
l l
FORM SAP-1.1 Page 5 of 7 O DRILL REPORT j
- 5. Drill / Exercise Elements (Continued)
- d. W' 1 the Security Force response be tested?
xes / No (1) Sabotage / Bomb Yes / N (2) Intruder Yes / o (3) Accountability @/o
- 6. Radioloaical Release h / No ;
- a. Meteorological capabilities.
(1) Will real-time meteorology be used? Yes / h (2) Will fixed meteorology be used? / No
- b. Dose Assessment.
(1) Will dose projection be made using computerized model? h No (2) Will field monitoring teams be dispatched? / No
( (3) Will dose projections warrant protective action recommendations? h / No
- c. Post Accident Sampling.
(1) Are samples of stack iodine / particulate sample required? / No (2) Should a reactor coolant sample be taken? No i
- d. Environmental.
(1) Should environmental media be collected? h/No (2) Should sampling devices be collected from environmental stations? Yes /h
- 7. Attached is a copy of the scenario for this drill. / No !
O t Rev. No. 9 Page 14 of SAP-1 i
t FORM SAP-1.1 Page 6 of 7 {
DRILL REPORT
- 8. Drill Controllers i
Name Location {
Lead Controller Catella. Fred Simulator Controller Romanowski, Joseph Simulator f Controller Prarie. Mark Control Room Controller Avrakotos. Nicholas TSC Controller Phv. Ken OSC Controller Flaherty. Joseoh EOF t
Controller Fine. Ira JNC i
Drill Controller / Observers Cont /Obser Boucher. Crystal Chemistrv/ PASS '
Cont /Obser Heath. Alan Fire Protection Cont /Obser MacCammon. Gordon Security Cont /Obser Farlev. Michael DESTINY Cont /Obser Mozzor. Matty Dose Assessment Drill Suonort Personnel I
Operator Morris. James Simulator ;
l
. Hardware Perrine. Garfield Simulator
Rev. No. 9 Page 15 of SAP-1
~ . _ . - . , . .
FORM SAP-1.1 Page 7 of 7 ,
\
DRILL REPORT i
- 9. Observers Name Orcanization Area of Responsibility Simoson, Don JAF TSC l Mayer, Dave JAF OSC Renair Team C/O Johnson, Neal JAF OSC Repair Team C/O Hocan, Mike JAF OSC Repair Team C/O Buiniskis, Tony JAF OSC Repair Team C/O Rottenberk. Robt JAF OSC Renair Team C/O To Be Determined IP-3 OSC'Renair Team Cf0 Feicenbaum. Paul WPO Onsite Field Monitoring ,
Grosiean, Alain WPO Offsite Field Monitoring .
Ellmers. Judd WPO Offsite Field Monitoring Childs, Verne JAF JNC Faison, Charlene WPO EOF To Be Determined IP-3 Simulator 1
k i
l
() t Rev. No. 9 Page 16 of SAP-1
-e, w ~,. +
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O O O JAFNPP EXERCISE CONTROLLERS / OBSERVERS December 14,1993 Fred Catella 349-6450 Joe Flaherty Matty Mozzor Lead Controller 593-5875 p 593-5831 (EOp .
349-6333 ntroHer NhmM h.
- Control Room Controiler
. ira Fine Charlene Faison 342-5900 Mike Farley EOF Obserwr JNC Controller 349-6165 ,
DESTINY Controlier i
, Verne Childs ,
Joe Romanowski 349-6448 Simulator Controller Nick Awakotos 349-6719/6770 To Be Determined TSC Controller Simulator Observers i Don Simpson TSC Observer 349-6225 Alan Heath OSC Controller Fire Protection Cont /Obser Gordon MacCammon Alain Grosjean Security Cont /Obser ea Johnson ,
(offsite - 593-5005) Mike Hogan Judd Ellmers Tony Buiniskis -
(offsite - 593-5037 or 8) Bob Rottenberk CrystalBoucher SIMLM.ATOR FAX: 349-6464 Paul Feigenbaum Chemistry / PASS C/O ,
(onsite - 593-5037 or 8) Repair Teams C/O CONTROL ROOM FAX: 349-6323
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j FORM SAP-1.2
SUMMARY
INFORMATION ,
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l l.. . . .. . - . . _ _ - .
F-F
. FORM SAP-1.3 Page of i ,
1 MESSAGE SHEET ,
MESSAGE NO. -
(
Exercise Time:
Issued To:
i Issued By:
4 MESSAGE :
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t Rev. No. 9 Page 18 of SAP-1
FORM SAP-1.4 .
DRILL AND EXERCISE SCENARIO DEVELOPMENT CHECKLIST (Use this checklist as a reference for drill or exercise development.) [
DRILLS
- 1. Drill Title '
- 2. Objectives [
- 3. Scope
- 4. Safety Precautions !
- 5. Time Schedule
- 6. Summary ,
- 7. Data .
.t
- 8. Drill Report O- 9. Accurate List of Valid EPIC Drill Screens EXERCISES i i
- 1. Exercise Title ;
- 2. Objectives i
- 3. Rules and Guidelines l
- 4. Event Summary 'l
- 5. Meetings ,
e
- 6. Timeline .
l
- 7. Messages ,
- 8. Data. !
- 9. Anticipated Actions l l
- 10. Method of Evaluation {
SECTION 2 James A. FitzPatrick Nuclear Power Plant 1993 Partial Participation Emergency Exercise December 14, 1993 EPECIAL INFORMATION
- 1. Simulate all contacts to any offsite agencies with the exception of Niagara Mohawk, Oswego County and New York.
State. (RECS calls should be made in accordance with !
procedure.)
- 2. Contact to NRC over ENS should be by procedure. Follow their instructions. Expect to have only the initial call and close of drill call.
- 3. There will be no impact to the new Support and '
Administration Building. If a site evacuation is conducted, building may be vacated.
- 4. Training currently scheduled will continue, with the !
O limitation that each manager must ensure that " Emergency Response Organization" staff positions are filled.
J
- 5. WPO Emergency Response Center (ERC) will be activated for this drill. Contact to that facility will be expected.
1 O
2-8
SECTION 2 James A. FitzPatrick Nuclear Power Plant 1993 Partial Participation Emergency Exercise December 14, 1993 SIMULATOR PRE-DRILL PREPARATIONS i
- 1. MIS and Training to verify the computer links between the Simulator and DESTINY.
- 2. Training to establish simulator malfunction program.
- 3. MIS to run Simulator Data Transfer Programs on the following:
- a. Simulator Computer
- b. Novell Network
- c. DESTINY
- 4. MIS to establish and run meteorological data " dummy file."
() 5. I&C to set up bridge phones and Gaitronics in simulator.
- 6. Training to set up fax machine in simulator.
- 7. Public Relations to send fax to all NYPA switchboards regarding drill.
- 8. Emergency Planning to set up controller communications. I&C to establish progressive conference call, if requested. i
- 9. Emergency Planning to stage controller / observer briefing with past drill report.
- 10. MIS to switch EPIC terminals and inform Control Room.
- 11. MIS to switch 708 data, inform Performance Engineering and put message on data.
- 12. Security to verify employees exempt from drill and accountability during drill, and input exempt names into the ,
accountability system.
O 2-9
SECTION 2 James A. FitzPatrick Nuclear Power Plant 1993 Partial Participation Emergency Exercise December 14, 1993 SIMULATOR TO EMERGENCY FACILITIES COMMUNICATIONS Phones /Gaitronics to Simulated Control Room /SS ,
Phones /Gaitronics for the emergency drill have been established in the simulator that tie into the normal plant system. These phones /Gaitronics will be activated only during drills and for testing. Communications in the simulator to be used for drills will be labeled "EP DRILLS ONLY."
ACTUAL CR EXT. SIMULATOR CR EXT.
NCO Desk 6666 7666 SS Desk 6665 7665 Asst. SS Desk 6323 7323 F
4-Way Hotline Actual Actual RECS Actual Actual ENS (FTS) 700-371-5321 Actual - special (plant exit. 6087) t Other Hotlines Actual Simulated :
In addition to these phones, five special lines have been 4 established for use by drill controllers.
Gaitronics Two Gaitronics stations have been established in the simulator.
One unit and speaker will be set up on the NCO desk and one unit and speaker will be set up in the SS's office. All communications'over these should be used using "line 3." All '
field communications to and from the simulator should be preceded i by "This is a drill. This is a drill." Plant staff wanting to contact the simulator control room should state " Simulator Line 3." Every. effort must be made during the drill not to interfere or confuse actual Control Room Gaitronics traffic with Simulator
( Gaitronics traffic. i 2-10
i SECTION 2
'O e James A. FitzPatrick Nuclear Power Plant 1993 Partial Participation Emergency Exercise ,
December 14, 1993 SIMULATOR TO EMERGENCY PACILITIES COMMUNICATIONS (continued)
Alarms / Announcements Alarms for drills from the simulator must be directed to the Control Room to activate. Simulator operators should request the alarm via the phone-to the Control Room SS (x6665) or via the simulator drill controller. The Control Room operator should-state "This is a drill. This is a drill." and then activate the alarm. The operator in the simulator should then immediately follow through with the proper announcement. l Dispatch of Personnel not Physically Located at the Simulator JAF staff will be dispatched to work via phone or Gaitronics ;
before the OSC is activated by Operations personnel in the O simulator.
After the OSC is activated and operational, all staff will be dispatched from the OSC as designated in procedure.
Please note: this includes drill Auxiliary Operators who will-be i located in the Work Control Center until emergency facility -
activation (OSC) and then be located in the OSC afte.r that. ;
Locs. Data Sheets and Turnover ,
c Any logs or data sheets that would require turnover from simulator CR to TSC or other facilities will be handled in the following manner. Simulator operator will hand data sheet to controller who will then fax the data over to the TSC or the Control Room. A fax will be placed in the simulator instructor's j area for data transmittals. Verbal turnovers should then be'done '
over the phone.
4 Turnover to Emercency Director and Public Informat{pn ;
^
Turnover to the Emergency Director and Public Information should be conducted in person at the simulator as conditions warrant. i Other Communications :
Other communications not covered by this short list that require assistance should enlist the help of a controller to resolve. l l
2-11
. . . . .. - . ... ..=. .. . .
U J
~
SECTION 2 a
James A. FitzPatrick Nuclear Power Plant ['
.1993 Partial Participation Emergency Exercise-December 14, 1993 ;
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SECTION 2 '
James A. FitzPatrick Nuclear Power Plant 1993 Partial Participation Emergency Exercise December 14, 1993 EPIC SCREENS AVAILABLE
- 1. PLANT
- 2. RRC (Radioactivity Release Control)
- 3. SCR (Secondary Containment Rad Control)
- 4. LOG 1 (Plant Parameters Log)
- 5. PART3 (NY State Part III Data Form)
O O
2-13
SECTION 3
%)
James A. FitzPatrick Nuclear Power Plant 1993 Partial Participation Emergency Exercise December 14, 1993 EVENT
SUMMARY
a n
)
O 3-1 I
I SECTION 3 l
James A. FitzPatrick Nuclear Power Plant
() 1993 Partial Participation Emergency Exercise December 14, 1993 Scenario Overview At 0700, the plant is at 70-75% power after a power reduction to~
identify leaking fuel pins. Offgas rad levels are elevated due to leaking fuel, and the plant is in Fuel Action Plan Level 2.
L-14 is cross-tied to L-13 due to an earlier failure of T-6. The plant is in day 4 of a Limiting Condition of Operation (LCO) status due to inoperable diesels. "A" and "C" Emergency Diesel Generators (EDGs) are inoperable due to a crack in the Emergency Service Water (ESW) line at the tee between 46ESW-2A and 3A. The line is isolated and drained, and weld preparation and grinding is proceeding. The reboiler was taken out of service for testing and calibration of the level controls.
At 0710, a seismic event Emergency Plant Information Computer (EPIC) alarm is received in the Control Room. The operators should enter and execute Abnormal Operation Procedure-#14 (AOP-14, Earthquake). Instrument and Control (I&C) personnel should be directed to pull the seismograph tape, Niagara Mohawk should be contacted to confirm the event, and the alarm should be reset.
O- Entry into the Emergency Plan at the Unusual Event level is expected at this point.
At 0745, an earthquake less than design (0.06G) occurs, causing a short and fire in the 10400 bus. The resulting ground fault causes loss of the 10400 bus and subordinate 600V L-gears (with the exception of L-14) and a momentary loss of the 10600 (vital) bus. The "D" EDG fails to start. Only the "B" EDG starts to restore power to the 10600 bus. Fire alarms and intermittent security alarms, alarm.
The problem with the "D" EDG will be given as a longitudinal crack in the air supply to the air start motors. This gives a task to the mechanics to put a patch on the supply pipe to restore the EDG. Availability of the EDG has no strong bearing on the scenario.
Also, coincident with the loss and restoration of the 10600 bus, there will be a failure of one bank of the Area Radiation Monitors (ARMS) and the buckling of a Security light pole that shall fall and in doing so eliminate a Security zone. -This will ,
L give I&C and/or Engineering the opportunity to_ troubleshoot and attempt repairs.
Operators should respond to the indications of the earthquake by executing AOP-14 which directs inspections of buildings, O- structures, systems and components as well as entry into the Emergency Plan.
3-2
SECTION 3 James A. FitzPatrick Nuclear Power Plant lN 1993 Partial Participation Emergency Exercise d
December 14, 1993 Scenario Overview (continued)
The fire brigade should respond to the fire in the West Electric Bay, which will be extinguished in less than ten minutes. Damage to the 10400 bus will be severe such that the bus in non-recoverable.
Control Room operators should take action in accordance with AOP-17, Loss of 10400 Bus, to start necessary redundant equipment and cross-tie L-gears to the 10300 bus. Reactor Protection System (RPS) "B" will also need to be restored and scrams.and isolations reset (10600 trip initiated). A scoop tube lock on the "B" Reactor Water Recirculation (RWR) pump will also need to be reset (10400 trip initiated).
A power reduction should be commenced based on EDG operability status, rg (j
Emergency declaration should be made to the Alert #13 level for earthquake. Unusual Event may also be declared based on 3 of 4 EDGs not operable (Unusual Event #7) or commencement of 24-hour shutdown required by Technical Specifications (Unusual Event #4).
Maintenance, I&C and Engineering may take action to temporarily repair the air supply line to the "D" EDG so that it'can be started.
At 0820, the buckled Security light pole is knocked over by a strong wind gust that knocks the pole onto a microwave station rendering it inoperable.
At 0915, a failure of one RWR pump flow controller will occur causing a rapid power increase. Fuel failure results. High Range Containment Radiation Monitor (HRCRM), Main Steam Line (MSL) and offgas radiation levels will.begin and continue to rise. When the automatic or manual scram signal is. reached, a failure to scram will occur. Rods will'be able to be inserted in a relatively short period of time by inserting additional scrams. :
When the Primary Containment Isolation System (PCIS) setpoint for !
high MSL radiation is reached, the Main Steam Isolation Valves (MSIVs) will close. This should occur at about 0925.
The operators are expected to attempt to manually reduce the RWR pump speed or' trip the pump. A manual scram may or may not be directed at this time. With rising process radiation levels, 01 action should be taken in accordance with the Annunciator i Response Procedures (ARPs). Ultimately, a scram and isolation 3-3
SECTION 3 James A. FitzPatrick Nuclear Power Plant
()- 1993 Partial Participation Emergency Exercise December 14, 1993 Scenario Overview (continued) should be called for. With the failure to. scram, Emergency Operating Procedure #2 (EOP-2, RPV Control) should be entered with the transition to EOP-3, Failure to Scram and entry into AOP-34, Backup Control Rod Insertion. Control rods can be inserted by resetting and inserting additional scrams. This can be accomplished in a relatively short period of time. EOP-3 should be exited with a return ts BOP-2. Conditions for an Alert based on either MSL Radiation 3x Normal (Alert #2) or Failure to Scram (Alert #6a) exist.
A Post Accident Sampling System (PASS) sample should be directed or prompted at this point.
At approximately 0940, following the MSIV closure, a leak develops in the drywell causing drywell temperature and pressure to rise. When drywell pressure reaches 2.7 psig, Emergency Core Cooling System (ECCS) and PCIS signals are generated. Leakage O from the primary containment into the Reactor Building as a result of the earlier earthquake subsequently begins as drywell pressure rises. Reactor Building ARMS begin and continue to rise. A General Emergency should be declared at this point based on loss of all three fission product barriers.
From approximately 0940 until the end of the scenario, a release will be underway via Standby Gas Treatment (SBGT) to the stack.
Upon reaching 2.7 psig ECCS signal, the 10500 bus will be lost on a ground fault when the "A" and "B" Residual Heat Removal (RHR) pumps start. The "D" RHR pump trips on starting. This leaves .
only the "C" RHR pump available for containment cooling, but no power is available to the "A" RHR loop valves or to the "A" and "C" Residual Heat Removal Service Water (RHRSW) pumps.
If/when an emergency depressurization is conducted, a break in one of the Safety Relief Valve (SRV) tailpipes is necessary to cause.a further increase in containment pressure as the reactor depressurizes.
EOP-4, Primary Containment Control, should be entered and EOP-2 reentered with the rising drywell pressure. The only available ;
RHR pump at this point is "C", which is in the RHR' loop with no )
power to the valves or the "A" side of RHRSW pumps _(loss of
()
a 10500). Thus torus cooling and containment sprays are not immediately possible or effective. Cross tie from RHRSW to RHR in the "B" loop may be attempted, but will initially be
'3 -4
SECTION 3
.- James A. FitzPatrick Nuclear Power Plant 1993 Partial Participation Emergency Exercise
)-
December 14, 1993 Scenario Overview (continued) unsuccessful unless mechanics clean the RHRSW strainers. This is provided as an alternate scenario with a success path.
The rising ARM readings in the Reactor Building should prompt entry into EOP-5, Secondary Containment Control, and AOP-9, Loss of Primary Containment Integrity. This should result in a Reactor Building evacuation and isolation of the Reactor Building and should preclude any additional efforts to establish containment sprays.
With the rising radiation readings in the Reactor Building, EOP-5 should be entered. The operators will eventually depressurize the reactor, either at normal rates via the SRVs or through emergency depressurization. In either event, primary containment pressure should remain high enough for a period of time to
~
continue the release into the Reactor Building and ouc through SBGT.
The releaqe will continue until the end of the drill, with varying rilease rates after some period of time.
Several nuisance events will occur in addition to the above.
Cracks in the fire loop will become evident at 0945 when fire system pressure drops and all pumps attempt to restore system pressure. This system may be restored by Operational Support Center (OSC) .
At 1015, the Technical Support Center (TSC) Heating Ventilation ,
Air Conditioning (HVAC) system will fail. This system may also be restored-by the OSC.
Finally, at 1040, a call will be received in the Control Room indicating that water is seeping from the east wall of the Sewage Treatment Facility. Efforts should be made to secure release of sewage liquid from the lake.
The exercise will end at 1130 as release pressure is removed and an end to the release is apparent.
3-5
SECTION 4 James A. FitzPatrick Nuclear Power Plant O- 1993 Partial Participation Emergency Exercise December 14,'1993 MEETINGS I
1 i
O O
4-1
SECTION 4 I'% James A. FitzPatrick Nuclear Power Plant
(~ 1993 Partial Participation Emergency Exercise December 14, 1993 MEETINGS Monday. December 13, 1993 0930 to 1015 NYPA Staff Initial Conditions Briefing (Work Control Center Conference Room) 1230 to 1400 NYPA Controller / Observer Briefing . (Support Center Conference Room) 1400 to 1500 NRC Observer Briefing (Support Center Conference Room) 1500 to 1700 NRC Training / Badging 1700 to 1800 NRC Tour of Emergency Facilities Tuesday, December 14, 1993 0600 to 0645 Simulator Briefing for_ Control Room Staff 0700 to 1130 NRC Partial Participation Encrgency Exercise 1200 to 1330 Facility Debriefing Wednesday, December 15, 1993 0900 to 1000 NYPA Controllers / Observers Debrief (Support Center Conference Room) 1000 to 1100 NYPA Exercise Critique (Support _ Center Conference Room) 1100 to 1130 NRC Exercise Critique (Support Center Confer 6nce Room)
O 4-2
SECTION 5
'[ James A. FitzPatrick Nuclear Power Plant >
.( 1993 Partial Participation Emergency Exercise L December 14, 1993 TIMELINE I. Timeline II. Summary Information III. Data Summary Graphs f
6
=
0 9
i O ;
5-1 i i
SECTION 5 -
. James A. FitzPatrick Nuclear Power Plant 1993_ Partial Participation Emergency Exercise
- December 14, 1993 j TIMELINE Time Kev Events ,
0700 Initial Conditions
- Leaking fuel pins - Failed Fuel Action Plan Level 2 I "A" and "C" EDGs inoperable
+ Reboiler out of service 0710 EPIC Seismic Alarm =0.02G Unusual Event conditions met 0725 Unusual Event should be declared by this time ,
0745 Seismic Event =0.06G Short/ fire / loss of 10400 bus
. Intermittent fire alarms ,
+ Momentary loss of 10600 bus
- "D" EDG fails to start ,
- Bank of ARMS fail [
+ Intermittent security alarms l
+ Security lighting buckled O
Alert level conditions met >
0800 Alert should be declared by this time 0820 Security lighting pole fails
+ Pole falls, destroying a microwave unit and fence !
0915 Rapid power increase
+ Failure of RWR pump flow controller ,
+ Fuel failure results
+ Increase radiation from HRCRM, MSL and Offgas 3 0925 Scram signal (manual or automatic) {
+ Failure to scram i
+ PASS prompt Operator action successful to shutdown reactor j l
0940 Release from containment becomes apparent General Emergency levels reached l 0955 General Emergency should be declared by this time [
1000 Loss of loop pressure for fire systems 1010 TSC HVAC failure 1040 Sewage Treatment Facility problem observed '
Os - Liquid release to the lake 1130 Drill Ends 5-2 i
SUMMARY
INFORMATION
(#
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Whm . 0700 The plant is at 70-75% power after r. power reduction to identify leaking fuel pins.
1 14 is cross-tied to 1 13 due to at, earlier failure of T-6.
e hh JW nc "A" and "C" EDGs are inoperable due to a crack in the ESW line at the tee between 46ESW-2A and 3A. The line is isolated and drained, and weld preparation and y; grinding is proceeding. The plant is in day 4 cf a 7-day LCO associated with the diesels.
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. n- $ m M The reboiler was taken out of service for testing and calibration of the level controls.
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- ,eA crew is scheduled to begin ST.
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78ACTIONg4 Operating crew will review initial data.
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MINPIS,NTER Higher than norrnal offgas rad levels due to leaking f uel pins. All other conditions 99.JADme -~3 egg
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SUMMARY
INFORMATION .
0710 A seismic event EPIC alarm is received in the Control Room.
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( a mn- .] I&C will be directed to pull the seismograph tape, NiMo should be contacted to
- g . . . . , . . .
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q confirm the event, and the alarm will be reset. After analysis, Emergency Plan should be entered. SS may activate eme"gency facilities.
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Seismic alarm is approximately 0.03G.
I Unusual Event #13, Seismic Event
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_. A The operators should enter and execute AOP-14 Earthquake. Security should be
....R, directed to assist in inspecting the site.
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.;:4 4:$ Higher than normal offgas rad levels due to leaking fuel pins. All other conditions
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~ ' hRAdM)T' A Misegne#S!b normal.
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5-4
SUMMARY
INFORMATION l i
M 0725
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-Q Response to Scismic Event to be observed. ;
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Higher than normal offgas rad levels due to leaking fuel pins. All other conditions .j h5 normal.
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SUMMARY
INFORMATION 1
0745 A seismic event less than design (0.06G) occurs, causing a short and fire in the 10400 bus. The resulting ground fault causes loss of the 10400 bus and subordinate -
600V L gears (with the exception of I 14) and a momentary loss of the 10600 (vital) ,
bus. 'D' EDG fails to start. Only the 'B' EDG starts to restore power to the 10600 !
bus. Intermittent fire and security alarms, alarm.
Coincident with the loss and restoration of the 10600 bus will be a failure of one bank of the ARMS, and the buckling of a security light pole.
?'rf : --h Operators should respond to the indications of the carthquake by executing AOP-14 k! i.
which directs inspections of buildings, structures, systems and components as well as entry into the Emergency Plan.
ti
= ) The fire brigade extinguished in lessshould than tenrespond to the fire minutes. Damage in10400 to the the West Electric bus will Bay, be severe suchwhich will be hE%
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h ww&m .
g that the bus is non-recoverable.
N
.. _ f A power reduction should be commenced based on EDG operability status.
The problem with the 'D' EDG will be given as a longitudinal crack in the air l
I ipa , ,
supply to the air start motors. This gives the task to the mechanics to put a patch
~
3 g on the supply pipe to restore the EDO.
\ N 7 ~h Availability of the EDG has no strong bearing on the scenario. ARM failure will '
Adf$$ . _ _ give 1&C and/or Engineering the opportunity to troubleshoot and attempt repairs.
(' Emergency declaration should be made for Seismic Event (UE #13). Unusual M.4 Event may also be declared based on 3 of 4 EDGs not operable (UE #7) or fire
$ (UE #8) or commencement of 24-hour shutdown required by Technical
- n _.. p Specifications (UE #4).
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4 i Control Room operators should take action in accordance with AOP-14 and AOP-j
~-
17,1. ass of 10400 Bus, to start necessary redundant equipment and cross-tic L Gears to the 10300 bus.
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(
3 RPS *B' will also need to be restored and scrams and isolations reset. A scoop tube bNR1wed lock on the "B" RWR pump will also need to be reset.
ume wp ,
Higher than normal offgas rad levels due to leaking fuel pins. All other conditions g+rMNPLANTglh n rmal.
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W Normal T@OFFSITEMRXb N h kkk Supplemental Scenario #2, Seismic Event #2 GSCENARIOr? Supplemental Scenario #3,10400 Bus /Short/ Fire g QW Supplemental Scenario #4,'D' EDG Air Line Failure
( M5 h Supplemental Scenario #5. Loss of ARMS 5-6 :
.i i
SUMMARY
INFORMATION Response to seismic event to be observed.
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ev .. .
v.g respewege i
. K6mLast4NT Maintenance, I&C and Engmeenng may take action to temporarily repair the air IMv ==?g ; supply line to the "D" EDO so that it can be started and correct any problems in :
U i PCIS or nuclear instrumentation. !
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. Alert #13, Seismic Event, should be made by this time.
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4 AOP-14 and AOP-17 rutn~"____ zw gggg*+gg l Em s, Higher than normal offgas rad levels due to leaking fuel pins. All other conditions ,
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i
SUMMARY
INFORMATION ,
0820
,ih.? A :.. "
Security lighting pole fails and collapscs. Unit hits microwave head and zone is -
i^ inoperative.
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fggACJ701 My Security will investigate, determine cause of zone failure, request OSC assistance in removing light pole, and use compensatory measures for event.
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H AOP-14 and AOP-17 yeMm f4 ,~,M, Higher than normal offgas rad levels due to leaking fuel pins. All other conditions RADWu5 normal.
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SUMMARY
INFORMATION i 0915 A failure of one RWR pump flow controller will occur causing a rapid power increase. Fuel failure results. HRCRM, MSL, and offgas radiation levels will begin and continue to rise.
Ultimately a scram and isolation should be called for. ;
When the automatic or manual scram signal is reached (due to process radiation levels), a failure to scram will occur. When the PCIS setpoint for high MSL ,
radiation is reached, the MSIVs will close.
i
}* hYk Nh ($[NNd The operators are expected to attempt to manually reduce the RWR pump speed or
/* trip the pump. A manual scram may or may not be directed because of the pump
.# % failure.
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Rods will be able to be inserted in a relatively short period of time by inserting additional scrams.
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g , j[gg An Alert should be declared based on either MSL Radiation 3X Normal (Alert #2) or Failure to Scram (Alert #6a).
g l[
hh u mgg With the failure to scram, EOP-2 should be entered with the transition to EOP-3 and entry into AOP-34. '
!W
~j Control rods can be inserted t,y resetting and inserting additional scrams. This can
.gj be accomplished in a relatively short period of time. EOP-3 should be exited with a
_y gji return to EOP-2.
., w-g Main Steam Line (MSL) or Offgas Rad Monitor action should be taken in
' '"% accordance with the ARPs.
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SUMMARY
INFORMATION
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A PASS sample should be directed or prompted at this point. '
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sa .
nWW%AMM$s N4)$$*
2:4ws%jM#t OYly'
$7 1
'mm.4ddkhd@s:.SMMO('.'
.s. g m..
em:w n, .cswr. x <'
l( ..y;p:., y. s
.'#2'SPE,CIAD%f t eq:g vm.:..a.:gwqpp.
- m -3mgp
<k
'mg.M .3sorg:mF#d.iJ' Qfl; y'::r:6f$b :: sex mdswa, QG ^?# W~ .,x.
' hdlf bh dhb.M NMRTen:W.Wfs EIBide? Alert #13 Alert #2 or Alert #6a w w: ::
m wan;%e.
. x .a:sa %m.s .Aym .q..a
' %p+%tu;;.m wnqui ;%4;i:
': .[?M'@s5'Y M Q# [
Wg f/EOPg{ ww EOP-2, EOP-3 and AOP-34 na.w:w$k'$:-'
Y:fh:4XNU%
"~#
n.
I@e.v.<, wm
WWRADR**
%!EN.s.~.R. -:
-k.s $.a:t
- 3 , .p.r.# , uht,Amy y
@h, .,y: OiM.. y:., TIE.,, '
- R.)Normal 7
- :: ? ly ww., . . .a ,
- <$$Y.;ih$h$$$
, .w n., .
%SU.P..P. h@ None ,
- SC.EN,A.R,IGl
- r. .
y;:9:?:- ?yp;$ : ? . .-
'Mj:- gyjg b.
'- ? _
% > r d .,.
s 5-10
SUMMARY
INFORMATION
('%. dhT544.g
- m. m_ __
Approximately 0940
(
n.gg.p._ p M'y +'.'-
gg: Evident that release from containment to the Reactor Building and out through the
~
q Stack.
W.-.. ... .
ffjff 7 Mtf MIME Y goitt .
.wggs :
1 armW gg _em:m 3 K'M M t, a . ..
y -
P w ~- ' ' '
k....j,
-g %. $L;.m;%Q meg ]
VOf7j'HM8]e$ $ $$$
KiB.h mm Y- f . 28.
MdW wMm%w DI
$36!@kd.[@h9'IfssfM
.f, M+ %# % Q?}W< M '.-':l
%$EACDON%n Operators should declare General Emergency.
macedt.:
9%re.g:#TWW;%c%i%
7; Mergvr e x.,,
hf$.
sG%@k wwe meh%% #
k
$$$k$$hhhh@M}h$h 9[#$IWm my w y$1
- s,1 #
7 43W$TfMNm ~r;r sDM_CL. "
(
/....vc s P. 4.v e..-<-c.e
\ $$$a[SPEGA0i?Eg:i
.s b
esuk siM ;.M o w .ou c* n
.%Tg u'.vvmau -[ty'gf.? we '
T::y y,yy;
%MA 3M, 94 .%MxW ;6 ?GWN QW@
w th+%k.+A%er@n;$w.
A ME, A. I.;M, MM: General Emergency # (loss of 3 of 4 fission product barriers) m - -
m
.v.+'f'
<WM
- & ....?&< . dW
%'sW gg%
. .....1 V,.
W ..vnm,me@iv..
AOP/ SOP! EOP-3 m g &: m%_ s w $ 9 saA%
_% 2 ,
pW- . NN- P% s .'d J
%g1N'%>>$%N:FLANT'W'@:T HRCRM = 10890 R/hr. MSL = 3 times normal MQf%M
- Iid@$(dgw nem wntsv> M;$$
iO f@ap_fPSTIEP Normal g
l@i1...~.g:v hdQW
- ECCCWiMF n, %:-.:.-:.:w%G W;SlJi!PQge None J' SCENARIOS <
< m : ens: .
6 6pWWWt
- me w x.4 x
' ' $ 4 .$
./. # % >
N YNI 4:j..:-y >
5-11 i
i
SUMMARY
INFORMATION l
O
) MMM Approximately 0943 1
y % .w..
." B.t.g f Following the MSIV closure, a leak develops in the drywell causing drywell !
M[kf[.;. temperature and pressure to rise. When drywell pressure reaches 2.7 psig, ECCS o
, 7e and PCIS signals are generated.
9.9s.u a
)p;py n Upon reaching 2.7 psig ECCS signal, the 10500 bus will be lost on a ground fault dhypg d when the "A" and *B" RHR pumps start. The 'D' RHR pump trips on starting.
w .. r .aacse+
[ . )gg p 6 % 49
$pW. This leaves only the 'C" RHR pump available for containment cooling, but no power S;F - is available to the *A* RHR loop valves or to the *A" and "C" RHRSW pumps.
QM hkhs N JM&
$$Wrd6@n. G :ia m mW#1**
g$g$$$a.pg2
- %.st w
4 *pw<.maa.yACDON%.6p J A > <:x s.uw E p The operator will eventually depressurize the reactor, either at normal rates via the "Fq@@$W SRVs or through emergency depressurization.
o <gngyp;g -
MSM
- Q %pM3D MEMt1l% .
LAUNMEM7 M% NN$$u%
s/fM@iq?M q e L $W
~A%
MSSPECIAdhg ifAvhen an emergency depressurization is conducted, a break in one of the SRV C gh ADh tailpipes will cause a further increase in containment pressure as the reactor MMMMg$$
MAmM *dN1 depressurizes.
psaswwer9 p(gggggg:n The only available RHR pump at this point is 'C", which is in the RHR loop with
%$@W""R no power to the valves or RHRSW pumps (loss of 10500). Torus cooling and 3d$$$[$ . $ containment sprays are not immediately possible or effective.
~~ n.eyn mEAbd&eds General Emergency #
W 3 W@#w%@5?dh
%%;i$sen%Q$%
pm.% mW n
4g96, AOP +.mwn vsgg EOP-4 should be entered and EOP-2 reentered with the rising drywell pressure.
&y:m#d :-man e % q %x h mya G d mwc.m., v. ..
f Leakage from the primary containment into the Reactor Building, as a result of the
@(jd(PLAN RAQ $f$
carlier carthquake, subsequently begins as drywell pressure rises. Reactor Building
%d fi M r$ '3 p ; ARMS begin and continue to rise.
...-......ne. ,e.
, JOFFSUKT*3,. A release will be underway via Standby Gas Treatment to the Stack.
g {RIDM:l^ .
- m. r e
_m..,
g.MSUPPAf None J, .,SCEN.AR.. , I,OS (J E .%
5-12
SUSIMARY INFORMATION bk M ,
Approximately 1000
- gn GNVENTwwwmM.: Alternate success path: drywell sprays can be initiated if *B' side RHRSW system is 1 cross-tied to RHR, and if the strainers are cleaned.
- m..u 9
4*F j All fire pumps will auto start to restore loop pressure. System pressure will drop to 85 pounds.
.eQ% r.y n.nyn. .
e.w :.m yy ,
' 3025MMi?MM;.
0, 4MWe$2 . * .
M,eawana.a@mm kS$ISh,EE,d5, M.S# dpfG.@.0.we=14/-: *. #
$!!EACDONy/i By 0955, a General Emergency should have been declared.
gtQurwm ,
~de w; 6 :J15f@i3MM E EY + thi .
lMQr a ng @4us 3 W m%:c:,
Ai?:;3hl;?%%WW8??W Q{1M&pW"~ $Wud %p d & % w c#$fs 3;djg1 sy%$
mn mym 4%
3 . . y ms:*.,.. w ^ ..
I iiWSPECIAliME w.*g Reactor Building rad levels should preclude any additional efforts to establish
\ Qfsps g gg@.rmoc i containment sprays.
gg WW%
eB giv3 g Primary containment pressure should remain high enough for a period of time to
- mg$9 W[$j; g# 3 M$$$hfhh! f W continue the release into the Reactor Building and out through SBGT.
@h M ic p W W Ibi?
hh A General Emergency should be declared at this point based on loss of all three fission product barri:rs.
kNfhhil n.-~
WAOP/ na+m@x@.
ISO The rising ARM readings in the Reactor Building should prompt entry into EOP-5 M$$jsd@Rj[$ and AOP-9, Loss of Primary Containment.
., .m.e .+ cs,.
$$;ww 1NPihNTM Rising rad levels in the Reactor Building should result in a Reactor Building D M A D $}% [,. evacuation and isolation of the Reactor Building, wqmn W q@s&pd un c. . . . . . .n.,.,+m . . .
hMF13rfE@ Low Range Stack Monitor up to 559192 cps.
,12RADTMs hkhk%$YQ&
m* y,r,_ m, .
MSUPPNg5 Supplemental Scenario #7, RHR and RHRSW Cross-Tie l TSCENARIO1 Supplemental Scenario #8,1.nss of Fire Loop v
me m' d ','s:w^.,JXh n' " 'cuw
..a Nu(dI5fWM$
n.
msg :dqg;t > & , ,
- Syk?b
- +
a , .
~
1 5-13
SUMMARY
INFORMATION MML 1010
~p%s%.
TSC HVAC System ileating/ Chiller Unit fails. Heating drops dramatically in TSC.
(@KF"_
g . , .f.
vgy" ;;c- - - - -, If TSC ventilation enabled, ventilation will fail.
. 'a
%g;p mg u
+
- a. .
s a
e,, m r.
a'.* . , .w .:
$w;<.,:;4' q w.6 c.A+ . .
MW AQM..:4 f@@yW f50 n=w?-$
Why3
. Y..e@+,p unwuba':.QUJif.& G ' wa
$$v..
'+b . .$.:q$$i!$.:iM:$$5 i: :w 4: 5r t I
4:9g:ws:w w ~Jg spACTION.@g;u.x. TSC should request OSC repair team to repair.
J M % u g gf. 2
$@h$$NDS$ E G$%cM!zgt R %R >qw $P%yIMU 3$$MhS n
bi?eeggewmem %$$$W
.J@M.4m$n SM e cx u..
2'I?,?@?! $%):l$$$ "Z:?9?i
,C 4;g, .s._
9 7 weSPECW:4 None capasaana MiXPRMB
$w QQ %w w.% d? g ws?"
mmu General Emergency #
W%
4%i ih'$$.:kSMM Bffs<w sad].[3u.
/94@':Q.. 4 gid?
- v. 9
~4+n'.
qv :.su , .m kw..g: s.{ :r:s.
' .r..w:
Sw) 4; -
Agggs4&eue&<W.:.s::;g; ;
' ;gAOP/ EON!M None i
- g. .wp .in8thjE%'$:. r
~
.s_..:M. . . ~
gjg w y+.S. ..va:v:Ac %: ;..:gg.
NfE M M W.t[gj Soms Reactor Building Rad Monitors up to 3/4 range. All others rising b,;.$ RADS'T dramatically.
v4W';; s."\:3@
k': s > ' ; ' .,(.Q
> y,r.wo.w a y..u.
MQoll*SITEyEsl 1 ow Range Stack Monitor up to 751351 cps. >
e uw:... nw .
.w:s,/
.g>('(.h"f
' '% W "y 9;w . ' . . . . . NN4 % ., yf'f 4;p .,. _ d
< /-'28# Sde:, .
3 ...:..,<.
MS- .
. ,. - . U. .P. ..P#. 1. .~ t Supplemental Scenario #9, TSC Ventilation System Failure iSCENARIO? ~
~,,'....g.,
Qi::"' }.jj{ <
4 <
PE ;
. . . x+
- , $h.k. . . ., .
e O ,' I $'";
v -
i 5-14 '
l
SUMMARY
INFORMATION
/~
k 1040 Cracks in Sewage Treatment Facility alarm with liquid release.
a
>s;;g h
u l
f i
ens.
L rm
??
, ?g@}t. :
k%@
<w Aaw; NEB lei $i?M 8kww yr.9 ;s .Y;.Wp,;_9-
- WXCTION
-,k' 'iM&4%T,NJwum.rm#'4.. OSC should investigate and conclude with containment.
. apcmm sw au senstgmy4Mye rmmemm h-+c:.,. i y$p@.?ANWGf3S&ggg W#$$" UR M
?xMfL-
- M ba E- t$4i
$$b. khhh marx 1SLMcMSM h +w o%n
\j $$x,s.e , None
$27 3;j'MRjSPSC3AU$$l >w::n,; }SL s;ng ,.
..........h.
.styynom ' q MMi mia w . ..nn.c W General Emergency #
y :en O!n wesh :$it?1i its. .
S/
i&geAQP/EOPEf wgsw*mAww&+p;( y:
N/A e cq+qlrlp%
$.2??
TMs + .
% y& ?, $ fl S'C d}e ,*.NI'NPhAN'UTsis! Most Reactor Building rad monitors are offscale, others are continuing to rise.
T38RhDlV4 w M:;m5Mi w - aG@&?M y ,;.:.y 3.y.w.w..,v. wm;-g &
.Jf.0F.F. - Sr.T,EMA; x.
low Range Stack Monitor is offscale; High Range Stack Monitor is 1 mR/hr. At SstsRADn7-3 100",1 mile downwind, Jose rate is 1 mR/hr.
p - 6Fs . . . .. . 9 / nf.+ .
N _U
< Msi,W" & M%EF y~o . .y g x W$dSUPW....g Supplemental Scenario #10, Sewage Treatment Facility Leak JSCENARI.Oj ,'
tes,+g gr<
. . ~ ' s 2%: 6-l,hhl g .;.1 <
@-0
_ &,, s
?fav
+ > .
t -
% ab ,
5-15
SUMMARY
INFORMATION 9
{mv}
WRhW --
ww" whi p4 Offsite dose rates continue to rise.
.g 4 .
r:7.m . . ,. j 4).$ mix ;
IN wlx:_
.'l:l, '
1' M brit : 9--
- ?.1 4 -
'p:bi .- E
. 3, u, l
4
@wa@4W5%
,1,p:c:>.;:w t
-a w
'1
.l Pf"4 l w .
n
- nt r- v.,
%$%'w;: . ihqwy .MM 1.::4.9 v b nw -2 95M@
- +'
- L Uki&;-j?$? sedW_3fhwtjh:n .<
won >+ss+
@~ %.$$dN?Os ww wn
'M' y:g gv#r m.s.t.&s.p:.gggNonc c + A. .. C.T.n%; IONiM 4 ~,g..>a
- A wmg,M K4j'dy a::w-8 ;. 4 # ins >W[y).
W 2;;. G ssw@ W-h MWes %
@;: 1.
BB$.:f^tg@_ M %A}N:
@?#WsfME w We hNii EM!$$k*mbre MM@eaWeNam M3mso.ru hse.WEspW::c...' sanw p Ob OMY6"YD:kOfN)!,C. N.k; w MmvSPE IAlf@y None f>TR@M,C nk fM74 m>;.n;
+ w$w;.p gw .%ge%n;qQ-
'~, 4se :>;>: wavy us
%SWh?MWN
< eAwde s4c- .gws:#o 4 ww:w3g:x, aw va:::. wer fWEAIR7" General Emergency #
MbhceML S
- muq m&w%l~
w%
- u. ns. , reg >M@
m .- . _ _ _ _
y%ymreng; AOP/EOPhg None
- mwWs g#6;@ a w.
am ..we.
9 ;.wr.u, h&IN:.yPLAlflW1 wit... s ypg Normal
- '"'~ m.
- :; R' ' -
.a.
- .a.s .+ :7 yf'%:K m_.wwanm nn.wy>,
M>:.A :.
iuneD ? <D E '
e w. r v5 4-M M -y. 4 Tl gf:rOITGI'IEjw Low Range Stack is offscale; High Range Stack is 1 mR/hr. Offsite dose rate at 3RADC _
w;iwesw 100*, up to 2.5 miles downwind, is 2 mR/hr.
+
vb fVM:p:' "
...q.., ..,
,,.CSU,PP. A. . None 24 SGEARIO'&6 iW = .( ' . ' , C.';:.y.g
. : :. 4 M 3fg ;.Ml 5:
_.7
, ;-. .; . . f:- gn.: @% g ~, ~' S:R -' s dbb' fd) .c .
e
> 3:str 39 i
k J.; 2:
5-16
SUMMARY
INFORMATION rx
(
i y;g .-. _ ;- -
d@ Q1MR @3_ . 1115 m.unnrwn.
Mi:- m RisinE offsite dose rates.
e?q4 kibT
, .Ew o dee >we. m . 4r 4 .
s y.m- om w ,- .
.g,,.,
.,;..! s s .; yj v ...cs 3
- . - s Mjp '
Mbyn
..$. s'}D:g
. 5%.'g.ggS .w
.W.m .D N' f'f...
MTQ
,1 Mand,)
s'~. .ama ep UI:b
- c
- n v. . s h::.h. ng;;;;h%' ;-:s : @-:.%!.I::
WfM6k:*My
% $ MC y p :;
- b%@lQ$ :s v:wc u; >: ? i
.:. .;^
tw ' H
',;:r M.>a q:;(
b, : {
ht Y
W
.$:gfS."..
m majdQRJg; j%y$
'N MWM%T v
W%.xs%y@Q
~.:- mm...<_.e.,.
A D.*
^.
,/- b
'.i:4:<ik.k -i%%'o. M.MSfM;;ye,'$
i m 4 a iww@sd~
4-ao. .%. v . >. x.
M<.c-.q.;;::A None
- n.~,C11.0,N,0 w:e s y h!!h5h ^ .ly$'
~.. r F$2%. gIs., .. w~.a. :.sn.i 3.ek q:s.ggy$;sf , . sg
- P,
&$thi??Y$N$ n.
+ 2%wMx..:; y 6 n
M%lip?gy$5si,f@
EdlA,s.taht.h x
f e .
- y
<_._._m.,...
\ @%SPEclAlfiEd o e w:mw None
" 6. JKT~
$f$w:$$sn;s av n i$ ud Inendww.ars idG'dii General Emergency #
%gEAI$g~sih ag .
-7 e.
d# cw~a:gac@3H yM
- h. ' isas:4 n
AOP/EOPJf None TmgY.hiQ^%v l V:.QEhf.
~
- Q.G !
- .,yyn.mm.g.p@,
>41N M ,P, Normal DRAD s e
s es ,
< a ' ' , / #
y~ j,yc.,..-/w..>a. .- ..;.
4Dff. S[lTn, : Low Range Stack is offscale; High Range Stack is 1 mR/hr. Offsite dose rate up to
.E.
~ RAD 4 ..e+ 3 mR/hr.
meew~:
ss- 9#;,
,: s s=
, ESU,. -.pE..s
.y.~.ps. --..._
I None E~.SC.,EN.~AR.
~ - IO.i a.
'h*'It
't
- . [- h n- ,' k('.;
i ~ >
/
\s >
5-17
SUMMARY
INFORMATION 8, . p i
N 9.#H.u.T.
g A'TubN IM. N,BW{Nv;'h'
- a. .# 4:.
kfh: s% 1130 4 ugvaawyvue .
$gi;E , . . ,
Exercise terminates.
mn.Mf;p%.; i.'~
Gll-;t
@y5$WM- NR:
3
,U g: -
%s Mm
+td % d?Nts 2. $"t s Ik::MO w- .:w . ',a
- y u.,v.m, 72 , . -%m.m. ;. .
w Ts.ypeff.w:.;
k.M,.W:e . . d >m.n.s. >'
g 40p .3 i.
4.mwl v ;;:. : s. ,
wm . m
(' l%
'N:Y mm
. %. ' y' f^My . ff@$e (Zw s' hF zwihdin . "d,,li 2.M
%: w w %n9:v e m ypfgg d Apr61:
m.ra an:y> %g.ww w ..
we% hww.w ME#tidni%
S.mAanm grg;, <. .w.*+. . . .s :y.
^-
Close out call on RECS from EOF.
N#.# A.C.@,D,k,gi.4,f.ME's'
<N,;44 _.-p :>~
.m.:s O..NM
? - .+
- e. Close
.x
~ out call on NRC FTS,%"n. -
May;m:w' tiWNistMsz p.
y* &:2::ytQyQ':.di%??
- #was d<( ~'+< v:'.c.~.N x'
- Q gjg:1s:4.g:a:u c ES4444@yr.%y@g.f
- g p:
-4 ap, : y n ,a c-w '
- v:QV:WW?tM1." >* 3 M.7st d@pe.af.wh.
gi.w de- ,n,
- ;ph Maicu
- p.
- gpu ~.ww.: ; eggs.
L nsSPECIAl# None b.Nhre.Mk.hh, wa L:.. 5>g
.an.m..sv >-
n.q N';'.hik.<)N awwxgpe :pmgmn:n. .
?,hkOP.TkbM:
se p-xmaw.w.a iptinEAU M 4R General Emergency #
.w.
y +;;4 w e.4ffy.s ww emA ..s yanm, m; ,
..w &lNk kq#g , W w% p~e & 's~-
4 g4.yww m w+.-g7:
Nonc QBWW?y[;?
- stemwne4 n:3ej;s mgu v .s. ,,. .%.m n e: rua. m MilhTLXNTj@ Reactor Building ARMS offscale.
, =ygype me.u. :c ..
- xp 2e #:2
_ ,:,v,f-p ..u me..4.%.- .
,2-
, #OITSTTES " low Range Stack is offscale; High Range Stack is 1 mR/hr. Offsite dose rate up to mE :-- o ,l,in.',
"ym %.:.R.4.
.x:
3 mR/hr.
N nr ; n p? c;3 ' yy ;; '-
N gt. . , >
ki hhki.. ' None SCEN. .E,R. i.o.. l.
C _, y, ,;'",'j. f f ' S
': '%. ~ l Y-_ f ,'
~ ,
'5 l .g
)
)' * ..,M'.-I'.;
5-18
D(
i
'l! ! i i i i i i f _ 03:, 3
]_// / /
/;
/ /
/
/ / ~T
/
/ f( -
- 51 11
/ / / / / /. . ov. , ,
.l l l l_ ! ! l
//__lj_j- l
- 54:01
/
',I ,[ .l [ l
. f/ - 0. 01 7~~T l ' l l l- l i -5:01 l /
l
/
I
! /
!l [ll' - J 01 l
j- ; . t-+
/ _/
! _ I.__!_
/
,l
/
,l
/
l
/
r- r-
-+
/
/
,I
/
! .H# -03:9
-929 829
/ / / / / / / / / / -72g
!- I -_I
/. l l l +
- l .! -l
_/a/--l!7// - 62 9 a ! i
/
/ / _
/ *
' - 52:9 d 7...[/
-429
~
ti
-5
'g e ,! / / ' l !
329 g 09 *
, l/ l/__.l._1___
l/L/
~
/
J I
-l / :
/
l - 22:9
-129 i 8
1 C ,
5 2
'/ / [4'_ y.! /
/
/ - 029 S #
o
< ,_u! . /- ! /
4 ;
/ / /'/ /
- 91:9 n.
x a
0 t l / / / I' 1 ,
l-ll l~ ' - 81;9 a 4
- y I
,y'
! ,!]I I / .- !
,i ' L, !
J. .
-71:9 l!
7 83:9
! ! / / / / // /]
/_ / / l / / / /
i - 51:9
-ocs y a
/_.f_ f ' / / / / /
l-l . 7~. ! _)/ l l .l l lI l. - s4:8 Q
!' i I t
/ !
I / /
]/. >
- 03:8 x 8
)._-l l l I l I - F. .! 51:8 E
i l l_ l L _.-l_ l l!
- - lI_ l 1 - one s1 lYlll 377 ~x \ .\x y-l s i
[! l
'x l l
\
x I
\
l I
N IlAO x x
-.l J]
sr
- 51:7 3 - 00:7 5 o N8 8 0 8 8 8 8 8 U O
f:
j J gj j
] f---
j- j
- 03:u 7~~ f-
- 51:11 f' --- ,/
j j - - - - i
~~
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SECTION 6 James A. FitzPatrick Nuclear Power Plant 1993 Partial Participation Emergency Exercise December 14, 1993 DRILL / CONTINGENCY MESSAGES I. Message Sheets II. Supplemental Scenarios III. Plant SPDS Displays
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O 6-1
3 k 4 FORM SAP-1.4_ Page 1 of- 19 MESSAGE SHEET MESSAGE NO. -1 .
~
Exercise Time: 0700 Issued To: All " Players" Issued By: All Controllers 1 MESSAGE Initial Conditions are as follows: , The plant is at 70-75% power, after a power reduction to identify _ leaking fuel pins. L-14 is cross-tied to L-13 due to an earlier failure of T-6. [
"A" and "C" EDGs are inoperable due to a crack in ESW1 line at the tee between 46ESW-2A and-3A. The line is isolated.and drained, andLweld preparation and grinding is proceeding. The plant is in day 4 of a;7- :
day LCO. O The reboller was taken out of service for testing and calibration of i the level controls. i The crew is scheduled to begin ST. l l THIS IS A DRILL O DO NOT initiate actions affecting normal plant operations
,, e s , , - -
4- e ww 4 h- m -* -- - a4 e h 9 O : S i t 9 p FAILED FUEL PLAN ACTION LEVEL 2 DATA O a i 6 l l
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1 1
UJAF CURRENT CHEMISTRY
SUMMARY
FOR Rx W0ter DATE/ TIME CPI,NO. M POWER 70 % MWth [<0.37] 3 t
~ nductivity O.I R pS/cm pH kOb I-131DE f04xlv pCi/gm I [<0.20] [< 1E-4'] 1
- 2. 3 i riod pCi/ml
.alloride (- I opb ECP mv SHE Total I
[ <15 ) [<-250] a Sulfate 5& opb 02 U.2- opb Activity D4 Y 10 pCi/ml [ <15 ] Silica lo opb H2 0.0 0$ opb Sol Zinc N SI opb Date i [<100 ) [4-6] RWCU EFFLUENT FEEDWATER / CONDENSATE SAMPLE DATE/ TIME / DATE/ TIME
^ Cond pS/cm O2 i Date/ Time In Service Feedwater [<0.06]O.055 [20-50] 1% 9 l 0.0 5 b ,o% CDI [ -- ]O .094 [__ ) l y.93 ,
Cond pS/cm [<0.08 ) [<0.08 ] CDO [<0.08] O M 3 [ -- ]246 l Silica ppL C 5~ <T H2 opb , I# 3 I# 3 H2 Flow - cfm 02 Flow ' _,cfm Activity pCi/ml l . ~2. Mr4 1.1f(D-N Fe [<2.0) - opb Cu[<0.1] ~' opb S.W. CHLORINE (PPM) DATE__I 9 A - B ' C SW out [0.5-2] l9 i Offgas: Date pCi/sec [<600] Recomb. Flow cfm Oxygen cfm i ids: Date gallons 161 mo I* $1 vr Curies 0.6 I 3 mo 0. 6f3 vr (Includes Tritium) Sample Cond Chloride Sulfate Silica TOC Activity , Date pS/cm ppb ppb ppb ppb pCi/ml j RW-Ik 33J ___ ___ 12ao W3L s W xlbi l Limit [<300 ) [<6000] [ <1.0 ) RW-OUT O .ll6 ___ ___ 75.2. 13f ND Limit [ <10 ) [<200 ) [<1500] [<1.0E-2] DWST 0 O II If IN ND Limit [<1.0 ) [ <20 ) [ <20 ) [ <20 ) [<400 ) [ < LLD ], ! WST b .W $l Ll \ C> 32% 3%2Yfo~' Limit [<1.0 ) [ <20 ) [ <20 ) [<100 ) [<400 ) [<l.5E-41 J CURRENT CHEMISTRY- OUT OE SPECIFICATION:' NOTIFICATIONS ' CtR # Date Svs Parameter Umit Vabe Action j 92-053 6/19M2 Aux Boller Oil Seo Pit / Oil & Grease 93-003 1/5S 3 Reverse Osmosis Outlet 92-Qg9 5/4M3 TBCLC Diss O I W
?JAF CURRENT' CHEMISTRY
SUMMARY
IFORD Rx Water DATE/ TIME CPI POWER % MWth [<0.37] l Conductivity pS/cm pH I-131DE pCi/gm ' l { l' [<0.20] [< lE-4 ) i
.hloride opb ECP mv SHE Total I pCi/ml
[ <15 ) [<-250] Sulfate opb 02 opb Activity pCi/ml [ <15 ] , Silica opb H2 opb Sol Zinc oph Date [<100 ) [4-6] ! RWCU EFFLUDir FEEDWATER / CONDENSATE ' SAMPLE DATE/ TIME / DATE/ TIME nd pWcm O2 Date/ Time In Service Feedwater [<0.06] [20-50] ! CDI [ -- ] [ -- ] Cond pS/cm ' [<0.08 ) [<0.08 ) CDO [<0.08] [ -- ] Silica ppb H2 opb [ <75 ) [ <75 ] H2 Flow cfm 02 Flow _ ,,_,cfm l Activity pCi/ml re [<2.0] opb Cu [< 0 .1 ] ,. opb S.W. CHLORINE (PPM) DATE A B C SW out [0.5-2] ! Offgas: Date pCi/sec [<600] Recomb. Flow cfm Oxygen cfm '
'iquids: Date gallons mo vr Curies mo vr (Includes Tritium) i Sample Cond Chloride Sulfate Silica TOC Activity '
Date pS/cm ppb ppb ppb ppb pCi/ml RW-IN --- --- Limit [<300 ) [<6000] [ <l.0 ] < RW-OUT --- --- Limit [ <10 ) [<200 ) [<1500] [<l.0E-2] ! i DWST j i Limit [<l.0 ) [ <20 ) [ <20 ) [ <20 ) [<400 ) [ < LLD ] ; WST Limit [<l.0 ) [ <20 ) [ <20 ) [<100 ) [<400 ) [<1.5E-4] CURRENT CHEMISTRY OUT OF SPECIFICATION:.NOTIFICATIOi4SL CIA # Date Sys Parameter Limit Value Action R2-053 6/19/92 Aux Boller Oil Seo Pit / Oil & Grease 93-003 1/5/93 Reverse Osmosis Outlet j 93-069 S/4/93 TBCLC Diss O, h
FORM SAP-1.4 Page 2 of 19 MESSAGE SHEET MESSAGE NO. 2 Exercise Time: 20700 Issued To: Person Readina Meteoroloaical Data Issued By: Simulator /TSC/CR Controllers MESSAGE Wind Direction - from 270* Wind Speed - 3 mph Stability Class - E (very stable) Sky Cover - Sunny Precipitation - none O P THIS IS A DRILL O DO NOT initiate actions affecting normal plant operations
FORM SAP-1.4 Page 3 of 19 MESSAGE SHEET MESSAGE NO. 3 Exercise Time: 0710 Issued To: Security Guard in CAS Issued By: Security Controller MESSAGE The building shakes for about ten (10) seconds at the same time seven (7) different zones alarm. Zone # continues alarming after the shaking stops. Report occurrence to the Control Room. /' V) THIS IS A DRILL O' DO NOT initiate actions affecting normal plant operations
,- FORM SAP-1.4 Page 4 of 19 i
'- MESSAGE SHEET MESSAGE NO. 4 Exercise Time: ~0710 Issued To: MIS nersonnel Issued By: OSC Controller MESSAGE The building shakes for about ten (10) seconds. Loud creaking noises and bangs are heard during the shaking.
Call the Control room and inform them of this. l L THIS IS A DRILL O DO NOT initiate actions affecting normal plant operations
l FORM SAP-1.4 Page 5 of 19 O'v MESSAGE SHEET l
)
MESSAGE NO. 5 Exercise Time: 20710 Issued To: Control Room / Simulator Staff Issued By: Simulator Controller ! MESSAGE The building shakes for about ten (10) seconds. O I I THIS IS A DRILL l 1 c. i DO NOT initiate actions arrecting normal plant operations J l I
h FORM SAP-1.4 Page 6 of 19 MESSAGE SHEET MESSAGE NO. 6 I Exercise Time: 0725 Issued To: Control Room i Issued By: Lead controller i MESSAGE PROMPT If an UNUSUAL EVENT has not been declared, the Shift Supervisor should be prompted to declare an UNUSUAL EVENT #13. O ,
'. i
.i r
THIS IS A DRILL ; O DO NOT initiate actions affecting normal plant operations k h
FORM SAP-1.4 Page 7 of 19 MESSAGE SHEET MESSAGE NO. 7 Exercise Time: 0745 or as OSC Repair Team arrives to repair EDGs Issued To: OSC crew assioned to renair EDGs Issued By: OSC Controller / Observer MESSAGE There is a longitudinal crack in the air start piping just downstream of EDG-47 and EDG-50 valves. One air bank is isolated and fully charged (normal standby mode); the other air bank is depleted, with the air compressor running continuously. THIS IS A DRILL O DO NOT initiate actions affecting normal plant operations
s FORM SAP-1.4 Page 8 of 19 / \ V MESSAGE SHEET MESSAGE NO. 8 Exercise Time: 0745 or as OSC Repair Team arrives to inspect ARMS Issued To: OSC crew assioned to repair ARMS Issued By: OSC Controller / Simulator Controller MESSAGE Indications as follows:
- 1. Trip unit meter downscale.
- 2. Auxiliary unit meter downscale.
- 3. 09-3-1-19 annunciator in.
- 4. No local horns will sound.
- 5. Local alarm " Power Available" lamps lit.
- 6. No upscale alarms, annunciator or indicators will be received.
- 7. EPIC points downscale.
- 8. Power supply "High Voltage" lamps npt lit.
- 9. D-C volts meter will indicate OV.
O/ THIS IS A DRILL O DO NOT initiate actions arrecting normal plant operations
- s FORM SAP- 1. 4 Page 9 of 19 MESSAGE SHEET MESSAGE NO. 9 Exercise Time: After 0745 Issued To: Security Guard in CAS Issued By: Security Controller MESSAGE Numerous zone alarms come in simultaneously. Some alarms continue intermittently for up to five (5) minutes.
Security patrol reports that light pole near Security Building appears to be bent and leaning toward the ground. O THIS IS A DRILL O DO NOT initiate actions affecting normal plant operations
i
,- FORM SAP-1.4 Page 10 of 19 (k )s MESSAGE SHEET MESSAGE NO. 10 Exercise Time: After 0745 Issued To: Fire Bricade Leader Issued By: OSC Controller (West Electric Bay)
MESSAGE Indications as follows:
- 1. A fire occurred in the West Electric Bay,
- 2. The fire appears to be out.
- 3. Smoke and fire damage on electrical gear is evident.
- 4. Electrical equipment is covered with black soot.
THIS IS A DRILL O' DO NOT initiate actions affecting normal plant operations , i
FORM SAP-1.4 Page 11 of 19' , 73
-- MESSAGE SHEET -
MESSAGE NO. 11 r Exercise Time: 0800
-)
Issued To: Control Room Issued By: Lead Controller MESSAGE - PROMPT If an ALERT has not been declared, the Shift Supervisor should be prompted to declare an ALERT #13. , 5 i THIS IS A DRILL j ([]) DO NOT initiate actions arrecting normal plant operations l 5 i
.- FORM SAP-1.4 Page 12 of 19 MESSAGE SHEET MESSAGE NO. 12 Exercise Time: 0820 Issued To: Security Guard in CAS Issued By: Security Controller MESSAGE Security zone adjacent to buckled light pole alarms. Security patrol indicates pole has collapsed and security microwave has been hit. THIS IS A DRILL O DO NOT initiate actions arrecting normal plant operations
. FORM SAP-1.4 Page 13 of 19 MESSAGE SHEET MESSAGE NO. 13 Exercise Time: =0850 Issued To: Person Readinct Meteorolo(Tical Data Issued By: Simulator /TSC/CR Controllers MESSAGE Wind Direction - from 275* Wind Speed - 4 mph Stability Class - D (very stable) Sky Cover - Sunny Precipitation - none O THIS IS A DRILL O DO NOT initiate actions arrecting normal plant operations
FORM SAP-1.4 Page 14 of 19 MESSAGE SHEET ! MESSAGE NO. 14 Exercise Time: After 0925 Issued To: Emercency Director Issued By: TSC Controller i MESSAGE i PROMPT This is a prompt for Post Accident Sample System (PASS). Please request a PASS sample at this point to allow enough time for : the sample to be processes. O 1 I t THIS IS A DRILL - initiate actions affecting normal plant operations i
i
, i FORM SAP-1.4 Page 15 of 19
>0 MESSAGE SHEET l MESSAGE NO. 15 Exercise Time: =0930 Issued To: Person Readina Meteoroloaical D_qta Issued By: Simulator /TSC/CR Controllers MESSAGE Wind Direction - from 280* Wind Speed - 5 mph Stability Class - C (very stable) Sky Cover - Sunny Precipitation - none O NJ THIS IS A DRILL O DO NOT initiate actions arfecting normal plant operations ,
FORM SAP-1.4 Page 16 :- o f 19 O> MESSAGE SHEET MESSAGE NO. 16 Exercise Time: 0955 Issued To: Control Room Issued By: lead Controller i MESSAGE PROMPT : If a GENERAL EMERGENCY has not been declared, the Shift Supervisor should be prompted to declare a GENERAL EMERGENCY #. O
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~
THIS IS A DRILL O DO NOT initiate actions affecting normal plant operations i l I
,. FORM SAP-1.4 Page 17 of 19 i
\ MESSAGE SHEET MESSAGE NO. 17 Exercise Time: =1000 Issued To: Simulator Control Room Issued By: Simulator Controller MESSAGE All fire pumps have started. System pressure has dropped to 85 pounds. O i THIS IS A DRILL l l O no Nor initiate actions arrecting normal plant operations l
,s FORM SAP-1.4 Page 18 of 19
('-) MESSAGE SHEET MESSAGE NO. 18 Exercise Time: =1040 Issued To: TSC Manaaer Issued By: TSC Controller MESSAGE Chemistry technician reports large crack in east wall of the Sewage Treatment Facility with liquid seeping out of crack. r THIS IS A DRILL O' DO NOT initiate actions arrecting normal plant operations
~ FORM SAP-1.4 Page 19 of 19 MESSAGE SHEET MESSAGE NO. 19 Exercise Time: 2 1130 Issued To: Emeraency Facilities Issued By: Lead Controllers MESSAGE Drill is terminated. Notify all agencies. Instruct personnel to remain in place for a debriefing.
Place call to the NRC via FTS in the TSC. Place RECS line call via RECS in the EOF. (03 THIS IS A DRILL 'D DO NOT initiate actions arrecting normal plant operations
SUPPLEMENT;AL SCENARIO NO. 1 SEISMIC EVENT #1 Time: 0710 Location: Throughout the Plant Site Responsibility: Simulator /OSC/ Security Controllers A. Initial Notification At 0710, vibration is noticed in the Control Room. Calls also are received in the Control Room from various locations on site, including I&C, Security and the Warehouse. F B. Postulated Event A seismic event occurs resulting in an approximate 0.03G force. C. Restoration Guidelines Operations and Security should walk down the site. Operations should execute AOP-14. No damage should be noted. Event can be terminated after walk downs. Security. zones are restorable; no visible damage. D. Radioloaical Conditions None E. Personnel Contamination None I
SUPPLEMENTAL SCENARIO NO. 2 d' SEISMIC EVENT #2 Time: 20745 Location: Throughout the Plant Site - Responsibility: Simulator /OSC/ Security Controllers l A. Initial Notification At =0745, vibration and loud creaking and straining is I noticed and heard in the Control Room. Numerous calls from , around the plant site indicate continued seismic activity. .i B. Postulated Event A seismic event occurs resulting in an approximate 0.03G , force. C. Restoration Guidelines Operations should execute AOP-14 and AOP-17. Scrams and isolations need to be reset. ' D. Radioloaical Conditions None E. Personnel Contamination
- None 5
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)
t SUPPLEMENTAL SCENARIO NO. 3 10400 BUS /SHORT/ FIRE Time: After 0745 , , Location: West Electric Bay Responsibility: OSC' Controller A. Initial Notification , Fire alarm panel indicates a fire in the West Electric. Bay. B. Postulated Event Electrical fire related to a short in 10400 bus occurs. Smoke and soot is evident in West Electric Bay but no fire. C. Restoration Guidelines Fire brigade should investigate and ventilate the area. D. Radiolocical Conditions O -None E. Personnel Contamination , None p O
m
,, . SUPPLEMENTAL SCENARIO NO. 4 "D" EDG AIR LINE FAILURE:
Time: 0745 Location: "D" EDG Room : Responsibility: OSC Controller A. Initial Notification At 0730, an earthquake causes the momentary loss of 10600~ bus, "B" EDG starts, and "D" EDG fails to start. B. Postulated Event There is a longitudinal crack in the air start piping, just downstream of EDG-47 and EDG-50 valves. One air bank is isolated and fully charged (normal standby mode). The other air bank is depleted, with the air compressor running continuously. C. Restoration Guidelines
/
( At about 0900, when the repair crew arrives, air is blowing out of crack, located under deck plate, between. isolation valves 47 and 50, and the "D" EDG skid. The air must be isolated, by closing the open isolation valve-(47'or 50, whichever is lined up). This will stop the air leak. The repair team leader chould report conditions found to the OSC Manager and estimated repair time. It is expected that the repair team will repair the leak with rubber gasketing' and clamps. , After repair is complete, either the 47 or 50 valve can be opened (whichever is fully charged), adequate repair verified, and the EDG started. Estimated time for repair is one hour. D. Radiolocical Conditions ! None E. Personnel Contamination 'I None i .(~
\s
l f3 SUPPLEMENTAL SQENARIO NO. 5 LOSS OF ARMS Time: 0745 Location: Control Room Responsibility: OSC Controller / Simulator Controller i A. Initial Notification l Annunciator 09-3-1-19, ARM Downscale, will appear. Operations will discover numerous JJuis on back panel are not - operational. B. Postulated Event A short develops outside of the power supply, causing a common failure to a bank of ARMS. C. Restoration Guidelines . Operations will request I&C/OSC to repair. With I&C repair, the following may be noted:
- 1. Trip unit meter will indicate downscale. <
- 2. Auxiliary unit meter (local) will indicate downscale.- !
- 3. K1 (at trip unit) will cause 09-3-1-19 to annunciate.
- 4. No local audio alarm horns will sound'or beacons light.
- 5. Local alarm " Power Available" lamps will remain lit (normal).
- 6. No upscale alarms, annunciators or indications will -be ~ r received.
- 7. EPIC points will indicate downscale. !
In addition, upon a loss of power event, the following will . occur for the power supply:
- 1. High voltage lamp will not be lit. i
- 2. D-C volts meter will indicate OV.
If technicians replace power supply, replaced unit fails ! again. If technicians opt to find short prior.to replacing . power supply, short will not be found'during exercise , period. . D. Radiolocical Conditions None . \- E. -Personnel Contamination f None , l
3 SUPPLEMENTAL SCENARIO NO. 6 fY
.d SECURITY LIGHTING POLE FAILURE Time: ~0820 Location: Security CAS Responsibility: Security Controller t
A. Initial Notification Zone alarms and security patrol indicate that buckled light pole has collapsed, destroying a microwave unit. B. Postulated Event Security lighting pole damaged in seismic event fails in high gust of wind. C. Restoration Guidelines Zone may be restored at any time by I&C repair team upon, discussion with controller. + () D. Radiolocical Conditions None E. Personnel Contamination None 1 O .
SUPPLEMENTAL SCENARIO NO. 7 i RHR AND RHRSW CROSS-TIE Time: 21000 Location: Simulator Control Room Responsibility: Simulator Controller A. Initial Notification Operator action. B. Postulated Event If operator decides to cross-tie the "B" side of RHRSW to RHR, this will be allowed to be accomplished, but will be uncuccessful until mechanics clear out strainer baskets. After' attempt is made, no flow or high DP will be indicated. C. Restoration Guidelines OSC repair team can accomplish this cross-tie if action is 1 taken to clear strainers. D. Radioloaical Conditions As listed in Section 7. E. Personnel Contamination None l O
SUPPLEMENTAL SCENARIO NO. 8 LOSS OF FIRE LOOP , I t Time: =1000 Location: Simulator Control Room Responsibility: Simulator Controller l A. Initial Notification ; Operator shall be handed a message sheet indicating that all the fire pumps have started and system pressure has been reduced to approximately 85 pounds. B. Postulated Event ) A break of the system loop, brought on by the seismic event, is bleeding off pressure and liquid. C. Restoration Guide]hlgs Fire Protection Controller has discretion to locate fire line break anywhere. Break can or cannot be repaired at -i O Fire Protection Controller's discretion. D. Radioloaical Conditions j L Dependent upon break area. E. Personnel Contamination None t i l
SUPPLEMENTAL SCENARIO NO. 9
.f" -
D' TSC VENTILATION SYSTEM FAILURE Time: 21010 i Location: TSC Responsibility: TSC Controller A. Initial Fotification Temperature in the TSC drops dramatically. , c B. Postulated Event ,. TSC air exchange unit fails to isolate heated air. Event'to - be controlled by TSC Controller via Operations. Symptoms per controller to OSC repair team. j C. Restoration Guidelines ! Heating may be restored at any time after OSC repair team . dispatched and problem troubleshooted. ; ( D. Radioloaical Conditions None E. Personnel Contamination None 3 h 9
.l
r l SUPPLEMENTAL SCENARIO NO. 10 SEWAGE TREATMENT FACILITY LEAK f Time: 1040 [ Location: Sewage Treatment Facility , Responsibility: OSC Controller A. Initial Notification . A call is received from the Chemistry Technician that a large' crack exists in the east wall of the Sewage Treatment Facility, and the liquid is draining out of the crack ! forming a large pool of liquid on the ground. B. Postulated Event [ Seismic event cracked holding tank in Sewage Treatment l Faci).ity. Liquid waste is draining onto the ground and l possibly into the lake. i C. Restoration Guidelines . f The leak will be stopped whenever a containment is built to stop liquid release. ; D. Radioloaical Conditions l t None 1 1 E. Personnel Contamination None
+
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/[1005PSIG]\O p I DIFF PRES { -0.89 IN H20{
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" 14:21:18 71XFtW-T4-t1 -J -
" PLANT PARAi1ETERS LOG CTPAUG-8H 2434.2 DW PRS 1.84 CTPAUG-P6 2436.4 DW/TRS DP 1.87 CORE {1WT 2431.7 A %O~2 f10H 2.68 CORE %CTP '>
9.P 6 %O2 f10N ****** CORE % WT G7.9 ff %H2 f10H 0.00 CORE %WTAU 98.1 5 %H2 NON ****** RX LUL 200.O DW T 112.3 RX PRS 1004.C i GEN NWE 821. TRS PRS -0.02 I GEN [1UAR 22J TRS LUL 13.o2 GEN H2 PRS 59.1 TRS WTR T 81.8 600 UOLTS 508 TRS RIR T 88.4 PLANT EFF 3 0 . c,,,r z . '; N2 PRS 118.1 CST LUL CND UAC 77' %
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f*\ p . s U V 15:02:44 20LS-357 GO7% '/ 14:21:19 C71T4-TR5L F: . ' Forn ERP-1,1.3 James A. F1tzpatrick Huclear Power Plant PART III - Plant Paraneters Sequence No. APPt1 REACTOR POWER 00.74 . IPt1 PEACTOR POuER 1.865 '. SRt1 RERCTOR POWER 0.9666E+06 CPS PX WATER LEVEL 200.2 Inch TAF FEEDWATER FLOW 10.31 t1L6/HR RCIC FLOW 0.0000E+00 GPt1 PEACTOR PRESSURE 1004. PSIG HPCI FLOW 0.0000E+00 GPt1 LPCI A FLOU -=%2750 GFt1 LPCI D FLOW -1.775 GPf1 "A" COPE SPPAY FLOW O.00COE+00 GPt1 "B" COFE SPFAY FLOW 0.0000E+00 GPr1 DPWELL SUt1P LEVEL MM FT STACK GAS FAD. / . D5 UCI/sec RX BLDG UENT PAD. 244.1 UCI/sec RFUEL FLR EXH RAD. 27.80 UCI/sec TD SLDG UENT PAD. 62.El UCI/see PW SLDG UENT RAD.
- 6.934 UCI/sec SERUICE WATER PAD. 0.1427E-05 UCI/nl STACK HI PAHGE RAD. 0.2961 CI/see TS SLD HI rat 4GE FBD. 9.311 CI/sec RW BLD HI RANGE RAD. 1.022 CI/sec 0FFGAS RAD. 14.58 mR/Hr DRWELL PAD. 7.680 R/Hr P GHEST ttSL RAD t10H 1725. nR/Hr DRWELL PRESSURE 1.83? PSIG DRWELL TEtiPEPATURE 112.3 Deg F TOPUS WATER AVG Tt1P 91.79 Deg F TORUS UATER LEVEL 13.92 FT LPWELL H2 CCHC 0.0000E+00
- DRYWELL 02 COHC 2.673
- CST LEUEL 272.4 Inch Ener9 enc 9 Director Approval: tit 1E :
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'N__ g ' f0FFGRS {RD VENTjTS UEt4TjRW UEtIT) t10DE SWITCH C 85 F 0 o O O O RUN 13.9 FT O SERVICE WRTER_{ 1 CPSl O l
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! 03584 TURB SLDG EXHi 0 MR/HR lCF[ 5.0213.
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! ERST CRESC RRER 17.6 02 082
- CRD REMOURL HRTCH 2.6 l 22, 007
! WEST CRESC RRER 17.6 ! 32j G82i
' WEST REFUEL FLOOR 351.1 ! 649l 199640j EXHRUST t CPt1) i ( CPf1) r! (CPt1)
REFUEL FLOOR EXH DUCT 72 928l 26002[ { DELOW REFUEL FLOOR EXH 13? l 863l 260967 W e e O O
O O O 03:40:13 12CRS-135 m n 03:20:57 93TS-4A ..._:-. PLANT PARRI1ETERS LOG
!CTPAUG-8H 1864.7 , DW PRS 1.77 lCTPRUG-P6
~
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>RX FLG T 451.3 TBCL T 78.1 l BAROI1 PRS 2o .94 4
0 . O O
,7 p Y(8 O N.Y 03:40:13 12 CPS-135 ER!Mggg3 n 03:20:57 93TS-4A $r J . W Forn EAP-1.1.3 Janes A. Fitzpatrick Nuclear Power Plant PART III - Plant Paraneters Sequence No.
APRl1 REACTOR POWER 75.67 . IPt1 REACTOR POWER 0.00 5 SRt1 REACTOR POWER 211745.63 CPS RX WATER LEVEL 201.72 Inch TAF FEEDWATER FLOW 7.22 T1LD/HP RCIC FLOU 0.00 GPit REACTOR PRESSURE o??.67 PSIG HPCI FLOW 0.00 GPt1 LPCI A FLOW 0.00 GPt1 LPCI B FLOW 0.00 GPt1 "A" CORE SPPAY FLOW 0.00 GPt1 "B" CORE SPRAY FLOW 0.00 GPt1 DRYWELL SUt1P LEVEL 19.64 Inch STACK GAS RAD. o.04 UCI/sec RX BLDG UENT RAD. 05.40 UCI/sec RFUEL FLP EXH RAD. 28,86 UCI/sec TB BLDG UENT RAD. 40.29 UCI/sec RW BLDG UEllT RAD. 8.05 UCI/sec SERVICE WATER RAD. 0.00 UCI/n1 STACK HI RANGE RAD. 0.3E CI/sec TB BLD HI RANGE RAD. 5.02 CI/sec RW BLD HI RANGE RAD. 1.03 CI/sec OFFGAS RAD. 16.54 nR/Hr DRYWELL RAD. 8.05 R/Hr HIGHEST T1SL RAD flott 825.66 mR/Hr DRYWELL PRESSURE 1.75 PSIG DRYWELL TEMPERATURE 110.66 Deg F TORUS WATER AUG Tt1P 84.69 Deg F TORUS WATER LEVEL 13.80 FT DRYWELL H2 CONC 0.00 5 DRYWELL 02 CONC 0.00 . CST LEVEL 288.34 Inch Energency Director Approval: TIME: L e O O
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F FT F PSIG %1 86.5l 958'~.5ff01'.5 8T.'I( 15.3 T1 1'1'.'7 [ 1. 5' ' 0.IITEt1EI~EUD l WL RAD l GROUP 1 ISOLATION URLUE STATUS RX BLDG A P t1SL RECIRC -0.83 IN H2O MSIUS HOGGER DRAIHS sat 1PLE [SRUs OPEN i 0[ GROUP 2 ISOLATION URLUE STATUS CNT DW CAD H2 DW FLOOR &l RX BLDG OFF-GAS RAD I sat 1PLE PURGE SUPPLY EQUIP DRHS UENT 18 t1R/HP DW/ TORUS TORUS RHR SAMPLE TIP A P INSTR PURGE & DRAIHS SYSTEN ISOLATION URLUE STATUS LOW RANGE CONTIHUOUS OFFSITE REL RATES RWCU ' UUC HPCI LOCATION RATES X CF = uCI/SEC(nl) ISOL I?OL TURB BLDG RADW BLDG STACK 10 CPS CF { o.0449 RCIC ~ UENT UENT RX BLDG EXH 137 CFt1 CF ! 95.9000 0FF-GAS LIQ RAD PEFUEL FLR EXH 72 CPM lCF 28.8564 A E TURS BLDG EXH 40.2785 53 CPt1 l CF EXH SYS FLOW RATES RADW DLDG EXH 50 CPt1 CF 8.0482 FLOW SW EFF (n1)' 1 CPS CF 0.0000 SYSTEM (CFM) SSGT 0 HIGH RANGE CONTINUOUS OFFSITE REL RATES , 0FF-GAS 96 ti911 LOCATION RATES- X CF -= CI/SEC
- STACK !
STACK O t1R/HR lCF- 0.3810 RX BLDG EXH 127939 'l TURD BLDG EXH 0 HR /HR CF' 5.0213 TURB BLDG EXH 93584 RADW DLDG EXH 0 MR/HR CF 1.0275 RADW SLDG EXH l 32359 a:0 5 - 2
~y 6 .
y
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O 04:01 :32 07titi-LOGIC-L NOFUnL // 03:59:53 33PT-103 PSIG
~
. i; 5
SCR RX j . _. _ PPU TOPUS DRYWELL PC PX BLDG. _ OFFSITE f, N ' ; PRES: ' .R ' ~ TErP ~%- TOP M. ~
~': --
- c. 4. . . R9!G i !H co .F F7 F... -- - - - -
- 3. - 1. , .1
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! CURREllT t1ARGill TO l AREA URLUE l1RX t10Rt1[t1RX SAFE
! ! ((1R/HR ) ( t1R/HR ) l ( t1R/HR )
- e -4 + 4 t SPEt4T FUEL POOL l RX BLDG ELEU 344
)LtlEU FUEL URULT RUCU PRECORT AREA M l} RWCU HX ROOri j M
FUEL POOL PutiP ROOT 1 _ _ _ _ . _ _ _ _ , l CONTAt1Ill EQUIP STRG j l i_RWCU Put1P AREA ; jM. ! l RX BLDG SRt1PLE AREA
! .M l RDCLC HX ARER 0.8 i 4! Goo
{ RX BLDG ELEU 272 i 1.o I 08i ooE TIP CUBICLE 4.7 ! 120! 905 EAST HCU ARER 3.7 i 26 996 WEST HCU AREA 3. 7 31 C96 EAST CRESC RREA 19.7 ol 981 . CRD ret 10 VAL HATCH ! 2.8 . 2 21 997! WEST CRESC AREA i 18.7 ! 81l 981l l WEST REFUEL FLOOR ! 374.6 ) 625[ 199625j { EXHAUST ( CPt1) ( CPri) l(CPt1)]
! REFUEL FLOOR EXH DUCT 72 ' 028j 269928l l BELOW REFUEL FLOOR EXH } 137 ! 8631 269863l s
O O O 04:04:13 02-3FT-64R-W 26. 565t1# /HR // 04:04:10 71bMR-10110C
" PLANT PRRRt1ETERS LOG CTPRUG-8H 1066.0 l DW PRS 1.70 CTPRUG-P6 lo51.O DW/TRS DP 1.76 CORE NWT 1440.3 A %O2 f10N 2.41 CORE %CTP So.1 B %O2 NON 0.00 CORE % WT 24.5 A %H2 NON 0.Co RX LUL 204.0 5 %H2 NON 0.00 RX PRS 969.6 ; DW T 111.7 i
GEN NWE 4?O.5 j GEN NURP' 189 '
;TRS PRS 6_ . 0 2 1 -
55.1 I TRe " LUL l '" ' - GEN H2 PRS a 84.2'o i 600 lTRS WTR T r l 600 UOLTS iTRS RIR T 80.5 i PLANT EFF 33.4 CST LUL 287.9 N2 PRS 120.0 l CND URC 27.24 CND DT RWCU IN T 498.8 ' CND LUL -1.O CUFD IN T 81.8 i LRKE T 50.0 RX DRN T 450.0 RX FLG- T 451.3-RBCL T 81.1 TBCL T 78.7 BAROM PRS 29.94 a + n l r .
- s 03:59:53 G3PT-1031C-LM:cETWPSIG // 03:40:13 12CEst135 M 400P31G Forn ERP-1.1.3 ~
James R. Fitzpatrick Huclear Power Plant PRRT III - Plant Paraneters Sequence Ho. . APRl1 REACTOR POWER 87.22 '.
-IRM RERCTOR POWER 0.00 %
SRM REACTOR POWER 500898.25 CPS RX WATER LEVEL 201.62 Inch TAF FEEDi;f1TER FLOW 8.47 f1LD/HR RCIC FLO14 0.00 GPM REACTOR PRESSURE 988.65 PSIG HPCI FLOW 0.00 GPM LPCI R FLOW 0.00 GPM LPCI B FLOW 0.00 GPM
*R" CORE SPRRY FLOW 0.00 GPt1 "B" COPE SPRRY FLOW 0.00 GPM DRYWELL SUMP LEVEL 19.96 Inch STRCK GRS RAD. 9.04 UCI/sec RX BLDG UENT RRD. 95.00 UCI/sec RFUEL FLR EXH RAD. 28.86 UCI/sec TD BLDG UENT RAD. 40.28 UCI/sec RW DLDG UEHT RAD. 't. 05 UCI/sec SERVICE WATER RAD. n.00 UCI/nl STRCK HI RANGE RAD. 0.38 CI/sec TB blD HI RRNGE RAD. 5.02 CI/sec RW DLD HI RANGE RAD. . 1.03 CI/sec OFFGRS RRD. 18.32 mR/Hr DRYWELL RRD. 33.50 R/Hr HIGHEST t1SL PRD MON 1179.23 nR/Hr DRYWELL PRESSURE 1.78 PSIG DRYWELL TEMPERATURE 111.47 Deg F TORUS WRTER RUG Tt1P 84.69 Deg F TORUS WATER LEVEL 13,80 FT DRYWELL H2 CONC- .0.00 %
DRYWELL 02 CONC O.00 % CST LEVEL 287.70 Inch Energency Director Approval: TIME: < - - ~s*< w -m4' ye--+- T- yw s ri=-T y--
O . O O
?F F
4 , PLANT OPERATING PARAMETERS at =0920 in the Scenario I t
'Y
_._______.____________.____________.--.,2_ . . 'J
[3 'i k,) }. 04:04:13 02-3FT-64R-W 2G. 205tle/ HR a 04 :04 :10 710kR-10110C m
~ ..
PLRHT _ REBCTOP SUILDING STAG T 136 0 ';H; [N-i 10 f.FS lC
! 131; R HF- lg TEMPERATURE [minnimissammes]O l 111 l l 3 PSIG l RRD LEIEL U~ ~'
U i h )[ PUNT HRP l DIRECTORY
/
WFfTER LEVEL [ }[ l p-D
/j >,nesirl\O p I DIFF PRES l -0.83 IN H3%[ l
't Y
W - - meceu gj \ j t., E l l
, 't ISOLRTION STRTUS }
L L - - 40,c i,N O i
, j GRP 1 lGPP 2 lLYidlih L I' .
U O U RBD RELERSE (, 50 %cLR O. . i P4f ig SYS/LOCRTION l CURRENT URLUE 2% . m vm3
,1 OFF-GRS 18 t1R/HR C-y;w , '~___'
i SCRAM IHITIRTED 1 if g i
~
RX BLDG EXH 1 137 CFM [ l /- ' TOPUS , N FLR N C CFM { V Ii4 $ff O x' t I e.t ue 'i \ O i N BLDG EXH! RRDW BLDG C W 53 CPM 50 CPM C lC y / ! 0.0 FSIG l i, ] f I i ISOLBTION STRTUS
~
' ~
~~v'-- .
w_% . Ocq. . ;.g. .v5
.:w%MP5J3:.: .
L lOFFGRS lRD VENTjTD UENTjRU VENT} J' . O O O MODE SUITCH O pud
$. es F , .O T 239 FT f 0- SERVICE URTER j 1CPSJO 1
l 6 - l . , __ _ -m ..
O O O 04:21:44 03DPT-231H-I M // 04 :21:44 03DPT-231D-Im RRC
! RX n_ RPU _
TORUS DRYWELL _' PC j RX SLDG ! 0FFSITE_ yy gr_. .;
;yp ; y-_: :gi.
;e w: :::;y. :: .; _z -
y,y M.. ii. i ' 1H ' . .sy# f.. . ..- .-- _ ;.gyz i
; ..FT '. .
. - ..:. TF .T . O.M.TG. ..
T 2 E^ g. .. . . . l GROUP 1 ISOLATION VALUE STATUS e l RX DLDG AP!
! MSL RECIRC -0 23 IN H2"l MSIVS { HOGGER
! DRAINS sat 1PLE
[SRVs OPEN { Oj GROUP 2 ISOLATION URLUE STATUS
; CNT , DW j CAD H2 bW FLOOR &l RX BLDG ! l' OFF-GR$ RAD ]
! SAMPLE i PURGE , SUPPLY l EQUIP DPHS! UENT ! 16 itR'HP l l DU/ TORUS TORUS RHR SAMPLE!
j A P INSTR PURGE & DRRIHS i [SYSTEMISOLATIONURLUESTATUS _ LOW RANGE CONTINUGUS OFFSITE REL RATES ; HPCI LOCATION i RATES X CF = uCI/SEC(n1)! TURS DLDG RADW BLDG. STACK l 10 CPS CF : 9.0440i RCIC 95.9000! UENT UENT , fRXSLDGEXH : 137 CPt1 CF i OFF-GAS l LIQ RAD i ' REFUEL FLR EXH 72 CPM ! CF ! 28.8564!
! E !
TURD BLDG EXH ! 53 CPr1lCFi 40.2785l
! EXH SYS FLOW RATES i .
RADW DLDG EXH 50 CPM iCFl S. 0482j SYSTEM
' FLOWd' .
SW EFF (n1 ) 1 CPS lCFi ' '
- 0. 000"0l (CFM)
SOGT ei HIGH RANGE CONTINIJOUS OFFSITE REL RATES l
' OFF-GAS ! 82 " '
i STACK i 6911 ! RX BLDG EXH 127966 STACK l 0 IIR HR lCFi 0.3810 TURS BLDG EXH . L EXHi 0 N W ' CF i 5.02G l 93584 RADW BLDG EXH l MReHRlCFl 1. 02;",j t 32359;- L .
O 04:04:13 02-3FT-64R-W 29.186t1#/HR // 04:04 :10 716KR-10110Cm 4 < '
- s 1
- > :._.,s
; . - , , je ; , ,
,7 _
3
., 1 1 , it_, , c -
.s o SCR '
l__ RX RPU_ TORUS DRWELL PC RX SLDG OFFSITE
- pgtgg . gg, p- . g - -
, PRES. H2 FT
_ _ __ . _p _PS IG. . . .. . _ _ . > . _ _ I, _ 50.9j ._. .. _. 960.6! __ PS.IG_7._.I.N_ 84._Tj. 202. 2l 13.9 111.31 1. 8- 0.1 TEMP l_y _L. f. U RAD . . _ . . .RAD CURRENT' T1ARGIN TO AREA : URLUE t1AX NORitf1RX SAFE I
! ( t1R/HR ) I t1R/HR ) f ( t1R/HR )
l SPENT FUEL POOL { RX BLDG ELEU 344 !M 6:
'~
W_
~~
l NEW FUEL URULT 1 {PUCUPRECORTAREA l M i RWCU HX ROOM l FUEL POOL PUMP ROOM M 'j ! CONTAt1IN EQUIP STRG ! RWCU PUMP ARER - gM _ . ; RX SLDG sat 1PLE ARER 'M j ' RSCLC HX RREA j O.7 ! 4l 999l RX 6LDG ELEU 272 ! 1.5 } 3Si 998! TIP CUSICLE 3.8 l 121 996! EAST HCU AREA 3.0 l 27 9971 WEST HCU AREA 3.0 32 977j ERST CRESC RRER 15.I 95: . 985 CRD REMOUAL HATCH i 2.3 1 23; 998i
~tJEST CRESC AREA h 15.1 i 8 51 985 WEST REFUEL FLOOR ! 302.7 1 600 199697,
[ EXHAUST ! (CPM) (CPM) (CPM) ! REFUEL FLOOR EXH DUCT ! 72 928 26092$ BELOW REFUEL FLOOR EXH ! 137 } 863l 269863j q- ~ -..au_ _- _ _ - - -- - - . - -. - . . - - - . . . - - - _ _ - - - - - _ . -- - - . ~ - - - - --- w - . . , s - , v s ., - --~ . . ,
O O 0; 04:23:20 33FCU-133-0 CLOSED // 04:23:17 07FBrt-R/B-D Of'r
' 2 PLANT PRRANETERS LOG i
CTPRUG-8H 1864.5 pro 1.78l l DW CTPRUG-P6 1669.1 'DW/TRS DP 1.75 CORE NWT 781.0 R %02 NON 2.41 < i CORE %CTP CORE % WT MM. 4 B %02 NON R %H2 NON 0.00 0.09 RX LUL 210.0 6 %H2 NON 0.00 RX PRS . DW T 110.7 GEN NWE ' 0.053 a, , TRS -PRS i GEN NURR '7 00 55.0 TRS LUL *"- GEN H2 PRS .,RS WTR T. 84.o;, i 600 UOLTS 601 PLRNT EFF 21.2 M Rm T 80.a - CST LVL 286.2 N2 = PRS 120.O CND URC 28.66 CND DT 20.'? RWCU IN T 486.o i CND LUL -1.6- CUFD IN T 78.8 i LRKE T 50.0 .RX DRN T 449.5 L e 8.1- RX FLG T 450.8 RBCL. T TBCL T 77.2' BARON PRS 29.94 c , n . . ., L
- I
., _ - - - , -4 . , _ , . , ._ , .. . . , , . , , , , _ . _ . ....s , , , , . . . . . , .,,m, . . , , -
\
04l04:13 02-3FT-64A-W 20. 20511# /HR // 04:04:10 71SKR-10110C Forn ERP-1.1.3 Janes A. Fit: patrick Huclear Power Plant PART III - Plant Parameters Sequence No. APRM REACTOR POWER 40.68 '. IRM RERCTOR POWER 0.00 % SRt1 REACTOR POWER 46244.28 CPS RX WATER LEVEL 202.38 Inch TAF FEEDWATER FLOU 4.97 MLD/HR RCIC FLOW 0.00 GPM RERCTOR PRESSURE 960.58 PSIG HPCI FLOW 0.00 GPM LPCI R FLOW 0.00 GPt1 LPCI O FLOW 0.00 GPM "A" CORE SPRRY FLOW 0.00 GPt1 "B" CORE SPRRY FLOW 9.00 GPM DRYWELL Sut1P LEVEL 20,18 Inch STACK GAS RAD. 9.04 UCI/sec RX BLDG UENT RAD. C5.90 UCI/sec RFUEL FLR EXH RAD. 28.86 UCI/sec TB SLDG UENT RAD. 40.28 UCI/sec RW BLDG UENT RAD. 8.05 UCI/sec SERVICE WATER RRD. 0.00 UCI/nl STACK HI RRHGE RAD. 0.38 CI/sec TB SLD HI RANGE RRD. 5.02 CI/sec RW BLD HI RRNGE RAD. 1.03 CI/sec OFFGHS RAD. 17.81 nR/Hr DRYWELL RAD. 130.83 R/Hr HIGHEST.MSL RAD MON 2372.28 nR/Hr SRYWELL PRESSURE 1.79 PSIG DRYWELL TEMPERATURE 111.37 Deg F TDPUO WATER AUG TitP- 84.70 Deg F TORUS WATER LEVEL 13.39 FT DRYWELL H2 CONC 0.00 % DRYWELL 02 CONC. 0.00 % CST LEVEL 237.45 Inch Energency Director Approval: tit 1E: k . .-..__.-._--___-----__--_--___----=---2 - - . -- - s - ~ , ,, <r .- ,-
O O O PLANT OPERATING PARAMETERS at =0923 in the Scenario i __ _____________-_______.___-___m_7 __ _ _--_. - m,a, =
- m n - = . e :. n = =5 m
O O O 04:24:16 02-3LT-83D .J
,*: . . . 111 </ 04:24:16 02-3LT-83A : . ~ . . .'
. ic. .: I l 4 PLRt(T ,
FEACTOR DUILDIllG STACK O.0 5.H2 JC N . 10 CP3 lO
! 218 PcHR lC TEt1PERATURE ![.'F :1:L'].;[,j[
1*8 U [l ' LJ RAD LEVEL N ][ l PLRtlT HELP j DIRECTORY i s WRTER LEVEL ji. "-, . : j ,[ l l F' D j, p3tg { g l L p l ; DIFF PRES L-0.81 IN H20.[ f, 'l y 5 W ! l E 7
% 1 1
mdF' ' a l ISOLRTION STATUS _.._i [Q)KRM]YIM&q t __ __ L b IN Em%
)
L RAD RELEASE l %PUR .O , l 7 t SYS/ LOCATION } CURREHT'UALUE ,! OFF-GRS
', 14f1R/HR((
SCRMf1 .RX DLDG EXH 137 CPt1 IT M D O i iORUS j REFUEL FLR EXHj
![~1
, 72 CPf1 l((
g r TURB DLDG EXHi 53 CPf1 9
/' -j. L- g, g . H2-'l .
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, RADW DLDG EXHi 50 CPf1 -
/ l 0.3 PSIGl iO
\ s I i
' ISOLATION STATUS I
' _ F_ .'P_'_'.._WW
._ _/ -
OFFGAS !!sRdTSTD UENTlRW UENT) t10DE SWITCH O
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$ 14,'oi .
O SERVICE WATER i i CPS 10
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l .- - .. .- - - . , . - - - - - . .- --
D / J V 04127:33 29PS-202D .- .
// 04:27:33 29PS-202A e Ei r 4-pT'
,uas ,
~]
2 5 3. s 1 ..
+
,_ s n +
RRC [ RX l RPU TORUS 1.8RYb] ELL PC i
~
RX BLDG. OFFSITE TEFF PRES -
.F 95tG ~
T15. 4I' ~i.9 ~0.' 1 TEt1P[FIAD [ W[ RAD (. GROUP 1 ISOLATION URLUE STATUS j l RX BLDG A P j pgggyg. MSL REC 1RC' HOGGEP' ~1 00 IN H205 L _ .._.-.__- N I k __ N E ' lSRVs OPEtt i 3j GROUP 2 ISOLATIOtt VALVE STATUS l l ~
.. ~ g g -
, ,... '" g g ; j OFF-GAS FAD j kiM- SLPPLY .i the . WENT [ 0 tiR'HR j _
tI SYSTEr1 ISOLATION URLVE STATUS I i LOW fat 4GE COtiTIt4UOUS OFFSITE REL RATES a
=
y HPCI TION l Re~' X CF = uCI/SECtml)
~
[ TURB 6LDG RADW BLDG STHs . ; 3S j CF ! 9.0492;
. RCIC UENT UENT ! RX BLDG EXH I CPit I CF; 95.9000i OFF-GAS 9! LIQ RAD l REFUEL FLR EXH 48 CPF CF i 19.0744!
WASTE ! TURB SLDG EXH i 53 CF.1 i CF i 40.2785! EXH SYS FLOW RATES RADW BLDG EXH S. 0482j
; l 50 CPfliCF }
' { FLOW j J EFF ( nl ) ' 1 CPS lCFi 0.0000!
, SYSTEM :
i SSGT l (CFri)d 600 HIGH rat 4GE cot 4TINUOUS OFFSITE REL RATES i OFF-GAS ! 268! I' STACK- 11777j LOCATIOt4 - l RATES X CF = CI/SEC i RX 6LDG EXH 4 STRCK i 0 t1R/HR t CF i O. 3310j TURD BLDG EXH , I TURD BLDG EXH } O r1R/HP !CFJ 5.0213! , RADW DLDG EXH l XHj 0 MP/HR }CF! 1.027] l 32359] 4u
-r-- - - n,- ,, . - . , + - , , . .. , .. ..n.. - ~ .. - - - -- - ----u ---
04:26:02 02-3LT-79 m IH 04:26:02 02-3LT-73 M IH n ..c,,..e~.,
~
,;t,, ,w>~ - , , -_] , _ ,
SCR j RX [ RPV TORUS .DRYWELL FC RX CLDG FSITE ;
- 2 pg g - -
. PSfG %
o 5. O.1
- II TEt1Pf RAD l WL' RRD f f CURRENT MMGJHTO l ARER l URLUE FIRX HORitMAX SRFEi
! ( t1R/HR ) ( T1R/HP) j ( F1R/HR ) !
2 i SPENT FUEL POOL M EO RX SLDG ELEU 344 W EE __- i HEW FUEL URULT ' lMM-IRUCUPRECORTRRER
, RWCU HX ROOM M.
_ 4 l FUEL POOL PUT1P ROOM i ; 1 CONTRMIN EQUIP STRG tM
' RWCU PUMP RRER :
,M
..M.
{RXBLDGSRt1PLERRER 'o l PDCLC HX RRER l 0.5 ! 4! 990i I RX SLDG ELEU 272 i 1.2 ' 39, 099! i TIP CUSICLE ! 2.9 ! 122 997f ERST HCU RRER ! Z3 i 28! 99::9
! WEST HCU RRER i
- 2. ? 33i 9M.
I ERST CRESC RRER ! 11.6 o[ 035) , CRD REMOURL HRTCH i 1.7 ! 23i **81 i WEST CRESC RRER ! 11.6 88 088 1 WEST REFUEL FLOOR l 231.4 760! 199769, f
- EXHAUST ; (CPM) (CPM) ; (CPM) l
! REFUEL FLOOR EXH DUCT ! 48 I 952! 260052[
[SELOW REFUEL FLOOR EXH l 137 i 863l 260863j g . g W w
- -, . . .m,. . - .
. - , . - --. , . . . . . . . . . m. - .. _ . . _ . . , , , . . . .. _ - . . ,
O O 0 04:28:07 38FT-101 -
. CFt1 u 04:27:51 02CS-2E-525 m
*2 PLANT PARANETERS LOG ,
{ CTPRUG-8H 1840.O i DW PRS 1.01l
- CTPAUG-P6 1053.0 DW/TRS DP I
CORE NWT 456.0 'A %02 NON i CORE %CTP CORE % WT M 11.O i B %O2 NON
!A %H2 NON 0.00 o 1
RX LUL ! B %H2 NON O.00 RX PRS 829.I ! DW T 115.7 ! GEN NWE 0.0 ' TRS PRS 1"84oi GEN NVAR 0-
,TRS 55.U LUL '
GEN H2 PRS !
'TR ,o WTR T 600 UOLTS O PLANT EFF 0.0 lMS M T l
122.2 CST LUL 263.8 l N2 PRS 120.0 lCND URC 23.92 lCND DT. 2.1 ! RWCU IN T 478.3
. !CND- LUL -7.3 : CUFD IN T 87.5 !
I LAKE- T 50.0 iRX DRN T 440.1 l-i _RX FLG T 450.1 lRBCL T 87.4 TBCL. T 87.5 BARON PRS 29.94
- c. .
% e.
ws-+=--+r- , v- w- werw -- w w w .w-* .w,4w --,
- wee ++----..-----w+-++e-.=wcw.--v,-w w-++w v r -we-=-,w=i--.=-=.'-*.Se,.*wvw w,-----emrv-www---,e--r-www-- .--w,--,, w w v.--*--vem-y- ,-..+eer -+-w-vv-e w 3- - - .-- - ,* ,,+>r w-- c-w~,- r-- -w +
~% s-1 04:25:15 05-K14-6 FESET ' 04:25:15 05-f:14-A P E'!ET Forn ERP-1.1.3 Janes A. F1 t patrick 14uclear Power Plant PART III - Plant Paraneters dequence No.
APRM REACTOR POWER 6 % IRT1 REACTOR POWER 74.20 ; SRt1 REACTOR POWER 3270080760.0 CPS RX WATER LEVEL Inch TAF FEEDWATER FLOW U.UO MLD/HR RCIC FLOW 194.S6 GPM REACTOR PRESSURE PSIG HPCI FLOW 4243.55 GPt1 LPCI A FLOW 0.00 GPM LPCI B FLOW 0.00 GPM "A" CORE SPRRY FLOW 0.00 GPt1 "D" CORE SPRAY FLOW 0.00 GPt1 DRYWELL SUMP LEVEL 20.41 Inch STACK GRS RAD. 0.05 UCI/sec RX DLDG UENT RAD. 95.40 UCI/sec
- RFUEL FLR EXH RAD. 23.86 UCI/sec TB DLDG VENT RAD. 40.29 UCI/sec RW BLDG VENT RAD. 8.05 UCI/sec SERVICE WATER RAD. 0.00 UCI/n1 STACK HI RANGE RAD. 0.38 CI/sec TD BLD HI RANGE RAD. 5.02 CI/sec RW BLD HI RANGE RAD. 1.03 CI/sec OFFGAS RAD. 12.01 mR/Hr DRYWELL RAD. M R/Hr HIGHEST MSL RAD MON 25.63 mReHr DRYWELL PRESSURE . 1.33 PSIG DRYWELL TEMPERATURE 113.82 Deg F TORUS WATER AUG TMP Deg F TORUS WATER LEVEL FT DRYWELL H2 CONC 0.00 %
DRYWELL 02 CONC 0.00 % CST LEVEL 285.37 Inch Emergency Director Approval: TIME: m. k . 6
-a1,.. - ,,w.r .,, . , w , -w, v. -- - . . - e.w- .o-,--++ ~ w i
=
v-O 4-r.
,m, 4,
v u S R ,- E . s T , E o M i r r A a n R e A S c P , G e , h + v O N t - I T i n - A 5 R 2 E 9 0 P
~
O w t , T a - N , A L , P + c 4 O w I -
w . 04:29:06 TCTGO4 .
// 04:29:05 94PS-104/105 m PLANT ..
REACTOR DUILDIllG STACK
^
y--~~., i [ 0.1 7.H2 ji'
.3 l 10 CF { [
- r. p,gg p { TEt1PERATURE '. T-l'. T..::!$C j i
- ! t 16 1.o SIGl RAD LEVEL [ ((
~
] PLRHT HELP Lj ~ C DIRECTORY WATERLEVEL[ ,U tl D /F 793 pgjg ]( p <
r I p DIFF PRES ! -1.04 IN H20l[ i, y f ; i i l W l l \ } \ E. Q hp$?" -lYY 5$ "
-c i i ISOLRTION STATUS L .m .
M[ENb t e [ I U U U RAD RELEASE re 5.PWR $j C f { "y ;
*SYS/ LOCATION I CURRENT URLUE t,
' .'h l
'~ ~ ~ ~
OFF-GAS 1 6 t1R.'HP [
- $CRppt INITIATED
%y; g ; -
RX DLDG EXH j 137 CPT1 l[ g TORUS h9 . , REFUEL FLR EXH! 48 CPf1 {
, i s , lTURS BLDG EXH; 53 CPf1 !i~
_.k /~ , I I
' lRADW DLDG EXHl 50 CPt1 ((
,7 ,l i
[ 2.2 PSIG } ' O ISOLATION STATUS
-m. . .auw
- s. ,-
-- m !
-~ , = - _ _ - - _ .
OFFGAS lI:TMIDiliTTD UENTjRW UENT) t10DE SWITCH O
~~
F
] U b U U SHUTDOUN FT O SERVICE WATER i 1 CPS 10 b
, . , ~ , , -- , , , - .
O ^ O 04:32:37 07-P m // 04:32:37 07-K
,, 2 ,- -
~s
;s. -
lus < 1i .. . E
~
~ . M t 1 o i RRC i RX [ RPU TOPUS DRYtJELL PC R.X SLDG ~
l OFFSITE PRES TEMP PRES H2 - PSIG F PSIG % . .
"'612Ts
~
~
~ii6.5f ~ 1.T 'it .1 ~TE}1P RAD [t[L' IAD
[ GROUP 1 ISOLATION VALUE STATUS l RX SLDG APl
. HSL -* RECIRC
' 1NS 5Vt' HOGGER [-1.02 INH 2O)
C.-. i_ __.. . _E IN . . __ _ lSRVs OPEH : j j GROUP 2 ISOLATION VALUE STATUS
^
i
~ '
' CAD N2 ')W FLOOR I ~ , . ,
DW [ OFF-GAS RAD
- PURGE SUPPLY EQUIP DRN!; . j a._ g . ! 6 t1F/HR
[,SYSTEMISOLATIONUALUESTATUS _ LOW RANGE CONTINUOUS OFFSITE REL' FATES HPCI LOCATION f RATES XCF=uCI/SEC(nl] f TURD BLDG l RADW BLDG
! STACK t 10 CPS CF 9.0507j RCIC
( ! UENT ! VENT RX DLDG EXH i 137 CPM CF 05.9000j OFF-GAS D REFUEL FLR EXH ! 48 CPM i CF 19.0744{ f' 3 l TURD BLDG EXH 53 CPf1 ' CF j 40.278$ EXH SYS FLOW RATES , RADW DLDG EXH ; 50 CFM CF i 8.0482l I FLOW l i SW EFF (nl) 1 CPS CF{ 0.0000! j SYSTEM (CFM) l I5BGT 6000i HIGH RANGE CONTIHUOUS OFFSITE REL RATES [ i
! 11776l l RX BLDG EXH I Oh !
TURD BLDG EXHi 0 MR/HR ICF1 5. 0213l
! TURS BLDG EXH l RADW BLDG EXH ] 32359) m ,
A
.-. _ ~ . . . - - - . -
d 04:31:37 23LT-2018 M FT u 04:31:03 20 TIS-532 m y, p; ,;; q ss . ; g- m _s
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sI1 SCR [ RX i RPU TORUS DRYWELL PC ._ RX 6LDG. OFFSITE PRES TS1P PRES H2 j MIG F ~
. PSIG '4 ~
_ 4* NE. E _ _. 116.3 fl .' ~~ T.' 1 TETIP[5A ) IJI'l RAD I ! CURRENT T1RRGIN TO l RRER. URLUE t1RX HORt1 T1AXSAFEl t t1R/HR ) ( t1R/HR ) - ( t1R/HR ) ! SPENT FUEL POOL 1 M ' RX SLDG ELEU 3<* i ! i NEW FUEL UAULT j RWCU PRECOAT APER i
- j. M{
RUCU HX ROOT 1 FUEL POOL PUt1P ROOM iM_ CONTRMIH EQUIP STRG ' i RWCU PUMP RRER
-y i
_ .M,I RX BLDG SRt1PLE AREA ! RBCLC HX RRER i 0.5 4 990' ( RX DLDG ELEU 272 l 1.2 39 909 l TIP CUDICLE 3.0 122 097! j ERST HCU RRER 2.4 28 098} WEST HCU RRER ! 2.4 ! 3 31 998i EAST CRESC ARE9 l 12.1 i 987 088{ CRD REMOVAL HATCH { 1.3 l 2 31 998l i WEST CRESC RRER 1 12.1 i 8 81 988i j WEST REFUEL FLOOR i 242.6 j 758; 199758! EXHAUST f (CPt1) l (CPri) l(CPt1) REFUEL FLOOR EXH DUCT I 48 I 952i 260052 SELOW REFUEL FLOOR EXH } 137 ] 863l 269863 .
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- . . . . 6 ' . . . . . 9 0 06 . 5 0 1 767 .
1 2 5- 2 3844 9 1 1 1 4 44 2 M2 F 3 G SPNNNNT SLTT S TTTT S , 3 O RDOOOO RU R R . w P NNNN s 1
#t L P L P' R P NN P 7 S TI I I NG 0
7 S R2222 W A' RL N , e =- 5 R TO0HH UDDF O 3 2 E
/ %%%% SSSS CF R 4 T WW W RRRR 2 UUXX A 4 .
e 0 E DDABABD TTTT N RCR-R B - O
+
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- - - NC LP NVPLE LV L -
7 t H GG %% N2O w UU
+
0 HVT - AAEEE 7 5: N E LL .. e 2 PPRRR NNN0A TDDDK CC - 3 TTOOOXX EEE0L SNNNA. BB
=
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+
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l l s 7 04:30:11 94TS-EHT-2/4 M // 04:29:40 94RTD-TFP-0~m DEG F Forn EAP-1.1.3 James A. Fitzpatrick ttuclear Power Plant PART III - Plant Parameters Sequence tio. APRM FEACTOR POWER -
- IRt1 REACTOR POWER 43.82 '/.
SRt1 REACTOR POWER 1828088832.0 CPS RX WATER LEVEL M Inch TAF FEEDWATER FLOW U.eu t1LD/HR RCIC FLOW 307.53 GPt1 REACTOR PRESSURE 656.0? PSIG HPCI FLOW 426?.44 GPM LPCI A FLOW 0.00 GPt1 LPCI B FLOW 0.00 GPt1 "A" CORE SPRAY FLOW 0.00 GPM "B" CORE SPRRY FLOW M GPt1 DRYWELL Sur1P LEVEL .x.64 Inch STACK GAS RAD. 0.05 UCI/sec RX BLDG VENT PAD. C5.90 UCI/sec RFUEL FLR EXH RAD. 14.07 UCI/sec TD DLDG vet 4T RAD. 40.28 UCI/sec RU BLDG vet 4T RAD. 8.05 UCI/sec SERVICE WATER RAD. 0.00 UCI/nl STACK HI RRt4GE RAD. 0.38 CI/sec TB BLD HI RANGE RAD. 5.02 CI/see RU SLD HI rat 4GE RAD. 1.03 CI/sec OFFGAS RAD. 6.00 mR/Hr DRYWELL RAD. M R/Hr HIGHEST MSL RAD MON 21.22 mR/Hr DRYWELL PRESSURE 2.01 PSIG DRYWELL TEMPERATURE 116.15 Deg F
~ TORUS WATER AVG Tt1P . Deg F TORUS WATER LEVEL FT DRYWELL H2 C0t4C U.09 .
DRYWELL 02 C0 tic 2.41 ".
/
CST LEUEL 245.78 Inch Energency Director Approval: TIllE : b O O O
L ! . 1_ 1_ O u S . R _ E T E o _ M i r a 1 A n R e _ A S c P , G e h O N t I T i n . A 0 R 3 _ E 9 0 P = . O t T a _ N - A
+
L _ P ._ O :
, !. ' 4
w
-S.
V V 04 :32:57 0714M-33G Wi+ r.- : . J. 04:32:57 07t4M-33F m'. PLANT _ . . PEACTOR LDING STACK
! O.1 *H2 .
l] ' L 10 CF2 lU M P-HR l g l TEMPERATUFE . (( RAD LEVEL [ [ 'l PLANT HELP DIRECTORY WATER LEVEL , M ][ p U [l 568PSIG]\O p , 5 l DIFF PRES i -1.00 IN H207- I
~ w :
Y f' W . xc ns p g< E MSi * - h n i j ISOLATION STATUS l L E IN[isbg:."
.7 Yy 1
'GRP 1 MliY[NM]
j ---- L -- J$ i U J Ll RAD RELEASE
.-O g"g)~~ --PWP f[ [
' j., .
!SYS' LOCATION CURRENT URLUE I '
Ej i0FF-GAS I 611R/HR i[ p [ ; TORUS lRX DLDG EXH r 137 CPM j[ [ / ! REFUEL FLR EXH! 48 CPM ! I: I, O 'e: , F 0.1 .H2 O iTuRe etDG ExHi sa Cert p(( f !PADW DLDG EXH! 50 CPt1 g
-'s. ?
? ,s j { 2.8 PSIG l \]I
' "' f I
.. ISOLATION STATUS i
'~ - ____# ;
, OFFGAS ip*RiisiiTTD UENTlRW UENT; MODE SWITCH C F 0 0 0 0 0 2HUTDOWN k- - ~
FT O SERVICE WATER l 1 CPS lO
- a r.. .
~
f 0; O O 04:37:28 13 SPI-1 -
- RPM // 04:37:23 23 SPI-161 m RPM r.
!i.
, D ,f I, ' * .e . ' !? m n- u .~ . .
, ..; 8 a .c - ~t <
RRC
~
[ RE 3 RPU TORUS DRYWELL. 1 PC - RX DLDG d5 FT5 3y y. _ g- y.. y y -- .
.. F .P'tG.
w ' 4 - . * . ~. P.SIG' . I.N S %_ x-
- y. - . - - - . - _ , _ - _ .- -- -
l 0 . 01 379.9 1 220.6L~ ,
.y 116.li 2.4 0.1 TEt1P l PAD ! WL RAD j GROUP 1 ISOLATION VALUE STATUS RX DLDG APj ML ] -1.00 IN H2Oj
; DRAINS i lsat E IRC 1PLEl HOGGER ii i {
MSIUS u j .
'SRVs OPEH ' Oj
[ GROUP 2 ISOLATION VALVE STATUS DW i OFF-GAS RAD CRD H2 ' IDW FLOOR tLi SRK EEDG. PURGE. SWPL,Y EQUIP ERHS_ m' LUENT _; 1
, 6 i1P-HR P
TIP D I ISYSTEt1 ISOLATION URLUE STATUS ! LOW RANGE CONTINUOUS OFFSITE REL RATES j
$ HPCI :
! STACK LOCATION RATES X CF = uCI/SEC( nl )
10 CPS iCF ?.0428i RCIC ITURD SLDG RADW DLDG , i ! VENT VENT II:tXBLDGEXH ! 137 CPM iCF 95.9000I l' OFF-GAS Dl REFUEL rLR EXH ! 48 CPM ! CF i 19.07441 3 '
' TURD SLDG EXH i 53 CPt1iCFl 40. 2?S5i EXH SYS FLOW RATES !
jRADW DLDG EXH 50 CFM ! CF 8.0482! I t FLOW ~~l l SW EFF (nl ) i 1 CPS 1CF, 0. 0000l SYSTEM i
'. ( CFri) a _.
r_S6GT l i 6000! HIGH RANGE CONTINUOUS OFFSITE REL RATES l i OFF-GAS I 0' - l 11730; t LOCATION RATES X CF = CI/SEC '
! STACK i . ,
I i RX BLDG EXH M TURB DLDG EXH 0 t1R/HR I CF t 5.021: TURS DLDG EXH RADW BLDG EXH 0 11R'HR j CF l 1.0275 RADW SLDG EXH ! 32359] b .
.v. . .,m... .w ., c . - , ,, , , . . . . .. -
04:37:13 33PT-102 munismulanummmimusurPSIG a 04:36:29 0?Hil-LOGIC-5 NORMAL y . , - , . ,_ ; . , -
. , , _ . . ,. , . , m. r, g b/ # 4 ,.q 1. e f g / 4 ,
SCR 1 f RX J RPU . TORUS DRYWELL PC 5ISLDG. OFFSITE , z : Pass- ~ WI. .TQP PRES H2- ~ .
-1 '^
.,. = - -_
_ . . - PSS_ _G_ ,-- En F^ ,-- PBIG 2 '
! 0. 0; 425.31 -217.0;- _ . _ . _
116.3j 2.4 7 . - - - - --.0.1)
- - - . .TEMPl RRD j WL '
PRD CURRENT i t1RRGIN.TO l. j RRER ' URLUE Il1RX HORTO1RX SAFEi i
} }
F ( T1R/HR ) (( t1R/HR ) } ( MR/HR ' )i
; SPEm FUEL POOL M 'M WM l RX DLDG ELEU 344 i HEW FUEL VAULT M '
M l RWCU PRECORT ARER __. [RUCUHXROOt1 .M . j FUEL POOL Puf1P ROOT 1 M 'M. ~ j CONTAMIN EQUIP STRG M iM ' i RWCU PUMP RRER ' M, RX BLDG SRt1PLE RRER M - RBCLC HX RRER ! 0.5 i 5i 1000! RX DLDG ELEU 272 i 1.0 1- 39l 995 TIP CUSICLE , 2.5 i 122} 093; EAST HCU RRER i 'O ! 28( 996i WEST HCU RRER 2.0 y 34; 9os! EAST CRESC RRER + 10.3 ! 100j ?90: CRD REMOURL HRTCH 1.5 I 23i 999:
! WEST CRESC RRER i 10.0 l 90; 990- ,
! WEST REFUEL FLOOR 200.0 1 800s 199800j i
} EXHAUST l (CPM) ! (CPM) (CPM) 3 6 i REFUEL FLOOR EXH DUCT ! 48 I 952 264952 l BELOW REFUEL FLOOR EXH l 137 j 863l 269863 24; .
)
v
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- O RDOOOO RU R R .
P NMMN PT L PLRR P NN P 3 2 S TI I ING 9 S R2222 WR RL N . - 2 R T0OHH UDDF O 7 4 E
/%%%% SSSS CF R WW 4 T W RRRR 2 UUXX A DDABABD 0
E TTTT N RCRR B - O/MA
/ ii! ;! i! ! !l ;. ,! . :f 1
R 4OOO6 7 0 O G I A 0 . 00 0 48 S . . . . . . . . . . . P P . . . 5 005O0 00 0 96 80005M4 3 - T 5 5 77 7 . N 1 A MP L - D H6TPTLS ERSSF LCTLT TT 8 6 8PWTWUR WARTF UADU + n T
- NC LP MUPLE LU L P
3 GG %% N2O 2 UU HUT . 9 2 AREEE N E LL 7 PPRRR NNN0A TDDDK CC 4 2 TTOOOXX EEE0L SNNNA BB 4 0
- CCCCCRR
' j !' ,:! i GGG6P
>I ifl CCCCL
!!l RT -
O
77
.Q-04:36:13 02-3PT-52D M PSIG // 04:36:09 06LT-52C 16'.553IH Forn ERP-1.1.3 Janes R. Fi tzpatrick 14uclear Power Plant PRRT III - Plant Parameters Sequence Ho.
RPRt1 REACTOR POWER 0.00 '; IRM RERCTOR POWER 0.00 % SRif RERCTOR POWER 98378.75 CPS RX URTER LEVEL 169.34 Inch TRF
' FEEDWRTER FLOW O.70 MLD/HR i
PCIC FLOW 397.99 GPt1 RERCTOR PRESSURE 469.32 PSIG HPCI FLOW 4272.22 GPt1 LPCI R FLOW 0.00 GPM LPCI B FLOW 0.00 GPt1 "R" CORE SPRRY FLOW 0.00 GPf1 "B" CORE SPRRY FLOW . GPt1 DRYWELL SUMP LEVEL 20.87 Inch STACK GAS RRD. .7.05 UCI/sec RX DLDG UENT RAD. 45.90 UCI/sec RFUEL FLR EXH RRD. 19.07 UCI/sec TD DLDG UENT RRD. 40.28 UCI/sec RW DLDG UEHT RRD. 8.05 UCI/sec SERVICE WRTER RRD.. 0.00 UCI/nl STRCK HI RANGE RAD. 0.38 CI/sec TD BLD HI RANGE RRD. 5.02 CI/sec RW DLD HI RANGE RAD. 1.03 CI/sec OFFGRS RRD. 6.00 mR/Hr DRYWELL RAD. M R/Hr HIGHEST MSL RAD MON l t> . y 1 mR/Hr DRYWELL PRESSURE 2.42 PSIG
- DRYWELL TEMPERATURE 116.45 Deg F TORUS WRTER RUG TMP Deg F TORUS WRTER LEVEL FT DRYWELL H2 CONC u.uy %
DRYWELL 02 CONC 2.41 % CST LEVEL Inch Energency Director Approval: TIME: 4
, , ~.w,. . . . . , . . , . v .,--,..w..c..e. e- .. , n , - .- ~ , , ..v.., ,- _,
. A O .
~
S R E T E o M i r a A n a R e A S c P G e - h O N t - I T i n A 0 R 0 . E 0 1 P = - O t T a N A . L _ P - z . 2_ _ O
O O O 04:48:31 03TR-244 f40PriRL // 04:48:07 18Rf1-021-28 M t1R/HR PLRHT REACTOR DUILDING STRCK
-~-
/ g 1 ;H2 l 'y !
R/HR 10 TEf1PERATURE [6[C F l[ _ PSIGl RAD LEVEL [MM PLRHT HELP O f~~~' - 0 DIRECTORY l WRTER LEVEL [ M (( l
]
D
/ 21 PSIG l5, C !
R [l q DIFF PRES l -1.00 It4 H20l[ Y d ; y j i
- -= q
\i E
l j ISOLRTIOH STATUS j L i {GRP 1 , M M'j C C C RAD RELERSE O %PWR !
} SYS/ LOCATION } CURRENT URLUE I OFF-GRS t 6 t!R/HR [
gtperi / / 'N . - RX BLDG EXH ! 137 CPt1 [ INITIRTED / TORUS RODS / ' REFUEL FLR EXHi 48 CPt1 [ IN / vl
/ 0.1 %H2 i T s O TURD DLDG EXH !
PRDW SLDG EXH! 53 CPf1 50 CPf1 [ 1[ x /
/ '/ L __ PSIGj \O l
'x / I ISOLATION STATUS N_ #
OFFGAS jftT.Edlii[TD UEHTjPW UENT T10DE SWITCH O F 0 0 0 0 0 SHUTDOWN FT C SERVICE WATER l 1 CPS lC
.- u i:
b .
l O O O l 04:53:09 18RIR-023-2 6 // 04:53:09 18RIA-023-2 M t ;", _ C" r~ PnpjTOq:
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T t).t. uT p i j o iorTTi<jTs
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- r s p ).
RRC h PyP RX 1 _.RPU TORUS DRYWELL PC .RX SLDG . _ _ OFFSITE PRES WL , H2 5 PSIG ~ IN .
\ *
- 0. 0l' ' ~19. 2l~ ~ 2057 _ _ _ _ ENEME_ tim NFfRAD T WL RRD l
l GROUP 1 ISOLATION URLUE STATUS RX BLDG A P "I' RECIRC -1.00 IN H2O ! t1SIUS HOGGER i DRAIHmo SRt1PLE (SRVs OPEH l 0l GROUP 2 ISOLATION VALUE STATUS j OFF-GAS RAD D4 TOPUS Mt TOPUS CAD N2 DW FLOOR ' RX BLDG SUPPLY . EQUIP DPH .'
'HP SAMPLa OENT' . 6 MR/HR
+ P IN9TP PUPGE 3 DFAINS. .
{_SYSTEMISOLATIONURLUESTRTUS_ LOW RANGE CONTINUOUS OFFSITE REL RATES HPCI LOCATION RATES X CF = uCI/SEC(nl) TURD DLDG RADW DLDG STRCK 1005 CPS CF 904.0884 I I' I '- UENT VENT RX SLDG EXH 137 CPt1 CF 95.9000 OFF-GAS D REFUEL FLR EXH 48 CPt1 CF 19.0744 3 TURS BLDG EXH 53 CPt1 CF 40.2785 EXH SYS FLOW RATES RADW BLDG EXH 50 CPM CF 8.0482 FLOW SW EFF (ml ) ' CPS CF O.0000 SYSTEN ( CFt1) SBGT 6000 HIGH RANGE CONTINUOUS OFFSITE REL RATES OFF-GRS O LOCATION RATES X CF = CI/SEC STACK 11724 STACK 0 r1R/HR CF 0.4840 RX BLDG EXH 0 TURB BLDG EXH 0 NR/HR CF 5.0213 TURS BLDG EXH RADW DLDG EXH 0 r1R/HR CF 1.0275 RADW BLDG EXH l 32359l wm . - L 4
~ _ ~ _ . - . . - - - - _ _ - - - - - . - - - . . - - - - - - - _ _ _ _ _ _ - - - - . - - - - . - - - _ - - -
i l l l 04:50:19 716US-10600F m VOLT // 04:50:18 71SKR-106500 ON
;- t g p .q ) .. L a v i u). :gs .p t >
np u / e g su; i u.,7;-;r > gp - i-e _ "-_ 3 7, . gs ,.s.;t _
- g. ,
<a-l 2 4 .
SCR l [ ._ RX . j_ . RPU TORUS DRYWELL PX BLDG. OFFSITE_ i ' lsPC H2 - l -PWR . PRES -
!- _%_._u PSIG.- *e.
l . . s . l { 0. 0{ ..19.2i _ _M . _ _ , , _ .l 0.1l TEt1P I PRD l UL l RAD CURREllT t1RRGIH TO ! RRER VALUE t1RX HORt1[t1RX SAFE ( t1R/HR ) I 4 ~ ( t1R/HR ) 1.(l1R/HR ) a SPENT FUEL. POOL ! l RX SLDG ELEU 344 l NEW FUEL VRULT l _ . 4 RWCU PRECORT ARER ! RWCU HX ROOT 1 i _ , FUEL POOL Put1P ROOT 1 i CONTRMIN EQUIP STPG i RWCU PUt1P RRER ! .__ ._
~
RX DLDG SAMPLE ARER RDCLC HX RRER 913 RX DLDG ELEU 272 , . ! 862 TIP CUSICLE : 114.8 ~~ 10j 885 EAST HCU RRER ! 960 WEST HCU RRER i 064 EAST CRESC RRER b~l251 ~58I 958 CRD REMOURL HRTCH ! 972 WEST CRESC RRER l 45.3 5 51 955 WEST REFUEL FLOOR ! 200.0 800j 199800 EXHPUST l ( CPt1) ( CPri) ( CPII) l REFUEL FLOOR EXH DUCT ! 48 oS2 269952} BELOW REFUEL FLOOR EXH l 137 l 863{ 269863j 6 . b
-- { il ,! ,7 O
1ll!!l. 0 0 0 0 0 0 1 696 4
. . ' . . . . . 9 0 0 .
0' 0 8966 . 6 2 9701 9 -
. 1 1 2 44 2 M
?
2 3 2 SPNNNNT SLTT S TTTT S 0 G- RD00O0 RU R R A O I P 11NI t ( 1 PLRR P NN P R E L S TI I I NG - 1 R2222 WA RL 1 T O' OHH i 9 0 S UDDF O 1 3
- R /%%%% SSSS CF R 5 E
- WW W RRRR 2 WUXX A 4
0 T DDABABD TTTT N RCRR B E O
;' ;! : !i!!itiii!!!!! < l oi1 A . 1 R
H R ~ 000O52 O 0 O 0O - O r7 R
/A . . . . . . . . . . . . . .
. 'P 1 7000029 0050U 00 0 95 . 0 - 1 91 5 5 ', 7 T 7 1 N 1 -
- A .
L _
. P _
9 2
- H6TPTLS E R S C" F LCTLT TT 1
2 0 8PWTWUR WARTF UADU _ 1
- - - 1C T LP 1UPLE l LU L .
t R B GG %% 12O ( UU HUT I . _ 4 AAEEE N E LL _ 1
- PPRRR NNN0A TDDDK CC 3
5 3 2 TTOOOXX EEE0L SNNNA BB _ 4 0
'" CCCCCRR GGG6P CCCCL RT _
r }ll' 4 O
04:50:19 715US-10600f m VOLT // 04:50:18 715ER-106500 ON Forn ERP-1.1.3 James R. Fitzpatrick Huclear Power Plant PART III - Flant Parameters ' Sequence Ho. APRM RERCTOR POWER 0.00 % IRM RERCTOR POWER 0.00 % SRM RERCTOR POWER 56.50 CPS RX WRTER LEVEL Inch TAF FEEDWRTER FLOW 1.31 MLD HR RCIC FLOW 0.00 GPM REACTOR PRESSURE 19.49 PSIG HPCI FLOW O.00 GPM LPCI A FLOW 0.00 GPt1 LPCI D FLOW 49.15 GPM "R" CORE SPRRY FLOW 5466.54 GPM
B" CORE SPRRY FLOW ,
GPM DRWELL SUMP LEUEL . - .. Inch STRCK GRS RAD. 408.25 UCI/sec RX BLDG UENT RAD. 95.99 UCI/sec RFUEL FLR EXH RRD. 19.07 UCI/sec TD SLDG UENT RAD. 40.28 UCI/sec RW DLDG UEHT RAD. 8.05 UCI/sec SERVICE WRTER RRD. 0.00 UCI/n1 STACK HI RANGE RAD. 0.48 CI/sec TS BLD HI RANGE RAD. 5.02 CI/sec RW BLD HI RANGE RAD. 1.03 CI/sec OFFGAS RAD. 6.00 mR/Hr DRWELL RAD. R/Hr HIGHEST MSL RAD MON 8.73 mR/Hr DRWELL PRESSURE - PSIG DRWELL TEMPERATURE . . Deg F TORUS WRTER AUG TMP . reg F TORUS WRTER LEVEL ' FT DRWELL H2 CONC 0.00 % DRYWELL 02 CONC 2.41 % CST LEVEL Inch Emergenc9 Director Approval: TIME:
+ a+--- '
--,g- gu y - g se 4
O O 'O . l I-i L l r i I L PLANT OPERATING PARAMETERS at ~1015 in the Scenario
f ( V(R. 05:04:59 10PS-1246 YE0 // 05:01:30 17RM-506 SF 3 CPS PLRHT . . . . REACTOR SUILDING STACK
' ~ ~ -_._
' 0.1 ;H2 _l h~' " s ,
! v7?51 CPS}O R /HF] g TEMPERATURE 6 lC F
}{ M PSIGl . RAD LEVEL _i J g -_
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! SYSTEt1 ISOLATION URLVE STATUS I I LOW RANGE CONTINUOUS OFFSITE REL RATES LOCATION RRTES X CF = uCI/SEC(nl )
I M CPS i CF l296713.0000! Tf*g7 TURD DLDGi kRDW DbbG l l STACK
}lf c c ..-; UENT i UENT i lRX BLDG EXH I 137 CPt1 i CF l C5. 9000!
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"- -WASTE l TURD BLDG EXH ! 53 CPt? 1 CF : 40.2785!
EXH SYS FLOW RATES i jRADW DLDG EXH l 50 CPr1 l CF { 9.0482j
! SW EFF (n13 1 CPS CF l 0.0000:
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, OFF-GAS 0
- LOC 3 TION l RATES X CF = CI/SEC
! STRCK i 117241 -
[ O ttR/HP CF ! 0.7671!
} RX BLDG EXH TURD DLDG EXHi 0 t1PeHR !CFi 5.0213i l TURD DLDG EXH i RADiJ DLDG EXH !
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! FUEL POOL PUt1P ROOM '
CONTRt11H EQUIP STRG i l RWCU PUMP RRER .Mj l RX DLDG SRMPLE AREA fM j ~ _ 475} l RSCLC HX RRER ' l RX SLDG ELEU 272 425i
! TIP CUDICLE l 475j i ERST HCU ARER '
503l f WEST HCU ARER- M 499i i ERST CRESC RREA 582j i CRD ret 10 VAL HRTCH M 450; WEST CRESC RRER 602!
; WEST REFUEL FLOOR s 200.O >
900! 199800i l EXHAUST l ( CPril l(CPt1) ( CPt1) l l FEFUEL FLOOR EXH DUCT ! 48 l 952 269952l l SELOW REFUEL FLOOR EXH l 137 l 863l 269863l 1 ('! 4 . 9 O O
O O O 2 05:07:26 10LS-102 lumannumusuun u 05:06:20 06PT-52C m
' 62 PLANT PARAf1ETERS LOG c .
iCTPAUG-8H 1645.I DW PRS l' .
- CTPAUG-P6 -0.O DW/TRS DP l CORE I1WT 0.0 . A P.02 I10N l l CORE P.CTP 0.O IB P.02 f10N 0.00i
! CORE P. WT 10.O i A P.H2 I10N i lRX LUL 247. ! B P.H2 f10N 0.00 !
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~
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!CND URC 0.00
'CND DT 0.0 i RWCU IN T 285.0
'CND LUL :- -
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C 05:04:59 10PS-1248 YE2 '/ 05:01:30 17 Fit-505 -
.' . CPS Forn EAP-1.1.3 Janes A. Fitzpatrick Nuclear Power Plant ,
PART III - Plant Paraneters Sequence No. APRt1 REACTOR FOWER 0.00 % IRt1 RERCTOR POWER 0.00 . SRt1 REACTOR POWER 54.34 CPS RX WATER LEVEL 210.22 Inch TAF , FEEDWATER FLOW 0.00 ItLS/HR RCIC F1 'W 0.00 GPM REACTOR PRESSURE 21.01 PSIG HPCI FLOW 0.00 GoM LPCI A FLOW 0.00 GPt1 LPCI 6 FLOW 1868.47 GPt1 "A" CORE SPRAY FLOW 5444.6 GPt1 "B" CORE SPRAY FLOW GPt1 DRYWELL Sut1P LEVEL . . . Inch l STACK GAS RAD. 133W6. 0 7 UCI/sec l RX BLDG UDIT RAD. 95.90 UCI/sec l RFUEL FLR ExH RAD. 19.07 UCI/sec l TB DLDG UENT RAD. 40.28 UCI/sec I RW BLDG UENT RAD. 8.05 UCI/sec SERVICE WATER RAD. 0.00 UCI/nl STACK HI RaHGE RAD. 0.64 CI/sec TD DLD HI RANGE RAD. 5.02 CI'sec RlJ BLD HI RANGE RAD. 1.03 CI/sec OFFGRS RAD. 6.00 nR/Hr DRYWELL RAD. R/Hr HIGHEST F1SL RAD t10H 7.53 nR/Hr DRYWELL PRESSURE PSIG DRYWELL TEt1PERATURE Deg F TORUS WATER AUG TitP - Deg F TORUS WATER LEVEL FT , DRYWELL H2 CONC 0.0v % l DRYWELL 02 CONC ?.41 % ' CST LEVEL M Inch Energency Director Approval: TIFIE : O O O
O O O
~
f i PLANT OPERATING PARAMETERS at ~1045 in the Scenario L L:
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m es er- r,- m e-*Js ehmuwaa +vw--k.m,m' w ,,w-rM--
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i C i l E E ISIO ! RRD LEVEL ~U PLANT HELP O' U f DIRECTORY iWATER LEVEL 6 _7 -_ _ _ _ _ Pi Q D /i o esIG7., 0 ! p [" ' DIFF PRES j -1.00 Itl H20l[ f D y ', r 3 i i l I ! u I E .p[Mf3f/g4N3j hiagjd g ,_ ,
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!RADW BLDG EXHj
./l ?.5 PSIG ! \O
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ISOLATIOtt STATUS I l - s
- j. - -- N
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O O O 05:07:26 10LS-102 NORhHL u 05:36:30 06PT-52C m 01 0 , hi( ' ' \' [ _ ,. E %:- ~ . _ -; - N _ - 'C RPC { RX l PPV TOPUS DRYWELL PC RX DLDG OFFSITI~ PWR PRES .W- H2-
,X HIG 1H %
I 0[0[ ~ 10[ 305.0[M_ _ __ _.
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FX DLDG A P j i (13103 3 t1SL l RECIRC l HOGGER { -1.00 IN H20f l DRAIHS j SAMPLE ! lSRVs OPEN Ol { GROUP 2 ISOLATION UALUE STATUS l
~~ @g ',. i 0FF-GAS RAD y g '
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- P INSTR 7 & DRAINS l SYSTEM ISOLATION URLIE STATUSj l LOW RANGE CONTINUOUS OFFSITE REL RATES i f LOCATION j RATES X CF = uCI/SEC(nl}l f iSTACK
#CIC - ' TURD BLDGRADW '- UENT DLDG i CPS f CF f 849762.6875!
UENT l fRXDLDGEXH i 137 CPM iCFi 95.0000! 0FF-GAS I PD ! REFUEL FLR EXH i 48 CPM i CF i 19.0744l g ' l TURD BLDG EXH 53 CPM iCF! 40.2785j EXH SYS FLOW RATES i RADW DLDG EXH i 50 CPt11CFj 8. 0482l i SYSTEM FLOW ! [SWEFF(nl) I 1 CPS iCF! 0.0000l
- l. (CFM) '
i SDGT , 600a HIGH RANGE CONTINUOUS OFFSITE REL RATES I
' 0FF-GAS Oi -! STACK I 11.'24l l RX BLDG EXH M STACK 1 MR
- HR } CF i 1.575f l TURD SLDG EXH i M D DLDG EXHI O MR/HP !CFi 5.02131 RADW DLDG EXHl 0 MP HR l CF j 1.0275{
l RADW BLDG EXH l 32359{ w t t- - t Tr eP-'-M --Mgi- M---w-r- m a n.F-ee + - +m*,- -ec- + - 5hy--+w---- --gw'-w4w -'-*ee
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( T1R/HR ) ! ( NR/HR ) l (I1R/HR ) i i SPENT FUEL POOL l '~ M i (RXBLDGELEU344 (( 4 LNEW FUEL URULT )MgM,M i PUCU PRECOAT AREA M ;M
'; RUCU HX ROOM ,
.i M
! FUEL POOL PUMP ROOT 1 M ~
i
! CONTRMIN EQUIP STRG ;
M i RWCU Put1P RREA , I RX DLDG SRMPLE ARER M
! RDCLC HX RRER Ot l l RX DLDG ELEU 272 n!
l TIP CUSICLE 0: IERST HCU RRER M 0! l (WESTHCUAREA .M Oj EAST CRESC RRER M O!
! CRD ret 10 VAL HRTCH M Oi i WEST CRESC RRER .
im O!
! WEST REFUEL FLOOR ! 200.0 i 800j 199800; EXHAUST l ( CPf1) j ( CPt1) f (CPri) ' I REFUEL FLOOR EXH DUCT 4 48 i 052I 269052
-BELOW REFUEL FLOOR EXH l 137 ! 563l 269863!
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b 4
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05:07:26 10LS-102 t 40F t19L << 05:06:30 06PT-52C M Forn EAP-1.1.3 Janes A. Fitzpatrick Nuclear Power Plant PART III - Plant Parameters Sequence Ho. APRt1 REACTOR POWER 0.00 % IRt1 REACTOR POWER 0.00 % SRt1 REACTOR POWER 54.75 CPS RX WATER LEVEL 379.67 Inch TAF FEEDWATER FLOW 0.00 t1LD/HR RCIC FLOW 0.00 GPM REACTOR PRESSURE 9.75 PSIG HPCI FLOW 0.00' GPl1 LFCI A FLOW 0.00 GPt1 LPCI B FLOW 0.00 GPt1 "A" CORE SPRAY FLOW 5454.05 GPM
0" CORE SPRAY FLOW .. -
GPt1 DRWELL Sut1P LEVEL
- Inch STACK GAS RAD. 999362.64 UCI/sec RX DLDG UENT RAD. 45.00 UCI/sec RFUEL FLR EXH RAD. 19.07 UCI/sec TD BLDG UENT RAD. 40.28 UCI/sec i RW SLDG UENT RAD. 8.05 UCI/sec l SERVICE WATER RAD. 0.00 UCI/nl
, STACK HI RANGE RAD. 1.47 CI/sec TB SLD HI RANGE RAD. 5.02 CI/see RW SLD HI RANGE RAD. 1.03 CI/sec OFFGAS RAD. 6.00 mR/Hr ! DRYWELL RAD. M R/Hr l HIGHEST t1SL RAD t10N 7.50 mR/Hr DRYWELL PRESSURE PSIG DRYWELL TEt1PERATURE Deg F l TORUS WATER AUG Tt1P Deg F l TORUS WATER LEVEL FT DRYWELL H2 CONC 0.09 % DRYWELL 02 CONC 2.41 % CST LEVEL Inch l Energency Director Approval: TIf1E : , l .
i l l r~'-) SECTION 7 (d. James A. FitzPatrick Nuclear Power Plant 1993 Partial Participation Emergency Exercise ' December 14, 1993 DATA I. Assumptions , II. Meteorological Information III. Plant Release Data " IV. Onsite Dose Rate Data and Maps V. Offsite Dose Rate Data and Maps VI. In-Plant Dose Rate Data and Maps VII. Area Radiation Monitors VIII. In-Plant Air Sample Data IX. PASS Data t t 6 i 6 P 7-1
SECTION-7 p)( ( James A. FitzPatrick Nuclear Power Plant 1993 Partial Participation Emergency Exercise December 14, 1993
+
s t r k I
'l~
O , e I. ASSUMPTIONS t' U O , I-1 ;
i t 1 I SECTION 7
- sO.
James A. FitzPatrick Nuclear Power Plant 1993 Partial Participation Emergency Exercise December 14, 1993 l Assumptions ; A. The plant has been running with failed fuel indicative of levels associated with Action Level 2 of the Failed Fuel Action Plan. , B. The leaks out of the drywell occur as steam leaks pressurize it to approximately 10-40 psig. The drywell leak rate is ' approximately 2.5 cfm (1.5% per day). C. A power spike causes approximately 10% to 20% fuel damage. , D. High Range Containment Radiation Monitor readings correspond to between 1% and 10% fuel failure. E. Area Radiation Monitor readings and Reactor' Building general area immersion dose rates were calculated using the ARTEMIS computer code. ARTEMIS is a compartmental transport model O for radioactive materials. Uniform mixing is assumed. 1 F. All dose rates have'been decay corrected. r G. Direct radiation readings in the Reactor Building'from the : drywell are minimal due to a dose reduction factor of 1 x-10 3 ! from the five foot thick drywell. Dose rates on contact with the wall near penetrations may show an increase as indicated ' on in-plant maps. H. The release is a filtered, elevated release from the plant stack. I. The release consists of primarily noble gases. J. Maximum dose rates will be approximately 5-10 mrem /hr at.1 ' mile down wind. > K. Predetermined meteorology and forecast meteorology'will-be used during this exercise. L. Post Accident samples will indicate approximately 20% of clad damage occurred as a result of the power spike. ! I-2 l
s e s & J w l SECTION 7 James A. FitzPatrick Nuclear Power Plant 1993-Partial Participation Emergency Exercise l December 14, 1993 P k O II. METEOROLOGICAL INFORMATION O ; i II-1
.. . _ - m . _ . = - . . .
i p SECTION 7 U James A. FitzPatrick Nuclear Power Plant 1993 Partial Participation Emergency Exercise December 14, 1993 Meteorolooical Summarv - The following conditions exist for the environmental release ' portions of the drill: TIME WIND DIRECTION WIND SPEED STABILITY (DEGREES FROM) CLASS l 0700 - 0850 270 3 E : 0851 - 0930 275 4 D 0931 - End 280 5 C Sky Cover: Sunny (0%) 5 i Precipitation: None o b I I
- O II 2 :
d
?- SECTION 7 James A. FitzPatrick Nuclear Power Plant 1993 Partial Participation Emergency Exercise December 14, 1993 Forecast The Lake Ontario region continues to enjoy the chilly, early winter conditions experienced so far this December. Temperatures are expected to remain in the 30s during the day and upper 20s at night. Skies will be clear, and there is a light breeze from the west helping to keep temperatures mild. Winds are expected to remain out of the west except on the Lake Ontario shoreline where winds may swing out of northwest very late in the day as rare winter-time gentle lake breezes begin.
The likelihood of rain or snow is 0% today and tonight, 25% tomorrow, and a 10% chance of snow showers on Thursday and Friday. , A weak low pressure area is stalled over Wisconsin and expected to bring cooler temperatures and snow into the area by Saturday. O dir-Syracuse National Weather Service Note: This forecast should be handed to players if a weather forecast is requested. THIS IS A DRILL O II-3 L
SECTION 7
~
James A. FitzPatrick Nuclear Power Plant 1993 Partial-Participation. Emergency Exercise December 14,.1993 r 6 r O III. PLANT RELEASE DATA O III-1
5 J
<wp .SECTION 7 ,
' )
' James A. FitzPatrick Nuclear Power Plant .
1993 Partial Participation Emergency Exercise December 14, 1993 Plant Release Datq (Note - Times are approximate) ' Summary: 0915 Power spike causes fuel damage , HRCRM, MSL and Offgas readings begin to increase ; 0925 MSL Isolation setpoint reached. When operators try scram reactor ATWAS occurs. . HRCRM continues to increase indicating fuel damage. 0945 ARMS begin to increase as leak out of drywell into the Reactor Building begins. , 0955 Continuing to End . Elevated release from stack begins and continues until end of drill. Stack flow will remain constant at 6000 cfm. , The release rate will increase linearly to approximately 6 Ci/s at 1200. The following pages provide data tables and graphical representations of the above data. 9 I III-2
December 14,1993 SECTION 7 Allr:odings in R/Hr High Range Containment Rod Mc'ilfor f'*% ? 4 li.m. .. .eb,. , , 37:m.00 9.:.16. i v> ~,.. f920A a.:o:,.9:J 2.. 7,,s ,,,;w.920 ?,.,. .s
,41. 92.1.,4 A ca., 9., ,:,3,,.2 ac.g.,.y !3 9,23,.g:. ,,
. y e .
oa mou , s. . 2 HRCRM 9.00 . 60.00 225.00 434.40 1371.00 2277.00 3150.00 u pswey , > m- w vm wi.:xuv.:n~-wpt ~yy., nvy. vyau.v.+w.p ~ m g.emany.gg nme a. +: 4 +
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. , , , , . ;w HRCRM 4001.00 4821.00 5615.00 6385.00 7109.00 7809.00 10890.00
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HRCRM 11720.00 12550.00 13380.00 14210.00 14635.33 15060.67 15486.00
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HRCRM 18888.67 19314.00 19739.33 20164.67 20590.00 21362.00 22134.00
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n -.,,,.; HRCRM 22906.00 23678.00 24450.00 25222.00 25994.00 26766 00 27538.00
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HRCRM 28310.00 29082.00 29854.00 30626.00 31398.00 32170.00 33640.67
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December 14,1993 SECTION 7 Allreadings in mR/Hr p Main Stoom Une Rod Monitor V
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a,,.w ..$: -x - . y.a; n .
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s.g.t.. , 17.4. .,.gg. , . 3.g,a__n_ g M8LRM 958.00 1071.00 1180.00 1405.00 1571.00 1819.00 1963.00
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December 141993 SECTION 7 All readings in mR/hr SJAE Rod Monitors b i 2: n_me.. s-,0.,,7.
... . :00 - ,+.,1._5
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~ ~ N- -
tow Range in CFM JAF Exercise Hbh Range in Mr/hr December 14,1993 SECDON 7 Stock Mon 5 ors 1 Trne 1129 11:10 11:11 11:12 11:13 11:14 11:15 11:16 11:17 11:18 11:19 1820 1121 1122 1]23 Re6eone Role CUsec 3.36 3.41 3.45 3 50 3.55 3.59 3 64 3 68 3.73 3.78 3 83 3 89 3 94 4DO 4.05
~
LO Range Emuent Monnors Stock CPS 3398653 3M4220 3489787 3535354 35tsues 3626487 3672054 3717621 3763181 3817913 3872638 3927363 3982088 4036813 4091538 i High Range Emuent Monitors Stock mR/hr(Itm+1fon) 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 Time 1124 1125 1124 1127 1128 1129 11:30 11:31 11:32 11:33 11:34 11:35 11:36 11:37 11:38 Release Rote ct/sec 4.10 4.16 4.21 4.27 4.32 4.38 4.43 4.48 4.54 4 59 4.65 4.70 4.75 4 81 - 4.86 LO Ronge Emuent Monitors Stock CPS 4146263 4200988 4255713 4310438 4365163 44190e8 4474613 4529338 4584063 4638788 4693513 4748238 480Z W1 4857ee8 4912413 High Range Emvent Monitors Stock mR/hr(llm+1 ton) 1 1 1 1 1 1 1 1 1 1 1 1 1 1 Time 11:39 11 40 11:41 11:42 11:43 11:44 11:45 11:44 11:47 11:44 11 49 1120 1121 11:52 11:53 H R*4eone Roto Cn/sec 4.92 4.97 5.03 5.08 5.13 5.19 5.24 5.30 5.35 5 41 5.46 5.51 5.57 H 5.62 - 5.68 LO Range Emuent Monitoes 03 Sleck CPS 4967138 5021863 5076588 5131313 5186038 5240763 5295488 5350213 5404938 5454663 5514388 5569113 5623838 5678563 5733288 High Range EWtuent Monitoes ' Stock mR/hr(1tm+1 ton) 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 Tbne 1124 11:55 11:66 1127 1128 1129 1220 1221 12D2 1223 1294 1296 -1296 1297 1228 Release Role CUsec 5.73 5.78 5.84 5.89 5.95 6.00 6.06 6.11 6.16 6.22 6.27 6.33 6.38 ' 6.43 6.49 LO Range Emuent Monitors Stock CPS 5788013 5842739 5897464 5952189 6006914 6061639 6116364 6171089 6225814 6280539 MMM4 6389989 6444714 6499439 6554164 High Range Emuent Monttore Stock mR/hr(Ilm+1 ton) 1 i 1 1 1 1 1 1 1 1 1 1 1 1 1
r3 SECTION 7 .Q , Jam'es A. FitzPatrick Nuclear Power Plant 1993 Partial Participation Emergency Exercise December 14, 1993 4 O IV. Oh' SITE DOSE RATE DATA AND MAPS O IV-1
SECTION 7 James A. FitzPatrick Nuclear Power Plant 1993 Partial Participation Emergency Exercise December 14, 1993 Onsite Dose Rate Data and Mans
~
There will be no dose rates measurable onsite as a result of the passing plume because we will be simulating a low level elevated release. There will be no dose rates measurable on contact with-- any building due to attenuation from the building structures. 9 O > O IV-2 ___________________u_____________________:
- 1. MAIN SECURITY Jf
- 2. SECURITY Ii
- 3. BUILDING & ' GROUNDS Ii
- 4. STACK / SAMPLE SHED b 5. CONTRACT SERVICES / WAREHOUSE '4
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- 6. DOSIMETRY II
- 7. RMS. HEL. NRC
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- 8. CONTRACT SERVICES
- 9. FAB SHOP ' f w ff II ,
- 10. ADMIN BLOG ANNEX -
q
- 11. CONDENSATE STORAGE TANKS .
'3
- 12. ARCHIVAL STORAGE ; e d, .f
- 13. RESPIRATOR MAINTENANCE IlllIIII IIIlllIII , .,,
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- 14. FUEL OIL STORAGE TANK 5 "l
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- 15. DRAFTING '
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- 17. SITE ENG DEPT ANNEX ,)j d 7, j g
- 18. REACTOR BLDG f j L
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20.SCREENWELL Ws \h 6 j lI}
- 21. HYDROGEN STORAGE iL gggg
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- 22. OXYGEN STORAGE I '
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- 23. FILTER BED TREATMENT BLOG, l ,jj i I
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- 25. CENTRAL PLANNING BLDG !lS ' '
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- 27. WAREHOUSE 2. UfCEATED '
- 28. WAREHOUSE 3. GAS BOTTLE STORAGE 'I '
- 29. PAINT SHOP D , 4 i<7,i 7 1 1 4
- 30. INTERIM RAD WASTE STORAGE IIIIUIIIIIIIIIIIIIIIIIIIIII
- 31. SEWAGE TREATMENT BLDG
- 32. SWITCH YARD
- 33. TRAINING / SIMULATOR
- 34. PROJECT SERVICES OFFICE
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- 34 ALL DOSES WILL BE "M 7EAD" A "2
FOR THE DURATION OF THIS A100 Availab!0 on EXERCISE Aperture Card Cy;()Li g oo3 K -
t SECTION 7 James A. FitzPatrick Nuclear Power Plant ' 1993 Partial Participation Emergency Exercise i December 14, 1993 6: O . V. OFFSITE DOSE RATE DATA AND MAPS i v t I: f O . m V-1 f = .
, SECTION 7
\~ James A. FitzPatrick Nuclear Power Plant 1993 Partial Participation Emergency _ Exercise December.14, 1993 Offsite Dose Rate Data and Mans Offsite dose rates will be detected no closer than 1 mile east of
- the plant beginning at approximately.1015-1030. The dose rates will increase to approximately 5 mR/hr by 1215. The release is primarily noble gas and a very small amount iodine.
The following pages are samples of expected MMRAS and IDAC displays, and tabular dose rate information. i O O V-2.
December 14.1993 SECTION 7 JAF Exercis3
~ All readings Closed Window Open window 2 times Closed Window All readings mR/hr MTM9*95EfR T=1020-10:15 K WIND DgTION TO 95 96 97 98l99 100 101 J l 102 :103 :104 :105 l
D 1.00 0 0 0 0 0 0 0 0 0 0 0 1 1.50 0 0 0 0 0 0 '0' O O O O S 2.00 0 0 0 0 0 Y 0 0 0 0 0 T 2.50 0 0 0 0 0 Y 0 0 0 0 0 A 3.00 0 0 0 0 0 Y 0 0 0 0 0 N 3.50 0 0 0 0 0 Y 0 0 0 0 0 C 4.00 0 0 0 0 0 0 0 0 0 0 0 E 4.50 0 0 0 0 0 Y 0 0 0 0 0 5.00 0 0 0 0 0 Y 0 0 0 0 0 D 5.50 0 0 0 0 0 Y 0 0 0 0 0 O 6.00 0 0 0 0 0 Y 0 0 0 0 0 W 6.50 0 0 0 0 0 Y 0 0 0 0- 0 N 7.00 0 0 0 0 0 Y 0 0 0 0 0 W 7.50 0 0 0 0 0 Y 0 0 0 0 0 1 8.00 0 0 0 0 0 Y 0 0 0 0 0 N 8.50 0 0 0 0 0 Y 0 0 0 0 0 D 9.00 0 0 0 0 0 Y 0 0 0 0 0 9.50 0 0 0 0 0 Y 0 0 0 0 0 10.00 0 0 0 0 0 0 0 0 0 0 0 M
~
= WIND DIRECTION TO~- & . . . . . .
,M T=10:15-10:30 95l96l97 98 99 100 101 '102 -103 1104 L105 D .1.00 0 0 0 0 0 0 0 0 0 0 0 1 1.50 0 0 0 0 0 0 0 0 0 0 0 S 2.00 0 0 0 0 0 Y 0 0 0 0 0 T 2.50 0 0 0 0 0 Y 0 0 0 0 0 A 3.00 0 0 0 0 0 0 0 0 0 0 0
- N 3.50 0 0 0 0 0 0 0 0 0 0- 0 C 4.00 0 0 0 0 0 Y 0 0 0 0 0 E 4.50 0 0 0 0 0 Y 0 0 0 0 0 5.00 0 0 0 0 0 0 0 0 0 0 0 D 5.50 0 0 0 0 0 Y 0 0 0 0 O O 6.00 0 0 0 0 0 Y 0 0 0 0 0 W 6.50 0 0 0 0 0 Y 0 0 0 0 0 ,
N 7.00 0 0 0 0 0 0 0 0 0 - 0 0 Y W 7.50 0 0 0 0 0 0 0 0 0 0 8.00 0 0 0 0 0 0 0 N 1 8.50 0 0 0 0 0 1 0 0 0 0 0 0 0 0 0 D 9.00 0 0 0 0 0 Y 0 0 0 0 0 9.50 0 0 0 0 0 Y 0 0 0 0 0 O ,0"O O O O O 6 Y 0 0 0 0 0 V-3 1. l
^
t
- December 14,1993 SECTION 7 JAF Ex rcise Allreadings CJosed Window Open window 2 tim'es Closed Window ' All readings mR/hr.
g . .. wp y g ;. F 'd { WIND DgTION TO l , T=10:30-10:45 95 96 97 98l+9 100 101 102 103!104 (105 ,
'D 1.00 0 0 0 0 1 1 1 0l0 0 0 3 1 1.50 0 0 0 0 1 1 1 0j0 0 0 L S 2.00 0 0 0 0 1 1 1 Ol0 0 0 T 2.50 0 0 0 0 1 1 1 0l0 0 0 -
A 3.00 0 0 0 0 1 1 1 0l0 0 0 ; N 3.50 0 0 0 0 0 0 0 0l0 0 0 C 4.00 0 0 0 0 0 0 0 0l0 0 0 E 42 0 0 0 0 0 0 0 0l0 0 0 ; 5.00 0 0 0 0 0 0 0 0l0 0 0
- D 5.50 0 0 0 0 0 0 0 0l0 0 0 O 6.00 0 0 0 0 0 0 0 0l0 0 0 W 6.50 0 0 0 0 0 0 0 0l0 0 0 N 7.00 0 0 0 0 0 0 0 0 l O' O O W 7.50 0 0 0 0 0 0 0 0lC 0 0 I 8.00 0 0 0 0 0 0 0 0l0 0 0.
N 8.50 0 0 0 0 0 0 0 0l0 0 0f - 7 D 9.00 0 0 0 0 0 0 0 0l0 0 ~ 0I 't 9.50 0 0 0 0 0 0 0 0l0 0 0 . 10.00 0 0 0 0 0 0 0 0!0 0 0 i O M WIND DIREChlON TO l T=10:45-11:00 95 96l 97 100 -101 102 - l103 104 ;105 l78l99 D 1.00 0 0 0 0 1 1 1 0 0 :0 0 ' i 1.50 0 0 0 0 1 1 1 0 0 0 0 S 2.00 0 0 0 0 1 1 1 0 0 0 0 l T 2.50 0 0 0 0 1 1 1 0 0 0 0 ; l A 3.00 0 0 0 0 1 1 1 0 0 0 0 [ j N 3.50 0 0 0 0 1 1 1 0 0 0 0 i C 4.00 0 0 0 0 1 1 1 0 0 0 0 l E 4.50 0 0 0 0 1 'l 1 0 0 0 0 : l 5.00 0 0 0 0 0 0 0 0 0 0 0 1 D 5.50 0 0 0 0 0 Y 0 0 0 0 0 -' O 6.00 0 0 0 0 0 0 0 0 0 0 0 [ W 6.50 , 0 0 0 0 0 0 0 0 0 0 0 '
. N 7.00 0 0 0 0 0 0 0 0 0 0 0 W 7.50 0 0 0 0 0 0 0 0 0 0 0 l l 8.00 0 0 0 0 0 0 0 0 0 0 0 N 8.50 0 0 0 0 0 0 0 0 0 0 0 -
D 9.00 0 0 0 0 0 0 0 0 0 0 0 ; 9.50 0 0 0 0 0 0 0 0 0 0 0 .
- O~ 10.00 0 0 0 0 0 0 0 0 0 0 0 ;
i V-4 f
Dacember 14,1993 SECTION 7 JAF Ecrcise All readings CJosed Window Open window 2 times Closed Window All readings mR/hr fili?!b$$#p , #'~ w - WIND DIRECTION TO T=11.00 - 11:15 95l96 .97~ 98l99 100 101 :102 103 :104 105 l D 1.00 0 0 1 1 1 2 1 1 l1 l0 0 1 1.50 0 0 1 1 1 12- 1 1 l1 l0 0 S 2.00 0 0 1 1 1 1 1 l1 l0 0 T 2.50 0 0 1 1 1 2 1 1 l1 l0 0 A 3.00 0 0 0 0 1 1 1 0l0l0 0 N 3.50 0 0 0 0 1 1 1 0l0l0 0 C 4.00 0 0 0 0 1 1 1 0l0l0 0 E 4.50- 0 0 0 0 1 1 1 0l0 0 0 5.00 0 0 0 0 1 1 1 0l0 0 0 D 5.50 0 0 0 0 1 1 1 0l0 0 0 O 6.00 0 0 0 0 1 1 1 0l0 0 0 W 6.50 0 0 0 0 0 1 0 0l0 0 0 N 7.00 0 0 0 0 0 0 0l0 0 W 7.50 0 0 10 0 0 0 0 0 0l0 0 0 , I 8.00 0 0 0 0 0 0 0 0l0 0 0 N 8.50 0 0 0 0 0 0 0 0l0 0 0 D 9.00 0 0 0 0 0 0 0 0l0 0 0 9.50 0 0 0 0 0 0 0 0l0 0 0 10.00 0 0 0 0 0 Y 0 0l0 0 0 : O a iraitBEGiS?im;FMitWW/frE WINU UlHtUllONIU T=11:15 -11:30 I 95l 96 97l 98. 99 100 101 :102 .303 :104 105 l D 1.00 1 1 1 1 2 3 2 1 1 1 1 i l 1.50 1 1 1 1 2 3 2 1 1 1 1 S 2.00 1 1 1 1 2 3 2 1 1 1 1 T 2.50 0 0 1 1 1 2 1 1 1 0 0 [ A 3.00 0 0 1 1 1 2 1 1 1 0 0 N 3.50 0 0 1 1 1 2 1 1 1 0 0 C 4.00 0 0 1 1 1 2 1 1 1 0 0 E 4.50 0 0 0 0 1 1 1 0 0 0 0 5.00 0 0 0 0 1 1 1 0 0 0 0 D 5.50 0 0 0 0 1 1 1 0 0 0 0 ! O 6.00 0 0 0 0 1 1 1 0 0 0 0 W 6.50- 0 0 0 0 1 1 1 0 0 0 0 N 7.00 0 0 0 0 0 0 0 0 0 0 0 W 7.50 0 0 0 0 0 0 0 0 0 0 0 1 8.00 0 0 0 0 0 0 0 0 0 0 0 l N 8.50 0 0 0 0 0 0' O O O O O D 9.00 0 0 0 0 0 T 0 0 0 0 0 9.50 0 0 0 0 0 0 0 0 0 0 0 10.00 0 0 0 0 0 Y 0 0 0 0 0 I V-5 e
i SECTION 7 James A.-FitzPatrick Huclear Power Plant 1993 Partial Participation Emergency Exercise December 14, 1993
************************** INPUT INFORMATION**********************
YOUR NAME: Drill Player TODAY'S DATE: 12-14-1993 CURRIJT TIME: 09:30:19 REACTOR NAME: FITZPATRICK NET ELECTRICAL OUTPUT: 821 CONTAINMENT TYPE: BWR-EITHER A TYPE I OR II EFFECTIVE STACK HEIGHT (M): 117.3 ELEVATED LEVEL WIND SPEED (M/SEC): 3.1 ELEVATED LEVEL WIND DIRECTION (TO): 74 STABILITY CLASS: C v INPUTS FOR GROSS RELEASE RATE: ; GROSS RELEASE RATE (CI/SEC): 7.00E+00 - IODINE, NOBLE GAS, AND FILTER EFFICIENCY INPUTS: PERCENTAGE IODINE: 0.00 ! PERCENTAGE NOBLE GAS: 100.00 IODINE TO NOBLE GAS RATIO: 0.00E+00 PERCENTAGE OF IODINE REMOVED BY FILTRATION: 100.00 TIME INTERVAL FROM REACTOR SHUTDOWN TO INITIATION OF RELEASE (HR): 0.50 TIME ESTIMATE FOR TOTAL DURATION OF RELEASE (HR): 8.00 AGE OF RELEASED MATERIAL: <1 DAY
- ELEVATED PLUME HAS TOUCHED DOWN
- BETWEEN 500.0 AND 968.0 METERS. ;
- SEE
SUMMARY
OUTPUT LISTED BELOW. * ' 3 () ************************** PLUME INFORMATION********************** V-6
l SECTION 7 James A. FitzPatrick Nuclear Power Plant 1993 Partial Participation Emergency Exercise December 14, 1993
- REVIEW THE FOLLOWING INPUT INFORMATION.* I YOUR NAME: Drill Player TODAY'S DATE: 12-14-1993 CURRENT TIME: 09:30:19 REACTOR NAME: FITZPATRICK NET ELECTRICAL OUTPUT: 821 CONTAINMENT TYPE: BWR-EITHER A TYPE I OR II EFFECTIVE STACK HEIGHT (M): 117.3 '
ELEVATED LEVEL WIND SPEED (M/SEC): 3.1 ELEVATED LEVEL WIND DIRECTION (TO): 74 i STABILITY CLASS: C INPUTS FOR GROSS RELEASE RATE: GROSS RELEASE RATE (CI/SEC) : 7.00E+00 , IODINE, NOBLE GAS, AND FILTER EFFICIENCY INPUTS: PERCENTAGE IODINE: 0.00 PERCENTAGE NOBLE GAS: 100.00 IODINE TO NOBLE GAS RATIO: 0.00E+00 PERCENTAGE OF IODINE REMOVED BY FILTRATION: 100.00 TIME INTERVAL FROM REACTOR SHUTDOWN TO INITIATION OF RELEASE (HR): 0.50 TIME ESTIMATE FOR TOTAL DURATION OF RELEASE (HR): 8.00 , AGE OF RELEASED MATERIAL: <1 DAY
- TEAR OFF AND REVIEW.
- O V-7 l
l SECTION 7 :
-James A. FitzPatrick Nuclear Power Plant / !
1993 Partial Participation Emergency Exercise December 14, 1993 l DISTANCE PLUME TRAVEL TIME CHI /Q. l (METERS) (MILES) (HOURS: MINUTES) VALUE 500.0 0.3 0 : 2.7 1.41E-07 ; 968.0 0.6 0': 5.2 2.79E-06 2016.0 1.2 0 : 10.7 2.66E-06 3225.0 2.0 0 : 17.2 1.68E-06 8064.0 5.0 0 : 42.9 3.77E-07 , 16129.0 10.0 1 : 25.9 8.90E-08
SUMMARY
CALCULATED DOSE RATES (REM /HR) r DISTANCE WHOLE BODY INFANT (METERS) (MILES) (REM /HR) THYROID 500.0 0.3 8.55E-03 0.00E+00 968.0 0.6 6.86E-03 0.00E+00 ! 2016.0 1.2 6.53E-03 0.00E+00 3225.0 2.0 4.13E-03 0.00E+00 I 8064.0 5.0 9.27E-04 0.00E+00 ; 16129.0 10.0 2.19E-04 0.00E+00 CALCULATED DOSE RATES (REMS) ' DISTANCE WHOLE BODY INFANT l' (METERS) (MILES) (REM /HR) THYROID 500.0 0.3 6.84E-02 0.00E+00 i 968.0 0.6 5.48E-02 0.00E+00 2016.0 1.2 5.22E-02 0.00E+00 3225.0 2.0 3.30E-02 0.00E+00 8064.0 5.0 7.41E-03 0.00E+00 16129.0 10.0 1.75E-03 0.00E+00 0 ********************* CALCULATIONS COMPLETED ******************** V-8
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SECTION 7 > James A. FitzPatrick Nuclear Power Plant. ! 1993 Partial Participation Emergency ~ Exercise December 14, 1993 e r O VI. IN-PLANT DOSE RATE DATA AND MAPS
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SECTION 7 3 . James A. FitzPatrick Nuclear Power Plant 1993 Partial Participation Emergency Exercise December 14, 1993 In-Plant Dose Rate Data and Maps In-plant dose rates will increase in the Reactor Building beginning at approximately 0945 and continue increasing until the exercise is terminated. The primary cause of the dose rates in the Reactor Building is immersion doses from drywell leakage. ,
.The drywell structure provides 1 x10 gamma attenuation (5 feet concrete) with some streaming near penetrations. '
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i SECTION 7 -i I James A. FitzPatrick Nuclear Power Plant j
.1993 Partial Participation Emergcucy Exercise l December 14, 1993
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SECTION 7 , James A. FitzPatrick Nuclear. Power Plant 1993 Partial Participation Emergency Exercise December 14, 1993 Area Radiation Monitors Tabular dose rates are provided for those areas near ARMS and-in contact with the drywell. Controllers should increase doses-slightly if near many penetrations. No significantly larger individual dose rates should be indicated on contact with or near , the drywell that could be misinterpreted as a singular source of the drywell leak. The leak is non-specific from many small spots. as opposed to one large crack or opening. This is necessary to prevent premature termination of the environmental release. All ARMS (except #12 Spent Fuel Area 369 East) will go offscale at 1045 mR/hr shortly after the drywell leak starts. General area dose rates are provided for those areas with offscale ARM values. Offscale ARM values are indicated in BOLD type.on the chart on the next page. O VII-2
O O O JAF Exercise Section 7 December 14,1993 ARM and Generat Area Dose Rote Summary . RX Building Dose Rates (ARMS) ARM Time # 07:00-09:30 9:30 9:34 9:35 9:36 9:37 9:38 9:39 9:40 9:41 9:42 9:43 9:44 9:45 9:46 9:47 Release Rote Cl/sec 0.00 0.00 0.02 0.06 0.08 0.11 0.15 0.18 0.20 0.21 0.22 0.23 0.24 0.25 0.26 0.27 Rx BLDG Gross Reading mr/hr os read 0 2 4 8 20 32 44 56 69 81 93 105 117 129 141 Rx Bldg 344 south 13 as read 0 1 1 2 5 9 12 15 18 22 25 28 31 35 38 Cleanup Precoot Tank Area 326 15 as read 0 1 1 3 7 11 15 20 24 28 32 37 41 45 49 Fuel Pool Pumos 326 17 as read 0 1 1 3 7 11 15 20 24 28 32 37 41 45 49 Contom Equ!p Storage Room 18 as read 0 0 1 1 3 6 8 10 12 14 16 18 20 22 24 Cleanup HX Ex Entrance 300 16 as read 0 1 2 3 8 13 18 22 27 32 37 41 46 51 56 Rx Cleanup Pump Area 300 19 as read 0 0 0 1 2 3 4 5 6 7 8 10 11 -12 13 < Rx H2O Sompte Area 300 20 as read 0 1 2 3 8 13 18 22 27 32 37 41 46 51 56 [ RBCLC Hx 300 21 as read 0 1 2 3 8 13 18 22 27 32 37 41 46 51 56 6 .Rx Bldg Access 272 23 as read 0 1 2 3 8 12 17 22 26 31 36 40 45 50 54 Rx Bldg TIP Machine 24 as read 0 0 0 1 2 3 5 6 7 8 10 11 12 13 15 East CRD HYD Control 272 25 as read 0 1 2 3 8 12 17 22 26 31 36 40 45 50 54 West CRD HYD Control 272 26 as read 0 1 2 3 8 12 17 22 26 31 36 40 45 50 54 Rx CRD Removal Hatch 272 28 as read 0 1 2 3 8 12 17 22 26 31 36 40 45 50 54 Equip Dr Sump 227 East Cresent 27 as read 0 1 1 2 5 9 12 15 18 22 25 28 31 35 38 Fl Dr Sump 227 West Cresent 29 as read 0 1 1 2 5 9 12 15 18 22 25 28 31 35 38 Rx Bldg 369 West refuel Floor Failed downscole 30 as read 0 2 3 6 15 24 33 42 52 61 70 79 88 97 106 New Fu61 Vault 369 North 14 as read 0 2 3 6 15 24 33 42 52 61 70 79 88 97 106 Spent Fuel Area 369 East 12 os read 0 2 3 6 15 24 33 42 52 61 70 79 88 97 106 Note: Values Greater than 1000 willindicate Offscale on ARMS (Except #12) and print BOLD in this table All Values in mR/hr
O O O JAF Exercise Section 7 December 14,1993 ARM and General Area Dose Rote Summary - RX Building Dose Rates (ARMS) ARM Time # 9:48 9:49 9:50 9:51 9:52 9:53 9:54 9:55 9:56 9:57 9:58 9:59 10:00 10:01 10:02 10:03 Refeose Rote Cl/sec 0.29 0.32 0.34 0.37 0.39 0.41 0.43 0.45 0.47 0.49 0.51 0.53 0.55 0.57 0.60 0.61 Rx BLDG Gross Reading mr/hr 85 137 189 240 292 344 395 447 499 550 831 922 1013 1104 1195 1286 Rx Bldg 344 south 13 23 37 51 64 78 92 106 120 134 148 223 247 272 296 320 345 Cleanup Precoot Tank Area 326 15 30 48 66 84 102 120 138 156 174 192 290 321 353 385 417 448 Fuel Pool Pumps 326 17 30 48 66 84 102 120 138 156 1 74 192 290 385 321 353 417 448 Contam Equip Storage Room 18 15 24 33 42 51 59 68 77 86 95 144 160 175 191 207 223 Cleanup HX Ex Entrance 300 16 34 54 75 95 115 136 156 177 197 217 329 365 436 401 472 508 Rx Cleonup Pump Area 300 19 8 13 17 22 27 31 36 41 46 50 76 85 93 101 110 118 <: Rx H2O Sompte Area 300 20 34 54 75 95 115 136 156 177 197 217 329 365 401 436 472 508 [ RBCLC Hx 300 21 34 54 75 95 115 136 156 177 197 217 329 365 401 436 472 508 1 .Rx B!dg Access 272 23 33 53 73 93 113 133 153 173 192 212 321 356 391 426 462 497 Rx Bldg TIP Machine 24 9 14 20 25 30 36 41 46 52 57 86 95 105 114 124 133 East CRD HYD Control 272 25 33 53 73 93 113 133 153 173 192 212 321 356 391 426 462 497 West CRD HYD Control 272 26 33 53 73 93 113 133 153 173 192 212 321 356 391 426 462 497 Rx CRD Removal Hatch 272 28 33 - 53 73 93 113 133 153 173 192 212 321 356 391 426 462 497 Equip Dr Sump 227 East Cresent 27 23 37 51 64 78 92 106 120 134 148 223 247 296 272 320 345 FI Dr Sump 227 West Cresent 29 23 37 51 64 78 92 106 120 134 148 223 247 272 296 320 345 Rx Bldg 369 West refuel Floor Folled downscole 30 64 103 142 181 219 258 297 336 375 414 625 693 762 830 899 967 New Fuel Vault 369 North 14 64 103 142 181 219 258 297 336 375 414 625 693 762 830 899 967 Spent Fuel Area 369 East 12 64 103 142 181 219 258 297 336 375 414 625 693 762 830 899 967 Note: Values Greater than 1000 will Indicate Offscole on ARMS (Except #12) and print BOLD in this table All Values in mR/hr
O O O JAF Exercise Section 7 December 14,1993 ARM and General Area Dose Rote Summary
- RX Building Dose Rates (ARMS) ARM Time # 10:04 10:05 10:06 10:07 10:08 10:09 10:10 10:11 10:12 10:13 10:14 10:15 10:16 Release Rote Cl/sec 0.63 0.65 0.67 0.69 0.71 0.73 0.74 0.76 0.78 0.80 0.82 0.84 0.86 Rx BLOG Gross Reading mr/hr 1377 1468 1559 1651 1742 1833 1924 2015 2106 2163 2272 2381 2490 Rx Bldg 344 south 13 369 394 418 442 467 491 516 540 565 580 609 638 668 Cleanup Precoat Tonk Area 326 15 480 512 543 575 607 639 670 702 734 754 792 830 868 Fuel Pool Pumps 326 17 480 512 543 575 607 639 670 702 734 754 792 830 868 Contom Equip Storage Room 18 238 254 270 286 301 317 333 349 364 374 393 412 431 Cleanup HX Ex Entrance 300 16 544 580 616 652 688 724 760 796 832 855 898 941 984 Rx Cleanup Pump Area 300 19 126 135 143 1 51 160 168 176 185 193 198 208 218 228
< Rx H2O Sompie Area 300 20 544 580 616 652 688 724 760 796 832 855 898 941 984 [ RBCLC Hx 300 21 544 580 616 652 688 724 760 796 832 855 898 941 984 4 Rx Bldg Access 272 23 532 567 602 637 672 708 743 778 813 835 877 919 961 Rx Bldg TIP Machine 24 143 152 161 1 71 180 190 199 209 218 224 235 246 258 East CRD HYD Control 272 25 532 567 602 637 672 708 743 778 813 835 877 919 961 West CRD HYD Control 272 26 532 567 602 637 672 708 743 778 813 835 877 919 961 Rx CRD Removal Hatch 272 28 532 567 602 637 672 708 743 778 813 835 877 919 961 Equip Dr Sump 227 East Cresent 27 369 394 418 442 467 491 516 540 565 580 609 638 668 FI Dr Sump 227 West Cresent 29 369 394 418 442 467 491 516 540 565 580 609 638 668 Rx Bldg 369 West refuel Floor Folled downscole 30 1036 1104 1173 1241 1309 1378 1446 1515 1583 1626 1708 1790 1872 New Fuel Youtt 369 North 14 1036 1104 1173 1241 1309 1378 1446 1515 1583 1626 1708 1790 1872 Spent Fuel Area 369 East 12 1036 1104 1173 1241 1309 1378 1446 1515 1583 1626 1708 1790 1872 Note: Values Greater than 1000 willindicate Offscale on ARMS (Except #12) and print BOLD in this tobie All Volues in mR/hr
=-________---________---.___m. _ _ _ _ _ _ . _ _ _ _ _ . . - _ _ . - _ . . _ _ . . - _ . _ _ _ _ _
O O O i l JAF Exercise Section 7 December 14,1993 i ARM and General Area
- Dose Rote Summary .
l RX Bu!! ding Dose Rates (ARMS) ARM Time # 10:17 10:18 10:19 10:20 10:21 10:22 10:23 10:24 10:25 10:26 10:27 10:28 10 29 Reloose Rote Cl/sec 0.87 0.92 0.96 1.00 1.05 1.09 1.13 1.17 1.22 1.26 1.30 1.35 1.39 l Rx BLDG Gross Reading mr/hr 2599 2708 2817 2926 3035 3144 3253 3362 3471 3580 3689 3743 3881 1 Rx Bldg 344 south 13 697 726 755 784 814 843 872 901 930 960 989 1003 1040 Cleanup PrecoatTonk Aroo 326 15 906 943 981 1019 1057 1095 1133 1171 1209 1247 1285 1304 1352 Fuel Pool Pumps 326 17 906 943 981 1019 1057 1095 1133 1171 1209 1247 1285 1304 1352 l Contam Equip Storage Room 18 450 468 487 506 525 544 563 582 600 619 638 648 671 l Cleanup HX Ex Entrance 300 16 1027 1070 1113 1156 1199 1243 1286 1329 1372 1415 1458 1479 1534 [ Rx Cleanup Pump Area 300 19 238 248 258 268 278 288 298 308 318 328 338 343 356
<: Rx H2O Sompte Area 300 20 1027 1070 1113 1156 1199 1243 1286 1329 1372 1415 1458 1479 1534
[ RBCLC Hx 300 21 1027 1070 1113 1156 1199 1243 1286 1329 1372 1415 1458 1479 1534 i Rx Bldg Access 272 23 1003 1045 1088 1130 1172 1214 1256 1298 1340 1382 1424 1445 1498 Rx Bldg TIP Machine 24 269 280 292 303 314 325 337 348 359 371 382 387 402 East CRD HYD Control 272 25 1003 1045 1088 1130 1172 1214 1256 1298 1340 1382 1424 1445 1498 West CRD HYD Control 272 26 1003 1045 1088 1130 1172 1214 1256 1298 1340 1382 1424 1445 1498 Rx CRD Removal Hotch 272 28 1003 1045 1088 1130 1172 1214 1256 1298 1340 1382 1424 1445 1498 Equip Dr Sump 227 East Cresent 27 697 726 755 784 814 843 872 901 930 960 989 1003 1040 F1 Dr Sump 227 West Crosent 29 697 726 755 784 814 843 872 901 930 960 989 1003 1040 Rx Bldg 369 West refuel Floor Folled downscole 30 1954 2036 2118 2200 2282 2364 2446 2528 2609 2691 2773 2814 2918 New Fuel Voult 369 North 14 1954 2036 2118 2200 2282 2364 2446 2528 2609 2691 2773 2814 2918 Spent Fuel Area 369 East 12 1954 2036 2118 2200 2282 2364 2446 2528 2609 2691 2773 2814 2918 Note: Values Greater than 1000 willIndicate Offscale on ARMS (Except #12) and print BOLD in this table All Votues in mR/hr
O O O JAF Exercise Section 7 December 14,1993 ARM and General Area Dose Rote Summary - RX Building Dose Rates (ARMS) ARM Time # 10:30 10:31 10:32 10:33 10.34 10:35 10:36 10:37 10:38 10:39 10:40 10:41 10:42 Release Rote Cl/sec 1.43 1.47 1.52 1.57 1.63 1.68 1.73 1.79 1.84 1.90 1.95 2.01 2.06 Rx BLDG Gross Reading mr/hr 4019 4157 4295 4433 4572 4710 4848 4986 5124 5262 5401 5539 5677 Rx Bldg 344 south 13 1077 1115 1152 1189 1226 1263 1300 1337 1374 1411 1448 1485 1522 Cleanup Precoat Tonk Area 326 15 1400 1445 1497 1545 1593 1641 1689 1737 1785 1834 1882 1930 1978 Fuel Pool Pumps 326 17 1400 1448 1497 1545 1593 1641 1689 1737 1785 1834 1882 1930 1978 Contom Equip Storage Room 18 695 719 743 767 791 815 839 863 887 910 934 958 982 Cleanup HX Ex Entrance 300 16 1589 1643 1698 1752 1807 1862 1916 1971 2025 2080 2135 2189 2244 Rx Cleanup Pump Area 300 19 368 381 394 406 419 432 444 457 470 482 495 508 520
<: Rx H2O Sompte Area 300 20 1589 1643 1698 1752 1807 1862 1916 1971 2025 2080 2135 2189 2244
[ RBCLC Hx 300 21 1589 1643 1698 1752 1807 1862 1916 1971 2025 2080 2135 2189 2244 l
$ .Rx Bldg Access 272 23 1552 1605 1658 1712 1765 1818 1872 1925 1978 2032 2085 2139 2192 Rx Bldg TIP Machine 24 416 430 445 459 473 488 502 516 530 545 559 573 588 East CRD HYD Control 272 25 1552 1605 1658 1712 1765 1818 1872 1925 1978 2032 2085 2139 2192 West CRD HYD Control 272 26 1552 1605 1658 1712 1765 1818 1872 1925 1978 2032 2085 2139 2192 Rx CRD Removal Hatch 272 28 1552 1605 1658 1712 1765 1818 1872 1925 1978 2032 2085 2139 2192 Equip Dr Sump 227 East Cresent 27 1077 1115 1152 1189 1226 1263 1300 1337 1374 1411 1448 1485 1522 FI Dr Sump 227 West Cresent 29 1077 1115 1152 1189 1226 1263 1300 1337 1374 1411 1448 1485 1522 Rx Bidg 369 West refuel Floor Folled downscole 30 3022 3126 3230 3333 3437 3541 3645 3749 3853 3957 4061 4165 4268 l New Fuel Yoult 369 North 14 3022 3126 3230 3333 3437 3541 3645 3749 3853 3957 4061 4165 4268 Spent Fuel Area 369 East 12 3022 3126 3230 3333 3437 3541 3645 3749 3853 3957 4061 4165 4268 l
l Note: Values Greater than 1000 willindicate Offscale on ARMS (Except #12) and print BOLD in this table All Values in mR/hr
O O O JAF Exercise Section 7 December 14,1993 ARM and Genero! Area Dose Rote Summary . RX Building Dose Rotes (ARMS) ARM Time # 10:43 10:44 10:45 10:46 10:47 10:48 10:49 10:50 10:51 10:52 10:53 10:54 10:55 Release Rote Cl/sec 2.11 2.17 2.22 2.28 2.33 2.38 2.43 2.48 2.52 2.57 2.62 2.67 2.71 Rx BLDG Gross Reading mr/hr 5777 5935 6094 6252 6411 6569 6728 6887 7045 7204 7362 7521 7679 Rx Bldg 344 south 13 1549 1591 1634 1676 1719 1761 1804 1846 1889 1931 1974 2016 2059 Cleanup Precoot Tonk Area 326 15 2013 2068 2123 2179 2234 2289 2344 2400 2455 2510 2565 2620 2676 Fuel Pool Pumps 326 17 2013 2068 2123 2179 2234 2289 2344 2400 2455 2510 2565 2620 2676 Contam Equip Storage Room 18 999 1027 1054 1082 1109 1137 1164 1191 1219 1246 1274 1301 1329 Cleanup HX Ex Entrance 300 16 2283 2346 2409 2471 2534 2597 2659 2722 2785 2847 2910 2973 3035 Rx Cleanup Pump Area 300 19 529 544 559 573 588 602 617 631 646 660 675 689 704
< Rx H2O Sompte Area 300 20 2283 2346 2409 2471 2534 2597 2659 2722 2785 2847 2910 2973 3035
[ RBCLC Hx 300 21 2283 2346 2409 2471 2534 2597 2659 2722 2785 2847 2910 2973 3035
$ Rx Bldg Access 272 23 2230 2292 2353 2414 2475 2536 2598 2659 2720 2781 2843 2904 2965 Rr. Bldg TIP Machine 24 598 614 631 6C 664 680 696 713 729 746 762 778 795 East CRD HYD Control 272 25 2230 2292 2353 2414 E 475 2536 2598 2659 2720 2781 2843 2904 2965 West CRD HYD Control 272 26 2230 2292 2353 2414 24i5 2536 2598 2659 2720 2781 2843 2904 2965 Rx CRD Removal Hatch 272 28 2230 2292 2353 2414 2474. 2536 2598 2659 2720 2781 2843 2904 2965 Equip Dr Sump 227 East Cresent 27 1549 1591 1634 1676 1719 1761 1804 1846 1889 1931 1974 2016 2059 FI Dr Sump 227 West Cresent 29 1549 1591 1634 1676 1719 1761 1804 1846 1889 1931 1974 2016 2059 Rx Bldg 369 West refuel Floor Folled downscole 30 4343 4463 4582 4701 4820 4939 5059 5178 5297 5416 5535 5655 5774 New Fuel Yoult 369 North 14 4343 4463 4582 4701 4820 4939 5059 5178 5297 5416 5535 5655 5774 Spent Fuel Areo 369 East 12 4343 4463 4582 4701 4820 4939 5059 5178 5297 5416 5535 5655 5774 Note: Values Greater than 1000 will indicate Offscale on ARMS (Except #12) and print BOLD in this table All Volues in mR/hr
O . O O JAF Exercise Section 7 December 14,1993 ARM and General Area Dose Rote Summary . RX Bullding Dose Rates (ARMS) ARM Time # 10:56 10:57 10:58 10:59 11:00 11 01 11:02 11:03 11:04 11:05 11:06 11:07 11 08 Release Rcte Cl/sec 2.76 2.81 2.86 2.91 2.95 3.00 3.05 3.09 3.14 3.18 3.23 3.27 3.32 Rx BLDG Gross Reading mr/hr 7838 7996 8122 8298 8474 8650 8826 9003 9179 9355 9531 9707 9884 Rx Bldg 344 south 13 2101 2144 2177 2225 2272 2319 2366 2414 2461 2508 2555 2603 2650 Cleanup Precoot Tonk Area 326 15 2731 2786 2830 2891 2953 3014 3075 3137 3198 3260 3321 3382 3444 Fuel Pool Pumps 326 17 2731 2786 2830 2891 2953 3014 3075 3137 3198 3260 3321 3382 3444 Contam Equip Storage Room 18 1356 1383 1405 1436 1466 1497 1527 1558 1588 1619 1649 1679 1710 Cleanup HX Ex Entrance 300 16 3098 3161 3210 3280 3349 3419 3489 3558 3628 3698 3767 3837 3907 l Rx Cloonup Pump Area 300 19 718 733 744 761 777 793 809 825 841 857 874 890 906 l <: Rx H2O Sompto Area 300 20 3098 3161 3210 3280 3349 3419 3489 3558 3628 3698 3767 3837 3907 , [ RBCLC Hx 300 21 3098 3161 3210 3280 3349 3419 3489 3558 3628 3698 3767 3837 3907 4 Rx Bldg Access 272 23 3026 3087 3136 3204 3272 3340 3408 3476 3544 3612 3680 3748 3816 Rx Bldg TIP Machine 24 811 828 841 859 877 895 914 932 950 968 987 1005 1023 ( East CRD HYD Control 272 25 3026 3087 3136 3204 3272 3340 3408 3476 3544 3612 3680 3748 3816 , West CRD HYD Control 272 26 3026 3087 3136 3204 3272 3340 3408 3476 3544 3612 3680 3748 3816 l Rx CRD Removal Hatch 272 28 3026 3087 3136 3204 3272 3340 3408 3476 3544 3612 3680 3748 3816 l Equip Dr Sump 227 East Cresent 27 2101 2144 2177 2225 2272 2319 2366 2414 2461 2508 2555 2603 2650 FI Dr Sump 227 West Cresent 29 2101 2144 2177 2225 2272 2319 2366 2414 2461 2508 2555 2603 2650 Rx Bldg 369 West refuel Floor Folled downscole 30 5893 6012 6106 6239 6371 6504 6636 6769 6901 7034 7166 7299 7431 New Fuel Yoult 369 North 14 5893 6012 6106 6239 6371 6504 6636 6769 6901 7034 7166 7299 7431 Spent Fuel Area 369 East 12 5893 6012 6106 6239 6371 6504 6636 6769 6901 7034 7166 7299 7431 l l l Note: Values Greater than 1000 willindicate Offscale on ARMS (Except #12) and print BOLD in this table Ali Values in mR/hr
O O O JAF Exercise Section 7 December 14,1993 ARM and General Area Dose Rote Summary . RX Building Dose Rotes (ARMS) l ARM Time # 11:09 11:10 11:11 11:12 11:13 11:14 11:15 11:16 11:17 11:18 11:19 Release Rote Cl/sec 3.36 3.41 3.45 3.50 3.55 3.59 3.64 3.68 3.73 3.78 3.83 Rx BLDG Gross Reading mr/hr 10060 10236 10412 10589 10737 10928 11119 11310 11500 11691 11882 Rx Bldg 344 south 13 2697 2744 2792 2839 2879 2930 2981 3032 3083 3134 3185 Cleanup Precoat Tonk Aroo 326 15 3505 3567 3628 3689 3741 3808 3874 3941 4007 4074 4140 Fuel Pool Pumps 326 17 350.5 3567 3628 3689 3741 3808 3874 3941 4007 4074 4140 Contam Equip Storage Room 18 1740 1771 1801 1832 1858 1891 1924 1957 1990 2023 2056 Cloonup HX Ex Entrance 300 16 3976 4046 4116 4185 4244 4319 4395 4470 4546 4621 4696 Rx Cleanup Pump Area 300 19 922 938 954 971 984 1002 1019 1037 1054 1072 1089
$ Rx H2O Sample Aroo 300 20 3976 4046 4116 4185 4244 4319 4395 4470 4546 4621 4696 H RBCLC Hx 300 21 3976 4046 4116 4185 4244 4319 4395 4470 4546 4621 4696 s Rx Bldg Access 272 23 3884 3952 4020 4088 4146 4219 4293 4367 4440 4514 4588
'Rx Bldg TIP Machine 24 1041 1060) 1078 1096 1111 1131 1151 1171 1190 1210 1230 East CRD HYD Control 272 25 3884 3952 4020 4088 4146 4219 4293 4367 4440 4514 4588 West CRD HYD Control 272 26 3884 3952 4020 4088 4146 4219 4293 4367 4440 4514 4588 Rx CRD Removal Hotch 272 28 3884 3952 4020 4088 4146 4219 4293 4367 4440 4514 4588 Equip Dr Sump 227 East Cresent 27 2697 2744 2792 2839 2879 2930 2981 3032 3083 3134 3185 Fi Dr Sump 227 West Cresent 29 2697 2744 2792 2839 2879 2930 2981 3032 3083 3134 3185 Rx Bldg 369 West refuel Floor Folled downscolo 30 7564 7696 7829 7961 8073 8217 8360 8503 8647 8790 8934 New Fuel Youl' 369 North 14 7564 7696 7829 7961 8073 8217 8360 8503 8647 8790 8934 l Spent Fuel Area 369 East 12 7564 7696 7829 7961 8073 8217 8360 8503 8647 8790 8934 i
l i Note: Values Greater than 1000 willindicate Offscale on ARMS (Except #12) and print BOLD in this table All Values in mR/hr
O O O JAF Exercise Section 7 December 14,1993 ARM and General Area Dose Rote Summary . RX Building Dose Rates (ARMS) ARM Time # 11:20 11:21 11:22 11:23 11:24 11:25 11:26 11:27 11:28 11:29 11:30 Release Rote Cl/sec 3.89 3.94 4.00 4.05 4.10 4.16 4.21 4.27 4.32 4.38 4.43 Rx BLDG Gross Reading mr/hr 12073 12263 12454 12645 12836 13026 13217 13408 13580 13780 13981 Rx Bldg 344 south 13 3237 3288 3339 3390 3441 3492 3543 3595 3641 3694 3748 C eonup Precoot Tonk Area 326 15 4206 4273 4339 4406 4472 4539 4605 4672 4732 4802 4871 Fuel Pool Pumps 326 17 4206 4273 4339 4406 4472 4539 4605 4672 4732 4802 4871 Contom Equip Storage Room 18 2089 2122 2155 2188 2221 2254 2287 2320 2349 2384 2419 Cleonup HX Ex Entrance 300 16 4772 4847 4923 4998 5073 5149 5224 5300 5367 5447 5526 Rx Cleanup Pump Area 300 19 1107 1124 1142 1159 1176 1194 1211 1229 1245 1263 1281
$ .Rx H2O Sompte Area 300 20 4772 4847 4923 4998 5073 5149 5224 5300 5367 5447 5526 H RBCLC Hx 300 21 4772 4847 4923 4998 5073 5149 5224 5300 5367 5447 5526 h
Rx Bldg Access 272 23 4661 4735 4809 4882 4956 5029 5103 5177 5243 5321 5398 Rx Bldg TIP Machine 24 1250 1269 1289 1309 1329 1348 1368 1388 1406 1426 1447 East CRD HYD Control 272 25 4661 4735 4809 4882 4956 5029 5103 5177 5243 5321 5398 West CRD HYD Control 272 26 4661 4735 4809 4882 4956 5029 51G3 5177 5243 5321 5398 Rx CRD Removal Hotch 272 28 4661 4735 4809 4882 4956 5029 5103 5177 5243 5321 5398 Equip Dr Sump 227 East Cresent 27 3237 3288 3339 3390 3441 3492 3543 3595 3641 3694 3748 Fl Dr Sump 227 West Cresent 29 3237 3288 3339 3390 3441 3492 3543 3595 3641 3694 3748 Rx Bldg 369 West refuel Floor Failed downscole 30 9077 9221 9364 9507 9651 9794 9938 10081 10210 10361 10512 New Fuel Yourt 369 North 14 9077 9221 9364 9507 9651 9794 9938 10081 10210 10361 10512 Spent Fuel Area 369 East 12 9077 9221 9364 9507 9651 9794 9938 10081 10210 10361 10512 Note: Values Greater than 1000 willindicate Offscale on ARMS (Except #12) and print BOLD in this table All Values in mR/hr
- * - * + - - = - - -
w -aw3gw gg-r% %# - - - y ei
, - ~.
SECTION 7 ;,
. James A. FitzPatrick Nuclear Power Plant 1993 Partial Participation Emergency Exercise December 14, 1993 t
.1 i
i 1 i 1 VIII. IN-PLANT AIR SAMPLE DATA j (Representative air sample data is provided for approximately 1045) i t i e i O 1 VIII-1 t
SECTION 7 James A. FitzPatrick Nuclear Power Plant () 1993 Partial Participation Emergency Exercise December 14, 1993 12/14/93 EXERCISE DATA Page 1 GDR/HP NUCLIDE ANALYSIS
SUMMARY
Version 2.1 New York Power Authority J. A. FitzPatrick Nuclear Plant All air samples taken everywhere EXCEPT the REACTOR BUILDING are normal. All air samples taken in or around the Reactor Building after 10:00 will read as follows: f i i VIII-2
SECTION 7 () 12/14/93 10:00 EXERCISE DATA Page 1 GDR/HP NUCLIDE ANALYSIS
SUMMARY
Version 2.1 New York Power Authority J. A. FitzPatrick Nuclear Plant Air Sample Test Spectrum Reported by: CHEMISTRY File ID: EXERCISE December 14, 1993 Library File: . . . . . .PLALIB. LIB (IN PLANT Air Sample Library ) MPC/LLD File: . . . . . .PLALLD.MPC (IN PLANT Air Sample. MPC/LLD's ) Detector #: 4 , Efficiency File: . . . ASPCS1D04.EFF (Glass Fiber'Filt./F&J Charcoal Cart.) Eff.=1/( 3.54E-02*En^-2.34E+00 + 1.57E+02*En^ 1.02E+00) 05/17/92 08:37 (Where En = Energy in MeV)
===================------- -- - ====== ------------- -- = = -
MEASURED or MDA CONCENTRATION Energy Concentration Less-Than Peaks LLD LLD Nuclide Group (kev) (uCi/cc ) Level Conc Found REQUIRED MET?
=================== -- ==_____ --- -
__________--- _ == ZN-65 1115.16 < 7.16E-10 MDA 6.25E-11 0 of 1 0.0E+00 Yes ( CE-144 133.54 < 2.46E-10 MDA 9.26E-11 0 of 1 5.0E-11 NO TC-99M 140.51 < 3.02E-11 MDA 1.18E-11 0 of 1 0.0E+00 Yes CE-141 145.44 < 4.21E-11 MDA 1.66E-11 0 of 1 5.0E-11 Yes CR-51 320.08 < 4.40E-10 MDA 1.59E-10 0 of 1 5.0E-11 NO BR-84 880.00 < 4.79E-10 MDA 1.23E-11 0 of 4 6.0E-11 Yes I-130 418.00 < 1.24E-11 MDA 2.20E-10 0 of 5 5.1E-10 NO I-131 364.48 9.01E-5 +-6.23E-06 -- 4 of 4 ------- --- HF-181 482.30 < 8.45E-11 MDA 3.00E-11 0 of 2 0.0E+00 Yes . 1-132 772.60 2.12E-7 +-1.23E-08 -- 5 of 6 0.0E+00 Yes I-133 529.87 3.08E-8 +-1.65E-9 -- 4 of 4 0.0E+00 Yes I-134 884.32 6.05E-7 +-2.75E-8 -- 11 of 11 5.2E-11 yes BA-140 537.32 < 1.76E-10 MDA 5.55E-11 0 of 5 0.0E+00 Yes ; SB-124 602.71 < 6.35E-11 MDA 5.91E-11 0 of 5 0.0E+00 Yes 1 CS-137 661.65 < 6.02E-11 MDA 5.46E-11 0 of 1 1.0E-11 NO , MO-99 739.58 < 5.29E-10 MDA 1.25E-10 0 of 4 5.0E-11 NO ZR-95 756.72 < 1.24E-10 MDA 1.01E-10 0 of 1 0.0E+00 Yes NB-95 765.79 < 2.32E-11 MDA 7.43E-11 0 of 1 0.0E+00 Yes ! CS-134 795.85 < 1.08E-10 MDA 2.82E-11 0 of 7 1.0E-11 NO CO-58 810.76 < 1.10E-10 MDA 3.70E-11 0 of 3 1.0E-11 NO MN-54 834.83 < 1.49E-10 MDA 5.35E-11 0 of 1 1.0E-11 NO , FE-59 1099.22 < 5.93E-11 MDA 5.79E-11 0 of 4 1.0E-11 NO 1-335 1260.41 9.12E-8 +-3.01E-9 -- 6 of 6 1.0E-11 NO CO-60 1332.49 < 1.46E-10 MDA 1.58E-10 0 of 2 1.0E-11 NO LA-140 1596.49 < 5.23E-11 MDA 5.10E-11 0 of 9 0.0E+00 Yes O f0TAL MEAS. ACT. : 8.46E-04 +- 2.33E-06 uCi/cc
================================================================----- ---=====
VIII-3 i
SECTION 7 James A. FitzPatrick Nuclear Power Plant () 1993 Partial Participation Emergency Exercise-December 14, 1993 12/14/93 10:00 EXERCISE DATA
***********************************************************************ge Pa 2 MPC CHECK MPC FILE: PLALLD.MPC I
Nuclide uCi/cc MPC % MPC I-131 9.01E-09 1.00E-10 9.01E+03 TOTAL: 9.48E-7 4.30E+04
==============__________ --------m======= ---== z__ __=_- = t MPCS for AIR SAMPLES !
AIR SAMP #: EXERCISE DATA LOCATION: Reactor Building RWP #: 93-XXXX
======================---= ------------- _ ___- -- ==========
-Sampling On: 12/14/93 Sampling Off: 12/14/93 rotection Factors: Particulates: 1.000 Iodines: 1.000 Respirator: None I
% MPC % MPC % MPC Eff. % MPC Eff. % MPC Eff. % MPC -
IODINES OTHERS TOTAL IODINES OTHERS TOTAL 4.30E+04 .000 4.30E+04 4.30E+04 .000 4.30E+04
% MPC TOTAL: 4.30E+04 h
O VIII-4
SECTION 7 James A. FitzPatrick Nuclear Power Plant '( ) 1993 Partial Participation Emergency Exercise December 14, 1993 12/14/93 1030-END EXERCISE DATA Page 1 GDR/HP NUCLIDE ANALYSIS
SUMMARY
Version 2.1 New York Power Authority J. A. FitzPatrick Nuclear Plant
****************************************************************************** i Mock In-Plant Gas Analysis Reported by: CHEMISTRY File ID: EXERCISE 1993 r Library File: . . . . . .GASLIB. LIB (Noble Gases Library )
MPC/LLD File: . . . . . .IPGLLD.MPC (In Plant Noble Gases ) Detector #: 3 Efficiency File: . . . 4 LGMSOD03. EFF (4 L Gas Marinelli (Foam Filled) ) Ef f. =1/ ( 3.17E-02*En^-2.97E+00 + 3.89E+02*En^ 9.69E-01) 03/29/92 14:14 (Where En = Energy in MeV)
~w=============______=======----- -========__ _- -=-----
MEASURED or MDA CONCENTRATION Energy Concentration Less-Than Peaks LLD LLD Nuclide Group (kev)
========,_.__,,__________________________________
(uCi/cc ) Level Conc Found REQUIRED MET? XE-133 80.97 5.51E-02 +- 3.25E-06 ---- 1 of 1 ------- --- XE-137 455.00 < 2.25E-06 MDA 2.65E-10 0 of 4 0.0E+00 Yes XE-131M 165.75 3.75E-03 MDA 3.00E-11 0 of 2 0.0E+00 Yes KR-85 514.10 3.84E-02 +- 6.05E-07 ---- 1 of 1 ------- --- KR-88 196.32 < 6.32E-05 MDA 3.25E-11 0 of 1 3.2E-11 No ; XE-133M 233.21 1.07E-05 +- 7.22E-06 ---- 1 of 1 ------- --- XE-135 249.79 < 1.87E-04 MDA ----- 1 of 1 ------- --- XE-138 258.31 < 5.31E-04 MDA ----- 1 of 5 ------- --- KR-87 402.58 < 2.70E-04 MDA ----- 1 of 4 ------- --- XE-135M 526.56 < 1.94E-04 MDA ----- 1 of 1 ------- --- KR-85M 149.50 < 3.57E-04 +- 5.03E-07 ----- 1 of 1 ------- --- - 305.00 I.D.Only TOTAL MEAS. ACT. : 9.73E-02 +- 1.09E-05 uCi/cc VIII-5
SECTION 7 James A. FitzPatrick Nuclear Power Plant () 1993 Partial Participation Emergency Exercise December 14, 1993 12/14/93 1030 EXERCISE DATA
***********************************************************************ge Pa 2 MPC CHECK MPC FILE: IPGLLD.MPC Nuclide uCi/cc MPC % MPC '
XE-133 5.51E-02 1.E-05 5.51E+05 XE-131M 3.75E-03 2.E-05 1.88E+04 KR-85 3.84E-02 1.E-05 3.84E+05 XE-133M 1.07E-05 1.E-05 1.07E+04 TOTAL: 9.73E-02 9.65E+05 j-~ =============================------ == ----- ======~---~~=________==------= \ MPCS for AIR SAMPLES AIR SAMP #: EXERCISE DATA LOCATION: Reactor Building RWP #: 93-XXXX
=================____-_m=============______==========----- =______==--- ======
Sampling On: 12/14/93 Sampling Off: 12/14/93 Protection Factors: Particulates: 1.000 Iodines: 1.000 Respirator: None
% MPC % MPC % MPC Eff. % MPC Eff. % MPC Eff. % MPC IODINES OTHERS TOTAL IODINES OTHERS TOTAL
.000 964500.000 964500.000 .000 964500.000 964500.000
% MPC TOTAL: 964500.000 O
VIII-6
, - - , - . . .. - -.. - -- ~ , . . - ..
l l SECTION 7 ' i hT**********************************************************************ge 12/14/93 1030 EXERCISE DATA' Pa 1 ! GDR/HP NUCLIDE A N A'L Y S I S
SUMMARY
Version 2.1- I New York Power Authority i J. A. FitzPatrick' Nuclear Plant !
****************************************************************************** i i
Air Sample-Test Spectrum Reported by: CHEMISTRY. I File ID: December 14, 1993 j Library File: . . . . . .PLALIB. LIB (IN PLANT Air Sample Library ) MPC/LLD File: . . . . . .PLALLD.MPC (IN PLANT Air Sample MPC/LLD's1 ) Detector #: 4 Efficiency File: . . . ASPCS1D04.EFF (Glass Fiber Filt./F&J Charcoal Cart.) Ef f . =1/ ( 3.54E-02*En^-2.34E+00 + 1.57E+02*En^ 1.02E+00) 05/17/92 08:37
-(Where En = Energy in MeV) i
===================------ =m==========-------- ==================- =
MEASURED or MDA CONCENTRATION , Energy Concentration Less-Than Peaks LLD ' . ID ; Nuclide Group (kev) (uCi/cc ) Level Conc Found REQUIRED dET? ,
===============-- - --
_______==------- - ----
.= _ _ u, . == ;
(N-65 1115.16 < 7.'16E-10 MDA 6.25E-11 0 of 1 0.0E+00 .Yes i
\m h-144 133.54 < 2.46E-10 MDA 9.26E-11 0 of 1 5.OE-3* NO ,
TC-99M 140.51 < 3.02E-11 MDA 1.18E-11 0 of 1 0.0E+00 Yes 1 CE-141 145.44 < 4.21E-11 MDA 1.66E-11 0.of 1 5.0E-11 Yes i CR-51 320.08 < 4.40E-10 MDA 1.59E-10 0 of 1 5.0E-11 NO ! BR-84 880.00 <.4.79E-10 MDA 1.23E-11 0 of 4 6.0E-11 Yes ; I-130 418.00 < 1.24E-11 MDA 2.20E-10 0 of 5 5.1E-10 NO , I-131 364.48 8.33E-04 +-6.05E-06 ----- 4 of '4 ------- ---
- HF-181 482.30 < 8.45E-11 MDA 3.00E-11 O lof 2.0.0E+00 Yes _;
I-132 772.60 < 4.28E-10 MDA 3.26E-10 0 of 6 0.OE+00 Yes I-133 529.87 < 6.54E-10 MDA 6.23E-11 0 of 4 0.0E+00 Yes l I-134 884.12 < 5.96E-11 MDA 2.12E-11 0 of 11 5.2E-11 NO ! BA-140 537.32 < 1.76E-10 MDA 5.55E-11 0 of 5 0.0E+00 Yes SB-124 602.71 < 6.35E-11 MDA 5.91E-11 0 of 5 0.0E+00 Yes ! CS-137 661.65 < 6.02E-11 MDA 5.46E-11 0 of 1 1.0E-11 NO I MO-99 739.58 < 5.29E-10 MDA 1.25E-10 0 of 4 - 5.0E-11 NO ' ZR-95 756.72 < 1.24E-10 MDA 1.01E-10 0 of 1.0.0E+00 Yes- t j NB-95. 760.79 < 2.32E-11 MDA 7.43E-11 0 of 1 0.0E+00 Yes CS-134 795.85 < 1.08E-10 MDA 2.82E-11 0 of 7 1.0E NO " f CO-58 810.76 < 1.10E-10 MDA 3.70E-11 0 of 3 1.0E-11 NO MN-54 834.83 < 1.49E-10 MDA 5.35E-11 0 of 1 1.0E-11 NO !
~FE-59 1099.22 < 5.93E-11 MDA 5.79E-11 0 of 4 1.0E-11 NO- 1 1-135 1260.41 < 6.07E-06 MDA 6.23E-11 0 of 6 1.0E-11 NO !
CO-60 1332.49 < 1.46E-10 MDA 1.58E-10 0 of 2 1.0E-11 NO- j LA-140 1596.49 < 5.23E-11 MDA 5.10E-11 0 of 9 0.0E+00 Yes ! l f0TAL MEAS. ACT. : 8.33E-04 +- 6.05E-06 uCi/cc i J VIII-7
- 1
?
SECTION 7 James A. FitzPatrick Nuclear Power Plant '( ) 1993 Partial Participation Emergency Exercise December 14, 1993 12/14/93 1030 - End EXERCISE DATA Page 2 MPC CHECK MPC FILE: PLALLD.MPC Nuclide uCi/cc MPC % MPC I-131 8.33E-04 9.E-09 9.26E+06 TOTAL: 8.33E-04 9.26E+06
=================================------- ==================__-___========-----
MPCS for AIR SAMPLES AIR SAMP #: EXERCISE DATA , LOCATION: Reactor Building RWP #: 93-XXXX
==============r===============------- ===========================,============
Sampling On: 12/14/93 Sampling Off: 12/14/93 rotection Factors: Particulates: 1.000 Iodines: 1.000 Respirator: None
% MPC % MPC % MPC Eff. % MPC Eff. % MPC Eff. % MPC IODINES OTHERS TOTAL IODINES OTHERS TOTAL ---------.-56 9255555 5 .000 9255555.556 9255555.556 .000 9255555.556 % MPC TOTAL: 9255555.556 >
O l VIII-8 l i
l SECTION 7 James A. FitzPatrick Nuclear Power Plant ( 7-[- 1993 Partial Participation Emergency Exercise December 14, 1993 12/14/93 1030-END EXERCISE DATA Page 1
*********************************************************************v********
GDR/HP NUCLIDE ANALYSIS
SUMMARY
Version 2.1 New York Power Authority i J. A. FitzPatrick Nuclear Plant Mock In-Plant Gas Analysis Reported by: CHEMISTRY File ID: EXERCISE December 1993 Library File: . . . . . .GASLIB. LIB (Noble Gases Library ) MPC/LLD File: . . . . . .IPGLLD.MPC (In Plant Noble Gases ) . Detector #: 3 Efficiency File: . . . 4 LGMS OD03. EFF (4 L Gas Marinelli (Foam Filled) ) Eff.=1/( 3.17E-02*En^-2.97E+00 + 3.89E+02*En^ 9.69E-01) 03/29/92 14:14 (Where En = Energy in MeV)
"'=========================------ ===--------- -
MEASURED or MDA CONCENTRATION Energy Concentration Less-Than Peaks LLD LLD Nuclide Group (kev) (uCi/cc ) Level Conc Found REQUIRED MET?
================------- =======__ --------- -- - - -
XE-133 80.97 4.58E-02 +- 3.25E-07 ---- 1 of 1 ------- --- XE-137 455.00 < 2.25E-06 MDA 2.65E-10 0 of 4 0.0E+00 Yes XE-131M 165.75 3.75E-03 MDA 3.00E-11 0 of 2 0.0E+00 Yes KR-85 514.10 3.79E-02 +- 5.25E-06 ---- 1 of 1 ------- --- KR-88 196.32 < 6.32E-05 MDA 3.25E-11 0 of 1 3.2E-11 No XE-133M 233.21 1.05E-05 +- 7.22E-06 ---- 1 of 1 ------- --- XE-135 249.79 < 1.87E-04 MDA ------ 1 of 1 ------- --- XE-138 258.31 < 5.31E-04 MDA ----- 1 of 5 ------- --- KR-87 402.58 < 2.70E-04 MDA ----- 1 of 4 ------- --- XE-135M 526.56 < 1.94E-04 MDA ----- 1 of 1 ------- --- KR-85M 149.50 < 3.57E-04 +- 5.03E-07 ----- 1 of 1 ------- --- 305.00 I.D.Only TOTAL MEAS. ACT. : 8.74E-02 +- 5.40E-06 uCi/cc VIII-9
. = _
SECTION 7 James A. FitzPatrick Nuclear Power Plant () 1993 Partial Participation Emergency Exercise December 14, 1993
******************************************************************s***********
12/14/93 1100-END EXERCISE DATA Page 2 MPC CHECK MPC FILE: IPGLLD.MPC i Nuclide uCi/cc MPC % MPC XE-133 4.58E-02 1.E-05 4.58E+05 XE-131M 3.69E-03 2.E-05 1.84E+04 KR-85 3.79E-02 1.E-05 3.79E+05 XE-133M 1.05E-05 1.E-05 1.05E+02 TOTAL: 8.74E-02 8.56E+05
, ____=__ ------------- .
kq./==================================--- MPCS for AIR SAMPLES AIR SAMP #: EXERCISE DATA LOCATION: Reactor Building RWP #: 93-XXXX
========------ ======================r-- ,- --- =-- ================
Sampling On: 12/14/93 Sampling Off: 12/14/93 Protection Factors: Particulates: 1.000 Iodines: 1.000 Respirator: None
% MPC % MPC % MPC Eff. % MPC Eff. % MPC Eff. % MPC IODINES OTHERS TOTAL IODINES OTHERS TOTAL >
.000 855505.000 855505.000 .000 855505.000 855505.000
% MPC TOTAL: 855505.000 r O
VIII-10
l SECTION 7 James A. FitzPatrick Nuclear Power Plant () n 1993 Partial Participation Emergency Exercise December 14, 1993 O IX. POST ACCIDENT SAMPLE SYSTEM (PASS) DATA O IX-1
r SECTION 7 w- James A. FitzPatrick Nuclear Power Plant , 1993 Partial Participation Emergency Exercise December 14, 1993 Post Accident Samole System (PASS) Data Due to the~ compressed time frame of the exercise, the PASS sample will be prompted at approximately 0930. PASS data indicates approximately 20% of fuel clad damage. 0:
- - ?
I t f L O IX-2
SECTION 7 ,
,(~p James A. FitzPatrick Nuclear Power Plant .(_j 1993 Partial Participation Emergency Exercise December 14, 1993 Sample Dose Rates A. Large Volume Sample ,
- 1. Sampling 580 mR/hr
- 2. Handling 385 mR/hr
- 3. Transport 2 mR/hr B. Small Volume Sample
- 1. Sampling 480 mR/hr
- 2. Handling 320 mR/hr (background) '
285 mR/hr (sample)
- 3. Transport 2 mR/hr ;
C. Particulate and Iodine Sample - One Second Sample ,
- 1. Sampling 480 mR/hr (background) 550 mR/hr (sample)
- 2. Transport 2 mR/hr (background) *
/~T 2 mR/hr (sample)
(J D. Gas Sample
- 1. Sampling 460 mR/hr (background) 700 mR/hr (sample)
- 2. Handling 820 mR/hr (background) 765 mR/hr (sample)
- 3. Transport 4 mR/hr (background) 4 mR/hr (sample) k O
IX-3
SECTION 7 je ~ James A. FitzPatrick' Nuclear Power Plant
-( 1993 Partial Participation Emergency Exercise December 14, 1993 ;
I. Exposure Rates Durina Analysis A. Chloride 3 mR/hr (background) 7 mR/hr [1 cm] (sample) 26 mR/hr [10 cm] ~ (sample) ' 80 mR/hr [60 cm] (sample) B. Boron 3 mR/hr (background) 60 mR/hr [1 cm] (sample) 5 mR/hr [10 cm] (sample) 10 mR/hr [60 cm] (sample) [ C. Hydrogen / Oxygen Analysis 3 mR/hr (background) 60 mR/hr [1 cm] (sample) 5 mR/hr [10 cm] (sample) 1 mR/hr [60 cm] (sample) D. Isotopic Analysis / Liquid ' 3 mR/hr (background) 1 mR/hr [1 cm] (sample) O_ 1 mR/hr [10 cm] (sample) 1 mR/hr [60'cm] (sample) . E. Small Volume Liquid Dilution 3 mR/hr (background) 70 mR/hr [1 cm) (sample) 7 mR/hr [10 cm) -(sample) 2 mR/hr [60 cm] (sample) F. Gas Dilution 3 mR/hr (background) 18 mR/hr [1 cm] (sample) 2 mR/hr [10 cm] (sample) O mR/hr [60 cm] (sample) G. pH Analysis 3 mR/hr (background) 7 mR/hr [1 cm) (sample) 1 mR/hr [10 cm] (sample) O mR/hr [60 cm] (sample) H. Isotopic Analysis - Gas Final Dilution Factor 5 mR/hr (background) 8 mR/hr [1 cm] (sample) 1 mR/hr-[10 cm) (sample) 1 mR/hr [60 cm] (sample) O IX-4
SECTION 7 . James A. FitzPatrick Nuclear' Power Plant (_ 1993 Partial Participation Emergency Exercise December 14, 1993 ; I. Isotopic Analysis - Particulate 3 mR/hr -(background) 14 mR/hr [1 cm] (sample) .; 1 mR/hr [10 cm] (sample) 1 mR/hr [60 cm] (sample) . II. Other Exposure Rates A. Background Exposure in Chemistry Lab 0-1 mR/hr B. Background Exposure in Count Room 0 mR/hr O
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O IX-5
I I j SECTION 7 i g- James A. FitzPatrick Nuclear Power Plant \ 1993 Partial Participation Emergency Exercise December 14, 1993 1 December 93 EXERCISE PASS REACTOR COOLANT DATA ' J TAKEN BETWEEN 0930-End Page 1 GDR/HP NUCLIDE ANALYSIS
SUMMARY
Version 2.1 New York Power Authority J. A. FitzPatrick Nuclear Plant
*********P******************************************************************** '
Reactor Water Example Spectrum Reported by: CHEMISTRY File ID: EXERCISE December 1993 Library File: . . . . .RXWLIB. LIB (Reactor Water Library ) i Detector #: 1 Efficiency File: . . 100BS1D01.EFF (100 ml Poly Bottle ) Eff.-1/( 1.70E-Ol*En^-2.26E+00 + 5.47E+02*En^ 9.32E-01) 03/30/92 02:01 (Where En - Energy in MeV) MEASURED or MDA CONCENTRATION O Nuclide Group Energy. (kev) Concentration (uCi/ml Less-Than Peaks
) Level Conc Found 93.10 TH-XRAY BKG. -------
1 of 1 TC-99M 140.39 < 1.11E-06 MDA 1.73E-04 0 of 1 RA-223 154.99 < 6.97E-05 MDA 2.30E-05 1 of 1 XE-135 249.77 1.10E+02 +- 3.20E-04 ------- 1 of 2 XE-135M 526.56 7.20E+01 +- 3.56E-05 ------- 1 of 1 ANNIH 511.01 BKG. ------- 1 of 1 1-132 772.60 6.41E-01 +- 3.52E-06 ------- 6 of 6 522.85 I.D.Only 630.15 1.D.Only 667.81 I.D.Only 954.65 I.D.Only : 1398.12 I.D.Only I-133 529.93 5.12E-01 +- 5.23E-05 ------- 1 of 4 I-134 884.12 8.97E-01 +- 1.06E-05 ------- 7 of 11 , 541.04 I.D.Only 595.40 I.D.Only 621.51 I.D.Only ' 847.14 I.D.Only 857.65 1.D.Only 1072.91 1.D.Only AS-76 559.24 < 9.10E-05 MDA 6.34E-05 0 of 1 RU-105 677.45 1.D.Only ------- 1 of 4 CO-58 811.91 < 6.54E-10 MDA 5.20E-04 0 of 2 MN-54 835.84 < 3.34E-07 MDA 6.50E-06 0 of 1 XE-131M 163.93 < 6.31E-07 MDA 7.25E-05 0 of 1 ' XE-133 80.97 5.50E+02 +- 2.30E-06 ------- 1 of l' KR-85M 151.18 5.82E+03 +- 3.22E-06 ------- 1 of 2 304.87 O KR-87 402.58 673.87 1.62E+03 +- 2.26E-05 ------- 1 of 3 KR-88 196.32 1.40E+03 +- 6.36E-05 ------- 1 of 1 IX-6 I
SECTION 7 James A. FitzPatrick' Nuclear Power Plant (
- m) 1993 Partial Participation Emergency Exercise December 14, 1993 December 1993 EXERCISE PASS REACTOR COOLANT DATA TAKEN BETWEEN 0930-End Page 2 3 MEASURED or MDA CONCENTRATION Energy Concentration Less-Than Peaks Nuclide Group (kev) (uCi/ml ) Level Conc Found XE-133M 233.21 2.20E+01 +- 2.10E-06 ------- 1 of 2
-ZN-65 1115.96 < l.38E-10 MDA 3.25E-06 0 of 1 CO-60 1332.79 < 3.05E-10 MDA 6.52E-07 0 of 2 1172.76 I.D.Only XE-138 258.31 2.40E+00 +- 6.02E-06 -------
1 of 1 I-135 1260.49 7.25E-01 +- 4.09E-05 ------- 1 of 12 NA-24 1368.85 < l.68E-06 MDA 7.85E-07 0 of 1 CE-144 133.54 < 3.86E-04 MDA 1.73E-04 0 of 2 CE-141 145.44 < 2.09E-04 MDA 7.68E-05 0 of .1 CR-51 320.08 < 2.54E-04 MDA 2.03E-04 0 of 1 1-131 364.48 3.88E+00 +- 5.12E-06 ------- 1 of 1 CS-137 661.65 3.02E+02 +- 6.02E-06 ---.---- 1 of 1 MO-99 739.58 < l.86E-04 MDA 1.99E-04 0 of 3 CS-134 795.85 < 2.81E-05 MDA 1.64E-05 0 of 6 FE-59 1099.22 < 6.44E-05 MDA 2.86E-05 0 of 2 KR-85 514.10 3.30E+02 +- 5.23E-05 ------- 1 of 1 TOTAL MEAS. ACT. . 1.02E+04 +- 4.27E-04 uCi/ml
.O -
IX-7
l i l SECTION 7 1
- i James A. FitzPatrick Nuclear Power Plant 'l
( 1993 Partial Participation Emergency Exercise December 14, 1993 December 93 EXERCISE PASS REACTOR COOLANT DATA TAKEN BETVEEN 0930-End
****************************************************************************** ol D0SE EQUIVALENT IODINE Dose Eq. Dose Equivalent ! # Nuclide Activity Factor Activity
- 1. I-131 3. 88 E+ 00 1.00E+00 - !
- 2. 1-132 6.41E-01 3.60E-02 2.31E+00 uCi/ml ,
- 3. I-133 5.12E-01 2.70E-01 1.38E-01 uCi/ml ,
- 4. I-134 8.97E-01 1.70E-02 1.53E-02 uCi/ml
- 5. 1-135 7.25E-01 8.40E-02 6.09E-02 uCi/ml TOTAL: 6.66E+00 2.52E+00 uCi/ml
**********************************************+*******************************
Gross Gamma - 6.72E+06 CPM / ml
****************k*************************************************************
b 6 IX-8
.E i
SECTION'7 ) James A. FitzPatrick Nuclear Power Plant 1993 Partial Participation Emergency Exercise December 14, 1993 _. (] December 93 EXERCISE PASS PRIMAPJ CONTAINMENT ATMOSPHERE DATA TAKEN BETWEEN 0930-End Page 1 GDR/HP NUCLIDE ANALYSIS
SUMMARY
Version 2.1 New York Power Authority J. A. FitzPatrick Nuclear Plant Air Sample Test Spectrum Reported by: CHEMISTRY File ID: EXERCISE 1993 Library File: . . .PLALIB. LIB (IN PLANT Air Sample Library ) MPC/LLD File: . . . . .PLALLD.MPC (IN PIANT Air Sample MPC/LLD's ) Detector #: 4 Efficiency File: . . ASPCSlD04.EFF (SILVER ZEOLITE CARTRIDGE ) Eff.-1/( 3.54E-02*En^-2.34E+00 + 1.57E+02*En* 1.02E+00) 05/17/92 08:37 (Where En - Energy in MeV) MEASURED or MDA CONCENTRATION Energy Concentration Less-Than Peaks LLD .LLD Nuclide Group (kev) (uci/cc ) Level Co.,c Found REQUIRED MET? ZN-65 1115.16 < 7.16E-10 MDA 6.25E-11 0 of 1 0.0E+00 Yes CE-144 133.54 < 2.46E-10 MDA 9.26E-13 0 of 1 5.0E-ll NO L TC-99M 140.51 < 3.02E-ll MDA 1.18E-11 0 of 1 0.0E+00 Yes CE-141 145.44 < 4.21E-11 MDA 1.66E-11 0 of ' l 5.0E-ll Yes CR-51 320.08 < 4.40E-10 MDA 1.59E-10 0 of 1 5.0E-11 NO BR-84 880.00 4.79E-10 MDA 1.26E-11 0 of 4 6.2E-11 NO I-130 418.00 1.24E-ll MDA 1.35E-10 0 of 5 6.3E-10 NC I-131 364.48 6.08E-02 +- 4.32E-04-------- 4 of 4 ------- --- HF-181 482.30 < 8.45E-ll MDA 3.00E-11 0 of 2 0.0E+00 Yes I-132 772.60 3.76E-02 +- 5.60E-05-------- 6 of 6 ------- --- 522.85 I.D.Only 630.15 I.D.Only 667.81 I.D.Only 954.65 1.D.Only 1398.12 I.D.Only I-133 529.87 1.20E-01 +- 5.02E-05-------- 1 of 4 ------- --- I-134 884.12 1.88E-02 +- 6.21E-05-------- 7 of 11 ------- --- 541.04 I.D.Only 595.40 I.D.Only + 621.51 I.D.Only 847.14 I.D.Only 857.65 I.D.Only 1072.91 I.D.Only BA-140 537.32 < l.76E-10 MDA 5.55E-11 0 of 5 0.0E+00 Yes SB-124 602.71 < 6.35E-11 MDA 5.91E-11 0 of 5 0.0E+00 Yes CS-137 661.65 < 6.02E-11 MDA 5.46E-11 0 of 1 1.0E-11 NO MO-99 739 58 < 5.29E-10 MDA 1.25E-10 0 of 4 5.0E-ll NO ZR-95 756.72 < 1.24E-10 MDA 1.01E-10 0 of 1 0.0E+00 Yes NB-95 765.79 < 2.32E-ll MDA 7.43E-11 0 of 1 0.0E+00 Yes CS-134 795.85 < 1.08E-10 MDA 2.82E-11 0 of 7 1.0E-11 NO CO-58 810.76 < 1.10E-10 MDA 3.70E-11 0 of 3 1.0E-11 NO MN-54 834.83 < 1.49E-10 MDA 5.35E-11 0 of 1 1.0E-ll NO FE-59 1099.22 < 5.93E-11 MDA 5.79E-11 0 of 4 1.0E-11 NO O 1-135 CO-60 1260.41 1.16E-01 +- 2.02E-05-------- 1332.49 < 1.46E-10 MDA 1.58E-10 1 0 of of 6 2 1.0E-11 NO LA-140 1596.49 < 5.23E-ll MDA 5.10E-11 0 of 9 0.0E+00 Yes TOTAL MEAS. ACT. 3.53E-01 +- 1.33E-06 uCi/cc IX-9
p SECTION 7
-] James A. FitzPatrick Nuclear Power Plant 1993 Partial Participation Emergency Exercise December 14, 1993 December 93 EXERCISE PASS PRIMARY CONTAINMENT ATMOSPHERE DATA TAKEN BETWEEN 0930-End- Page 2 MPC CHECK MPC FILE: PIALLD.MPC Nuclide uCi/cc MPC % MPC k$k3k ~ " bbhbbh h$bbh b$hbb+bb I-132 3.76E-02 2.E-07 1.88E+07 I-133 1.20E-01 3.E-08 4.00E+08 I-134 1.88E-02 5.E-07 3.76E+06 I-135 1.16E-01 1.E-07 1.16E+08 TOTAL: 3.53E-01 1.21E+09 MPCS for AIR SAMPLES AIR SAMP #:1234 LOCATION:NONE RWP #: 93-XXXX Sampling On: 12/14/93 Sampling Off: 12/14/93 Protection Factors: Particulates: 1.000 Iodines: 1.000 Respirator: none
% MPC % MPC % MPC Eff. % MPC Eff. % MPC Eff. % MPC 10 DINES OTHERS TOTAL IODINES OTHERS TOTAL khkbbbbbbbbb bb khkkbbbbbb bb khkkhbbbbb$bbb bbb khkbb6bbbb$bbb
% MPC TOTAL:1214560000.000 l
i l l f IX-10
f SECTION.7 ( James A. FitzPatrick Nuclear Power Plant 1993 Partial Participation Emergency Exercise December 14, 1993 December 93 EXERCISE PASS PRIMARY CONTAINMENT ATMOSPHERE DATA TAKEN BETWEEN 0930-End Pa
************************************************************************ge ******
1 GDR/HP NUCLIDE ANALYSIS
SUMMARY
Version 2.1 New York Power Authority J. A. FitzPatrick Nuclear Plant Mock In-Plant Gas Analysis Reported by: CHEMISTRY File ID: EXERCISE 1993 Library File: . . . . . .GASLIB. LIB (Noble Gases Library ) MPC/LLD File: . . . .IPGLLD.MPC (In Plant Noble Gases -) Detector #: 3 Efficiency File: . . 4LGMS0D03.EFF (NOBLE GAS VIAL SAMPLE ) Eff.-1/( 3.17E-02*En^-2.97E+00 + 3.89E+02*En* 9.69E-01) 03/29/92 14:14 (Where En - Energy in MeV) O MEASURED or MDA CONCENTRATION Energy Concentration Less-Than Peaks LLD LLD Nuclide Group (kev) (uCi/cc ) Level Conc .Found REQUIRED MET 7 XE-133 80.97 3.02E+02 +- 6.03E-07 ------- 1 of 1 ------ --- l XE-131M 165.75 9.01E-01 +- 6.32E-06 ------- 1 of 1 ------ --- ! KR-85 514.10 2.00E+01 +- 8.72E-06 ------- 1 of 1 ------ -- i- KR-88 196.32 8.60E+01 +- 5.30E-07 ------- 1 of 1 ------ --- XE-133M 233.21 1.20E+01 +- 6.32E-06 ------- 1 of 1 ------ --- XE-135 249.79 5.81E+01 +- 6.23E-07 ------- 1 of 1 ------ --- l XE-138 258.31 1.31E+00 +- 5.12E-07 ------- 1 of 5 ------ --- ( KR-87 402.58 1.00E+01 +- 5.30E-07 ------- 1 of 4 ------ --- l XE-135M 526.56 3.94E+01 +- 6.02E-0'7 ------- 1 of 1 ------ ---
- . KR-85M 149.50 3.49E+01 +- 5.03E-07 ------- 1 of 1 ------ ---
- 305,00 I.D.Only 1
TOTAL MEAS. ACT. 5.65E+02 +- 1.09E-05 uCi/cc l IX-11
Y .p SECTION 7 .v. > James A. FitzPatrick Nuclear Power Plant 1993 Partial Participation Emergency Exercise December 14, 1993
****************************-:.r*********************************u*************
December 93 EXERCISE PASS PRIMARY CONTAINMENT ATMOSPHERE DATA . TAKEN BETWEEN 0930-End Pa
*************************************************************************ge *****
2 MPC CHECK MPC FILE: IPGLLD.MPC - - Nuclide uCi/cc MPC % MFC XE-133 3.02E+02 1.E-05 3.02E+09 XE-131M 9.01E.01 2.E.05 4.51E+06 KR-85 2.00E+01 1.E-05 2.00E+08 KR-88 8.60E+01 1.E.06 8.60E+09 , XE-133M 1.20E+01 1.E-05 1.20E+08 XE-135 5.81E+01 4.E-06 1.45E+09 XE-138 1.31E+00 1.E-06 1.31E+08 KR-87 1.00E+01 1.E-06 1.00E+09 XE-135M 3.94E+01 1.E.06 3.94E+09 KR-85M 3.49E+01 6.E-06 5.82E+08 TOTAL: 5.65E+02 1.90E+10 MPCS for AIR SAMPLES AIR SAMP #: DRILL IDCATION:INPLANT RWP #: 93-XXXX Sampling On: 12/14/93 Sampling Off: 12/14/93 Protection Factors: Particulates: 1.000 Iodines: 1.000 Respirator: None
% MPC % MPC % MPC Eff. % MPC Eff. % MFC Eff. % MPC IODINES OTHERS TOTAL 10 DINES OTHERS TOTAL
.000 1.90E+10 1.90E+10 .000 1.90E+10 1.90E+10
% MPC TOTAL: 1.90E+10 IX-12
.I e
SECTION 8 C-
.i l
James A. FitzPatrick Nuclear Power Plant [ 1993 Partial Participation Emergency Exercise i December 14, 1993 . i METHOD OF EVALUATION I. SAP-6 " Drill / Exercise Conduct" i f i i O O t e i f i e [ l O 1 8-1 - i
---_.____--_-__--__-_.__---____.______--____L-_______._-.--
4 NEW YORK POWER AUTHORITY l (].
%) JAMES A. FITZPATRICK NUCLEAR POWER PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE EMERGENCY PLAN VOLUME 3 ;
1 PROCEDURE NO.: SAP-6 j INFORMATIONAL USE j TITLE: DRILL / EXERCISE CONDUCT
- PORC REVIEW NO.: Meeting No. 93-04s' Date 3 [3s /93 f
APPROVED BY: / 4<f / v v i V< ' Resident Manager APPROVED BY: M i / Emergency Planning Co l PAGE NO. 1 2 3 4 5 6 7 8 9 10 REV. NO. 7 7 6 7 7 5 7 5 7 8 PAGE NO. 11 12 13 14 15 16 17 18 19 20 REV. NO. 0 5 5 5 5 5 5 5 5 5 PAGE NO. 21 22 23 24 25 26 27 28 29 30 REV. NO. 5 5 5 5 5 5 5 5 7 5 PAGE NO. 31 32 33 34 35 36 37 38 39 40 REV. NO. 5 5 5 5 5 5 5 5 5 5 PAGE NO. 41 42 43 44 45 REV. NO. 5 5 5 5 5 a Rev. No. 8
EMERGENCY PLAN IMPLEMENTING PROCEDURE . . SAP-6 DRILL / EXERCISE CONDUCT
- 1.0 PURPOSE j To establish a procedure for the_ conduct and. evaluation of all Emergency Plan Drills and Exercises at JAFNPP. This procedure also outlines the management controls used to' ,
ensure that corrective actions are implemented. l
2.0 REFERENCES
2.1 NUREG-0654 " Criteria for the Preparation _and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants." 2.2 JAFNPP Emergency Plan and Implementing Procedures, Volumes 1, 2 and 3. 2.3 SAP-1 MAINTAINING EMERGENCY PREPAREDNESS *. 2.4 Administrative Procedure-02.03 PROCEDURE FOR CONTROL & ' DISTRIBUTION OF THE EMERGENCY PLAN & IMPLEMENTING l PROCEDURES *. 3.0 INITIATING EVENTS ; Act Applicable. ; 4.0 PROCEDURE 4.1 Drill Conduct is discussed in Section 5 of this procedure. This section delineates the minimum , acceptable activity for a drill at JAFNPP. " 4.2 Exercise Conduct is discussed in Section 6 of this procedure. This section delineates the minimum acceptable activity for an exercise at JAFNPP.
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4.3 Observer Conduct is discussed in Section 7 of this procedure. This section specifies the minimum acceptable, preparation, training and response required for an observer of a JAFNPP drill or exercise. 4.4 Critiques and Corrective Actions are discussed in Section 8 of this procedure. This section specifies the method in which problems with Emergency Preparedness at JAFNPP are handled.
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Rev. No. 7 Page 1 of SAP-6 i
5.0 DRILL CONDUCT 5.1 Drills shall be directed with the frequency established by-SAP MAINTAINING EMERGENCY PREPAREDNESS. 5.2 Drills shall be directed'by a Lead Controller who shall be responsible for conducting the drill in accordance with the drill scenario and the drill report. 5.2.1 The Lead Controller may conduct a briefing with drill participants. The intent of such a briefing would be to insure that drill participants understand their function and purpose in the drill. The Control Room briefing. should be similar to a shift turnover briefing. 5.2.2 The Lead Controller may delegate controller responsibilities to other individuals. Controllers and observers can be used for this purpose. A controller shall be called such when that individuals sole responsibility is to assist in the conduct of a drill. An observer can function as a controller when assigned the task of providing information or instruction during a certain aspect of a drill. () 5.2.3 The Lead Controller shall insure that plant safety is not compromised by a drill, and may ; stop a drill at any time if in his opinion plant safety may be affected. 5.2.4 The Lead Controller shall attempt to collect the signatures of as many. participants as possible for training documentation. This responsibility can be delegated to other controllers, or observers. 5.2.5 The Lead Controller shall commence and end the Drill, upon approval from the JAFNPP Resident Manager. 5.2.6 The Lead Controller shall ensure that drill observers are stationed to properly. observe the drill. 5.2.7 The lead controller should distribute a fact : sheet to the Emergency Response Facilities describing plant conditions in effect approximately eight (8) hours prior to drill commencement. 5.3 During a' drill, when (public address system) O~ announcements are made, those announcements shall be prefaced or followed by the words "This-is a' Drill." r Rev. No. 7 Page- 2 of SAP-6
1 l l i i T: 5.4 During a drill when contacting any offsite or non-NYPA institution, the individual shall insure that the organization fully realizes that no emergency exists onsite and that it is a test of the JAFNPP Emergency Plan. 5.5 Drills shall be conducted using the guidance . established by Form SAP-6.1 " Drill Conduct checklist." l 5.6 The Emergency Planning Coordinator shall conduct an observer meeting prior to a drill. The meeting shall be to inform the observers of their specific tasks. 5.7 Radiological L 1ergency Medical Drills are limited in scope and partlcipation by plant personnel. Therefore, , only one lead controller is necessary in the Control Room, one observer / controller accompanying the victim and one controller at the destination hospital. Each observer / controller may be briefed individually. The Control Room controller must be a NYPA employee and the other controllers / observers may be medical consultant personnel. Drill documentation will be a combination of NYPA drill report and Control Room Observer Evaluation Form (SAP-6.2), supplemented by the medical consultant's evaluation of performance. () 6.0 EXERCISE CONDUCT ! An Exercise shall include all items specified for a drill , with the following differences 6.1 Exercises shall be conducted with the frequency established by SAP MAINTAINING EMERGENCY ! PREPAREDNESS. 6.2 A Lead Controller stationed in the Control Room shall be responsible for conducting the exercise in accordance with the written scenario. As a minimum, r controllers shall also be present in the Technical : Support Center, Operational Support Center, and the Emergency Operations Facility. 6.3 Every attempt should be made to include Federal, State , and local input into the development of the exercise ; scenario. 6.3.1 The Exercise scenario shall be developed by a committee headed and organized by the Emergency . Planning Coordinator at JAFNPP. 7.0 OBSERVER CONDUCT .
'O 7.1 Observers shall be used to record.all significant events and the time at which they occur during a drill :
or exercise using Form SAP-6.2 " Evaluation Form." The Rev. No. 6 Page 3 of SAP-6 5
r
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.i drill or exercise scenario shall state the objectives a .
of.the drill or exercise.which will determine the major' areas for the observers to-concentrate their; f
-observation. Actions to be observed include: the. t ability to control the emergency, timely and proper ;
notification, availability and use of equipment and 1 personnel for control and recovery, assessment of ! consequences of the emergency actionsLtaken by .l emergency personnel, and the necessity for off-shift l notifications. l 7.2 Observers shall be selected with thelconcurrence of the Resident Manager. 7.3 There'shall be enough observers to match-all points i specified in the drill / exercise scenario or drill form l (SAP-1.2). The degree of; observation shall be made j based on the extent of the drill'or scenario. As a : general' rule, however, observers shall be stationed to 'j observe all expected major actions of the drill . expected and as. listed in objectives statement of the drill or exercise scenario. At least two observers must be available for drills and at least eight observers for an exercise. > y 7.4 In plant observers shall be badged following normal l plant badging procedures, and are required to ; i participate during accountability. drills. ; 7.5 Observers shall be visibly identified as observers, and' -l they should take no part in the action of the drill or i exercise except to: ;
-i 7.5.1 Indicate simulated conditions to the exercise or drill participants, (e.g., survey. meter .
. readings, contamination levels,Letc.), but only .i after instructions by the lead controller or ,
i individual acting on-behalf of lead controller-7.5.2 Observe poor communication techniques'and! 'f procedures and note / correct such occurrences 1 when they. occur. 1 i 7.5.3 Prevent the communication of simulated. emergency ~ l conditions as. actual conditions outside!of.thef f
-exercise or drill area-and to ensure that radio ,
or telephone messages are periodically preceded' " i and. ended by the statement "This:is a Drill." 7.5.4 Prevent actions which might create a hazard to ' personnel or equipment.- In such' cases, observers shall require personnel participating i O. in the exercise or drill'to indicate the action j verbally. .l Rev. No. 7 Page 4 -of-SAP-6 ; f
... ... -- -- .- a
7.6 Observers shall be briefed as to their duties prior to the commencement of the drill or exercise. Drill observers should.be briefed within 24-hours of the commencement of a drill. Exercise observers should be briefed within 24 hours of the commencement of an exercise and written aids and procedures shall be provided for use by the observers. This 24-hour time . frame may be adjusted to compensate for unannounced exercises. i 7.7 Training shall be provided to observers by the JAFNPP Training Department and/or drill / exercise lead controllers. The training provided for observers will entail the briefing listed in Section 7.6. The . briefing shall include a review of the drill or exercise scenario, the observer duties with regard 1to the assigned areas of observation, and the key points to be noted. The Emergency Planning Coordinator shall develop a list of observers to be trained. Exceptions to the qualified observer list may be made by the > Emergency Planning Caordinator.
- 7.8 At the conclusion of the drill or exercise, the Emergency Planning Coordinator shall collect the .
completed " Observer Evaluation Forms" (SAP-6.2), , compile a list of participants and conduct a critique : with the observers. . 7.9 Observers shall familiarize themselves with the duties and action requirements of the personnel they are : monitoring. The Drill Report SAP-1.2 shall list Observers' Name,. Organization, Area of Responsibility, ' and Reference Procedures. Observers shall review
- referenced procedures. Observers shal2. use the .:
following as g idelines. 7.9.1 Control Room The observer shall observe the action of ! personnel assigned to the Control Room and ; personnel who report to the Control Room for : assignment. In addition, special attention will be given to the following. - i Notifications to onsite personnel and offsite agencies. Request for the call-in of off duty personnel. Operations handling of accident conditions. > O i
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Rev. No. 7 Page 5 of SAP-6 i
t r~i Instructions given to Search and Rescue, 'i Repair-and Corrective Action Teams and H.P. ;
, Tech's by the Shift Supervisor (SS), as applicable. I Does the SS handle the emergency by directing people or by trying to do the work himself?
Are the time frames of actions by the SS reasonable enough? - Actions of personnel in the Control Room. Communications with the EOF. Communications with the TSC. 7.9.2 Control Point It is to be noted that all normal practices such : as sign out and use of frisker and the portal monitor are to be accomplished.unless the H.P. i Technician gives other directions because of radiological conditions. The observer will pay special attention to the above along with the following. - No one is wearing radiological protection clothing when leaving. " All alarms from monitoring equipment are acknowledged. 7.9.3 Assembly Area + Observe the following for assembly area personnel: P They seek out their assembly area, generally-stay together as a group and remain orderly. j Time of assembly and completed accountability. 7.9.4 Emergency Operation Facility This is the command post for'the Emergency and it should seem so to the observer. Look for the , following things: The Emergency Director is in command of the EOF. i
'Rev. No. 5 Page 6 of SAP-6
a $ u K Any extra personnel, spectators and those
) awaiting orders,-are quietly standing out of the way. .
Has the Emergency Director contacted the TSC ' Manager? The Radiation Protection or Support Personnel are performing duties in an efficient manner and reporting results to the Emergency Director. , Instrumentation deployed in the EOF is placed in an non-interfering position. How problems with the radio and telephone are handled. Using time as criteria, release rates and thyroid and whole body exposures to the offsite population are calculated quickly after the receipt of data from the Control Room or the Offsite Monitoring Team (s). The time frame of updates to offsite agencies and the reporting of exposure data and 1 changes to site meteorological conditions, to
-O those same agencies.
The Emergency Director assigns, where possible, the duty of making routine calls to someone else thereby leaving himself free to command the action. Assessment Teams methods to make protective actions to offsite populations.
- 7.9.5 Off-Site Monitoring Teams t!e observers shall observe the following items:
Received KI dose, if necessary. ;
- Operational check performed on survey instruments, sample counter and' sample pump before leaving the site.
Equipment availability verified. Assignment of TLD's and dosimeters before leaving the site.
) -
Silver Zeolite Cartridges made available before leaving the site. Rev. No. -7 Page 7 of SAP-6
r r - Survey. instrument operationally checked out
- T,) and turned on prior to leaving to take field readings.
- Radio check out by communicating to EOF or
- TSC before leaving.
Beta and gamma. field surveys performed on the f way to sample point. Sampling and field surveys performed at , sample location. 5 Instrument calibration _ performed and samples counted. Work performed in a professional manner. 7.9.6 On-Site Monitoring Team On-site monitoring teams may be assigned field survey work along the perimeter of the site. , Check on the following items: : Where do they receive their instructions? , Dosimeter and TLD are being worn. (} What type of survey instruments used. Do they have radio / cellular phone available? , Radio / phone check performed. Field readings taken along the route to the designated area. :
~
Work performed in a professional manner. 7.9.7 Security Force Are all security personnel accounted for? A i Does security direct people to the assembly area for accountability? r Are access and egress roads controlled? ! 7.9.8 Technical Support Center The' area maintained as a controlled area. Are communications initiated? Are H.P. Surveys performed and by_whom? Rev.-No.- 5 .Page 8 1of SAP-6 l
i, g ,. 7.9.9 Operations Support Center ; How is it staffed? What and how many teams are brought to the OSC? Are phones continuously manned? Are H.P. Surveys performed and by whom? ' 7.9.10 Radiation Protection Office j Do they report to the OSC when an Evacuation .; Alarm Sounds? Do they receive instructions and from whom? Are accurate protective measures taken if an entry into the controlled area is required? Who are survey results reported to? (CR and/or TSC) 7.9.11 Fire Brigade {}- Do they receive instructions nd from whom? Are protective measures taken if an entry into a controlled are is required? ; Are Fire preplans consulted? Is assistance requested from local support fire departments? 7.10 Immediately following the exercise / drill, observers / i controllers should conduct a short critique for ' participants in their assigned area. 8.0 CRITIOUES AND CORRECTIVE ACTIONS < 8.1 Critique !
~
A post exercise / drill critique should be held for observers and' plant supervision by the Emergency Planning Coordinator. The critique should be held within 24 hours of the drill / exercise, at a time and place specified by the Emergency Planning Coordinator. This meeting'shall be held to help resolve questions raised by various observers and plant supervisors and j to develop a list of corrective actions as necessary. [ The observations should include those actions noted by l the observers which were not in accordance with approved procedures. In addition, the exercise drill Rev. No. 7 Page of SAP-6
.)
l observers should identify any areas which require i clarification, development or revision of procedures.
}
8.2 Emergency Plan Improvement Items / Lessons Learned Report I Following the critique, the Emergency Planning l Coordinator shall' develop a list of Deviation and Event , Reports (DER's), improvement items and lessons learned as a result of the drill or exercise. These-items may be generated as a result of comments made at the critique, comments made by observers and controllers, or comments made by drill / exercise participants. The Emergency Planning Coordinator or designee shall review these comments and categorize significant comments into
" DER's", " Lessons Learned" or " Improvement Items." l This listing and associated proposed corrective actions ,
shall be submitted to the General Manager - Support Services for concurrence and approval. From this listing, the General Manager - Support Services shall decide which of these items warrant entry into the . JAFNPP Action Commitment Tracking System (ACTS) and assign a completion date. The administration of the ACTS is controlled by JAFNPP Administrative Procedure AP-03.08 " Action Commitment and Tracking System *." 1 8.3 The Emergency Planning Coordinator shall, after the preparation and review of the Emergency Plan e Improvement Items / Lessons Learned listing, present the listing to the Plant Operating Review Committee (PORC). The PORC shall review the listing. This review shall be incorporated into the PORC meeting minutes. 8.4 Any items identified during the critique that pertain to the scenario package'used for the drill / exercise shall also be used to improve the package for future use. Scenario packages do not need to be updated until subsequent use. 9.0 FIGURES. FORMS AND ATTACHMENTS 9.1 FORM SAP-6.1 Drill or Exercise Conduct Checklist 9.2 FORM SAP-6.2 Observer Evaluation Forms O Rev. No. 8 Page 10 of SAP-6 , i
/"' . FORM SAP 6.1 DRILL OR EXERCISE CONDUCT CHECKLIST
- 1. Prepare a drill or exercise scenario.
- 2. Prepare a drill or exercise report.
- 3. Present the drill or exercise to the Plant Operating Review Committee Representative.for approval.
- 4. Brief observers on the entire drill or exercise.
- 5. Brief the individual observers on specified tasks.
- 6. Issue Observer Aids and Drill / Exercise Observation Sheet.
- 7. Initiate the drill or exercise.
- 8. Ensure the " flow" of activity throughout the drill or exercise.
- 9. Terminate the drill or exercise when it's purpose
() is accomplished.
- 10. Conduct a critique with participants or observers. [
- 11. Collect Drill / Exercise Observation Sheets.
- 12. Complete Emergency Plan Corrective Action Report, list all deficiencies and recommendations.
- 13. Present the Emergency Plan Corrective Action Report to PORC. ,
- 14. Complete action required on deficiencies.
t r (:) Rev. No. O Page 11 of SAP-6~
FORM SAP-6.2 OBSERVER EVALUATION FORM DATE: LOCATION: CONTROL ROOM OBSERVER: CONTROLLER: YES NO
- 1. Did the Shift Supervisor /ED demonstrate he is in '
charge?
- 2. Did the Control Room classify the '.
emergency correctly in accordance with IAP-2?
- 3. Were notifications made to NYS and Oswego County within 15 minutes of event classification?
Were updates timely?
- 4. Was timely notification made to the NRC (must be completed within one' hour from event classification)?
- 5. Were communications prefaced with "This is a drill?"
- 6. Log the following times for event classification and notifications:
Class. RECS Plant Staff NRC Time EAL _ Time Time Time NUE ALERT ' SAE GE Did the SS/ED direct Security to initiate call outs? (Not necessary during normal working hours.)
- 7. Were timely briefings given to plant staff?
- 8. Was the ENS phone manned?
- 9. Did the Control Room experience any emergency plan equipment failures?
I If yes, what were the failures and how was the problem addressed: 1 O Rev. No. 5 Page 12 of SAP-6
FORM SAP-6.2 g' QBSERVER EVALUATION FORM (CONTROL ROOM CONTINUED) l YES No
- 10. Did Control Room _ personnel adhere to procedures (EOP's, AOP's, Tech. Specs., etc.)?
- 11. Was staffing level adequate? !
- 12. Was Emergency Director turnover from the SS thorough?
Was plant staff advised of this transfer of responsibilityi
- 13. Once initiated, was accountability conducted and maintained throughout the emergency?
- 14. Was shift turnover demonstrated?
- 15. Were logs properly maintained by key personnel?
- 16. Was the plant staff adequately informed regarding plant status?
- 17. Was data flow between facilities and teams accurate,
() timely and complete?
- 18. Was habitability performed in accordance with EAP-14.6?
- 19. Were all objectives met?
If not, explain: t I
~~~
Rev. No. 5 Page 13 of SAP-6
FORM SAP-6.2 [ OBSERVER EVALUATION FORM \ (CONTROL ROOM CONTINUED)
- 20. Miscellaneous Comments and Notes:
O O Rev. No. 5 Page 14 of SAP-6
i FORM SAP-6.2 i ODBERVER EVALUATION FORM DATE: LOCATION: TSC ' l 0 3 SERVER: CONTROLLER: YES NO ,
- 1. Was the TSC activated in a timely manner?
- a. Time TSC was called for activation
- b. Time TSC declared themselves operational
- 2. Was the TSC set-up in accordance with EAP-14.1?
- 3. Did the TSC Manager demonstrate he is in charge?
- 4. Were offsite notifications made in accordance with EAP-1.1?
- 5. Were onsite notifications made in accordance with EAP-1.1?
- 6. Were communications prefaced with "This is a drill?"
() 7. Log the following times for event classification and notifications (if applicable): Class. RECS Plant Staff NRC EAL Time Time Time Time NUE ALERT SAE GE
- 8. Was staff familiar with their equipment and responsibilities?
- 9. Was the staffing level adequate?
- 10. Were periodic briefings held on plant status?
- 11. Were plant staff aware of changes in emergency classification?
- 12. Were status boards updated in a timely manner? ,
- 13. Were logs properly maintained by key personnel?
() 14. Did the technical staff support the Control Room?
- 15. Were corrective actions / solutions well thought out?
Rev. No. 5 Page '15 of SAP-6 P
4 FORM CAP-6.2 OBSERVER EVALUATION FORM O- (TSC CONTINUED) YES NO-
- 16. Did the TSC experience any emergency plan equipment '
failures? If yes, what were the failures and how was the problem addressed: L
- 17. Did the Emergency Director classify the emergency correctly?
- 18. Was a site evacuation called for?
If yes, were local authorities and Niagara Mohawk notified?
- 19. Was the transfer of the Emergency Director and his
() responsibilities from the TSC to the EOF smooth and complete?
- 20. Once initiated, was accountability conducted and ,
maintained throughout the emergency? l l
- 21. Was shift turnover demonstrated? l
- 22. Was data flow between facilities and teams accurate, timely and complete?
- 23. Was habitability performed in accordance with EAP-14.6?
- 24. Was a Radiation Protection technician dispatched to the JNC upon activation?
- 25. Were all objectives met?
If not, explain: ; O Rev. No. 5 Page 16 of SAP-6
FORM SAP-6.2 OBSERVER EVALUATION FOEM ~
-(TSC CONTINUED)
- 26. Miscellaneous Comments and Notes:
O 3 O i Rev. No. 5 Page 17 of. SAP-6
. ~ .
I k FORM SAP-6.2 OBBERVER EVALUATION FORM DATE: LOCATION: OSC OBSERVER: CONTROLLER: YES NO
- 1. Was the OSC activated in a timely manner?
- a. Time OSC was called for activation
- b. Time OSC declared operational
- 2. Was the OSC set up in accordance with EAP-14.5?
- 3. Did the OSC Manager demonstratr .se is in charge?
- 4. Was the staffing level adequate?
- 5. Was shift turnover demonstrated?
I
- 6. Were logs properly maintained by key personnel?
() 7. Were status boards updated in a timely manner?
- 8. Log the following times OSC became aware of event classification.
NUE Alert SAE GE
- 9. Were periodic briefings conducted in the OSC i regarding plant status?
- 10. Was data flow between facilities and teams accurate, timely and complete?
- 11. Did the OSC experience any emergency plan equipment <
failures? If yes, what were the failures and how was the problem addressed:
- 12. Once initiated, was accountability conducted and maintained throughout the emergency?
- 13. Was habitability performed in accordance with +
EAP-14.6? Rev. No. 5 Page 18 of SAP-6
i l FORM SAP-6.2 l
. i OBSERVER EVALUATION FORM %) (OSC CONTINUED)
YES NO
- 14. Were repair team briefings adequate and timely?
- 15. Were repair team debriefings adequate and timely?
- 16. Were emergency exposure authorizations necessary?
If yes, were actions consistent with procedures?
- 17. Were individual personnel exposure histories obtained in a timely manner for repair team personnel availability?
- 18. Was status of repair teams adequately maintained?
- 19. Were emergency tasks prioritized and acted upon in assigned priority?
- 20. Were all objectives met?
If not, explain: O ( l l Rev. No. 5 Page 19 of SAP-6
FORM SAP-6.2 OBSERVER EVALUATION FORM i (OSC CONTINUED)
- 21. Miscellaneous Comments and Notes:
O i l I i l l t I l l O Rev. No. 5 Page 20 of SAP-6
FORM SAP-6.2 OBSERVER EVALUATION FORM O~ DATE: LOCATION: REPAIR & CORRECTIVE ACTION TEAMS OBSERVER: CONTROLLER: TEAM ACTIVITY: YES NO
- 1. Did the team consist of a minimum of two individuals?
- 2. Was a briefing conducted?
- If so, did it include:
- a. most direct route
- b. proper tools
- c. tasks understanding
- d. visual aids (maps, drawings, etc.)
- e. simulations
() 3.
- f. radiation area dose rates Were the OSC Manager and Emergency Maintenance Coordinator cognizant of all Repair and Corrective Action Team efforts?
- 4. Did SS approve work on safety related items?
- 5. Was TSC direction obtained for engineering repair work?
- 6. Was RWP or Emergency Plant Entry Form prepared?
(circle one)
- 7. Was dosimetry, protective clothing, etc. issued in accordance with the above form?
- 8. Were there any Emergency Plan equipment failures?
If so, what were they and how was problem addressed? O Rev. No. 5 Page 21 of SAP-6
b FORM SAP-6.2
- (
OBSERVER EVALUATION FORM ,
\ (REPAIR & CORRECTIVE ACTION TEAMS CONTINUED)
YES NO i
- 9. Was a debrief conducted?
- 10. Were all objectives met? ,
I If not, explain: O , l' O
-1 Rev. No. 5 Page 22 of. SAP-6
FORM SAP-6.2 r' OBSERVER EVALUATION FORM C (REPAIR & CORRECTIVE ACTION TEAMS CONTINUED)
- 11. Miscellaneous Comments and Notes:
e O Rev. No. 5 Page 23 of SAP-6
FORM SAP-6.2 ODSERVER EVALUATION FORM DATE: LOCATION: FIRE BRIGADE OBSERVER: CONTROLLER: YES NO
- 1. Time Control Room notified of fire Time fire alarm sounded Time fire brigade dispatched Time fire brigade responded to scene
- 2. Was fire alarm sounded and the announcement properly made over the plant page?
- 3. Was offsite assistance requested?
If yes, was Security directed to: -
- a. allow immediate access
- b. provide dosimetry
- c. direct and escort fire company
- d. collect dosimetry upon exit 1
- 4. Were all unnecessary personnel evacuated from the fire area?
() 5. Was Rad Protection requested to perform a survey? Were radiological conditions properly assessed? 6.
- 7. Was emergency exposure criteria addressed and implemented?
- 8. Were all communications preceded with "This is a Drill?"
- 9. Were fire brigade members familiar with their duties?
- 10. Was the emergency classified correctly?
- 11. If the OSC was activated, was the fire brigade dispatched from the OSC with a radiation protection technician?
- 12. Were all objectives met?
If not, explain: ; O Rev. No. 5 Page 24 of SAP-6
FORM SAP-6.2 OBSERVER EVALUATION FORM _(g^)g (FIRE BRIGADE CONTINUED)
- 13. Miscellaneous Comments and Notes:
k 1 O Rev. No. 5 Page 25 of SAP-6
FORM SAP-6.2 OBSERVER EVALUATION FORM DATE: LOCATION: SECURITY / ACCOUNTABILITY OBSERVER: CONTROLLER: YES NO '
- 1. Was the emergency classification posted at main security?
- 2. Were call-outs performed as directed by the SS/ED?
(Not required during normal working hours.)
- 3. Was site access controlled?
- 4. Were guards dispatched to access roads?
- 5. If accountability was called for:
- a. Time site access / egress was restricted
- b. Time accountability was initiated
() c. Time accountability completed
- 6. Did accountability clerks report to their assigned assembly areas when directed?
- 7. Were accountability readers and sign-in sheets used?
- 8. Did accountability clerks experience any emergency plan equipment failures?
If yes, explain: i t I l l 9. Was movement of personnel between onsite facilities L adequately controlled?
- 10. Was movement of personnel badging offsite timely '
and orderly?
- 11. Was assembly in the Training Building auditorium O controlled?
Were personnel updated regarding plant conditions? l I ! Rev. No. 5 Page 26 of SAP-6 I i _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ . _ . _ _ _ . . _ . . _ _ _ _ . . _ _ _ _ _ _ . _ _ _ _ . _ _ . _ _ _m
FORM SAP-6.2 OBSERVER EVALUATION FORM , (SECURITY / ACCOUNTABILITY CONTINUED) YES NO
- 12. Was continuous accountability maintained for the remainder of the emergency?
- 13. Was site evacuation called for?
If yes, were personnel directed to proceed to the Howard Road remote assembly area? If yes, did the maps distributed to evacuating personnel coincide with the selected evacuation route?
- 14. Were all objectives met?
If not, explain: l 0 -. C:) Rev. No. 5 Page 27 of SAP-6
FORM SAP-6.2
"'g _ OBBERVER EVALUATION FORM - (V (SECURITY / ACCOUNTABILITY CONTINUED)
- 15. Miscellaneous Comments and Notes:
i t 0 O Rev. No. 5 Page 28 of SAP-6
FORM SAP-6.2 OBSERVER EVALUATION FORM DATE: LOCATION: CHEMISTRY TECHNICIAN i OBSERVER: CONTROLLER: YES NO
- 1. Did he/she report to Control Room upon implementing -
the Emergency Plan?
- 2. What tasks were required by the ED for the chemistry Technician?
- 3. Was the technician familiar with the procedures for the tasks?
- 4. What tasks were required by the Chemistry Supervisor
() for the technicians? Were they familiar with the procedures for the tasks?
- 5. Did any emergency plan equipment fail to operate?
If ves, what were the failures and how was the problem addressed?
- 6. If PASS was demonstrated, was the above 3-hour time commitment met?
O Rev. No. 7 Page 29 of SAP-6
1 FORM SAP-6.2 ! [} OBSERVER EVALUATION FORM V (CHEMISTRY TECHNICIAN CONTINUED)
- 7. Miscellaneous Comments and Notes: l O
I O Rev. No. 5 Page 30 of SAP-6
FORM SAP-6.2 OBBERVER EVALUATION FORM ( ' DATE: LOCATION: FIELD MONITORING OBSERVER: CONTROLLER: YES NO ;
- 1. Were teams assembled in a timely manner?
- 2. Were teams familiar with procedures?
- 3. Time the team was dispatched:
Team was dispatched from OSC/ EOF (circle one)
- 4. Did team obtain the proper equipment prior to leaving?
- 5. Were equipment checks pert aed prior to departure?
- 6. Were calibration dates current?
- 7. Were communication checks conducted prior to departure?
- 8. Was a vehicle /110V power supply check conducted?
O 9. Was the team briefing adequate?
- 10. Did the briefings include:
- a. Plant conditions / nature of release?
- b. Meteorological conditions?
- c. Projected dose rates / stay time ;
- d. Protective measures?
- e. Use of KI?
- f. Dosimetry recording?
- g. Types of readings / samples-to be obtained?
- h. Means of communication? '
- 1. Emergency exposure limits?
- 11. Was the communications flow between team and dispatcher timely and accurate and complete?
- 12. Were teams briefed frequently by the dispatcher?
- 13. Were survey results properly relayed to the dispatcher?
- 14. Were communications prefaced with "This is a Drill?"
() 15. Were teams proficient in proper survey / sampling techniques? Rev. No. 5 Page 31 of SAP-6
FORM SAP-6.2 <~4 OBBERVER EVALUATION FORM h (FIELD MONITORING CONTINUED) YES NO
- 16. Were proper plume traversing techniques demonstrated?
If no, explain: f
- 17. Were vehicles and equipment checked for contamination upon return?
- 18. Was shift turnover demonstrated?
- 19. Did teams experience any Emergency Plan equipment failures?
If yes, explain:
- 20. Were all objectives met?
If not, explain: O Rev. No. 5 Page 32 of SAP-6
FORM SAP-6.2 o OBSERVER EVALUATION FORM i (FIELD MONITORING CONTINUED)
- 21. Miscellaneous Comments and Notes:
P O Rev. No. 5 Page 33 of SAP-6
FORM SAP-6.2 r- OBSERVER EVALUATION FORM ( DATE: LOCATION: EOF OBSERVER: CONTROLLER: YES NO
- 1. Was the EOF activated in a timely manner?
- a. Time EOF was called for activation
- b. Time EOF declared themselves operational <
- 2. Was the EOF activated in accordance with EAP-14.2?
- 3. Did the EOF Manager demonstrate he is in charge?
- 4. Was the transfer of command and control from the TSC to the EOF adequate?
Time ED assumed duties at the EOF
- 5. Were offsite notifications made in accordance with EAP-1.1?
(Note the time forms are issued in comments section.)
- 6. Were communications prefaced with "This is a Drill?"
- 7. Log the following times for event classification and notifications (if applicable):
Class. RECS Plant Staff NRC EAL Time Time Time Time ' NUE ALERT SAE GE
- 8. Was staff familiar with their equipment and responsibilities?
- 9. Was the staffing level adequate?
- 10. Were periodic briefings held on plant status?
- 11. Was EOF staff aware of changes in emergency classification?
(q f _)
- 12. Were EAL's classified correctly?
- 13. Were status boards updated in a timely manner?
Rev. No. 5 Page 34 of SAP-6
FORM SAP-6.2 OBSERVER EVALUATION FORM ( (EOF CONTINUED) YES NO
- 14. Were logs properly maintained by key personnel?
- 15. Did the EOF experience any emergency plan equipment failures:
If yes, what were the failures and how was the problem addressed: t
- 16. Did the ED consult with state and county representatives regarding protective action recommendations?
- 17. Was long term facility staffing considered in O accordance with EAP-43?
- 18. Was shift turnover demonstrated?
- 19. Was data flow between facilities accurate, timely and complete? . _ _
- 20. Was the ED aware of plant decisions?
- 21. Was access control adequate?
- 22. If a release was in progress, were incoming personnel monitored to prevent spread of contamination?
- 23. Were all objectives met?
If not, explain: Rev. No. 5 Page 35 of SAP-6
i FORM SAP-6.2 - OBSERVER EVALUATION FORM .( (EOF CONTINUED)
- 24. Miscellaneous Comments and Notes:
O O Rev. No. 5 Page 36 of SAP-6
FORM SAP-6.2 OBSERVER EVALUATION FORM t DATE: LOCATION: DOSE ASSESSMENT OBSERVER: CONTROLLER: , YES NO
- 1. Did dose assessment personnel perform equipment checks upon arrival?
- 2. Were personnel familiar with the equipment?
- 3. Was the transfer of activities from the TSC to the EOF timely and complete?
- 4. Were meteorological forecasts obtained? i
- 5. Were status boards updated and utilized? ,
- 6. Were Part II forms completed accurately and on time?
- 7. Were EAP-4 forms properly completed and utilized?
() 8. Was field survey data utilized for comparison with computer projected doses? Were discrepancies resolved?
- 9. Were field teams briefed periodically regarding plant status?
- 10. Were dose calculations and the determination of protective action recommendations performed efficiently and in a timely manner?
- 11. Was the interface with TSC radiological personnel (re: effluent monitor readings, effluent sample results, PASS samples, etc.) adequate? .__
- 12. Were offsite liaisons utilized for the exchange -
and comparison of field survey data and dose projections?
- 13. Was there someone available to interface with and answer questions for offsite liaisons?
- 14. Were offsite liaisons included in discussions regarding PARS?
, 15. Were the results of dose calculations and protective action recommendations correct and in accordance with established procedures? Rev. No. 5 Page 37 of SAP-6
FORM SAP-6.2 OBSERVER EVALUATION FORM [ ' : (DOSE ASSESSMENT CONTINUED) YES NO
- 16. Were'all communications prefaced with "This is a Drill?"
- 17. Was shift turnover demonstrated?
- 18. Did any emergency plan equipment fail to operate? ,
If yes, what were the failures and how was the problem address?
- 19. Were all objectives met?
O If not, explain: O Rev. No. 5 Page 38 of SAP-6
FORM SAP-6.2 e ODBERVER EVALUATION FORM (, (DOSE ASSESSMENT CONTINUED)
- 20. Miscellaneous Comments and Notes:
O i t Rev. No. 5 Page 39 of sap-6
FORM SAP-6.2 OBSERVER EVALUATION FORM DATE: LOCATION: JNC OBSERVER: CONTROLLER: YES NO
- 1. Was the JNC activated in a timely manner?
- a. Time JNC was called for activation
- b. Time JNC was operational
- 2. Was the JNC set up in accordance with JNC procedures?
- 3. Was information flow between the plant, EOF and JNC accurate, timely and complete?
- 4. Did the utility effectively share information with state and county public information staff?
- 5. If technical information was required, was the information obtained frem appropriate personnel?
( 6. Were news releases reviewed and authorized by
\ designated personnel prior to their release to the media?
- 7. Were news releases timely, accurate and complete?
- 8. Was .ounty activation of the EBS system timely?
- 9. Were county EBS messages appropriate, timely, and complete?
- 10. Was information provided.to the media consistent with the EBS messages?
- 11. Was information released understandable to the public?
- 12. If protective actions were implemented, were affected areas appropriately specified?
- 13. Were press briefings held frequently to give available information as conditions changed?
- 14. When conditions were static, were briefings held frequently to keep the media updated?
(~ 15. Did the media spokesperson present material
'\ effectively?
Rev. No. 5 Page 40 of SAP-6
i FORM SAP-6.2
..P OBSERVER EVALUATION FORM s__
( - (JNC CONTINUED) Y YES NO
- 16. Were questions by the media handled properly by the media spokesperson?
- 17. Were status boards and displays updated accurately and timely?
- 18. Was the JNC staff aware of changes in emergency classification?
- 19. Did the rumor control staff respond promptly and accurately to calls?
- 20. Were measures taken to centrol the spread of rumors that threaten to have an adverse effect on adherence to protective actions?
- 21. Were support functions such as reg)stration and security performed effectivelyi
- 22. Was habitability initiated and maintained in accordance with EAP-14.6?
- 23. Did the JNC experience any emergency plan equipment failures?
If yes, explain:
- 24. Were communications prefaced with "This is a Drill?"
- 25. Was shift turnover demonstrated?
- 26. Were all the objectives met? i If not, explain:
)
Rev. No. 5 Page 41 of SAP-6
FORM SAP-6.2 (~Y OBSERVER EVALUATION FORM '( (JNC CONTINUED) i
- 27. Miscellaneous Comments and Notes:
O . O Rev. No. 5 Page 42 of SAP-6
FORM SAP-6.2 OBSERVER EVALUATION FORM { , DATE: LOCATION: ERC OBSERVER: CONTROLLER: YES NO
- 1. Was the ERC activated in a timely manner? I i
- a. Time ERC was called for activation
- b. Time ERC declared operational
- 2. Was the ERC set-up in accordance with procedures?
- 3. Did the Recovery Manager demonstrato command and control?
- 4. Was notification received in accordance with JAF procedure EAP-1.1?
- 5. Were communications prefaced with "This is a drill?"
- 6. Log the following times for event classification and notifications (if applicable):
O Jlass. RECS Plant Staff NRC EAL Time Time Time Time NUE ALERT - SAE GE '
- 7. Was staff familiar with their equipment and responsibilities?
- 8. Was the staffing level adequate?
- 9. Were periodic briefings held on plant status?
- 10. Was staff aware of changes in emergency classification?
- 11. Were status boards updated in a timely manner?
- 12. Were logs properly maintained by key personnel?
- 13. Was shift turnover demonstrated? .
() 14. Was data flow between facilities accurate, timely and complete? Rev. No. 5 Page 43 of SAP-6
FORM SAP-6.2 ODBERVER EVALUATION FORM k (ERC CONTINUED) YES NO
- 15. Did-the ERC experience any emergency plan equipment failures?
If yes, what were the failures and how was the problem addressed:
- 16. Were all objectives met?
If not, explain: , O 17. Miscellaneous Comments and Notes: t i l l O Rev. No. 5 Page 44 of SAP-6
FORM SAP-6.2 OBSERVER EVALUATION FORM (' (ERC CONTINUED)
- 17. Miscellaneous Comments and Notes (continued):
t i l l l Rev. No. 5 Page 45 of SAP-6 l i I}}