ML20244B974

Plan for Brunswick Steam Electric Plant Emergency Exercise, 890523

ML20244B974
Person / Time
Site:	Brunswick
Issue date:	05/23/1989
From:	CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML20244B895	List: ML20244B893 ML20244B974
References
NUDOCS 8906140074
Download: ML20244B974 (161)

Text

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CAROLINA POWER & LIGHT COMPANY PLAN FOR BRUNSWICK STEAM ELECTRIC PLANT EMERGENCY EXERCISE MAY 23, 1989 I

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(87-2HRC/pcj) ]

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CAROLINA POWER in LIGHT COMPANY PLAN FOR BRUNSWICK STEAM ELECTRIC PLANT EMERCENCY EXERCISE MAY 23, 1989 TABLE OF CONTENTS PACE I. MISSION AND PURPOSE OF EXERCISE .................................... I j l

II . . SCOPE AND OBJECTIVES A. Scope ........................................................ 1 B. Objectives ................................................... 1 III. 3ITUATION AND ASSUMPTIONS A. ExerciseDates................................................3 B. Exercise Locations / Facilities ................................ 3 IV. ' CONCEPTS AND CONDUCT OF THE EXERCISE A. Exercise Scenario ............................................ 5 B. BSEP Exercise Organization Activities ........................ 5 C. Eval ua tion and Cri t i q ue . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 D. Exercise Exempt Personnel .................................... 8 E. General Guidance-for the Conduct of the Exercise.............. 8 V. COHMAND, CONTROL, AND COMMUNICATIONS A. Site Emergency Coordinator (SEC) ............................. 9 B. Co mmu n i c a t i o n s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 C. Records ...................................................... 10 D. Exercise Message Card ........................................ 10 E. Time ......................................................... 10 F. Message Preamble and Close ................................... 10 VI. ATTACHMENTS Attachment 1 ................... Instructions for Controllers and Evacuators Attachment 2 ................... Instructions and Rules for Players Attachment 3.................... Exercise Control / Evaluation Organization Attachment 4.................... Scenario and Time Schedule of Simulated Plant Conditions (87-2HRC/pcj)

L CAROLINA POWER & LICHT COMPANY PLAN FOR BRUNSWICK STEAM ELECTRIC PLANT EMERCENCY EXERCISE May 23, 1989 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 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. Participants include those utility personnel necessary to implement the proper response and will'not include state or county resources 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 'om 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 capabilities exist to accomplish notification of off-site agencies.

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

7. Demonstrate the adequacy of the information provided in the initial notification, as well as follow-up notifications to the state and counties.

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8. Demonstrate ability of personnel to activate the Technical Support Center, Operations Support Center, and Emergency Operations Facility as described in the emergency plan and procedures.

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

10. Demonstrate the ability to communicate between emergency response facilities.

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

12. Demonstrate the adequacy of the Technical Support Center in providing accident assessment and mitigation, dose assessment, and communication / notification activities.

13. Demonstrate the adequacy of the Emergency Operations Facility in coordinating off-site utility activities.

14. Demonstrate recordkeeping requirements as described in the plan and procedures.

15. Demonstrate that status boards are maintained and updated.

16. Demonstrate the ability to provide adequate radiation protection services such as dosimetry and personnel monitoring.

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

18. Demonstrate the ability to support the radiological assessment process while maintaining personnel radiation exposure as low as reasonably achievable (ALARA).

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

20. Demonstrate the ability to provide safe on-site access to off-site emergency services and/or support personnel (normal security access procedures will be adhered to).

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

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

23. Demonstrate those NRC identified open items resulting from the 1988 BSEP exercise.

(87-2HRC/pcj)

I III. SITUATION AND ASSUMPTIONS A. Exercise Dates

1. Submit exercise scope, and objectives to NRC:

Exercise - 75 days (March 10, 1989).

2. Submit exercise scenario to NRC:

Exercise - 45 days (April 9, 1989).

3. Final Evaluator Meeting:

Exercise - May 22, 1989 TSC/ EOF Training Building, Room No. 143-B.

i 4, Exercise:

May 23, 1989

5. Evaluator Croup Meeting:

May 23, 1989

6. Lead Evaluator Meeting: - Room No. 122 May 24, 1989

7. Post Exercise Critique Report to Players May 24, 1989

8. NRC Exit / Critique May 24, 1989 B. Exercise Locations / Facilities

1. Brunswick Plant, Southport, North Carolina

a. Control Room Function is to provide plant control and initial direction of all plant related emergency operations.

b. Operations Support Center (OSC) 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.

(87-2HRC/pcj)

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c. Technical Support Center (TSC) The Technical Support Center is located in 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

j. field, mobile, radiological monitoring teams prior to EOF activation; on site dose projections; off-site dose projections prior to EOF activation; display of status of

. plant parameters; and provide an emergency reference collection of selected engineering and plant documents.

I 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 l addition to the normal plant communications system, l redundant emergency communications facilities in the TSC l provide telephone contact with required agencies and other response centers by use of the Corporate Emergency Communications System.

d. Emergency Operations Facility (EOF)

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 provide support in: Technical Analysis, Administration j and Logistics, Radiological Control, and Emergency Communications.

e. Meteorology Tower. Located north of the TSC on the plant l 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: Actual

2. Subsequent: Actual l f. Miscellaneous, Facilities l ( l') Brunswick County Airport, 25-foot elevation, 3200-l foot runway, is located approximately 5 miles via l

Route 133 from the BSEP. Phone (919) 457-6577.

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

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

Oak Island Inn, Yaupon Beach (919) 278-5442 Ocean Crest Motel, Long Beach (919) 278-5212 Best Western Carolinian, Wilmington (919) 763-4653 IV. CONCEPTS AND CONDUCT OF THE EXERCISE A. Exercise Scenario The exercise will simulate an off-normal incident at BSEP that should escalate to a Site Emergency and require: accident recognition and classification; assessment of on-site and off-site-radiological consequences; alerting, notification, and mobilization of various organizations and personnel; in plant corrective actions; activation and use of emergency facilities and equipment; effective use of communications; preparation of reports, messages, and records; and implementation of on-site protective actions.

During the course of the exercise, 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 Exercise Ditector; 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 3 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 for the particular emergency activity they perform. Players, therefore, are responsible for initiating actions and/or 1

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l 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 provide an exercise basis whitn tests the plant 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 facilities will be identical with their intended operation in a real emergency. Players will be identified by wearing a ID badge or WHITE ribbon.

2. The Exercise Director will be responsible for overall conduct of the exercise and to arrange preparation at the conclusion of the exercise for a consolidated evaluation and critique report.

3. Lead Controller will be responsible for coordinating controller input as necessary to initiate player response and keep the exercise action moving according to the scenario and exercise objectives.

4. The Controllers will deliver " Exercise Message Cards" to designated exercise players at various times and 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 according 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 ID badge or RED ribbon.

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, functions, and/or actiu; ties of the plant radiological emergency response plan and procedures. Selection of evaluators is based on their expertise in, or their qualifications to evaluate the activity or area assigned. For example, hes).ch physics activities will be evaluated by qualified health physics personnel. When feasible, persons designated as Controllers for a given function will also be assigned as evaluators of that function. Evaluators will record their observations, and 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 esercise. They will take steps whenever possible to collect (87-2HRG/pcj)

data on the time and motion aspects of tha activity observed for post exercise use in designing system improvements.

Evaluators will be identified by wearing a ID badge or BLUE ribbon. When an Evaluator is serving id a Controller role, they will wear a ID badge or RED ribbor .

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

C. Evaluation and Critique

1. The evercise will be evaluated by Evaluators who will be assigned to key locations and re;ponse activities where they will record their observations. Following the exercise, Evaluators will present their findings at critiques as scheduled in Section III.A of this plan.

2. The following facilitics will te evaluated in addition to the Plant Emergency Plan and Procer:ures:

a. Control Room.

b. Operational Support Center.

c. Technical Support Center.

d. Emergency Operations Facility.

3. The following activities will be evaluated as appropriate based on response to the scenario,

a. Accident recognition, classification, and assessment,.

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

c. Alerting, notification rsnd mobilization activities.

d. In plant corrective actions.

e. Activation and use of emergency facilities and equipment.

f. Use of communications equipment and procedures.

g. Preparation of reports, messages, and records.

h. Protective actions.

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

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

5. Any deficiency in the Plant Radiological Emergency Response Plan and implem(nting procedures, training, 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.

(87-2HRC/pcj)

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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, chemistry, etc.

E. General Guidance for the Conduct of the Exercise

1. Simulating Emergency Actions Since exercises are intended to demonstrate actual capabilities as realistically as possible, participants should act as they would during a real emergency. Wherever possible, actions should be carried out. Only when it is not feasible to perform an action should it be simulated. Any orders given that for any reason cannot or should not actually be performed 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 area 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 implement this 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.

c. Exercise part icir<ents will not intentionally take illegal actions when beiag called out to participate in an exercise. Spouifically, 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 propert y (public or private), other personnel responding to the exercise, members of the general public, animals, and the environment.

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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 receiv4 continuous public notice and scrutiny; therefore, the conduct of an exercise could arouse public concern that an tetual 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."

5. Maintaining Emergency Readiness During the performance of an exercise the ability to recognize a real emergency, terminate the exercise, and respond to the nee 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 exercise, requiring the actions of Company personnel, then the exercise will be terminated by the Lead Controller or the Exercise Director in consultation with appropriate plant management. All messages about the real events will be clearly identified as such. For example, precede a peak message with:

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

V. COMMAND, CONTROL, AND COMMUNICATIONS A. Site Emergency Coordinator (SEC)

The SLC has immediate and unilateral authority to act on behalf of t's.* Company to manage and direct all on-site emergency operations involving the facility. During the exercise, he will have responsibility also for the simulated emerFency exercise operations. The SEC will be located in the Control Room at the beginning of the exercise and will relocate to the TSC upon activation of the TSC.

(87-211RC/ pcj )

B. Communications

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

C. Records BSEP Emergency Procedures require that plant personnel responsible for maintaining records during an emergency shall provide a copy of those records to the Emergency Preparedness Specialist following an emergency or emergency exercise.

D. Exercise Message Card The " Exercise Message Cards" are prepared by the exercise drill planners / controller prior to the exercise to satisfy the requirements of the exercise scenario. The purpose of the completed form is to initiate the appropriate exercise player response and to keep the exercise action moving according to the scenario and exercise 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 shoald be done.

E. Time

1. All CP&L in plant exercise participants will repo:rt 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 MESSACE" should be used at the beginning and end of each message.

(87-2HRC/pcj)

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INSTRUCTIONS FOR CONTROU.ERS 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. I

2. The in plant controllers will be coordinated by the Exercise Lead l Controller located in the TSC (Ext. *). 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. *) 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.

Two kinds of messages will be used:

Controlling 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 controller should follow up with an explanation of the message and answer questions to ensure that the participant understands the message.

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.

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

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4. Note that the scenario events are hypothetical. Any portions of the scenario depicting plant system operational transients are simulated j 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 an'd 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 commencement, all telecommunications should be tested to ensure satisfactory communications between the lead controllers and all other controllers.

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 observing the players.

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

scenario.

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

(87-2HRC/pej)

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8. Issue the message on time. Make sure the players understand it.

9. Remember to call the Exercise Lead Controller to report on F.tatus 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.

16. Be at your post at least 20 minutes prior to any player action commencement. Set yourself up.

17. The federal eval aators 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 for actual plant conditions. 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 criticine the players' actions during the play.

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

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6. Don't allow the media /other external influences to distract the players. No interviews with players are allowed unless arranged through appropriate Corporate Communications personnel.

7. Don't a' low simuistion when equipmeist and facilities are available except for causing flow discharge of fire extinguishers, operation of plant sy'etems, etc.

NOTE

• All participants will comply with radiation e<.posure control practices

.for actual conditions existing at the station at the time of the exercise.

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(87-2HRC/pcj)

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' Attachment 2' s INSTRUCTIONS AND RULES FOR PLAYERS

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' All players (at 1 east the leaders of the player groups) must read and follow the rules given below. This is important to the successful demonstration cf 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. IPlay'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 actions.. .'f authorized to simulate an action, tell the evaluator how and when you would actually do them.

6. Periodically cpeak 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 benefit.

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. ,

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9. If the controller intervenes with your play, it is for a good reason. Obey your controller's directions at all times. This is I

essential to the overall success of the exercise. '

10. If you disagree with your controller, you can ask at s to reconsider i or consult with the controller's command center at .ime permits. )

You must, however, accept his/her word as final anc proceed. 1

11. Respond to the controller's questions.

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

This is essential to the overall success of the exercise.

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, 13. . . You must play as -if radiation levels sctually are present , in L accordance with the information you have received. This will.

! require that ;ou 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 j 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.

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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 IIICH RADIATION AREAS IN TIIE PLANT WIT 110UT AUTHORIZATION FROM TifE CONTROLLER. FOLLOW ALARA PRINCIPLES.

16. Demonstrate knowledge of your e-s mency plan, emergency operations, l and procedures.

17. Utilize status boards, log book, three part interoffice memos, etc., as much as possible to document and record your actions, instructions, and reports to your co players. This is very i important. Remember, "Put it is, writing." {

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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 yoor 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 preparedness.

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, l

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ANN UAL EXERCISE MAY 23, 989 TIME EMERGENCY CLASS FACILITY UNIT 1 OIL FIRE 0200 DAMAGE 0300 l OIL LEAK l 0400~ OIL LEAK OBSER%

lTaccw InsTa Ara l wuEL ALERT l ACCIDENT:

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~

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l ANNUAL EMERGENCY DRILL -'5/23/89 1

-I 1I At 0300, a tanker on its way to the port of Wilmington strikes a submerged oaject in the Cape Fear River near the intake canal for the Brunswick Steam Electric Plant. The Coast Guard and ship's Captain estimate that 50,000 gallons of No. 2 fuel oil has leaked from the vessel and cannot be stopped.

1 Visibility is hampered by fog. The speed and direction of travel of the oil cannot be accurately determined.

As daylight approaches, a Security Guard reports the odor of fLe1 oil which secas to be especially prevalent at the intake structure. A call is made to the Coast Guard to help determine the source.

Circulating water and service water cooling capabilities are affected to the extent that much higher than normal temperatures are being experienced on components utilizing circulating water and service water for cooling due to fouling of the heat transfer surfaces.

The dispatcher calls at 0100 to give permission to reduce Unit 2 reactor power for main turbine valve testing and to complete control rod operability checks.

By 0230, this testing has been completed satisfactorily. The Control Operator starts to increase power but the dispatcher calls and requests that power not be increased before 0600 in the morning.

o MSC/89-043

___m___ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ . _ _ _ . _ _

The Control Operator coordinates with the Unit 2 Reactor Building Auxiliary Operator to perform PT-09.2, HPCI System Operability Test, which will go overdue on his shift.

At 0430, Unit 2 Service Air System is lost due to fouling of the heat transfer surfaces. Operations personnel will cross-tie with the Unit 1 Service Air System.

i At 0500, while carrying out refueling operations in support of the Unit 1

. refueling outage, a spent fuel bundle is accidentally bumped into the side of the fuel pool. _The bundle is still attached to the grapple at the full-up position. The Reactor Building ventilation will isolate on high radiation and the Unit I refuel floor is evacuated. Control Room personnel should declare an Alert and request activation of the TSC and OSC.

The "2A" reactor recirculation pump trips at 0700 due to a high oil temp. This places reactor operation in a core thermal instability region. For some unexplainable reason, the HPCI system discharge path shifts and now injects to the reactor vessel. Substantial fuel damage occurs and it is determined that ,

I a MCPR Safety Limit has probably been exceeded. The reactor scrams and the l l main steam isolation valves close.

l L

L RCIC and SRVs are used for decay heat removal. The B loop of RHR is placed in service to provide suppression pool cooling. The A loop of RHR will be unavailable due to loop maintenance.

MSC/89-043 1

l 1

C__________._______.___.._..__ _ _ _ . _ _ . _ _ _ _ J

i After the B loop of RHR is placed in suppression pool cooling, an oil leak on the B RRR pump comes in contact with the motor heater. A fire alarm is received in the Control Room at 0755. The alarm is confirmed by a Fire Watch in the area. A Site Emergency should be declared. The Fire Brigade responds to the fire. Outside aseistance is obtained from the Southport Fire Department (Southport Fire Department will participate).

Decay heat removal has been further compromised by this fire. Plans will need to be set into motion to combat the various problems presented in this drill scenario.

It is anticipated that repair teams will be assembled to complete maintenance on the Unit 2, A loop RHR, to repair the B loop RHR and to repair the Unit I refuel bridge.

Upon successful repair of either A or B loop RHR, perations personnel should begin to implement decay heat removal. A discussion of future recovery actions j is expected at this time.

MSC/89-043 ,

l l

l

_ _ _ - - _ _ _ - - - - _ - _ _ _ _ _ _ _ _ _- _ .s

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CEPIP-18 b

y' p

R;v. 3 June 1987 CP&L 9

q' EXERCISE MESSAGE CARD U-1 l

and U-2 Plant Message.No. .Date 5/23/89 Time 0345 MESSAGE FOR: SOS FROM: CONTROLLER MESSAGE / SIMULATED PLANT CONDITIONS: "THIS IS AN EXERCISE MESSAGE" Initial Conditions Unit 1 - Refueling outage, Circ. water system drained, core alterations in progress. 30 days after shutdown Unit 2 - 90% power, 75% coreflow. Main turbine valve testing and control rod operability tests have been completed. Dispatcher has requested that power be held at this level until the morning peak. A-loop RHR is removed from service for repairs to the limitorque operator of 2E11-F017A. HPCI PT9.2 will be overdue at 0500.

ACTIONS EXPECTED:

Inform Control Room staff of simulated plant conditions.

7 g .%

FOR CONTROLLER USE ONLY W

0 4CEPB 18-22 h______m________- . - - _

.i-CEPIP-18 R3v. 3 June 1987 CP&L EXERCISE MESSAGE CARD U-l and l o

U-2 Plant t

' Message No. Date 5/23/89 0400 Time MESSAGE FOR:- SOS FROM: CONTROLLER MESSAGE / SIMULATED PLANT CONDITIONS: "DIIS IS AN EXERCISE MESSAGE" A security' guard has called to report the scrong odor of fuel oil in the vicinity of the intake structure.

ACTIONS EXPECTED:

1. Determine that the fuel oil is in the intake canal and is not a leak from the main fuel on storage tank.

2. Reference AOP-33.0, oil spills in the Cape Fear River.

3. Reference FPP-012, hazardous materials and oil releases.

4. . Consult PEP's for emerg, classification, if any.

FOR CONTROLLER USE ONLY The oil spill and problems caused by it will remain throughout the drill.

l 4CEPB 18-22 1

9

CEPIP-18 Rev. 3 June 1987 CP&L EXERCISE _ MESSAGE CARD Unit 1 l

and Unit 2 Plant Message No. Date 5/23/89 Time 0430 MESSAGE FOR: SOS FROM: CONTROLLER MESSAGE / SIMULATED PLANT CONDITIONS: "THIS IS AN EXERCISE MESSAGE" You have received the following annunciators in the last few minutes:

1. UA-1, 1-10, NSW header press-low

2. UA-1, 1-9, CSW header press-low

3. UA-3, 3-4 TBCCW HX, outlet temp. high

4. UA-1, 3-2, air compr. D trip 2A, B, and C air compressors manually started on low S. A. pressure UA-1, 5-4.

2A S.A. compressor tripped after 8 minutes on high cooling water temperature, (UA-1, 3-3).

_ Condenser vaccuum slowly dropping.

ACTIONS EXPECTED:

1. Respond to annunciators

2. Cross-tie air systems to U-1.

3. Refer to A0P-17.0, TBCCW system failure.

Refer to AOP-18.0, NSW system failure.

Refer to AOP-19.0, CSW system failure. .

Refer to AOP-20.0, air system failures.

4. Reduce load until plant conditions stabilize.

FOR CONTROLLER USE ONLY Reducing load and cross-tying air systems with Unit 1 reduces heat input to TBCCW system, and Unit 2 operation is stable. Equipment cooled by TBCCW and RBCCW stabilizes at higher than normal temperatures. TBCCW heat exchanger outlet stabilizes at 106 F.

Shifting operating Sw pumps on U-2 only temporarily improves heat transfer.

~

4CEPB 18-22

l

!. CEPIP-18 i Rgv. 3 June 1987 CP&L EXERCISE MESSAGE CARD l

U-l Plant Message No. Date 5/23/89 Time 0505 l MESSAGE FOR: SOS FROM: CONTROLLER MESSAGE / SIMULATED PLANT CONDITIONS: "THIS IS AN EXERCISE MESSAGE" Refuel floor SRO has reported that a spent fuel bundle was accidently bumped into the side of the fuel pool, ARM's are alarming, and the floor is evacuated. Bundle is still attached to the grapple at the full-up position.

SRO is at 98' change room. U-1 C.O. reports reactor building isolation on high radiation. Both SBGT's have started. Annunciator UA-03-3-7 was received.

ARM l-27 l-28 in alarm ACTIONS EXPECTED:

1. Notify appropriate Control Room personnel.

2. Reference A0P-7.0, spent fuel damage.

3. Declare ALERT per PEP, call out TSC/OSC.

4. Reference AOP-5.0, Rad. spills, high rad., and airborne activity.

5. 4-hour RED phone report due to sec. contai,nment isolation and SBCT "

system actuation.

6. Enter E0P-03-SCCP.

ARM l-27 North of fuel pool 1-28 Between fuel pool and Rx. cavity FOR CONTROLLER USE ONLY 4

4CEPB 18-22

CEPIP-18 Ray. 3 June 1987 CP&L EXERCISE MESSAGE CARD l

Unit 1 Plant Message No. Date 5/23/89 Time 0530 MESSAGE FOR: Personnel Decon Technician FROM: CONTROLLER

)

MESSAGE / SIMULATED P" ANT CONDITIONS: "THIS IS AN EXERCISE MESSAGE" Three individuals who had been working on the Unit 1 refuel floor at the time of the fuel handling accident have reported to personnel decon. All individuals showed whole body & facial contamination, but were clean after showering.

ACTIONS EXPECTED:

- Communicate to H.P. window

- Set up whole body count FOR CONTROLLER USE ONLY enes 4CEPB 18 22

-_ __.______.__.mm __ _ _ ______ _._______________________.___.m m_______m. _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ . _ _ _ _ . . _ _ _ _ _ . _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _______5

CEPIP-18 Rev. 3 June 1987 CP&L EXERCISE MESSAGE CARD l

Unit 1 Plant Message No. Date 5/2g89 Time 0600 MESSAGE FOR: Dosimetry Technician FRCH: CONTROLLER MESSAGE / SIMULATED PLANT CONDITIONS: "THIS IS AN EXERCISE MESSAGE" Results of whole body count of individuals from 117'.

I-131 P CI  % MPOB_

Worker A 162 23.1 Worker B 123 17.6 Worker C 97 13,8 ACTIONS EXPECTED:

Communicate this information to H.P. supervision.

FOR CONTUSLLER USE ONLY l

4CEPB 18.22

CEPIP-18 Rev. 3 June 1987 CP&L EXERCISE MESSAGE CARD l

Unit 1 Plant Message No. Date 5/23/89 Time 0600 MESSAGE FOR: Shift Opet.iting Supervisor FROM: CONTROLLER MESSAGE /SIMULATEL PLANT CONDITIONS: "THIS IS AN EXERCISE MESSAGE" Health physics reports that dose rates in radwaste 23' fuel pool filter area have increased from 15 mr/hr - 30 mr/hr ACTIONS EXPECTED:

Isolate fuel pool cleanup system FOR CONTROLLER USE ONLY O

4CEPB 18-22

CEPIP-18 Rev. 3 June 1967 CP&L EXERCISE MESSAGE CARD l

U-1 Plant Upon Successful Visual / Ops Message No. Date 5/23/89 Time Check of Refuel Bridge MESSAGE FOR: Repair Team (Unit 1 Refuel Bridge)

Fr.0M: CONTROLLER MESSAGE / SIMULATED PLANT CONDITIONS: "THIS IS AN EXERCISE MESSAGE" ,

1

1. The refuel bridge operates erratic when moving from north to south. It continues to move af ter the job stick is released.

ACTIONS EXPECTED:

Troubleshoot control circuit for north / south movement.

FOR CONTROLLER USE ONLY Provide message to repair team dispatched to repair Unit I refuel bridge.

Message provided upon successful visual / operation check. Since the refuel bridge has a fuel bundle suspended the operation check should be perfo**med by a qualified operator.

4CEPB 18-22

CEPIP-18 Rev. 3 June 1967 CP&L EXERCISE MESSAGE CARD l

U-l

! ~

Plant '

After checking refuel Message No. Date 5/23/89 7g bridge joystick contacts MESSAGE FOR: Repair Team (Unit 1 Refuel Bridge)

FROM: CONTROLLER MESSAGE / SIMULATED PLANT CONDITIONS: "THIS IS AN EXERCISE MESSAGE" The joystick contacts for north / south travel appear to be sticking and need to be replaced.

ACTIONS EXPECTED:

Notify OSC of the findings FOR CONTROLLER USE ONLY

~*

Provide message to repair team af ter they have simul'ated checking joystick contacts.

4CEPB 18-22

CEPIP-18 RGv. 3 June 1987 CP&L EXERCISE MESSAGE CARD l

U-1 Plant At least I hour after Message No. Date 5/23/89 Time beginning repair MESSAGE FOR: Repair Team (Unit Refuel Bridge)

FROM: CONTROLLEn MESSAGE / SIMULATED PLANT CONDITIONS: "THIS IS AN EXERCISE MESSAGE" Joystick replaced. Bridge operating correctly.

ACTIONS EXPECTED:

Notify OSC that job is complete.

FOR CONTROLLER USE ONLY O

4CEPB 18-22

CEPIP-18 Rov. 3 June 1987 CP&L EXERCISE MESSAGE CARD l

U-2 Plant Message No. Date 5/23/89 71 , 0630 MESSAGE FOR: SOS FROM: CONTROLLER MESSAGE / SIMULATED PLANT CONDITIONS: "THIS IS AN EXERCISE MESSAGE"

1. HPCI is running in full flow test, VT-2 inspection in progress per PT 9.2. B-loop RHR in supp. pool cooling.

2. Reactor power is 70%.

3. Sufficient compensatory action has been taken on S0W to maintain Unit 2 stable operation.

ACTIONS EXPECTED:

Inform appropriate control room personnel.

FOR CONTROLLER USE ONLY

~'

HPCI will fail to injection mode inexplicably when 2A recirc pump drops at T=3.5 hrs.

4CEPB 18-22

CEPIP-18 Rev. 3 June 1987 CP&L 1 EXERCISE MESSAGE CARD U-2 Plant Message No. Date 4/21/R9 Time 0700 l l

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

1. Received annunciators A-06, 2-3 recirc MG 'A' drive motor trip.

A-06, 2-5 MG bearing and oil temp. high

2. HPCI inexplicably shifted to injection mode.

3. Large power oscillations were seen on APRMS.

4. Main steam line h1 rad. scrammed the reactor.

5. Annunciators received per attached.

ACTIONS EXPECTED:

Per attached.

1 FOR CONTROLLER USE ONLY Region B entered, core thermal hydraulic instability. When HPCI shifted to injection, fuel damage resulted.

1 4CEPB 18-22 l

l

_ _ _ _ . _ _ _ _ _ _ _ . _. ___-_ - _____----__ -_-_ _ _ _ O

t-Actionsiexpected

- APP A-05, 1 Rx auto scram system A <

APP A-05,.2-7 Rx auto scram system B l APP A-05,_3-7 Main steam line Hi Hi rad trip' i- APP A-05, 4-6 'MSIV not full open -

' APP . A-05, 5-3 Group I isolat$on logic 'A/c tripped AFP A-05, 5-4 Grcup I isolation logic B/d tripped AFP UA-23, 2-6 Main steam line rad. high APP _ UA-03, 5-2 Process off-gas rad high APP UA-03, 2-7' Area rad. Rx.bidg. high

_1. Consult the above annunciator procedures AOP 3.0 moderator temp. decrease A0P.5.3 main steam line or Off gas rad high

2. Consult the above A0P's

3. Consult E0P-01-FP-3 E0P-03-SCCP E0P-01-EPP E0P-04-RECP E0P-02-PCCP E0P-01-LEP-02

. 4. Declare RPCI inop.' consult T/S 3.5.1 for HPCI operability.

5.- Utilize OG6.1 to determine the extent (if any) of review.

6. Gr. I II & VI isolations exist

7. Use RCIC for level control.

8. 4-hour red phone report due to RPS actuation, HPCI injection, group isolations.

CEPIP-18 Rav. 3 l June 1987 CP&L '

EXERCISE MESSAGE CARD l l U-2 Plant l

l Message No. Date 5-23-89 Time 0755 l

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

1. Fire alarm U-2 -17' SE reactor building.

2. Annunciator A-01, 4-7 RHR pump 2B overload A-01, 3-7 RHR pump 2B trip

3. Fire watch reports a large pump motor is engulfed in flames in south RHR -17' elevation.

4. ARM in SRHR is alarming.

ACTIONS EXPECTED:

1. Respond to annunciators, refer to AOP -5.0 for high radiation in SRHR.

2. Request off-site assistance.

3. Consult PFP-013, and applicable assd procedures.

5. SITE EMERGENCY-fire compromising the function of a saf ety system (RHR)

6. 1-hour red phone deportability (50.72(b)(1-)(VI).

7. Enter E0P-03 -SCCP, as appropriate.

FOR CONTROLLER USE ONLY Fire may be in a radiological hazards area due to RCIC turbine operation with reactor fuel damage.

4CEPB 18-22

~ ~ ~ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . _ _ _

~

CEPIP-18 Rov. 3 June 1987 CP&L EXEPCISE MESSAGE CARD l

2 Plant l

Message No. Date 5/7,I / El Time 0810 1

l.

I l

MESSAGE FOR: Shift Operating Supervisor l

FROM: CONTROLLER MESSAGE / SIMULATED PLANT CONDITIONS: "DiIS IS AN EXERCISE MESSAGE" The following annunciators are received:

AFP - A-03 window 5-2 APP A-03 window 5-3 APP A-02 window 5-7 APP A-02 window 6 'i l

ACTIONS EXPECTED:

A-03, window 5-2 RCIC isolation trip A-03, window 5-3 RCIC turbine tripped A-02, window 5-7 steam leak detection ambient temp. high A-02, window 6-7 steam leak detectionatemp high f

FVR CONTROLLER USE ONLY p

4CEPB 18 22

.______._m____ _ _m._ _ _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ . _ _ _ _

l CEPZP-18 RQv. 3 June 1987 CP&L EXERCISE MESSAGE CARD l

U-2 Plant l

Message No. Date 5/23/89 Time 0845 MESSAGE FOR: Fire 3rigade Leader

! FROM: CONTROLLER MESSAGE / SIMULATED PLANT CONDITICMS: "THIS IS AN EXERCISE MESSAGE" The fire is out in south RER -17' elevation. Apparently the fire was fueled by oil leaking from the 3 RHR pump. Dtmage to the B RHR pump and motor appears extensive. Damage to nearby equipment appears to be limited but its impossible to tell based on visual obacrvations.

ACTIONS EXPECTED:

1. Maintenance activities to restore A-loop RHR.

2. Maintenance activities to restore B-loop RHR,.

i FOR CONTROLLER USE ONLY 4CEPB 18-22 l

l l

i l

l

CEPIP-18 Ray. 3 June 1987 CP&L EXERCISE MESSAGE CARD l

1:

_I!-?

1 Plant Upon Receipt of Clearance Message No. Date 5/23/89 Time on D RHR MOVs MESSAGE FOR: Repair Team (B Loop RHR)

FROM: CONTROLLER l

l l

MESSAGE / SIMULATED PLANT CONDITIONS: "THIS IS AN EXERCISE MESSAGE" Note: This clearance is SIMULATED and all actions associated with the evaluation /

testing of D hHR MOVs shall be simulated.

ACTIONS EXPECTED:

Describe actions which would be necessary to complete the requested maintenance activity to the controller.

Actual locations should be identified, procedures reviewed, personnel protective actions observed. -

j

)

FOR CONTROLLER USE ONLY I

Ensure that all activities associated with the evt:1uation/ testing of D RHR MOVs are simulated.

4CEPB 18-22 I

CEPIP Rev. 3 June 1987 CP&L EXERCISE MESSAGE CARD l

U-2 Plant At least 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after repair Message No. Date 5/23/89 Time team leaves OSC MESSAGE FOR: Repair Team (B Loop RHR)

FEOM: CONTROLLER MESSAGE / SIMULATED PLANT CONDITIONS: "THIS IS AN EXERCISE MESSAGE" Bridge and Megger readings for MOVs associated with D RHR pump appear to be satisfactory.

ACTIONS EXPECTED:

Report findings to OSC.

1 FOR CONTROLLER USE ONLY j Provide message upon successful demonstration of knowledge necessary to carry out j activity, j 4CEPB 18-22 k _ _ . _ _ _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ __

l l

CEPIP-18 Rev. 3 June 1987 CP&L l EXERCISE MESSAGE CARD l

U-2 i

l Plant Upon Receipt of Clearance Hessage No. _ Date 5/23/89 Time on D RHR Pump Motor MESSAGE FOR: Repair Team (B Loop RHR)

PROM: CONTROLLER i MESSAGE / SIMULATED PLANT CONDITIONS: "THIS IS AN EXERCISE MESSAGE" Electrical clearance has been completed on D RHR pump motor.

NOTE: This clearance is S1MULATED and all actions associated with the evaluation / testing of D RHR pump motor shall be simulated.

ACTIONS EXPECTED:

j Describe actions which would be necessary to complete the requested maintenance activity to the controller.

Actual locations should be identified, procedures reviewed, personnel protective actions observed. -

FOR CONTROLLER USE ONLY Ensure that all activities associated with the evaluation / testing of D RHR pump motor are simulated.

~

4CEPB 18-22

CEPIP-18 Ray. 3 June 1987 CP&L EXERCISE MESSAGE CARD l

U-2 Plant At least I hour after re-Message No. Date 5/23/89 Time Pair team leaves OSC MESSAGE FOR:

Repair Team (B Loop RHR)

FROM: CONTROLLER MESSAGE / SIMULATED PLANT CONDITIONS: "THIS IS AN EXERCISE MESSAGE" Bridge and Megger readings for D RHR pump motor are within the required range.

ACTIONS EXPECTED:

Report findings to OSC.

FOR CONTROLLER USE ONLY Provide message upon successful demonstration of knowledge necessary to carry out activity.

~

4CEPB 18-22 l

i i

. 1

CEPIP-18 Rev. 3 June 1987 CP&L EXERCISE MESSAGE CARD l

U-2 Plant Upon Receipt of Order to Message No. Date 5/23/89 Ti:ne Reasonable 2-Ell-F017A Limitorque Operator l

MESSAGE FOR: Repair Team (RHR A Loop)

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

1. Upon receipt of order to reassemble 2-Ell-F017A Limitorque Operator carry out all activity necessary for reassembly, simulate actual reassembly.

2. Estimated completion in 3-4 hours.

ACTIONS EXPECTED:

1 FOR CONTROLLER USE ONLY Provide message to Repair Team upon receipt of order to reassemble 2-Ell-F017A.

4CEPB 18-22

t CEPIP-18 Rev. 3 June 1987

]

CP&L I EXERCISE MESSAGE CARD l

U-2 Plant ,

3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> after reassembly Messago No. Date 5/23/89 Time began i

MESSAGE FOR: Repair Team (RHR A Loop) i FRCH: CONTROLLER MESSAGE / SIMULATED PLANT CONDITIONS: "THIS IS AN EXERCISE MESSAGE"  !

2-Ell-F017A Limitorque operator is assembled and valve can be manually stroked at this time.

ACTIONS EXPECTED:

Report completion of work to OSC.

FOR CONTROLLER USE ONLY O

4CEPB 18 22

1 UNIT 0 PEP-02.6.21 Attach 2::nt 5 Page 1 of 1 EX3IBIT 2.6.21-5 SAFETY PARAMETER N SPLAY SYSTEM (UNIT / )

ogerable. Inoperable Standby Running Yes No' Tsolated M - Not available Time _A f W ~

i 1 HPCI Flow (gpm) T AREA RAD MONITORS mR/hr 2 Core Sprav A Flow (epm) -r 37 Rx. Bldr. 20 ft Airlock . f-3 RHR A Flow (apm) r Rx. Bldg. 50 ft Sample 4 RCIC Flow (gpm) 1 5 38 Station /

5 Core Sprav B Flow (epm) i a: 39 Rx. Blda. 50 ft Airlock i /

6 RHR B Flow (epm) i r Rx. Bldg. North of Fuel l 7 SLC Iniecting i A/ 40 Pool i /

8 CRD Flow (gpm) F Ao Between fuel Pool and -

~ l 9 APRM % i o 41 Drwell inors,,f u /._

(

10 Reactor Pressure (psie) i o Turbine Bldg. Sample T1 Reactor Level (in) fr/c.o,o/c/ 42 Station . F" 12 Main Stack Flow Pate (sefm) i ry oo o 43 SJAE A (mR/hr) i i Turbine Bldg. Roof Vent "

44 SJAE B (mR/hr) /

13 Flow (sefm) /Ycau R%. Bldg. Ventilation Rx. Bldg. Roof Vent flow 45 @ nitor (mR/hr) e1 14 (sefm) r40 ou Uervice Water Rad Monitor Rx, Bldg. Negative Press 46 fcps)

~ 90 15 (inchen n' water vacuum) ,3f 16 Suppression Pool Level (in) - 19 OT13FR UNIT 17 nr nwell Pressure (psic) I o Turbine a'dg. Roof Vent IR SBGT Flow A (se emi i 5 47 Flow (scim) /Y,000 19 SBGT Flow B (sefm) i s Turbine nidg. Roof 20 Drwell H, 4409 (% cone.) er 4R Vent Monitor (uCf/=ee.) /, o 21 Drwell H; 4410 (I cone.) '

of 22 Drwell 0; 4409 (I cone.) .t o 23 Drvwell 0; 4410 ( cone.) ao . f 24 AOG Systein Fl ow ( sef m) r 25 Off-Site Power Available v

Main Stack Gas Monitor 26 (UCL/sec) 1. i"'6d Tushine Bldg. Vent Monitor 77 (uCi/sec) /. O DRYWELL HIGH RAD MONITOR !R/hr 28 D22-RM-4195 - 30 ft El. I =/

24 D22 DM-4196 - 57 ft El. I*/

3 0 n ') b RM-419 7 - 2 3 + t F1 44/

31 D22-RM-4198 - 57 +t F1 6ei 32 Drvvell Temn '*Fi i 99 33 Suppression Pool Temp (*F) i FO RX. BLDG. ROOF VENT RAD MONITOR 34 Particulate (comi i rO O 45 Todine (cpm) iFoo 36 Noble Gas (cpm) i a4 0 0 PEP-02.6.21 Rev. 16 Page 22 of 34 l

____m._ _____m______m._

UNIT 0 PEP-02.6.21 Attach =nt 5 Page 1 of 1 EXHIBIT 2.6.21-5 SAFETY PARAMETER DISPLAY SYSTEM (UNIT / )

gerable Inoperable Standby Running Yes No Tsolated NJ - Not available Time OPOo I HPCI Flow (gpm) T AREA RAD MONITORS l mR/hr 2 Core Sprav A Flow (epm) '

Jr 37 Rx. Blde. 20 ft Airlock I ,p 3 RHR A Flow (epm) L Rx. Bldg. 50.ft Sample 4 RCIC Flow (gpm) 6 7 38 Station /

5 core Sprav B Flow (epm) i J 39 Rx. Blde. 50 ft Airlock i r 6 RHR B Flow igpm) i I Rx. Bldg. North of Fuel l 7 SLC Iniecting i A/ 40 Pool ~

I /

8 CRD Flow (gpm) i 40 Between fuel Pool and 9 APRM % i e 41 Drvwell /b mus /4 10 Reactor Pressure (psie) i e Turbine Bldg. Sample 11 Reactor Level (in) I /;tc.odej 42 Station .F 12 Main Stack Flow Rate (scfm) ire con 43 SJAE A (mR/hr) I a_

Turbine Bldg. Roof Vent '

44 SJAE B (mR/hr) i /

13 Flow (sefm) /v000 Rx. Bldg. Ventilation Rx. Bldg. Roof Vent Flow l 45 Monitor (mR/hr) ,3 14 (sefm) IG cou Service Water Rad Monitor Rx. Bldg. Negative Press 46 (eps) '7'O 15 (inches n' water vacuum) ,IT 16 Suppression Pool Level (in) 1 -a_<r OTyra t; NIT 17 nrrvell Pressure (psic) i - Turbine 5'dg. Roof Vent IR SBGT Flow A (sefM i f 47 Flow (sefm) /YOdo 19 SBGT Flow B (sefm) 6 5 Turbine Eldg. Roof 20 Drwell H, 4409 (% cone.) i or 4R Vent Monitor (uCf/=ee.1 /. v 21 Drvvell H; 4410 (% cone.) 1 . o s-22 Drvwell 0; 4409 (% cone.) i20 23 Drvwell 0; 4410 ( conc.) 1 2.e. (

24 AOC System Flow (sefm) l E 25 Of f-Site Power Available i y Main Stack Gas Monitor 26 (tCi/sec) L f, ##

Turbine Ridg. Vent Monitor

?7 (UCilsec) I d e

DRYWELL HICH RAD MONITOR R/hr 28 D22-RM-4195 - 30 ft El. t es 24 022-RM-4196 - 57 ft F.1 14/

30 n'?-RM-4197 - 23 f t F1 1.t 31 D22-RM-4198 - 57 +t F1 i./ i 32 Drvvell Temn ('r) i g 33 Suppression Pool Temp (*F) i Po RX. BLDG. ROOF VENT RAD MONITOR . . _

34 Particulate (com) iWo 35 fodine (cpm) Joo 36 Noble Gas (cpm) 'apo ,

O PEP-02.6.21 Rev. 16 Page 22 of 34 l m__ _ _ _ _ _ ____ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ . _ _

UNIT 0 l

. PEP-02.6.21 Attachm2nt 5 Page 1 of 1 EXHIBIT 2.6.21-5 l SAFETY PARAMETER DISPLAY SYSTEM (UNIT / )

Ogerable Inoperable Standby Running Yes No Tsolated FA,- Not availab3e Time O y/ r 1 HPCI Flow (gpm) r AREA RAD MONITORS I mR/hr

'2 Core Sprav A Flow (epm) u r 37 Rx. Blde. 20 ft Airlock ' ,e 3 RHR A Flow (epm) ,

Rx, Bldg. 50 ft Sample 4 RCIC Flow (gym) i s: 38 Station /

~

$ Core Nerav B Flow (epm) I r- 39 Rx. Blde. 50 ft Airlock i f

~~

6 RHR B Flow (epm) i JE Rx. Bldg. North of Fuel l 7 SLC Iniecting i r/ 40 Pool I t i 8 CRD Flow (gpm) i /o Between Fuel Pool and 9 APRM % i o 41 Drvwell /b a m /w.,

10 Reactor Pressure (psie) i O Turbine Bldg. S sple 11 Reactor Level (in) i Fl,yd,/ 42 Station _r-12 Main Stack Flow Rate (sefm) irroou 43 SJAE A (mR/hr) I 2. _

Turbine Bldg. Roof Vent 44 SJAE R (mR/hr) /

13 Flow (sefm) /* eo Rx. Bldg. Ventilation ,

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

14 (sefs) 3'6 000 Rx. Bldg. Negative Press '

Service Water Rad Monito} 9'O 46 (cos) .

l 15 (inchee n' water vacuum) $r ]

16 Suppre==1nn Pool Level (in) i -r y. c OTyrR UNIT  !

17 nr well Pressure (este) 4 n Turbine b'da. Roof Vent l 1R SBCT 710w A (sefm) i 5 47 T1ow (sefm) /s/ 000 i 19 SBGT Flow B (sefm)  : 5 Turbine Bldg. Roof 20 Drewell H, 4409 (% cone.) I , o s- 4R Vent Monitor (uC1/=ce.1 /. p 21 Drvvell H.* 4410 (% cone.) i of l 22 Drvvell 0; 4409 (% cone.) l2o 1 23 Drvwell 0; 4410 (' cone.) m o . r- l

~

24 AOG System riov (sefm)  %- j 25 Off-Site Power Available v )

Main Stack Gas Monitor l 26 (uCi/sec) 1. fs II 1 Tuthine Bldg. Vent Monitor 77 fuci/sec) /,Op'#

DRYWELL HIGH RAD MONITOR lR/hr -

28 D22-RM-4195 - 30 ft El. i ce 24 0 2 2 8M-4196 - 5 7 f t 5.1 l ./

30 n99-RM-4197 - 23 f t F1, 4 Af 31 D22-RM-4198 - 57 ft *1 i <f 32 Drvwell Temn ("r) I rg 33 Suppression Pool Temp (*F) i 97; RX. BLDG. ROOF VENT RAD MONITOR 34 Particulate (com* i ytn, 45 Todine (cpm) Loc 36 Noble Gas (epm) sev 0 PEP-02.6.21 Rev. 16 Page 22 of 34 l l

UNIT 0

+ ,

PEP-02.6.21 Attachtsnt 5 Page 1 of 1 EXHIBIT 2.6.21-5 SAFETY PARAMETER DISPLAY SYSTEM (UNIT / )

gerable Inoperable S,tandby Running Tes No Tsolated NA - Not available Time OWo 1 HPCI Flow (gpm) i r AREA RAD MONITORS mR/hr 2 Core Sprav A Flow (crm) .5 37 Rx. Blde. 20 f t Airlock , y-3 RNR A Flow (apm) x Rx. Bldg. 50 ft Sample 38 Station /

~

4 RCIC Flow (epm) i s

$ Core Sprav B Flow fepm) # 2: 39 Rx. Blde. 50 ft Airlock i /

6 RHR B Flow (gpm)

• 5 Rx. Bldg. North of Fuel 7 SLC Iniecting i A/ 40 Pool /

8 CRD Flov (gpm) I do Between Fuel Pool anc l 9 APRM I o 41 Drvwell I 0 c v e c. &

10 Reactor Pressure (psic) i o Turbine Bldg. Sample 11 Reactor Level (in) I rm da.,,1 42 Statitsn ,f 12 Main Stack Flow Pate (sefm) ify coo 43 SJAE A (mR/hr) 'l 2_

Turbine Bldg. Roof Vent '

44 SJAE B (mR/hr) /

13 Flow (sefm) f y oco Rx. Bldg. Ventilation Rx. Bldg. Roof Vent flow l 45 Monitor (mR/hr) ,4 14 (sefm) Its coo Service Water Rad Monitor Rx, Bldg. Negative. Press 46 (eps) 9'O 15 (inchen n' unter vacuum) I i' 16 Suppre**1on Pool Level (in) 1 xar OT}:rR UNIT d' 17 nr uwell Pressure (psic) i o Turbine b'dg. Roof Vent IR SBCT Flow A (sefe I s 47 Flov (sefm) / V #00 19 SBGT Flow B (sefm) 1 S Turbine Bldg. Roof l 20 Drwell H, 4409 (I cone.) I,or 4R Vent Monttor (uCf/=ce.) I /, 0 21 22 Drwell H; Drwell 0; 4410 4409 (I cone.) i .or_

(I cone.) I 1.,

23 Drwell 0; 4410 ( cone.) m 5-24 A0G System Flov (sefm) r 25 Off-Site Power Available v Main Stack Gas Monitor #

, 26 (uCi/sec) 1. 5 s r/

Turbine Bldg. Vent Monitor 17 (uCi/sec) -d.

O s "'

DRYVELL HIGH RAD MONITOR IR/hr 28 D22-RM-4195 - 30 ft El. I cf 2(e n22 nM-4196 - 57 ft F.1 l/

30 ni?-RM-4197 - 23 fr F1 ier 31 D22-RM-4198 - 57 't F'. i .f 32 Drvwell Temn (=rs i y, l

33 Suppression Pool Temp (*F) ieo RX. BLDG. ROOF VENT RAD MONITOR 34 Particulate (com$ t rvo 35 Todine (cpm) iJos 36 Noble Gas (com) 4 m.00 0 PEP-02.6.21 Fev. 16 Page 22 of 34 l w_ . . . - - - . . . . . . __ _ _ _ _ _ - . . . _ _ _ . - . _ _ .

UNIT 0

(' PEP-02.6.21 Attachment 5 Page l'of 1 EXHIBIT 2.6.21-5 SATETY PARAMETER DISPLAY SYSTEM (UNIT / )

gerable inoperable Standby Running Yes No T*olated

{A,- Not availab]e Time O W r- 1 1 HPCI Flow (ppm) r AREA RAD MONITORS mR/hr 2 Core Sprav A Flow (rpm) r 37 Rx. Blde. 20 f C Airlock , y-3 RNR A Flow (ppm) i y Rx. Blog. 50 ft Sample 4 RCIC Flow (gym) i I 38 Station a 5 Core Sprav B Flow (epm) e r 39 Rx. Blde. 50 ft Airlock i  ;

6 RHR B Flow (rpm) e r Ex. Bldg. North of Fuel l 7 SLC Iniecting iu 40 Pool i /

8 CRD Flow (gpm) iIo Between Fuel Pool and 9 APRM % O 41 Drvwell he r, /*

10 Reactor Pressure (psie) i o Turbine Bldg. Sample 11 Reactor Level (in) Irtcod ,d 42 Station ,f 12 Main Stack Flow Fate (scfm) IM eau 43 $JAE A (mR/hr) i t lurbine Bldg. Root Vent 44 SJAE B (mR/hr) i /

13 Flow (sefs) /V,000 Rx. Bldg. Ventilation Rx. Bldg. Roof Vent flow 45 Monitor (mR/hr) ,7 14 (sefm) rt coo Service Water Rad Monitoi l

Rx. Bldg. Negative Press 46 (eps) 90 l

15 (inches n' water vacuum) .ff

! 16 Suppression Pool Level fin) i - 2_ t OTFrR UNIT 17 nr vvell Pressure (psie) i O Turbine b'dg. Roof Vent I A S BCT Fl ow A (se'*) I 5 47 Flow (sefm) /V #80 19 SBGT Flow B (setm) i 5 Turbine hidg. Roof 20 Drvwell H, 4409 (" cone.) i,or LA Vent Monitor (UCi/=ec.) /. O 21 Drvwell SI; 4410 (I cone.) I.05-22 Drvwell 0; 4409 (I cone.) I xo 1 23 Drvve11 0; 4410 (' cone.) i a s. s-24 AOC System riou (sefm) Ir 25 Off-Site Power Available i y Main Stack Gas Monitor 26 (UCi/sec) A. rs- T' Turbine Bldg. Vent Monitor 77 (uct/sec)

DRWELL HIGH PAD MONITOR lN#"

I i R/hr 28 D22-RM-4195 - 30 f t E1. t .s 24 022-DM-4196 - 57 ft E1 I ts 30 n n-RM-4197 - 23 ft F1 e .s 31 D22-RM-4198 - 57 ft F1 t .s 32 Drvve11 Temn a't) i y9 33 Suppression Pool Temp (*F) i po RX. BLDG. ROOF VENT RAD

, MONITOR l 34 Particulate (comb i foo M f ortine (epm) i 3<2 o 36 Noble Gas (epm) I a os O PEP-02.6.21 Rev. 16 Page 22 of 34 l l

1 l

UNIT 0 PEP-02.6.21 Attach: nt 5 Page 1 of 1 EXHIBIT 2.6.21-5 SAFETY PARAMETER DISPLAY SYSTEM (1: NIT / )

gerable Inoperable S,tandby Running Yes No Tsolated N,A - Not available Time oroo I HPCI Flow (epm) i I AREA RAD MONITORS mR/hr 2 Core Sprav A Flow (epm) i r 37 Rx. Blde. 20 ft Airlock , c-3 RHR A Flow (gpm) i y Rx. Bldg. 50 ft Sample 4 RCIC Flow (gym) } % 38 Station 1 5 Core Sprav B Flow repm) i y 39 Rx. Blds. 50 ft A!rlock i ,

6 RHR B Flow (gpm) e r Fx. Bldg. North of fuel-l 7 SLC Iniecting iu 40 Pool l / .

8 CRD Flow (gpm) t (. o Between Fuel Pool and l 9 APRM Z l e 41 Drvwell IL u , /s, 10 Reactor Pressure (psig) iO Turbine Bldg. Sample j 11 Reactor Level (in) is, d,./ 42 Station I . S'-

12 Main Stack Flow Pate (setm) 6 6 9 coo' 43 SJAE A (mR/hr) i L Turbine Bldg. Roof Vent l 44 SJAE B (mR/hr) l i 13 Flow (sefs)  ! /% #00 Rx. Bldg. Ventilation Rx. Bldg. Roof Vent flow l 45 Montter (mR/hr) ,y 14 (sefm) IJ 4 cc o' Rx. Bldg. Negative Press Service 46 (cps) Water had Monitoq#/O l

15 (inches n' water vacuum)_ _ _ _ _ _ , 7J-16 Suppre== inn Pool Level (in) 6 2 +f OTprR UNIT 17 nr a'well Pressure (psic) 6 o Turbire k'dg. Roof Vent IA SBGT Flow A (sefm1 15 47 Flow (sefm) / 8/ c c o 19 SBGT Flow B (sefm) i 5 Turbine bldg. Rooi 20 Drvve11 H, 4409 (I cone.) i.oc 4R Vent Monitor (uC1/=ce.1 /. O 21 Drvwell H; 4410 (I cone.) i . o f-22 Drvvell 0; 4409 (I cone.)  !

w 23 Drvve110; 4410 (" cone.) 20,s-24 A0G System Flov (sefm) r 25 Of f-Site Power Available y Main Stack Gas Monitor

. 26 (uci/sec) 2.3p 7#

Turbine Blds. Vent Monitor 77 (uCi/sec) /.o r r#

DRYkT.LL HIGH RAD MONITOR Rihr -

28 D22-RM-4195 - 30 ft El. <<

24 n22 RM-4196 - 57 ft F.1  ! +i 30 h"-Rw-419 7 - 23 8 e F1 # *s 31 D22-RM-4198 - 57 ft F1 Ii 32 Drvvell Temn Fi 8 s-*

33 Suppression Pool Temp ( *Fi i pp l

RX. BLDG. ROOF VENT RAD MONITOR 34 Particulate (comi u .v c o M _fodine (cpm) Isoc 36 Noble Gas (epm) Isou 0 PEP-02.6.21 Fev. 16 Page 22 of 34 l

__._____._______._m _ _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ . _ _ _ - . _ _ _ ._ _ _ _ _ . . . -

UNIT 0 PEP-02.6.21 Attschm nt 5 Pare 1 of 1 EXHIBIT 2.6.21-5 SAFETY PARAMETER DISPLAY SYSTEM (UNIT / )

gerable ineperable Standby Running Yes No Tsolated l NJ - Not availab3e Time O r/ f~

l HPCI Flow (apm) r AREA RAD MONITORS mR/hr 2 Core Sprav A Flow (epm) r 37 Rx. Blde. 20 f t Airlock 3 3 RHR A Flow (gpm) i L Rx. Bldg. 50 ft Sample 4 RCIC Flow (apm) i s 38 Station to 5 Core Sprav B Flow fepmp i 25 39 Rx. Blde. 50 ft Airlock i so 6 RHR B Flow (gpm) iT Ex. Bldg. North of Fuel  ;

7 SLC Iniecting  ! /v 40 Pool Po o 8 CRD Flow (gpm) I to Between Fuel Pool and 9 APRM % i o 41 Drvwell /roo 10 Reactor Pressure (psie) i o Turbine Bldg. Sample 11 Reactor Level (in) Irt ..ok/ 42 Station . S~

- 12 Main Stack Flow Rate (sefm) 170eco '

43 SJAE A (mR/hr) I 2.

Turbine Bldg. Roof Vent 44 SJAE B (mR/hr) i 13 Flow (sefm) ty0so Rx. Bldg. Ventilation Rx. Bldg. Roof Vent flow 45 Monitor (mR/hr) 1 14 (sefm) d ~

Service Water Rad Monitoi' Rx. Bldg. Negative Press 46 (eps) Yo 15 (techen n' water vacuum) ,V 16 Suppression Dool Level (in) .t? OTFFR UNIT 17 Dr*well Pressure (psir) i o Turbine U dg. Roof Vent IR SBGT Flow A (sc#m} l .t o o o 47 Flow (sefm) / Y ooo 19 SBGT Flow B (sefm) 17,0 0 Turbine Ridg. Roof 20 Drvwell H, 4409 (" cone.) i or 4R Vent Monitor (uCf/=ee.) /v 21 Drvwell H; 4410 (% cone.) I,or 22 Drvwell 07, 4409 (% cone.) so 23 Drvvell 0; 4410 (' cone.) 3 o. 5-24 A0G System Flow (sefm) r 25 Off-Site Power Available v Main Stack Gas Monitor '

, 26 (u0i/see) r. o s #

Turbine Bldg. Vent Monitor 77 (uCi/sec) 2.1pr#

DRYVELL HIGH RAD MONITOR IR/hr 28 D22-RM-4195 - 30 ft El. It/

20 D 2 2 SM-4196 - 5 7 f t E.1 6 ./

30 n'?-Rv-4197 - 23 f t F1 i st 31 D22-RM-4198 - 57 *t r1 i ./

32 Drvvell Temn '"ri i V9 33 Suppression Pool Temp (*F) Ir0 RX. BLDG. ROOF VENT RAD MONITOR

!4 Particulate (com' t 75 y Todine (cpm) I pf 36 Noble Gas (cpm) l 53 0 PEP-02.6.21 Fev. 16 Page 22 of 34 l e

UNIT 0 PEP-02.6.21 Attachmnt 5 Page 1 of 1 EXHIBIT 2.6.21-5 SAFETY PARAMETER DISPLAY SYSTEM (UNIT / )

gerable Inoperable Standby Running Yes No Tsolated 3 - Not avr.ilable Time 057o I HPCI Flow (rym) I r AREA RAD MONITORS mR/hr 2 Core Sprav A Flow (epm) l x- 37 Rx. Blde. 20 ft Airlock 5-3 RHR A Flow (epm) I s. Rx. Bldg. 50 ft Sample 4 RCIC Flow (gpm) i I: 38 Station /o 5 Core Sprav B Flow iepm) t I 39 Rx. Blde. 50 ft Airlock i fo

,6 RHR B Flow (epm) i p Rx. Bldg. North of Fuel 7 SLC Iniecting i A/ 40 Pool fo o 8 CRD Flow (gpm) 1 4v Between Fuel Pool and 9 APRM % i o 41 Drvwell /$~C O 10 Reactor Pressure (pste) l- o Turbine Bldg. Sample 11 Reactor Level (in) I Ftwd 42 Station , .5~

12 Main Stack Flow Pate (sefm) 6 yo n o 43 SJAE A (mR/hr) z Turbine Bldg. Roof Vent 44 SJAE B (mR /hr) f 13 Flow (sefs) /Yvoo Rx. Bldg. Ventilation Rx. Bldg. Roof Vent Flow 45 Monitor (mR/hr) J 14 (sefm) O Service Water Rad Monito1' Rx. Bldg. Negative Press 46 (eps) Yo 15 (inchen n' water vacuum) ,y 16 Suppression Dool Level (in) 6-23 OTFFR UNIT 17 nr vvell Pressure (psic) i o Turbine b'dg. Roof Vent IR SBGT Flow A (sef@ i soo o 47 Flow (sefm) /V ro o 19 SBGT Flow B (sefm) Ifoeu Turbine Bldg. Roof '

20 Drwell H, 4409 (% cone.) i , of- 4R Vent Monitor (uCf/=ec.i /, O 21 Drvvell H; 4410 (* cone.) 1. 0 5~

22 Drvvell 0; 4409 (I conc.) Iso 23 Drvvell 0; 4410 (9 cone.) 120. r-24 A0G Svstem Flow (sefm) Ir 25 Off-Site Power Available I y Main Stack Gas Monitor 26 (uCi/sec)

Turbine Bldg. Vent Monitor ros"

'87 (uci/sec) /.oe# #

DRYkT.LL HIGH IRAD MONITOR iR/hr 28 D22-RM-4195 - 30 ft El. t 4, 24 n22.ng.4196 - 57 ft r.1 Ia 30 n'?-RM-4197 - 23 ft F1 1 -/

31 D22-RM-4198 - 57 *e r'. l ./

32 Drvwell Temn ("M t 6, 5 33 Suppression Pool Temp ( *F) I po RX. BLDG. ROOF VENT RAD MONITOR 34 Particulate (com) tT3

.M f ortine (cpm) sc 36 Noble Gas (cpm) p.5 0 PEP-02.6.21 Fev. 16 Page 22 of 34 l

UNIT 0 PEP-02.6.21 Attachment 5 Page 1 of 1 EXHIBIT 2.6.21-5 SAFETY PARAMETER DISPLAY SYSTEM (UNIT / )

Ogerable Inoperable Standby Running Yes No Tsolated NA - Not available Time crys-1 HPCI Flow (gpm) l % AREA RAD MONITORS mR/hr 2 Core Sprav A Flow (epm) 1 I 37 Rx. Blde. 20 ft Airlock 5-3 RHR A Flow (gpm) i r Rx. Bldg. 50 ft Sample 4 RCIC Flow (gpm) r 38 Station /0 5 Core Sprav B Flow (epm) I r 39 Rx. Blde. 50 ft Airlock i fa 6 RHR B Flow (gpm) ' r Rx. Bldr. North of Fuel 7 SLC Iniecting I fu 40 Pool S oo 8 CRD Flow (gpm) i Go Between Fuel Pool and 9 APRM % i o 41 Drwell /rea 10 Reactor Pressure (psie) I o Turbine Bldg. Samp <

11 Reactor Level (in) ( pt.o /.4 42 Station ,

t--

12 Main Stack Flow Pate (scfm) i yo co o 43 SJAE A (mR/hr) I a Turbine Bldg. Roof Vent l 44 SJAE B (mR/hr) /

13 Flow (sefm) I/voso Rx. Bldg. Ventilation Rx. Bldg. Roof Vent Flov l 45 Monitor (mR/hr)  ?

14 (sefm) I O Service Water Rad Monito1' Rx. Bldg. Negative Press 46 (eps) #o f

15 (inches n' water vacuum) ,V 16 Suppremainn Dool Level (in) l- s 9 OT2rR UNIT 17 nr vwell Pressure (psie) i o Turbine L'dg. Roof Vent la SBGT Flow A (sefM 17ooo 47 Flow (sefm) /V vp v 19'SBGT Flow B (sefm) lyooo Turbine Bldg. Roof 20 Drvvell H, 4409 (% cone.) i , o c- 4R Vent Monitor (uCf/=ee.) /, a 21 Drvwell H; 4410 (! cone.) I , o r-22 Drvvel1 0; 4409 (! cone.) i 2. o 23 Drvwell 0; 4410 P cone.) isc r 24 AOG Sy s t em Fl ow ( se f m) ir 25 Of f-Site Power Available I y Main Stack Gas Monitor 26 (uCi/sec) /,2 / #

Turbine Bldg. Vent Monitor 17 (uCi/sec) /,0 # "

DRYkT.LL HIGH RAD MONITOR 'R/hr 28 Dj2-RM-4195 - 30 ft El. t ti 20 022 #M-4196 - 57 ft F.1 . I ci 30 n'9-RM-4197 - 23 't F1, 6 Af 31 D22-RM-4198 - 57 't r' . i ts 32 Drvwell Temn ("M i vy 33 Suppression Pool Temp (*F) i 90 RX. BLDG. ROOF VENT RAD MONITOR 34 Particulate (com) i If 35 Todine (cpm) i Tr 36 Noble Gas (epm) t rs l

0 PEP-02.6.21 Fev. 16 Page 22 of 34 l

UNIT 0 PEP-02.6.21 Attachment 5 Page 1 of 1 EXHIBIT 2.6.21-5 SAFETY PARAMETER DISPLAY SYSTEM (UNIT / )

Ogerable I,noperable Standby Running Yes No Tsolated NA - Not available Time Ot00 1 HPCI Flow (gpm) 10 AREA RAD MONITORS mR/hr 2 Core Sprav A Flow (rpm) '

r 37 Rx. Blde. 20 ft Airlock 5-

~3 RHR A Flow (apm) '

t Rx. Bldg. 50 ft Sample 4 RCIC Flow (apm) 6 :: 38 Station /o 5 Core Sprav B Flow (cpm) I

_39 Rx. Blde. 50 ft Airlock i fa lL 6 RHR B Flow (epm) i I Rx. Bldg. North of Fuel l 7 SLC Iniecting j v 40 Pool Sip o 8 CRD Flow (gpm) I go Between Fuel Pool and 9 APRM % !o I.1 Drvwell /5 ao 10 Reactor Pressure (psie) i o Turbine Bldg. Sample 11 Reactor Level (in) Irt /u9 42 Station , S' 12 Main Stack Flow Pate (sefm) t7e000 63 SJAE A (e@/hr) i t Turbine Bldg. Roof Vent 44 SJAE B (mR/hr) s 13 Flow (sefm) /yooo Rx. Bldg. Ventilation Rx. Bldg. Roof Vent Flow 45 Monitor (mR/hr) 3 14 (sefm) O Service Water Rad Monito1' Rx. Bldg. Negative Press 46 (eps) Yo 15 (inches n' water vacuum) ,V 16 Superegginn pool Level (in) i-sy OTyrR UNIT 17 nr vwell Pressure (psig) I o Turbine P dg. Roof V"ent IR SBGT Fl ow A (sefm) + 3ece 47 Flow (sefm) / Y 000 19 SBGT Flow B (sefm) 8Joo. Turbine Bldg. Roof " '

20 Drvvell H, 4409 (% cone.) I,or 4R Vent Monitor (uCf/=ec.) /. o 21 Drvwell H; 4410 (I conc.) I , o s-22 Drvwell 0; 4409 (% cone.) 1 ao 23 Drvwell 0; 4410 (' cone.) x o. c 2/,A0G 3 System Flow (sefm) z:

25 Of f-Site Power Available y Main Stack Gar Monitor 26 (uCi/sec) A /grF Turbine Bldg. Vent Monitor 77 (uCi/sec) /,0 s ' #

DRYWELL HIGH RAD MONITOR R/hr -

28 D22-RM-4195 - 30 ft El. t *r 20 022 9M-4196 - 57 ft F.1 l .i 30 n'?-Rv-4197 - 23 ft F1 I -i 31 D22-RM-4198 - 57 ft ri, 6f 32 Drvvell Temn ('r) t yt 33 Suppression Pool Temp (*F) I e, 1 RX. BLDG. ROOF VENT RAD i MONITOR 36 Particulate (comi i r3 35 Todine (cpm) zy 36 Noble Gas (com) r4 I

O PEP-02.6.21 Rev. 16 Page 22 of 34 l i

UNIT 0 PEP-02.6.21 Attach = nt 5 Page 1 of 1 EXHIBIT 2.6.21-5 SAFETY PARAMETER DISPLAY SYSTEM (UNIT / )

gerable Inoperable Standby Running Yes No Tsolated 3 - Not available Time 64/S'

~

1 HPCI Flov (epm) t- AREA RAD MONITORS mR/hr 2 Core Sprav A Flev (epm) r 37 Rx. Blda. 20 ft Airlock to 3 RHR A Flow (spm) r' Rx. Bldg. 50 ft Sample 4 RCIC Flow (gpm) i t 38 Station //

5 Core Sprav B Flow fepm) iT 39 Rx. Blde. 50 ft Airlock i s7 6 RHR B Flow (epm)  ! r Rx. Bldg. North of Fuel 7 SLC Iniecting I af $ 90o1 .). s 0 8 CRD Flov ( apm) I do Between Fuel Pool and 9 APRM % 1 0 41 Drwell 700 10 Reactor Pressurra (psie) i O Turbine Bldg. Sample 11 Reactor Level Itn) I f:tw 42 Station , S-12 Main Stack Flow Pate (sefm) i ro e,o o 43 SJAE A (mR/hr) i2 Turbine Bldg. Root Vent 44 SJAE B (mR /hr) /

13 Flev (sefm) /v evo Rx. Bldg. Ventilation Rx. Bldg. Root Vent Flow 45 Monitor (mR/hr)'- 7 14 (sefm) o Service Water Rad Monitor Rx. Bldg. Negative Press ,46 (ces) 9'o 15 (inchen n' water vacuum) .9 16 Suppres=1rm Pool Level (in) 1-29 nTFFR UNIT 17 Drwell Pressure (osic) i O Turbine u dg. Roof Vent IR SBGT Flow A ( s c'O lsooo 47 Flow (sefm) /9 000 19 SBGT Flow B (sefm) 17eco Turbine Bldg. Roof

,20 Drvvell H, 4409 (% cone.) .or 4R Vent Monitor (uCi/=ec.) 1. u 21 Drvvell H; 4410 (% cone.) '

. o s-22 Drvvell 0; 4409 I% cone.) i ao 23 Drvwell 0; 4410 (f cone.) 6 .2 o . s-24 AOG System Flov (sefm) r E Off-Site Power Available y Main Stack Gas Monitor 26 (tC1/sec) .1, / pd Turbine Bldg. Vent Monitor 77 (uCi/sec) /. o K #

DRYWELL HIGH RAD MONITOR IR/hr 28 D22-RM-4195 - 30 ft El. i <<

24 n22-tM-4196 - 57 ft 8.1 . i .,

30 n"-Rw4197 - 23 't F1 i .i 31 D22-RM-4198 - 5 7 ft r' . i et 32 Drvvell Temn (m i 99 33 Suppression Pool Temp ( *F) I g-o RX. BLDG. ROOF VENT RAD MONITOR 34 0 articulate (comt ze i 15 Todite (cpm) er 36 Noble Gas (com) 55 .

O PEP-02.6.21 Fev. 16 Page 22 of 34 l f

.m. _ . _ ._ . _ _ _ . . _ . _ . . . _ _ . . _ - . , . . . . _ . _ . _ _ . . _ - _ . _ _ . , . _ _ _ _ _ _ . . _ . . . _ . _ _ . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ . _ . _ _ _ _ . _ _ _ _ _ _ - _ _ - - -

UNIT 0 PEP-02.6.21 Attcchm2nt 5 Page 1 of 1 EXHIBIT 2.6.21 SAFETY PARAMETER DISPLAY SYSTEM (UNIT / )

Ogerable Inoperable Standby Running Yes No Tsolated NA - Not available Time C6 ?o 1 HPCI Flow (gpm) T AREA RAD MONITORS mR/hr 2 Core Sprav A Flow (epm) sr 37 Rx. Blde. 20 ft Airlock ir 3 RHR A Flow (epm) T Rx. Bldg. 50 te Sample 4 RCIC Flow (epm) '

r 38 Station /6 5 Core Sprav B Flow (epm) 8

• 39 Rx. Blde. 50 ft Airlock I /6 6 RHR B Flow (gpm) I r Rw, Blda. North of Fuel 7 SLC Iniectine i A/ 40 Pool /oo 8 CRD Flow (epm)

~

i Go Between Fuel Pool and 9 aP'RM % i o 41 Drvwell 35 0 10 Reactor Pressure (psie) I o Turbine Bldg. Sample 11 Reactor Level (in) !st../A2' 42 Station , f-12 Main Stack Flow Pate (scfm) 17 7' cou 43 SJAE A (mR/hr) I 1 Turbine Bldg. Roof Vent 44 SJAE B (mR/hr) /

13 Flow (sefm) /Y oeo Rx. Bldg. Ventilation Rx. Bldg. Roof Vent Flow 45 Monitor- (mR/hr) 7 14 (sefm) O Service Water Rad Monitov Rx. Bldg. Negittive Press 46 (eps) '/O 15 (inchee n' water vacuum) ,Y 16 Suppren=1on Pool Level (in) s. x 9 nTHrR UNIT 17 nr vvell Pressure (ps12) i o Turbine A'dg. Roof Vent IR SBGT Flow A (sef9)  ! Poco 47 Flow (sefm) tvooo 19 SBGT Flow B (sefm) i7ooo Turbine Bldg. Roof 20 Drvwell H, 4409 (: cone.) ,06 4R Vent Monitor (uCf/cee.1 /. o 21 Drvvell H; 4410 (7. cone.) , o f-22 Drvwell 0; [409 (1 cone.) i ao 23 Drvwell 0; 441n ( conc.) ao. r 24 AOG System Flow (sefm) 27 25 Off-Site Power Available v

/

Main Stack Gas Monitor 2G (uC1/sec) 1. y pt '

Turbine Bldg. Vent Monitor 97 (uCi/sec) 1.. l e ""

DRYVELL HIGH RAD MONITOR iR/hr 28 D22-RM-4195 - 30 ft El. et 20 D22-RM-4196 - 57 ft El. I 4/

30 n19-Rw-4197 - 23 ft F1, { ,f 31 D22-RM-4198 - $7 ft F1 i ef 32 Drvvel) Temn I'ri tyk 33 Suppression Pool Temp (*F) iF7 RX. BLDG. . ROOF VENT RAD MONITOR 34 Particulate (comi ,

r5 45 Todine (cpm) s t_

36 Noble Gas (cpm) 21s O PEP-02.6.21 Fev. 16 Page 22 of 34 l l

l

. I

UNIT 0 PEP-02.6.21-Attachment 3 3 Page 1 of 1 EXHIBIT 2.6.21-5 SAFETY PARAMETER DISPLAY SYSTEM (UNIT / )

- Ogerable Inoperable Standby Running Yes No Tsolated NA - Not available Time C6 W 1

~

1 HPCI Flow (epm) I r AREA RAD MONITORS mR/hr 2 Core Sprav A Flow (epm) r 37 Rx. Blde. 20 ft Airlock 3o 3 RHR A Flow (epm) r Rx. Bldg. 50 ft Sample 4 RCIC Flow (epm) 6 z 38 Station 1_ o 5 Core Sprav B Flow tepm) i T. 39 Rx. Blde. 50 ft Airlock i 2_ o 6 RHR B Flow (gpm) t% Rx. Bldg. North of fuel 7 SLC Iniecting l As 40 Pool S0 8 CRD Flow (epm) i 4, o Between fuel Pool and

• ~

9 APRM % 1 o 41 Drvwell /5 0 10 Reactor Pressure (psie) I o Turbine Bldg. Sample al Reacccr f.evel (in) !n,s.or 42 Station ,F 12 Main Stack Flow secc t ecfm)J /rcoo 43 SJAE A (mR/hr) i 2_

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

Rx. Bldg. Roof Vent Flow j 3 14 (sefm) l O Service Water Rad Monitor Rx. Bldg. Negative Press 46 (eps): 90 15 (inchen n' water vacuum)- <Y 16 Suppremainn Pool Level (in) 6-29 OTFFR UNIT 17 nr vuell Pressure (esia) i o Turbine R'dg. Roof Vent IR SBGT Flow A (scfmi ipooo 47 Flow (sefm) /4 coo 19 SBGT Flow B (sefm) 17 oco Turbine Bldg. Roof 20 Drvwell H, 4409 (% cone.) I . 05- 4R Vent Monitor (uCf/=ec.T /, v 21 Drvwell H; 4410 (* conc.) ,or I2 Drvwell 0; 4409 (% cone.) So 23 Drvwell 0; 441n ( cene.) 2.o, r 24 AOG Systeni Flow (sefm) r-25 Off-Site Power Availtble y Main Stack Gas Monitor 26 (uCi/see)_ f,5 gri Turbine Ridg. Vant Monitor

7 (uCi/sec) /, d# "

DRYWELL HIGH RAD MONITOR R/hr 28 D22-RM-4195 - 30 ft El. i er 24 022 RM-4!96 - $7 ft F.1 l .,

3n n n-RM- 19 7 - 23 + t F1 I .,

31 D22-RS-4198 - 5 7 f t M. i ./

32 Drvvell Temn I*ri t 99 33 Suppression Pool Temp (*F) itv RX. BLDG. ROOF VENT RAD ,

MONITOR 34 Particulate (comi ' rs 35 Todine (com) rr 36 Noble Gas (cpm) r4 0 PEP-02.6.21 Rev. 16 Page 22 of 34 l 1

UNIT 0 PEP-02.6.21 Attachment 5 Page 1 of 1 EXHIBIT 2.6.21-5 SAFETY PARAMETER DISPLAY SYSTEM (UNIT / )

02 erable Inoperable Standby Running Yes No isolated 3 - Not available Time 670C 1 HPCI Flow (gpm) =. AREA RAD MONITORS i r.R/hr 2 Core Sprav A Flow (epm) 2 37 Rx. Blde. 20 f t Airlock i ef-3 RHR A Flow (epm) z Rx. Bldg. 50 ft Sample 4 RCIC Flow (epm)  % ,

38 Station /c 5 Core Sprav B Flow repm) 1 3: 39 Rx. Blde. 50 ft Airlock i is 6 RHR B Flow (gpm) e C. Rx. Bldg. North of Fuel I 7 SLC Iniecting i A/ 40 Pool lVo 8 CRD Flow (gpm) 1 6o Between Fuel Pool and 9 APRM % 1 o 41 Drwell /Yo l 10 Reactor Pressure (psie) i o Turbine Bldg. Sample l 11 Reactor Level (in) !ftw./ 42 Station . 5-~

l- 12 Main Stack Flow Pate (scfm) 171 43 SJAE A (mR/hr) 2 Turbine Bldg. Roof Vent 44 SJAE B (mR /hr) f 13 Flow (sefm) l y oo o Rx. Bldg. Ventilation Ax. Bldg. Roof Vent flow 45 Monitor (mR/hr)  ?

[4,(sefs) C Service Water Rad Monitor Rx. Bldg. Negative Press 46 (eps) Yo 15 (inchea n' water vacuum) ,Y 16 Suppression pool Level (in) i_25 _ OTFFR UNIT 17 nr *well Pressure (osie) I o Turbine u dd. Roof Vent IR SBGT Flow A (scfmi I :r o o , 47 Flow (scim) / Y, o o o 19 SBGT Flow B (sefm) iroop Turbine Bldg. Roof

~[0 Drwell H, 4409 (% cone.1 i o .e 4R Vent Monitor (uCi/ cec.) /. O 21 Drwell H; 4410 (% cone.) I , o .r 22 Drwell 0; 4409 (% cone.) go 23 Drwell 0; 4410 ( cone.) sog 24 AOG Svstem Flow (sefm) r 25 Of f-Site Power Available '

v Main Stack Gas Monitor 26 (uCi/sec) 9.O s O Turbine Bldg. Vent Monitor 77 fuci/sec) /, o p f "

DRYWELL HIGH RAD MONITOR R/hr 28 D22-RM-4195 - 30 ft El. .f 24 D22 nM-4196 - 57 ft E1 1 -r ,

I 30 n'?-RM-4197 - 23 ft F1 l ./

31 D 22-RM-4198 - 57

• t F1 ( ur 32 Drvve11 Temn <ar) i g9 33 Suppression Pool Temp (*F) i yo RX. BLDG, ROOF VENT RAD MONITOR 34 Particulate (comi 75 M Todine (cpm) 55 36 Noble ,G_as (cpm) 5s 0 PEP-02.6.21 Rev. 16 Page 22 of 34 l I

i UNIT 0 FEP-02.6.21 Attachment 5 Page 1 of 1 EXHIBIT 2.6.21-5 SATETY PARAMETER DISPLAY SYSTEM (1 NIT / )

r Ooerable Inoperable . Standby Ru'nning Yes No Tsolated NA - Not available Time () 7 f,f~

l HPCI Flow irpm) QC AREA RAD MONITOR 5 mR/hr 2 Core Sorav A Flow (epm) =r 3 RHR A Flow (epm) 37 Rx. Blde. 20 f t Airlock /O 4 RCIC Flow (epm)

I s: Rx. Bldg. 50 ft Sample ic 38 Station /O 5 Core'Sprav B Flow (epm) 6 RHR B Flow (rpm) i 1: 39 Rx. Blde. 50 ft Airlock i /0 I nr Rx. Bldg. North of Fuel 7 SLC Iniecting i A/ 40 Pool f0 8 CRD Flow (spm) !to-9 APRM %

Between Fuel Pool and

} o 41 Drvvell /fd-10 Reactor Pressure (psis) I o Turbine Bldg. Sample 11 Pst etor Level (in) Irt ds,7 42 Station . T' 12 MaYn Stack Flow Rate (sefm) 174 ODO- 43 SJAE A (mR/hr) s at Turbine Bldg. Roof Vent 44 SJAE B l (mR/hr) i 13 Flow (sefm) i/voco Rx. Bldg. Ventilation ,,

Rx. Bldg. Roof Vent Flow 45 Monitor (mR/hr) c' 14 (sefm) <3 Rx. Bldg. Negative Press Service Water Rad Monitog 46 (cos) i VO 15 (inchen n' unter vacuum) ,y 16 Suppremmion Dool Level (in) . 3_ t OTHER UNIT 17 ".r*well Pressure (psin) i o Turbine F'.dg. Roof Vent 34 SBGT Flow A (sefmi )7een 47 Flow (sefm) # Y r o c) 19 SBGT Flow B (sefm) 300, Turbine Bldg. Roof 20 Drvve11 H, 4409 (% cone.) .or 4R Vent Monitor (uCf/=ee.) /. o 21 Drvwell H; 4410 (% cone.) _ e ,-

22 Drvve110: 4409 (% cone.) so 23 Drvvell 0; 4410 (' cone.) t o , 3-24 AOG Systes Flov (sefm) 7C 25 Of f-Site Power Available V Main Stack Gas Monitor #

26 (tCi/sec) /tJ76 #

Turbine Bldg. Vent Monitor

'7 (uCi/sec) /. 8 F "#

DRYWELL HIGH RAD MONITOR R/hr -

28 D22-RM-4195 - 30 ft El. 4s 2 0 D ? 2 DM-419 6 - 5 7 f t F.1 t/

3n n'9-Rw-4197 - 23 ft F1 't 31 D 22-RM-4198 - 5 7 't c1 .i 32 Drvvell Temn ("ri rv 33 Suppression Pool Temp (*F) tro RX. BLDG. ROOF VENT RAD MONITOR 34 Particulate (comi 3:r 45 Todine (cpm) l 2:s 36 Noble Gas (epm) %7 s O PEP-02.6.21 Fev. 16 Page 22 of 34 l I

J

UNIT 0 PEP-02.6.21 Attachunt 5 Page 1 of 1 EXHIBIT 2.6.21-5 SAFETY PARAMETER DISPLAY SYSTEM (L* NIT / )

Ogerable Inoperable Standby Running Yes No Tsolated NA - Not available Time C 78d i HPCI Flow (epm) r AREA RAD MONITORS mR/h'r '

2 Core Sprav A Flow (epm) r 37 Rx. Blde. 20 ft Airlock C 3 RHR A Flow (epm) I r Rx. Bldg. 50 fe Sample 4 RCIC Flow (rpm) i 2 38 Station- -5 5 Core Sprav B Flow (epm) # 2; '

39 Rx. Blde. 50 ft Airlock 6 6 RHR B Flow (rpm)

• T Rx. Bldg. North of Fuel 7 SLC Iniecting A CRD Flow (gpm) iy 40 Pool Kd I go Between Fuel Pool and j 9 APRM % i e 41 Drwell I / /C 10 Reactor Pressure (psta)  : o Turbine Bldg. Sample 11 Reactor Level (in) I pc,Js 42 Station- < 3-12 Main Stack Flow Pace (scie) i 75, o oo 43 SJAE A (mR/hr) i 2.

Turbine Bldg. Roof Vent 44 SJAE B (mR/hr) i l f 13 Flow (sefm) I l'/ vo c> Rx. Bldg. Ventilation Rx. Bldg. Roof Vent Flow 14 (sefm) O 45 Monitor (mR/hr) 1 Service Water Rad Monitor Rx. Bldg. Negative Press ( 46 (cps) '/'a 15 (inchen nr' water vacuum) I , P 16 Suporension Pool Level (in) 1 - 2.9 OTF". l' NIT 17 nr *vell Pressure (pste) I ^-

Turbine a'dg. Roof Vent j 1R SBGT Flow A (sedan i vco o 47 Flev (sefm) i/YJec 19 SBGT Flow B (sefm) 1 7eco Turbine ildg. Roof 20 Drwell H, 4409 (1 cone.) i ,cr 44 Vent Monitor (uCfIcee.) /'O 21 Drwell H; 4410 (% cone.) i , o s-22 Drwell 0; 4409 (% cone.) i le 23 Drwell 0; 4410 (' cone.) I Ac. s-24 AOG System Flow (sefm) { T 25 Off-Site Power Available i y Main Stack Gas Monitor 26 (uCi/sec) 04F Turbine Bldg. Vent Monitor 77 fuci/see) /, O E DRWELL HIGH RAD MONITOR .R/hr 2R D22-RM-4l95 - 30 ft El. i .i 20 022 RM-4196 - 57 f t 5.1 I A/

30-no?-RM-4197 - 23 ft F1 i */

31 D22-RM-4198 - 57 f e r'. i </ ~

32 Drvwell Temn '"ri i dr9 J3 Suppression Pool Temp ( *Fi i w RX. BLDG. ROOF VENT RAD l MONITOR I 34 Particulate (comi  ! If 45 Todine (cpm) I cf 36 Noble Gas (cpm) 1 Es O PEP-02.6.21 Rev. 16 Page 22 of 34 l t'- _ _ _ , _ _ , , _ _ _ _ _ _ _ _ , , _ _ , _ _ _ _ , _ _ _ _ _ _ _ _ _ _ _ _ _ , _ _ _ _ _ _ _ _ _ _

UNIT 0 PEP-02.6.21 Attachment 5 Page 1 of 1 EXHIBIT 2.6.21-5 SAFETY PARAMETER DISPLAY SYSTEM (UNIT / )

02 erable I,noperable Standby Running Yes No Tsolated 3 - Not available Time O 7ff~

l HPCI Flow (epm) l I' AREA RAD MONITORS mR/hr 2 Core Sprav A Flow (epm)  ! x 37 Rx. Bldr. 20 f t Airlock 3 RHR A Flow (epm) 1 i r Rx. Bldg. 50 ft Sample 4 RCIC Flow fepm) i n 38 Station 5 Core Sprav B Flow (epmp i 7 J

39 Rx. Bldg. 50 ft Airlock c 6 RHR B Flow (apm) l

1. % Rx. Bldg. North of Fuel 7 SLC Iniecting 1 A/ 40 Pool 8 CRD Flow (gem) SO 1 60 Between Fuel Pool and 9 APRM % o I

41 Devwell faa 10 Reactor Pressure (psie) I & Turbine Bldg. Sample 11 Reactor Level (in) I rc. ./.,/ 4 2 Station . 3~

12 Main Stack Flow Pate (sefm) 6 7(co p 43 SJAE A (mR/hr) 1 Turbine Bldg. Roof Vent 44 SJAE P l' (mR/ hr) /

13 Flow (sefm) I / y, 000 Rx. Bldg. Ventilation Rx. Bldg. Roof Vent Flov 14 (sefm) l I U 45 Monfter (mR/hr) 1 Rx. Bldg. Negative Press Service Water Rad Monitor 46 (eps) fo 15 (inchen n' water vacuum) '/

16 Supprenainn Dool Level (in) .Af nTHER UNIT 17 nrarwell Pressure (psie) e Turbine Mdg. Roof Vent 1A SBGT Flow A (se'm) l y 000 47 Flow (sefm) /y000 19 SBGT Flow B (sefm) I re co Turbine Bldg. Roof '

20 Drwell H, 4409 (% cone.) i er f A Vent Monitor (uCi /*ec.) /0 21 Drwell H; 4410 (% conc.) I o 3-22 Drwell 0; 4409 (% cone.) ( s c, 23 Drwell 0; 4410 ( cone.) 10. <-

24 AOG Systern Flow (sefm) c 25 Of f-Site Power Available f y Main Stack Gas Monitor f 26 (uCi/see) [, O f~7f -

Turbine Hldg. Vent Monitor 77 (uC1/sec) /, O 6 DRYWELL HIGH RAD MONITOR IR/hr .

28 D22-RM-4195 - 30 fe El. i as

'~'

2o 022 RM-4196 - 57 ft 5.1 I at 30 n'?-RM-4197 - 23 ft F1 Iat 31 D22-RM-4198 - 57 *t F1 1 ee 32 Drvvel) Temn <ari i rMP 33 Suppression Pool Temp (*F) i 80 - __

RX. BLDG. ROOF VENT RAD MONITOR J4 Particulate (comi ra 45 Todine (epm) -c r 36 Noble Gas (com) ~J J 0 PEP-02.6.21 Fev. 16 Page 22 of 34 l e

' ir i

UNIT 0 PEP-02.6.21 Attachm:nt 5 Page 1 of 1 EXHIBIT 2.6.21-5 SAFETY PARAMETER DISPLAY SYSTEM (UNIT / )

Oeerable Inoperable Standby- Running Yes No Tsolated n - Not available Time O #Co i HPCI Flow (epm) I r AREA RAD MONITORS I mR/hr 2 Core Sorav A Flow (rpm)  ! r 3 RHR A Flow impm) 37 Rx. Blde. 20 f t Airlock A i r Rx. Bldg. 50.ft Sample 4 RCIC Flow (epm) I r 38 Station 5 Core Sprav B Flow (spm) 3 6 RHR B Flow (gpm)

I r 39 Rx. Blds. 50 ft Airlock 1 3

• =_ Rx. Bldg. North of Fuel 7 SLC Iniecting !u 40 Pool ~40 8 CRD Flow (gpm) i 40 9 APRM %

Between Fuel Pool and i e 41 Drwell o.m sc au 10 Reactor Pressure (psis) i c Turbine Bldg. Sample 11 Reactor Level (in) $ FL..e/.J 42 Station .T '

'I2 Main Stack Flow Rate (scim) i7foop 43 SJAE A (mR/hr) 2.

Turbine Aldg. Roof Vent '

4h SJAE B (mR /hr) s 13 Flow (sefm) / v sao Rx. Bldg. Ventilation 14 (sefs)

Rx. Bldg. Roof Vent Flow l

i O 45 Monitor (mR/hr) /

Service Water had Monito1' Rx. Bldg.' Negative Press 46 (cos) YO 15 (inchen n' water vacuum) <V 16 Supprem=4nn Pool Level (in) -zt nTyrR UNIT 17 nr *well Pressure (psie) i o Turbine M dg. Roof Vent IA SBGT Flow A (sefm) l 300o 47 Flow (sefm) / Y 00u 19 SBGT Flow B (sefm) i g o ro Turbine aldg. Roof 20 Drwell H, 4409 (:: cone.) e or LA Vent Monitor (uCf/=ee.) /. O 21 Drwell H,' 4410 (% cone.) O . o s-22 Drwell 0; 4409 (% cone.) le 23 Drwell 0; 4410 ( cone.) no, f 24 A0G System riov (sefm) r 25 Off-Site Power Available y Main Stack Gas Monitor l 26 (uci/see) l C;~O E Turbine Bldg. Vent Monitor

'7 (uC1/sec) /. O 6 DRWELL HIGH RAD MONITOR lR/hr 28 D22-RM-4195 - 30 ft El. I *s 24 n?2-pM-4196 - 57 ft c.1 i .t 30 n'?-Rw-4197 - 23 *t F1 i 4 i 31 D22-RM-4198 - 57 *t c'. f<l 32 Drvvell Temn ("ri i g9 3 3 Suppression Pool Temp ( *F) 6 70 RX. BLDG. ROOT VENT RAD MONITOR 36 pa rticul a t it (comi l , r. s 45 Todine (com) ' rf 36 Noble Gas (cpm) t~ s O PEP-02.6.21 Rev. 16 Page 22 of 34 l

UNIT 0 PEP-02.6.21 Attachtesnt 5 Page 1 of 1 EXHIBIT 2.6.21-5 SAFETY PARAMETER DISPLAY SYSTEM (UNIT f )

Oeerable Inoperable Standby Running Yes No Tsolated NA - Not available Time of/f' 1 HPCI Flow (Epm)  ! r AREA PAD MONITORS I mR/hr 2 Core Sprav A Flow (rem) --

R Rx. Blde. 20 f t Airlock i f 3 RHR A Flow (epm)  ;- Rx. Bldg. 50 ft Sample j 4 RCIC Flow (epm) e ; 38 Station i 2.

5 Core 9prav 8 Flow frem) r 39 Rx. Bldt. 50 ft Airlock ! 3 6 RHR B Flow (epm) *

r. Rx. Bldg. North of Fuel 7 SLC Iniecting 40 Pool 8 CRD Flow (apm)

? A/

/0 1 Jc Between Fuel Pool and 9 APRM % i e 41 Drwell Cbw.3 u /,

10 Reactor Pressure (este) i r. Turbine Bldg. Sample l

11 Reactor Level (in)  ; ac..J,ci 42' Station f' . f~

12 Main Stack Flow Pate ( s e f m) t 74 o o 0 43 SJAE A (mR/hr) i 1.

Turbine Bldg. Roof Vent 4. SJAF B (mR/hr) i l ,

13 Flow (sefm) I / v eco Rx. Bld g. Ventilation Rx. Bldg. Roof Vent flow 14 (sefm) l 45 Monitor (mR/hr) [

i C . Service Water Rad Monitog Rx. Bldg. Negative Press j 46 fees) I yo 15 (inchea n' unter vacuum) I,V 16 Supere==1ne pool Level ( in) ' t - 2.e OTurn t' NIT 17 vwell Pressure (esir) i c Turbine dg. Roof Vent IA FBGT Flow A ( se'M i F ooc, 47 riew (se e,) / Y eae 19 SBGT Flow B (sefm) 13 oro Turbine Eida. Roof l 20 Drwell H, 4409 ( ". cone.) 6 e_ or ". A L'ent Montier (uCf/=ec.T I /. O 21 Drwell HL 4410 (* cone.) I e o .3-22 Drvvell 0; 4409 ( '. conc.) I le 23 Drwell 0; 441n s" cone.) ! so, f 24 AOG Sysres riou (acfm) I r 25 Of f-Site Power Available i y Main Stack Gas Monitor 26 (uci/seci Turbine Bldg. Vent Monitor fOi: f' 77 (uCi/see) /, O f DRWELL HIGH RAD MONITOR iR/hr 28 D22-RM-4195 - 30 ft E1. I *s 20 972 cM-4196 - 57 ft c.1 . i .s 30 n'?-Rw-4197 - 23 *t F1 I ei 31 D 22-RM-4198 - 5 7 ft #1 I <l 32 Drvvell Temn '*ri i g9 3 3 Suppression Pool Temp (*F) i 70 NX. BLDG. ROOF VENT RAD l MONITOR I 34 Particulate (com) I ry 45 Todine Icpm) rr 36 Noble Gas (cpm) 55 n ?E'-n.s. Der. :

Hre >> of : '.

e

_.._._m__-__.__________ _ ___

UNIT 0 PEP-02.6.21 Attachm3nt 5 Page 1 of 1 EXHIBIT 2.6.21-5 SAFETY PARAMETER DISPLAY SYSTEM (UNIT / )

gerable Inoperable Standby Running Yes No Tsolated 3 - Not available Time _ 0 8 3 n 1 HPCI Flow (gem) i r AREA RAD MONITORS I mR/hr 2 Core Sprav A Flow frpm) i T 37 Rx. Blde. 20 ft Airlock i f 3 RHR A Flow (rpm) I r Rx. Bldg. 50 ft Sample 4 RCIC Flow (epm)  ; 33 Station /

8 5 Core Sprav B Flow Irpm>

6 RHR B Flow (gpm)

< r 39 Rx. Bldt. 50 ft Airlock i 2 i r. Rx. Bldg. North of fuel _

7 SLC Iniecting 40 Pool 8 CRD Flow (epm) i A/

3 t Ac Between Fuel Pool and 9 APRM % i e 41 Drwell 0,,ca 10 Reactor Pressure (esir) ,

e. Turbine Bldg. Sample j 11 Reactor Level (in)  : s . .J, ,

42 Station i . 5~

12 Main Stack Flow Pate (scrm) i7400s !.3 SJAE A (mRihri i 1.

Turbine Bldg. Roof Vent l 44 SJAE P (mR/hr) i ,

13 Flow (sefm) I / w eco Rx. Bldg. Ventilation Rx. Bldg. Roof Vent Flow 45 Monitor (mR/hr) /

14 (sefm) O Rx Bldg. Negative Press Service Water Rad Monito3

[ 46 (ces) I Yu 15 (inchen n' water vacuum) I,V 16 Supere==1on Dool Leve1 (in) i_ze nTur? UNIT 17 ne wwell Pressure (esia) - O Turbine 'da. Roof Vent 14 SBCT Flow A ( m e'M i?coe 47 Flow (se#1) /YN 19 SBGT Flow B (sefm) 8 3 ero Turbine ;1de. Roof l

20 Drwell H, 4409 ( ': cone.) i e or A Vent Monitor (uCi 'cee .i I

/.R 21 Drwell Hi 4410 ( *. cone.) 1 0 or 22 Drvvell 0; 4409 (t cone.) i ao 23 Devvell 0; 44tn (* cone.) i so, f 24 AOG SysreA rinu 8sefm) ir 25 Of f-Site Power Available i y Main Stack Gas Monitor l 26 (uCi/see) If OGT' Turbine Bldg. Vent Monitor 77 (uct/see) lI / OE DRWELL HIGH RAD MONITOR iRihr 28 D22-RM-4195 - 30 ft El. t as 24 0?2 DM-4196 - 57 ft r1 l as 30 n99.Rw-4197 - 23 't r1 i 4 1 31 D22-RM-4198 - 57 Fe C1 6<s 32 Drvwell Temn <=r) i g, 33 Suppression Pool Temp (*F) t 70 RX. BLDG. ROOF VENT RAD l MONITOR I 34 Particulate (cemi i r.s 45 Tortine (epm) Tf 36 Noble Gas (epm) CJ 0 PEP-02.6.21 Fev. 16 Page 22 of 34 '

l

UNIT 0 PEP-02.6.21 Attachmsnt 5 Page 1 of 1 EXHIBIT 2.6.21-5 SAFETY PARAMETER DISPLAY SYSTEM (UNIT / )

Operable Inoperable Standby Running Yes No isolated

_N_A - Not available Time G) 8 Yi-1 WPCI Flov (spm) l I' AREA RAD MONITORS i mR/hr

? Core Sprav A Flev (epm) i T 37 Ex. Blde. 20 ft Airlock i 5-3 RHR A Flow (2pm) i ;- Rx. Bldg. 50 ft Sample 4 RCIC Flow (com)

~

1 38 Station /

5 Core Sprav B Flow (cpm) 4 - 49 Rx. Bldc. 50 ft Airlock i /

6 RHR B Flow (com) * :. Rx. Bldg. North of Fuel 7 SLC Iniecting t A/ 40 Pool /

8 CRD Flow (cpm) i A- Between Fuel Pool and j 9 APRM "% i e, il Drvwell I Do w . r c. e 10 Reactor Pressure (psic) 6 e. Turbine Bldg. Sample

. 6' 11 Reactor Level (in) pt , /, ,f 42 Station 12 Main Stack Flow Pate (sefm) '74oop 43 SJAE A tmR/hr) 1 2 Turbine Bldg. Root Vent W SJAF B (mR/hr) I /

l 13 Flow (sefm) I / 4 poo Rx. Bldg. Ventilation Rx. Bldg. Roof Vent Flow l 45' Monitor (mR/hr) /

14 (sefm) I C Service Water Rad Monitot Rx. Bldg. Negative Press 46 (ces) t'a 15 (inchen n' water vacuum) , Y .

16 Suppression Pool Level (in) 42.9 OTurR UNIT 17 nt"vell Pressure (esic) C Turbine 'de. Roof Vent IR SBCT Flow A (sefmi i?cce i? riew (sc im) / k doo 19 SBGT Flow B (sefm) i] eco Turbine 4'da. Rocf 20 Drvvell H, 4409 ( *. cone.) I e_05 LQ Uent Men: tor (vri'aec.' /. O 21 Drvwell H; 4410 (" conc.) i 0 er 22 Drvvell 0; 4409 (* conc.) I ao 23 Drvuell 0; 4410 (* cone.) 1 2 o .r 24 AOC Systes riov 'sefm)  ! ;r 25 Of f-Site Power Available i v Main Stack Gas Monitor 26 (uC1/sec) J'() ; I' Turbine Bldg. Vent Monitor 77 (uC1/sec) /, o r # O DRYWELL HICH RAD MONITOR i R/hr 28 D22-RM-4195 - 30 ft El. ' .i i

24 D?? DM-4196 - 57 ft F.1  ! 4s 30 n'?.RM-4197 - 23 ft F1 i <i 31 D22-RM-4198 - 57 ft r' , i <t 32 Drvve11 Temn '*ri I 49 33 Suppression Pool Temp ('F) f FC RX. BLDG. ROOF VENT RAD MONITOR 34 Particulate (com$ i :: s 45 Todine (com) t -rf 36 Noble Gas (cpm) I CJ Page 22 of 34 0 PEP-02.6.21 Fev. 16

UNIT 0 PEP-02.6.21 Attachrent 5 Page 1 of I EXHIBIT 2.6.2'*5 SAFETY' PARAMETER DISPLAY SYSTEM (UNIT / )

Standby Running Yes ~ No Tsolated Ogerable Inoperable NA - Not available Time _j0foo AREA RAD MONITORS ,[,, mR/hr 1 HPCI Flow (gpm) I' 37 Rx. Bldg. 20 ft Airlocq ,

. f-2 Core Sprav A Flow (epm) r 3 RHR A Flow (spm) I

- Rx. Bldg. 50 ft Sample 4 RCIC Flow (spm) t : 3B Statien l /

5 Core Sprav B Flow (2pm) 6 z 39 Rx. Bldc. 50 ft Airlock l /

6 RHR B Flow (epm) i 2:. Rx. Bldg. Northoffuel]

i e/ 40 Fool /

7 SLC Iniecting 8 CRD Flow (gpm) !4- Between Fuel Pool and T i e al Drvwell i Cow.j c. e 9 APRM %

10 Resctor Pressure (psic) i r_.

Turbine Bldg.. Sample S~

11 Reactor Level (in)  ! pt ,,,/,,/ 42 Station ,.

12 Main Stack Flow Pate (sefm) !7gopp 43 SJAE A (mR/hr) t 2 Turbine Bldg. Roof Vent

.- SJAF .R (mRihr) I /

/ 4 aoo Rx. Bldg. Ventilation 13 Flow (sefm)

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

14 (sefm) C Service Water Kad Monicot Rx. Bldg. Negative Press 46 (cos) t'o 15 (inches n' water vacuum) , V .

AT"rt UNIT 16 Supprescinn pool Level (in) ! -se 17 nr *well Pressure (psig) O Turbine 'da. Roof Vent

/

17 Flow (sc #m) doo IR SBGT Flow A (sefmi I300e ijoro Turbine Ridg. Roof 19 SBGT Flow B (sefm) 20 Drvwell H, 4409 (" cone.) ! o_ of LA Vent Mon: tor (urt/eec.T f . c>

21 Drvvell HL 4410 (% conc.) i0.09 22 Drvvell 0; 4409 (*. cone.) f so 23 Drvwell 0; 4410 (' cone.) i 2.o , f~ .

24 A0G System riou (sefm) i ;r y

25 Of f-Site Power Available '

Main Stack Gas Monitor '

26 (uci/sec) J7d /r f '

Turbine Bldg. Vent Monitor '

77 (uCi/sec) /, 0 # #

DRYWELL HIGH RAD MONITOR iR/hr 28 D22-RM-4195 - 30 ft El. i *s 24 D22 DM-4196 - 57 ft 5.1 l .i Jn n'?-RM-4197 - 23 f t F1  ! 4 /

31 D22-RM-4198 57 't r'. I

44 SJAE B (mR/hr) ) /

Turbine Bldg. Roof Vent

/ V ega Rx. Bldg. Ventilation 13 Flow (sefm) 45 'Monicer (mR/hr) /

Rx. Bldg. Roof Vent Flow C . Service Water Rad Monitor' 14 (sefm) 46 (eps) I t'O Rx. Bldg. Negative Press 15 (inches n' water vacuum) , Y .

n7prR (NIT 16 Suppression Pool Level (in) 1 - 2.9 'dg. Roof Vent

O Turbine 17 nr uwell Pressure (os12)  ?? r]ow (sc i ,) / k d oo 18 SBCT Flow A (aefmi i3coe '

19 SBGT Flow B (sefm) 13 e ro ' Turbine Ride. Roof

(" cone.) i e c5 54 Vent Monttor (UCf'aec.i /. O 20 Drvvell H, 4409 21 Drvwell H; 4410 (" cone.) 10 or 22 Drvvell 0; 4409 (% cone.) 1 3.o

( cone.) so f 23 Drvwell 24 A0G System rinw (sefm) 044410 ;r 25 Off-Site Power Available v Main Stack Gas Monitor 26 (uCi/sec) f6E f' Tvrhine Bldg. Vent Monitor #

27 (uci/sec) /rC#P

R/hr DRYWELL HIGH RAD MONITOR 2B D22-RM-4195 - 30 ft El. i *i 24 n22 oM-4196 - 5 7 ft e. t . I t 4 ;

4 I 30 n??-RM-4197 - 23 ft F1

't F'. I < 1 31 D22-RM-4198 - 5 7 32 Drvvell Temn ("Fi i V9 33 Suppression Pool Temp ( *F) t 70 RX. BLDG. ROOF VENT RAD MONITOR 2' S 34 Particulate (com' 45 f odine (epm) .. 375 36 Noble Gas (epm) { $5 l

Page 22 of 34 0 PEP-02.6.21 Fev. 16

) '

UNIT 0 PEP-02.6.21 Attachm3nt 5 L Page 1 of 1 l'

EXHIBIT 2.6.21-5 SAFETY PARAMETER DISPLAY SYSTEM (UNIT / )

No Tsolated Ogerable Inoperable Standby Running Yes Time d)9 76)

NA - Not available AREA RAD MONITORS mR/hr-1 HPCI Flow (gpm) I 27 2 Core Sprav A Flov (2pm) *-

37 Rx. Blde. 20 ft Airlock . f-Rx. Bldg. 50 ft Sample 3 RHR A Flow (epm)  :-

/

4 RCIC Flow (epm) i 38 Station-5 Core Sprav B Flow (Epm) # :. 19 Rx. Bldc. 50 ft Airlock i- /

6 RHR B Flow (cpm) ' r.. Ex. Bldg.. North of Fuel i A/ ;0 Fool /

7 SLC Iniecting 8 CRD Flow (apm) 3 #7 Between Fuel Fool and 9 APRM % i e 41 Drvwell Do . f c , 5 Turbine Bldg. Sample 10 Reactor Pressure (psic) I r. l l . 5~

11 Reactor Level (in)  : pz ,./ ,/ 02 Station 12 Main Stack Flow Pate (scfm) ; 74 o o p_ 4J SJAE A (mR/hr) >

Turbine Bldg. Roof Vent

'. SJAF F (mR/hr) i /

l i / V aco - Rx. S1dg. Ventila tion 13 Flow (sefm) 45' Monitor (mR/hr) /

Rx. Bldg. Roof Vent Flow C Service Water Rad Monitor 14-(sefm) 46 (eps) t'O Rx. Bldg.-Negative Press 15 (inches n' water vacuum) .Y .

n?"rR LNIT

'16 Supprem=1on Pool Level fin) 1 -se O Turbine 'dz. Roof Vent 17 nr uwell Pressure (esic)  ?? Flew (sc im) / k' # 00 IA SBCT Flow A (scfmi i3Coe ij cro Turbine 'de. Roof 19 SBGT Flow B (sefm) '8 "ent Moe : tor f uC ' '=ec . ' / , CP 20 Drvwell H, 4409 (% cone.) I o or 21 Drvwell H; 4410 ( *. cone.) 10 09 22 Drvwell 0; 4409 (% cone.) I ao 23 Drvwell 0; 4410 (" cone.) 12 o f 24 AOG System riou (sefm) I r-i y 25 Off-Site Power Available '

Main Stack Gas Monitor 26 (ucilsec) STO F '

Turbine Bldg. Vent Monitor

'7 (uCi/sec) /< C #' #

R/hr DRYW7.LL HIGH RAD MONITOR 28 D22-RM-4195 - 30 ft El. i *i 24 022 DM-4196 - 57 ft E1, i et t 4 ;

30 n9?-RM-4197 - 23 ft F1 i < 1 31 D 22-RM-4198 - 5 7 ft c' .

32 Drvwell Temn ("ri e v9 33 Suppression Pool Temp (*F1 I FO RX. BLDG. ROOF VENT RAD MONITOR i :: f 34 Darriculate (comi 45 ro dine (epm) i :f 36 Noble Gas (cpm) i 55 Page 22 of 34 0 PEP-02.6.21 Rev. 16

- - _ - _ - _ - - _ _ _ _ _ _ - ' ' - ' ~ - - - - - - - . , _ , _ _ _ , _ , _

UNIT 0 PEP-02.6.21 ,

Attachment 5 Page 1 of 1 EXHIBIT 2.6.21-5 SAFETY PARAMETER DISPLAY SYSTEM (UNIT 3- )

s Ogerable Inoperable Standby Running Yes No Tsolated Nh g - Not available Time O 3 Y S~

l HPCI Flow (gpm) l 5 AREA RAD MONITORS mR/hr 2 Core Sprav A Flow (epm) s 37 Rx. Blde. 20 f t Airlock . S-3 RHR A Flow (apm) 1; Rx. Bldg. 50 ft Sample j 4 RCIC Flow (epm) i s 38 Station /

5 Core"Sprav B Flow (epm) I f 39 Rx. Blde. 50 ft Airlock i r 6 RHR B Flow (gpm) t S Bx. Bldg. North of Fuel 7 SLC Iniecting { A/ 40 Pool /

8 CRD Flow (gpm) I to Between Fuel Pool and l 9 APRM % i no 41 Drvwell l% c e, /

10 Reactor Pressure (psir) 6 / oo o Turbine Bldg. Sample l 11 Reactor Level (in) l /s 7 42 Station  ! < S' 12 Main Stack Flow Rate (sefm) Irg oco 43 SJAE A (mR/hr) t fev Turbine Bldg. Roof Vent 44 SJAE B (mR/hr) /co 13 Flow (sefm) /y oou Rx. Bldg. Ventilation Rx. Bldg. Roof Vent Flow '

45 Monitor (mR/hr) , 3 14 (scfm) 396 00 0 Service Water Rad Monitor Rx. Bldg. Negative Press '

46-(cps) V#

15 (inchen or water vacuum) 3 16 Suppren=1on Pool Level (in) 1 -30 OTHFR UNIT 17 nr rwell Pressure (psfr) i ,2 Turbine B'dg. Roof Vent IR SBGT Flow A (sefmi f 47 Flow (sefm) / Y CO O 19 SBGT Flow B (sefm) S Turbine Bldg. Roof '

20 Drvwell H, 4409 (% conc.) I, o r- 4R Vent Monitor (uCfleec.) /, O 21 Drvwell H; 4410 (% cone.) I , o f' 22 Drvve11 0; 4409 (% conc.) If.S 23 Drvwell 0; 4410 (Y cone.) I p. P 24 AOG System Flow (sef m) lto 25 Off-Site Power Available i te

/

Main Stack Gas Monitor 26 (uCilsec) 3 . T'n d Turbine Bldg. Vent Monitor l

77 (uCi/sec) /, o E "#

DRYWELL HIGH RAD MONITOR 'R/hr 28 D22-RM-4195 - 30 ft El. 1 2o D22 RM-4196 - 57 ft F.1 ST 30 n97.RM-4197 - 23 ft F1 7 31 D22-RM-4198 - 57 ft F1 6 ro 32 Drvwell Temn (*ri i f/r 33 Suppression Pool Temp (*F) i y3-RX. BLDG. ROOF VENT RAD MONITOR 34 Particulate (com) /00o M Todine (cpm) 9,90 36 Noble Gas (cpm) l Sou 0 PEP-02.6.21 Fev. 16 Page 22 of 34 l

l' l'

UNIT 0 PEP-02.6.21 Attcchrant 5 l= Page 1 of 1

EXHIBIT 2.6.21-5 SATETY PARAMETER DISPLAY SYSTEM (UNIT L)

Ogerable I,noperable Standby Running Yes No Tsolated A

,N,A,- Not available Time 0900 1 HPCI Flow (epm) r _

AREA RAD MONITORS mR/hr

? Core Sprav A Flow (epm) f 37 Rx. Blde. 20 f t Airlock , g-3 RHR A Flow (epm) J- Rx. Bldg. 50 ft Sample 4 RCIC Flow (epm) i r 38 Station /

5 Core Sprav B Flow fepm) 1 5 39 Rx. Blde. 50 ft Airlock i /

. 6 RHR B Flow (gpm) I s Rx. Bldg. North of Fuel 7 SLC Iniecting i x/ 40 Pool /

8 CRD Flow ( epm) I to Between Fuel Pool and 9 APRM % iqv 41 Drvwell r>m e c, /s 10 Reactor Pressure (psie) i acco Turbine Bldg. Sample

, 11 Reactor Level (in)  !/r7 42 Station , 3~~

l 12 Main Stack Flow Pate (sefm) I S roao 43 SJAE A (mR/hr) I foe

. Turbine Bldg. Roof Vent 44 SJAE B (mR /hr) ,co l 13 Flow (sefm) /y (a v Rx. Bldg. Ventilation Rx. Bldg. Roof Vent Flow 45 Monitor (mR/hr) .3 14 (sefm) rv coo Service Water Rad Monitor Rx. Bldg. Negative Press 46 (eps) 40 15 (inches n' water vacuum) ,7 16 Suppression Pool Level (in) 1 -3u OTFFR UNIT 17 nr arwell Pressure (oste) i 2 Turbine M dg. Roof Vent l 1R SBGT Flow A (sefni i c 47 Flow (sefm) /yecs 19 SBGT Flow B (sefm) I f Turbine Bldg. Roof 20 Drvwell H, 4409 (% cone.) I.or 4R Vent Monitor (uC1/=ee.1 /. o 21 Drvwell H; 4410 (* cone.) I , a g-22 Drvwell 0; 4409 (% cone.) ,, 9 23 Drvwell 0; 441n (' cone.) i, y 24 AOG System Flow (sefm) go 25 Off-Site Power Available ,.

Main Stack Gas Monitor /

26 (uCi/sec) 2 . TE #

Turbine Bldg. Vent Monitor 77 (uCi/sec) /. 0a ' #

DRYVELL HIGH RAD MONITOR R/hr 28 D22-RM-4195 - 30 ft El. I J

'24 0 2 2 RM-4196 - 5 7 f t F.1 . Icr 30 n'?-RM-419 7 - 23 ft F1 I 7 31 D22-RM-4198 - 57 ft F1, t< o 32 Drvwell Temn <*ri i / / J' 33 Suppression Pool Temp (*F) i p f-RX. BLDG. ROOF VENT RAD MONITOR 34 Particulate (comi toog 35 Todine (cpm) 3 ca 36 Noble Gas (cpm)  ! 300 0 PEP-02.6.21 Fev. 16 Page 22 of 34 l l

)

4

_ _ _ - _ _ - - - _ - . _ _ - - _ _ _ - _ _ - _ . - - _ _ _ . . _ _ . - - - - _ _ 1

UNIT 0 PEP-02.6.21 Attachm2nt 5 Page 1 of 1 EXHIBIT 2.6.21-5 SAFETY PARAMETER DISPLAY SYSTEM (UNIT 3_J

'gerable Inoperable Standby Running Yes No Tsolated NJ - Not available Time CY/f' 1 HPCI Flow (epm) ( AREA RAD MONITORS mR/hr 2 Core Sprav A Flow (epm) c 37 Rx. Blde. 20 ft Airlock ,r 3 RHR A Flow (epm) 0 Rx. Bldg. 50 ft Sample 4 RCIC Flow (gym) c 38 Station /

5 Core .4prav B Flow fepm) I j 39 Rx. Blde. 50 ft Airlock i f 6 RHR B Flow (gpm) iJ Rx. Bldg. North of Fuel 7 SLC In4ecting  ? 4/ 40 Pool /

8 CRD Flow (gpm) I to Between Fuel Pool and 9 APRM % 140 41 Drvwell Oom u la-10 Reactor Pressure (psie) i f oo o Turbine Bldg. Sample 11 Reactor Level (in)  ! /8 7 42 Station ,r 12 Main Stack Flow Pate (sefm) t re e co 43 SJAE A (mR/hr) /vo Turbine Bldg. Roof Vent "

44 SJAE B (mR / hr) /co 13 Flow (scfm) / y cou Rx. Bldg. Ventilation Rx. Bldg. Roof Vent Flow 45 Monftor (mR/hr) ,3 14 (scfm) f6 000 Service Water Rad Monitor Rx. Bldg. Negative Press '

46 (eps) Yo 15 (inchen n' water vacuum) ,7 16 Suppre==1nn pool Level (in) l_Jo OTyrR UNIT 17 nr *well Pressure (psie) I ,n Turbine rida. Roof Vent IR SBGT Flow A (sefmi  ! 3 /.7 Flow (sefm) /'/ coo 19 SBGT Flow B (sefm) 1 5 Turbine Bldg. Roof 20 Drvvell H, 4409 (% cone.) ! ,or 4R Vent Monitor (uci /=ce.) /. O 21 Drvvell H; 4410 (% cone.) !,or 22 Drvvell 0; 4409 (% cone.) If 9 23 Drvwell 0; 4410 (' cone.) f. y 24 AOG System Flow (sefm) cc 25 Of f-Site Power Available p Main Stack Gas Monitor T!

26 (uCilsec) 1,c p Turbine Bldg. Vent Monitor

'7 (udi/sec) /. o a r#

DRYWELL HIGH RAD MONITOR 'R/hr 28 D22-RM-4195 - 30 ft El. 3 24 022 uM-4196 - 57 f t 5.1 r5-30 n99.Rw-4197 - 23 ft F1 !7 31 D 22-RM-419 8 - 5 7 ' t F1 iro 32 Drvvell Temn ("Fi i //r 33 Suppression Pool Temp (*F) Ipr RX. BLDG. ROOF VENT RAD MONITOR 34 Particulate (comi /eco M Todine (cpm) .$70 36 Noble Gas (cpm) 3eo O PEP-02.6.21 Rev. 16 Page 22 of 34 l

UNIT 0 PEP-02.6.21 Attachrcnt 5 Pass 1 of 1 EXHIBIT 2.6.21-5 SAFETY PARAMETER DISPl.AY SYSTEM (UNIT 'L )

Ogerable Inoperable Standby Running Yes No Tsolated NJ - Not available Time C WO 1 HPCI Flow (epm) ( AREA RAD MONITORS mR/hr 2 Core Sprav A Flow (epm) s 37 Rx. Blde. 20 ft Airlock t-3 RHR A Flow (apm)  :- Rx Bldg. 50 ft Sample 4 RCIC Flow (gpm) i f 38 Station /

5 Core Sprav B Flow fepm) i 3 39 Rx. Blde. 50 ft Airlock i /

6 RHR B Flow (gpm) 6 5 Rx. Bldg. North of Fuel l 3 7 SLC Iniecting  ! /t/ 40 Pool I / {

8 CRD Flow (gpm) I 6a Between Fuel Pool and 9 APRM % i 70 41 Drwell Douc u(e 10 Reactor Pressure (psie) Iffs Turbine Bldg. Sample-

.I1 Reactor Level (in) I f y7 42 Station , S~

12 Main Stack Flow Pate (sefm) #4 y eco 43 SJAE A (mR/hr) ' yo Turbine Bldg. Roof Vent '

44 SJAE B (mR / hr) 6c o 13 Flow (sefm) /v 000 Rx. Bldg. Ventilation Rx. Bldg. Roof Vent Flow 45 Monitor (mR/hr) <?

14 (sefm) f6,00 0 Service Water Rad Monito1' Rx. Bldg. Negative Press 46 (eps) 6/o 15 (inchen nr water vacuum) ,7 16 Suppremmion Dool Level (in) I _ p e, OTFrR UNIT /s99iPc 17 nr vwell Pressure (psie) I . 2. Turbine -dg. Roof Vent IR SBGT Flow A (sefM i ( 47 Flow (sefm) /'/' 00 0 19 SBGT Flow B (sefm) i 5 Turbine Bldg. Roof '

20 Drwell H, 4409 (% cone.) I,or 4R Vent Monitor (uCfIcee.1 /, o 21 Drwell H, 4410 (% cone.) i o f' 22 Drwell 0; 4409 (% cone.) I f , cf 23 Drwell 0; 4410 (9 cone.) f , te 24 AOG System riov (sefm) 70 25 Off-Site Power Available se Main Stack Gas Monitor i /

26 (uCi/see) i t . ne= r/

Turbine Bldg. Vent Monitor 77 (uCi/sec) 1, 0 G '

DRYWELL HIGH RAD MONITOR R/hr 28 D22-RM-4195 - 30 ft El. I 1 20 n 2 2 DM-4196 - 57 f e F.1. i fu 30 n n-Rw-4197 - 23 ft F1 l r

31 D22-RM-4198 - 57 ft F1 i fa 32 Drywell Tenn f*r) I //t 33 Suppression Pool Temp (*F) i P S-RX. BLDG. ROOF VENT RAD MONITOR 34 Particulate (com) i ta00 45 f ortine (com) <oc 36 Noble Gas (cpm) ygo O PEP-02.6.21 Rev. 16 Page 22 of 34 l

- _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ . _ _ _ - . _ _ _ _ _______.._.________.____m___

1-UNIT 0 PEP-02.6.21 Attachmnt 5 Page 1 of 1 EXHIBIT 2.6.21-5 SAFETY PARAMETER DISPI.AY SYSTEM (UNIT .L )

gerable Inoperable Standby Running Yes No Tsolated 3 - Not available Time 0 9v/-

1 HPCI Flow (epm) l < AREA RAD MONITORS '

mR/hr 2 Core Sprav A Flow (epm) i , 37 Rx. Blde. 20 f t Airlock , r-3 RHR A Flow (epm) ir Rx. Bldg. 50 ft Sample 4 RCIC Flow (gpm) i J 38 Station f 5 Core Sprav B Flow (epm) 1 5 39 Rx. Blde. 50 ft Airlock I i 6 RHR B Flow (gpm) i 5 Rx. Bldg. North of Fuel 7 SLC Iniecting  ! /v 40 Pool /

8 CRD Flow (gpm) i4o Between Fuel Fool and j 9 APRM % i 70 41 Drwell i n,v,, s e,/a.

10 Reactor Pressure (psie) I 990 Turbine Bldg. Sample 11 Reactor Level (in)  ! /#7 42 Station _

,r 12 Main Stack Flow Rate (sefm) i 6 y eco 43 SJAE A (mR/hr) i yo Turbine Bldg. Roof Vent 44 SJAE B (mR/hr) to 13 Flow (sefm) /9. coo Rx. Bldg. Ventilation Rx. Bldg. Roof Vent Flov 45 Monitor (mR/hr) .3 14 (sefm) rs on e Service Water Rad Monitor Rx. Bldg. Negative Press 46 (eps) 90 15'(inchen nr water vacuum) ,7 16 Suppre==1on Pool Level (in) 1-Jo OTFFR UNIT 17 nr vvell Pressure (psie) I ,2 Turbine 5'da. Roof Vent IR SBGT Flow A (sc+m) l- _T 47 T1ov (sefm) /y evo 19 SBGT Flow B (sefm) I 5 Turbine Bldg. Roof 20 Drvvell H, 4409 (I cone.) !,oy 4R Vent Monitor (uCi /=ec.) /o 21 Drwell H; 4410 (* cone.) } , o5-22 Drwell 0; 4409 (I cone.) i f, y 23 Drvvell 0: 441n (' cone.) /.9 24 AOC Systes Flow (sefm) w 25 Off-Site Power Available '

v Main Stack Gas Monitor 26 (uci/see) 1g?

Turbine Bldg. Vent Monitor 27 (uCi/sec) /,0 p ro DRWELL HIGH RAD MONITOR IR/hr -

28 D22-RM-4195 - 30 fe El. I 1 20 D22 eM-4196 - 57 ft F.1 Iro in n n-RM-4197 - 23 ft F1 Ir 31 D22-RM-4198 - 57 't F1 15- o 32 Drvvell Temn (*r) I ri a.

33 Suppression Pool Temp (*F) I w RX. BLDG. ROOF VENT RAD MONITOR 34 Particulate (comi tooo M Todine (cpm) I .ra v 36 Noble Gas (cpm) l Joo

~

O PEP-02.6.21 Fev. 16 Page 22 of 34 l

UNIT 0 PEP-02.6.21 Attachment 5 Page 1 of 1 EXHIBIT 2.6.21-5 SAFETY PARAMETER DISPLAY SYSTEM (UNIT 'l )

.Ogerable Inoperable Standby Running Yes No Tsolated

_NA - Not available Time Oroo 1 HPCI Flow (epm) l 5 AREA RAD MONITORS I mR/hr 2 Core Sprav A Flow (epm) i 5 37 Rx. Blde. 20 ft lirlock I . 5-3 RHR A Flow (epm) l -r Rx. Bldg. 50 ft Sample 4 RCIC Flow (gpm) i 5 38 Station /

5 Core Sprav B Flow (epm) 15 39 Rx. Blde. 50 ft Airlock I /

6 kHR B Flow (epm) I f Rx. Bldg. North of fuel 7 SLC Iniecting i A/ 40 Pool /

8 CRD Flow ( gpm) I do Between Fuel Pool and 9 APRM % i 70 41 Drwell D o- w at 10 Reactor Pressure (psie) If90 Turbine Bldg. Sample 11 Reactor Level (in) i/y7 42 Station . P-12 Main Stack Flow Pate (scfm) 159eou 43 SJAE A (mR/hr) i Po Turbine Bldg. Roof Vent 44 SJAE B (mR/hr) t Fo 13 Flow (sefm) /4,000 Rx. Bldg. Ventilation Rx. Bldg. Roof Vent Flow 45 Monitor (mR/hr) ,T 14 (sefm) f4 cao Service Water Rad Monitor Rx. Bldg. Negative Press '

46 (cos) Yo 15 (inches n' water vacuum) ,7 16 Superem=1on Pool Level (in) l-30 OTFFR UNIT 17 nr vvell Pressure (esia) I 2 Turbine F'dg. Roof Vent IR SBGT Flow A (sefm) I 5 47 Flow (scfm) /9 000 19 SBGT Flow B (sefm) i 5 Turbine Bldg. Roof 20 Drwell H, 4409 (% cone.) i , of- 4R Vent Monitor (uC1/ cec.T /. O 71 Drwell H; 4410 (% conc.) 1 05-22 Drwell 0; 4409 (% conc.) i /, 9 23 Drwell 0: 44Ln (9 cone.) i f, y 24 A0G System riow (sefm) I ro 25 Off-Site Power Available I y Main Stack Gas Monitor #

26 (uCi/sec) 1, d Turbine Bldg. Vent Monitor F"

77 (uCi/sec) /. d E DRYWELL HIGH RAD MONITOR iR/hr 28 D22-RM-4195 - 30 fe El. I 1 24 022 FM-4196 - 57 ft F.1 . I fv 30 n n-RM-4197 - 23 +t F1 I r 31 D22-RM-4198 - 57

• t F1 I fo )

32 Drvvell Temn ('ri e //t 33 Suppression Pool Temp (*F) I yr RX. BLDG. ROOF VENT RAD MONITOR 36 Particulate (comi I/000 35 Todine (cpm) I too 36 Noble Gas (com) 1Joo O PEP-02.6.21 Rev. 16 Page 22.of 34 l

l UNIT 0 PEP-02.6.21 Attach: ant 5 Page 1 of 1 EXHIBIT 2.6.21-5 SAFETY PARAMETER DISPLAY SYSTEM (UNIT A)

Ogerable Inoperable Standby Running Yes No Tsolated l NA - Not available Time 03~/5' 1 HPCI Flow (epm) $ AREA RAD MONITORS 4 mR/hr 2 Core Sprav A Flow (epm) '

S 37 Rx. Blde. 20 ft Airlock i

, f-3 RHR A Flow (epm) ac Rx. Bldg. 50 ft Sample 4 RCIC Flow (gpm) i 5 38 Station /

5 Core Sprav B Flow repmp i 5 35 Rx. Blde. 50 ft Airlock i /

6 RHR B Flow (gpm) e i Bx. Bldg. Sorth of Fuel

~7'SLC Iniecting i ev 40 Fool /

l 8 CRD Flow (gpm) I to Between Fuel Fool and 9 APRM % i vo 41 Drvwell oc usow, (A 10 Reactor Pressure (psie) 6990 Turbine Bldg. Sample 11 Reactor Level (in) I /P 7 42 Station , f' 12 Main Stack Flow Pate (setm) 17oooo 43 SJAE A (mR/hr) i ro Turbine Bldg. Roof Vent 44 SJAE B (mR/hr) ro 13 Flow (sefm) / y coo Rx. Bldg. Ventilation Rx. Bldg. Roof Vent Flow l 45 Monitor (mR/hr) ,7 14 (sefm) Ir4 cao Service Water Rad Moni;oi Rx. Bldg. Negative Press / 46 (eps) I#

15 (inchem n' unter vacuum) .?

16 Supprem=1on Pool Level fin) -po OTFFR UNIT 17 nr *well Pressure (psic) i 1 Turbine M dg. Roof Vent

! 1R SBGT Flow A (sc*mi i 5 47 Flow (sefm) /7000 19 SBGT Flow B (sefm) i 5 Turbine Bldg. Roof 20 Drvuell H, 4409 (% conc.) i ,or 4R Vent Monitor (uC1/=ee.1 /.0 21 Drvwell H; 4410 (I conc.) I , of' 22 Drvwell 0; 4409 (I cone.) If.,

23 Drvvell 0; 4410 (' cone.) s.f 24 A0G System Flow (sefm) 7c 25 Off-Site Power Available y Main Stack Gas Monitor 26 (uci/see) 5os'r Turbine Bldg. Vent Monitor 77 (uCi/see) /Op r#

DRYVELL HIGH RAD MONITOR IR/hr 28 D22-RM-4195 - 30 ft El. x 24 022-FM-4196 - 57 ft u.1 . i fa 30 n'7-RM-4197 - 23 't F1 i r-31 D22-RM-4198 - 57 ft c1 iS, 32 Drvwell Temo ("F4 i / /1 33 Suppression Pool Temp (*F) i 45-l RX. BLDG. ROOF VENT RAD MONITOR 34 Particulate (ceb$ 6/eca 45 fodine (epm) i .rp e 36 Noble Gas (cpm) I Jos O PEP-02.6.21 Fev. 16 Page 22 of 34 l L

l l.

l

UNIT O PEP-02.6.21 Attachment 5 Page 1 of 1 EXHIBIT 2.6.2'-5 SAFETY PARAMETER DISPLAY SYSTEM (UNIT L) 02 erable inoperable Standby Running Yes No Tsolated 3 - Not available Time Offo 1 HPCI Flow (rpm) i 5 AREA RAD MONITORS I mR/hr 2 Core Sprav A Flow (rpm) I _c 37 Rx. Blde. 20 ft Airlock i , 5-3 RHR A Flow (apm) I r Rx. Bldg. 50 ft Sample a RCIC Flow (epm) i r 38 Statien /

5 Core Sprav B Flow (epm) 6 e 39 Rx. Blde. 50 ft Airlock i f 6 RHR B Flow (gpm) i r Rx. Bldg. North of Fuel l 7 SLC Iniecting i Af 40 Pool  !/

8 CRD Flow ( gpm) i 60 Between Fuel Pool and 9 APRM % i ro 41 Drwell Douan,4 10 Reactor Pressure (ps12) I150 Turbine Bldg. Sample 11 Reactor Level (in) I sp7 42 Station , 5~

12 Main Stack Flow Pate (sefm) t 7o c o 43 SJAE A (mR/hr) I ro Turbine Bldg. Roof Vent 44 SJAE B (mR/hr) Go 13 Flow (sefm) /Y000 Rx. Bldg. Ventilation Rx. Bldg. Roof Vent Flow ,45 Monitor (mR/hr) .7 14 (sefm) M 000 Rx. Bldg. Negative Press '

Service 46 (eps) Water Rad Monitoi[

I '/O 15 (inches n' water vacuum) ,7 16 3uppre==1on Pool Level (in) 1 -fo OTFFR LWIT 17 nr vvell Pressure (psic) I ,1 Turbine F'dg. Roof Vent IR SBGT Flow A (sc+mi i s 47 Flow (sefm) /Y 000 19 SBGT Flow B (sefm) 1 5 Turbine Bldg. Roof l 20 Drvvell H, 4409 (% conc.) I,or 4R Vent Monitor (uCfIcec.) I/o 21 Drwell H; 4410 (I conc.) i _ of-22 Drwell 0; 4409 (% conc.) Ife 23 Drwell 0; 441n (" cone.) I p, 9 24 AOC Systes Flow (sefm) i7o l 25 Off-Site Power Available I v Main Stack Gas Monitor l 26 (uci/sec) l R ov7 '

i l Turbine Blde. Vent Monitor l

77 (uCi/sec) /,Op r#

DRWT.LL HIGH RAD MONITOR IR/hr 28 D22-RM-4195 - 30 ft El. i 2 24 0 2 2 DM-4196 - 5 7 f t F.1 . i .ro jn n'?-Rv-4197 - 23 't F1 I c-31 D22-RM-4198 - 57 ft Fi. I ca 32 Drvwell Temn far) efft 33 Suppression Pool Temp (*F) I pr RX. BLDG. ROOF VENT RAD MONITOR 34 Da rt icul a,t e (com4 i fee p M iodine (epm) I ,cco 36 Noble Gas (com) i Jos O PEP-02.6.21 Fev. 16 Page 22 of 34 l a

UNIT 0 PEP-02.6.21 Attachment 5 Paae 1 of 1 I EXHIBIT 2.6.21-5 SAFETY PARAMETER DISPLAY SYSTEM (UNIT 1)

Ogerable I,noperable Standby Running Yes No Tsolated I Q - Not availab3e Time 0.5'c'y*

r 1 HPCI Flow (gpm) 5 AREA RAD MONITORS I mR/hr ~

2 Core Sprav A Flow (epm) s 37 Rx. Blde. 20 ft Airlock ) , y-3 RHR A Flow (epm) r Rx. Bldg. 50 ft Sample 4 RCIC Flow (rpm) 65 38 Station /

5 Core Sprav B Flow (epmt i S 39 Rx. Blde. 50 ft Airlock i i 6 RHR B Flow (epm) *< Ex. Bldg. North of Fuel 7 SLC Iniecting i A/ 40 Pool _ /

8 CRD Flow ( rpm) 1 4o Between Fuel Pool and 9 APRM % I ro 41 Drwell /)cwoe, ea 10 Reactor Pressure (psic) teg Turbine Bldg. Sample 11 Reactor Level (in) Irv7 42 Station 5-12 Main Stack Flow Pate (setm) 17o o,ss 43 SJAE A (mR/hr) i to Turbine Bldg. Roof Vent '

44 SJAE B (mR/hr) i Fo 13 Flow (sefm) /vcoo Rx. Bldg. Ventilation Rx. Bldg. Roof Vent Flow 15 Monitor (mR/hr) 3 14 (sefm) T4 cog Service Water Rad Monitor Rx. Bldg. Negative Press # 46 (eps) Yo 15 (inches n' water vacuum) ,?

16 Sopnre<=1on Dool Level (tn) 1. yo OTprR UNIT 17 nr *well Pressure (esic) I .2 Turbine M dg. Roof Vent I A SBGT Fl ow A (sc+mi 1 5 47 Flow (sefm) /F cea 19 SBGT Flow B (sefm) i J Turbine Mdg. Roof l 20 Drwell H, 4409 (% cone.) i ,cr 4R Vent Monitor (uCfIcee.) I /. v 21 Drwell H; 4410 (% cone.) I , o g-22 Drvve110; 4409 (% cone.) i f, y 23 Drwell 0; 4410 (' cone.) I r. 5 24 AOG Systein riow (sefm) l po 25 Off-Site Power Available i y Main Stack Gas Monitor 26 (uC1/see) f.1 #1 Turbine Bldg. Vent Monitor

?1 luCt/sec) 1. c er

• DRYkT.LL HIGH PAD MONITOR !R/hr 28 D22-RM-4195 - 30 ft El. I 2.

24 022 EM-4196 - 57 ft E1 In 30 n n-RM-4197 - 23 ft F1 i a-31 D22-RM-4198 - 57 +t O. ira 32 Drvve1] Teen '*ri i /s2 33 Suppression Pool Temp ('F) e pr RX. BLDG. ROOF VENT RAD MONITOR 34

• articulate (comb isees 6 Yodine (cpm) I .4 ee 36 Noble Gas (cpm) i Joo O PEP-02.6.21 Fev. 16 Page 22 of 34 l

l' NIT 0 PEP-02.6.21 Attachment 5 Page 1 of 1 ETHIBIT 2.6.21-5 SAFETY PARAMETER DISPLAY SYSTEM (UNIT 1)

Oy,erable Inoperable Standby Running Yes No Tsolated 3 - Not available Time 04co 1 HPCI Flow (epm) { c AREA RAD MONITORS rnR/hr 2 Core Sprav A Flow (epm) i e 37 Rx. Blde 20 f t Airlock , fZ 3 RHR A Flow (epm) i r Rx. Bldg. 50 ft Sample 4 RCIC Flow (epm) i 5 38 Station /

5 Core Sprav B Flow tepms e 5 39 Rx. Bldg. 50 ft Airlock i f 6 RHR B Flow (epm)

• 5 Ex. Bldg. North of fuel 7 SLC Iniecting i y 40 Pool /

8 CRD Flow (gpm) I do Between Fuel Pool and 9 APRM % i 7e 41 Drwell C a u t.

10 Reactor Pressure (psie) i veo Turbine Bldg. Sample 11 Peactor Level (in) isp7 42 Station , S-12 Main Stack Flow Pate (setm) ivesco 43 SJAE A (mR/hr) i ro 44 SJAE B (mR/hr)

Turbine Bldg. Roof Vent l 70 13 Flev (sefm) I / 4 coe Rx. Bldg. Ventilation Rx. Bldg. Roof Vent Flow l 45 Monitor (mR/hr) ,3

~

14 (sefs) 13-( ce u Service Water Rad Monito3 Rx. Bldg. Negative Press -

46 (eps) I 4/O 15 (inchen n' water vacuum) ,7 16 Suppre==1on Dool Leve1 (in) i-3o ATFrR t' NIT 17 nrwell Pressure (psie) i,t Turbine b'da. Roof Vent lA SBGT Flow A (sc+m) i3 47 Flow (scfm) /'/ 000 19 SBGT Flow B (sefm) i J Turbine Bldg. Roof 20 Drvwell H, 4409 (I cone.) i or 4R Vent Monitor (uCf /cee.) /. o 21 Drwell H; 4410 (* cone.) 6, or 22 Drweil 0; 4409 (I cone.) i f, 23 Drwell 0; 4410 (' cone.) Q f, y 24 AOC System Finw (sefm) { /o 25 Of f-Site Power Available i 9 Main Stack Gas Monitor 26 (uct/seel 2 . / 3 'l Turhine Bldg. Vent Monitor 77 (uci/see) / , a r "'

DRYWELL HIGH RAD MONITOR IR/hr 28 D22-0.M-4195 - 30 ft El. i 1 20 n22 PM-4196 - $7 ft 5.1 i n.

jn nn-Rw-4197 - 23 f r F1 i r 31 D22-RM-4198 - $7 ft F1 i ,cp 32 Drvve11 Temn Ti i e r 2_

33 Suppression Pool Temp (*F) t y <-

RX. BLDG, ROOF VENT RAD MONITOR 34 # articulate (comi  !/oco 45 Todine (cpm) { _N o 36 Noble Gas (epm) i Poo O PEP-02.6.21 Fev. 16 P4pe 22 of 34 l

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

EXHIBIT 2.6.21-5 SAFETY PARAMETER DISPt AY SYSTEM (UNIT 1)

Ogerable Inoperable Standby Running Yes No Tsolated NA - Not available Time O 6 /J' 1 HPCI Flow frpm) ,,,

l 5 AREA RAD MONITORS mR/hr 2 Core Sprav A Flow (epm,) 5 37 Rx. Blde. 20 ft Airlock ,F 3 RHR A Flow (epm) 7- Rx. Bldg. 50 ft Sample 4 RCIC Flow (epm) i 5 38 Station /

$ Core Sprav B Flow tepm) i 5 39 Rx. Blde. 50 ft Airlock i r 6 RHR B Flow (epm) 4 5 8x. Bldg. North of Fuel 7 SLC Iniecting i A/ 40 Pool /

8 CRD Flow (gpm) i Go Between Fuel Pool and 9 APRM %. I 70 41 Drvve11 (7cww /a 10 Reactor Pressure (psis) i 9,o Turbine Bldg. Sample 11 Reactor Level (in) l/g 7 42 Station , 5-12 Main Stack Flow Pate (setm) i 70oog 43 SJAE A (mR/hr) 90 Turbine Bldg. Roof Vent 44 SJAE B (mR/hr) yo 13 Flow (sefm) /Y 000 Rx. Bldg. Ventilation Rx. Bldg. Roof Vent Flow j 45 Monitor (mR/hr) ,1 14 (sefm) If4 000 Service Water Rad Monito1' Rx. Bldg. Negative Press 46 (cos) Yo 15 (inchen n' water vacuum) ,7 .

16 Suppre== inn Pool Level (in) i ~ 7o nTyrR UNIT 17 nr *well Pressure (psie) i 1 Turbine b'dg. Reof Vent IR SBCT Flow A (sefm) 1 5 47 T'.ow (sefm) /V too 19 SBGT Flow B (sefm) i 5 Turbine Bldg. Roof 20 Drvwell H, 4409 (% cone.) i , o s- 4R Vent Monitor (uCi /mee.1 /, o 21 Drvvell H; 4410 (I cone.) 6 , o s-22 Drvwell 0; 4409 (% cone.) I r. ,

23 Drvwell 0; 4410 (' cone.) /. y 74 AOC System riov (scfm) 7o 25 Off-Site Power Available '

V Main Stack Gas Monitor c, 26 (uCi/sec) 1./sT2 Turbine Bldg. Vent Monitor 77 (uCi/see) /.o r F # -

DRYWELL HIGH RAD MONITOR IR/hr 28 D22-RM-4193 - 30 ft El. i L 24 0 2 2 RM-4196 - 5 7 f t F.1 iso 30 n'?-RM-4197 - 23 +t #1 I r 31 D22-RM-4198 - 57 ft F1 i ;ro 32 Drvvell Temn (*F) I r i a._

33 Suppression Pool Temp (*F) i y S-RX. BLDG. ROOF VENT RAD MONITOR 34 Particulate (com$ f oo o ,

45 Todine (cpm) ' ro u 36 Noble Gas (com) ' 70 0 0 PEP-02.6.21 Fev. 16 Page 22 of 34 l

. _ _ _ . _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ . . - ._ i'-

UNIT 0 PEP-02.6.21 Attachmnt-5 Page 1 of 1 EXHIBIT 2.6.21-5 SAFETY PARAMETER DISPLAY. SYSTEM (UNIT 1) {

-Ogerable ,I, nope rable ' Standby Running Yes No Tsolated g - Not availab)e Time 0630 1 HPCI Flow (epm) ytoo AREA RAD MONITORS mR/hr 2 Core Sprav A Flow (epm) 3 37 Rx. Blde. 20 f t Airlock , r-3 RHR A Flow (epm) r Rx. Bldg. 50 ft Sample 4 RCIC Flow (gpm) i 3 38 Station /

5 Core Sprav B Flow (epm) i 5 39 Rx. Blde. 50 ft Airlock i i 6 RHR B Flow (gpm) i .5 Bx. Bldg. North of Fuel 7 SLC Iniecting i A/ 40 Pool /

8 CRD Flow (gpm) 1 6o Between Fuel Pool and 9 APRM % iyo 41 Drvwell o . -. /& j 10 Reactor Pressure (psie) i990 Turbine Bldg. Sample 1 Ify7 i.

I1 Reactor Level (in) 42 Station .T 12 Main Stack Flow Pate (scfm) ty :r o o o 43 SJAE A (mR/hr) p'o Turbine Bldg. Roof Vent 44 SJAE B (mR/hr) pa 13 Flow (sefm) f 4 cou Rx. Bldg. Ventilation Rx. Bldg. Roof Vent Flow l 45 Monitor (mR/hr) ,i 14 (sefm) f S 6 oes Service Water Rad Monitor Rx. Bldg. Negative Press 46 (eps) !90 15 (inches n' water vacuum) ,7 16 Suppression Pool Level (in) l-Jo OTyrR UNIT 17 nr uwell Pressure (psie)- t . 2. Turbine M dg. Roof Vent IR SBGT Flow A (sefmi i 3Ooo 47 Flow (sefm) / V 000 19 SBGT Flow B (sefm) i S Turbine Bldg. Roof 20 Drvvell H, 4409 (% cone.) I of 4R Vent Monitor (uCf/=ec.) /. 0 21 Drvwell H;, 4410 (% cone.) o f-22 Drvwell 0; 4409 (% cone.) f, 9 23 Drvwell 0; 4410 (' cone.) I r. S 24 A0G System Flow (sefm) 7, 25 Off-Sice Power Available V Main Stack Gas Monitor

~

26 (uci/see) /. R FN Turbine Bldg. Vent Monitor 77 fuCi/sec) /,0 s ""

DRYVELL HIGH RAD MONITOR R/hr 28 D22-RM-4195 - 30 ft El. i L 24 D22 8M-4196 - 57 ft E1. I so 30 n'?-RM-4197 - 23 fr n. I r 31 D22-RM-4198 - 57 ft M. iso 32 Drvwell Temn ("M i fir  :

33 Suppression Pool remp (*F) 6 yr RX. BLDG. BOOF VENT RAD MONITOR 34 Particulate (enmi icoo M Todine (cpm) _

3 oo 36 Noble Gas (com)  ! 700 i

0 PEP-02.6.21 Fev. 16 Page 22 of 34 l l

UNIT 0 PEP-02.6.21 Attach snt 5 Page 1 of 1 EXHIBIT 2.6.21-5 SAFETY PARAMETER DISPI.AY SYSTEM (UNIT .t )

02 erable Inoperable Standby Running Yes No Tsolated

_NA - Not availabl e Time C6 '/S~

1 HPCI F?ow (gpm) 4 7e o AREA RAD MONITORS mR/hr 2 Core Sprav A Flow (epm) s 37 Rx. Blde. 20 ft Airlock ,r 3 RHR A Flow ( epm) r Rx. Bldg. 50 ft Sample 4 RCIC Flow (epm) r 38 Station /

5 Core Sprav B Flow frpm) t i 39 Rx. Blde. 50 ft Airlock i a 6 RHR B Flow (gpm) i r Rx.-Bldg. North of Fuel 7 SLC Iniecting i u 40 Pool /

8 CRD Flow ( gpm) i Go Between Fuel Pool and l 9 APRM % 17o 41 Drwell IOm m te 10 Reactor Pressure (ps12) I 990 Turbine Bldg. Sample 11 Reactor Level (in) i tv / 42 Station ,f 12 Main Stack Flow Rate (setm) 177 coo 43 SJAE A (mR/hr) I go Turbine Blda. Roof Vent '

44 SJAE B (mR/hr) 50 13 Flow (sefs) /v coo Rx. Bldg. Ventilation Fx. Bldg. Roof Vent flow 45 Monitor (mR/hr) 7 14 (sefm) I't e c o Service Water Rad Monitor Rx. Bldg. Negative Press / 46 (eps)  : tro 15 (inches n' water vacuum) ,7 16 Supprescinn Pool Level (in) I yo OTFFR l' NIT 17 nr vwell Pressure (psie) 1. 2 Turbine M dg. Roof Vent IR SBGT Flow A (sefM iFoou 47 Flow (sefm) /4/ 00 0 19 SBGT Flow B (sefm) i s Turbine Bldg. Roof 20 Drvwell H, 4409 (: cone.) I . or 4R Vent Monitor (uCf/=ec.T /. O 21 Drvwell H; 4410 (I conc.) 1, or 22 Drwell 0; 4409 (1 cone.) /. e

< 23 Drvwell 0; 44tn ( conc.) /. y 24 AOG System Flow (sefm) 70 25 Off-Site Power Available '

v Main Stack Gas Monitor 26 (uci/sec) / , c- / I Turbine Bldg. Vent Monitor 77 (uCi/sec) /.0 F DRYWELL HIGH RAD MONITOR R/hr 28 D22-RM-4195 - 30 ft El. I 1 24 022-RM-4196 - 57 ft F.1 . iso 30 n97-RM-4197 - 23 ft F1 r 31 D22-RM-4198 - 57 ft F1 rv 32 Drvwell Temn ("r) i /rr 33 Suppression Pool Temp ("F) t w RX. BLDG. ROOF VENT RAD MONITOR 34 Particulate (comi /cea 45 Todine (cpm) rce 36 Noble Gas (cpm) Joo O PEP-02.6.21 Rev. 16 Page 22 of 34 l

FIGURE 1 I THERMAL POWER LIMITATIONS

/ / / / / /

/ CORE THERMAL INSTABILITY REGIONS

/ /

90-80 .

I 70 '

' /

U REGION A , RECION C 60 _

50 __

RECION 40 -

W 30 --

NOTE: FOR CORE FLOWS LESS

~~ THAN 19 64 SS/M MAINTAIN 20 DRE L N ER LESS

@g

~~

10 O l l l 19 25 30 35 CORE FLOW (MLES/HR)

(

0 A0P-04.3 Rav. 7 Page 8 of 8

7_--____-_

FIGURE I FLOW CONTROL OPERATIONAL MAP

' ' ' ' ' I 120 - A. Natural Circulatio l B. Minimum Recirculation Pump Speed l 110 - C. Analytical Lower Umst of Master 4V i Power Flow Contici 100 -D. ' Analytical Uccer Umst of Master p -w V ewer Flow Contr  %

ge6 g

\

• / '

'# M!

g ,,

/ f$i lY'% b

" / \

Ar adiXf y y .c ,w 3

g

@ r r  ; -

sf i

M

- # i l Minimum Power une ll, l '/

4 1

, , . . f 20

/ a station

/ # R 930 "

O

() ( ) (2 ) ( ) ( } } } ( } }' (8 re FI (M1.8S/MR) 45 ,

(35)

-APRM/LPRM Noise Surveillance Region (Two Loop) i BSEP/Vol. XX/ENP-24.0 12 Rev. 4 l

____._______--..__.---____u-_-__._-_----

UNIT 0 PEP-02.6.21

-Attachmcnt 5 I Page 1 of 1 L EXHIBIT 2.6.21-5 l-SAFETY PARAMETER DISPLAY SYSTEM (UNIT ,j ,,)

g Ogerable~ ' Inoperable Standby Running Yes No Tsolated NA - Not available- Time 6700 l: 1 HPCI Flow (gpm) yTo o AREA RAD MONITORS mR/hr

? Core Sprav A Flow (epm) 5 37 Rx. Blde. 20 ft Airlock ,r

~

3 RHR A Flow (apm) or Rx. Bldg. 50 ft Sample 4 RCIC Flow (epm) 4 ye o 38 Station /

5 Core Sprav B Flow (2pm) 1 5 39 Rx. Blde. 50 ft Airlock I /

6 RHR B Flow (rpm) IS e eo Rx. Bldg. North of Fuel

? SLC Iniecting i r/ 40 Pool / ,,

8 CRD Flow (gpm) tfoo Between Fuel Pool and 9 APRM Z i o 41 Drvwell Da w. cc, (s.

10 Reactor Pressure (psie) ty1o Turbine Bldg. Sample 11 Reactor Level (in) t/ 70 42 Station' . Y~

12 Main Stack Flow Rate (setml i76rev- 43 SJAE A (mR/hr) 2.

Turbine Bldg. Roof Vent 44 SJAE B (mR/hr) f 13 Flow (sefm) /4cro Rx. Bldg. Ventilation Rx. Bldg. Roof Vent Flow 45 Monitor (mR/hr) 7 14 (sefm) d) Service Water Rad Monitor Rx. Bldg. Negative Press 46 (eps) '/ o 15 (tochen n' vnter vacuum) ,v 16 Suppression Pool Levei .' in) _ 2 y , y- n;pru ifNIT 17 nrwwell Pressure (usic) 4 ,7 Turbine M dg. Roof Vent IR SBGT Flow A (sefm) Ipoco 47 Flow (sefm) / Y , c a o_,

19 SBGT Finv B (sefm) 17oco Turbine Bldg. Roof 20 Drvwell H, 4409 (% cone.) I or 48 Vent Monitor (uCf/=ce.) /. 0 ,,

21 Drvwell H; 4410 (% cone.) , o s-22 Drvwell 0; 4409 (% cone.) 2o 23 Drvwell 0,; 4410 (' cone.) 2.o 24 A0G Svste'h Flow (sef m) 55, e 25 Off-Site Power Available v Nain Stack Gas Mor.itor '

, 26 (uC1/sec) ,.

9. o g ' *-

Turbine Blalg. Vent Monitor rv 17 (uCi/sec) /. O v -

DRYWELL HIGH_ R&D MhNITOR R/hr 28 D22-RM-4195i- 30 f t El. I _S-24 D22 PM-4196 - 57 ft F.1 I 3- 3 30 n'n-RM-4197 - 23 ft F1 i 6 Il D22-RM-4198 - 57 ft F1 i5v 32 Drvwell Temn ("ri t //8 33 Suppression Pool Temp (*F) 6 91 RX. BLDG ROOF VENT RAD MONITOR 34 particulate (comi  ::(

45 Todine (cpm)  ;;c 36 Noble Gas (cpm) ar f l

0 PEP-02.6.21 Rev. 16 Page 22 of 34 l

O ,

1 w

UNIT 0 J PEP-02.6.21 Attachmsnt 5

. .Page 1 of 1 EXHIBIT 2.6.21-5 SAFETY PARAMETER DISPLAY SYSTEM (UNIT OL ) 3 1

]

,0gerable. Inoperable Standby Running Yes No Tsolated {

l NA - Not available Time /$7)P/jf l i HPCI Flow (epm) 5Ey AREA RAD MONITORS i mR/hr

-2 Core Sorav A Flow (rem) r 37 Rx. Blde. 20 ft Airlock i .c 3 RNR A Flev (epm) a Rx. Bldg. 50 ft Sample {

4 RCIC Flow (epm) i uco 38 Station I /

5 Core Sorav B Flow frpm) 5 J,9_Rx. Blde. 50 ft Airlock i  ;

c 6 RHR B Flow (epm) f r coo Rx. Bldg. Forth of Fuel l 7 SLC Iniecting i A/ 40 Pool 1- l 8 CRD Flow ( cmn) i roo Between Fuel Pool and l 9 APRM % 8 o __ 11 Drvuell I g o w f a (.

10 Reactor Pressure (psie) I' $ 5'd Turbine Bldg. Sample l 11 Reactor-Level (in) I f70 42 Station I sI~

, , 12 Main Stack Ficw Pate (sefm) 174 eq3 u 43 SJAE A (mR/hr) i 1

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

13 Flow (sefm) sv oov Rx. Bldg. Ventilation Rx. Bldg. Roof Vent flow 45 Monitor (mR/hr) .3 14-(scfm) ()

46 Service Water Rad Monitog YD Dx. Bldg. Negative Press (cos) 'I 15 (inches .n' unter vacuum) Y '

,16 j Suppre==1n" Dool Level (in) i - A f. 3' OTyrg UNIT 17 nr uwell Pressure (psic) I .7 Turbine 'dg. Roof Vent 3R SBGT Flew A (sefm) i7oo0 47 Flow (se#m) /VCOO 19 SBGT Flow B (sefm) i Joao Turbine Ridg. Roof .)

20 Drvvell H, 4409 ( cone.) i.or f. S Vent Montter (uCi/ cec.i i /. O

(* cone.) 1.or 21 Drvve ll H ^, 4410 22 Drvvell 0; 4409 (% conc.) i 2 0 23 Drvvell 0; 4410 (' cone.) z0 24 AOG System Flow (sefm) str 25 of f-Site Power Available '

y Main Stack Gas Monitor 26 (uCi/sec) /, 0 s #

Turbine Bldg. Vent Monitor 77 (uct/sec) f.p p r*

DRYWELL HIGH RAD MONITOR R/hr 2B D22-RM-4195 - 30 ft El. '

1 2 4 0 2 2 BM-4196 - 5 7 f t 5.1 . i rr 30 n'?-Rv-4197 - 23 ft F1 6 40 31 D22-RM-4198 - 57 't F1 Iff 32 Drvvell Temn t'ri i s/3 33 Suppression Pool Temp (*F) i qz RX. BLDG. ROOF VENT RAD MONITOR 34 Particulate (comi I 355 45 todine (cpm) i 105 36 Noble Gas (cpm) i 1?S 0 PEP-02.6.21 Rev. 16 Pate 22 of 34 l I.

M UNIT 0 PEP-02.6.21 Attschacnt 5 EXHIBIT 2.6.21-5 SAFETY PARAMET.IR DISPLAY SYSTEM (UNIT OL )

p j; ogerable Inoperable Standby Rut'ning Yes No Tsolated 1.

l NA - Not available Time G7 7yg)

~

1 HPCI Flow (epm) AREA RAD MONITORS I$/F(Q(( I mR/hr

? Core SDrav A Flov ( cprio ir 37 Rx. Blde. 20 f t Airlock i , c-3 RHR A Flov (apm) 'r ,

Rx. Bldg. 50 ft Sample 4 RCIC Flev (epm) .veo ,

39 Station /

5 Core Sprav B Flov aepm) ' 5 39 Rx. Bldc. 50 ft Airlock i ,

6 RHR B Flov (apm) 'I soo Fx. Blde. North or Fuel l

7 SLC Iniecting i n/ 40 Pool i /

8 CRD Flov (apm) 'roo Between Fuel Pool and j 9 APRM % 1o 31[Drvvell IOc wa s w. tu 10 Reactor Pressure (esir) vi 776 ' Turbine Bldg. Sample l 11 Reactor Level (in) l /70 41,jtation I , i-12 Main Stack Flev Pate t scfm) I (mR/hr)

Turbine Bldg. Roof Vent ?foco QL'AE 44 3JAE B A (mR/hr) i i t 2.

13 Flev (sefm) / v ces Rx. Bldg. Ventilation Rx. Bldg. Root Vent flov l 45 Mcnitor (mR/hr) <2 14 (sefm) I d2 Sef71ce Water Rad Monitog YU Rx. Bldg. Negative Press 46 (eps)  !

15 (inchea n' water vacuum) .Y 16 Supore==1nn pool Level (in) l-LR i ATFrR L' NIT 17 nr vvell Pressure (esir) 8 .7 Turbine 'da. Roof Vent la~S BGT Fl ow A (sc'*) iJorg 4? ri eg (ge s ,) j/fogo g

19 SBCT Flow B (sefm) 1Joao Turbine R!dg. Roof 20 Drvvell H, 4409 ( ". cone.) i .cr '. R 1*e n t Mon. or (uCf'aec.i /. O 21 Drvvell H; 4410 (" conc.) 1.cr 22 Drvvell 0; 4409 (* conc.) I 1c 23 Drvvell 0; 4410 (' cone.) 'zc 24 AOC Systen riov (sefm) 3rf 25 Off-Site Power Available y Main Stack Gas Monitor 26 (uci/sec) E O f

Turbine Bldg. Vent Monitor 77 (uct/sec) 1. v F r' DRYWELL HIGH RAD MONITOR IR/hr 28 D22-RM-4195 - 30 ft El. I 7 24 0 2 2 RM-4196 - 5 7 f t F.1 I fr 30 n9?.RM-4197 - 23 't F1 I to 31 D22-RM-4198 - 57 *t #1 I 3-ir 32 Drvvell Temn s ari i lib 33 Suppression Pool Temp (*F)  : St RX. BLDG. ROOF VENT RAD MONITOR 34 Particulate (com$ i 74 K iodine (cpm) i15 36 Noble Gas (cpm) 1 555 O PEP-02.6.21 Rev. 16 Page 22 of 34

i UNIT 0 PEP-02.6.21 Attechtsnt 5' Page 1 of 1 EXHIBIT 2.6.21-5 SAFETY PARAMETl'R DISPLAY SYSTEM (UNIT .'L )

ogerable Inoperable Standby Ruhming . Yes No Tsolated NA - Not available Time __ 6 7Ff~

l HPCI Flav (epm) I hUho o AREA RAD MONITORS i mR/hr 2 3cce Sprav A Flow (2pm) I y 37 Rw. Side. 20 ft Airlock i ,e 3 RHR A Flow (rom) t 5: P. x . Bldg. 50 ft Sample 4 RCIC Flow (apm) i ya o _ 38 Station 1 5 Core Sprav B Flow # rpm) 5 39 Rx. Blde. 50 ft Airlock i e 6 RHR B Flow (gpm) 7 SLC Iniecting icwoo Rx. Bldg. North of fuel l i A/ 40 Pool I i 8 CRD Flow (gpm) Irou Between Fuel Pool and l 9 APRM % i e 41~Drvwell l oss. , c a rt 10 Reactor Pressure (psie) i- 7 7 y Turbine Bldg. Sample l 11 Reactor Level (in) i / 7 0 ___ 42 St'ation  ! c-12 Main Stack Flow Pate (sefm) 1 7f s o c- 43 SJAE A (mR/hr) i L Turbine Bldg. Root Vent l 44 SJAE B (m R / h r) t  !

13 Flow (sefm) I e V ocv Rx. Bldg. Ventilation Rx. Bldg. Roof Vent Flow 45 Monitor (mR/hr) ,3 14 (sefm) (7 Service Water Rad Monitog Rx. Bldg. Negative Press 46 (cos) I 9u 15 (inchen n' water vacuum) Y 16 Superemainn pool Level (in) 1 1 9 .I n7 pen gg77 f 17 nr rvell Pressure (ps12) i 7 Turbine 'da. Roof Vent l l A SBGT Fl ow A (se'mi iJoro 4* r]ow (se em) l/VCud 19 SBGT Flow B (sefm) iJoao Turbine Aldg. Roof 20 Drsvell H, 4409 ( cone.1 i.cr f. E Pent Mor t or (uCf 'aec . i /. U 21 Drvvell Hi 4410 (f cone.) i,er 22 Drvwell 0; 4409 (1 cone.) 1-0 23 Drvwell 0; 4410 (' cone.) 3.c 24 AOC System rinu (sefm) 2rf 25 off-Site Power Available v Main Stack Gas Monitor 26 (uci/sec) 3~ W #

Turbine Bldg. Vent Monitor 27 luct/sec) 1. C F Y' DRYkTLL HIGH RAD MONITOR 'R/hr 28 D22-RM-4t95 - 30 ft El. I 7 24 022 RM-4196 - 57 f t F.1 I5c 30 n o ?-RM-4197 - 23 ft r1 i ,o 31 D22-RM-4198 - 5 7 't r1 I 3- r 32 Drvvell Temn (*r) i t/b 33 Suppression Pool Ter.p (

• F) i St RX. BLDG. ROOF VENT RAD MONITOR 34 Particulate (comt i 305 6 Todine (epm) I cr y 36 Noble Gas (cpm)  ! c55 0 PEP-02.6.21 Rev. 16 Page 22 of 34  !

l'.s ,

LTIT 0 PEP-02.6.21 Attsch2snt 5 Page 1 of 1 EXHIBIT 2.6.21-5 SAFETY PARAMETER DISPLAY SYSTEM (UNIT 1)

Operable jnoperable Standby ' Running Yes No Tsolated NJ - Not available Time _O B O # )

l L 1 HPCI Flow (rpm) y300 AREA RAD MONITORS mR/hr l 2 Core Sprav A Flow (epm)  % 37 Rx. Blde. 20 f e Airlock r 3 RHR A Flow (rpm) '

5 Rx. Bldg. 50 ft Sample 4 RCIC Flow (gpm) I u o ce 38 Station /  ;

5 Core Sprav B Flow f rpm) 8 ,( 39 Rx. Blde. 50 ft Airlock i i 6 RHR B Flow (epm) 6 s Rx. Bldg. North of Fuel 7 SLC Iniecting i A/ 40 Pool /

8 CRD Flow (gem) i / cci Between fuel Pool and 9 APRM % i O 41 Drwell Do s n > <s t.a.

10 Resetor Pressure (psie) i 47L Turbine Bldg. Sample 11 Reactor Level (.in) I / 70 ' 42 Station . , $~

12 Main Stack Flow Pate (scim) i74oea 43 SJAE A (mR/hr) i 1 Turbine Bldg. Roof Vent 44 SJAF. B (mR/hr) i l

13 Flow (sefm) I / y cou Rx. Bldg. Ventilation Rx. Bldg. Roof Vent Flow l t.5 Monitor (mR/br) - 3 14 (sefs) I O Service Water Rac Monitor Rx. Bldg. Negative Press 46 (eps) N 15'(inchen n' water vacuum) . 't 16 Suppre== inn Pool Level (in) 1 -19 r OTyrR LNIT 17 nr vvell Pressure (esia) i 3 Turbine kids. Roof Vent IR SBGT Flow A (sc N Igooo 47 Flow (sefm) U dCM 19 SBGT Flow B (sefm) i ?co o Turbine Bldg. Roof 20 Drwell H, 4409 ( cone.) i ,or 4R Vent Monitor (uCi/*ee.I l ', O 21 Drvvell H; 4410 (*. cone.) I.tr 22 Drvvell 0; 4409 (I cone.) i 2.<

23 Drvvell 0; 4410 (' cone.) 1o 24 AOC System riow (sefm) -r a 25 Of f-Site Power Available v Main Stack Gas Monitor /

26 (uci/see) .or'r Turbine Bldg. Vent Monitor

'7 (uci/see) / dc #

DRYkT:LL HIGH RAD MONITOR R/hr 28 D22-RM-4195 - 30 ft E1. i y 24 022 RM-4196 - 57 ft F.1 . i 53-30 n$9-RM-4197 - 23 ft F1 I io 31 D22-RM-4198 - 57 ft r' . i f r-32 Drvvell Temn (m i ; i rf 33 Suppression Pool Temp (*F) i 9.t RX. BLDG. ROOF VENT RAD MONITOR 34 Particulate (com5 i IS 45 Todine (cpm) i TS 36 Noble Gas (epm) I r5 0 PEP-02.6.21 Fev. 16 Page 22 of 34 l

UNIT O PEP-02.6.21 Attscheent 5 Page 1 of 1 L

EXHIBIT 2.6.21-5 SAFETY PARAMETER DISPLAY SYSTEM (UNIT ll )

Ogerable Inoperable Standby Running Yes No Tsolated NA - Not available Time _678/f--

1 HPCI Flow (gpm) l Gr.?O O _ AREA RAD MONITORS I mR/hr 2 Core SDrav A Flow ( epm) I dC -37 Rx. Blde. 20 ft Airlock i . f 3 RHR A Flow (epm) I qa Rx. Bldg. 50 ft Sample 4 RCIC Flow (gpm) l 3: 5 38 Statien -l 5 Core Sprav B Flow (gpm) 6 ,( 39 Rx. B1de. 50 ft Airlock i #

6 RHR B Flow (gpm) i oc Ex. Bldg. North of Fuel 7 SLC Iniecting  ! A/ 40 Pool I

~B CRD F1cw (apm) i /00 Between Fuel Fool and 9 APRM % i O 41 Drvvell cy, ,o , u, (,

l 10 Reactor Pressure (pste) i 6/o Turbine Bldg. Sample j L 11 Reactor Level (in) i / 70 42 Station f .%

~

12 Main Stack Flew Pate (setm) i 7( oe o_ 43 SJAE A (mR/hr) i i Turbine Bldg. Roof Vent 44 SJAF. B (mR/hr) i  ;

13 Flow (sefm) l/yocu

. Rx. Bldg. Ventilation Rx. Ridg, Roof Vent Flov l

/ 45 Monitor (mR/hr) ,3 14 (sefs)' I () Service Water Rad Monicoq Rx. Bldg. Negative Preos 46 (cos) l 70 15 (inches n' vnter vacuum) 9 -

16 Suppre==1nn Dool Level (in) -2 9. c nTPrR UNIT 17 ne wwell Pressure (esia) 1 3 Turbine u dg. Roof Vent I A S BCT Fl ow A (se'm) I?ooo 47 Flow (se#m) /V SCd 19 SBGT Flow B (sefm) iJeeo Turbine U dg. Roof l 20 Drvvell H, 4409 ( cone.) i .or 4R Vent Monitor (uCf/=ce.) I /,O 21 Drvwell H; 4410 (* cone.) 6.Or 22 Drvwell 0 4409 (I cone.) I 2.,

23 Drvwell 0; 4410 (' cone.) It o 24 AOC Svstem riow (sefm) i 77J 25 Of f-Site Power Available v Main Stack Gas Monitor /-

, 26 (uCi/see) T' O # rt Turbine Bldg. Vent Monitor

?7 (uci/see) /. d C "

DRYWELL HICH RAD MONITOR R/hr 28 D22-RM-4195 - 30 ft E l~ . 7 24 D22 WM-4196 - 57 ft 5.1 rr 30 n99-RM-4197 - 23 fr F1 '

/o 31 D22-RM-4198 - 57 *t #2 Irr 32 Drvvell *amn ) I ris 33 Suppression Pool Temp (*F) i ff' RX. BLDG. ROOF VENT RAD

~~-

MONITOR 34 Particulate (comi 25 45 Todine (epm) 55 36 Noble Gas (epm) :rs O PEP-02.6.21 Fev. 16 Page 22 of 34 l

_ . _ _ _ _ _ _________m

UNIT 0 PEP-02.6.21 Attachant 5 {

Page 1 of 1 EXHIBIT-2.6.21-5' SAFETY PARAMETER DISPLAY SYSTEM (UNIT 2L )

i Ogerable ineparable Standby Running Yes ^ No Tsolated NA - Not available Time (Ef3d7 1 HPCI-Flow (epm) i V?co AREA RAD MONITORS I mR/hr 2 Core Sprav A Flow (epm) i 10 37 Rx.-Blde. 20 ft Airlock i .T 3 RHR A Flow (epm) I qa Rx. Bldg. 50 ft Sample l 4 RCIC Flow (gym) i 3rS , 3,8 Station I / i 5 Core Sprav B Flow (epm) e ,r 39 Rx. Blde. 50 ft Airlock i f 6 RHR B Flow (gpm)

• is R'x . Bldg. North of Fuel 7 SLC Iniecting i A/ 40 Pool 1 8 CRD Flow f apc.) i /Co Between fuel Pool and 9 APRM I i O 41 Drvwell n o s,, , c A 10 Reactor Pressure (pste) i J'9 F Turbine Bldg. Sample 11 Reactor Level (in) i / 70 42 Station . f~

12 Main Stack Flow Rate (setm) i 74000 43 SJAE A '

(mR /hr) i 2 Turbine Bldg. Roof Vent ee SJAE F (mR /hr) 6 r 13 Flow (sefm) / y ava Rx. Bldg. Ventilation i Rx. Bldg. Roof Vent Flow l 45 Moniter (es/hr) .8 14:(sefs) I () Service Water Rad Monitor Rx. Bldg. Negative Press j 46 (eps) 9'O 15 (inches n' water vacuum) t 9 16 Suppre== inn Pool Level (in) i - A S. r OTFr9 UNIT 17 hevve11 Pressure (pste) i I Turbine "'da. Roof Vent IR SBCT Flow A (sc'mi i?cco 47 Flow (sefm) /IOCU 19 SBGT Flow B (sefm) 1Joeo Turbine Bldg. Roof l 20 Drvvell H, 4409 (" cone.) i ,or 4R Vent Monitor (uci/=ce.) I /,v 21 Drvve11 H; 4410 (2 cone.) i.Or 22 Drvvell 0; 4409 (% cone.) I i.,

23 Drvwell 0; 4410 (' conc.) 61_o 24 AOC Systes riov (sefm) } gra 25 off-Site Power Available i y .

Main Stack Gas Monitor e

. 26 (uci/sec) f.opr' Turbine Aldg. Vent Monitor 77 (uCi/sec) /. d F "

DRYWELL HIGH RAD MONITOR R/hr 28 D22-RM-4195 - 30 ft El. y 24 0 2 2 RM-4196 - 5 7 ft 8.1 . Isr 30 ni?-RM-4197 - 23 ft F1 6 /d 31 D22-RM-4198 - 57 ft F1 i fr 32 Drvwell Temn ri 6ylg_

33 Suppression Pool Temp (*F) i 76 RX. BLDG. ROOF VENT RAD

~~'

MONITOR 34 Particulate (comi i IES n Todine (cpm) i 55 36 Noble Gas (cpm) i cr5 0 PEP-02.6.21 Rev. 16 Page 22 of 34 l

UNIT 0 PEP-02.6.21 Attachment 5 Page 1 of 1

' EXHIBIT 2.6.21-5 SAFETY PARAMETER DISPLAY SYSTEM (UNIT ll )

Og,e rable inoperable Standby Running Yes No Tsolated NA - Not available Time 88/[

l HPCI Flow (epm) i K?co AREA RAD MONITORS I mR/hr 2 Core Sprav A Flow (epm)  ! CL 37 Rv. Blde. 20 ft Airlock i f-3 RHR A Flow (epm) i v_ Rx. Bldg. 50 ft Sample l 4 RCIC Flow (epm) r SCs 38 Station I /

5 Core Sprav B Flow (epm) # ,r 39 Rx. Blde. 50 ft Airlock I r 6 RHR B Flow (gpm) ' tr R3. Bldg. North of Fuel 7 SLC Iniecting -

s/ 40 Pool I 8 CRD Flow (gpm) t /co Between fuel Pool and l 9 APRM % i O 41 Drvvell l_ Oo w.f s,4 10 Reactor Pressure (ps12) I YF6 Turbine Bldg. Sample l

!! Reactor Level (in) I / 70 42 Station l , f~

12 Main Stack Flow Rate (scrm) i 7( ca p 63 SJAE A (n@ihr) t i Turbine Bldg. Roof Vent l 44 SJAF B (mR/hr) I r 13 Flow (sefm) I / y cov Rx. Bldg. Ventilation

'y Rx. Bldg. Roof Vent Flow l 45 Monitor (mR/hr) 14 (sefm) I Service Water Rad Monitoq Rx. Bldg. Negative Press. 46 (eps) 'l 9/0 15 (inchen n' water vacuum) .P 16 Supprem=1on Dool Level (in) 1 -19t r OTurg UNIT 17 ne arvell Pressure (pste) 1 5 Turbine dg. Roof Vent IR SBCT Flow A (sefmi i?oco 47 Flow (sc#m) /ESCd 19 SBGT Flow B (sefm) I ?ooo Turbine aldg. Roof 20 Drvvell H, 4409 (% cone.) I .or LR Vent Monitor (uCi/cee.) /,d 21 Drvvell H; 4410 (% cone.) i .tr 22 Drvvell 0; 4409 (% cone.) '

2.a 23 Drvvell 0; 4410 (' cene.) i o 24 A0G System view (sefm) 7J

• 25 Off-Site Power Available v Main Stack Gas Monitor /

26 (uci/sec) f 0F #

Turbine Bldg. Vent Monitor 77 (uct/see) /, d r "# '

DRYWELL HIGH RAD MONITOR R/hr 28 D22-RM-4195 - 30 ft El. I 7 24 n22 RM-4196 - 57 f t r.1 I rr 30 n9?.RM-4197 - 23 ft F1 i ,o 31 D22-RM-4198 - 57 ft r'. i 3 s-32 Drvvell Temn ("ri i rig 33 Suppression Pool Temp ( *F) i 10/

RX. BLDG. ROOF VENT RAD MONITOR 34 particulate (ecm4 I JL5 35 Todine (epm) t 55 36 Noble Gas (epm) l 27 5 0 PEP-02.6.21 Rev. 16 Page 22 of 34 l 1

UNIT 0 PEP-02.6.21 Actscheent 5 Page 1 of 1 EXHIBIT 2.6.21-5 SAFETY PARAMETER DISPLAY SYSTEM (UNIT CL )

Ogerable I,noperable Standby Running Yes No Tsolated NA - Not available Time (7100 1 HPCI Flow (Epm) i Vfod, AREA RAD MONITORS I mR/hr

? Core Sprav A Flow (epm) t CL 37 Rx. Blde. 20 ft Airlock i , r-3 RHR A Flow (rpm) I 1p Rx. Bldg. 50 ft Sample 4 RCIC Flow (gym) Iuco 38 Station /

5 Core Sprav B Flow (apm) * ,( 39 Rx. Blde. 50 ft Airlock i ,

6 RHR B Flow (gym) i d: Ex. Bldg. North of Fuel l 7 SLC Iniecting i n/ 40 Pool I /

8 CRD Flow (gpm) i /Co Between fuel Pool and l 9 APRM % ._ ,, i O 41 Drvwell la,m ,c /L 10ReactorPressurs.4731a) I Y:1Y ' Turbine Bldg. Sample l

!! Reactor Level I5 I / 70 42 Station I . S-12 Main Stack Flow I+'Ib (sefm) i7{oco #

43 SJAE A (mR/hr) i x Turbine Bldg. Roof Vent 4k SJAF B (mR/hr) i /

13 Flow (sefm) /v cou Rx. Bldg. Ventilation Rx. Bldg. Roof Vent flow j

/

45 Moniter (mR/hr) 8 14 (sefm) I G? Service Water Rad Monitor Rx. Blda. Negative Press l 46 (eps) TD 15 (1nchen n' water vacuum) I .P 16 Suppre==1nn Pool Level (in) 1 -2 9. r OTyrR UNIT 17 ne vvell Pressure (psir) i 3 Turbine M da. Roof Vent IR SBCT Flow A (sc'*) I?occ 47 Flow (scfm) /E8Ci 19 SBGT Flow B (sefm) i ?oeo Turbine Ridg. Roof l 20 Drvwell H, 4409 (% conc.) I .or 4R \'ent Montter (uCi/cee.1 I l.d 21 Drvwell H; 4410 (7. conc.) i ,er 22 Drvwell 0; 4409 (% cone.) i 2 ,

23 Drvwell 0; 441n (' cone.) 1 e 24 AOC System Flow (sefm) gra 25 Of f-Site Power Available v Main Stack Gas Monitor /

d

. 26 (LCi/see) _f'0 6 Turbine Blda. Vent Monitor 77 (uCi/see) /. 0 6 " #

DRYWELL HIGH RAD MONITOR 6 R/hr 28 D22-RM-4195 - 30 ft El. i 7 24 0 2 2 RM-4196 - 5 7 f t 8.1 i 53-30 n99-RM-4197 - 23 ft F1 t eg 31 D22-RM-4198 - 57 ft *1 I f3-32 Drvwell Temn ("Fi i //r .

33 Suppression Pool Temp (*F) I /Oy _

RX. BLDG. ROOF VENT RAD MONITOR 34 Particulate (com) 25 35 Todine (cpm) 55 36 Noble Gas (cpm) l 07 5 0 PEP-02.6.21 Rev. 16 Page 22 of 34 l

l UNIT 0 PEP-02.6.21 Attechant 5 1 Page 1 of I f

EXHIBIT 2.6.21-5 ~

SAFETY PARAMETER DISPLAY SYSTEM (UNIT 1_)

gerable I, nope rable Standby Running Yes No Tsolated j , j l NA - Not available Time ## # ~ ~/ #' #

1 HPCI Flow (Epm) ygoo AREA RAD MONIIDRS mR/hr 2 Core Sorav A Flow (epm) 2; 37 Rx. Blde. 20 ft Airlock 5-3 RHR A Flow (epm) 7 Rx. Bldg. 50 ft Sample 4 RCIC Flow (ape) 9ec 38 Station /

5 Core Sprav B Flow (epm) # 33 39 Rx. Blde. 50 ft Airlock /

6 RHR B Flow (epm) + roo c.:. Fx. Bldg. North of Fuel

~7'SLC Iniecting i Ai 40 ?ool /

8 CRD Flow (epm) I /o o Between Fuel Pool and 9 APRM % i o 41 Drvvell . %,m /c.

' 10 Reactor Pressure (psie) i Turbine Bldg. Sample 11 Reactor Level (in) i/70 42 Station .5' 12 Main Stack Flow Pate (scfm) i 7f o c o 43 SJAE A (mR/hr) I i Turbine Bldg. Roof Vent 44 SJAE B (mR/hr) /

13 Flow (sefm) . / v c ou Rx. Bldg. Ventilation Rx. Bldg. Roof Vent Flow '

45 Monitor (mR/hr) .I 14 (sefm) O Service Water Rad Monitor Rx. Eldg. Negative Press 46 (eps) PO 15 (inches n' water vacuum) .V 16 Suppre==1on Pool Level (in) l 2 5. r OTHFR (NIT <

17 nr vvell Pressure (os12) I .7 Turbine Mdg. Roof Vent IR SBGT Flow A (scfmi I3o00 47 Flow (sefm) /V000

~

19 SBGT Flow B (sefm) 1 Soo o Turbine Bldg. Roof 20 Drvwell H, 4409 (% cone.) i , or 4R Vent Monitor (uCf /=ec.) /. O 21 Drvwell H; 4410 (% cone.) i 05-22 Drvvell 0; 4409 (% cone.) so 23 Drvwell 0; 4410 (' conc.) so . r-24 A0G System Flow (sefm) vr.r 25 Off-Site Power Available v Main Stack Gas Monitor 26 (uCt/sec) 5: o r t '

Turbine Bldg. Vent Monitor 77 (uCi/sec) / . O tr ' #

DRYWELL HIGH RAD MONITOR R/hr 28 D22-RM-4195 - 30 ft El. i 7 24 022-RM-4196 - 57 ft E1 I _r- e-30 n9?-RM-4197 - 23 ft F1 i fo 31 D 22-RM-4198 - 5 7 ft F1 i Srg-  !

32 Drywell Temn (*ri iffy 33 Suppression Pool Temp (*F) l RX. BLDG. BOOF VENT RAD MONITOR 34 Particulate (comi l 7r _

45 Todine (epm) 7: 5 36 Noble Gas (cpm) 5?S 0 PEP-02.6.21 Rev. 16 Page 22 of 34 l f

UNIT 0 PEP-02.6.21 Attachment 5 Page 1 of 1 EXHIBIT 2.6.21-5 SAFETY PARAMETER DISPLAY SYSTEM (UNIT .1) gerable Inoperable Standby Running Yes No Tsolated t',,,,.J. p .r4<fy N,A A - Not available Time , h' c...,. p g 1 HPCI Flow (spm) vfo o AREA RAD MONITORS mR/hr 2 Core Sprav A Flow (epm)  % 37 Rx. Blds. 20 ft Airlock ,r 3 RHR A Flow (apm) roop 7, Rx. Bldg. 50 ft Sample 4 RCIC Flow (spm) i p e ,, 38 Station /

5 Core Sprav B Flow icpm) i yr 39 Rx. Blds. 50 ft Airlock i /

6 RHR B Flow (epm) Ec co o Bx. Bldg. North of fuel 7 SLC Iniecting i A/ 40 Pool /

8 CRD Flow ( gpm) i i ocs Between Fuel Pool and 9 APRM I I c; (.! Drwell co m sc , ta 10 Reactor Pressure (psie) i Turbine Bldg. Sample 11 Reactor Level lin) l ivo 42 Station ,f 12 Main Stack Flow Pate (scfm) 1 rc 8ov 43 SJAE A (mR/hr) .

I Turbine Bldg. Roof V?nt 44 SJAE B (mR/ hr) '

/

13 Flow (sefm) / y eo Rx. Bldg. *.'entilation Rx. Bldg. Roof Vent Flow 45 Monitor (mR/hr) ,  ?

14 (sefm) O Service Water Rad Monitor Rx. Bldg. Negative Press 46 (cos) 90 15 (inchen n' water vacuum) . V 16 Suppremainn pool Leve1 (in) i . 2 y, f ATFrR UNIT ____

17 nr vvell Pressure (pcie) i ,J Turbine b'dg. Roof Vent tR SBGT Flow A (scfC 1 3 eso 47 Flow (sefm) /7000 19 SBGT Flow B (sefm) y nsa Turbine Bldg. Roof '

l 20 Drwell H, 4409 (% cone.) .cc 4R Vent Monitor (uCf /=ec.) / . (./

21 Drwell H; 4410 (% cone.)  ! cr 22 Drwell 0; 4409 (% cone.) l

L u 23 Drwell 0; 4410 (' cone.) a o. r 24 AOC Systein Flow (sef m) 7: r 25 Off-Site Power Available y Main Stack Gas Monitor 26 (uCi/sec) fo?'

Turbine Bldg. Vent Monitor

~

'87 (uCi/sec) /.06 I

DRYWELL HIGH RAD MONITOR R/hr 28 D22-RM-4195 - 30 fe El. iy 24 0 2 2 DM-419 6 - 5 7 f t F.1 . ice- '

30 n'9-RM-4197 - 23 ft F1 I <c 31 D22-RM-4198 - 57 ft F1 irr I 32 Drvwell Temo ("Fi I , /r 33 Suppression Pool Temp (*Fi l l RX. BLDG, ROOF VENT RAD MONITOR 34 Particulate (comi qs 45 Todine (cpm) rc 36 Noble Gas (cpm) 75 0 PEP-02.6.21 Fev. 16 Page 22 of 34 l o

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l' 1989 ANNUAL EXERCISE f'

Habitability Survey Results All habitability survey results in Brunswick Steam Electric Plant Emergency Reeponse Facilities will be "as read" for the duration of the exercise, l

1 i

l l

l l

1.

l E_________________________________ _ _ _ _ . _ _ _ _ _ _ _ ._ _ _ - _ _ _ _ . . _ . . _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ . _. . _ _ _ _ _ _ _ _ _ _ _ _ _ _

l l 1989 ANNUAL EXERCISE 1

l Unit 1 l Summary of In-Plant Radiological Conditions l

l. Following the fuel handling accident, the Reactor Building ventilation is isolated by the radiation monitor, SBGT activates, and building ARMS start to respond. Initially, ambient dose rates due to air activity in secondare containment vill be high on 117', and gradually reach an equilibrium increase of 15 mr/hr throughout the building. Continued improvement vill occur as time progresses. Contamination levels will be slightly above normal.

l Duringthecourseggthisaccident, the main stack effluent monitor increases I to a high of 2.1 E vei/sec. There are no significant off-site dose conse-quences from this release rate.

The Radvaste Building will show a small increase in radiation levels on 23' due to operation of the fuel pool cleanup system.

The Unit 1 Turbine Building will not be affected by this exercise.

Radiation levels in Unit i Reactor Building are indicated on the attached charts for RMS and ARMS.

l l

l l

C____________ _ _ _ .

f 1989 ANNUAL EXERCISE Unit 1 Equilibrium Air Activity After Accident Inside Secondary Containment l Nuclide uci/ml

'~# -4 Kr-85 2.6 E l

-4 Xe-133 3.6 E

-5 I-131 1.2 E

~

Xe-131m 1.7Ef 6.5 E '

1989 ANNUAL EXERCISE Unit 2 Summary of In-Plant Radiological Conditions l

l Prior to 0700, all radiological conditions in Unit 2 Reactor Building are normal ("as read"). At 0700, minor cladding damage occurs due to a recircu-lation pump trip and the injection of water from the condensate storage tank to the reactor vessel. The reactor scrams on a main steam line Hi Hi radia-tion indication. The resultant fuel cladding failure, combined with the operation of RHR Loop B, RCIC and HPCI, will result in significant dose rate increases in the area of Unit 2 South RHR, HPCI, and HPCI roof.

l Air samples and surf ace contamination will be "as read". Abnormal radiation levels are defined on the attached survey maps. All other areas vill be "as j read".

This accident does not result in any type of release to the environment.

l The Unit 2 Turbine Building is not affected by this accident.

t l

l l

BRUNSWICK STEAM ELECTRIC PLANT SURVEY NO.

RADIOLOGICAL SURVEY RWP NO.

REACTOR BUILDING #2 20' SOUTH SIDE DATE T-27.W TIME 0 7'O M DOSE RATE CONTAMINATION INST. TYPE INST. TYPE SURVEYOR SERIAL NO. SERIAL NO.

RX POWER EFFICIENCY REVIEWED BACKCROUND )

^

AINDICATEs SMEAR RESULTS ELECTRICAL IN OPM/100cma DUTLETS B-BETA IN MRAD /HR/100em2 E POINT RESULT 5

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t- _. - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___ _

BRUNSWICK STEAM ELECTRIC PLANT SURVEY NO.

RADIOLOGICAL SURVEY RWP NO.

REACTOR BUILDING #2

-17' SOUTH R.H.R.

DATE TIME 0 7 / # ~ #F/# 00SE RATE CONTAMINATION INST. TYPE INST. TYPE SURVEYOR SERIAL NO. SERIAL NO. _

RX POWER EFFICIENCY REVIEWE0 BACKCROUNO SMEAR RESULTS IN OPM/100cm2 B-BETA IN MRAD /HR/ID0 car POINT RESULTS A INDICATES ELECTPICAL DUTLET Aff AI N C-*/

Q NORTH >

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3. CONTACT 110SE RATES AT . IN gjg l 4. BETA DOSE RAFE IN MRAD /HR JNDtCA?ED JY A 'B'

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_ -__-_ _ = _ _ _ _ _ _

l l BRUNSWICK STEAM ELECTRIC PLANT SURVEY NO.

RADIOLOGICAL SURVEY RWP NO.

REACTOR BUILDING #2 '

l -I7' HPCI ROOM DATE TIME 0 7/F J DDSE RATE CONTAMINATION INST. TYPE INST. TYPE SURVEYOR SERIAL NO. SERIAL NO.

RX POWER EFFICIENCY l REVIEWED BACKGROUND l

l SMEAR RESULTS l

IN DPM/100 cme B-BETA IN MRAD /HR/100cm2 NORTH > POINT RESULTS A tt A- S g ed I

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todo #/de#

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i _

). SMEAR LOCATION CIRCLED

2. DOSE 3!TC AT LOCATIGN TAKEN IN mR/HR.

3. CONTACT DrJSE RATLS AT

• IN mfi/HR.

4. BETA CCSE RATE IN mRAO/HR IN0!r.ATED BY A *s'

,cc - a n a .. s . ~ ., a ..-

• ~

BSEP/CDi v!!!/ELRC-0100 l

I cftIfCZ w o'e 4 oI af r s 4/ d h .e l .

l

BRUNSWICK STEAM ELECTRIC PLANT SURVEY NO.

RWP ND.

RADIOLOGICAL SURVEY REACTOR BUILDING #2

-17' SOUTH R.H.R.

DATE T IME O y/ r- m.- COSE RATE CD'eTAMINAT]DN INST. TYPE INST. TYPE SURVEYOR SERIAL NO. SERIAL 140.

RX POWE ' EFFICIENCY .

REVIEWED BACKGROUND .

SHEAR RESULTS IN DPM/100 cme g

5-BETA IN MRAD /HR/100cm 2 POINT RESULTS All AI NN

\ A INDICATES ELECTRICAL DUTLET NORTH +

Q a CR0 runP A CRO PUMP O

Q R 1 3

.M "

A ed*~

EM Acor o y

m I _

Q'^

F70 00 '-

Yooo .__

\ ,j- -

RHRj y yovu { ..

j -

3000 y re o-e 1. SMEAR LDCATION CIRCLED

2. DOSE RA!F AT LOCATION TAKE'd tN mR/HR.

L I 3. CTnif e r.T DOSE M*.T E S A r * !N

~~ mR/HR.

4. OETA MSE RATE IN MRAD /HR IEDICATED B'I A *B*

BSE.P/VOL. V!!I/E&RC-DIDO

• M **Ja '

.s ra.dla di e n t's vel r ds. s Y" is o l' #.* e n oC x c. y e

BRUNSWICK STEAM ELECTRIC PLANT SURVEY ND.

RWP NO.

RADIOLOGICAL SURVEY -

REACTOR BUILDING #2

-17' SOUTH R.H.R.

DATE TIME 09## 2 DOSE RATE CONTAMINAT]DN INST. TYPE INST. TYPE SURVEYDR EERIAL ND. SERIAL NO.

RX POWER -EFFICIENCY REVIEWED BACKGROUND SMEAR RESULTS IN DPM/100cm8 B= BETA IN MRAD /HR/100cm2

\ POINT RESULTS Aff AI N '

a INDICATES ELECTRICAL OUTLET

_ NORTH >

1 l

e cRD Puner A CR0 Puter O

O.- x n

. . _ good e svoo AU*A - wo o

/T

._D<L. pa) ,

y -

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/s -.._-. --

3 3 pJ - -

7 o o' 3, to o ,

~

L SMEAR LOCATION CIRCLED

2. DOSE RATE AT LLCATION TAVI.N IN mR/HR.

I 3. CONTACT COSE RATES AT e !N

__ J mR/HR.

4 CETA D3;E 8 TATE 14 mRAWHR IUDICA1ED W A "B"

~

L' '

f R Ad* s f fe /sysdr o' n e e u .r e c/ e a- +o ** e- s lo e OC 4 C 2:.c ,

BRUNSWICK STEAM ELECTRIC PLANT SURVEY ND.

RADIOLOGICAL SURVEY RWP NQ.

REACTOR BUILDING #2 9* & 20* NORTH-AND SOUTH RHR ROOMS DATE TIME 07/0 W CDSE RATE CONTAMINAT!DN INST. TYPE INST. TYPE SURVEYDR SERIAL NO. SERIAL NO.

RX POWER EFFICIENCY REVIEWED BACMGROUND SMEAR RESULTS 2D* N.RHR 20* 5.RHR IN DPM/1DDema B+9 TA IN MRAD /HR/10Dem8 r , PDINT RESULTS A- t c.. As rea cJ o -

v W

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• E. Dost RATE AT LDCAT!aN TAl(EN JN mR/M.

[-.-. -

o-0 P-- .

1 C3ffACT Dost RATES AT

• IN

4. SETA 00$( RATE JN mR AC/>M

( NORTH gpeg]CAftg gy A *g*

• c w fJ dos.e en /e5 Jn +u ay .- ~ f. a - cf *****'""*C'*'* l 5 C '~ h ANA & .* f k cdayeae/oc/ ,= u r ( ,

BRUNSWICK STEAM ELECTRIC PL. ANT SURVEY ND.

RADIOLOGICAL SURVEY RWP ND.

REACTOR BUILDING #2 9' HPCI ROOF DATE TIME # 7/# } DDSE RATE CONTAMINATION INST. TYPE INST. TYPE SURVrf.YDR SERIAL ND. SERIAL NO.

RX POWER EFFICIENCY REVIEWED BACKCROUND

- A~~ -

o SMEAR RESULTS IN CPM /IDDem8 B= BETA IN MRAD /HR/1DDeme PDINT RESULTS HC $3 f"t a-c/

i )

0 /

• I 0

s u a 0

\

(f N

j Y

/

0 /

l

()

1

\*'0 Y/ h a l 0)

'I

1. SMEAR LDCATION CIRCLED

2. DCSE RATE AT LOCATION TAKEN D 1N mR/H4. i

3. CDNTACT DDSE RATES Af e IN mR/HR.

4. GETA DCSE RATE IN MRAD /HR INO]CATED GY A *B" BSEP/VOL. VIII/EERC-DICO

(**

L. - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

i 1989 ANNUAL EXERCISE I

Unit 1 i

Reactor Coolant Sample Results After Fuel Handling Accident Nuclide pei/mi Co-58 2.6 E"'

-0 Co-60 1.4 E

~

Cr-51 4.6 E

-I I-131 9.5 E Mn-54 2.4 E '

~0 Xe-131m 1.5 E

-5 Xe-133 4.2 E i

I 3

1

.i l

i L__ ----

4 1989 ANNUAL EXERCISE Unit 2 Reactor Coolant Sample Results After 0700 Nuclide ci/ml I-131 4.1 E+

I-132 1.4 E+

I-133 3.8 E+

I-134 2.2 E+

I-135 1.7 E+

Xe-133m 3.2 E+

Xe-133 4.5 E+

Xe-135m 9.9 E+

Xe-135 1.6 E+

~

Kr-85 2.3 E

~

Kr-87 6.6 E

~

Kr-88 7.1 E Cs-137 1.4 E+

Nb-95 4.9 E+

l l

l 1

l l

l 1

L-_ _ _ . - - _ __ __ _ _ _ _ _ _ _ _ _ _ _ _

l..

1989 ANNUAL EMERGENCY EXERCISE Radiation Readings For Unit 2 PASS Samples I. Reactor Coolant A. Small (diluted) vial - unshielded 40 mR/hr contact "as read" at I foot B. Small (diluted) vial - shielded 1 mR/hr contact "as read" at 1 foot C. Large (undiluted) vial - unshielded 1700 mR/hr contact 25 mR/hr at I foot D. Large (undiluted) vial - shielded 50 mR/hr contact "as read" at I foot II. PASS Panel Monitor Readings During Acquisition A. Area Monitor (RI-507) 10 mR/hr during reactor coolant sample B. Liquid Monitor (RI-665) 1700 mR/hr during reactor coolant flush NOTE: All other sample reading will be "as read" or normal.

h_,__u. .-____.- -___.--.2_.m-_-_--_m.a__-____m_ -_m.___.--__._..m____ _ . _ _ _ _ __m__-___--.____ ... ___-_.m-____.. __ __ _ , _ _ . _ ___ _m___-m__. - -.___-_m__--_.__.__.m.-_______..___m_._

x Yt1l k

. - -=+ y q - . - _- < - - ,, r a: g.m. ,y . .-

~ - n. g o. ,.r ., p o p.,.r _,q g._..g c,c.-

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.s r 2 _,6s.e, l'

l d,ra. ._ _; /J i4

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l

--. _.vr. _ a_.-. c. _6. . ] ;:.

1.

-" ur t. :+c ere: r ar i .n c f tne F1selon orec t..t c t s are:

n .wat Or satee m .u . . _ v .: . - .x .. ; / .1 J . 3 '. .n 9uctression Pool O.OOE+00 aci, ml w, 1,s , . . ~ . -

c 2n weactcr warer . G o ,.. + v c_ a em

's-137 2n Sucore=sicn pool O.OOE+00 >.C 1 / m i c:e-133 2n Drywei'. r-u r 0 . 0 0 '_~ - 0 0 ;Ci/cc a in -crus Hir Ae O. OUc+<>U n.,1 / c c l #, r' - fS 5 . " Dr}/We j 1 nip !1 X)E+OO U C,1/ ." C

'. r- e b in , crus 9.r O.OOE+00 uC /cc

'im wtween the eactor snurcown anc the samo.te : me :a -

.ud3~ cavs  !

i i

i

~No _encervative 7ie ,c a u . . values or- the inventory Lcrrection Factors were used.

Estimate of fuel /claccina camace himary Coolant AnalyS1E

.s4 ,,.,%,. uz.

. , _ i

. .e. - _c- ( .u ,m- i / a l ) ,

..cwadinc ruel i rallure Yeltdown

)

I

- . 31 3.04E+01 5.98 (1 -/ i C c-: 3"7 1.07E+01 6.89 (1 %

Cont ai nment Gas Ana tvsIE I

__ C;_ :DZ

.d _ _ _C A_IF<.uC

_ _ /_1_ _ _ _ _ _ _ _.s_/o -

,__accine - Fuel 6 . Fallure deltcOWW Xe-133 O.OOE+00 0.00 O.00 5 O.OOE+00 0.00 O.00 l

l 1

1

l.

i

i. ATTACHMENT I 1

l l

BRUNSWICK STEAM H.ECTRIC PIANT OPERATIONS ON-SHIFT DRILL SCENARIO Drill Type: Fire Brigade Drill Drill No.: FD-89-2-010 i

(

l i

Appreval: _ N /J , vg- Date: _3 -/O - 87 hanager'~geratpr.s/ Designee i l

BSEP/Vol. VII/0I-36 13 Rev. 3 l s I w______-.________________. _ _ _ - _ _

l DRlLL NUMBER FD-89-2-010 l ATTACIDiENT 1 (Cont'd) 1-DRlLL SCENARIO DATA SHEET l

l Date May 23, 1989 Time of Initiation Unit Number 2 Location South RHR Room -17' El.

Initial Condition:

Simulated Unit 1 100% Power / Unit 2 100% Power Shift Number NS-4/RS-3 Shift Foreman David Savage SOS Dick Labelle l

Type of Drill Announced X Unannounced Off-Site Fire Department Yes X No Department Southport Fire Department Brief Description An oil fire will be simulated in the B RHR pump in the Unit 2 Reactor Building. This scenario will be performed concurrently with the plant annual emergency exercise and will be used to evaluate Control Room and Fire Brigade responses. This drill will also serve to comply with commitments for off-site fire department participation in plant fire emergency exercise.

1 BSEP/Vol. Vll/01-36 14 Rev. 4 i

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DRILL NUMBER FD-89-2-010 l ATTACHMENT I (Cont'd)

DRILL SCENARIO DATA SHEET Training Objectives

1. The Control Room will acknowledge annunciator UA-26, window 3-8.

An Auxiliary Operator will be dispatched to investigate the alarm i 2. within one minute after detector alarm initiation.

The investigating Auxiliary Operator will report the fire to the

3. -Control Room within six minutes after detector alarm initiation.

The plant fire alarm will be sounded within seven minutes after

4. detector alarm initiation. '

The plant fire brigade will assemble at the designated muster point

5. within fourteen minutes after detector alarm initiation, or within* I The Control Room will ref erence and f ollow procedures FFP-013, ASSD-00,

6. ASSD-01, and 2-ASSD-06.

Utilizing Pre-fire Plan RB2-1-D, the Shifr Fire Commander will organize

7. and implement a plan of attack on the fire and will protect exposures.

The Shift Fire Commander will request the assistance of the Southport

8. Fire Department, and will demonstrate his ability to control and*

The plant fire brigade and the Southport Fire Department will demonstrate

9. their abilities to operate firefighting equipment, protect exposures.*

The Shift Fire Commander will assess damage to the fire area and will

10. report this information to the Control Room within 59 minutes from*

Means of Initiation Fire detection pull station RX3-5 will be operated to initiate this drill.

Expected Alarms

1. Annunciator UA-26, 3-8 3.

See attached annual emergency

2. message cards. 4. q

{

Applicable Prefire, Plans I

I

Prefire Plan  :

Number  : Title {

Reactor Building South RHR Room -17' El.  !

1.  : RB2-1-D  : Pre-Fire Plan l

2.  :  :

• Training Objectives continued on Page 15a.

BSEP/Vol. VII/01-36 15 Rev. 4 l

l l

DRILL NUMBER FD-89-2-010 Traininn Obiectives (Continued)

5. seven minutes after the plant fire alarm sounds.

coordinate their activities in conjunction with those of the plant fire

8. brigade.

9. and extinguish the fire.

10. detector alarm initiation.

i

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I f

15a

DRILL NUMBER FD-89-2-010 l ATTACHMENT I (Cont'd) ,

DRILL SCENARIO DATA SHEET ,

l Applicable Operating or Emergency Procedures j

Procedure  :

Number  : Title

1.  : PFP-013  : Plant Site General Fire Plan Alternative Safe Shutdown Procedure

2.  : ASSD-00  : User's Guide

3.  : ASSD-01  : Alternative Safe Shutdown Procedure Index Alternative Safe Shutdown Reactor ,

4.  : ASSD-06  : Building South Expected Response - Brief Description

1. Control Room The Control Room will acknowledge the alarm initiating this drill, will reference and follow applicable operating and emergency procedures, and vill provide appropriate support to the fire brigade.

1. Fire Ground The fire brigade will demonstrate their ability to rapidly respond to the fire scene, protect exposures, and work effectively with the Southport Fire Department to control and extinguish the fire.

Special Tools and Equipment

1. Area hose stations

2. Portable fire extinguishers 1

3. AFFF (optional) 1 I

4.

BSEP/Vol. VII/01-36 16 Rev. 4 s

1

- --_-_____.-__A

DRILL NUMBER FD-89-2-010 ATTACHMENT I (Cont'd)

DRILL SCENARIO DATA SHEET Vital Equipment to be Protected

1. 2C RHR Pump

2. Division I and II cabling

3. HPCI Room Precautions Personnel will not use portable radios in the Unit 2 Reactor Building, and hose lines will not be charged with water.

Equipment / Systems Which Should be Energized None i

l Automatic Fire Suppression in the Area

1. South RHR Room sprinkler system 2.

Special Conditions / Risks Personnel providing escort service for Southport Fire Department firefighters will follow all HP and Security regulations.

.i i

1 l

I BSEP/Vol. VII/0I-30 17 Rev. 4 1

- _ - _ _ _ _ _ - _ _ _ - _ _ _ _ _ - - - _ - _ _ _ _ _ _ _ _ - _ _ _ _ . __ _ _ _ _ ~

DRILL NLHBER FD-89-2-010 ATTACHMENT I (Cont'd)

DRILL SCENARIO DATA SHEET On-Fhift Drill Evaluators and Assignments Assignment ,

1. Control Room Monitors - 2

2. Shif t Fire Comnander Monitor

3. Fire Brigade Drill Monitors - 3 4.

-)

5.

6.

Special Instructions Southport Fire Department hose and equipment must be used and connected to the Reactor Building standpipe system to verify equipment compatibility.

Criteria for Terminating the Drill This drill will be tern'.nated upon successful completion of the training objectives, or irr.ediately terminated if a condition exists which threatens the safety of plant personnel or equipment, j

. Other:

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BSEP/Vol. VII/01-36 18 Rev. 4 l

1 E__ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _.

j

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DRILL NDSER FD-89-2-020 ATTACHMENT I (Cont'd)

DRILL SCENARIO DATA SHEET Prepared By Terry Sa rner Date 02-15-89 NOTE: The contents of this drill scenario is privileged information and l shall not be divulged to any unapproved personnel.

Reviewed By e .[ Date ,;2[// f Real-Time Training Supervisor Reviewed By a t / Date ff04k Fire Protect /lon Supervisor Approval . [ 4 I nf,,,of4/ Date 3 /J/[/7 Principal Engineer - Operations Concurrence M8 M Security Date A//f/[f Notified (Qhw . di, Date 2_!/~/ Ph Operations - QA (

Concurrence 0 w Date 2 - t>fy sy Site Nuclear Safety BSEP/Vol. VII/01-36 19 Rev. 4

ATTACHMENT I (Cont'd)

DRILL NUMBER FD-89-2-010 I l

FIRE DRILL EVALUATION DATA SHEET NOTE: This Data Sheet is required for evaluation of fire drills only.

Date 05/23/89 Unit 2 Location South RHR Room -17' El. j Plant Condition Simulated: Unit 1 100% Power / Unit 2 100% Power Shift Shift Number NS-4/RS-3 Foreman David Savage SOS Dick Labelle Shift Fire Commander Drill Response

1. Time drill was initiated

2. Elapsed time from initiation to dispatching A0 Minutes

3. Elapsed time from initiation until A0 reports fire to Control Room 4 Elapsed time from initiation to general fire alarm Minutes

5. Elapsed time from initiation full brigade on fire ground ,_

Minutes Fire Alar = Asseusment SAT ___ UNSAT BSEP/Vol. Vil/01-36 20 Rev. 4 l

l DRILL NUMBER FD-89-2-010 ATTACHMENT I (Cont'd) l DRILL EVALUATION DATA SHEET l

l Training Objectives SAT /UNSAT l

The Control Room will acknowledge annunciator UA-26,

1. window 3-8.

Auxiliary Operator will be dispatched to investigate the l 2. alarm within one minute after detector alarm initiation

• l The investigating Auxiliary Operator will report the fire

3. to the Control Room within rix minutes after*

The plant fire alarm will be sounded within seven minutes l 4. after detector alarm initiation.

l The plant fire brigade will assemble at the designated

5. muster point within fourteen minutes after detector

• The Control Room will reference and follow procedures

6. PFP-013. ASSD-00 ASSD-01, and 2-ASSD-06.

Utilizing Pre-fire Plan RB2-1-D, the Shift Fire Commander

7. will organize and implement a plan of attack on the fire

• The Shift Fire Commander will request the assistance of

8. the Southport Fire Department, and will demonstrate his*

The plant fire brigade and the Southport Fire Department

9. will demonstrate their abilities to operate firefighting*

The Shift Fire Commander will assess damage to the fire

10. area and will report this information to the Control Room

• P,ercentage of Satisfactory Drill Objectives  %

Training Objectives Comments Equipnent Restored (As Appropriate)

Equipment Used During Drill Initial

i. , ,

1.

2. 2.

3. 3.

4. 4.

5. 5.

BSEP/Vol. VII/01-36 21 Rev. 4

DRILL NUMBER FD-89-2-010 Training Objectives (Continued) l 3.- detector alarm initiation.

5. alarm initiation, or within seven minutes after plant fire alarm sounds.

7. and will protect exposures. ~

ability to control and coordinate their activities in conjunction with

8. those of the plant fire brigade.

9. equipment, protect exposures, and extinguish the fire.

10. within 59 minutes from detector alarm initiation.

O b

21a

DRILL NUMBER FD-89-2-010 ATTACHMENT I (Cont'd)

DRILL EVALUATION DATA SHEET Fire Brigade / Drill Participant Evaluation Position  : Name  : Sat  : Unsat~~~

1. Unit 1 Shiit Foreman  :  :  :

2. Unit 1 Control Operator  :  :  :

3. Unit 2 Shift Foreman  :  :  :

4 Unit 2 Control Operator  :  :  :

5. Drill Participant  :  :  :

6. Drill Participant  :  :  :

7. Drill Participant  :  :  :

8. Drill Participant  :  :  :

9. Drill Participant  :  :  :

10. Drill Participant  :  :  :

11. Drill Participant  :  :  :

12. Drill Participant  :  :  :

13. Drill Participant  :  :  :

14. Drill Participant  :  :  :

15. Drill Participant  :  :  :

Recommended Remedial Action 4

BSEP/Vol. VII/01-36 2? Rev. 4

DRILL NUMBER FD-89-2-010 1

ATTACHMENT I (Cont'd)

DRILL EVALUATION DATA SHEET Recommended Remedial Action (Cont'd) l

... ~

_ _ _ . , _ _ . _ . _ _ . _ _ _ _ _ _ . l

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i BSEP/Vol. VII/01-36 23 Rev. 4

l

! ATTACHMENT I (Cont'd)

ON SHIFT DRILL NO. FD-89-2-010 DRILL EVALUATION DATA SHEET

, The above drill has been evaluated and determined to be l satisfactory / unsatisfactory.

l l Signature  : Position  : Date

1.  : Drill Specialist  :

2.  : Evaluation  :

3.  : Evaluation  : .-

4,  : Evaluation  :

5.  : Evaluation  :

Fire Support

6.  : Supervisor  :

Principal Engineer -

7.  : Operations  :

1 m

BSEP/Vol. VII/01-36 24 Rev. 3

DRILL NUMBER FD-89-2-010 ATTACHMENT I (Cont'd) I FIRE DRILL EVALUATION DATA SHEET NOTE: This Data Sheet is required for evaluation of fire drills only.

REQUIREMENTS / CRITERIA  : SAT  : UNSAT 80% of the training objectives have been met.  :  :

Alarms were responded to as evidenced by proper use of annunciator procedures.  :  :

General fire alarms were sounded in accordance with operating procedure.  :  :

The Fire Brigade responded to the fire alarm and announcements with proper equipment and turnout gear, and assembled at the simulated  :  :

fire location within 14 minutes from the time l the alarm came into the Control Room.

Prefire plans / procedures were properly utilized.  :  :

Drill participants demonstrated adequate knowledge and simulated the use, placement, and operation  :  :

af the eculpment required.

The Control Room operators demonstrated satisfactory response to the simulated emergency by utilizing correct operating and  :  :

emercenev procedures.

The Fire Brigade / Drill Participants and Control Room established effective communications. :  :

The Fire Brigade responded to the simulated fire scenario in a manner which would have, I under actuni conditions, controlled and extinguished the fire.  :  : ,

The drill participants demonstrated satisf actory '

plant knowledge and identified and protected vital equipment in the fire ground / drill scene i area needed for safe shutdown of the plant.  : ,

The drill was carried out in a man:mr which I did not cause bedily injury to Fire Brigade  :  : j ei other associated personnel. {

l Other Requirements / Criteria _,,

BSEP/Vol . VII/0I-36 25 Rev. 4 1 l

l 1

DR1LL NLHBER FD-89-l'-010 i 1.TTACEMENT I (Cont'd) i?OSTDRILL CRITIQUE SREET u  !

Dat.<. of Critique _ Lacation of Drill S. RHRJ o_om -17' El. Unit 2

.,- Dat:e of Drill 0$/23/89 Time of Drill ,

l Fize Egigade/ Drill Participants Attend _ing, 1- . _ .

2. ,

s

- 4- .,

S- . ._

6.

'. 7. . _ . .

8. -

9. _. -

r .

10. 11. 12. _ ._,,

13 14. 15. .,_ _ _ _ _ , .

Drill Evaluaters Attend h  ;

1. 2. 3.

4. 5. 6.

Training Obiectives Discussed

. - =_ .--

m.

._. . _, _ =-

BSEP/Vol. V11/01-36 26 Rev. 4

DRILL NLHBER FD-84-2-010

//rTACHMENT I (Cont'd)

POSTDR7LL CRITIQUE SHEET Unsatisfactory Perfcmance , Discussed HM 4 1

Evaluation of Pr.efire Plans /Procedur es Used by YanicJpants

_ _ _ . . _ ~ - _ _. .

Reswdial Actions Liscussed

.= -. - - -  :.

L ,

Chances to Prefire Plans 9ecair_ed Yes No

,Q ances to Operatiue Piecedures Recuired Yes _

No t

Drill Specialist Date FOTE: Forward copy to 1. Real-Time Training

2. Prinedpal Engineet - Operations l

t BSLP/Vol. VIX/01-36 27 Rev. 4

._ .-. _ .__ _ __ __ _d

ATTACHMENT I (Cont'd)

DRILL NUMBER N/A DRILL EVALUATOR WORK SHEET NOTE: This form is not required for use in fire brigade drills.

Date Unit Plant Condition Simulated Unit 1 / Unit 2 Shift Shift Number Foreman S O S ._. -.

Drill Response s 1. Time drill was initiated:

1

2. Initiating event:

3. Shulated Symptoms:

a. f.

,b .

'_~' g.

t c. h.

d. i.

c. j.

4. Simulated Automatic Actions:

a.

D.

c.

d. _

5, Operar.or Actions: SAT /UNSAT a, ,,,,_,,,,,,,, ,

b. __ _ _ , _ _ _ _ , , ,

c. . . . - ,_ -

E S- . __

h- _. __ - -

i~ - _ - -

.i - _, .

1 ESEP/Vol. VII/07-36 28 Rei. 4 t

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l

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ATTACHMENT I (Cont'd) i DRILL NUMBER N /A DRILL EVALUATOR WORK SHEET (Cont'd)

NOTE: This form is not required for use in fire brigade drills. I

6. Simulated Supplementary Actions: SAT /UNSAT a.

b. -

c.

d.

e. _

7. Recovery Procedure: SAT /UNSAT R.

b. _ , _ ,

c. . - -

e. _,

8.0 Other Criteria: SAT /UNSAT f

amespumag Comments: , , , _ .

Drilf EEaluator Signature BSEP/Vol. v11/OI+36 29 Rev. 4

DRILL NUMBER FD-89-2-010 l ATTACIDiENT I (Cont'd)

DRILL EVALUATOR WORKSHEET Date 05/23/89 Assignment Control Room Monitor Evaluator Watch Synchronized ,

Training Objectives to be Observed SAT /UNSAT The Control Room will acknowledge annunciator UA-26,

1. window 3-8. j An Auxiliary Operator will be dispatched to investigate the

2. alarm within one ninute after detector alarm initiation.

The investigating Auxiliary Operator will report the fire'to

3. the Control Room within six minutes after detector alarm

• The plant itre alarm will be sounded within seven minutes

4. after detector alarm initiation.

The Control Room will reference and follaw procedures PFP-013,

5. ASSD-00, ASSD-01, ar.d 2-ASSD-06.

Pre-Fire Plans or Procedures Used Number Title SAT /UNSAT

1. ,

2. __ - _ _

3. , _ _ .

4. _

Time of Initiation Planned _ Actual First Response Type _

Tine _ _ __

l j Time General Fire Alarm SoundeA _ ,

SN1 or UNSAT

• Continued on page 30a.

BSEP/Vol. VII/OI-36 30 Rev. 4

(

DRILL NUMBER FD-89-2-010 Training Objectives (Continued)

3. initiation.

I I

i f 1

30a

_. 1 --- _ - _____-_-

DRILL NLHBER FD-89-2-010 ATTACHMENT I (Cont'd)

DRILL EVALUATOR WORKSHEET Drill Participants Shift Fire Commander N/A Time N/A

Time  : Name  : Time  : Name 1,  :  : 6.  :

2.  :  : 7.  :  :

3.  :  : B.  :  :

4.  : -

9.  :  :

5.  : _.

10.  :  : _,

Chronological Sequence of Events

Time  : Event Description f

1.  :  : _

2.  :  :

3.  :  :

4  :  : _. _, . )

i

5.  :  : , , .

6.  :  :

7.  :  : . . - - .

8.  :  :

i 9- .

1 i

i BSEP/Vol. VII/01-36 31 Rev. 4 l l

-._____n. _ _ - - _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ - - __ . . _ - - _ . - -

DRILL NUMBER FD-89-2-010 ATTACHMENT I (Cont'd)

DRILL EVALUATOR WORKSHEET Chronological Sequence of Events

Time  : Event Description

10.  :  :

11.  :  :

l l

12.  : -

13.  :  :

14. -

15.  :  :

16.  :  :

,17 .  :  : .

18. -

19.  :  :

20. -

,1. . .

\

22.  : _

23. -

_2_4. . : . _ _ .

25.  :

26.  :  : ._

_2 7... - -

28.  : ._ .  : .._.

29.  :  : .-

30.  :  :

BSEP/WI. VII/01-36 32 Rev. 4

i DRILL NUMBER _ FD-89-2-010 ATTACHMENT I (Cont'd),

DRILL EVALUATOR WORKSHEET Special Tools or Ecuipment Used Description SAT /UNSAT 1.

2.

3.

4.

Fire Ground / Drill Scene Evaluation ( X N/A)

Control Room Evaluation ( N/A)

Prefire Plan / Procedures Evaluation (Sat Unsat )

General Coments/Recomended Renedial Action l -

Drill Evaluator Date BSEP/Vol. VII/01-36 33 Rev. 4 l

L _ - _ - _ _ - - _ _ _ _ l

DR1LL NUMBER FD- 3 9-2-010 ATTACHMENT 1 (Cont'd)

DRILL EVALUATOR WORKSHEET l

Date 05/23/89 Assignment Shift Fire Commander Monitor Evaluator Watch Synchronized Training Objectives to be Observed SAT /UNSAT The plant fire brigade will assemble at the designated muster

1. point within fourteen minutes after detector alarm initiation

• Utilizing pre-fire plan RB2-1-D, the Shift Fire Commander will

2. organize and implement a plan of attack on the fire and will*

The Shift Fire Commander will request the assistance of the

3. Southport Fire Department, and will demonstrate his ability

• The plant fire brigade and the Southport Fire Department will

4. demonstrate their abilities to operate firefighting equipment.*

The Shift Fire Commander will assess damage to the fire area

5. and will report this information to the Control Room within*

Pre-Fire Plans or Procedures Used Number Title SAT /UNSAT 1.

2.

3.

4.

Time of Initiation Planned Actual First Response Type  !

Time Time General Fire Alarm Sounded SAT or UNSAT

• Continued on pag 30a.

BSEP/Vol. VII/0I-36 30 Rev. 4

l' i 1

i DRILL NUMBER _ FD-89-2-010 Training Objectives (Continued)

1. or within seven minutes after the plant fire alarm sounds.

2. protect exposures. l to control and coordinate their activities in conjunction with those

3. of the plant fire brigade. ,

j

4. protect exposures, and extinguish the fire.

5. 59 minutes from detector alarm initiation.

I 30a

l DRILL NUMBER FD-89-2-010 ATTACHMENT I (Cont'd)

DRILL EVALUATOR WORKSHEET Drill Participants l- Shitt Fire Commander N/A Time N/A

Time  : Name  : Time  : Name

1.  :  : 6.  :  :

2.  :  : 7.  :  :

1

3.  :  : 8.  :  :

4.  :  : 9.  :  :

5.  :  : 10.  :  :

Chronological Secuence of Events

Time  : Event Description

1.  :  :

2.  :  :

3.  :  :

4.  :  :

5.  :  :

6.  :  :

7.  :  :

8.  :  :

9.  :  :

BSEP/Vol. VII/DI-36 31 Rev. 4 l

DRILL NLYBER TD-89-2-010 ATTACHMENT I (Cont'd)

DRILL EVALUATOR WORKSHEET Chronological Sequence of Events

Time  : Event Description

10.  :  :

11.  :  :

12.  :  :

13.  :  :

14.  :  :

15.  :  :

16.  :  :

17.  :  :

18.  :  :

19.  :  :

20.  : -

21.  :  :

22.  :  :

23.  :  :

24.  :  :

25.  :  :

26.  : *

27.  :  :

28.  :  :

29.  :  :

30.  :  :

I I

BSEP/Vol. VII/OI-36 32 Rev. 4 t

I

- - - - - - - - - _ _ __________J

DRILL NUMBER FD-89-2-010 ATTACHMENT I (Cont'd)

DRILL EVALUATOR WORKSHEET j Special Tools or Equipment Used Description SAT /UNSAT 1.

2.

3.

4 Fire Ground / Drill Scene Evaluation ( N/A) l Control Room Evaluation ( X N/A) l l

Prefire Plan / Procedures Evaluation (Sat Unsat )

General Comments / Recommended Remedial Action Drill Evaluator Date BSEP/Vol. VII/0I-36 33 Rev. 4

DRILL NUMBER FD-89-2-010 ATTACHMENT I (Cont'd)

DRILL EVALUATOR WORKSHEET Date 05/23/89 Assignment Fire Commander Monitor Evaluator Watch Synchronized Training Objectives to be Observed SA'I/UNSAT-The plant fire brigade will assemble at the designated muster

1. point within fourteen minutes after detector alarm initiation

• The plant fire brigade and the Southport Fire Department will

2. demonstrate their abilities to operate firefighting equipment,*

3.

4, 5.

Pre-Fire Plans cr Procedures Used Number Title SAT /UNSAT 1.

2.

3.

4.

Time of Initiation Planned Actual First Response Type Time l

Time General Fire Alarm Sounded SAT or UNSAT

• Continued on page 30a.

BSEP/Vol. VII/01-36 30 Rev. 4

l l

DRILL NUMBER FD-89-2-olo Training Objectives (Continued)

1. or within seven minutes after the plant fire alarm sounds.

4. protect exposures, and extinguish the fire, s

I l

l

)

l 30a

DRILL NUMBER FD-89-2-010 ATTACHMENT I (Cont'd)

DRILL EVALUATOR WORKSHEET Drill Participants i'

Shift Fire Commander N/A Time N/A

Time  : Name  : Time  : Name

1.  :  : 6.  :  :

2.  :  : 7.  :  :

3.  :  : 8.  :  :

4.  :  : 9.  :  :

5.  :  : 10.  :  :

Chronological Sequence of Events

Time  : Event Description

1.  :  :

2.  :  :

3.  :  :

4.  :  :

5.  :  :

6.  :  :

7.  :  :

i

8.  :  :

9.  :  :

l BSEP/Vol. VII/01-36 31 Rev. 4

DRILL NMBER FD-89-2-010 ATTACHMENT I (Cont'd)

DRILL EVALUATOR k'ORKSHEET Chronological Sequence of Events

Time  : Event Description

10.  :  :

11.  :  :

12.  :  :

13.  :  :

14.  :  :

15.  :  :

16.  :  :

17.  :  :

18.  :  :

19.  :  :

20.  :  :

21.  :  :

22.  :  :

23. -  :

24.  :  :

25.  :  :

26.  :  :

27.  :  :

28.  :  :

i

29.  :  :

(  :

30.  :

BSEP/Vol. VII/0I-36 32 Rev. 4

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