Text

Emergency Preparedness Exercise on 871117
	ML20149E404
Person / Time
Site:	Brunswick
Issue date:	11/17/1987
From:	; CAROLINA POWER & LIGHT CO.
To:	;
References
	NUDOCS 8802110036
	Download: ML20149E404 (192)
	v • d • e

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s BSEP ENERGENCY EXERCISE HOVEMBER 17, 1987

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SCENARIO CHANGES

1. Time line-1145 Normal injection path "not" nvniinble for SLC.

2. Time line flowchnet-1145 SLC discharge valve C41-F005 lenking.

3. Additional inforention for message N1-seismic chnet rendout.

4. Message N2-drop the word contigency, this message is to be given in the Control Room.

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5. Nessage N7A-change time from 1035 to 1005.

6. .SPDS datn sheet, 1100-change line 7 from "Y" to "N".

7 SPDS datn sheet, 1115-HAY chnnge from "Y" to "N" if Control Room doesn't A get to this point in the EOP by 1115.

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8. SPDS dntn, line 26-mnin stock gas monitor, sheets:

0830-5.5 E+1 0845-4.0 E+1 0900-6.5 E+1

) 0915-6.5 E+1 3

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0930 through 1045-7.0 E+1 1100 through 1245-5.0 E+1 These chnnges were necessney to mnke end dnta consistnnt between the mnin Stock gns monitor and the SJAEs.

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I i PW FOR BRUNSfICK STEAM ELECTRIC PLANT stEnogNCY EXERCISE l i NOVINBER 17, 1987 i

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CAROLINA POIfER & LIGHT COMPANY PLAN FOR BRUN5 DICE STEAM ELECTRIC PLANT EMERGENCY EXERCISE 50VEMBER 17. 1987 .

TABLE OF CONTENTS PAGE I. M I SS IO N AN D PU R POSE O F EX E RC I S E . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 l

l II. SCOPE AND OBJECTIVES A. Scope ........................................................ 1 B. O bj e c t i v e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1

)

l III. SITUATION AND ASSUMPTIONS ;

l A. Exercise Dates ............................................... 3 i B. Exercise Locations / Facilities ................................ 4 1 IV. CONCEPTS AND CONDUCT OF THE EXERCISE A. Exercise Scenario ............................................ 5 ,

7s B. BSEP Exercise Organization Activities ........................ 6

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C. Evaluation and Critique ...................................... 7 i s D. Exercise Exempt Personnel .................................... 8 l E. General Guidance for the Conduct of the Exercise.............. 8 V. COMMAND, CONTROL. AND COMMUNICATIONS A. Site Emergency Coordinator (SEC ) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 B. Co mm un i c a t i o ns . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 C. Records ...................................................... 10 D. Exercise Message Card ........................................ 10 l E. Time ......................................................... 11 F. Message Preamble and Close ................................... 11

0. Ex e r c i s e Sc 0 pe . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . v . . . . . . 10 VI. ATTACHMENTS Attachment 1 ................... Instructions for Controllers and Evacuators Attachment 2 ................... Instructions and Rules for Players i

Attachment 3.................... Exercise Control / Evaluation Organization l Attachment 4.................... Scenario and Time Schedule of Simulated Plant Conditions f[N.

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Attachment 5.................... Facility Map (87-2HRG/poj)

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( CANDLINA POWER & LIGHT COMPANY s/m

)

PLAN FOR BRUN3 FICK STEAM ELECTRIC PLANT DGtRGENCY EXERCISE Bovember 17. 1987 I. MISSION AND PURPOSE OF EXERCISE To activate and evaluate major portions of emergency response capabilities and other elements of the CP&L Brunswick Steam Electric Plant Plan, associated implementing procedures, and the CP&L Corporate Emergency _ Plans in accordance with Nuclear Regulatory Commission (NRC)

Regulation 10 CFR 50.47(b).

II. SCOPE AND OBJECTIVES A. Scope b

A simulated accident at the Brunswick Steam Electric Plant (BSEP) which could escalate to a general emergency and will involve

. planned response and recovery actions to include: emergency classification; notification of off-site organizations and plant personnel; actions to correct the emergency conditions; and initiation of accident assessment and protective actions as necessary to cope with the accident. The exercise will simulate an

/ .h emergency that results in off-site radiological releases which

\ s_,jl require responses by state and local government personnel.

B. Objectives

1. Demonstrate the ability of on-site personnel to effectively utilize the emergency action level scheme.

2. Demonstrate the ability of on-site personnel to classify the emergency based on existing plant conditions.

3. Demonstrate the adequacy of the control room staff in the ability to perform control and accident mitigation activities along with accident assessment.

4 Demonstrate the adequacy of procedures for alerting, notifying, and mobilizing emergency response' personnel (some individuals will be pre-staged within the local area).

5. Demonstrate that communications capabilitieu exist to accomplish notification of off-site agencies.

6. Demonstrate the ability to notify off-site authorities within 15 minutes of the emergency classification.

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[ 7. Demonstrate the adequacy of the information provided in the initial notification, as well as follow-up notifications to the State and Counties (state and local government organizations will not participate).

(87-2HRG/poj)

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's / II. SCOPE AND OBJECTIVES (Cont'd)

8. Demonstrate the ability of on-site personnel to formulate protective action recommendations based on pre-established criteria.

9. Demonstrate at,ility of personnel to activate the TSC, OSC, EOF, and Plant Media Center as described in the emergency plan and procedures.

10. Demonstrate transfer of responsibility between emergency response facilities as described in the plan and procedures.

11. Demonstrate the ability to communicate between emergency i response facilities.

12. Demonstrate the adequacy of the Operations Support Center in providing manpower support and coordination.

13. Demonstrate the adequacy of the Technical Support Center in ,

providing accident assessment and mitigation, dose assessment, r and communication / notification activities.

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( Demonstrate the adequacy of the EOF in coordinating off-site

\ utility activities.

15. Demonstrate recordkeeping requirements as described in the plan and procedures. ,

16. Demonstrate that status boards are maintained and updated.

17. Demonstrate the ability to provide adequate radiation protection services such as dosimetry and personnel '

monitoring. :

18. Demonstrate the capability to perform radiological monitoring activities and assessments.

19. Demonstrate the ability to support the radiological assessment process while maintaining personnel radiation exposure as-low- !

i as-reasonably achievable ( ALARA). j 1

20. Demonstrate the assessment of radiological consequences of the f l accident and of any releases of radioactive material to the

! environment. ;

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l 21. Demonstrate the activation, operation, and reporting of the >

field monitoring teams within and beyond the site boundary.

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22. Demonstrate the ability to perform on-site accountability l within 30 minutes from the time of the order for ;

accountability. ,

(87-2HRG/poj) l

II. SCOPE AND OBJECTIVES (Cont'd)

23. Demonstrate the ability to providh safe on-site access to off -

site emergency svrvices and/or support personnel (normal security access procedures vill be sdhered to).

24 Demonstrate proper procedures for the fire brigade response to the type of fire chosen for the exercise.

25. Demonstrate the adequacy of the interface between off-site fire support personnel and the plant fire brigade.

26. Demonstrate the capability'to produce public information releases.

i III. SITUATION AND ASSUMPTIONS A. Exercise Dates

1. Submit exercise scope, and objectives to NRC:

Exercise - 75 days (September 3, 1987).

2. Submit exercise scenario to NRC:

Exercise 45 days (October 2, 1987).

3. Final Evaluator Meeting:

Exercise - November 16,1987; 1400 hours0.0162 days 0.389 hours 0.00231 weeks 5.327e-4 months l TSC/ EOF Training Building, Room No. 122.

4 Exercisa:

November 17,1987; 0800 to 1600 hours0.0185 days 0.444 hours 0.00265 weeks 6.088e-4 months

5. Evaluator Group Meeting:

November 17,1987; 1600 to 1800 hours0.0208 days 0.5 hours 0.00298 weeks 6.849e-4 months

6. Lead Evaluator Meeting:

November 17,1987; 1800 to 2000 hours0.0231 days 0.556 hours 0.00331 weeks 7.61e-4 months

7. Post Exercise Critique Report to Players:

November 18,1987; 1100 hours0.0127 days 0.306 hours 0.00182 weeks 4.1855e-4 months 8 NRC Exit /Cr.itique November 18,1987; 1130 hours0.0131 days 0.314 hours 0.00187 weeks 4.29965e-4 months (87-2HR0/poj )

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) III. SITUATION AND ASSUMPTIONS (Cont'd)

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B. Exercise Locations / Facilities

1. Brunswick Plant, Southport. North Carolina

a. Control Room (see Attachment #5). Function is to provide plant control and initial dA"ection of all plant related emergency operations.

b. Operations Support Center (OSC) (see Attachment #5). The OSC will be located in the Service Building. The function of the OSC is to provide an area for assembly and briefing of off-shift and other support personnel.

c. Technical Support Center (TSC) (see At tachment #5). The Technical Support Center is located it. the Training Building and is to provide an assembly location for technical personnel who provide engineering and management support of plant activities following an accident; direction and coordination of overall plant emergency activities; direction and coordination of field, mobile, radiological monitoring teams prior to EOF activation; cn-site dose projections; off-site dose

,s projections prior to EOF activation; display of status of

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plant parameters; and provide an emergency reference s

,,,) collection of selected engineering and plant documents.

The TSC is activated and emergency functions performed in accordance with the provisions of the plant radiological emergency response plan and procedures.

The TSC will perform the Emergency Operations Facility (EOF) functions until the EOF is operational. In addition to the normal plant communications system, redundant emergency communications facilities in the TSC provide telephone contact with required sgencies and other response centers by use of the Corporate Emergency Communications System.

d. Plant Media Center. Located behind the Information/ Visitor Center at the Brunswick Site. The Center will be staffed by CP&L Site Public Infoqmation Coordinator and other Corporate Public Information personnel. Work stations and a briefing room are available at the Center for CP&L personnel to assist the media representatives by provide Ozsediate access to accurate emergency related information and providing equipment for document reproduction and for communications. Media participation will be simulated.

/ ) e. Emergency Operations Facility (EOF) (see Attachment

( ,, / #5). The EOF is located in the plant Training Building. When activated, the EOF is managed by the Emergency Response Manager. He will have a staff to (87-2RR0/;cj )

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(V III. SITUATION AND ASSUMPTIONS (Cont'd) provide support in: Technical Analysis, Adttinistration and Logistics, Radiological Control, and Baergency Communications. '

f. Meteorology Tower. Located north of the TSC on the plant site. Measures wind at 11.46 meters (38 feet) and 104.55 meters (345 feet) above the ground.

Meteorology and Weather .

1. Start of Exercise: As advised by Controller i

2. Subsequent: As advised by Controller 3 Corporate Emergency Operations Center (CEOC), Raleigh, '

The Corporate Emergency Operations Center is located on the lith floor in the Center Plaza Building, Raleigh, NC.

h. Miscellaneous Facilities (1) Brunsw'ick Counjy Airport, 25-foot elevation, 3200-foot runway, in located approximately 5 miles via Route 133 from the BSEP. Phone (919) 457-6577. ;

(2) Motels Sea Captain Hotel, Southport, NC (919) 457-5263.

1 Wayward Wynds, Yaupon Beach (919) 278-5975.

Oak Island Inn, Yaupon Eeach (919) 278-5442 .

Ocean Crest Motel, Long Beach (919) 278-5212 ,

l Best Western Carolinian, Wilmington l

(919) 763-4653 i l

j IV. CONCEPTS AND CONDUCT OF THE EXERCISE j l

A. Exercise Scenario The exercise will simulate an off-normal incident at BSEP that may i escalate to a General Emergency and require: accident recognition i and classification; assessment of on-site etnd off-site radiological ;

consequences; alerting, notification, and mobilization of various organizations and personnel; in-plant corrective actions; ;

y activation and use of emergency facilities and equipment; effective ,

use of communications; preparation of reports, messages, and :

recards; taking on-site protective action, reco:stending off-site (87-2HRO/poj) l l

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( ) protective action; and maintaining public relations. During the

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course of the exerciee, there will also arise incidents that

require deployment of CP&L radiological monitoring teams for off-site monitoring. The scenario and time schedule of simulated plant conditions is contained in Attachment 4 Only the NRC and CP&L Controllers / Evaluators will receive the scenario.

B. Brunswick Exercise Organization Activities The exercise organization will consist of players; the Corporate Exercise Director; Lead Controller; the Controllers; the Chief Evaluator; the Evaluators; and Observers as follows:

1. The CP&L Players include all plant and other CP&L personnel assigned to perform functions of the emergency positions as described in Section 3 of the Plant Emergency Procedures (PEP). The success of the exercise is largely dependent upon player reaction, player knowledge of the Radiological Emergency Response Plan and Procedures, and an understanding of the Exercise Plan and objectives. Some situations affecting player action or reaction may exist at the time the exercise play begins, however, most will be introduced through the vehicle of Controller Exercise Message Cards and messages generated by players as a result of following the procedures

, -~s for the particular emergency activity they perform. Players,

( ) therefore, are responsible for initiating actions and/or

\ _ ,/ messages during the exercise according to the procedures, ,

responsibilities, and tasks outlined for their particular function in the Plant Radiological Emergency Response Plan and Procedures and in the Exercise Plan and objectives. Certain inconsistencies (such as plume width, release duration, technical reason for the simulated release, etc. ) may be identified by players. These may be intentional and required to frovide an exercise basis which tests the plant and corporate capabilities to the maximum extent feasible in a limited time frame. With the exception of the already cited and potential inconsistencies, the internal operations of the emergency response Tscilities will be identical with their intended operation in a real emergency. Players will be identified by wearing a WHITE ribbon, arm band or ID badge.

2. The Corporate EP Exercise Director will be responsible for overall exercise preparation; to oversee conduct of the exercise; to arrange preparation at the conclusion of the exercise for a consolidated evaluation and critique report; and to prepare and follow-up on an itemized list of corrective actions recommended as a result of evaluation and critique.

3. Lead Controller will be responsible for exercise nreparation as directed by the Corporate Exercise Director. This will

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include development of the exercise plan, the scenario and the centro 11er input messages.

_, During the exercise the Lead (87-2KRG/poj) l I

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) Controller will coordinate controller input as necessary to

'x_- initiate player response and keep the exerciae action moving according co the scenario and exercise objectives.

4 The Controllers will deliver "Exercise Message Cards" to designated exercise players at various times ard places during the exercise; inject or deliver additional messages, signs, etc., as may be required to initiate the appropriate player response and keep the exercise action moving accon31ng to the scenario and exercise objectives; observe the exercise at their assigned locations; prepare critique notes; and submit recommendations on corrective actions to the Chief Exercise Evaluator prior to the scheduled critique. Controllers will be identified by wearing a RED ribbon, arm band, or ID badge.

5. Chief Evaluator and Evaluators are CP&L or other qualified personnel who are assigned to observe and judge the effectiveness of selected organizations, personnel, fanctions, and/or activities of the plant radiological emergency response plan and procedures. Selection of evaluators is based on their expertise in, or their qualifications to evaluato the activity or area assigned. For example, health physics activities will be evaluated by qualified health physic.s personnel. When feasible, persons designated as Controllers

-x for a given function will also be assigned as evaluators of

[ ) that function. Evaluators will record their observations, and is_,/ provide recommendations on corrective actions to the Chief Exercise Evaluator prior to the scheduled critique. They will critique exercise performance on the basis of standards or requirements contained in the Plant Radiological Emergency Response Plan and Procedures; in the "Actions Expected" portion of the Exercise Message Cards and in the plan for the exercise. They will take steps whenever possible to collect data on the time and motion aspects of the activity observed for post exercise use in designing system improvements.

Evaluators will bo identified by wearing a BLUE ribbon, arm band, or ID badge. When an Evaluator is serving in a Controller role, he will wear a RED ribbon, arm band, or ID badge.

6. Observers from various CP&L components and from other organizations may be authorized on a limited basis to participate in the exercise solely for the purpose of observing exercise activity.

C. Evaluation and Critique

1. The exercise will be evaluated by Evaluators who will be assigned to key locations and response activities where they 7 s will record their observations. Following the exercise,

( Evaluators will present their findings at critiques as

( ) , scheduled in Section III. A of this plan.

-7 (87-2HRG/poj)

( ) 2. The following facilities will be evaluated in addition to the

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Plant Emergency Plan and Procedures:

a. Control Room.

b. Operational Support Center.

c. Technical Support Center.

d. Plant Media Center.

e. Emergency Operations Facility.

f. Corporate Emergency Operations Center.

g. Corporate Media Center

3. The following activities will be evaluated:

a. Accident r6 cognition, classification, and assessment.

b. Assessment of on-site and off-site radiological consequences.

c. Alerting, notification and mobilization activities.

d. In plant corrective actions.

e. Activation and use of emergency facilities and equipment.

f. Use of communications equipment and procedures.

s. Preparation of reports, messages, and records,

h. Protective actions.

i. Public information.

j. On-site and off-site radiological monitoring.

(p) 4 Evaluations will be made on the basis of exercise objectives; N__/ standards or requirements contained in the Plant. Radiological Emergency Response Plan and implementing procedures; and notations in the "Actions Expected" portion of the Exercise Message Cards for the area evaluated.

5. Any deficiency in the Plant Radiological Emergency Response Plan and implementing procedures, tralising, etc., that is identified through the critique process shall be documented by the Chief Evaluator and corrected by the organizations and individuals who have responsibility for the areas identified. Management controls shall be established to ensure that corrective actions are taken as necessary.

D. Exercise Exempt Personnel Some plant personnel must be exempt from exercise participation in order to maintain vital plant functions such as security, normal operations, chemist ry, etc.

E. General Guidance for the Conduct of the Exercise

1. S_imulating i Emergency Actions f ~s Since exercises are intended to demonstrate actual

( ) capabilities as realistically as possible, participants should

\_/ s act as they would during a real emergency. Wherever possible, actione should be carried out. Only when it is not feasible to perform an action should it be simulated. Any orders given (87-2HR0/pej)

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( ) that for any reason cannot or should not actually be performed N_/ should begin with the word "Simulate." For example, the order to put out a fire that is being hypothesized would state:

"Simulate discharging the fire extinguisher." Where such actions are being taken, it is suggested that participants inform any controller / evaluators in the ares of what action really would be taken had the emergency been real.

2. Avoiding Violation of Laws Intentional violation of laws is not justifiable during any exercise. To implecent 1his guideline, the following actions must be taken:

a. All evaluators and potential exercise participants must be specifically informed of the need to avoid intentional violation of all federal, state, and local laws, regulations, ordinances, statutes, and other legal restrictions.

b. Exercise participants will not direct illegal actions being taken by other exercise participants or members of the general public.

, ~s o. Exercise participants will not intentionally take illegal

( ) actions when being called out to participate in an

( /s, exercise. Specifically, local traffic laws such as speed limits will be observed.

3. Avoiding Personnel and Property Endangerment Participants and evaluators will be instructed to avoid endangering property (public or private), other personnel responding to the exercise, members of the general public, animals, and the environment.

4 Actions to Minimize Public Inconvenience It is not the intent, nor is it desirable or feasible, to effectively train or test the public response during the conduct of radiological emergency exercises. Public inconvenience is to be minimized.

The actions of federal, state, and county agencies and nuclear power plant operators receive continuous public notice and i

scrutiny; therefore, the conduct of an exercise could arouse public concern that an actual emergency is occurring. It is important that conversations that can be monitored by the public (radio, loudspeakers, etc.) be prefaced and conclude with the words, "This is an exercise message."

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(87-2HRG/poj)

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-(x_ /) 5. Maintaining Emergency Readiness l

During the performance of an exercise the ability to ' recognize a real emergency, terminate the exercise, and respond to the new situation must be maintained. Therefore, the exercise scenario and actions of participants will not include any actions which seriously degrade the condition of systems, equipment or supplies, or affect the detection, assessment, or response capability to radiological or other emergencies.

Actions taken by the participants will also avoid actually reducing plant or public safety. The potential for creating real radiological or other emergencies will be specifically avoided.

If a real emergency occurs during the exerciso, requiring the actions of Company personnel, then the exercise will be terminated by the Lead Controller or the Emergency Exercise Director in consultation with appropriate plant management.

All messa6es abcut the real events will be clearly identified as such. For example, precede a peak message with:

"This is NOT, repeat NOT an exercise message."

w V. COMMAND, CONTROL, AND COMMUNICATIONS

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\s_ I A. Site Esq;poncy Coordinator (SEC) s The SEC has immediate and unilateral authority to act on behalf of the Company to manage and direct all on-site emergency operations involving the facility. During the exercise, he ,will have responsibility also for the simulated emergency exercise operations. The SEC will be located in the Control ' doom et the beginning of the exercise and will relocate to the TFC upon activation of the TSC. .

B. Communications Communication equipment and procedures are described in Plant Emergency Procedures (PEP). The telephone will be the primary means of communications.

s C. Records , ,,

BSEP Emergency Procedures require that plant Aersonriel responsible for maintaining records during an emergency anall provide a copy of those records to the Emerge.ncy Preparedness Specialist following an emergency or emergency exercise. ' ~-

D. Exercise Message Card t . ,

The "Exercise Message Cards" are prepared by' the exerciso drill .

planners / controller prior.to the exercise to satisfy the requirements of the exercise' scenario. The purpose of the

., (87-2HFG/poj)

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,- I O) g s_ / l completed fo'rm is to initiate the appropriate exercise player -

response and to keep the exercise action moving according to the scenario and er.ercise objectives. The messages that are delivered to players during the play of the exercise should allow "free play," i.e., should not tell the players what should be done.

E. . Time

1. All CP&L in-plant exercise participants will report time of incidents, messages, etc., in accordance with time based on the Control Room clocks.

2. Local 24-hour clock time will be used to reference time in all reports and communications.

F. Message Preamble and Close The words "THIS IS AN EXERCISE MESSAGE" should be used at the beginning and end of each message.

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(87-2HRG/pcj)

_ _ ___. ,_. _ _ , _ _ _ _ . _ _ _ . . . . _ , _ _ . __ . - - - . . _ _ . - _ . , _ . . - . - . _ _ . . . - _ . ~ .--

Attatheent 1 (g) INSTRUCTIONS FOR CONTROLLERS AND EVALUATORS

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1. Personnel are assigned as controllers or evaluators at all key function areas to monitor and control the exercise. In addition, they will accompany radiological monitoring teams, plant health physics personnel, and maintenance repair / rescue teams.

2. The in-plant controllers will be coordinated by the Exercise Lead Controller located in the TSC (Ext. 8). He/she will be responsible for the overall conduct of the exercise scenario. If unable to reach the Exercise Lead Controller, contact the OSC Lead Controller (Ext. #).

Field controllers should contact the Environmental Monitoring Lead Controller in the EOF (Ext. 8) regarding coordination problems or questions.

3 Message forms and simulated Control Room data will be used to initiate, modify, and complete the events comprising the overall scenario.

Selected controllers will use the message forms to place the scenario events in effect and to trigger responses from the involved emergency response organizations. Each controller will have copies of the messages controlling the portion of the exercise scenario for which he/she is responsible.

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( Two kinds of messages will be used:

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Controll'ing Messages used as a primary means of implementing scenario events by announcing or placing an event in effect by hypothesizing conditions resulting from previous actions.

Contingency Messages used at the discretion of the controllers with the approval of the Exercise Lead Controller in order to maintain the scenario plan continuity or schedule.

Controlling messages will be presented to the designated exercise participant at the time specified in the event schedule. The $'ntroller should follow up with an explanation of the message and answer questions to ensure that the participant understands the message.

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Controllers will not initially provide information to the participants regarding scenario development or resolution of problem areas encountered. The participants are expected to obtain information through their own organization and exercise their own judgment in determining response actions and resolving problems, b

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Phone numbers will be promulgated at the Controller / Evaluator briefing preceeding the exercise.

(87-2RRG/poj)

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) 4. Note that the scenario events are hypothetical. Any portions of the scenario depicting plant system operational transients are simulated s

events. No Control Room actions, or reactions involving operation of plant systems or affecting generation capability, will be initiated.

All exercise scenario messages will be previewed by and ended with the words "THIS IS AN EXERCISE." Controllers stationed at areas vital to maintaining generating capability should be especially aware and take extra precautions in issuing messages or giving instructions regarding the scenario events.

5. Required controllers will have the time-related plant and radiological parameters of the exercise scenario. This information should be issued upon request to the appropriate exercise participants by either the Control Room controller or controllers accompanying the radiological monitoring field teams.

6. Some exercise participants may insist that certain parts of the scenario are unrealistic. The controllers and evaluators have the authority, with the approval from the lead controllers, to clarify any questions regarding scenario content. In some cases, it may be necessary to exercise "controller's prerogative" and say, "This is due to exercise requirements" to preserve the continuity and objective of the exercise.

7. Prior to ocamencement, all telecommunications should be tested to ensure s satisfactory communications between the lead controllers and all other

[ controllers. '

b 8. Controllers will commence their assignments at assembly locations for players that they are to observe or as directed by the lead controllers.

9. Players are not allowed to introduce problems or events into the exercise or its scenario.

CONTROLLER'S AND EVALUATOR'S RULES 1.- Know the overall Controller's Organization.

2. Identify the players by name and function.

3. Identify yourself at all times to all players. Wear identification as provided by CP&L.

4. Identify the phone (or radio for field teams) you will use to maintain communications with lead controllers.

5. Position yourself to maximize your effectiveness in issuing messages and obser' ring the players.

-s 5. Be sure you understand the player's scenario script and the master scenario.

7. Keep the play on schedule by checking your script.

(87-2RRG/pcj)

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( ) 8. Issue the message on tims. Make sure the players understand it.

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9. Remember to call the Exercise Lead Controller to report on status of players' actions if off schedule or if in doubt about what to do. Call for advice if players depart significantly from the scenario script.

10. Allow the players reasonable flexibility to perform their functions and demonstrate their skill, knowledge, and initiative.

11. Identify the federal evaluators (s). Make sure they are reasonably aware of all your actions and those of the players.

12. Make notes on good and bad points of players' actions, the strengths and weaknesses, and areas for improvements.

13 Attend the post-exercise critique session to provide your comments and recommendations to the Lead Controller.

14. Identify the players' leaders. Work with them as appropriate.

15. .If a real emergency occurs and this affects the players, call off your portion of the exercise, and notify the Exercise Lead Controller immediately.

fs 16. Be at your post at least 20 minutes prior to any player action

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commencement. Set yourself up.

The federal evaluators will not issue "surprise" messages or direct "surprise" actions at the players. They must work through the Exercise Lead Controller. This is essential for the success of the exercise.

18. Controllers and federal evaluators do not have to follow the radiation exposure control practices appropriate for the simulated radiation levels. However, the players must follow the radiation protection rules. Controllers and evaluators will be exempt from accountability and have access to all areas.

19. Do not issue contingency messages without clearance from the Exercise Lead Controller.

DON'Ts

1. Don't leave your post at key times.

2. Don't prompt the players to take action.

3 Don't coach the players.

4. Don't criticize the players' actions during the play.

O 5. Don't forget to call the lead controllers to seek advice or help as necessary.

(87-2HRG/poj)

r 6. Don't ' allow the media /other external influences to distract the players. No interviews with' players are allowed.

7.- Don't allow simulation when equipment and facilities are available ,

except for causing flow discharge of fire extinguishers, etc. i

. NOTE i

All participants will comply with radiation exposure control practices for actual conditions existing at the station at the time of the exercise. - i F

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Attachment 2

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( INSTRUCTIONS AND RULES FOR PLAYERS w

All players (at least the leaders of the player groups) must read and follow the rules given below. This is important to the successful demonstration of emergency response capabilities.

1. Identify your controller by his identification badge. These controllers are also evaluators.

2. NRC/ FEMA (federal agencies) evaluators are also present. Identify them by their identification badges. They are here to judge players' performance and approve the emergency plan.

3 Visitors may be present. Identify them by their identification badges.

4. Identify yourself by.name and function to the exercise controllers and the NRC/ FEMA evaluators. This will be helpful.

5. Play out all actions, as much as possible, in accordance with your emergency plan and procedures as if it were a real emergency.

Unless authorized by the controller, you should not simulate your .

acticns. If authorized to simulate an action, tell the evaluator s how and when you would actually do them.

\s_s 6. Periodically speak out loud, identifying your key actions and decisions to the controller and federal evaluators. This may seem artificial, but it will assist in the evaluation process and is to your benefj;.

7. If you are in doubt, ask your controller for clarification. The controller will not prompt or coach you.

8. The controller periodically will issue messages or instructions designed to initiate response actions. You must accept these messages immediately. They are essential to your successful '

performance.

9. If the controller intervenes with your play, it is for a good reason. Obey your controller's directions at all times. This is essential to the overall success of the exercise.

10. If you disagree with your controller, you can ask him to reconsider or consult with the controller's command center as time permits.

You must, however, accept his/her word as final and proceed.

11. Respond to the controller's questions.

s 12. You must not accept any message / instruction from the federal evaluators. If they want to initiate actions, test you abilities, s or give you "surprises," they must work through your controller.

This is essential to the overall success of the exercise.

~

(87-2HR0/poj)

,m

[ ) 13. You must play as if radiation levels actually are present, in

\_/

s accordance with the information you have received. This will require that .you wear radiation dosimeters, anti-contamination clothing, observe good radiation protection practices, and be aware of and minimize your radiation exposure. Identify the individuals in your emergency response organization responsible for informing you of these items. Follow their instructions.

14. The controllers and federal evaluators are exempt from acting as if radiation levels from the emergency exercise are present. Do not let them confuse you or cause. you to act unwisely.

15. If you are entering normal nuclear station radiation areas, observe all rules and procedures. No one (even the controller and federal evaluators) is exempt from radiological practices and procedures required by actual conditions.

NOTE: DO NOT ENTER HIGH RADIATION AREAS IN THE PLANT WITHOUT AUTHORIZATION FROM THE CONTROLLER. FOLLOW ALARA PRINCIPLES.

16. Demonstrate knowledge of your emergency plan, emergency operations, and procedures.

17. Utilize status boards, log book, three-part interoffice memos, n etc., as much as possible to document and record your actions,

[ $

instructions, and report's to your co-players. This is very

\s_g/ ,

important. Remember, "Put it in writing."

18. Do not enter into conversations with the visitors.

19. You may answer questions directed to you by federal evaluators. If the question is misdirected to you or you do not know the answer, refer them to your lead player or the controller.

20. Keep a list of items you feel will improve your plans and ;

procedures. Provide this to your lead player. Lead players will '

ensure these are considered. If necessary, they will identify them to the controller. Remember one of the main purposes of the exercise is for you, the players, to assure yourself that you are prepared adequately. Areas for improvement or lessons learned, when identified, will improve your overall emergency planning and prepare dness.

21. A critique of the exercise will occur after the exercise is terminated. Provide your input to your lead player or the controller. This will help in the overall evaluation the controller will present at the critique.

(87-2HRG/poj )

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(v) Exercise Basics Date: /Vdu. /2 /98'J Begin Time: O[@O End Time: /[dO Location (s): hvA/Su / C/C 1 Announced Full Scale Max. EAL Site Emergency Unannounced F Small Scale 1 General Emergency l

l Extent of Participation Notification Activation I e i Participants 3 ;A U 0 m e e I I j 3 o .4S 0 3 $ 3 $ E Y 3 e a t a ; a t ; a u e in E ; 8 a E a % t3 L 1 x e 3 a 8 8 8 m va a e a it CP&L Site l X X X X 'X 'X SY>

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(87-3RR0/pcj)

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INITIAL CONDITIONS Brunswick Unit 1 ,

Unit 1 is in cold shutdown.

Brunswick Unit 2 Unit 2.is at 100% power. The plant is stabh and 2C CSW pump is out of service due to motor failure.

Due to a bad modem at the BSEP Meteorological Tower, access to weather data from the tower is not possible. Repairs to be made by 1500 hours0.0174 days 0.417 hours 0.00248 weeks 5.7075e-4 months on November 17, 1987.

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\J NARRATIVE SU)f!ARY

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LThis ' exercise 515 initiated by?iit seismic event 'whichIdamages-reactor 5.Nternals?

~

resulting in blockage of coolant flow to.a small- percentage of, fuel .

fassemblies. This results in fuel element heat.up and. ultimate fuel cladding N f

failure. The'mainTsteam line radiation monitors ~will:startfshowing an d

~

increase approximately one. hour.into the event.;

The diesel generator l fuel' oil storage tank willt also; be dasaged b[ th6' seismic $/

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event. .Approximately:one~ hour and forty-five minutes;into the. exercise,La -

fire willLbe reported at this ' tank. f 0ff-site assistance will be esquired for the fire.

The fuel cladding damage will result in main steam line isolation valve closure and reactor scram signals three hours into the exercise. One main steam line will fail to isolate and all control rods will not fully insert.

There will be some increase in radioactivity within the turbine building due to the continued steam flow to the condenser. There will be no off-site radiological consequences as a result of this event. Reactor power will be approximately 10%. The Standby Liquid Control System (SLC) will be initiated to shutdown the reactor.

At three hours and forty-five minutes into the event, it will be discovered

.- that the SLC discharge valve has failed. Activities required for a repair (m)

\j entry will be initiated at this time.

The main steam line that failed to isolate will be closed four hours into the exercise. The reactor will not be shutdown at this time due to failure of all rods to insert and failure of the SLC System. This will result in using SRV's to reject heat from the reactor to the suppression pool and containment heat up.

All control rods will be~ fully inserted five hours into the exercise. 7 Simultaneously with the~ control rod insertion, a break will occur in .the scram; discharge volume header. This results in releasing reactor coolant, directlyf into secondary containment with a release path from the main stack via the' Standby Gas Treatment System.' The Environmental Monitoring Team will provide off site radiological assessment of this release. The exercise will be terminated when the scram discharge volume header is isolated and recovery actions are initiated.

(87-4HRG/poj)

i 7/

UNUSUAL EVENT x_

0800 Seismic event annunciator alarms, seismic monitoring confirms earthquake.

0900 Main steam line high rad. annunciator is alarming for Unit 2. This is giving an early indication of fuel damage in Unit 2.

0945 A.O. reports a fire at Fuel Oil Storage Tank. This event is a result of the scismic event and will require assistance from off-site fire department.

ALERT 1045 Fire at Fuel Oil Storage Tank has been extinguished.

1100 The following conditions occur:

1. Main steam line Hi Hi Rad trip.

2.. B main steam line MSIV's do not close.

3. Reactor power remains at 10% with some control rods not inserted.

The Control Room Operator should begin iajecting the Standby Liquid Control s System (SLC) per E0P-1.

( )

\s_/ 1145 A.O. discovers a large leak between the body and bonnett on the SLC discharge valve (2C41-F005). Normal injection path i av311able for SITE EMERGENCY 1145 Declare site emergency due to a failure to scram and failure of the SLC.

1200 B main steam line MSIV's have been closed.

1215 Initiate repair activities on SLC discharge valve (2C41-F005).

GENERAL EMERGENCY 1300 A.O. reports a break in the south scram discharge volume header.

1305 Release of radioactive material outside secondary containment from the main stack via the Standby Gas Treatment System.

1430 Scram discharge volume header has been isolated. Plans for recovery operation will begin.

(87-4HR0/poj)

BSEP B.MER6ENCY PR.EPAREDNE65 EXERctse N O V E M B E R 17 3 1987 TIM E EMBE FAtLED f:UEL / FAILURE To CLAM Sc. GAM pl6c.44AF6E i%ILURE '540T %%)N osoc

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CEPIP-18 I

Rev. 3

,_ June 1987 CP&L l

EXCRCISE MESSAGE CARD

_ BSEP Plant Message No. 1 Date 11/17/87 Time 0800 MESSAGE FOR: SOS FROM: CONTROLLER MESSAGE / SIMULATED PLANT CONDITIONS: "THIS IS AN EXERCISE-MESSAGE"

1. . Seismic Event Annunciator UA 28 window 6-4.

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ACTIONS EXPECTED:

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1. Enter APP for Seismic Event, perform evaluation.

i 2. Determine magnitude of Event to be .07g.

3. Declare UE.

4. Commence Unit S/D per GP-05 h

FOR CONTROLLER USE ONLY 5

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L 4CEPB 18-22 6

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4-CEPIP- 18 Rev. 3 June 1987 CP&L

\ EXERCISE MESSAGE CARD I

BSEP Plant Message No. 2 Date 11/17/87 Time 0810 4

MESSAGE FOR: Shift Foreman FROM: CONTROLLER (CONTINGENCY)

MESSAGE /SIMULAIED PLANT CONDITIONS: "THIS IS AN EXERCISE MESSAGE" The Corporate Meteorological Center calls you to report earthquake activity of unknown magnitude in the Wilmington area with some damage reported.

1 ACTIONS EXPECTED:

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FOR CONTROLLER USE ONLY 036 /F UNusunt. 69,ur HMS A&f Bf9A) OfCtAMfD Rf 4CEPB 18 22

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Q CP&L EXERCISE MESSAGE CARD BSEP ,

t Plant i Message No. 2a (Contingency) Date 11/17/87 Time 0830 MESSAGE FOR: SOS FROM: CONTROLLER (LEAD) !

MESSAGE / SIMULATED PLANT CONDITIONS: "THIS IS AN EXERCISE MESSAGE" ,

Declare an Unusual Event due to alarm on seismic monitor and confirmation of earthquake. (PEP-02.1 14.1)

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ACTIONS EXPECTED:

Declare Unusual Event !

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FOR CONTROLLER USE ONLY l

s To be used only with approval of the exercise lead controller.

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CEPIP-18 Rev. 3 June 1987 O CP&L EXERCISE MESSAGE CARD BSEP Plant Message No. 3 Date 11/17/87 Time 0900 l

MESSAGE FOR: SOS FROM: CONTROLLER MESSAGE / SIMULATED PLANT CONDITIONS: "THIS IS AN EXERCISE MESSAGE"

1. Main steam line B: HiRad Annunciator is alarming.

ACTIONS EXPECTED:

1. Reduce power per AOP - O Main steam line high radiation.

2. Follow actions of APP for main steam line Hi Rad.

FOR CONTROLLER USE ONLY r.

4CEPB 18 22

i CEPIP-18 Rev. 3 June 1987 ,

CP&L EXERCISE MESSAGE CARD i

BSEP Plant i 4

Message No. Date 11/17/87 Time 0945 t i

MESSAGE FOR: Passerby '

l FROM: CONTROLLER MESSAGE / SIMULATED PLANT CONDITIONS: "THIS IS AN EXERCISE MESSAGE" You observe a large fire burning in the area surrounding the No. 2 Fuel Oil Storage Tank. l l

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l ACTIONS EXPECTED:

. Report fire to the Control Room. !

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! FOR CONTROLLER USE ONLY j If no one is available to receive this message then call it in to the Control Roon. l 2

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4CEPB 18-22 i 4 !

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t Plant i 9 . !

Message No. Date Time !

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MESSAGE FOR:

4 i

FROM: CONTROLLER '

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4 MESSAGE / SIMULATED PLANT CONDITIONS: "THIS IS AN EXERCISE MESSAGE" i

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MESSAGEji,HASBEENDELETED.

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.! ACTIONS EXPECTED:

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CEPIP-18 .

Rev. 3

- June 1987 if, I CP&L k-EXERCISE MESSAGE CARD BSEP Plant Message No. 6 Date 11/17/87 Time 0947 MESSAGE FOR: Controller FROM: SCENARIO WRITING TEAM FOR CONTROLLER USE ONLY:

The Shif t Fire Commander should respond to fire scene in approximately 10 minutes ;

after sounding the fire alarm. The fire brigade should respond within 15 minutes.

The Shif t Fire Commander should establish a command post upwind of the fire scene.

Fire hoses should be deployed, charged and water discharged from hose nozzles.

The use of AFFF should be simulated.

The fire brigade should not be allowed to extinguish the fire until after the ar- '

O rival of the off-site fire department. The off-site fire department should be utilized to their fullest capacity to assist with extinguishment and exposure protection.

As necessary controllers should observe th'at personnel safety is ensured. It may be necessary to temporary secure plant fire brigade activities while awaiting plant access by the off-site fire department. If this is necessary it should be done in a manner which will not adversely impact the demonstration of the off-site fire department /on-site fire brigade interface. ,

The fire should have been extinguished and all objectives demonstrated by ap-proximately 1045 hours0.0121 days 0.29 hours 0.00173 weeks 3.976225e-4 months .

I to 4CEPB 18-22 i

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i CEPIP-18 Rev. 3 June 1987 7- s CP&L (s EXERCISE MESSAGE CARD BSEP l Plant j l

Message No. 7 Date 11/17/87 Time 1030 l 1

l MESSAGE FOR: Media Center (Corporate if Plant not activated) !

FRON: CONTROLLER MESSAGE / SIMULATED PLANT CONDITIONS: "THIS IS AN EXERCISE MESSAGE" To the Plant Media Center Controller: -

You are to call the Media Center and represent yourself as the local media (do not use real names of local media people . .. Tim Smith or Jane Jones should be used). Ask the following questions:

Why has the Southport Fire Department been called to the Plant?

Is there a fire such as occurred at Chernobyl burning there? .

Should residents living near the plant evacuate?

ACTIONS ZXPECTED:

Respond to Questions:

i FOR CONTROLLER USE ONLY n

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4CEPB 18-22

( CP&L EXERCISE MESSAGE CARD 6 BSEP Plant !

i Message No. 7A (Contingency) Date 11/17/87 Time 1035 MESSAGE FOR: Site Emergency Controller FROM: CONTROLLER (LEAD)

MESSAGE / SIMULATED PLANT CONDITIONS: "THIS IS AN EXERCISE MESSAGE" !

4 Based on fire potentially affecting safety-related equipment declare an ALERT. '

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l ACTIONS EXPECTED:

i t Declare Alert and implement appropriate procedures. ';

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) FOR CONTROLLER USE ONLY ,

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To be used only with approval of exercise lead controller.

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CEPIP-18 Rev. 3 June - 1987 CP&L

% EXERCISE MESSAGE CARD BSEP P1 ant s

Message-No. 8 Date 11/17/87 '

Time 1100

. i MESSAGE FOR: SOS FRON: CONTROLLER ,

t MESSAGE / SIMULATED PLANT CONDITIONS: "THIS IS AN EXERCISE MESSAGE"

1. Main Steam Line Hi Hi Rad. Trip.

2. "B"Main Steam Line MSIV's did not close.

3. All Control Rods not full inserted. ,

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i ACTIONS EXFICTED:

1. Follow actions per E0P (Path 1 to Level Power Control). l

2. Attempt to Isolate B main steam line, t i

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4CEPS 18-22 ,

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Y CP&L (j

e EXBCISE MESSAGE CARD Unit 2 P1 art Date //, / 7!d7_ Uma //80 Message No.

MESSAGE FOR: (0990c m (ogygog,4 pg TROM: {tfRtt$5 bfAQ 00MM0LifR

" 3 IS IS AN EXIRCISE MESSAGE" MESSAGE /SI.WLATID PLAST CONDITIONS:

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()SE As 4fC6STA2] to MSC/87-120

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Rev. 3 '

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Plant ,

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Message No. 9 Date 11/17/87 Time 1140 t s

MESSAGE FOR: SOS ~# '

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FRON: CONTROLLER !

't 4 .f MESSAGE / SIMULATED PLANT CONDITIONS: "THIS IS AN EXERCISE MESSAGE" -

, 1 A large leak has occurred at the flanged connectiot of 2-C41-F005 (SLC discharge).

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a ACTIONS EXPECTED: '

1. Declare site emergency due to failure to scram and f allute of SLC.

2. Er.tter LEP-03 (Alternate Boron Injection Method.s). i 1 '

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CEPIP-18 Rev. 3 June 1987 ,

CP&L i EXERCISE MESSAGE CARD BSEp i Plant Message No. 10 Date 11/17/87 Time 1145-1300 MESSAGE FOR: Repair Team i

FROM: CONTROLLER (See below) 3 MESSAGE / SIMULATED PLANT CONDITIONS: "THIS IS AN EXERCISE MESSAGE" ,

1. Clearance has been completed.

i 2. Visual observation indicates a leak between the body and bonnett on ;

i

[ 2 C41-F005 (SLC Discharge). '

4 ,

l ACTIONS EXPECTED:

Initiate repair, i

')

k i

J i

i j FOR CONTROLLER USE ONLY i l

i Give to players upon arrival at valve mock up.

{ *Use Valve rock up.*

4 f

4CEPB 18-22

.. ... . . - . . . . - . . . . . - = - , - _ - - = - - . - . . . . .

I

!' i CP&L i

EXERCISE MESSAGE CARD i

BSEP I Plant Message No.10A (Contir.;ency) Date 11/17/87 Time 1155 !

t HESSAGE FOR: Site Emergency Coordinator ;

i i

FROM: CONTROLLER ~(LEAD) e i

r MESSAGE / SIMULATED PLANT CONDITIONS: "THIS IS AN EXERCISE MESSAGE" 4

Declare Site Emergency due to failure to scram and failure of SLC. ,

i t

r

. t ACTIONS EXPECTED:

i Declare Site Emergency.

I, -

i i

.i 1

1

} FOR CONTROLLER USE ONLY i

Tct bet used only with approval of, exercise lead controller. ,

i >

I i

l i

l I i

1 o b

CEPIP-18 Rev. 3

, June 1987 '

O t

CP&L EXERCISE MESSAGE CARD !

BSEP Plant Message No. 11 Date 11/17/87 Time 1200 .

MESSAGE FOR: SOS '

FROM: CONTROLLER l

i MESSAGE / SIMULATED PLANT CONDITIONS: "THIS IS AN EXERCISE MESSAGE" i

1. "B" Main Steam Line MSIV's have been closed.

e ACTIONS EXPECTED:

1. Recognize that heat from the reactor is being rejected to the i

, suppression pool.

2.

Enter containment control section of E0P-01 i

E I

h ,

! I i

l FOR CONTROLLER USE ONLY k e-l I

1 ;

t MEPS 18-22 l

CEPIP-18 !

R.v. 3 June 1987 l CP&L EXERCISE MESSA0E CARD 4

BSEP i Plant i

Message No. 12 Date 11/17/87 Time 1205 MESSA0E FOR: Emergency Repair Director 4

FROM: CONTROLLER (CONTINGENCY)

MESSA0E/ SIMULATED PLANT CONDITIONS: "THIS IS AN EXERCISE MESSA0E" r

Initiate team to repair valve #2 C41-F005 - (SLC Discharge).

2 ACTIONS EXPECTED:

?

! 1. Damage Control Director notifies OSC to muster a repair team. '

2.

) Notify Control Room to prepare Clearance for repair of #2 C41-F005.

t i

FOR CONTROLLER USE ONLY 4,

Use only if decision has not been made to repair 2 C41-F005 (SLC Discharge). -

o ,

I l

l '

4CEPB

, 18-22 l

i l -

l CEPIP-18 Rev. 3

/m

June 1087 l CP&L '

\s_ EX'ERCISE MESSAGE CARD BSEP Plant Message No. 13 Date 11/17/87 Time 1300 i

MESSAGE FOR: Plant Media Center Controller -

FROM: CONTROLLER (LEAD)

MESSAGE / SIMULATED PLANT CONDITIONS: "THIS IS AN EXERCISE MESSAGE" To the Plant Media Center Controller:

You are to call the Plant Media Center and represent yourself as the local media (do not use real names of local media people ... Tim Smith or Jane Jones should be used). Ask the following questions:

"THIS IS AN EXERCISE MESSAGE."

Who is responsible for ordering an evacuation? By what criteria is the decision made to order an evacuation?

\

Are residents being evacuated at this time? And if so, when will they be allowed to return?

What precautionary measures should residents living beyond evacuation zones observe? ,

What is being done to protect the homes and preperty these evacuees are being forced to leave behind?

What accommodations will be made for residents if their homes are isolated i indefinitely by contamination?

Have there been any traffic accidents during the accident?

Did people really know what to do before all this happened? ;

i

/~~

[ **

, l

\ :

f l

l 4CEPB 18-22 i f

CEPIP-18 Rev. 3 4

June 1987

CP&L.

EXERCISE MESSAGE CARD BSEP Plant ~

Message No. 14 Date 11/17/87 Time 1300 MESSAGE FOR: SOS FROM: CONTROLLER MESSAGE / SIMULATED PLA.'.'T CONDITIONS: "THIS IS AN EXERCISE MESSAGE"

1. All control rods indicated fully inserted.

2. . A0 reports break in south scrata discharge volume header.

i i

e I

eI I

ACTIONS EXPECTED:

1. Exit the Level Power Control Procedure and enter end Path Procedures.

j i 4

I l i

[

l 1 !

i FOR CONTROLLER USE ONLY i

1 i

i !

d .

i !

)

4CEPB 18-22 '

CEPIP-18 Rev. 3 June 1987 Q[s np

) CP&L EXERCISE MESSAGE CARD BSEP Plant Hessage No. 14 Date 11/17/87 Tie:e 1300 MESSAGE FORT SOS FROM: CONTROLLER MESSA0E/ SIMULATED PLANT CONDITIONS: "THIS IS AN EXERCISE MESSAGE"

1. All control rods indicated fully inserted.

2. A0 reports break in south scraw discharge volume header.

Nb *t n Y SS L a n1 ffraylny 5t o y, fo aff pwsi Sc ta m dl1 e kary s A,lsen e A*-c/*s 4

ACTIONS EXPECTED:

1.

Exit the Level Power Control Procedure and enter end Path Procedures.

FOR CONTROLLER USE ONLY m

e 4CEPB 18-22

~ _ ,

? i 1 i i

j< l a t CP&L EXERCISE MESSAGE CARD-

BSEP j

-Plant- ;

i '

1

j. Message No. 14A Date 11/17/87 Time 1320 !

- i

.j MESSAGE FOR: Site Emergency Coordinator i i '

l' ,

i FROM: CONTROLLER (EXERCISE LEAD) I 3

Y t !

l MESSAGE / SIMULATED PLANT CONDITIONS: "1HIS IS AN EXERCISE MESSAGE" i f.

I Declare' General Emergency due to release. i i 1 i,

A l I

I '!

I i i I

! i I i L

i ACTIONS EXPECTED: '

l f i

Declare General Emergency.

f I

i

[

f

[

FOR CONTROLLER USE ONLY i i

3 h used only with approval g exercise lead controller.

{

k l

l i

l i i I

{ t i

f

CEPIP-18 Rev. 3 June 1987 CP&L EXERCISE MESSAGE CARD BSEP Plant Message No. 15 Date 11/17/87 Time After 1300 MESSAGE FOR:

Plant Media Center Controller FROM: CONTROLLER (LEAD)

MESSAGE / SIMULATED PLANT CONDITIONS: "THIS IS AN EXERCISE MESSAGE" What about jobs? Should a release of radioactivity isolate businesses as well as homes for a long time, will you find new jobs for displaced workers? "

How did the fire at the plant differ from the one at Chernoby1?

What amounts of radiation were the South;iort firefighters exposed to?

Will CP&L replace fire department equipment which was contaminated during the fire?

L i l ACTIONS EXPECTED:

i a !

Respond to questions. ,

i 1

i l

] FOR CONTROLLER USE ONLY ;

)

is f i

a h

! 4CEPB 18-22

l I

l CEPIP-.8 Rev. 3 l June 1987 i CPhL EXERCISE MESSAGE CARD MFD Plant 16 !

Message No. Date 11/17/87 Time 1400 MESSAGE FOR: Plant Media Center Controller FROM: CONTROLLER (LEAD)

MESSAGE /SIMJLATED PLANT CONDITIONS: "THIS IS AN EXERCISE MESSAGE" To the Plant Media Center Controller:

You are to call the Plant Media Center and represent yourself as the local taedia (do not use real names of local media people ... Tim Smith or Jane Jones should be used). Ask the following questions:

"THIS IS AN EXERCISE QUESTION:"

V -

I understand that there has been a release of radiation at the Brunswick Plant. Is this another Chernobyl?

Where can I get more information about what is happening at the Plant?

And how can the public find out what's going on?

What precautionary measures have been taken to protect the public?

I'm hearing a lot of unconfirmed reports about what is going on at the Plant. Why should officials in the Company's Raleigh Office know more than people in the Southport area about conditions in the Emergency Planning Zone?

What about reports that hundreds of workers may have been injured at the Plant because of some kind of e.xplosion? If there are injured, where are they being treated? Do local hospitals have Emergency Room Staff and Pacilities to handle injuries?

Just what kind of damage has occurred at the Plant? What is the condition of the fuel, the Reactor, and the Reactor Coolant Systems? Is there the risk of a meltdown?

Do people who treat contamination victims run the risk of being contaminated themselves? I-Do local health facilities have the expertise to treat radiation sickness?

Por example, could bone-marrow treatment be performed locally?

IK;EPs 18-22

I CEPIP-18 Rev. 3 June 1987 1 .

CP&L

\'-

EXERCISE MESSAGE CARD BSEP Plant Message No. 17 Date 11/17/87 Time ,Af,ter 1400 MESSAGE FOR: Plant Media Center Controller FROM: CONTROLLER (LEAD)

MESSAGE / SIMULATED PLANT CONDITIONS:

"THIS IS AN EXERCISE MESSAGE" (Continued)

What about long-term contamination? How long will it take before the full effects of contamination could be'. known?

When the sirens were sounded to alert the Public, did all the sirens sound?

If they did not, how did people get the message?

When will the residents be evacuated?

\s- -

How many residents evacuated. and where have they all gone?

Have you heard from the President of the United States or any other Government Officialefrom Washington?

Is the Plant keeping State and local officials informed about current status and project conditions?

FOR CONTROLLER USE ONLY ACTIONS EXPECTED:

/

As you ask the above questions, you may further identify other questions which i

"ould he appropriate to ask. Please "free play" the asking of questions which s

will stimulate the Plant Media Center in their assigned emergency role.

4 I \

d I

4CEPR 16-22

CEPIP-18 Rev. 3 O June 1987 CP&L l EXERCISE MESSAGE CARD BEFP Plant Message No. 18 Date 11/17/87 Time 1430 MESSAGE FOR: Plant Media Center Controller FROM: CONTROLLER- (LEAD)

MESSAGE / SIMULATED PLANT CONDITIONS: "THIS IS AN EXERCISE MESSAGE" To the Plant Media Center Controller You are to es11 the Plant Media Center and represent yourself as the local media (do not use real names of local media people .. . Tim Smith or Jane Jones should be used). Ask the following questions: ;

"IMIS IS AN EXERCISE QUESTION:"

Os -

Why does it take so long to get information from you? The incident at the Plant released radiation hours ago, why can't you confirm those I

reports sooner? Won't a Geiger Counter tell me what I need to know?

How about insurance? What's the status of this "Price-Anderson Act?"

How much coverage does it offer and for whoa? People? Power Plants? i l

We have heard reports that if people who evacuated the area around the Brunswick '

+

Plant, CP&L will pick up the cost in full? What is that address?

I've been hearing reports that some white puffs of smoke have been coming out of the Plant? Is there another problem which you haven't told us about?

- Will CP&L have any problems meeting the electricity needs of all your customers if this Power Plant must shutdown indefinitely? i There are several Dairy Farms within fifty miles of the Plant. Whose ;

responsibility is it to gauge the' impact of an accident on agriculture?

What has this emergency taught you? What do you know that you did not know before?

We have heard reports that the National T.V. Networks have been given special or exclusive access to the Plant for T.V. coverage. Would you O please coimeent on this report? .'

l i

Q i l !

4CEPs 18-22

t CEPIP-18 !

Rev. 3 .

June 1987 i CP&L- ,

EXERCISE MESSAGE CARD BSEP Plant -I I

Message No. 19' Date 11/17/87 Time 1430 MESSAGE FOR: SOS FROM: CONTROLLER ,

MESSAGE /SIMJLATED PLANT CONDITIONS: "THIS IS AN EXERCISE MESSAGE" '

1. Reactor Scram has been reset. !

F j

i i

s I

ACTIONS EXPECTED: I

'l

1. Report to TSC that scram discharge volume break has been isolated. i i

t t

i FOR CONTROLLER USE ONLY i

I t

l 4CEPB 18-22

i

CEPIP-18 Rev. 3 June 1987 O

g .

CP&L EXERCISE MESSAGE CARD '

i BSEP ,

Plant r

Message No. 20 Date 11/17/87 Time 1430 MESSAGE FOR: Plant Media Center Controller

. FRON: CONTROLLER (LEAD)

MESSAGE / SIMULATED PLANT CONDITIONS: "THIS IS AN EXERCISE MESSAGE" (Continued)

Have you uncovered any defects that may be conunon to some or all of your other f Nuclear Plants? What impact would this emergency have on the operation of these i other. plants?

What kind of assistance from outside agencies are you getting in your efforts to to restore the Plant? -

("

How do you rely on local, State, and county officials to cooperate during this emergency?

1 -

How responsive have these agencies been so far to your request for assistance? i

FOR CONTROLLER USE ONLY ACTIONS EXPECTED: i As you ask the above questions, you may further identify other questions which l would be appropriate to ask. Please "free play" the asking of questions which !

will stimulate the Plant Media Center in their assigned emergency role. I i

i I

f.

?

I i <

j 4CEPs 18-22

. UNIT 0 j PEP-02.6.21 Attachment 5 i Page 1 of 1 l' EXHIBIT 2.6.21-4 l SAFETY PARAMETER DISPLAY SYSTEM (UNIT L ) ,

l gerable I,noperable Standby Running Yes No Isolated NJ - Not available Time , ordo l l

1 HPCI Flow (gpa) O AREA RAD MONITORS mR/hr <

o 2 Core S:> ray A Flow (spa) 37 Rx. Bldg. 20 ft Airlock i 3 RHR A .rlow (gpm) O ,

Rx. Blds. 50 ft Sample j 4 RCIC Flow (spa) 0 38iStation J

~

5 Core S > ray B Flow (spm) O _ 39 Rx. Blds. 50 ft Airlock .1 i I 6 RHR B Flow (spa) O Rx. Blds. North of Fuel 7 SLC Injecting # 40 Pool J ~

8 CRD Flow (spa) /o o Between Fuel Posi and ;

, 9 APRM % /00 41 Drywell hk ;

, _10 Reactor Pressure (psis) foog Turbine Bldg. Sample j 11 Reactor Level (in) 191 _42 Station ' o, a !

12 Main Stack Flow Rate (sefm) loh. coo 43 SJAE A (mR/hr) Sao :

! Turbine Bldg. Roof Vent 44 SJAE B (mR/hr) .14.o .

I 13 Flow (sefs) 14.000 Rx. Bldg. Ventilation !

Rx. Bldg. Roof Vent Flow 45 Monitor (mR/hr) 1 ;

14 (sefs) 112.000 Service Water Rad Monitor !

l Rx. Bldg. Negative Press 46 (eps) /0 15 (inches of water vacuum) .25

) 16 Suppression Pool Level (in) - 3 81 OTHER UNIT l

) 17 Drywell Pressure (psis) .So Turbine Bldg. Roof Vent !

i 18 SBGT Flow A (sefs) I a 47 Flow (sefs) J J l 19 lSBGT Flow B (sefs) o Turbine Bldg. Roof l 20 Drvwell H, 4409 ( cone.) 0 48 Vent Monitor (uci/sec.) I ,

. 21 Drywell H; 4410 (I cone.) o !

j 22 Drywell 0; 4409 (% cone.) /. J. !

i 23 Drywell 0; 4410 (% cone.) /.6 '

! . 24 A0G Systen Flow (scia) 40 -

25 l0ff-Site Power Available Y Main Stack Gas Monitor '

l 26 (uci/sec) 5.of + 1 -

j Turbine Bldg. Vent Monitor 27 (uci/sec) 4./Ef D DRYWELL HIGH RAD MONITOR R/hr !

i 28 D22-RM-4195 - 30 fe El. /2 l

, 29 D22-RM-4196 - 57 fe El. Vo l l 30 022-RM-4197 - 23 fe El. /0 ,

l 31 D22-RM-4198 - 57 ft E).. 35 i

32 Drywell Temp ('F) { ffs ;

! 33_ Suppression Pool Tee) ('F) I ?1 !

RX. 8LDG. ROOF VENT TAD I l- _

MONITOR ;

{ 34 Particulate (cpm) 4f. coo j 35 Iodine (epm) joo l 36 Noble Gas (cpa) foe j

'f a

UNIT 0 PEF-02.6.21 Attachment 5 i s Page 1 of 1 SAFETY PARAME R I PLk S STEM (UNIT L )

gerable inoperable 5,tandby Running Yes No Isolated NA - Not available Time OP/5 1 HPCI/ lev (spa) ARIA RAD MONITORS mR/hr 2 Co'.e S:> ray A Flow (sps)

~TIMR A flow (spm) o o ~ T/

Rx. Bldg. 20 ft Airlock f i

_. O Rx. 81ds. 50 fe ' Sample

! 4 RCIC Flow (spa) o 38 Station & _,

5 Core S > ray B Flow (spa) ~ o _ 39 Rx. Blds. 50 ft Airlock 1 -.

6 RHR B flow (spa) O Rx. Bldg. North of Tuol !

7 SLC Injecting N 40 Pool ,2 i 8 CRD Flow (spa) /,0 Between Fuel Fool and 9 APRM Z 10 0 41 Dryvell O w nseale

10 Reactor Pressure (psis) 1. 00_g Turbine Bldg. Sample 11 Reactor Level (in) '12/7 42 Station '

O. a ;

.; 12 Main Stack Flow Rate (sefm) 6(,,000 43 SJAE A (mR/hr) .sni Turbine Bldg. Roof Vent 44 SJAE 8 (mR/hr) J60 13

~'

Flow (sefs) 14,000 Rx. Bldg. Ventilation i Rx. Bldg. Roof Vent Flow 45 Monitor (mR/hr) l l

< 14 (sefs) 14LOOD Service Water Rad denitor i j Rx. Bldg. Negative Press 46 (eps) to

.as 15 (inches of water vacuum) 16 Suppression Pool Level (in) - 1 a} OTHER UNIT ;

17 Dryvell Pressure (psis) . _t o Turbine Bldg. Roof Vent !

18 $5GT Flow A (sefa) I o 47 Flow (sefe) .T '

19 SBGT Flow B (sefs) o Turbine Bldg. Roof l l 20 Drvvell H, 4409 ('. cone.) o 48 Vent Monitor (uct/sec.) , I ,

. 21 Dryvell H: 4410 (I cone.) o !

22 Dryvell 0; 4409 (% cone.) /. a -

23 Dryvell 0; 4410 (% conc.) p. 6 !

. . 24 A0G Systen Flev (sefa) 40 l

! 25 Off-Site Power Available Y

! Main Stack Gas Monitor ;

]

26 (uci/see) 3. 0E + 1 i Turbine Bldg. Vent Monitor i (uci/sec) l 27 2.#G+0

! DRYWELL HIGH PAD MONITOR R/hr !

) 28 D22-RM-4195 - 30 ft El. l ta ,

1 29 D22-AM-4196 - 57 ft El. I 40 f

, 30 Q22-RM-4t97 - 23 ft El. lo ;

j 31 D22-RM-4198 - 57 ft El. '

ta i 32 Drvvell Temp ('F) i i t.5 l 33 Suppression Pool Tems ('F) 1 I f e7 _

) RX. BLDG. ROOT VENT RAD :

j MONITOR -

4 34 Particulate (cpm) 1,000 +

i 35 Iodine (eps) aoo [

J 36 Noble Gas (cpe) /00 ;

i ,

I I _ _

i UNIT 0 "

PEP-02.6.21 Attachment 5 9

Page 1 of 1 I i SAFETY PARMfE I PLk S STEM (UNIT 1 )

gerable Inoperable S,tandby R,unning Yes No Isolated 3 - Not available Time 0p30 $

1 HPCI Flov (gpm) O AREA RAD MONITORS mR/hr }

2 Core Spray A Flov (gpm) O 37 Rx. Bldg. 20 ft Airlock / i 3 RHR A Flow (gpm) O Rx. Bldg. 50 ft Sample ]

4 RCIC Flov (gpm) 0 38 Station 4 _!l

--J Core Spray B Flow (gpm) a ~39IRx. Bldg. 50 fC Airlock a 6 RHR B Flov (gpm) o Rx. Bldg. North of Fuel "l 7 SLC Injecting N 40 Pool y 8 CRD Flov (gpm) (,0 Between Fuel Pool and "

9 APRM % f00 41 Dryvell Dun seafe, 10 Reactor Pressure (psig) 1,005 Turbine Bldg. Sample 11 Reactor Level (in) ' l g (, 42 Station

0, a J

, 12 Main Stack Flow Rate (scfm) I,t, g 43 SJAE A (mR/hr) 390' ]

Turbine Bldg. Roof Vent 44 SJAE B (mR/hr) .2Po

~

13 Flov (sefm) 14,000 Rx. Bldg. Ventilation Rx. Bldg. Roof Vent Flov 65 Monitor (mR/hr) /

14 (s_c fm) / 7a,000 Service Water Rad Monitor q Rx. Bldg. Nezative Press 46 (eps) /0 15 (inches of water vacuum) ,45 ;

16 Suppression Pool Level (in) -J9 OTHER UNIT -

17 Dryvell Pressure (psig) I .Jo Turbine Bldg. Roof Vent 18 SBGT Flow A (sefe) I o 47 Flov (sefe) 27 19 SBGT Flow B (scfm) o Turbine Bldg. Roof l 20 Drvvell H, 4409 ( cone.) O 48 Vent Monitor (uci/sec.) I 21 lDrvvell H; 4410 (% conc.) 0 22 Drvvell 0; 4409 (% cone.) 1. ,;L h

~

23 Dryvell 0; 4410 (% cone.) / , 6, m 24 AOG Systes Flow (sefe) "

. i 1/0 25c0ff-Site Power Available y Z f Main Stack Gas Monitor =

26 (uci/see) 5. o E+ 1_

Turbine Bldg. Vent Monitor 3 27 (uci/sec) 4.4E+0 6 DRYVELL HIGH RAD MONITOR

~

R/hr -

28- D22-RM-4195 - 30 ft El. M 29 D22-RM-4196 - 57 ft El. 1 40 30 022-RM-4197 - 23 ft El. l l0 -

31 D22-RM l.198 - 5 7 f t El. I 25 -

32 Drvvell Temp ('F) l tis 2 Suppres_sion Pool Teep (*F) 9 33 RX. BLDG. RG0F VEhT RAD MONITOR 34 Particulate (cpm) 1 M

/,000

=

2 35 Iodine (cpm) 400 36 Noble Gas (epm) /00 -

UNIT 0 PEF-02.6.21

]

( Attachment 5 Page 1 of 1 SAFETY PARAME ER IP S EM (UNIT .'2 ) l 02erable Inoperable S,tandby R,unning Yes Isolated No i i NJ - Not available Time CFAIS 4

1 HPCI Flow (spa) O ,

AREA RAD MONITORS mR/hr 2 Core Spray A. Flow (gpa) o 37 Rx. Bldg. 20 ft Airlock / ,

i 3 RHR A Flov (spm) O Rx. Bldg. 50 ft Sample '

4 RCIC Flow (spa) o 38 Station J _

5 Core S iray B Flov (spa) o _ 39 Rx. 51ds. 50 ft Airlock 4 6 RHR B Flow (spa) O Rx. Bldg. North of fuel '

7 SLC Injecting N 40 Pool 2 8 CRD Flow (spa) 60 .

Between Fuel Fool and 9 APRM I C5% 41 Dryvell Nm u le, ,

1 10 Reactor Pressure (psip /O:23 Turbine Bldg. Sample ,

4 11 Reactor Level (in) /N 42 Station

o, a 4 12 Main Stack Flow Rate (sefm) && ooo 43 SJAE A (mR/hr) #t.d Turbine Bldg. Roof Vent 44 SJAE 3 (mR/hr) Sec ,

13 Flow (sefs) /#.000 Rx. Bldg. Ventilation !

Rx. Bldg. Roof Vent Flow 45 Monitor (mR/hr) /

l

. 14 (sefs) /72,000 Service Water Rad Monitor t (eps)

~

Rx. Bldg. Negative Press 46 /c 15 (inches of water vacuus) 25 i l

16 Suppression Pool Level (in) - sq OTHER UNIT :

1 17 Dryvell Pressure (psis) .3o Turbine 81dg. Roof Vent (

l 18 S8GT Flow A (sefs) I o 47 Flow (sefs) I ;

19 SSGT Flow B (sefs) o Turbine Bldg. Roof q 20 Drvve11 H, 4409 (: cone.) o 48 Vent Monitor (uci/sec.) T

. 21 Dryvell H; 4410 (2 cone.) o '

4 22 Dryvell 0; 4409 (% cone.) /. 1 23 Dryvell O' 4410 (I cone.) /. 6 .

j . 24 A0G Systen Flev (sefs) 4to l l 25 Off-Site Power Available Y i Main Stack Gas Monitor

} 26 (uci/see) 5.oE+1 ,

j Turbine 81ds. Vent Monitor ,

j 27 (Mi/see) J. #E+o l DRYVELL HIGH RAD MONITOR R/hr !

) 28 D22 RM-4195 - 30 fe El. /a i j 29 D22-RM-4196 - 57 ft El. l

1 ;

30 Q22-RM-4197 - 23 ft El. 11 i ll 31 D22-RM-4198 - 57 ft El. SS !

32 Dryvell Temp ('F) l /15 _ I

33 Suppression Pool Tem * ("F) i J1 ' !

! RX. BLDG. ROOF VENT RAE l l

MONITOR l

! 34 Particulate (cpm) /,odo i 35 Iodine (epm) Joo~ '

{ 36 Noble Gas (cpe) /00 i

-t UNIT 0 PEP-02.6.21 i Attachment $

Page 1 of 1 l

, EXHIBIT 2.6.21-4 i SAFETY PARAMETER DISPLAY SYSTEM (UNIT 1 ) , j gerable Inoperable S,tandby Running Yes No Isolated NJ - Not available Time 6100 HPCI Flow (spa) o f

1 AREA RAD MONITORS mR/hr ;

2 Core Spray A Flou (spa) O 37 Rx. Bldg. 20 ft Airlock / !

3 RHR A Flow (spa) o Rx. Blds. 30 ft Sample l 4 RCIC Flow (spe) o 38 Station ;t

_l 5 Core Stray B Flow (spa) o 39 Rx. Bldg. 50 ft Airlock a

6 RHR 5 Plow (spe) o Rx. Bldg. North of Fuel i j 7 SLC Injecting o 40 Fool gt 8 CRD Flow (spa) /,o _ Between Fuel Fool and l

, 9 APRM I 449h 41 Drywell hm /,

Reactor Pressure (psis) Turbine Bldg. Sample 10 /400 11 Reactor Level (in) '/n 42 Station '

O. .t i 12 Main Stack Flow Rate (sefm) /,4. oop 43 SJAE A (mR/hr) $56 Turbine Bldg. Roof Vent '

44 SJAE B (mR/hr) #fo l 13 Flev (sefs) /d odo Rx. Bldg. Vent 11ation j Rx. Bldg. Roof Vent Flow '

45 Monitor (mR/hr) / j 14 (sefs) /fAodd Service Water Rad Monitor Rx. Bldg. Negative Press 46 (eps) /0 ,

15 (inches of water vacuum) .a5 i 16 Suppression Pool Level (in) 24 OTHER UNIT !

'17 Dryvell Pressure (psis) , ga Turbine Bldg. Roof Vent l l

l 18 SBGT Flow A (scia) i O 47 Flev (sefs) J .'

19 SBGT Flow B (sefs) o Turbine Bldg. Roof ll 20 Drvve11 H, 4409 (f. cone.) a 48 Vent Monitor (uci/sec.) 7 l

. . 21 Dryvell H: 4410 (I cone.) 0 !

l 22 Drywell 0; 4409 (% cone.) /, a i

! 23 Drywell 0; 4410 (% cone.) /. 6 :

i . 24 A0G Systed Flow (sefs) Wo <

I 25 Off-Site Power Available V ,

I Main Stack das Monitor I j 26 (uCi/sec) .S. o E *L l Turbine 7143 . Vent Monitor .

I 27 (uCi/sec) J. #E +0 DRYVELL IIT ' RAD MONITOR R/hr l 28 D22-RM-4195 30 fe El. i /2 l

, 29 D22-AM-41s D 57 fe El. 1 #/ l 30 022-RM-4197 - 23 ft El. l /a i l 31 D24-RM-4198 - 37 ft El. I J5 l 32. Dryvell remp (

F2 ' //S

! 33 Suppress.on Pool Temp ('F) n f5 l RX. SLDG. ROOF VENT RAD j MONITOR l 34 Particulate (cpm) /,000 l 35 Iodine (eps) 'Joo 1 36 Noble Gas (cpe) /00 1

_ UNIT 0 PEP-02.6.21 Attachment 5 EXHIBIT 2.6.21-4 SAFETY PARAMETER DISPLAY SYSTEM (UNIT f. )

Ojerable Inoperable S,tandby Running Yes No Isolated 3 - Not available Time o 't i C 1 HPCI Flov (gpm) O ' AREA RAl) MONITORS

'mR/hr 2 Core Spray A Flov (gpm) o 37 Rx. Bldt. 20 ft Airlock /

3 RHR A Flov (gpm) o Rx. Bldg. 50 ft Sample g 4 RCIC Flov (gpm) O 38 Station 4 _

p 5 Core Spray B Flov (gpm) o _ 39 Rx. Bldg. 50 fC Airlock &

$ 6 RHR B Flov (gpm) O Rx. Bldy.. North of Fuel 7 SLC Injecting i N 40 Pool 4 i 8 CRD Flov (gpm) 60 Between Fuel Pool and g 9 APRM % '75 '/g 41 Dryvr,11 b3e, /c, MO Turhine Bldg. Sample 10 Reactor Pressure (psie) 1i Reactor Level (in) / F'1 42 Station '

O. t 12 Main Stack Flow Rate (sefm) /A.000 43 SJhE A (mR/hr) 556

) Turbine Bldg. Roof Vent 44 SJAE B (mR/hr) Wo a- 13 Flov (sefm) /0 00o Rx. Bldg. Ventilation

/

Rx. Bldg. Roof Vent Flov 45 Monitor (mR/hr) 9 14 (sefm)

Rx. Bldg. Negative Press 15 (inches of water vacuu:n)

/73,000

,M 46 (eps)

Service Water Rad Monitor

/o k 16 Suppression Pool Level (in) ,3 8) OTHEP. UNIT

17 Drvvell Pres +ure (psig) . 27 Turbine Bldg. Roof Vent 18 SBGT Flov A (sefm) I O 47 Flov (sefs) 7

_ 19 lSBGT Flow B (sefm) o Turbine Bldg. Roof l E

20jDrvvell H., 4409 (" cone.) o 48 Vent Monitor (uci/see.) T 21jDryvell H: 4410 (% cone.) 0 22 Drvvell 0; 4409 (% cone.) /. 5 g 23 Dryvell 0; 4410 (% conc.) /,1 24lA0G Systes Flow (sefm) !

L

25l0ff-Site Power Available V r Main Stack Gas Monitor E 26 (uCi/see) 3 oE+l n Turbine 81dg. Vent Monitor T 27 (uCi/sec) .) . d/ Et o

_ DRYVELL HIGH RAD MONITOR R/hr

- 28' D22-RM-4195 - 30 fe El. 16 29 D22-RM-4196 - 57 ft El. I 59

_ 30 Q22-RM-4l97 - 23 ft El. l fo 31l D22-RM-4198 - 57 ft El. l 30

_ 32 Drvvell Temp ('F) { fl4

_ 33 Suppression Pool Teep ("F) I 95 RX. BLDG. ROOF VENT RAD

. MONITOR 34 Particulate (cps) /.000 35' Iodine (cpm) Moo 36 Noble Gas (cpm) /00

UNIT 0 PEP-02.6.21 f'~'

i Attachment 5 Page 1 of I

\ EXHIBIT 2.6.21-4 SAFETY PARAMETER DISPLAY SYSTEM (UNIT '2- )

Ogerable Inoperable Standby Running Yes No Isolated NA L - Not available Time c)'f3o 1 HPCI Flov (gpa) O ARIA RAD MONITORS mR/hr

~l Core S? ray A Flev (gpm) o 37 Rx. Bldg. 20 ft Airlock /

3 RHR A Ilov (gpm) o Rx. Bids. 50 ft Sample 4 RCIC Flov (spm) o 38 Station A ~

5 Core Soray B Flov (spa) 0 39 lbc. Blds. 50 ft Airlock a 6 RHR B Flov (spa) o Rx. Bldg. North of Fuel 7 SLC Injecting o 40 Pool 4 8 CRD Flov (spa) 60 Between Fuel Pool and 9 APRM % 60 41 Dryvell %m g a l,_

10 Reactor Pressure (psis) ffo Turbine Bldg. Sample 11 Reactor Level (in) I

/f7 42 Station '

O, 2 12 Main Stack Flow Rate (sefm) 46.000 43 SJAI A (mR/hr) Gfd Turbine Bldg. Roof Vent 44'SJAE B (mR/hr) #90 13 Flov (scfm) /V,odo Rx. Bldg. Ventilation Rx. Bldg. Roof Vent Flov 45 Monitor (mR/hr) /

[

\

14 (sefm)

Rx. Bldg. Negative Press

/7J,ood 46 Service Water Rad Monitor (eps) /0 15 (inches of water vacuum) . 05 16 Suppression Pool Level (in) - 39 OTHER UNIT 17- Dryvell Pressure (psis) 45 Turbine Bldg. Roof Vent 18 SBGT Flow A (sefs) I o 47 Flov (sefm) JI 19 'SBGT Flow B (sefs) o Turbine Bldg. Roof [

20 Dryvell H, 4409 ( cone.) o 48 Vent Monitor (uci/sec.) JF

, 21 Dryvell H; 4410 (! cone.) 0 22 Dryvell O' 4409 (1 cone.) /, V 23 Dryvell O' 4410 (% . cone.) A7

. 24 A0G Systes Flov (sefr) l 35 2510ff-site Power Available V Main Stack Gas Monitor

_26 (uC1/sec) 6. 06 f1 Turbine Bldg. Vent Monitor ,

J 27 (uCi/sec) J. VE

O DRYWELL HIGH RAD MONITOR R/hr 28 D22-RM-4195 - 30 f t El. ( fo 29 D22-RM-4196 - 57 ft El. I 36 30- Q22-RM-4197 - 23 ft El. /c 31 D22-RM-4198 - 57 ft El.

50 32 Dryvell Temp ('F) j'll3

, 33 Suppression Pool Teep ('F) I f.5 RX. BLDC. ROOF VENT RAD N- MONITOR i

34 Particulate (cpm) n /sooo 35 Iodine (epm) ~ 400 l

36 Noble Gas (cpm) /00

. UNIT 0 PEP-02.6.21 Attachment 5 Page 1 of 1

, EXHIBIT 2.6.21-4 SAFETY PARAMETER DISPLAY SYSTEM (UNIT 1 )

Ogerable Inoperable Standby Running Yes No Isolated CMS NJ - Not available Time 1 HFCI Flow (2ps) 0 ARIA RAD MONITORS mR/hr~~~

2 Core Spray A Flow (spa) 0 37 Rx. Bldg. 20 ft Airlock /

3 RMR A Flow (spa) 0 Rx. 51ds. 50 ft Sample 4 RCIC Flow (spm) o _

38 Station 2 _

i 5 Core Spray B Flow (spa) 0 39 Rx. 51ds. 50 ft Airlock 22

! 6 RNR 5 Flow (spa) D Rx. Bldg. North of Fuel 7 SLC Injecting N 40 Fool 'l 8 CRD Flow (spa) 4g> Between Fuel Fool and 9 APRM I 55 41 Drywell t' . /.

10 Reactor Pressure (psis) 917 Turbine 31dg. Sample l 11 Reactor Level (in) /f7 42 Station *

0. A i 12 Main Stack Flow Rate (scfm) 4L.oco 43 SJAE A (mR/hr) 4mtb

, Turbine 51dg. Roof Vent 44 SJAE 5 (mR/hr) eqwo i 13 Flow (sefa) /4,000 Rx. Aldg. Ventilation i Rx. 51ds. Roof Vent Flow 45 Honitor (aR/hr) /

14 (sefa) /7Aiaco Service Water Rad Monitor j Rx. Bldg. Negative Fress 46 (eps) /0 15 (inches of water vacuus) .Js 16 Suppression Fool Level (in) - Aq OTHER UNIT 17 Dryvell Pressure (psis) .As Turbine 81dg. Roof Vent

! 18 SBGT Flow A (sefa) I o 47 Flow (sefs) J" ,

i 19 $8GT Flow 8 (sefs) C Turbine 51dg. Roof [

20 Drywell H, 4409 ( conc.) o 48 Vent Monitor (uci/sec.) JF

. 21 Drywell H; 4410 (I co.ie.) 0 22 Dryvell 0; 4409 (I cone.) L3 i

23 Drywell 0; 4410 (% cone.) /, f

. 24 A0G Systei Flow (sefs) J.T

) 25 10ff-Site Fever Available V

. Main Stack Gas Monitor I 26 (uCi/see) 5, o E + 1

! Turbine Bldg. Vent Monitor

} 27 (uci/see) 4. W*O

! DRYVILL HIGH RAD MONITOR R/hr

! 28 D22-RM-4195 - 30 f t El. '

/0 29 D22-RM-4196 - 57 ft El. l 54 30 Q22-RM-4197 - 23 ft El. la j

31 D22-RM-4198 - 57 ft El. 30 --

32 Dryvell Temp ('F) i 11 3 33 Suppression Pool Temp ('F) i FL ,

! AX. BLDG. ROOT VEAT RAD l _ MONITOR j 34 Particulate (cpa) / 000 3

35 Iodine (eps) Ada 36 Noble Gas (cpa) ,

/00 i

o .

I UNIT 0 PEP-02.6.21 Attachment 5 i

[ Page 1 of 1

(' EXHIBIT 2.6.21-4 SAFETY PARAMETER DISPLAY SYSTEM (UNIT 1 )

Ogerable Inoperable Standby R,unning Yes No Isolated NA - Not available Time /4h00 1 I!PCI Flow (spm) o AREA RAD MONITORS mR/hr 2 Core Spray A Flov (gpa) o 37 Rx. Bldg. 20 ft Airlock /

~T RHR A Flow (gpm) o Rx. Bids. 50 ft Sample

-4 RCIC Flow (gpm) o 38 Station 3 ~

$ Core $ > ray B Flow (gpa) ~ e o ~39 lRx. Bldg. 50 ft Airlock 2 6 RHR B Flov (spm) O Rx. Bldg. North of Fuel 7 SLC Injecting // 40 Pool ;2 8 CRD Flow (gps) Go Between Fuel Pool and 9 APRM ! 5/ 41 Dryvell Tkmesca le 10 Reactor Pressure (psig) '

903 Turbine Bldg. Sample 11 Reactor Level (in) /s2r 42 Station

dA 12 Main Stack Flow Rate (sefm) && 000 43 SJAE A" (mR/hr) 616 Turbine Bldg. Roof Vent 44!$JAE B (mR/hr) gppo 13 Flov (sefs) /V ooo Rx. Bldg. Ventilation Rx. Bldg. Roof Vent Flow

~

45 Monitor (mR/hr) /

14 (sefs) /73,0o 0 Service Water Rad Monitor Rx. Bldg. Negative Press 46 (eps) /o 15 (inches of water vacuum) , 42 5 16 Suppression Pool Level (in) - m9 OTHER UNIT

17 Dryvell Pressure (psis) , Jt s Turbine Bldg. Root Vent i 18 'SBGT Flow A (sefm) 1 0 ,47 Flow (sefm) jf 19'SBGT Flow B (sefm) o Turbine Bldg. Roof l 20 Dryvell H, 4409 (: cone.) o 48 Vent Monitor (uci/sec.) f 214 Dryve11 H; 4410 (1 cone.) o 221Dryvell 0; 4409 (I cone.) /5 23 Dryvell 0; 4410 (% cone.) /, y

. 24 AOG Systes Flev (sefm) l 36 1 25 (Of f -Site Power Available y Main Stack Gas Monitor i 26 (uCi/sec) 6, oE + l Turbine Bldg. Vent Monitor 27 (uCi/sec) J.4tE+O DRYVELL HIGH RAD MONITOR R/hr 1 28 D22-RM-4195 - 30 f t El. i /0 29 D22-RM-4196 - 5 7 f t El. I ig t 30 Q 22-RM-4 l 9 7 - 2 3 f t El. l /o 1 31 D22-RM-4198 - 57 ft El. I 25C I 32 Dryvell Temp ('F) { /f 3

! 33 Suppression Pool Temp ('F) I 96 RX. BLDG. ROOF VENT RAD k MONITOR 34 Particulate (cpm) /,000 ;

35 Iodine (cpm) 'Joo '

I 36 Noble Gas (cpm) '

/ho

UNIT 0 PEP-02.6.21 o)

(

\sd

' EXHIBIT 2.6.21-4 Attachment 5 Page 1 of 1 SAFETY PARAMETER DISPLAY SYSTEM (UNIT 1) 02erable I,noperable S,tandby R,unning Yes No Isolated 3 - Not available Time /C/S 1 HPCI Flov (gpm) o i ARIA RAD MOSITORS mR/hr 2 Core Spray A Flow (gpm) o 37 Rx. Bldg. 20 ft Airlock /

3 RHR A Flow (gpm) o Rx. Bids. 50 ft Sample '

4 RCIC Flov (gpm) o 38 Station 3 ~~

3 Core Saray B flow (gpm) o 39 Rx. Blds. 50 ft Airlotk JlL 6 kHR 8 riov (gpm) o Rx. 81ds. North of Fuel 7 SLC Injecting N 40 Pool ;2 8 CRD Flov (spa) /,0 Between Fuel Pool and 9 APRM %

10 Reactor Pressure (psis) 30 415 41 Dryvell Turbine 81dg. Sample ZLQ 11 Reactor Level (in) ///, 42 Station '

d ;l 12 Main Stack . low Rate (sefm) &&,ddo 43 SJAE A (mA/hr) bab l Turbine Bldg. Roof Vent '

44 SJAE 8 (mR/hr) Soo 13 Flev (sefs) /4.000 Rx. 81d3 . Ventilation Rx. Bldg. Roof Vent Flow 45 Monitor (mR/hr) /

,f 14 (sefm) /71 00o Service Water Rad Monitor ;

\ Rx. Bldg. Negative Press 46 (eps) /0 .

15 (inches of water vacuum) . .l2 5 16 Suppression Pool Level (in) - ;2 9 OTHER UNIT i 17 Dryvell Pressure (psis) I . .a ~s Turbine Bldg. Roof Vent

. 18 SBGT Flev A (sefm) I o 47 Flov (sefs) I :

19fSBGT Flow B (sefm) o Turbine 81dg. Roof [

20, Drvve11 H, 4409 ( cone.) o 48 Vent Monitor (uci/sec.) I 21l Dryvell H; 4410 ( cone.) 0 22'Dryvell 0; 4409 (% conc.) /. g ,

23- Dryve11 0; 4410 (% cone.) i

/. 9 1 , 24 A0G Systes Flov (sefm) 36

_25l0ff-site Power Available V I Main Stack Gas Monitor '

26 (uci/sec) / 06+/

i Turbine Bldg. Vent Monitor

] 27 (uci/sec) : .2.4/ d'/O

DRWELL HIGH RAD MONITOR R/hr 28 D22-RM-4195 - 30 tt El. I

/4 I9I D22-R.M-4196 - $7 ft El. I 3 /,

30 Q22-R.M-4197 - 23 fe El. /0 [

31 D22-RM-4198 - 57 ft El. I' 30 l 32:Drnell Temp ('F) { //f 33 Suppression Pool Teep ('F) l TG RX. 8LDG. ROOF VENT RAD MONITOR ,

34 Particulate (epm) /,004 35 Iodine (epm) 'so 36 Noble Gas (cpm) /00 1

I

UNIT 0 ,

PEP-02.6.21 gs Attachment 5 i Page 1 of 1

\y_-) EXHIBIT 2.6.21-4

, SAFETY PARAMETER DISPLAY SYSTEM (UNIT fL_) ;

Ogerable Inoperable Standby Running Yes No Isolated -

NA - Not available Time /030 i HPCI Flow (gpm) i o . ARIA RAD MONITORS .mR/hr 2 Core Spray A Flov (gpa) o 37 Rx. Bldg. 20 ft Airlock / 3 3 RHR A Flev (gpm) o Rx. 31dg. 50 ft Sample !

4 RCIC Flov (gpm) o 38 Station 3 ~

- 3 Core S) ray B Flov (spm) o 391Rx. 81ds. 50 ft Airlock ,lL 6 RHR 5 Flov (gpm) o Rx. 81ds. North of Fuel I

., 7 SLC Injecting At 40 Pool ;t 8 CRD Flov (gpm) 6o Between Fuel Pool and i.

9 APRM % #5 41 Dryvell Nek 10 Reactor Pressure (psis) '

910 Turbine Bldg. Sample 11 Reactor Level (in) I /77 42 Station '

0, ;t 12 Main Stack Flow Rate (scfm) 666.000 43 SJAI A (mR/hr) 6Vb Turbine Bldg. Root Vent 44ISJAE B (mR/hr) 3/O 13 Flow (sefs) /4.000 Rx. Bldg. Ventilation Rx. Bldg. Roof Vent Flov 4f Monitor (mR/hr) / ,

14 (sefm) /71 000 Service Water Rad Monitor

( 46 (eps)

~

Rx. Bldg. Negative Press /0 ;

15 (inches of water vacuum) .45 16 Suppression Pool Level (in) ,39 __

OTHER UNIT 17 Dryvell Pressure (psis) .g3 Turbine 81ds. Roof Vent

{ 18- SBGT Flow A (sefm) i o j 47 Flov (sefm) j[ ,

19ISBGT Flow 8 (sefm) o Turbine Bldg. Roof l 20lDryvell H, 4409 ( cone.) o 48 Vent Monitor (uci/see.) 'E ,

21IDryvell H; 4410 (! cone.) o 22 Dryvell 0; 4409 (% cone.) j4 23 Dryvell 0; 44l0 (I cone.) J,o

, , 24 A0G Systes Flev (sets) 1 52 l 2510ff-Site Power Available 7 i Main Stack Gas Monitor

26 (uci/see) 5.oE+ l

, Turbine Sldg. Vent Monitor 27 (uCi/sec) 2.4f+o DRYWILL HIGH RAD MONITOR R/hr

28 D22-RM-4195 - 30 f t El. 1 /o 29 D22-RM-4196 - 5 7 f t El. i 3E, t 30i O22-AM-4197 - 23 ft El. /c !

31 D22-RM-4198 - 57 ft El. n 30 l 22 Dryvell Temp ('F) { / /;t [

33 Suppression Pool Teep (*F) i FG l RX. BLDG ROOF VENT RAD MONITOR 34iParticulate (cpm) '

/. ooo 35' Iodine (cpm) '200 36 Noble Gas (cpm) /00 l

UNIT 0 [

, PEF-02.6.21 !

Attachment 5 i I Fage 1 of.1 !

,' EXHIBIT 2.6.21-4 i SAFETY FARAMETER DISPLAY SYSTEM (UNIT L ) [

j gerable Inoperable 5,tandby R,unning Yes No Isolated !

t I NA - Not available Time /de,/f ;

}

l 1 HPCI Flow (spa) 0 _ ARIA RAD HONITORS mR/hr ,.

2 Core Spray A Flow (spa) o 37 Rx. 51d3 20 fe Airlock / -

. 3 RHR A Flow (spa) o Rx. 51ds. 50 ft Sample l l 4 RCIC Flow (spe) o 38 Station a j 15 Core Spray 5 Flov (spa) ~~ o ,

_ 39 Rx. Blds. 50 fe Airlock a j j 6 RHR 5 Flow (sps) o Rx. 51dg. North of Tuol l

! 7 SLC Injecting N ,,

40 Fool ,n ;

8 CRD Flov (spa) 1,0 Between Fuel Fool and ;

9 APRM I NJ 41 Dryvel,1 Tw- k ,

3 10 Reactor Pressure (psis) 970 Turbine I,1dg. Sample !

i 11 Reactor Level (in) /f7 42 Station e

o. 2 f j 12 Main Stack Flow Rate (sefs) /,ho#0 43 SJAZ A , (mR/hr) /, v4 l Turbine 51d3 . Roof Vent 44 SJAE 5 (mR/hr) sto l l 13 Flow (sefs) /9.000 / Rx. 31d 3 . Ventilation I i

Rx. Bldg. Roof Vent Flow 45 Monitor (mR/hr) / ,

14 (sefs) /7A dd# Service Water Rad Monitor j Rx. Bldg. Negative Press 46 (eps) /0 ;

i 15 (inches of water vacuum) .25 j 16 Suppression Pool Level (in) ,pq 0711ES UNIT l

l 17 Drvvell Pressure (psis) 1; 4V Turbine Bldg. Roof ' lent j l 18 SIGT Flow A (sefs) I o 47 Flow (sefm) T .!

i 19 SIGT Flow 5 (sefa) o Turbine B1'd'37 Roof

! 20 Drvvell H, 4409 ( cone.) 0 48 Vent Monitor (uci/sec.) _f l;

, 21 Dryvell H' 4410 (I cone.) O l

22 Dryvell 0; 4409 (I cone.) /, /, !

l 23 Dryvell O' 4410 (1 cone.) /. 4 -

i . 24 A0G Systei Flov (sefa) 44 !

25 Off-Site Power Available Y f!

l Main Stack Gas Monitor l 26 (uCi/see) 5,oEn ;

l Turbine 81ds. Vent Monitor l

27 (uci/sec) J. NE +0 ORYVELL HIGH RAD MONITOR R/hr t 28 D22-RM-4195 - 30 ft El. /o I 29 D22-RM-4196 - 57 ft El. 1 &,

I 30 Q22-RM-4197 - 23 ft El. {

/0 ,

I 31 D22-AM-4198 - 57 ft El. I- .40 !

32 Dryvell Temp ('F) { //a !

33 Suppression Pool Teep ('F) I ft, t

RX. BLDG. ROOF VENT RAD i MONITOR 34 Particulate (eps) / , aa c 35 Iodine (eps) Ma 36 Noble Gas (eps) /00 t

1_ - -- . _ _ _ _ _ . . - - ___ _ J

I t/ NIT 0 l'EP-02.6.21

{

(

Attachment 5 Page 1 of 1 l' EXHIBIT 2.6.21-4 SAFETY PARAMETER DISPLAY SYSTEM (UNIT .A )

02 erable ,I,no pe rable Standby R_unning Yes No Isolated 3 - Not available Time //00 ;

1 HPCI Flow (gpa) C ,

AREA RAD MOSIT0kS 'mR/hr I 2 Core Spray A Flow (gpm) o 37 Rx. 81dt. 20 fC Airlock /

3 RHR A Flow (spm) o Rx. Bids. 50 fe Sample

- 4 RCIC Flow (spm) 0 38 Station J 5 Core S> ray 8 Flev (spm) o 39IRx. 81ds. 50 fC Airlock ;$

6 RHR 8 "lov (spm) O Rx. Bldg. North of Fuel 7 SLC Injecting ## 40 Pool .2 8 CRD Flow (spa) >/co Between fuel Pool and 9 APRM I ID% 41 Dryvell be le_

10 Reactor Pressure (psis) 4G5 Turbine 81dg. Sample r 11 Reactor Level (in) 120 42 Station

5 12 Main Stack Flow Rate (sefm) /J, . 000 43 SJAE A (mR/hr) JJb l Turbine Bldg. Roof Vent 44' SJAE 8 (mR/br) /Go 13 Flov (sefs) /#.0o0 Rx. Bldg. Ventilation p Rx. Bldg. Roof Vent Flow 45 Monitor (mR/hr) /

14 (sefm) /'/1 000 Service Water Rad Monitor

(' Rx. Bldg. Negative Press 46 (eps) /0 15 (inches of water vacuum) .J5 16 Suppression Pool 1.evel (in) _J9 OTHER UNIT ,

17 Dryvell Pressure (psig) .14, Turbine Bldg. Roof Vent

_18 SBGT Flow A (sefm) I o 47 Flov (sefe) J 19I SBGT Flow B (sefs) o Turbine Bldg. Roof l 20'Drvve11 H, 4409 ( cone.) a 48 Vent Mot itor (uci/sec.) I I 21 Dryvell H; 4410 (! cone.) a 22 Drvve11 0: 4409 (% cone.) /,1 23- Drvve11 0; 4410 (% cone.) ,;2 . /

. 24iA0G Systoi Flev (sefm) I aA I 2510ff-Site Power Available Y L Main Stack Gas Monitor j 26 (uci/sec) /.06 # / '

Turbine Bldg. Vent Monitor i

27 (uCi/sec) 5.oEf3 DRYWELL HIGH RAD MONITOR R/hr j 28 D22-RM-4195 - 30 ft El. 6 (

29 D22-RM-4196 - 57 fe El. I /.1 '

l 30 Q22-RM-4197 - 23 ft El. l 5 [

! 3tl D?2-RM-4198 - 57 ft El. 1 /o

32 Drvvell Temp ('F) i //o

(^

(

33 Suppression Pool Temp ('F)

RX. SLDG. ROOF VE.NT RAD l P6

{'

MONITOR I 34 Particulate (epm) /, ooo 35 Iodine (cpm) 'Joo t 36 Noble Gas (cpm) /oo ,

i

l l

l UNIT 0 l PEP-02.6.21 p Attachment 5 Page 1 of 1 1 t> EXHIBIT 2.6.21-4 )

SAFETY PARAMETER DISPLAY SYSTEM (UNIT 1) l gerable Inoperable S,tandby R_unning Yes No Isolated I NA - Not available Time ///5 ]

1 HPCI Flow (gpm) __

o ' AREA RAD MONI,TCRS , ~[~~~'

hr I 2 Core Spray A Flow (gpm) o 37 Rn. Bldg. 20 ft Airlock 1 /

3 RHR A ilow (gem) D Rx. Bldg. 50 ft samplo 4 RCIC Flow (gpm) o 3S S"ation Jl1

-5 Core Spray B Flow (gpm) o 39iRx. Bldg 50 fC Airicek 2 o

~

6 RHR B Flow (gpm) Rx. Bldg. Nerth of Feel

~

177 SLC Injecting V 40 Poel n 8 CRD Flow (gpm) >/co Between Fuel Fool and 9 APRM 7 99, 41 Drywell, b,3,7a /e, 10 Reactor Pressure (psig) 94 5 Turbina Bldg. Sample 11 Reactor Level (in) /f7 42 Station - 3 12 Main Stack Flow Rate (sefm) /,/,,000 43 SJAZ A ~'"(mR/hr) J /b

Turbine Bldg. Roof Vent 44 SJAE B (mkIhr) ,/ho 13 Flow (sefm) /4s OOO Rx. Bldg, Ventilation L Rx. Bldg. Roof Vent flow 45 Monitor (mR/hr) _,L_,, _

14 (sefm) /Lh000 Se Wice Water Rad Monitor

, Rx. Bldg. Negative Press 46 (eps) /0 _

15 (inches of water vacuum) -'c25-16 Suppression Pool Level (in) -49 OTHER UNIT 17 Dryvell Pressure (psig) ,Jo Turbine Bldg. Roof Vent 18 SBGT Flow A (sefm) I o 47 Flow (s.cfmL T 19 'SBGT Flow B (sefm) O Turbine Ble.g. Roof l ~

l 20 Drvve11 H, 4409 (% cone.) o 46 Vent Monit,or (uCi/sec.) _C

. 21' Dryvell H: 4410 (% cone.) o 22 Dryvell 0; 4409 (% cone.) /,1

,23 Drywell 0; 4410 (% cone.) J./

i . 24 A0G Syste5 Flow (sefm) i J J.

25 Off-Site Power Available V Main Stack Gas Monitor 26 (uCt/ rec) f.06+I Turbine Bldg. Vent Monitor l 27 (uCi/sec) 6'.o&+3 DRYWELL HIGH RAD MONITOR R/hr 28 D22-RM-4195 - 30 ft El. /,

29 D22-RM-4196 - 57 ft El. ,

/2 ;

30 022-RM-4197 - 23 ft El. 5 31 D22-RM-4198 - 57 ft El. I /0 32 Drywell Temp (*F) l //O Suppression Pool Temp ("F) i f/,

i O 33MONITOR RX. BLDG. ROOF VENT RAD l 34 Particulate (cpm) /sooo l 35 Iodine (cpm) 'Jed 36 Noble Gas (com) /do

UNIT 0 PEP-02.6.21

, []j

-s EXHIBIT 2.6.21-4 Attachment 5 Page 1 of 1

'H SAFETY PARAMETER DISPLAY SYSTEM (UNIT Jl )

gerable Inoper- le S_tandby Running Yes No Isolated 830 3 - Not available . Time 1 HPCI Flow (gpm,\ O ' AREA RAD MONI' ORS nR/hr 2 Core Spray A Flow (gpm) O 37 Rx. Bldg. 20 ft Airlock /

3 RHR A Flow (gpm) O Rx. Bldg. 50 ft Sample

~~#

4 RCIC Flow (gpm) O 38 Station 2 _

5 Core Spray B Flow (gpm) a _39lRx Bldg. 50 ft Airlock 2 6 RHR B Flow (gpm) O Rx. Bldg. North of Fuel 7 SLC Injecting y 40 Pool-A 8 CRD Flow (gpm) >/00 Between Fuel Pool and 9 APRM % rJ % 41 Drywell Do.,nsa,le, 10 Reactor Pressure (psig) 9.25 Turbine Blag. Sample 11 Reactor Level (in) 1

/97 42 5tation '

3 12 Main Stack Flow Rate (sefm) , /, /,,ooo 4 3 SJAE A ___( mA/hr) gob Turbine Bldg. Roof Vent 44 SJ/.EB (mR/hr) /40 13 Flow (sefm) /4,00u - Rx. Bldg. Ventilation Rx. Bldg. Roof Vent Flow 45 Monitor (mR/hr) /

[. 14 (sefm) /74.o00 Service Water Rad Monitor

, ( Rx. Bldg. Negative Press 15 (inches of water vacuum)

.45 46 (eps) 4

/0 l

l 16 Suppression Pool Level (in) -29 OTHER UNIT l 17 Drywell Pressure (psig) .AO Turbine Bldg. Roof Vent i

18 SBGT Flow A (sefm) i O 47 Flow (cefm) 27 19ISBGT Flow B (sefm) M Turbane Bldg. Roof 20 Drvwell H., 4409 (% cone.) o 48 "ent Monitor (uci/sec.) f

. 21 Drywell H: 4410 (% cone.) o 22 Drvwell 0; 4409 (% cone.) /, p g Drywell 0; 4410 (% cone.) At

. 24I A0G Syste:ii Flow (sefm) e eno 25l0ff-Site Power Available V Main Stack Gas Monitor 26 (uci/sec) _

J OE+/

Turbine Bldg. Vent Monitor 27 (uCi/sec) 6'06+3 DRYWELL HIGH RAD MONITOR R/hr 28 D22-RM-4195 - 30 fe El. l /,

29- D22-RM-4196 - 57 fe El. t /2 30 Q22-RM-4197 - 23 f t El. l 5 31 D22-RM-4198 - 57 ft El. I /C l 32 Drywell Temp (*F) l //O N 33 Suppression Pool Temp (*F) l F/,

) RX. BLDG. ROOF VENT RAD MONITOR g Particulate (cpm) /,. ooo_

35 Iodine (epm) aoo l 36 Noble Gas (cpm) /04

1 UNIT 0 l PEP-02.6.21 I

['~'

s Attachment 5 Page 1 of 1 l I j

' EXHIBIT 2.6.21-4 SAFETY PARAMETER DISPLAY SYSTEM (UNIT Jl ) I Ogerable Inoperable Standby Running Yes No Isolated 3 - Not available Time //4'$ )

1 HPCI Flow (gpm) o ,

' ARIA RAD MONITORS mR/hr

_2 Core Spray A Flow (gpm) O 37 Rx. Bldg. 20 f t Airlock /

3 RHR A Flow (gpm) o Rx. Bldg. 50 ft Sample 4 RCIC Flow (gpm) o 38 Station ;l _,

o ~39

~~ 5 Core Spray B Flow (gtm) ~ libc. Bldg. 50 f t Airlock ;L 6 RHR B Flow (gpm) O Rx. Bldg. North of Fuel 7 SLC Injecting A/ 40 Pool JR 8 CRD Flow (gpm) >/00 Between Fuel Fool and 9 APRM % q$6 41 Drywell Ebmosca k 10 Reactor Pressure (psig) 943r Turbine Bldg. Sample 11 Reactor Level (in) /97 42 Station '

B 12 Main Stack Flow Rate (sefm) 66,000 43 SJAE A (mR/hr) ;206 Turbine Bldg. Roof Vent 44'SJAE B (mR/hr) /6/o 13 Flov (sefm) /#,000 Rx. Bldg. Ventilation

,/

~s Rx. Bldg. Roof. Vent Flow 45 Monitor (mR/hr) /

) 14 (sefm) /74,000 Service Water Rad Monitor sd Rx. Bldg. Negative Press 46 (eps) /o 15 (inches of water vacuum) ,;2 6 16 Suppression Pool Level (in) _ Jt 9 OTHER UNIT 17 Drywell Pressure (psig) .ao Turbine Bldg. Roof Vent 18 SBGT Flow A (sefm) I o 47 Flow (sefm) jr 19 SBGT Flow 9 (sefm) O Turbine Bldg. Roof

~

Drywell E! 4409 l 20 (% cone.) o 48 Vent Monitor (uci/sec.) 27 21 Dryvell H 4410 (% cone.) o 22 Drywell 0; 4409 (% conc.) /.7 23 Drywell 0; 4410 (% conc.) 2.s 24 lA0G Systes Flow (sefm) 1 J20 25 l0f f-Site Power Available V Main Stack Gas Monitor 26 (uci/sec) 106+1 Turbine Bldg. Vent Monitor 27 (uci/sec) 6.0 G+ 3 DRYWELL HIGH RAD MONITOR R/hr 28l D22-RM-4195 - 30 ft El. 1 6

29 D22-RM-4196 - 5 7 f t El. l /2 30 022-RM-4197 - 23 ft El. l 5 31 D22-RM-4198 - 57 ft El. I /0 32: Drywell Tecp ('F) { //o __,

33 Suppression Pool Temp ("F) i 16 RX. SLDG ROOF VENT RAD MONITOR 34l Particulate (cpm) /,000 35 Iodine (cpm) 'J200 36 Noble Gas (cpm) /00

UNIT 0 PEP-02.6.21

'~^

Attachment 5 Page 1 of 1 SAFETY PARAME R I PLk S STEM (UNIT 1 )

Ogerable Inoperable Standby Running Yes No Isolated NA - Not available Time /c2 do 1 HPCI Flow (gpm) 4, goo.TisF ' AREA RAD MONITORS mR/hr 2 Core Spray A Flow (gpm) o 37 Rx. Bldg. 20 ft Airlock /

3 RHR A Flow (gpm) O Rx. Bldg. 50 ft Sample 4 RCIC Flow (gpm) Voo 38 Station ;l __

-5 Core Spray B Flow (gpm) o _ 39 Rx. Bldg. 50 ft Airlock 3 6 RHR B Flow (gpm) o Rx. Bldg. North of Fuel 7 SLC Injecting N 40 Pool ;l 8 CRD Flow (gpm) p/00 Between Fuel Pool and 9 APRM % #% 41 Drywell bmd 10 Reactor Pressure (psig) // to Turbine Bldg. Sample 11 Reactor Level (in) /70 42 Station '

3 12 Main Stack Flow Rate (scfm) 66,000 43 SJAE A (mR/hr) /O' Turbine Bldg. Roof Vent 44 SJAE B (mR/hr) 6 l

13 Flow (sefm) /g,000 Rx. Bldg. Ventilation 45 Monitor (mR/hr) /

s Rx. Bldg. Roof Vent Flow

') 14 (r,c fm) /7A,000 Service Water Rad Monitor

\s./ Rx. Bldg. Negative Pre.ss 46 (eps) /0 15 (inches of water vacuum) , .25 16 Suppression Pool Level (in) -Jp,5 OTHER UNIT 17 Dryvell Pressure (psig) ! .J7 Turbine Dldg. Roof Vent 18 SBGT Flow A (sefm) I o 47 Flow (sefm) ][

19 ISBGT Flow B (sefm) O Turbine Bldg. Roof

['

20 'Dryvell H, 4409 (% conc.) o 48 Vent Monitor (uci/sec.) 27

. 21 Drywell H; 4410 (% cone.) 0 22 Dryvell 0; 4409 (% cone.) 4,0 23 Drywell 0; 4410 (% cone.) 0. g

. 24 A0G Systed Flow (sefm) l C 2510ff-Site Power Available V Main Stack Gas Monitor 26 (uci/sec) 9.oe+ /

Turbine Bldg. Vent Monitor l 27 (uci/sec) 5.0S*3 l DRYWELL HIGH RAD MONITOR R/hr l 28 D22-RM-4195 - 30 f t El. i

/0 29 D22-RM-4196 - 5 7 f t El. 1 /F 30 022-RM-4197 - 23 ft El. l 9 31 D22-RM-4198 - 57 ft El. i /G

32. Drvvell Temp ('F) { //5

' [

\

33 Suopression Pool Temp (*F)

RX. BLDG. ROOF VENT RAD i 40 MONITOR l 34 Particulate (cpm) /,000 35 Iodine (cpm) 3do 36 Noble Gas (cpm) /00 l

l

l I

. UNIT 0 l PEP-02.6.21 l fg Attachment 5 Page 1 of 1 iV)

' EXHIBIT 2.6.21-4 SAFETY PARAMETER DISPLAY SYSTEM (UNIT 1) gerable Inoperable S,tandby R,unning Yes No Isolated i 3 - Noe available Time /.2/5 1 HPCI Flow (gpm) O AREA RAD MONITORS 'mR/hr 2 Core Spray A Flow (gpm) O 37 Rx. Bldg. 20 ft Airlock /

3 RHR A Flow (gpm) O Rx. Bldg. 50 fe Sample 4 RCIC Flow (gpm) t/OO _ 38 S ta tion J2 ~

5 Core Spray B Flow (gpm) 0 39 Rx. Bldg. 50 ft Airlock A 6 RHR B Flow (gpm) o Rx. Bldg. Norch of Fuel 7 SLC Injecting N 40 Pool J 8 CRD Flow (gpm) A lho Between Fuel Pool and 9 APRM % 3.5 41 Drywell hnsule, 10 Reactor Pressure (psig) 450 Turbine Bldg. Sample 11 Reactor Level (in)

~

135 42 Station -

3 12 Main Stack Flow Race (sefm) (,(,3 000 43 SJAE A (mR/hr) p' Turbine Bldg. Roof Vent 44 ISJAE B (mR/hr) 5 13 Flow (sefm) /4,000 Rx. Bldg. Ventilation Rx. Bldg. Roof Vent Flow 45 Monitor (mR/hr) /

O 14 (sefm) ~

f r13,000

~

Service Water Rad Monitor 46' (cps) k Rx. Bldg. Negative Press /0 15 (inches of water vacuum) .25 16 Suppression Pool Level (in) - j g , r7 OTHER UNIT 17 Drywell Pressure (psig) , J t, Turbine Bldg. Roof Vent 18 SBGT Flow A (sefm) I o 47 Flow (sefe) I 19 SBGT Flow B (scfm) O Turbine Bldg. Roof l

20 Drvve11 H, 4409 (% cone.) o 48 Vent Monitor (uCi/sec.) I

. 21 Drywell H; 4410 (% cone.) O I

22 Drywell 0; 4409 (% cone.) d,o 23 Drywell 0; 4410 (% cone.) .1, .5

. 24' A0G Systes Flow (sefm) I o l 25l0ff-Site Power Available Y Main Stack Gas Monitor j 26 (uCi/sec) 9.oe + 1 Turbine Bldg. Vent Monitor 27 (uci/sec) 5.o E+ 3 DRYWELL HIGH RAD MONITOR R/hr l 28 D22-RM-4195 - 30 fe El.

l

/1 29 D22-RM-4196 - 57 ft El. I s 30 Q22-RM-4197 - 23 ft El. /./

31 D22-RM-4198 - 57 ft El. 1b 32 Drywell Temp (*F) { /ts

,- 33 Supprersion Pool Temp (*F) l 4/,

RX. BLDG. ROOF VENT RAD MONITOR 34 Particulate (cpm) /,poo 35 Iodine (cpm) Joo l 36 Noble Gas (cpm) /00 l

UNIT 0 PEP-02.6.21 Attachment 5 '

Page 1 of 1 I

O' SAFETY PARAME E IPk EM (UNIT L )

f. erable Inoperable S_tandby Running Yes No Isolated 3 - Not available Time /o73 0 1 HPCI Flov (gpm) '

o AREA RAD MONITORS mR/hr 2 Core Spray A Flow (gpm) o 37 Rx. Bldg. 20 ft Airlock /

3 RHR A Flow (gpm) 0 Rx. Bldg. 50 ft Sample 4 RCIC Flow (gpm) z/oo 38 Station il _ _ ,

"S Core Spray B Flow (gpm) o _39IRx. Bldg. 50 fC Airlock 3

6 RHR B Flow (gpm) o Rx. Bldg. North of Fuel 7 SLC. Injecting N 40 Pool et 8 CRD Flow (gpm) J /00 Between Fuel Pool and

_9.'APRM % J.5 41 Dryvell baje, 10 Reactor Pressure (psig) E'15 Turbine Bldg. Sample 11 Reactor Level (in) '

/g3 42 Station '

O. 3 12 Main Stack Flow Rate (sefm) I.6,000 43 SJAE A (mR/hr) /, '

Turbine Bldg. Roof Vent 44 SJAE B (mR/hr) 4 13 Flow (sefm) /6 000 Rx. Bldg. Ventilation Rx. Bldg. Roof Vent Flow 45 Monitor (mR/hr) /

14 (sefm) /7A,000 Service Water Rad Monitor O' Rx. Bldg. Negative Press 15 Cinches o" water vacuum) ,45 46 (eps) /0 16 Suppression Pool Level (in) - af OTHER UNIT 17 Dryvell Pressure (psig) I , So Turbine Bldg. Roof Vent 18 SBGT Flow A (sefm) i o 47 Flow (sefm) .T~

19'SBGT Flow B (scfm) o Turbine Bldg. Roof l 20- Drvwell H, 4409 (% cone.) 0 48 Vent Monitor (uC1/sec.) I

. 21 Dryvell H; 4410 (% cone.) 0 22 Dryvell 0; 4409 (% cone.) .7, /

23 Dryvell 0; 4410 (% cone.) ,

2, #

. 24! A0G Systes Flow (scfm) i o 251 0ff-Site Power Available V Main Stack Gas Monitor 26 (uci/sec) 4,0E + 1 Turbine 81dg. Vent Monitor 27 (uci/sec) f.06fD ^

DRWELL HIGH RAD MONITOR R/hr 28 D22-RM-4195 - 30 ft El. /7 29 D22-RM-4196 - 57 ft El. I J#

30 022-RM-4197 - 23 fe El. //,

31 D22-RM-4198 - 57 ft El. l 2 32 Dryvell Temp (*F) l /Jo 33 Suppression Pool Temp (*F) l /07 RX. BLDG. ROOF VENT RAD MONITOR 34 Particulate (cpm) /, ooo 35 Iodine (cpm) 'J200 36 Noble Gas (epm) /00

1 UNIT 0 ,

PEP-02.6.21 1 l Attachment 5

)\3 Page 1 of 1 EXHIBIT 2.6.21-4 SAFETY PARAMETER DISPI.AY SYSTEM (UNIT L ) ,

02 erable Inoperable Standby Running Yes No Isolated NA - Not available Time /;2497 1 HPCI Flow (gpm) /> ' ARIA RAD MONITORS mR/hr 2 Core Spray A Flow (gpm) O 37 Rx. Bldg. 20 ft Airlock /

3 RHR A Flow (gpr.) 1500 Rx. Bldg. 50 ft sample 4 RCIC Flow (gpm) goo 38 Station ;t

~$ Core Spray B Flow (gpa) o 39 Rx. Bldg. 50 ft Airlock A 6 RHR B Flow (gpm) 74000 Rx. Bids. North of Fuel i 7 SLC Injecting tv 40 Pool ;t 8 CRD Flow (gpm) > / 00 Between Fuel Pool and 9 APRM % J.4- 41 Drywell no.%oo le 10 Reactor Pressure (psig) 4th) Turbine Bldg. Sample 11 Reactor Level (in) i /40 .42 Station '

O. ;t '

12 Main Stack Flow Rate (scfm) 166,000 43 SJAE A (mA/hr) 5' Turbine Bldg. Roof Vent 44 ISJAE B (mR/hr) 3 13 Flow (sefm) /#3000 Rx. Bldg. Ventilation Rx. Bldg. Roof Vent Flow 45 Monitor (mR/hr) 0. f (sefm)

~ ~

14 /72,000 Service Water Rad Monitor l Rx. Bldg. Negative Press 46 (eps) /0 15 (inches of water vacuum) . ;ts >

16 Suppression Pool Level (in) -372 OTHER UNIT 17 Dryvell Pressure (psig) l . S' Turbine Bldg. Roof Vent 18 SBGT Flow A (sefm) i o 47 Flow (sefm) Jr 19ISBGT Flow B (sefs) D Turbine Bldg. Roof l @

20!Dryve11 H, 4409 (% cone.) O 48 Vent Monitor (uci/sec.) ar 21tDryve11 H; 4410 (% cone.) O 22 Dryvell 0; 4409 (% cone.) J. J 23 Dryvell 0; 4410 (% cone.) J. 4 24 A0G Systes Flow (sefm) i O ,

! 25 lof f-Site Power Available V I

Main Stack Gas Monitor '

26 (uci/sec) I. 0E * '

Turbine Bldg. Vent Monitor 27 (uci/sec) 7.06 fo DRYWELL HIGH RAD MONITOR R/hr 28 D22-RM-4195 - 30 f t El. J?o 29- D22-RM-4196 - 57 ft El. I of 30 022-RM-4197 - 23 ft El. l /f ,

_3_1_D22-RM-4198 - 57 ft El. I J4 32 Drywell Temp ('F) { /JV 33 Suppression Pool Temp ('F) I //S

, RX. BLDG. ROOF VENT RAD l

MONITOR 34 Particulate (cpm) /,000 35 Iodine (cpm) 440 0 36 Noble Gas (cpm) /00 1-+ -- -

UNIT 0 PEP-02.6.21 N

Attachment 5 O' , EXHIBIT 2.6.21-4 Page 1 of 1 SAFETY PARAMETER DISPLAY SYSTEM (UNIT A) 02 erable Inoperable 5,tandby funning Yes No Isolated NA - Not available Time /30d 1 HPCI Flow (gpm) O ' AREA RAD MONITORS .mR/hr 2 Core Spray A Flov (gpm) O 37 Rx. Bldg. 20 ft Airlock oppscale 4;3h RHR A Flow (gpm) 3 7500 Rx. Bldg. 50 fe Sample 4 RCIC Flow (gpm) 400 T._5 Core ~ Spray B Flow (gpm)'~ - ~ O _

38 Station

_ 39 Rx. Bldg. 50 ft Airlock ogg_

to 6 RHR B Flow (gpm) */500 Rx. Bldg. North of Fuel 7 SLC Injecting N 40 Pool 2.

8 CRD Flov (gpu) >/co Between Fuel Pool and

, 9 APRM % a 41 Dryvell N _-A l 10 Reactor Pressure (psig) 900 Turbine Bldg. Sample 11 Reactor Level (in) /qa 42 Station -

o. 2 12 Main Stack Flow Rate (sefm) r/A,ooo 43 SJAE A (mR/hr) 4' '

Turbine Bldg. Roof Vent 44 SJAE B (mR/hr) 2 13 Flow (sefs) /#,o00 Rx. Bldg. Ventilation

, Rx. Bldg. Roof Vent Flow 45 Monitor (mR/hr) dp 14 (sefm) o Rx. Bldg. Negative Press Service Water Rad Monitor 46 (eps) /0 l 15 (inches of water vacuum) . 25 16 Suppression Pool Level (in) .71.5 OTHER UNIT 17 Dryvell Pressure (psig) , (, Turbine Bldg. Roof Vent 18 SBGT Flow A (sefm) I A goo 47 Flow (sefm) I 19 SBGT Flow B (sefs) 3000 Turbine Bldg. Roof l

20 Drvvell H, 4409 (I cone.) o 48 Vent Monitor (uci/sec.) _f

. 21 Dryvell H; 4410 (I cone.) o ,

22 Dryvell 0; 4409 (% cone.) .m , a 23 Dryvell 0; 4410 (% cone.) ,a s

. 24 A0G Systei Flow (sefa) 1 0

25l0ff-Site Power Available V Main Stack Gas Monitor '

26 (uci/sec) /. 06 t '/ ,

Turbine Bldg. Vent Monitor ;

27 (uci/sec) /., ,0 6 +O DRYVELL HIGH RAD MONITOR R/hr 28 D22-RM-4195 - 30 ft El. /0 l 29 D22-RM-4196 - 57 ft El. 17 30 Q22-RM-4197 - 23 ft El. /4 j 31 D22-RM-4198 57 fe El. /0 l 32 Dryvell Temp (*F) l /J.7 l 33 Suppression Pool Temp ('F) 1 /2A RX. BLDG. ROOF VENT RAD MONITOR 34 Particulate (cpm) foo 35 Iodine (cpm) /d0 36 Noble Gas (cpm) (so ,

f UNIT 0

,_s PEP-02.6.21

[ Attachment 5

\ Page 1 of 1

, EXHIBIT 2.6.21-4 SAFETY PARAMETER DISPLAY SYSTEM (UNIT 1)

Ogerable Inoperable Standby Running Yes No Isolated NA - Not available Time /3/5F 1 HPCI Flow (gpm) O ' AREA RAD MONITORS mR/hr 2 Core Spray A Flow (gpm) O 37 Rx. Bldg. 20 ft Airlock (4Fseate Nigh 3 RHR A Flov (gpm) 7500 Rx. Bldg. 50 ft Sample 4 RCIC Flow (gpm) o 38 Station

- 5 Core S~ pray B Flow (gpm) -~~ O 39 Rx. Bldg. 50 ft Airlock O/toh le 4 4 6 RHR B Flow (gpm) 7500 Rx. Bldg. North of Fuel 7 SLC Injecting b/ 40 Pool g 8 CRD Flow (gpm) > /00 Between Fuel Fool and 9 APRM % o 41 Dryvell Phocrea le.

10 Reactor Pressure (psig) 9 10 Turbine Bldg. Sample 11 Reactor Level (in) 14 6 42 Station '

O. 4%

12 Main Stack Flow Rate (sefm) e72.ooo 43 SJAE A (mR/hr) 4/'

Turbine Bldg. Roof Vent 44ISJAE B (mR/hr) a 13 Flov (sefm) /sV. 000 Rx. Bldg. Ventilation p Rx. Bldg. Roof Vent Flow 45 Monitor (mR/hr) 0. 7

( 14 (sefe) O Service Water Rad Monitor

}' Rx. Bldg. Negative Press -

46 (eps) /d 15 (inches of water vacuum) ?>O 16 Suppression Pool Level (in) -47 OTHER UNIT 17 Dryvell Pressure (psig) ,7 Turbine Bldg. Roof Vent 18 SSGT Flow A (sefm) I shaco 47 Flov (sefm) 2I 19 lSBGT Flow B (sefm) 5000 Turbine Bldg. Roof g 20lDryvell H, 4409 ( cone.) o 48 Vent Monitor (uCi/sec.) ][

. 21iDryvell H; 4410 (% cone.) o 22 Dryvell 0: 4409 (% cone.) 3,3 23 Dryvell 0; 4410 (% cone.) ;g, 6, 24 A0G Systes Flow (sefm) I o 25l0ff-Site Power Available V Main Stack Gas Monitor '

26 (uci/sec) /, 0 6 + 7 Turbine Bldg. Vent Monitor 27 (uci/see) 6.oa+ 0 DRYVELL HIGH RAD MONITOR R/hr 28 D22-RM-4195 - 30 f t El. $'

29 D22-RM-4196 - 57 ft El. I 4 30 022-RM-4197 - 23 ft El. l 4 31 D22-RM-4198 - 57 ft El. I G 32l Dryvell Temp ('F) { /50 33 Suppression Pool Temp ('F) I /;us RX. BLDG. ROOF VENT RAD MONITOR 34 Particulate (cps) 700 35 Iodine (cpm) /do 36 Noble Gas (cpm) 40

UNIT O '

PEP-02.6.21 Attachment 5 ;

, EXHIBIT 2.6.21-4 SAFETY PARAMETER DISPLAY SYSTEM (UNIT 1 )

gerable I,noperable S_tandby R,unning Yes No Isolated

_ g - Not available Time /33C 1 HPCI Flow (gpm) /) ' AREA RAD MONITORS .mR/hr 2 Core Spray A Flow (gpm) O 37 Rx. Bldg. 20 ft Airlock RHR A Flow (gpm) ogm t, Hg 3 rJ600 Rx. Bldg. 50 fe Sample 4 RCIC Flow (gpm) #00 38 Station

_ 39 Rx. Bldg. 50 ft Airlock hr, Q _

- 5 Core Spray B Flow (gpm) -- d /o 6 RHR B Flow (gpm) '1500 Rx. Bldg. North of Fuel 7 SLC Injecting N 40 Pool 2 8 CRD Flow (gpe) A/bo Between Fuel Fool and 9 APRM % o 41 Drywell h je_

10 Reactor Pressure (psig) 6'75 Turbine Bldg. Sample 11 Reactor Level (in) l '7a 42 Station '

O..R 12 Main Stack Flow Rate (sefm) 9.2.000 43 SJAE A (mR/hr) 3' Turbine Bldg. Roof Vent 44- SJAE B (mR/hr) m 13 Flow (sefm) /4/,000 Rx. Bldg. Ventilation Rx. Bldg. Roof Vent Flow 45 Monitor (mR/hr) O. f 14 (sefm) O Service Water Rad Monitor Rx. Bldg. Negative Press 46 (eps) /0

-( 15 (inches of water vacuum) >D 16 Suppression Pool Level (in) ,;1') OTHER UNIT 17 Dryvell Pressure (psig) ,P Turbine Bldg. Roof Vent 18 SBGT Flow A (sefm) I_sooo 47 Flow (sefm) f 19 SPGT Flow B (sefs) 3000 Turbine Bldg. Roof

[.

i 20, Drvve11 H, 4409 (2 cone.) a 48 Vent Monitor (uci/sec.) I

. 21'Dryvell H; 4410 (2 cone.) 0 22 Dryvell 0; 4409 (% cone.) g2. 4 -

23 Dryvell 0; 4410 (% coric.) 3.rf

. 24 A0G Systes Flow (sefm) 0 25 Off-Site Power Available V Main Stack Gas Monitor 26 (uCi/see) 1,oE4 7 Turbine Bldg. Vent Monitor 27 (uci/sec) 4.dE+O DRYVELL HIGH RAD MONITOR R/hr 28 D22-RM-4195 - 30 fe El. l 3

29 D22-RM-4196 - 57 ft El. I L 30 022-RM-4197 - 23 ft El. 3 31 D22-RM-4198 - 57 ft El. 6 32 Dryvell Temp ('F) { /n 33 Suppression Pool Temp ('F) I ///,

RX. BLDG. ROOF VEhT RAD MONITOR s 34 Particulate (cpm) '700 35 Iodine (epm) /00 36 Noble Gas (cpm) 40

(JNIT 0 PEP-02.6.21 Attachment 5

, EXHIBIT 2.6.21-4 SAFETY PARAMETER DISPLAY SYSTEM (IJNIT L) gerable Inoperable Standby Running Yes No Isolated NA - Not available Time /3g5 1 HPCI Flow (gpm) C AREA RAD MONITORS .mR/hr 2 Core Spray A Flow (gpm) o 37 Rx. Bldg. 20 ft Airlock of.fe,L, 4l;g 3 RHR A Flow (gpm) /7500 Rx. Bldg. 50 fe Sample 4 RCIC Flow (gpm) O 38 Station

~5 Core S) ray B Flow (gpm) ~ o 39 Rx. Bldg. 50 ft Airlock offsul. H4k(D

6 RHR S riov (gpm) 750c Rx. Bldg. North of Fuel 7 SLC Injecting u 40 Pool k 8 CRD Flow (gpa) >100 Between Fuel Pool and 9 APRM % 0 41 Dryvell h(

10 Reactor Pressure (psig) /,40 Turbine Bldg. Sample 11IReactor Level (in) /40 42 Station '

O. .;t.

12 Main Stack Flow Rate (sefm) 71000 43 SJAE A (mR/hr) 3' Turbine Bldg. Roof Vent 44 SJAE B (mR/hr) 1 13 Flow (scfa) /4 000 Rx. Bldg. Ventilation Rx. Bldg. Roof Vent Flow 45 Monitor (mR/hr) D.F 14 (sefm) O Service Water Rad Monitor ,

Rx. Bldg. Negative Press 46 (eps) /D

\ 15 (inches of water vacuum) >0 16 Suppression Pool Level (in) -J7 OTHER UNIT 17 Dryvell Pressure (psis) 1 ,f Turbine Bldg. Roof Vent 18 SBGT Flow A (sefm) iMo00 47 Flow (sefm) 1 19 SBGT Flow B (sefs) 4000 Turbine Bldg. Roof ['

~20 Drvve11 H, 4409 (% conc.) o 48 Vent Monitor (uci/sec.) 1

. 21 Dryvell H; 4410 (! conc.) 0 22 Dryvell 0; 4409 (% cone.) 7, 5 23 Dryvell 0; 4410 (% cone.) 3, f

. 24 AOG Systes Flow (sefs) l O 25l0ff-Site Power Available V ,

Main Stack Gas Monitor '

l 26 (uCi/sec) /064 7 Turbine Bldg. Vent Monitor '

27 (uci/sec) V.oE*o DRYWELL HIGH RAD MONITOR R/hr 28 D22-RM-4195 - 30 fe El. 3 '

29 D22-RM-4196 - 57 ft E1. L g 30 Q22-RM-4197 .23 fe El. l 8 31 D22-RM-4198 - 57 ft El. I 6 32 Dryvell Temp ('F) l // f 33 Suppression Pool Temp ('F) l //m RX. BLDG, ROOF VENT RAD MONITOR

^

34 Particulate (cpm) ?Co 35 Iodine (com) /00 36 Noble Gas (cpm) 40

i 1

UNIT 0 !

PEP-02.6.21 O , EXHIBIT 2.6.21-4 Attachment 5 SAFETY PARAMETER DISPLAY SYSTEM (UNIT 1 )

gerable I_ nope rable S,candby Running Yes No Isolated 1

3 - Not available Time /M 1 HPCI Flow (gpm) o _ ' AREA RAD MONITORS 'mR/hr 2 Core Spray A Flow (gpm) O 37 Rx. Bldg. 20 ft Airlock RHR A Flow (gpm) ophie g i 3 9500 Rx. Bldg. 50 ft Sample 4 RCIC Flow (gpm) o 38 Station 5 Core S > ray B"Flow (gpm) -' o ~ 39 Rx. Bldg. 50 ft Airlock Offwie l0 Q

6 RHR S riov (gpm) 9500 Rx. Bldg. North of Fuel 7 SLC Injecting n 40 Pool 8 CRD Flow (gpm) 1

> /00 Between Fuel Fool and 9 APRM %

10 Reactor Pressure (psig) q00 0 41 Drywell Turbine Bldg. Sample DhnWk 11 Reactor Level (in) I 10 4 42 Station '

O . a.

12 Main Stack Flow Rate (sefm) (la .c oo 43 SJAE A (mR/hr) E' ;

Turbine Bldg. Roof Vent 44 SJAE B (mR/hr) 1 ,

13 Flow (sefm)- 14,000 Rx. Bldg. Ventilation Rx. Bldg. Roof Vent Flow 45 Monitor (mR/hr) O. f (sefm) 14 0 Service Water Rad Monitor Rx. Bldg. Negative Press 46 (eps) 10 1

15 (inches of water vacuum) >c 16 Suppression Pool Level (in) _ 29 __

OTHER UNIT ,

17 Dryvell Pressure (psig) l 5 Turbine Bldg. Roof Vent l 18 SBGT Flow A (sefm) I3000 47 Flow (sefm) I l

19ISBGT Flow B (sefm) 3000 Turbine Bldg. Roof 20 Drvve11 H, 4409 (% cone.) D 4_8 Vent Monitor (uci/sec.) I ;

. 21 lDrywell H; 4410 (1 cone.) o '

22IDryvell 0; 4409 (% cone.) a,5 23 Drvve11 0; 4410 (% cone.) 1. 0)

. 24 A0G Syste:ii Flev (sefs) 1 0 25l0ff-Site Power Available N Main Stack Gas Monitor '

26 (uci/see) 1.ba&O Turbine Bldg. Vent Monitor 27 (uci/sec) 4.0E+O '

DRYWELL HIGH RAD MONITOR R/hr 28 D22-RM-4195 - 30 ft El. 3 29 D22-RM-4196 - 57 ft El. I 5 30 Q22-RM-4197 - 23 ft El. 3 l D22-RM-4198 - 57 fc El.

~

31 L 5 -

32 Dryvell Temp ('F) l (IB ,

l 33 Suppression Pool Temp (*F) I lD9 l RX. BLDG. ROOF VENT RAD l MONITOR 34 Particulate (cpm) 900 35 Iodine (epm) 100 36 Noble Gas (epm) Iso

UNIT 0 l PEP-02.6.21 I O ,. EXHIBIT 2.6.21-4 Attachment 5 l SAFETY PARAMETER DISPLAY SYSTEM (UNIT .2, )

02 erable Inoperable S,tandby R,unning Yes No Isolated 3 - Not available Time ////S 1 HPCI Flow (gps) o ' ARIA RAD MONITORS mR/hr I 2

3 Core Spray A Flow (gpe)

RHR A Flev (gpm) 7esoo 0 37 Rx. Bldg. 20 ft Airlock Rx. Bldg. 50 fe Sample wwg 4 RCIC Flow (gpm) O 38 Station

~5 Core S~sray B Flow (gpa)' ~~ 0 39 Rx. Bldg. 50 ft Airlock ofFsatic Q_._.

to

, 6 RHR 8 riov (gpm) 9%c Rx. Bldg. North of Fuel 7 SLC Injecting N 40 Pool , 2 8 CRD Flow (gpm) >100 Between Fuel Fool and 9 APRM % O 41 Dryvell 10 Reactor Pressure (psig) '70s Turbine Bldg. Sample Thwah 11 Reactor Level (in) Mo 42 Station .

O.4 12 Main Stack Flow Rate (sefm) 01000 43 SJAE A (mR/hr) F Turbine Bldg. Roof Vent 44ISJAE B (mR/hr) /

13 Flow (sefs) 14,660 Rx. Blds. Ventilation 14 Rx. Bldg. Roof Vent Flow (sefm)

D 45 Monitor (mR/hr)

Service Water Rad Monitor CL

~

Rx. Bldg. Negative Prers 46 (eps) /d 15 (iriches of water vacuum) - >0 .

16 Suppression Pool Level (in) _. 31 OTHER UNIT 17 Dryvell Pressure (psig) , .3 Turbine Bldg. Roof Vent 18 SBGT Flow A (sefs) 19 SBGT Flow 5 (sefs) i300o 47 Flow (sefs) I 3o00 Turbine Bldg. Roof l 20 Drvve11 H, 4409 (I cone.) O 48 Vent Monitor (uci/sec.) l' 2_1 Dryvell H; 4410 (I cone.) 0 ,

22 Dryvell 0; 4409 (% cone.) .7. .g ;

i 23 Dryvell 0; 4410 (% cone.) 5. o

. 24 AOC Systei Flov (sefs) 1 0 25iOff-Site Power Available V ,

Main Stack Gas Monitor '

26 (uci/sec) 1.o6 6 1 '

Turbine Bldg. Vent Monitor 27 (uci/sec) #.06# O DRYWELL HIGH RAD MONITOR R/hr 28 D22-RM-4195 - 30 ft El. i 5 29 D22-RM-4196 - 57 ft El. I 5 30 022-RM-4197 - 23 fe El. 3 l

31 D22-RM-4198 - 57 ft El. 5 32 Dryvell Temp ('F) { /CE 33 Suppression Pool Temp ("F) l /05 l RX. BLDG, ROOF VENT RAD l MONITOR ___

i 34 Particulate (cpm) 700 35 Iodine (cpm) /40 36 Noble Gas (cpe) 4r0

1 l

UNIT 0 PEP-02.6.21 l

Attachment 5

, EXHIBIT 2.6.21-4 SAFETY PARAMETER DISPLAY SYSTEM (UNIT L )

Ogerable Inoperable Standby Running Yes No Isolated NA - Not available Time /4(d()

1 HPCI Flow (gpm) o AREA RAD MONITORS .mR/hr 2 Core Spray A Flow (gpm) o 37 Rx. Bldg. 20 ft Airlock orP_s t ,

RHR A Flow (gpm) h 3 93roo _ Rx. Bldg. 50 ft Sample 4 RCIC Flow (gpm) O 38 Station

- 5 Core S1 ray B Flow (gpm) ~~ CFFsyde $dft_

o _ 39 Rx. Bldg. 50 ft Airlock 10 6 RHR 8 flow (gpm) 7500 Rx. Bldg. North of Fuel 7 SLC Injecting // 40 Pool ;l a CRD Flow (gpm) 60 Between Fuel Pool and 9 APRM % o 41 Drywell h w le, 10 Reactor Pressure (psig) 7/o Turbine Bldg. Sample 11 Reactor Level (in) i

/4o 42 Station -

6t a 12 Main Stack Flow Rate (scfm) 74, oop 43 SJAE A (mR/hr) ap' Turbine Bldg. Roof Vent 44 SJAE B (mR/hr) /

i 13 Flow (sefs) /4f,M10 Rx. Bldg. Ventilation Rx. Bldg. Roof Vent Flow 45 Monitor (mR/hr) 0. 9 14 (sefm) -

o Service Water Rad Monitor Rx Bldg. Negative Press 46 (eps) /d i 15 (inches of water vacuum) . ;15 16 Suppression Pool Level (in) - ;11 OTHER UNIT '

17 Drywell Pressure (psis) i ,3 Turbine Bldg. Roof Vent '

18 SBGT Flow A (sefm) I,gooo 47 Flow (sefs) C' 19 ISBGT Flow B (sefs) 5000 Turbine Bldg. Roof g 20 Drywell H, 4409 (% cone.) o 48 Vent Monitor (uCi/sec.) CI <

. 21 Drywell H; 4410 (! cone.) o 22- Drywell 0; 4409 (% cone.) 22. a 23 Drywell 0; 4410 (% cone.) g.0

. 24 AOG Systed. Flow (sefs) i O

25l0ff-Site Power Available y Main Stack Gas Monitor '

i 26 (uci/sec) /.og A 7 I

Turbine Bldg. Vent Monitor 27 (uci/see) M44 +0 DRYWELL HIGH RAD MONITOR R/hr 28- D22-RM-4195 - 30 ft El. l 3

I 29 D22-RM-4196 - 5 7 f t El. l 5 30 i O22-RM-4197 - 23 f t El. 3 31 D22-RM-4198 - 57 ft El. l 5

32 Dryvell Temp ('F) l /00 33 Suppression Pool Temp ('F) I fo / '

RX. 8LDG. ROOF VENT RAD MONITOR l 34 Particulate (cpm) 700 35 Iodine (cpm) A90 36 Noble Gas (cpm) tro

l UNIT 0 ,

PEP-02.6.21 '

Attachment 5 EXHIBIT 2.6.21-4 SAFETY PARAMETER DISPLAY SYSTEM (UNIT 1 )

02 erable Inoperable 5,tandby R,unning Yes No Isolated 3 - Not available Time /4/4/6 1 HPCI Flow (gpm) O AREA RAD MONITORS .mR/hr 2 Core Spray A Flow (gpm) o 37 Rx. Bldg. 20 ft Airlock RHR A Flow (gpm) swat,_ Migh 3 75oo Rx. Bldg. 50 ft Sample 4 RCIC Flow (gps) 0 38 Station oppa Q_

-5 Core S stay B Flow (gpm) o 39 Rx. Blds. 50 fC Airlock fo 6 RHR 8 riov (gpm) q<oo Rx. Bldg. North of Fuel 7 SLC Injecting A/ 40 Pool 8 CRD Flow (gpm) 3 do Between Fuel Pool and 9 APRM % o 41 Drywell hale 10 Reactor Pressure (psig) 7 /_4- Turbine Bldg. Sample i

11 Reactor Level (in) I /14 42 Station '

O. A 12 Main Stack Flow Rate (sefm) //J u o 43 SJAE A (mR/hr) m' i

Turbine Bldg. Roof Vent 44 SJAE B (mR/hr) /

13 Flow (sefs) /$.doo

/

Rx. Bldg. Ventilation Rx. Bldg. Roof Vent flow 45 Monitor (mR/hr)

O 0, p (sef'n) 14 O Sewice Water Rad Monitor Rx. Bldg. Negative Press 46 (eps) /0 -

15 (inches of w~ater vacuum) . 75 16 Suppression Pool Level (in) -J1 OTHER UNIT 17 Dryvell Pressure (psig) .J Turbine Bldg. Roof Vent 18 SBGT Flow A (sefm) a 3000 47 Flow (sefm) 7 19(SBGT Flow B (sefs) 3000 Turbine Bldg. Roof 20lDrvve11 H, 4409 cone.) I {

( o 48 Vent Monitor (uCi/sec.)

. 21JDrywell H; 4410 (2 cone.) o _

22(Dryvell 0; 4409 (% cone.) A.7 23 Dryvell 0; 4410 (% cone.) 3,/

, . 24 A0G Systen Flow (sefs) i o

25 lcf f-Site Power Available V Main Stack Gas Monitor 26 (uci/sec) /.o M 7 Turbine Bldg. Vent Monitor 27 (uci/sec) f/.o EfC DRWELL HIGH RAD MONITOR R/hr 1 28: D22-RM-4195 - 30 ft El. 3 ,

29- D22-RM-4196 - 57 ft El. I 5

30 Q22-RM-4197 - 23 ft El. 3 31 D22-RM-4198 - 57 ft El. 5 32 Drywell Temp ('F) /00 33 Suppression Pool Temp ('F) l 47 RX. BLOG. ROOF VENT RAD MONITOR 34 Particulate (cpm) 900 35 Iodine (cpm) /od 36 Noble Gas (cpm) 60

UNIT 0 PEP-02.6.21 Attachment 5

\ EXHIBIT 2.6.21-4 SAFETY PARAMETER DISPLAY SYSTEM (UNIT A )

02 erable Inoperable S,tandby Running Yes No Isolated NA - Not available .

Time /500 1 HPCI Flow (gpm) l o ' AREA RAD MONITORS 'mR/hr 2 Core Spray A Flow (gpm) o 37 Rx. Bldg. 20 ft Airlock h,I,. h 3 RHR A Flov (gpm) 7600 Rx. Bldg. 50 ft Sample 4 RCIC Flow (gpm) o 38 Station

~5 Core Spray B Flov (gpm) O 39 'Rx. Bldg. 50 ft Airlock offwf< kA_ _

/c 6 RHR B Flow (gpo) r>500 Rx. Bldg. North of Fuel 7 SLC Injecting ,

N 40 Fool 4 8 CR.D Flow (gpm) /,o Between fuel Pool and 9 APRM % o 41 Dryvell 10 iteactor Pressure (psig) bn=>ce lt 7ao Turbine Bldg. Sample 11 Reactor Level (in) /92 42 Station '

o, ,o 12 Main Stack Flow Rate (sefm) 7a,000 43 SJAE A (mR/hr) a' Turbine Bldg. Roof Vent 44lSJAE B (mR/hr) /

13 Flow (sefm) /L ooo R'x. Bldg. Ventilation R:5. Bldg. Roof Vent Flov 45 Monitor (mR/hr) O, P (sefe)

~

14 O Service Watar Rad Monitor Rx. Bldg. Negative Press 46 (cps) /0 x 15 (inches of water vacuum) .45 16 Suppression Pool Level (in) .;lt 1 OTHER UNIT 17 Dryvell Pressure (psig) d Turbine Bldg. Roof Vent 18 SBGT Flov A (scfm) iBooo 47 Flow (sefm) I 19lSBGT Flow B (sefs) B0o0 Turbine Bldg. Roof g

( 20(Drvve11 H, 4409 (% cone.) o~ 48 Vent Monitor (uCi/sec.) T f . 21 {Dryvell H; 4410 (% cone.) 0 l 22iDrvvell 0; 4409 (% cone.) 2. P 23 (Dryvell 0; 4410 (% cone.) S,/

l 24lA0G Systed Flow (sefm) l o 2510f f-Site Power Available V Main Stack Gas Monitor '

26 (uCi/sec) /. o& e 4 Turbine Bldg. Vent Monitor '

i 27 (uci/sec) 4/.o E4 0 DRYWELL HIGH RAD MON 1 TOR R/hr 28 D22-RM-4195 - 30 ft El. 3 29 D22-RM-4196 - 57 ft El. I 6 30 Q22-RM-4197 - 23 ft El. 3 31 D22-RM-4198 - 57 ft El. 6 32 Dryvell Temp ('F) l 92 33 Suppression Pool Temp ('F) I 94 RX. BLDG. ROOF VENT RAD j l MONITOR

_34 Particulate (cps) /J00 l 35_ Iodhe (cpm) /do l 36 Noble Gas (cpm) 40 l

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N0lSS38dnS

( BRUN3 FICK ANNUAL EMERGENCY EXERCISE

( (UNIT 2 REACTOR BUILDING RADIOLOGICAL CONDITIONS)

Prior to 1300 hours0.015 days 0.361 hours 0.00215 weeks 4.9465e-4 months , all radiological conditions in the Unit 2 Reactor Building will be "as read." From 1300 hours0.015 days 0.361 hours 0.00215 weeks 4.9465e-4 months until drill termination (except in the North and South 3HR rooms, where radiation levels will increase at 1245 hours0.0144 days 0.346 hours 0.00206 weeks 4.737225e-4 months ), radiological conditions will be elevated due to the following:

- Dumping of reactor coolant into the reactor building due _ to the scram discharge volume failure.

- Buildup of radioactive material in the Standby Gas Treatment -

System.

- Operation of RHR loops A and B.

The following attachments provide radiation and airborne radioactivity levels in affected areas of the Reactor Building.

After 1300 hours0.015 days 0.361 hours 0.00215 weeks 4.9465e-4 months contamination surveys og the Reactor Building - 17 ft.,

20 f t.,

and 50 f t. levels are 500,000 DPMf100 cm. On the 80 ft. level contamination surveys show 10,000 DPM/100 cm.

O i

J I

r J

i (87-6HRG/pcj)

l .

l

, IN-PLANT RADIOLOGICAL SURVEY RESULTS UNIT 2 REACTOR BUILDING

-17' ELEVATION (SOUTH RHR) i Time: 1245 to 1500 Hours Note: All readings in nR/hr i

l I

I

~

NcATH > 1 l

. k i !! "B" CRD PUMP I 'o l

"A" CRD PUMP c l

SUMP [

t

< % ill l womai I

=

Sja l i

l 2000 -

}

"D" RHR PUMP 7k D > 4ewl HFCI i "B" RHR' PUMP ROOM ,

COOO ?

I l

t t

l 4

h e

I e

. IN-PLANT RADIOLOGICAL SURVEY RESULTS UNIT 2 REACTOR BUILDING

-17' ELEVATION (NORTH RHR)

Time: 1245 to 1500 hours0.0174 days 0.417 hours 0.00248 weeks 5.7075e-4 months Note: All readings in mR/hr 1

I l

l, I

i E

l NO RTH y L ks <j l

i

\ !

e 4-RBCDT Heat 6 1 Enchanger ,

,hSED1.

\ Roce l5M !

v ,

[

Il 2000 fee -

ll ,

6- W~ U U lll!! 8 ' t ;

l Cooo ,

?; RH PLPit

/ IM .

'l Cj '

4000 2 A R+ PW:

m y' '

?C l t

H7:. F.3y & ,o

'{ -FJ ,

Orr GAS DRAIN TA9 ,

/ C

\

(f _

b y-,.--,- ,_,,- . . . .. -

.g ...-.----.7..~..- ... .. . - . . . , . = . . . . . - . . - . . - ~ . - . . . . . _ . .

-IN-PLANT RADIOLOGICAL SURVEY RESULTS '

UNIT 2 REACTOR BUILDING I 50' ELEVATION :

1300 to 1500 hours0.0174 days 0.417 hours 0.00248 weeks 5.7075e-4 months

~

Time: -

Note: All readings in mR/hr f i.

?

i l l

l. i

f 6

I t

)

I i

4 i

I- I o

u =

l 1 i g

5 '

i l f 0 l' 3 o 0 0 &

l [~

~e "U u a. !

C 4

l j

- a

=

f MAN $g i O

5 -g l

f, if

_" w x I j

n -

E- &

= .I h" d' -

9 4 l .

j - ;

ELEVAtont,4 l y

}- g -

le g >

STAinwsu . 0 !

i t -

i i,0 0 I 3 IIB - i :

TO'NE AfdLOUL I g

i i

i

.i i ;

I l

l I 3

i a

. IN-PLANT RADI0 LOGICAL SURVEY RESULTS-UNIT 2 REACTOR BUILDING

. 80' ELEVATION-(EAST SIDE):

?

q Time: 1300, to 1500 hours0.0174 days 0.417 hours 0.00248 weeks 5.7075e-4 months Note: All readings in mR/hr- ,

t

=========- _-/ % -V .

SLC D I i

I b

O '

a l !

J l ;

I 0 S l -

b a

O i ~-

a 0

NORTH j I !

A >

~

ELECTRICAL ;

OUTLETS

]

i , ;

d L_J I-' l !

5 4

$- t i

i i t t ,

f i

.. [

, 3 i

f l

+

l 4

I I e i I

. . . . . . , . , _ - - . . _ - - -- _ _ - , . - . . . ..- . . . _ .. _ _.. -. - .. . _ . _ -_ - .. ._ _ .-.. .__ __. ~ . _ -

[

-IN-PLANT RADIOLOGICAL SURVEY RESULTS -!

t - t/: . UNIT 2 REACTOR BUILDT.NG I I 20' ELEVATION ;

ji, >

-M g- l b' :; . ; Time: 1300 to-1500 hours i Note: All readings' in mR/hr y

, o ,i t

, i t j b ' \' l q ,

8 1, ,- (8 ' N' ' > l

!;f c , i b ). l h i f- .i L

[ A 44&4 i 3- -

j 2ooo See i 5

- p- = i g- -

g =_al

-. . 4 C '

ff E l

F r_

E W'V gv %o

~

N' l j

r i N ' T- ji ,

i l I e i se,e

, <l ;

I. ; ww 1, -d, .

.q r

i-J /_.

s ,

b \

/9' i

{} t :i I

[ t N i

4

,j = 8440 -

( -

gj I- = l (7 -

1 2

. .t. L - - .L __, ,

'4 f- , ] f, seee seee !

O *** O 2 ,

i ;

i l

t t

l l

0

l' 4

] !

UNIT 2 REACTOR BUILDING AIR SAMPLES Air samples obtained in the Unit 2 Reactor Building af ter 1300 hours0.015 days 0.361 hours 0.00215 weeks 4.9465e-4 months will indicate the following activities:

l l Location Gross Activity (uCi/co) MPC !

-17' Elevation (all) 4.46 E-6 12 .

20' Elevation (south side) 3.22 E-4 140 l 20' Elevation (north side) 6.87 E-5 30 -

50' Elevation (all) 6.48 E-8 0.7 -

, 80' Elevation (all) 3.28 E-9 0.06 :

i i

i !

i l.

e I i l I !

l l s

1 !

l I l l

l :

l l l

1 i

l

! I i !

i (87-6HRG/poj) t L

.. . - - - . . , . - _ ._ . _ _ . - _ - - . _ - _ . . . . _ . _ - _ . , . _ .._..~,.,,,-._,,-.,-.,,--....,,-.-,.n,,,-,'

_ g:

[' )t BRUN5fICE ANNUAL EMLPMGENCY EIERCISE (11/17/87)

(#f (IURBINE 1RIILDING RADIOLOGICAL CONPITIONS)

Between 1100 and 1230 hours0.0142 days 0.342 hours 0.00203 weeks 4.68015e-4 months , a quantity of radioactive steam is released into the Turbine Building due to a Main faeam Isolation Valve failing to

. close. The following survey maps indicate expected dose rates (mR/hr). Areas not covered by survey maps will be considered to have dose rates "as read."

At all other times during the drill, Turbine Building dose rates will be "as read."

Any air samt activity of 8x10"ges taken in the Turbine Building will indict.te gross uC1/cc.

~

- Particulate MPC ratio: 0. 4 (Between 1100 and

- Iodine MPC ratio: 0. 8 1;!30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months )

At all other times, air sample results will be "as ' read." ,

Contamination surveys af ter 1100 hours0.0127 days 0.306 hours 0.00182 weeks 4.1855e-4 months will indicate T0,000 lPM/1002 e,

in the Turbine Building. +

h w

f

.~

4 w

G 4 .

b

. - - . , , . - -- . _ _ , _ , _ . . .+,,, --- , - g.

?

. BRUNS *11CK ST W. ELECTRIC PLANT Survey No. !

RADIOLC,CICAL SURVEY RWP No.

U/1 Breezevty c 4

~

, bt?Oh 5sCo t h kMMQf}( &g=g(zg3goQ! [ , j=gg 4

, ova - l DATE: /(/e 7 /M TIME: , a w, DOSE RATE: '

CONTAMINATION:

INS *. TYPE: INST.

SURVEY BY: SERIAL NO: ETT:

REVIEVED BY: a"'^" PO'wT.R : BKC:

Ail flos6 's, 's .w f1/hr 0 g. a m

^

SMEAR RZ.SC T.s Point DPM/100 W 6-

! l

{ l t n -

t (v) I ' n

s. ,' I i i

l I I t

l i l I i l

~ '

l . .

l j,

'} !

l :r=

l i

[L bL I -

@ 2 i i i i .

y I ?

= 1 I wm E i l

i i. , , .

l l - i I'

(9) h l 1 1 .

l - . I i i'

I r

l ) NNI.5 :

(

i D:se hate head:n.s: Gene ra. Area Re ac:ngs e ee ce :nd:ca-l sj ted in mK/hr at the Irrat;en : 4 'g e n . Centac, d:ngs are-te be indicated :n tah ' n t and den,,:ed v.th an asterisx <*l.

,;) C e n t ari .a t i ,'- hesults: Recorded in DPM iou c:rl Indicate a.d circ'e .ccat:c -

l :!ET 's : VI;;<E!.K-0;Us l

l

BRUNSVICK STEAM ELECTRIC FMJff Survey No.

m RADIOLOGICAL SURVEY RWP. No.

V) Unit 2 Breeseway LNnuen knwru E,mree.'ev Ewer.e-

,, oo -

DATE: __ h/17It? TIME:_ saw DOSE RATE: v CONTAMDIATION:

INST. TYPE: INST.

SURVEY BY: SERIAL NO: EFF

,REVIEVED BY:

REACTOR POWER: REC:

i i

) O i

I i SMEAR RESULTS g OOO O O O Poine prufiooe ,

00 0 00 J

~

(1 SS gt,y C3 g" SJAZ

- 000

s'

\

l

.D M -

T i

(m l

Cond.

Ali dow .-a k3 Pumps

,- .n g /A r A :

RTP B )

i Cond.

O

~

Booster Pymps N -

,s I i Conden,sor _

Bay _ j I

- i O

g NOTES: (1) Dose Rate Readings: General Area Readings are to be indica-ted in mR/hr at the location taken. Contact readings are to be indicated in mR/hr and denoted with an asterisk (*).

(2) Contamination Results: Recorded in DPM/100 cm . Indicate 2 and circle location. !

1 l BSEP/Vol.'VIII/E&RC-0100

l 1

.. l BRUNSUICK STEAM ELECTRIC PLANT Survey No.

RADIOLOGICAL SURVCY RWP No. I I

Opuusw.cz Anusoi. Encuenct l~xt nc,sa U/1 TB 38' DATE: 11/r r7/?'7 TIME: _i(((( DOSE RATE: CONTAMINATION:

INST. TYPE:

INST.

SURVEY BY: SERIAL NO: EFF:

REVIIVED BY: REACTOR POVER: EKG:

pom derJo eu .64/hr 14 & SMEAR RESULT.5 g- 'l Point DPM/100cm3 I -

I I

) l l

CQ I E '

' M' '

4 n>

1 0- .

O i !

l

! $ $ I E ' '

j ;

. 1 NOTES: (1) Dose Rate Readings: General Area Readings are to be indica-ted in mR/hr at the location taken. Contact readings are to be indicated in mR/hr and denoted with an asterisk (*).

(2) Contamination Results: Recorded in DPM/100 cm . Indicate 8 and circle location.

BSEP/Vol. VIII/E&RC-0100

BRUNSVICK STEAM ELECTRIC PLANT Survey No.

RADIOLOGICAL SURVEY RWP No.

f)ROkj$ W4 A c uAL Unit 2 Turbine Building ENF M M O'

)g, Elevation 6 AEA C OF.

DATE: /t /t7 /M TIME: !$N ~ DOSE RATE: / CONTAMDIATIOur INST. TTPE: INST.

SURVEY BY: _

SERIAL NO: EFF:

REVIEWED BY: REACTOR POVER: BEG:

Den <> Ra ks .~ m n/hr a .- g _ S== =Esafs J

l Point DFM/100cm a

[ ; O i E

O a c m e cm a

@e m O

a E E a

_ __ C'Sh NOTES: (1) Dose Rate Readings: General Area Readings are to be indica-

[

\

ted in mR/hr at the location taken. Contact readings are to be indicated in mR/hr and denoted with an asterisk (*).

(2) Contamination Results: Recorded in DPM/100 cm . Indicate 2

and circle location.

BSEP/Vol. VIII/E&RC-0100

BRUN$VICK STEAM ELF.CTRIC PLANT Surysy No.

AADIOLOGICAL SURVEY RWP No.

70' Turbine Deck Interface b

newma:.a Anwar Emeccaincv E.ea,. x .

un oc> -

/l//7kM DATE: TIME: iun DOSI RATE: / CONTomuTInt:

INST. TYPE: INST.

w avu BY: SIRIAL NO: EFF:

ETII ED BY: REACTOR POWER: BKC:

Ocse) 12ct kJ ,4 .w 11/h r 1 ,

g l Point . DPM/1D W dh 1 Guevakt e '

i 8

i l

l O 1

'V I

k'rD 6 kbh x- tQ- l gleh ,

I

. I t ,

I l l l

l l

l P-in I UsI

( y ,3 , e w.w t h (?gg fmo n I

I I

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1 NOTES: (1)' Dose Rate Readings: General Area Readings are to be indica-

\ ted in mR/hr at the location taken. Contact readings are to be indicated in mR/hr and denoted with an asterisk (*).

1 (2) Contamination Results: Recorded in DPM/100 cm'. Indicate and circle location.

BSEP/Vol. VIII/E6RC-0100

, _ _ __ _ _ _ . . . _ - . . _ . _ _ . . ..._._~. -

a BRUNSfICK ANNUAL EMERGENCY EIERCISE I

(AREA RADIATION MONITOR READINGS)

Prior to 1300 hours0.015 days 0.361 hours 0.00215 weeks 4.9465e-4 months , Unit 2 ARM's will read "normally" with the exception of the Turbine Building ARM's (all reading 3-5 mR/hr between 1100 and 1230 hours0.0142 days 0.342 hours 0.00203 weeks 4.68015e-4 months ; otherwise normal). Af ter 1300 hours0.015 days 0.361 hours 0.00215 weeks 4.9465e-4 months , Unit 2 ARM readings will be as .

indicated on the attached sheets.

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I UNIT 2 AREA RADIATION MONITOR READINGS TIME: 1300-1500 Hours

'O

/M6 ann Range Detector Arno,4c, Channel (mR/hr) Designation Location (Bldg.)(LA/Ar) 2-l* 0.1 -

108 Radwaste Bldg. EL 3 ft. Radwaste A s "s*I '

N MCC and Sump Area 2-2* 0.1 -

103 Radwaste Bldg. EL 3 ft. Radwaste As Nac!

S MCC and Sump Area 2-3* 0.1 -

103 U-2 Cond Filter - Demin Aisle Radwaste 45 d*!

2-4* 0.1 -

103 U-1 Cond Filter - Domin Aisle Radwaste A ' "

2-S* 0.01 - 100 Radwaste Control Room Radwaste A8 ^4 2-6* 0.01 - 100 Radwaste Sampling Station Radwaste As N8I 2-7* 0.01 - 100 Radwaste Drum Capping Station Radwasta 45 WCI 2-8* 1.0 - 10 4

Radwaste Drum Storage Radvaste A5 ""'I

-~ 2-9* 0.01 - 100 U-2 Turb. Hall Access Corridor ,

Turbine A' "I

\ 2-10* 0.01 - 100 U-2 FW Heater Bay Access Corridor Turbine A$ W42 2-11 0.01 - 100 U-2 Turb. Bldg. Sampling Station Turbine 45 N'I 2-12 0.1 -

10 3 U-2 Turb. W Moist Sep Drain Tanks Turbine 46 N IO i

! ESS I .

2-18 0.1 - 103 2B RHR System Hx and Pump Room Reactor # 10 ESS II 2-19 0.01 - 100 U-2 Rx Bldg. Airlock EL 20 ft. Reactor a LOC i.

2-20 0.01 - 100 U-2 Dryvell Entrance Reactor # /00 l

\

2-21 1.0 - 10" U-2 TIP Room Reactor 45 Wd'I

Radiation level signals supplied to common area recorders, i
5-16
UNIT 2 AREA RADIATION MONITOR READINGS Time: 1300-1500 Hours O Range Detector PAconcu Agnewc, Channel (mR/hr) Designation Location (Bldg.)(=R/V) ,
2-22 0.01 - 100 U-2 Decontam. Room EL 20 ft. Reactor 7(00 2-23 0.01 - 100 U-2 Equipment Entry EL 20 ft. Reactor > fM 2- 2 '+ 0.01 - 100 U-2 Rx Bldg. Sampling Station Reactor T IC O 2-25 0.01 - 100 U-2 Rx Bldg. Airlock EL 50 ft. Reactor 10 2-26 0.01 - 100 U-2 Inside New Fuel Vault Reactor fis Mu[
EL 98 ft. 8 in.
2-27 0.01 - 100 U-2 North of Fuel Storage Pool Reactor N5 'h i 2-28 102 - 106 U-2 Between Rx and Fuel Pool Reactor A5 W^2 EL 117 fc. 4 in.
Reactor /I5 2-29 0.01 - 100 U-2 Cask Wash Area Refuel Floor '#'
2-30 0.01 - 100 U-2 Spent Fuel Pool Cooling System Reactor A 3 "#
w !
J
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f 5-17 j
jNE 2
MAIN STRAM LINE N0llITOR READINGS AS 011 FUNCTION OF TIME I
?
t Time "A" "B" "C" "D" !
0800 70 65 70 85 'f 0815 70 65 70 85 i-0830 75 70 75 95 0845 90 85' 90 110 l 0900 100 100 105 120 i 0915 115 115 120 140 4 0930 130 130 135 160 0945 145 140 150 180 1000 160 150 160 200 ;
1015 170 160 170 210 1030 180 170 180 220 1045 190 180 190 230 1 1059- 200 185 200 240 1100 40 130 40 40 1115 40 140 40 50
' 1130 40 150 40 50 !
1145 35 160 35 40 !
1159 35 170 35 40 1200 35 40 35 - 40 ,
1215 35 40 35 40 :
1230 35 40 35 40 !
1245 35 40 35 40 i
1259 35 40 35 40 !
-0
~
1300 0 0 0 1315 0 0 0 0
, 1330 0 0 0 0 l
1345 0 0 0 0 ;
1400 0 0 0 0 !
l 1415 0- 0 0 0
1430 0 0 0 0 l 1445 0 0 0 0 ,
1 1500 0 0 0 0 '
4 i
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(87-6HRG/pcj )
- , - . - . _ _ . _ . - . . . , _ _ . , - . . _ . . _ _ , _ _ . . _ . . - - _ . - _ _ - - . _ _ _ _ - . _ - _ . . _ _ _ _ . -- -- _ . . -_ . k
,/ }
, m.
-- \ _.
M AI N STEAM LI N E M O N ITO R R EADI N GS 0800 1045- -
250 240--
230-- , "A"
/ ,
220-- ,/
- - e'B" 210-- ,/
/ . . - . .
200-- ,
' --~~~~- '
eO / '
/ '
160--
/
./-
, .;[,- -/
150-- / ,. ./
240-- ,-
- ,p/,..
/
130--
120-- -
[
/ * ',f,. /
110--
/ ,-/
i00-- ' -'
90-- #
. /. 7 y
e0--
7,,
70--
_ _'- s 60 - ; -
0800 0830 0900 0930 1000 1030 TIM E BNPST1
O O MAIN STEAM LI N E M O N ITO R R EADI N GS 1045 1105 245
--~ ' ~ ~ '
n5-- 1
, . .A" l
205-- g _ "B" i
..c.,
185-- _ _ - - ,
. _ _ "o" 165--
145--
m \
E 125--
.\ ~
ji
,o .t a
85--
65-- -
l
~~
30 . . . . . . . . . . .
1045 1055 1059 1105 1050 1100 TlM E BNPST1
v V _
M AI N STEAM LI N E M O N ITO R R EADI N GS 1100 1145 170 160-- -
p
. . A' '
150-- p'
- 8 140-- p -
p' . ..__. C
-_-_ __. D" 120--
110--
Cr r
g 100--
E 90--
80--
70--
60--
50-- ,----------s_
_ 's,
- f- . ---.... - .. . . ... . ..
30 '
1100 1115 1130 -1 1 4 5 TIM E BNPST3
V N M AIN STEAM LI N E M O N ITO R R EADI N GS 1145 1205 1MO
~~~"~ . . A' '
iso-- 1 150--
,40 .
\ ....... ..c..
130-- ___ "D"
}
120--
{
110--
y200 - 1 90--
1
\
a0--
g 70--
{
60--
50--
.O..
\
30 ' '
l 1145 1155 1159 1205 1150 1200 TIM E BNPST4
M M AI N STEAM LI N E M O N ITO R R EADIN GS 1200 1245 50)
"A"
_ ..B"
....... "C"
. __. __ D" m
x .----. ---.-._.- _.- _. __.._._. .-.
g 40-- -- ----------- -
E 30 ; '
1200 1215 1230 1245 TIM E BNPSTS
O
~
A M AI N STEAM LI N E M O N ITO R R EADI N GS 1245 1305 LEGEND sogn so- -
{
( ....... 'C' t
. - _ ..o .
m 25-- {
c Z l E ,{
15--
{
3 .
I O
l l l . . . . . .
1245 1255 1259 1305 1250 1300 TlM E BNPST6
l
+ -
POST ACCIDENT SAMPLING SYS7EM (PASS) RESULTS- ,,
The following information will be' applicable for any PASS samples obtained after 0900.
> RADIATION READINGS FOR VARIOUS TYPES OF SAMPLES Reactor Coolant Samoles Small (diluted) vial - unshielded: 6.0 mR/hr contact O J,1 mR/hr at i ft Small (diluted) vial - shielded: 0.1 mR/hr contact "sa read" at 1 it Large (untiluted) vial - unshielded: 600 mR/hr contact 10 mR/hr at i ft Large (undiluted) vial - shielded: 10 mR/hr contact 0.2 mR/hr at i ft queoression Pool (RNR) Liqyid Sanc1gg Large (undiluted) vial - unshielded: 10 mR/hr contact i mR/hr at i ft All other Supp. Pool (RHR) samples indicate "as read".
Drvwell Air Samolea 20 mR/hr contact 0.5 mR/hr at i ft l Torus Air Samoles to mR/hr contact 0.Q mR/hr at 1 ft
> RADIATION MONITOR READINGS ON RMS II PASS CONTROL PANEL These readinga are applicable during sample aquisition.
Area Monitor (RI-507): "as read" Liquid Monitor (RI-665): 0.005 R/hr (Rx coolant - small) 0.5 R/hr (Rx coolant - large)
"as read" (Wetwell liq - small) 0.01 R/hr (Wetwell liq -
large)
Cartridge Monitor (RI-704): 20 mR/hr (Drywell air) 10 mR/hr (Torus air)
BauMswn Aans EHarasncY EmcisE (tulo,hr)
PASS Smla) Analysa Resalb JCLs CE Qayamu. Ai[ ) AEx7cr Cocour ) h as Ast ThRus L&rEnf h
,r-,31 43E-A 0. 0 E+ 1 6 a E ,3 7aE-1 6.5 E-1 31 E.1 9 3 E-3 // E-1 T- #33 S f E - 1. 3.1 E+t 2 3 E-s 9.6 E-1 o3i
%e.- th% 5 o E-I I H E-l I ? E-L 2 4 E. 3 T e.- # 33 6.9 E+o d.OE+C 5 a E-l O E-R Xe -i3G 7 G E- a. 3 6 E-; 4 6 E- A [OE-3 Ne.-ISC l 2.E-I G 9 E-I 9 I E-L i A E .t NP- 77 3. 0 E 'A. 4 7E A [PelE-3 P./ E-4 k< ?7 c.c e-x a .1 e-I a. , e- x 2.ssa xy-yr 1. o E-o 5 7E-r 7a 5-x 9.s e-s 3 9 E-v I 4 E+I 3. 'f e -c. l <-e-a Cs-137 I_ )
v c) e
__ _a._. A _.-_ A-_a._ . - --._ 22 -_a__m._. 2_ _ . _ _ d. _.a .he au . 4..L.. amm.m 4A.mm..ae_s .m-a. ah 4A-1+ u--e t
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r MEOROLOGICAL FOREAST INPUT DATA MESSAGES i'
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Carolina Power & Light Company V -
ON SITE METEGROLOGIC A L DATA Date: ,
NOVEM pcet. 17, /??/
brun$too't(
TLuc (EST ) 09:00 o?:/5' CC:go og:w l Upper Speed (mph) (m/s) 72/ 7O/ 7,9 / R3/
Opper Direc. (DEG) _38[ _O_! / 7)(>5 ()G 3 Lower Speed (mph). (m/s) 1l / /, 9 / 1[/ s?, 7 /
Lower Direc. (DEG) 3% 350 oh 359 M Te=p. (*F) Sl 52 5* [3*
, AT ( C/100m) ,d f f, h [/, h f [/,[d Stability Class [ [ [ [
TLue (Esf ) 09.'r0 09:ff ( . </ : 3 () (29 : 95 r
Upper Speed _(mph) (m/s) Y,Y / [,7 / /O,9 / //,2/ _
Upper Direc. (DEG) O / 9' D3 7 D Vy Oro9 Lower Speed (g (m/s) _ 3, 3 3. O 4, h [,9 Lower Direc. (DEG) CDY O / [c, ['1 (() h[pC l m Temp. ( F) 53 f3 Syo ff A T ( C/100:n) Yh, D- [O, O2 ~O, Q 3 /*),4/
Stability Class F E E D
(. ) D p -
Carolina Power & Light Company ONSITE ' METEGROLOGIC A L DATA Date: })oVEM oc A l7, 19T 7 0runwic k Tims (ES T ) 10:0 0 'o:/5~ _ /o: 3 0 to:vs-Upper Speed (cph) (m/s) /1[/ /7. O / ///,3 / /f 4//
Upper Direc. (DEG) Ol[ C[7 O9y C7O Lower Speed (eph). (m/s) 4. 3 / 6. 9 / 7, p / 9, t/ f Lower Direc. (DEG) h73 hhh h hk hhh .
m re=p. ( r) 54, 5(, 57 f7 A T ( C/ loom) ~C. 92 -D 79 - /, /9 -/. 2(c>
Stability Class D D D D Time ( EST ) //:06 lll15~ //: 30 //: W Upper Speed (mph) (m/s) /[7 / /8. O / /[,9 / /f 9 /
Upper Direc. (DEG) /OO O 89 O@Y 073 Lov-r Speed ( g (m/s)
/O.I /o. f __ /o , 9 //,3 Lower Direc. (DEC) b M ~/ ()h(_O h7/
m temp. ( r) R 57 EP 59 O e > < c'1 > -o.77 -o.94 - /. o / -/ /v seasuier Cia.. O D D O .
(. )
Carolina Power & Light Company
\ -
ONSITE METEGROLOGIC A L DATA Date: Duce 10 e et. I71097 brun%drN Time (Esr) 12?oo 12 :/5~ l2 :3D /2 : ys-Upper Speed g (m/s) /4,6 / ((/ /d l / /y,//
Upper Direc. (DEG) O 77 O9[ O 80 OC/4/
Lower Speed (mph). (m/s) //,7/ Q/ /o,f/ /0,9 /
Lover Direc. (DEG) 073 O b. O7f C ((9 MS Temp. ( F) O
[oO [n O [n / A?
J
^
ar cCnoa) -/,22 -/,27 - /. 3 y ' /. 2 5~~
Stability Class b b b b rime (EST) 13:00 ) 3:/5~ l3:30 / 3: s5~
Upper Speed g (m/s) 13.7/ /f.3/ / Y. 9 / /5A>
Upper Direc. (DEG) hb hkh O9k h c97 Lower Speed (mph) (m/s) /O , S 9M //. 3 JO, O Lower Direc. (DEG) b k[o O Tv Oh7 O(h um temp. ( r) ,f2 (02 /r3 o r3o c
O ^' ec" -> -/. 0 7 -/.2a -/. s s -/. yo .
Stability class b b b b
Carolina Power & Light Company V ON SITE METEGROLOGIC A L DATA Date: NN E N GER. l'7 , l '? P 'T Bri,scvre.K u
~'
Time (E57~5 /Y*oo l't:/s 19:3 0 /4.y-r Upper Speed g (m/s) /[f/ //,, / / l:4, 7 / /4j,9 /
Upper Direc. (DEC) 0Q9 /O / C9[ C 9/ __
Lower Speed (mph). (m/s) //,[/ //,3 / //,7 / //,9/
Lower Direc. (DEG) O90 [) 7[ O hk O gC)
AMB Temp. ( F) (o3 (of GN (oy
^
A T ( C/100m) ~/. Yb ~f, 3 h -[, h 7 ~/. h3 Stability Class b O [ D Ti=e (EST) /5:00 /5:/5 /3:3 0 /s .* W Upper Speed (cph) (m/s) /E C / ,//, f)/ /(,,3/ //,,7/
Upper Direc. (DEG) O 7/n /CD /O Y /O9 Lower Speed (mph) (m/s) /O. 7 /o. 9 / D. 9 13. O Lower Direc, (DEG) O 9h hk[O O9k /Od na Temp. (*F) (c 5* (es 65* (c (c
AT ( C/100m) ~ /, 5 '/. f/ 'f. hh I/,[d Stability Class O O f) C,
~
C> O Carolina Power & Light Company .
METE O R O L'O GIC AL FORECAST FOR' OMV (7,195-'1 Ti=e Issued: ~ /3k.'O O Daee:
Received By: _
Issued By: _
fu M 6 t> J ,' r Torecasti.ocation:
A) Next 1 Hour [d
1) Wind Direction: Sector ////E Deg.
(Steady; Variable)
2) Winds Should Remain S /6 Deg.
2a) Variation Should m.
3) Wind Velocity [ to /O (MPH)
4) Stability Class ["
cattered, Steady)
5) Precipitation Activity Will 3e ('
6) Precipitation Type (Rain, Rainshowers, Thunderstor:s, Ice, Snow) l
7) Precipitation Intensity (Light, Moderate, Severe)
B) Next 3 Hours:
kl'McfSi MM[" b d / MIM 1 3h 6: E - r)
No (%phis n C) Remarks: _
8
~
O-- O NX a '
(\v) ,
%-g Carolina Power & Light Company .
FORECAST FOR.
METE O R O L'O GIC AL NWt* NNf' /7, /W7 Tine Issued: O DO Date:
Received By:
Issued 3y: _ _
f u n e, n , l r ['
Forecast Location:
~~
A) Next i Hour 95
1) Wind Direction: Sector A/GE<VF nes.
(S teady; Variable)
2) Winds Should Re=utin .
/f Deg.
2a) Variation Should Be
3) Wind Velocity: 9 to /2 OTH)
4) Stability Class 6~ O
$cattered, Steady)
5) Precipitation Activity Will Be
6) Precipitation Type (Rain, Rainshovers, Thunderstor:s, Ice, Snow)
7) Precipitation Intensity (Light, Moderate Severe)
B) Next 3 Hours:
h h nds :ENG-E~ 12 -/le mo' h _
$da b : D blo her:p:hok.'en C) Remarks:
g
(
a
a .
O .
4@&L Carolina Power & Light Company ,
FOR METE O E O L'O GIC AL FORECAST NoveO Vl% MS7 Ti=e Issued:' /O I O O
' Date:
Received By:
Issued 37:
Forecast Locationi brurtfoJrd A) Next 1 Ecur O90 Sector Deg.
1) Wind Direction: '
Steady; hifting; Variable)
2) Winds Should Remain
/)
\
24) Variation Should 3e f /O Deg. .
3) Wind Velocity: /1 to /[o (MPH)
4) Stability Class b Seattered, Steady)
5) Precipitation Activity Vill Se
6) Precipitation Type (Rain, Rainshovers, Thunderster=s, Ice, Snow)
7) Precipitation Intensity (Light, Moderate, Severo)
B) New- 3 Hours:
M Ws: E' / 2 -/6 m ,4 hkh n
h:,AL n ,
C) Re arks:
, O_ __
=
~ O O .
C~>4@&L Carolina Power & (.lght Company .
FORECAST FOR METE O R O L'O GIC AL Novm hv l'7,19?7 Ti=e Issued: ;// /*) O ,
Date:
Received By: , , _
Issued 37:
Torecast Location:
bruMrs,;r E A) Ne.xt 1 Ecur hb
1) Wind Direction: Sector [ _ Des.
g '
Shif ting; Variable)
2) Winds Should Remain 2a) Variation Should Be I[O Deg.
3) Wind Velocity: /2 , to __ b (MPE)
4) Stability Class b __
Scattered, Steady)
5) Precipitation Activity Will Se
6) Precipitation Type (Rain, Reinshovers Thunderstor=s, Ice, Snow)
7) Precipitation Intensity (Light, y.ederate, severe)
B) Next 3 Hours
' V!GA f l2-/G m ch 8fa4 : /7 f %;p4k C) Rc= arks: _
k
~
O .
~@@&[
t Carolina Power & Light Company .
FORECAST FOR:
METE O E O L'O GIC AL Time Issuedt EO C)
Dace: Nove%h/ l /7,175 7 Received By:
Issued By: _
~
Torecasti.ocatient runstdir_k -
A) Next 1 Ecur 9O
1) Wind Directient Sertor [ _ Deg.
n
Shi! ting; Variable)
2) Vinds Should Remain
/O Deg.
2a) Variation Should Be
3) Wind Velocityt b to /b (MPH)
4) Stability Class b
5) Precipitation Activity Will 3 (Nene, Scattered, Steady)
6) Precipitation Type (Rain, Rainshovers, Thundersterns, Ice, Snow)
7) Precipitstion Intensity (Light, Y.ederate, Severe)
B) Next 3 Hours:
_ kGA' f 13-l(c> mph
$hh : D ._
J' L % :., hk i
' C) Renar ks l
=, m .v
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s x (*
\. 5.. " ; _> ,
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t Carchtra Power & Ught Company usTs o n O L O GIC AL
~
FORsCIST F O R:
Time Issued: / 3 ',* O O
~ N O W N,,l'7,lH?7 }
- page:
Received By:
Issued By: __
r u M 5 6 n'r k 2 5,/___
Forecast Location: ! .>
~ . . . ,
~
y y.
A) Next 1 Hour S ect.or ' [ ,,,,. _, _ " D e g . O
1) Wind Direction: .-
' I O
Shittb 3;. Variable) k 2) Winds Should Remain ftea '
A[O , s _ Deg.
23) Variation Should Be
3) Wind Veloci:.y: ! t: !b' OTH)
4) Stability Class _b 7 Scattered, Steady)" - ~
5) Precipitation Activity Will 34 g,e Snow)
6) Precipitation Type (Rain, Rainshowers, Thunderstoms, Ice .
7) Precipitation Intensity (Light; Mcdersje. Sg/.ere) s
.~
, s B) Next 3 Hours: .
M,Ms: E- ESE 'llf - 1 % n h /
STA B .' D - c, '
No frer; o; bd,'e n . :.
y, .
d [,
s % C) Re=seks: r' /
ywes _ e t '- "Pw
'fo' / r 4 #^
sh4 Dh e -"N' M i J g - '/.
s e
/ y e * ,1
- - - - - - - - - - _ _ _ _ _ -- ----m_____#_. . _
.c ,
( ~D.?
.)
o .
Cf8&L Carolina Power & Light Company FORECAST F O R:
METE O R O L'O GIC AL bOdt!*k/ l'7,19?? Time Issued: / .' O O pace:
Received By:
Issued.By:
Torecast Location: funSevic k A) Uext 1 Hour
1) Wind Direction: Sector [ _ Deg.
Steady; hif ting; Variable)
2) Winds Should Remain 2a) Variation Should Be I/O Deg.
,/h to /k O!?H)
3) Wind Velocitv:
4) Stability Class b
5) Precipiestion Ac ivity Will Be None, Scattered, Steady)
6) Pret.ipitation Type (Rain, Rainshowers, Thunderstor=s, Ice, Snow)
' 7) Precipitation Intensity (Light, Modern te, Severe)
3) Next 3 Hours:
E)%s : E- ES E' l1- 19 m o h '
-ma : D-c
& Prec: Ahc ,
C) Renarks:
/n\
U
- *e*@W-
l
(,)
~
o .
(~)cp&L Carolina Power & Light Company .
FOR; METE O R O L'O GIC AL FORECAST Time Issued: / O O Date: N o d h h / 1 7 , 79 P '/
Received By:
Issued By:
Forecast Location: ruMSO)?ck A) Next 1 Hour /OO'
1) Wind Direction: Sector [~E$F Deg.
('h hif ting; Variable) k 2) Winds Should Remain 2a) Variation Should 3e 1/O Deg.
l
3) Wind Velocity: /h to /9 (MPH)
4) Stability Class b~b Scattered, Steady)
5) Precipitation Activity Will Be 1
6) Precipitation Type (Rain,' Rainshowers, Thunderstor=s, Ice, Snow)
7) Precipitation Intensity (Light, Moderate, Severe)
B) Next 3 Hours:
10;nds: ES E- S E' STAlf : D-L lb Rec:,;4ahon l~
l 1
C) Renstks:
l V
_[ y k]\ BSEP ANNUAL EMERGENCY EXERCISE (RADIOLOGICAL ENVIROIMENTAL MONITORING)
Based on a failure of the Scram Discharge Volume in the Unit 2 .9eactor Building at approximately 1300 hours0.015 days 0.361 hours 0.00215 weeks 4.9465e-4 months , an elevated - (stack) release of radioactive material to the environment will comence. Following comencement of the release, environmental dose rates and air sample results will be as described in the attached sheets.
Whole body and thyroid dose projection isopleths are attached.
Projections for known and unknown radionuclide mixes.are included since dose projections may be performed prior to the availability of isotopic information. Environmental measurements will most closely reflect the known isotope mix.
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ENVIROIRElfrAL AIR SAMPLE RESULTS Though a small release of radioactive material from the Turbine Building will occur between 1100-1230 hours, there will be no measurable environmental effects. Following the commencement of the plant release at 1300 hours0.015 days 0.361 hours 0.00215 weeks 4.9465e-4 months , air sample radiation levels and analysis results. will be as follows:
Contact Dose.
Contact Dose Rate Rate Before Lab Contact Dose Rate Just After Sampling Lab Analysis Analysis Survey Just After Sampling For Silver Zeolite For Either Results Location Time For Particulate Sample Cartridge Cartridge (uCi/cc)
Hwy 87 near 1305- 0.4 mR/hr or 4 mR/hr or 0.8 mR/hr or I-131:6.37E-8 B&I Grocery Store 1500 1000 cpm 8000 cpm 2000 cpm I-133:9.68E-8 I-135:8/14E-8 Cs-137: 1.18E-9 Hwy 211 Near Ent- 1310- 0.4 mR/hr or 4 mR/hr or 0.8 mR/hr I-131:5.65E-8 rance to Dutchman 1500 1000 cpm 8000 cpm 2000 cpm I-133:8.90E-8 Acres I-135:7.60E-8 Cs-137: 1.02E-9 l
Hwy 211 at 1315- 0.3 mR/hr or 3 mR/hr or 0.6 mR/hr or I-131:4.64E 8 i Beaverdam Creek 1500 750 cpm 6000 cpm 1500 cpm I-133: 8.90E-8 I-135:5.93E-8 Cs-137:8.60E-10 l Intersection Hwy 1305- 0.1mR/hr or 1 mR/hr or 0.2 mR/hr or I-131:1.86E-8 l 133 and 87 near 1500 250 cpm 2000 cpm 500 cpm I-133:2.65E-8 Plant Entrance I-135:1.98E-8 Cs-137:3.44E-10 l
l l
l l
l l (87-5HRG/pcj)
[N ENVIROlGUDFTAL RADIATION LEVEL READINGS
(
Though a small release of radioactive material from the Turbine Building will occur between 1100-1230 hours, there will be no measurable environmental effects. Pollowing the commencement of the plant release at 1300 hrs.,
radiation reedings at the following representative downwind locations .will be
.as follows:
Survey Location Time Radiation Reading Hwy 87 near B&I 1305-1500 0.3 mR/hr Grocery Store Hwy 211 near entrance 1310-1500 0.3 mR/hr to Dutchman Acres Hwy 211 at Beaverdam 1315-1500 0.2 mR/hr Creek Intersection Hwy 133 1310-1500 0.1 mR/hr and 211 Intersection Hwy 133 1305-1500 0.1 mR/hr and 87 near Plant t Entrance l
t I
l (87-5HR0/poj)
Es k
J f.'-
lII HYROID DOSE? PROJECTION I -10:02:00 09-14-1987 r3TABILITY-CLASS : D t~4,Iy'\ VELOCITY ' : ' 15.(MPH)
. BLOWING FROM 90' (DEGREES)
-3 - - TERM : 738-(CURIES).
.dk v dTED DURATION OF RELEASE : - l' (HOURS) -
l RELEASE HEIGHT : ~100'(METER 6)
~
TIME FROM SAMPLE TO-RELEASE : 0'(HOURS) .
OCF : 1284438 - (REM /HR) / (CURIE /M^3)~
. DISTANCE DOSE X/Q i(METERS / MILES) iREMS) (SEC/ METERS ^3) 804 /~ 0.50 7.16E-03 2.72E-08 1608 / '1.00 1.97E-01 7.47E-07
'2412 /. 1.50 3.04E-01 1.15E-06 3216./ 2.00 3.11E-01 1.18E-06
-4020 /- 2.50 2.86.E-01 1.09E-06 4824:/ 3.00. -2.56E-01 9.71E-07
"'5628 / 3.50 2.27E-01 8.60E-07
'6432-/ 4.00 2.01E-01 7.64E-07 7236 /- 4.50 ~1.79E-01 6. 81 E - O '7 i - 8040 / 5.00 1.61E-01 6.10E-07
-8844 / 5.50 1.46E-01 5.51E-07
, 9648 / 6.00 l1.32E-01 4.99E-07 L0452-/- 6.50 l'.20E-01 4.56E-07 l1256 / 7.00- 1.10E-01 4,18E-07 t
l I-- l l
6 B
l E
Thyroid-Known Mix i P
t i
~-m>--,n,-.+,, -
mm,.,,-.w,--.-...,r,w,--,---,..ern-- n_,..n.,..- _ _ - ---,---- _ -- --_ --.
4 HOLE BODY DOSE FROJECTION 10:28:42 09-14-1987 STABILITY CLASS : D l 4I VELOCITY : 15 (MPH) ELOWING FROM 90 (pdGHEES) i TERM : 35269.2 (CURIES)
TED DURATION OF RELEASE : 1 (HOURS)
RELEA9E HEIGHT : 100 (METERS)
FIME FROM SAMPLE TO RELEASE : 0 (HOURS)
?CF : 40.73542 (REM /HR)/(CURIE /M^3)
DISTANCE DOSE X/u (METERS / MILES) (REMS) (SEC/ METERS ^3) 402 / 0.25 3.24E-11 8.11E-14 804 / 0.50 1.09E-05 2.72E-08 1206 / 0.75 1.34E-04 3.36E-07 1608 / 1.00 2.98E-04 7.47E-07 2010 / 1.25 4.08E-04 1.02E-06 2412 / 1.50 4.61E-04 1.15E-06 2814 / 1.75 4.77E-04 1.19E-06 3216 / 2.00 4.72E-04 1.18E-06 3618 / 2.25 4.55E-04 1.14E-06 4020 / 2.50 4.34E-04 1.09E-06 4422 / 2.75 4.11E-04 1.03E-06 4824 / 3.00 3.86E-04 9.71E-07 5226 / 3.25 3.65E-04 9.14E-0/
5628 / 3.50 3.43E-04 8.60E-07 6030 / 3.75 3.23E-04 8.10E-07 6432
/ 4.00 3.05E-04 7.64E-07
/ }/ 4.25 2.88E-04 7.20E-07
\ !/ 4.50 2.72E-04 6.81E-07 I6I8 / 4.75 2.576-04 6.44E-07 -
8040 / 5.00 2.44E-04 6.10E-07 8442 / 5.25 2.31E-04 5.79E-07 8844 / 5.50 2.20E-04 5.51E-07 9246 / 5.75 2.09E-04 5.24E-07 9648 / 6.00 1.99E-04 4.99E-07 iOO50 / 6.25 1.9UE-04 4.77E-07 t0452 / 6.50 1.82E-04 4.56E-07 t0854 / 6.75 1. ~74 E - U 4 4.36E-U7 il256 / 7.00 1.67E-04 4.18E-07 1
l
, [x}
N Whole Body-Known Mix
1
)
' 4 HOLE BODY DOSE PROJECTION 14:10:01- 09-11-1987 23TAgILITY CLASS ~: D WT' p*hVELOCITY , s.' 15 " (MPH) BLOWING FROM 90 ~(DEGMEES)
M ? TERM's - 36000 -(CURIES)-
1 (HOURS)
.li $YdkkTEDDURATIONOFRELEAdE
'tELEASE. HEIGHT':. '100 (METERS)
- TIMELSINCE' REACTOR SHUTDOWN's O-(HdURS)
>CFt t' -379 -(REM /HR)/(CURIE /M^3)
DISTANCE DOSE X/Q (METERS / MILES). (REMS) -(SEC/ METERS ^3)
-804 /- 0.50 1.03E-04 2.72E-08 L 1608 / 1.00- 2.83E-03 7.47E-07 L 2412 / 1.50 4.38E-03 1.15E-06 3216 / 2.00 4.46E-03 1.18E-06 4020 /- 2.50 4.12E-03 1.09E-06 4824'/ 3.00 3.68E-03 9.71E -5628 / 3.50 3.26E-03 8.60E-07
'6432 / 4.00 2.89E-03 7.64E-07 7236 / 4.50 2.58E-03 6.81E-07 8040-/ 5.00 2.31E-03 6.10E-07 8844 / 5.50 _2.09E-03 5.51E-0/
-9648 / 6.00 1.89E-03 4.99E-07 10452 / 6.50 1.73E-03 4.566-07
!1256-/' 7.00 1.58E-03 4.18E-07 Whole Body-Unknown Mix
- - _ - - . - - - . _ . - - _ . - - . - - - . - _ _ - .- __--- - _ _ _ - - uan un
, THYROID DOSE PROJECTION 14:32:24 09-11-1987
[' ) VELOCITY :
^?ILITY CLASS : .D BLOWING FROM 90 (DEGREES)
\ 15 (MPH)
'\
LtdRCE TERM : 5400 (CURIES)
ESTIMATED DURATION OF RELEASE : 1 (HOURS)
RELEASE HEIGHT : 100 (METERS)
TIME SINCE REACTOR SHUTDOWN : 0 (HOURS)
DCF : ~661700 (REM /HR)/(CURIE /M^3) kkkfkNbfMILES) (kkkb) (SEbfkETERS^3) 402 / 0.25 8.05E-08 8.11E-14 804 / 0.50 2.70E-02 2.72E-08 1206 / 0.75 3.34E-01 3.36E-07 1608 / 1.00 7.41E-01 7.47E-07 2010 / 1.25 1.01E+00 1.02E-06
~2412 / 1.50 1.15E+00 1.15E-06 2814 / 1.75 1.19E+00 1.19E-06
'3216~/ 2.00 1.17E+00 1.18E-06 3618 / 2.25 1.13E+00 1.14E-06 4020 / 2.50 1.08E+00 1.09E-06 4422 / 2.75 1.02E+00 1.03E-06 4824 / 3.00 9.64E-01 9.71E-07 5226 / 3.25 9.07E-01 9.14E-07 5628 / 3.50 8.54E-01 8.60E-07 6030 / 3.75 8.04E-01 8.10E-07 4.00 7.58E-01 7.64E-07
[~'532
\
/
34 /. 4.25 7.15E-01 7.20E-07
\ 1236 / 4.50 6.76E-01 6.81E-07 7638 / 4.75 6.39E-01 6.44E-07 8040 / 5.00 6.06E-01 6.10E-07 8442 / 5.25 5.75E-01 5.79E-07 8844 / 5.50 5.47E-01 5.51E-07 9246 / 5.75 5.20E-01 5.24E-07 9648 / 6.00 4.96E-01 4.99E-07 10050 / 6.25 4.73E-01 4.77E-07 10452 / 6.50 4.52E-01 4.56E-07 10854 / 6.75 4.33E-01 4.36E-07 11256 / 7.00 4.14E-01 4.18E-07 Thyroid-Unknown Mix
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93
e s-l EVALUATION CHECKLISTS 1
l l
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i l
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i 3CN:37-1717
' -- ' ..)$.an 5.0-4
i l
7'~'S -Control Room Controller-t i
\d Not Yes No Observed
1. Did the operators respond quickly to the initiating events and properly assess the situation
2. Did the Control Room personnel take appropriate actions to mitigate the emergency condition in an expeditious manner?
3. Were appropriate abnormal conditions and emergency operations procedures used and periodically reviewed during the emergency situation?
4. Did the Shift Supervisor receive immediate notification of the emergency condition?
5. Were there sufficient measurable / observable indica-tions to recognize the Emergency Action Levels? ,
6. Were classifications of the emergency conditions timely and accurate?
7. Did Control Room personnel know when to refer to r~'s the emergency plan implementing procedures and which procedures to use?
8. Was the emergency classification upgraded or down-graded when appropriate?
l 9. Did the Shift Foreman promptly assume control l and authority?
10. Did the Shift Foreman initiate the correct response actions to implement onsite and offsite assessment and protective response measures?
11. Were such measures implemented in a prompt and well throughout manner?
12. If an emergency condition required corrective action in plant, was a team assembled and briefed in a timely manner?
13. Did the Shift Foreman practice efficient use of available personnel?
l 14. Was assistance requested from the appropriate l
emergency response organizations?
l l
l l
l SCN:37-3717 DlP7-3?-05-R0 5.0-5
) <
l 1
-Control Room Controller-(
\s. Not Yes No Observed-
15. Were personnel aware of their emergency response roles and functions?
16. Did the Shift Foreman review the declared emergency classification (s) with the Site Emergency Coordinator upon his arrival at the TSC?
17. Were appropriate decision-making responsibil'i ties transferred to the TSC upon its activation?
18. Were manpower and staffing requirements for protracted operations assessed?
19. Were notification procedures available and used for mobilizing onsite emergency response personnel and augmenting the emergency response staff?
20. Were emergency response phone listings available, complete, and up-to-date?
21. Were initial and follow-up notification forms s readily available and properly completed?
\s_,e 22. Did the Control Room communicators appear to understand and use the communications equipment and systems effectively?
23. Did Control Room personnel transmit data in a timely and knowledgeable manner?
24. Did the Control Room communicators use the statement, "this is a drill," or a similar statement?
25. Were communications links checked?
26. Were all communicatica networks operational?
l 27. Were commmedestions adequate to ensure that the
! flow of information was timely, ef fective, l and efficient?
l
28. Were dedicated communication links with the TSC, l
EOF, and OSC available and used?
9 SCN: 37- U17 3 N P ? - t .' - : 5-R0 5.0-6 l
n -Control Room Controller-(/
L.
Yes Not No Observed
29. Were general status announcements or periodic updates provided to Control Room personnel throughout the emergency?
30. Was the plant page party system used to apprise emergency workers of changes in the status of the emergency situation?
31. Was there a proper flow of data between the TSC and the Control Room?
32. Were Control Room' logs maintained?
33. Did operators obtain the appropriate information necessary to Support dose projection calculations?
34. Did operators obtain release rate and offsite .
dose assessment information from the appropriate radiological monitoring systems when required?
35. Was a calculator or computer immediately available for performing dose projection calculations?
( 36. Were dose projection calculations performed efficiently and accurately?
37. Were emergency supplies and equipment, such as respirators and protective clothing available to Control Room personnel?
38. Was the ambient noise level in the Control Room acceptable?
39. Was access to the Control Room restricted to specific individuals?
40. Was a post-drill / exercise critique held to evaluate Control Room performance?
SCN:37-3717 RNPD-s7-15-R0 5.0-7
s
,-_s -Technical Support Center'(TSC) Controller-
[ )
(/ Yes Not No Observed.
1. Was the TSC activated automatically upon the declaration of an Alert?
2. Did emergency response personnel assigned to the TSC report in a timely manner?
3. Were TSC personnel aware of their assigned work areas?
4 Were TSC personnel familiar with their assigned duties and responsibilities?
5. Did applicable personnel in the TSC refer to and utilize their checklists?
6. Did TSC personnel have up-to-date phone listings for onsite and offsite contacts? .
7. Was command control authority transferred from the Control Room to the TSC according to procedures?
[' 8. Did communications contain the statement "this
( ,
is a drill," or a similar statement?
( 9. Did the 'ite Emergency Coordinator formally accept the transfer of resconsibilities from the Control Room?
10. Was the TSC formally declared operational by the j
Site Emetgency Coordinator?
11. Were TSC personnel informed of the change of command?
12. Did the Site Emergency Coordinator demonstrate the ability to maintain command control over all emergency response activities conducted from j the TSC7
13. Were plant status briefings periodically conducted by the Site Emergency Coordinator?
14. If necessary, did the Site Emergency coordinator make offsite protective action recommendations in a proper and timely manner?
\
SCN:37-3717
F '- i 7 -0 5 -RO 5.0-8
<- s -Technical Support Center (TSC) Controller-IQ)\ Yes Not No Observed
15. Were manpower and staffing requirements for protracted operations assessed?
16. Did TSC personnel demonstrate, if necessary, the ability to identify the need for outside assistance when station capabilities were exceeded? _
17. Did TSC personnel demonstrate the ability to classify the emergency condition in a timely manner?
18. Did technical personnel demonstrate their ability to react to escalating emergency classification?
19. Did the TSC Accident Assessment Team demonstrate ,
the ability to gather, assess, and disseminate information to help mitigate the emergency conditions?
20. Did the TSC staff adequately Support the Control Room staff's efforts to identify the cause of an s incident, mitigate the consequences of that incident, and place the unit in a safe and stable conditions?
21. Did TSC personnel demonstrate the ability to respond to mitigating circumstances and properly de-escalate the emergency situation?
22. Were the notification procedures available and used for mobilizing onsite emergency response personnel and augmenting the emergency response staff?
23. Were communication links established with other emergence response facilities in a timely manner?
24. Did TSC personnel properly communicate withs
a. Control Room?
b. OSC?
c. EOF 7 l
SCN: 37-3717 a.NPD-37-05-RO 5.0-9
f
/'~'N -Technical Support Center (TSC) Controller-kj Not Yes No Observed
25. _Did the Logistic Support Director notify the Emergency Security Team Leader of anticipated emergency vehicle access to the site necessary to Support emergency response activities? _ _ _
26. Were ne essary modifications to the security program coordinated with the Emergency Security Team Leader coordinator?
27. Were the perjodic follow-up notifications conduc'ed t per procedure?
28. Were the initiating conditions or events posted on Plant Status Boards in 4 timely fashion?
29. Were the subsequent plant status reports posted in a timely manner? -
30. Did the TSC have suitable communications with the field monitoring teams? ,,_ ,
fN 'J a . Were the initial radiological conditions ascertained in a timely manner?
(
32. Did the Dose Assessment Coordinator receive proper data to be able to assess radiological conditions (e.g., meteorological data and release rate data)?
33. Did the TSC receive prompt information regarding permanent and portable radiological monitoring results?
34. Was effluent sampling information available?
35. Were the correct procedures and methods used for making dose projection calculations?
36. Were dose projections performed in a timely manner?
37. Was there a clear interface between the TSC staff and field monitoring teams?
\
SCN 87-3717 RNPD-87-05-RO 5.0-10
-Technical Support Center (TSC) Controller-O (ss Not Yes No Observed
38. Did the Radiological Assessment Coordinator adequately coordinate the activities of the Onsite Survey Teams with those of the Radiological Monitoring Teams?
39. Were habitability surveys initiated by the Radiological Assessment Coordinator?
40. Was the TSC monitored for radiological hazards?
41. Did TSC personnel demonstrate the ability to properly define protective action recommendations?
42. Did the TSC have sufficient protective equipment and supplies for the personnel assigned to the TSC7 *
43. Was the status of the TSC ventilation addressed?
44. Were procedures available to, and used by, TSC personnel?
\ 45. Were technical resources and other information, s, such as as-built drawings, maps, and emargency plan implementing procedures, readily available?
! 46. Was the operational and functional adequacy of the TSC demonstrated during the drill / exercise?
47. Was the ambient noise level in the TSC acceptable?
l 48. Was a post-drill / exercise critique held to l evaluate TSC performance? '
I SCN:87-3717 l RNPD-37-05-RO 5.0-11
'- -Emergency Operations Facility (EOF) Controller-Not Yes No Observed
1. Was the Emergency Response Manager notified following the Notification of Unusual Event and Alert declarations?
2. Was the EOF activated in a timely manner?
3. Were EOF personnel aware of their assigned work areas?
4. Was the EOF activated as prescribed in the emergency plan implementing procedures?
5. Were security controls exercised concerning personnel permitted access to the EOF 7 ,
6. Was there a clear and precise transfer of responsibility from the TSC staff to the EOF staff? .'
7. Did the Emergency Response Manager declare the EOF operational prior to accepting full responsibility for offsite activities?
8. Did the Emergency Response Manager maintain comand control over the emergency response activities conducted from the EOF 7
9. Was there a clear dissemination of authority and control in the EOF organization? -
10. Did the EOF staff initiate and coordinate activities in an efficient and timely mannor?
11. Were procedures available to, and used by, EOF personnel?
12. Did EOF personnel have up-to-date phone listings for onsite and offsite emergency contacts?
13. Were current plant status announcements and periodic updates made? __
14. Did comunications contain the statement "this l is a drill," or a sirallar statement?
15. Were appropriate EOF staff members aware of l
decisions regarding protective action recomendations for the general pubile and emergency workers within the 10-mile EPZ?
SCNtS7-3717 RNPD-87-05-RO 5.0-12
-Emergency Operations Facility (EOF) Controller-
{
Not Yes No Observed
16. Did the EOF staff perform manpower projections to support contracted operations and notify the Administrative and Logistic Manager accordingly?
17. Did the EOF staff demonstrate the ability to obtain outside resources when station capabilities were exceeded?
18. Were communicators correctly assigned and comunication checks performed in a timely fashion?
19. Were dedicated communication links available and operational?
20. Were the comunication links between the EOF and other locations, including mobile personnel, effective? .
21. Following changes in the emergency classification level, were notifications made to the proper authorities when required?
g 22. Did the EOF staff inform and update the appropriate County, State, and Federal emergency response personnel in a timely manner?
23. Did EOF personnel demonstette the ability to gather, assess, and disseminate information l regarding the status of emergency conditions and the status of emergency response activities in a timely manner? _
24. Did the EOF staff demonstrate the ability to Support the TSC staff's efforts to identify the cause of an incident, mitigate the consequences of
[
that incident, and place the unit in a safe and l stable condition?
( 25. Did the EOF staff demonstrate the ability to l analyze current plant conditions and identify l projected trends and potential consequences?
26. Were there sufficient sources of technical expertise available and utilized?
27. Were technical resources and other information such as as-built drawings, maps, and emergency
\ plan implementing procedsres, readily available?
SCN 87-3717 RNPD-37-0$-RO 5.0-13
<-~s -Emergency Operations Facility (EOF) Controller-Not Yes No Observed
28. Were procedures and other necessary documents used?
29. Did the EOF staff demonstrate the ability to utilize vendor and other outside resources to assist accident analysis and mitigation efforts where necessary?
30. Did the Radiological Control Manager demonstrate the ability to perform offsite dose assessment activities in a timely manner?
31. Did the EOF staff demonstrate the ability to perform timely assessments of offsite radiological conditions to support the formulation of protective action recommendations? .
32. Was there an adequate flow of information between State and RNPD radiological assessment personnel regarding offsite radiological conditions?
33. Did the EOF staff effectively direct and coordinate the Radiological Monitoring Teams' activities?
34. Were the EOF radiological assessment personnel in frequent communication with the Radiological Monitoring Teams?
35. Did the Radiological Contcol Manager demonstrate the ability to coordinate the activities of
the Radiological Monitoring Teams with those i of the Onsite Survey Teams?
l l 36. Were the emergency plan implementing procedures l effectively used to provide adequate protection i to station personnel and the general public?
37. Was there good communication between EOF personnel, State, and Local authorities regarding the f protective action recommendations?
38. Was the operational and functional adequacy of the EOF demonstrated?
s 39. Wat the ambient noise level in the EOF acceptable?
U SCNt87-3717 RNPD-87-05-RO 5.0-14
-i
,_,, -Emergency Operations Facility f EOF) Controller-( Yes Not No Observed
40. Did the EOF have sufficient protective equipment and supplies for personnel stationed in the EOF?
41. Did the EOF staff demonstrate, if appropriate, the ability to de-escalate the emergency response based on current plant conditions and projected trends? __ ;_
42. Did the EOF staff remain involved through the de-escalation of the emergency situation?
,r
43. Was the EOF staff able to identify and discuss appropriate reentry and recovery activities based on current or projected conditions? ,_,_
44 Was a post-drill / exercise critique held to evaluate EOF performance? _ ,
t i
/
SCNt87-3717 RNPD-37-05-RO 5.0-15
rx -Plant Monitoring Team Coneroller-f t
~\ Not Yes No Observed
1. Did the team response to, and prepare for, survey tasks in a timely manner?
2. Did the team have the proper equipment?
! a. Dosimetry?
b. Survey instruments?
c. Maps?
d. Protective clothing / respiratory protection equipment?
e. Radio?
f. Vehicle (if needed)? ~~
g. Sampling equipment? ,
3. Prior to deployment, was the team adequately briefed regarding potential hazards and conditions? .
4. Prior to deployment, was a team leader identified?
5. Were the survey instruments and radios functionally checked prior to starting on the survey and were the instrument calibrations current?
\ 6. Was personnel dosimetry available and issued to the team members? __,
7. Were teams supplied with appropriate high-range personnel dosimeters?
8. Were procedures followed while taking samples?
i 9. Were appropriate precautions taken in the handling and storing of any high-level samples? __,
10. Were samples collected in a timely m4nner?
11. Were samples analysed within the required time limit?
12. Were emergency monitoring procedures available to, and used by, team personnel?
l
13. Were the capabilities in place for dealing with both heavily contaminated personnel and those ;
individuals only slightly contaminated?
4 SCN 87-3717 RNPD-87-05-RO 5.0-16 l
l
< t / _, [
l? ,; , .s '
4
-Plant Monitoring Tasm Controller-r
Not o, -
Yes N
-.o. Observed
14. Was respiratory protection equipmect available , 5 and used while making the surveys? ,
15. Were communications properly maine.eine'dt-t
16. Did cosununications contain the statement "this is a drill," or similar statement? ' or _ _ _ _ _ -
s ,
17. Upon return, was.:he team properly debrief,ed? , .
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'~'
/ -Environmental Mouitoring Teams Controller-
\
Not Yes No Observed
1. Did team members arrive at the staging area and prepare themselves in a timely manner?
2. Was the team equipped v.ith the following suppliest
a. Survey instruments?
b. Air samplers?
c. Radio?
d. Maps?
e. Protective clothing?
f. Respiratory protection equipment?
3. With respect to the team's vehicles
a. Was it fully gassed?
b. Were the keys readily available?
c. Was a release survey completed prior to deployment?
4. Prior to deployment, was a team leader identified?
5. Prior to deployment, did team personnel perform preoperational checks on the following equipments
[*
\,
a.
b.
Radio?
Survey meters?
c. Sampling equipment?
l
6. Were the inutruments calibrated within the current i calendar quarter or within the prescribed schedule?
l l 7. Was the team briefed prior to dispatch?
8. Was the vehicle properly designed or modified to hold team members, and monitoring, protective, safety, and auxiliary equipment?
l 9. Were there enough team members to adequately conduct survey and sampling activities?
10. Was the vehicle and/or team equippef. with an adequate radio system that permitted unimpeded transmission and reception of data and instructions?
O SCNtS7-3717 l RNPD-87-05-RO 5.0-18 l
l .-
p -Environmental Monitoring Teams Controller-
\
\ Not Yes No Observed
11. Did the EOF provide adequate instructions regarding what measurements were to be performed?
12. Did the radio comunications contain the statement, "this is a drill," or a similar statement?
13. Were radio comunications clear, concise, and accurate?
14. Were comunications properly maintained?
15. Did the Environmental Monitoring Coordinator exhibit good ALARA practices in directing team? -
16. Was information transmitted to the EOF comunicator in a timely manner?
17. Was the team kept apprised of the status of the emergency situation?
18. Were dose rate measurements taken to verify radiation levels while in transic to monitoring g and/or sampling sites?
\
19. Was the team able to find the monitoring and/or sampling locations?
l 20. Did the team demonstrate a knowledge of proper survey and sampling techniques? __
l l 21. Did team personnel know how to operate and/or i handle monitoring, sampling, and auxiliary equipment?
22. Were air samplers run for an appropriate time interval?
23. Were samples counted outside the plume?
24. Was the proper procedure used for field counting of airborne samples?
25. Were good sample handling techniques used to avoid cross-contamination? _
!O V ,
1 SCNI87-3717 i RNPD-37-05-RO 5.0-H
-Environmental Monitoring Teams Controller-Not Yes No Observed
26. Was raw field data converted correctly to uCL/cc
1. for both particulate and iodine airborne samples?
27. Were vehicle surveys performed periodically?
28. Was the team aware of sample drop location (s)?
29. Did the team members keep track of their
individual exposure?
30. Were packet dosimeters checked on a regular basis?
31. Were data sheets properly filled cut and maintaired?
32. Were standby areas clearly identified to the team?
33. Were space batteries available for portable radios? ,'
34 Were backup instruments available in case of a failure of the primary instruments?
35. Were the team members and vehicle properly surveyed upon completion of their monitoring O, tasks?
36. Were the team members debriefed upon their return?
37. Upon return, wi.s equipment returned to its original l status?
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SCN 87-3717 RNPD-87-05-RO 5.0-20
-Medical Emergency Controller-v Not Yes No Observed
1. Was the information concerning the event transmitted properly to the Control Room?
2. Was the response team organized and dispatched quickly?
3. Prior to deployment, was a team leader identified and properly briefed?
4. Prior to deployment, were the radiological conditions analyzed for potential personnel hazards?
5. Prior to deployment, was the team adequately briefed regarding the actual or potential radiological and operational conditions? ,
6. Was access to the site coordinated with security to minimize ambulance and rescue team ingress and egress times?
7 . Was health physics coverage available and O 8.
utilized, if required?
Were access badges, dosimetry, and security escort standing by for ambulance or other emergency personnel?
9. Was the required equipment available to support the medical emergency response? _
10. Was adequate first aid equipment available?
11. Was the worst-case situation philosophy exercised on the victim?
12. Were communications adequately demonstrated during the response (i.e., were they maintained on a frequent basis)?
13. Did the emergency response team follow proper procedures?
14 Were radiological controls implemented during evaluation, treatment, and transport? _
15. Did the team practice contamination control during the response?
SCN87-3717 RNPD-87-05-RO 5.;-El
~s -Hedical Emergency Controller-Not Yes No Observed
, 16. Did the ambulance have to wait for an excessive period of time to receive the victim for transport?
, 17. Were proper radiological controls practiced by the ambulance and hospital personnel?
18. Were proper release procedures practiced and followed?
19. Were appropriate procedures employed to minimize ambulance or other transport vehicle contamination? --
20. Were appropriate procedures employed to maintain the hospital free of contamination?
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I SCNIS7-3717 '
, RNPD-37-05-RO 5.:-1L I
/N -Corporate Emergency Operations Centwe (CEOC) and <
( Plant Media Center (PMC) Controllers-v Not Yes No Observed
1. Were the CEOC and PMC activated in a timely manner?
2. Were the CEOC and PMC activated as prescribed in the emergency plan implementing procedures?
3. Were procedures broken out and used?
4. Was there a clear dissemination of authority and control in the organizations?
5. Were dedicated communication links available with all necessary points of contact?
6. Did the CEOC and PMC staff initiate and coordinate activities in an efficient and timely manner? .
l
7. Were current plant status announcements and periodic updates made?
l 8. Did the CEOC and PMC demonstrate operational and functional adequacy during the exercise?
N
9. Was there sufficient coordination in the i preparation, review, and release of information to provide accurate and timely releases to the l general public and news media?
10. Was the ability to establish, operate, and coordinate an effective rumor control demonstrated?
11. Were accurats and timely information releases i made to the general public and the news media?
l 12. Did the PMC contain sufficient equipment and supplies to support all required public information activities?
13. Upon activation of the CEOC and PMC, was a check made to assure operability of all phone and telecopy equipment? __
SCNt87-3717 RNPD-87-05-RO , -23 l _
F I. '-
3g 2
-Corporate Emergency Operations Center (CEOC) and ED Plant Media Center (PMC) Controllers-Not [
L Yes No Observed
14. Was a "Media Call" list used to properly notify representatives of the media of the emergency?
15. Was a post-drill / exercise critique held to evaluate CEOC and PMC personnel performance? :
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i SCN:87-3717 RNPD-87-05-RO ' .' - 14
(II ,
. ~~s -Assembly, A: countability, and Evacuation Controllers-i 1 l'3 i
\- Not 3
Yes No Observed
1. Did the RNPD security organization mobilize and respond to the declaration of an Alert in a timely and effective manner?
2. Did RNPD security personnel adequately control site access in accordance with applicable security procedures?
3. Were appropriate security procedures available to, and used by security personnel?
4. Did communications contain the statement "this is a drill," or a similar statement?
5. Was site access limited to those persons necessary to perform emergency-related tasks?
6. Were security posts and access control points
established and maintained as appropriate?
7. Did the RNPD security organisation demonstrate the ability to account for all personnel in a ss timely manner?
3 ss _s' 8. Was the evacuation conducted in an efficient manner?
9. Dit the security organization initiate steps to locate unaccounted-for individuals?
10. Were these steps cooroinated with the Site Emergency Coordinator?
i j
1 s__ A' i
SCN:87-3717 RNPD-87-05-RO '..-23
v.r% \
1 CAROLINA POWER & LIGHT COMPANY Exercise Critique Form To: Chief Evaluator Date:
1. Type of activity or facility observed (such as off-site dose assessment, notification, decontamination, public information, TSC, EOF, etc.):
2. Location:
3. Date:
4. Time: From To
5. Procedure numbers that apply to ictivity and/or facility evaluated: ,
6. Names of personnel evaluated:
7. With respect to the particular function or activity you are evaluating, do you think that the Plan and Procedures are adequate (explain if necessary)?
8. Either here or in an attached report state your conclusions as to the favorable aspects of the function or facility ooserved. Include good points which you observed.
9. Either here or in an attached report, enumerate the deficiencies observed and give your recommendations for corrective action. If you have none, so state. .
10. Overall Rating:
Excellent -
Satisfactory -
Unsatisfactory -
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ML20149E404

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