ML18038A329

Rev 1 to Scenario 19, Nine Mile Point Nuclear Station Unit 2 Emergency Preparedness 1990 Annual Exercise.

ML18038A329
Person / Time
Site:	Nine Mile Point
Issue date:	09/24/1990
From:	Andrews J, Peifer M, Salemi A NIAGARA MOHAWK POWER CORP.
To:
References
NUDOCS 9010160254
Download: ML18038A329 (499)

Text

ACCELERATED DIST. BUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9010160254 DOC.DATE: 90/09/24 NOTARIZED: NO DOCKET FACIL:50-410 Nine Mile Point Nuclear Station, Unit 2, Niagara Moha 050004 AUTH. NAME AUTHOR AFFILIATION ANDREWS,J.L. Niagara Mohawk Power Corp.

SALEMI,A.M. Niagara Mohawk Power Corp.

PEIFER,M.A. Niagara Mohawk Power Corp.

RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

Rev 1 to Scenario 19, "Nine Mile Point Nuclear Station Unit 2 Emergency Preparedness 1990 Annual Exercise."

DISTRIBUTION CODE.. DFOID TITLE: Direct Flow COPIES RECEIVED.LTR Distribution: 50 Docket (PDR g Avail)$

ENCL SIZE..GO NOTES RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL INTERNAL: NUDOCS-ABSTRACT LE 0 EXTERNAL: NRC PDR NSIC NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE iVASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR ~ ENCL 4

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EMERGENCY PREPAREDNESS EXERCISE SCENARIO N9 1990 ANNUAL EXERCISE

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NINE MILE POINT NUCLEAR STATION UNIT ¹2 SCOPE OF THE EMERGENCY PREPAREDNESS EXERCISE TO BE CONDUCTED ON OCTOBER 2, 1990

1. Classification and Notification.

2. Inplant Radiological Monitoring.

3. On-Site and Off-Site Radiological Monitoring

4. Post Accident Sampling.

5. Rad/Dose Assessment, and Protective Action Recommendations.

6. Emergency Response Facilities Staffing and Activation.

7. Damage Control Response.

8. Corporate Support.

9. Oswego County Participation (Partial).

10. New York State Participation (Partial).

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Efi NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT UNIT NO. 2 1990 ANNUAL EXERCISE SCENARIO 19, REV. 1

'Submitted.~by:

J.. Andrews, Drill Coordinator 'ate

-.. APPROVALS

A. M...Salemi, Manager Emergency Preparedness Date M. A. Peifer, anager Nuclear Services Date

• K. A. Dahlberg, S ation Superintendent NMPNS Unit 1 Date O

• R. B. Abbott, Station Superintendent NMPNS Unit 2 Date

• J. F~Firlit,'ice President - Nuclear Generation Date

• These signatures denote Niagara Mohawk Power Corporations approval to commit appropriate resources to perform this Emergency Preparedness Exercise. Since these individuals may be exercise players, they have not been allowed to view the material contained in this scenario.

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NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT UNIT NO. 2 1990 ANNUAL EXERCISE SCENARIO 19, Rev. 1 VOLUME I TABLE OF CONTENTS SECTION TITLE PAGE 1 0

~ Obj ectives

1. 1 Obj ectives 1-1 1.2 Previously Identified Deficiencies/Areas 1-6 Requiring Improvement 2.0 Drill Schedule and Participating Organizations 2-1 3.0 Scenario Events 3.1 Simulated Events 3-1 3.2 Actual Events 3-2 4.0 Reports 4-1 5.0 Exercise Instructions 5.1 Observer/Controller Instructions 5.1-1 5.2 Pre-Exercise Control Room Briefing 5.2-1 5.3 Evaluation Packages 5.3-1 6.0 Scenario Assumptions 6-1 7.0 Scenario Summary and Timeline 7.1 Narrative Summary 7.1-1 7.2 Event Timeline 7.2-1 7.3 Supplemental Scenarios 7.3-1 8.0 Drill Messages 8.1 Control and Contingency Message Summary 8.1-1 8.2 Rumor Control, Media Inquiry Calls and NRC Message Summary 8.2-1 9.0 In-Plane Data Tables 9.1 Operational Data 9.1.1 Plant Parameter Data 9.1-1 9.1.2 Plant Equipment Status 9.1-5

NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT UNIT NO. 2 1990 ANNUAL EXERCISE SCENARIO 19, Rev. 1 VOLUME I TABLE OF CONTENTS (continued)

SECTION TITLE PAGE 9.2 DRMS Data 9.2.1 Area Radiation Monitors 9.2-1 9.2.2 Continuous Air Monitors 9.2-7 9.2.3 Process Radiation Monitors 9.2-12 9.2.4 Monitor Information 2 Days Later 9.2-22 10.0 Radiological and Meteorological Data 10.1 Meteorological Data 10.1-1 10.2 Radiological Sample Data 10.2-1 10.3 In-Plant Radiological Data 10.3-1 10.4 Radiological Release Data 10.4-1

0-NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT UNIT NO. 2 1990 ANNUAL EXERCISE SCENARIO 19, Rev. 1 SYNOPSIS OF CHANGES BETWEEN REV.O AND REV. 1 Cover Sheet o Change in Nuclear Support Approval Sections 1 thru 4 o No changes Section 5.1 o Minor typographic corrections Section 5.2 o No changes Section 5.3 o , No changes Section 6 o Minor typographic corrections Section 7.1 o Editorial changes Section 7.2 o Addition of clock time o Minor correction to reflect 8.1 timeline Section 7.3 o Minor typographical corrections o Addition of clock time o Correction of references to reflect message numbering changes o Addition of PASS sample dose rates Section 8.1 o Addition of clock time o Additional indications for messages OC-5, OC-6, OC-8 o Addition of contingency message OC-7C and DC-2C o Change OC-15 (from Rev. 0) to DR-1 o Renumbering of messages Section 8.2.1 o No change Section 8.2.2 o No change Section 8.2.3 o No change Section 8.2.4 o Addition of clock time Section 9.1.1 o Change Reactor level to OSH starting Q 05:05 o Change RHR C flow to .75 starting Q 05:15 o Change LPCS flow to 0 starting Q 05:05 Section 9.1.2 o Change LPCS status to I starting Q 01:10

NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT UNIT NO. 2 1990 ANNUAL EXERCISE SCENARIO 19, Rev. 1 SYNOPSIS OF CHANGES 'BETWEEN REV 0 AND REV 1 (Continued)

Section 9.2.1 o Addition of clock time Section 9.2.2 o Addition of clock time.

Section 9.2.3 o Addition of clock time Section 9.2.4 o No changes Section 10.1 o Addition of clock time o Addition of 06:00 met forecast o Change met forecasts from EDT to EST per NMPC comments Section 10.2 o Addition of clock time Section 10.3 o No changes Section 10.4 o Addition of clock time

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 1.0 OBJECTIVES

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 1.0 OBJECTIVES This exercise scenario is designed to satisfy the requirement to conduct an annual NRC observed exercise in accordance with 10CFR Part 50, Appendix E.

This Section contains the objectives which Niagara Mohawk Power Corporation (NMPC) will demonstrate during the conduct of this exercise.

A. Radiolo ical Emer enc Pre aredness Plan and Im lementin Procedures

1. Evaluate the adequacy and implementation of radiological emergency preparedness plans and implementing procedures for Nine Mile Point Nuclear Station.

2. Demonstrate the adequacy of emergency response capabilities of NMPNS.

3. Demonstrate the capability of NMPNS to implement its radiological emergency preparedness plan in a manner that would provide adequate protective measures for the health and safety of the public.

B. Notification Procedures

1. Demonstrate the capability of NMPNS to communicate with the Nuclear Regulatory Commission via the NRC Emergency Notification System (ENS) hot-line and Health Physics Network (HPN) line.

2. Demonstrate the capability of NMPNS to notify and activate emergency response personnel in accordance with established emergency response procedures.

3. Demonstrate, as appropriate, the capability of NMPNS to notify Federal, State and Local agencies in accordance with established emergency response procedures.

Emer enc Communication

1. Demonstrate that adequate NMPNS voice and data communications capabilities exist among the Unit 2 Control Room, Technical Support Center (TSC), Emergency Operations Facility (EOF),

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Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 Operations Support Center (OSC), Corporate Emergency Operations Center and the Joint News Center (JNC); and the ability to maintain communications with governmental agencies as appropriate.

2. Demonstrate the ability to alert station personnel of emergency conditions by the use of emergency alarms and/or announcements.

3. Demonstrate the ability of NMPNS to coordinate, control, and deploy radiological field monitoring teams and damage control teams via its field communications systems.

4. Demonstrate the adequate coordination of/and communication with Nine Mile Point Nuclear Station radiological monitoring and damage control teams.

5. Demonstrate that adequate emergency communications systems are in place to allow for efficient transmittal of data among and between emergency response facilities.

MPNS Emer enc Res onse Facilities

1. Demonstrate the activation, adequacy of staffing, equipment and set-up as appropriate of emergency response facilities, as well as the adequacy of space and habitability for radiological emergency management at:

NMPNS Control Room (Unit No. 2),

NMPNS Technical Support Center, NMPNS Operations Support Center, NMPNS Emergency Operations Facility, Joint News Center, and Corporate Emergency Operations Center.

NOTE: The Joint News Center will be prestaged.

2. Demonstrate access control and security, as stated in procedures, at appropriate emergency response facilities.

3. Demonstrate the ability to maintain proper documentation and record control (i.e., status boards, logs and forms).

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Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 E. Direction and Control

1. Demonstrate the ability of key emergency personnel to initiate, coordinate, and make decisions in a timely manner during a radiological emergency and clearly demonstrate the incident command concept.

2. Demonstrate the existence of (1) organizational direction and control and (2) an integrated radiological emergency'esponse which includes deployment of field monitoring teams, and acquisition, receipt, and analysis of field data for evaluation and verification.

F. Public Information

1. Demonstrate adequate staffing of the Joint News Center by NMPC public information personnel and other NMPC personnel.

2. Demonstrate the ability of Joint News Center personnel to address rumors and issue periodic'ublic information releases.

3. Demonstrate that NMPC can provide technical, radiological and other appropriate information to the media.

4. Demonstrate the ability of NMPC to issue communications as requested to the investment community.

5. Demonstrate the ability of NMPC to disseminate communications to NMPC employees.

6. Demonstrate the timely issuance of news releases.

G. Accident Assessment and Evaluation

1. Demonstrate the ability of NMPNS staff to classify emergency situations in accordance wi,th established emergency response procedures.

2. Demonstrate the adequacy of activation, operation, and the reporting of results of the NMPNS field monitoring teams.

3. Demonstrate the ability of the Radiological and/or Dose Assessment Groups to adequately receive and assess radiological data from field teams.

4. Demonstrate the ability of the Radiological and/or Dose Assessment Groups to calculate dose projections.

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Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1

5. Demonstrate the ability of NMPNS personnel to recognize degrading plant conditions and provide appropriate assessment and response.

H. Protective Response

1. Demonstrate the decision making process of NMPC to recommend appropriate protective actions.

I. Radiolo ical Ex osure Control

1. Demonstrate the decision process for limiting exposures to emergency workers.

2. Demonstrate the record keeping of radiation exposures and use of dosimetry for emergency workers.

3. Demonstrate emergency workers knowledge of dosimetry and protective equipment.

4. Demonstrate assessment of TSC, OSC, EOF, Control Room, and JNC habitability.

J. Post Accident Samolin System

1. Demonstrate the ability to implement Post Accident Sampling System procedures.

K. Dama e Control

1. Demonstrate the decision making process leading to appropriate inplant damage control actions.

2. Demonstrate the capability of NMPC damage control teams to locate and obtain the materials required to effect repairs to postulated equipment failures in a timely manner.

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 L. R~ecover

1. Demonstrate the ability of NMPC emergency response personnel to terminate the emergency in accordance with established emergency response procedure.

M. Emer enc Pre aredness Trainin

1. Demonstrate the ability of NMPNS to perform an adequate self-critique of its performance during the exercise.

Also, to identify areas in need of improvement as a result of the exercise.

2. Provide training and test Niagara Mohawk Power Corporation emergency response personnel in their respective emergency functions through active participation in this drill.

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Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 1.2 Previousl Identified Deficiencies Areas Re uirin Im rovement

1. Demonstrate that TSC Radiation Monitor status boards in TSC have capability to trend radiological parameters.

(NCTS-003238-04)

2. Demonstrate that Control Room Communications Staff is adequate and can perform their notification responsibilities. (NCTS-503465-04)

3. Demonstrate that core damage estimates can be performed accurately and receive proper supervisory review.

(NCTS-503465-01)

4. Demonstrate that the Corporate Emergency Director and/or Site Emergency Director can properly carry out responsibilities within procedural guidelines. (i.e.,

Protective Action Recommendations) (NCTS-003238-08)

5. Demonstrate that Damage Control activities can be initiated in a timely manner. (NCTS-003238-11)

6. Demonstrate that appropriate personnel maintain adequate emergency activities logs as necessary. (NCTS-003238-13)

7. Demonstrate that adequate numbers of qualified emergency response personnel are available to fill required emergency positions. (NCTS-003238-17)

8. Demonstrate that press releases receive proper reviews for technical accuracy prior to dissemination. (NCTS-003238-25)

9. Demonstrate the effectiveness of Station Notifications using the site GAI-tronics paging system. (1990 QA.SRAB Audit Repoit 89026-RG/IN)

10. Demonstrate that PASS sample can be obtained within NUREG time requirements. (1990 SRAB Audit Report 89026-RG/IN) 1-6

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 2.0 DRILL SCHEDULE AND PARTICIPATING ORGANIZATIONS

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. le 2.0 DRILL SCHEDULE AND PARTICIPATING ORGANIZATIONS

~Brieiie October 1, 1990 13:00 hours Final briefing for all Observers/Controllers Location: NMPNS Nuclear Training Center Room Bl/B3 Attendees: Designated Observers/Controllers Drill October 2, 1990 06:30 hours Control Room Observers/Controllers should be in place prior to 06:00 hours. All other Observers/Controllers should be in place at 06:30 hours.

Criticrue October 3, 1990 ll:00 hours Critique of drill to be conducted by NMPNS Manager Emergency Preparedness Location: NMPNS Nuclear Training Center Room Bl/B3 Attendees: Drill Observers, Participants, and Interested Site Supervision D. Those expected to participate in the drill may include, but are not limited to, the following:

1. TSC, EOF, Corporate EOC, PACC and JNC personnel

2. NMPNS personnel with emergency duties

3. Corporate support

4. NMPC Security

5. New York State (partial participation)

6. Oswego County (partial participati.on) 2-1

O.

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. le

7. All station personnel (limited participation). Station personnel not having emergency duties will not participate in the exercise.

Those expected not to participate are:

1. Onshift NMPNS No. 1 and 2 Operations personnel

2. Selected Security personnel

3. JA Fitzpatrick Power Plant personnel

4. NMPNS Unit 1 and 2 personnel not specifically assigned exercise emergency response functions.

5. NRC 2-2

0 0'

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 3.0 SCENARIO EVENTS

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 3.0 SCENARIO EVENTS 3.1 Simulated Events A. All plant parameter data B. All radiological data C. All meteorological data D.. All scenario related events E. JNC set up (JNC will be pre-staged with necessary equipment prior to the drill to better assess JNC operations instead of JNC activation)

F. Operational response activities requiring equipment manipulations.

G. Use of plant sampling systems.

H. Media and financial inquiries (actual inquiries will be made by drill controllers and/or others making the actual inquiries)

I. All communications with selected offsite agencies after the initial notification.

3-1

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 3.2 Actual Events A. Declaration of emergencies B. Notification to selected offsite agencies C. Emergency notifications over the site paging system D. Activation of Emergency Response Facilities as necessitated by procedure E. Damage Repair Team response F. Downwind survey teams G. In-plane survey teams H. Use of protective clothing by all in-plant teams (if warranted by scenario data and directed by exercise response personnel)

I. SCBAs to be carried as appropriate J. Dose assessment/protective action recommendations K. Other evolutions required by emergency procedures which do not affect plant equipment or operations L. Station Evacuation M. Personnel Accountability N. Search & Rescue

0. Post Accident Sampling P. New York State (partial) Participation Q. Oswego County (partial) Participation Only if required 3-2

Nine Nile Point Unit 2 1990 Annua1 Exercise Scenario No. 19, Rev. 1 4.0 REPORTS

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 4.0 REPORTS The drill report report shall be issued in accordance with Procedure S-EPMP-4 for review within 30 days following the drill.

The designated reviewer(s) will determine whether any deficiencies and/or corrective actions are required. Approval of identified corrective actions is required. Approval of identified corrective actions may be granted during the post-drill critique and prior to the issuance of the exercise report so long as the individual(s) required by Unit 2 Technical Specifications to perform the review are present.

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Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 5.0 DRILL INSTRUCTIONS

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 5.1 OBSERVER CONTROLLER INSTRUCTIONS

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 OBSERVER CONTROLLER INSTRUCTIONS A. Exercise Control Or anizat on Drill/Exercise Observer/Controllers will be appointed in order to control, observe, and later critique exercise activities.

The title "Observer/Controller" is used to designate either a single or dual function during the exercise. Observers will be assigned to watch exercise activities as they occur. They will neither provide input nor have active involvement by giving direction to any participants during the exercise.

Their only function is to quietly observe in order to later help develop a representative critique of exercise participants'ctions. Controllers will be assigned to various "key" locations in order to actively control the progress of the exercise. They will input Control and Contingency Messages at the appropriate times, and provide any necessary interpretation to exercise participants.

Controllers will be the only ones who can answer participant's questions. They will also function as Observers to help evaluate performance; thus Observer Controllers. The designation of Observer/Controller will mean either Observer, Controller or Observer and Controller. The "Lead Controller" is the lead exercise manager (or controller), and will be located in the Control Room, TSC or EOF. Prior to the exercise, Observer/Controllers instructions will be provided in order to familiarize all Observer/Controllers with the entire scope of the exercise, and answer specific questions.

Table 5-1, Observer/Controller Assignment Sheet, provides a listing of all exercise Observers and Controllers, their locations and phone numbers.

Observer/Controllers should familiarize themselves with the duties and action requirements of the personnel they are monitoring.

The evaluation packages in section 5.3 provide basic evaluation criteria which must be addressed by the observer/controller in order to effectively critique the exercise. Evaluation criteria are grouped according to exercise activity location and individual (or team) functions.

NOTE: Specific exercise performance must be compared directly with appropriate emergency procedures.

Therefore, individuals assigned as Observer/

Controllers shall be cognizant of the respective procedures and all actions that shall be carried out by the participants they observe.

5.1-1

i Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 At the discretion of NMPC, certain facilities may not be manned and/or participate for this exercise. Where facilities are not manned or participating an Observer/Controller will be pre-positioned to provide the appropriate information.

Exercise Control Instructions All Controllers should be pre-positioned at least 15 minutes prior to the start of the exercise or activation of the center which they are observing.

2. Prior to exercise commencement, all Controller communications will be tested to ensure satisfactory exercise control. This test will be initiated by the Drill/Exercise Controller located in the Control Room.

All Controllers will comply with instructions from the Lead Controller.

4. Observers, Controllers and Observers/Controllers should be considered "invisible" and are therefore exempt from

~facilit drill activities (e.g., facility TLD's, facility sign in, frisking, etc.). Observers, Controllers and Observers/Controllers are not exempt from accountability and must card in when accountability is announced.

All Controllers will synchronize their watches with the TSC Controller(s) who will synchronize their watches with the Unit 2 Control Room via the Control Room Controller(s). This will help ensure that messages are delivered at the proper time. Times on messages are given in time relative to the start of the scenario and clock time, i.e., 00:00 (06:30) indicated time zero or start and (06:30) A.M.

6. Each Controller will have copies of the messages controlling the progress of the exercise scenario.

Messages shall be delivered by the Controllers at the appropriate times, to the designated individual(s). If the response of exercise participants necessitates the use of a contingency message, the situation should be discussed with the Lead Exercise Controller prior to issuance of the message.

Controllers will use the following techniques to control the exercise in accordance with the scenario:

a. Control Messa es - Control messages provide information to the participants and/or cause the participants to take action needed to keep the exercise moving smoothly. The Controller will give a hard copy of the control message to the designated 5.1-2

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 participant at the specified time. Simultaneously, the Controller will provide the essential information verbally . The Controller will follow through and clarify the message by answering questions to ensure that the participants do not extraneous meaning into the message. Controllers will not tell participants what action they are expected to take.

Contin enc Messa es - Contingency messages will be used only if participants fail to take the major control messages by the actions expected from the time designated. Controllers will give the contingency message to the designated participant and explain in as much detail as necessary what actions the participant is expected to perform.

Contingency messages are used to keep the exercise on schedule, though their use may indicate inadequate plan implementation.

Control Information - Controllers for Health Physics and Environs Field Teams will provide instrument readings and other information to team members verbally. Controllers will refer to their current location on the maps and the applicable time period to obtain requested data.

Control Guidance - Controllers will provide verbal guidance to participants to keep the exercise oriented to the pre-arranged scope and scenario.

Controllers will direct participants to simulate certain actions that are outside the immediate scope of the exercise at the time participants announce their intention to perform the action.

Observer/Controllers will note that the participants simulated the action. Participants must request information that is not automatically provided from participants at other location. Controllers will steer participants away from types of information that are outside the exercise scope to avoid bogging the exercise down in a quest for information that Controllers do not possess and have no intention of providing.

All messages controlling the progress of the scenario have an Alpha-numeric designation. The alpha portion of the designation for typical functions is defined as follows:

OC Operations Controller DC Drill/Exercise Controller DR ~ Damage Repair Controller EO "E" Operator Controller SC Security Controller 5.1-3

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 The numeric portion of the designation is the sequential message for that particular controller.

All contingency messages have a "C" designation following the message number (e.g., "OC-.2C).

7. Each Controller will have appropriate copies of time-related plant and radiological parameters (data) corresponding to the development of the exercise scenario. This information should be issued to the appropriate exercise participants only after the player has satisfactorily produced for the controller the actual (real time) plant information. This demonstration must be made each and every time scenario data is given to the players. This applies to all scenario data. When a player requests data before the time it becomes available, the player should be instructed to refer to the last set of data he received. If the player feels he needs new data immediately, but the next set of data is not yet available, the Controller may inform the player of the trend (increasing or decreasing) of the parameter in question.

8. The Lead Controller may authorize other controllers to modify the scenario to fit unusual conditions or events to maintain the scenario within the scope of the exercise objectives and in order to maximize the practical training benefit presented by the drill experience. If a modification is made the Facility Controller authorized to make the modification will report to the Lead Controller the specific scenario changes that were made.

9. If environmental samples inside or outside the site are deemed necessary, they will be collected, if possible, and their analysis conducted or simulated, as directed by a Controller. Observer/Controllers will accompany the survey teams, both onsite and offsite.

10. Controllers shall not provide information to the exercise participants regarding scenario development or resolution or problems areas encountered. The exercise participants are expected to obtain information through their own organizations and exercise their own judgments in determining response actions and resolving problems:

11. Any inquiries originating from the general public, as a result of drill activities, will be referred to either a Controller or to the Public Information personnel - Rumor Control at 1-800-634-9920. An explanation will consist

'only of stating that an emergency exercise is underway at the plant and all events are simulated (i.e., not real).

5.1-4

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1

12. Some exercise participants may insist that certain parts of the scenario are unrealistic. The Lead Controller has the sole authority to clarify any questions regarding scenario content.

13. Each Observer/Controller will take detailed notes regarding the process of the exercise and the responses of the exercise participants at their respective assigned locations. This information should be completed on the "Exercise/Drill Observation Sheet" (see Figure 5-1).

Each Observer/Controller should carefully note the arrival and departure times for exercise participants, the times at which major activities or milestones occur, and problems areas encountered. All notes taken should be retained for the purposes of reconstructing the exercise chronology and preparing a written critique of the exercise.

In order to systematically verify that. exercise objectives have been met, Evaluation Checklists have been provided for each Observer/Controller specifically designed for their areas of observation.

14. All Controllers should provide copies of Figure 5-2 to all participants in their respective area to complete and return the form to the Emergency Coordinator with exercise comments.

15. Damage Control Teams will be dispatched to participate in supplemental scenario equipment exercises. Damage Control Teams may not be dispatched for all repairs.

This information will be transmitted to the Maintenance Coordinator in the form of a message. Damage Control Teams that are dispatched may be allowed to return to the OSC for further assignment or be directed to an alternate location to simulate the equipment repair after acquiring the appropriate tools, parts, and executing the requisite exposure control measures.

16. Operators, damage control personnel, technicians, etc.

should not go into the plant on a exercise related matter without a Controller.

17. All participants and observer/controllers will wear appropriate headgear and footgear when going into the plant.

5.1-5

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1

18. In the event of a real emergency during the exercise, the exercise may be immediately terminated or suspended by the Emergency Coordinator or the SSS, if deemed appropriate.

19. The Lead Controller will determine when the exercise objectives have been sufficiently demonstrated to terminate the exercise. Following coordination with the facility lead controllers, the Lead Controller will make an announcement over the station Gaitronics that the exercise is completed and terminated.

20. After completion of the exercise, and before the end of the next normal working day, the Emergency Preparedness Manager will hold a verbal critique, where all Observer/Controllers shall discuss their observations and any noted shortcomings, and present their recommendations to improve performance and emergency preparedness.

Written comments will be requested at the conclusion of the critique.

5.1-6

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 TABLE 5-1 OBSERVER CONTROLLER ASSIGNMENT SHEET 5.1-7

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1A TABLE 5-1 OBSERVER CONTROLLER ASSXGNMENT SHEET Controller Observer (0) Phone Location Number* Controller C 0 C Number s

1. Unit

~

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2 Control Room:

Command & Control Operations CR-1 CR-2 R. Cam a L. Na on lli C C

49-1136 349-1136

~ Operations CR-2 J. Kam'nski C 349-1136

~ Communications CR-3 M. Eron C 349-~ 136

~ Coordination CR-4 J. M. Benson C 349-1136

2. Technical Support Center (TSC):

~ Command & Control TSC-1 T. Cotte C 349-2575 2488

~ Rad Assessment TSC-2 E. Leach C 34 876

~ Tech Assessment TSC-3 J. S adafo e C 349-1223 2444

~ Tech Assessment TSC-3 R. Murne C 349-2575

~ Communications TSC-4 J. Do le C 349-2575

~ Coordination TSC-5 D. LeCu er C 349-2575

3. Operational Support 349-2553 Center (OSC): OSC-1 C. D. Howes C OSC-2 P. Ha tnett C 349-2553.

OSC-3 'J. Savoca C 349-2553 PASS-1 B. Bock C 349-2553

4. Emergency Operations Facility (EOF):

~ Command & Control EOF-1 A. M. Salemi C 349-2943 2944

~ Rad Assessment EOF-2 J. N. Duel 1 C 349-1058

~ Tech Assessment EOF-3 M. Meier C 349-1063 2979

~ Tech Assessment EOF-3 J. Dolne 0 349-1058

~ Coordination EOF-4 J. Andrews 0 349-2943 2944

~ EOF-PACC EOF-5 D. Cienava C 349-2956

~ EOF-Guest Observer EOF-6 R. Haun 0 349-2943 2944

5. Joint News Center 342-5900

( JNC) JNC-1 B. Burtch JNC-2 G. Gazda 342-5900

• The Controller Number references the area to be observed with the appropriate checklist in Section 5.3 to be filled out by that Observer/Controller.

NOTE: To contact the Drill SSS call 349-1260.

5. 1-8

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1A TABLE 5-1 OBSERVER CONTROLLER ASSIGNMENT SHEET Controller Observer (0) Phone Location Number* Controller C 0 C Number s

6. Alternate Access Point or Security Control Point(s) SCP-1 P. Carroll 0 349-1025 1026

7. Station Survey/ Radio, Sample Team(s) SAM-1 B. Hoe 349-2553

8. Environmental (Team A) ENV-1 T. Ca rolls C 593-4646 Survey/Sample (Team B) ENV-2 J. Lace C 593-4645 Team (s) (Team C) ENV-3 B. Edwards C 593-4651

9. Damage Control Teams Suppl. Sc. 1 T. Dou hert C 349-2282 Radio Suppl. Sc. 2 T. J. Wanek C 349-2282 Radio Suppl. Sc. 3 P. Lavallee C 349-2282 Radio Suppl. Sc. 4 L. Dick C 349-2282 Radio Suppl. Sc. 5 J. Hiab 34 -2282 Rad'o Suppl. Sc. 6 T. Ottman C 349-2282 Radio 349-2282 Radio 349-2 82 Radio

10. Corporate Emergency Operations Center EOC-1 J. Chiodo 4 8-7850 ll. Fire Response FR-1 D. Forbes GAI-tronics

12. Security Tactical Operations Center STO-1 C. Boniti 34 -1313

13. PACC PACC R. Wells 428-6916

14. Oswego County OSCO-1 J. Pavel 349-2976 15 'RC Inquiries NRC-1 Gu dziel 34 973

• The Controller Number references the area to be observed with the appropriate checklist in Section 5.3 to be filled out by that Observer/Controller.

NOTE: To contact the Drill SSS call 349-1260.

5.1-9

0 0

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 FIGURE 5-1 EXERCISE DRILL OBSERVATION SHEET Observer's Name: 'xercise/Drill Date:

Observer's Location:

Exercise/Drill

Title:

Emer enc Pre aredness Drill Scenario No 15 Information To Provide:

Time Drill Comments: Time Drill Terminated:

OBSERVATIONS COMMENTS AND RECOMMENDATIONS NOTE: Observations should include the proper and effective use of procedures, equipment and personnel.

Signature:

Title:

5.1-10

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 FIGURE 5-1 (continued)

EXERCISE DRILL OBSERVATION SHEET Signature:

Title:

5.1-11

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 FIGURE 5-2 DRILL EXERCISE PARTICIPATION RRCORD Please complete the information below and sign at the bottom if you participate in a drill or exercise. This information will be used to update your training records. Any comments you may have regarding this drill/

exercise will be considered for resolution and incorporated into the Emergency Preparedness Program as appropriate.

Name: Soc. Sec. No.

(Print) Last First MI Drill/Exercise Date Emergency Position(s) assumed I DO / DO NOT have an Oswego County Emergency Access ID Card (Green Card)

(circle)

Comments The above information is correct to the best of my knowledge.

t Signature Date RETURN COMPLETED SHEET TO: A drill/exercise controller, observer, or A.

Salemi, Emergency Preparedness Department, Nine Mile Point.

5.1-12

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 5.2 PRE-EXERCISE CONTROL ROOM BRIEFING

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 5.2 PRE-DRILL CONTROL ROOM BRIEFING The Station Shift Supervisor may suspend or terminate the exercise at any time plant conditions warrant.

B. Do not take any actions that will affect normal plant operations.

Take immediate action(s) to restore safe operation, if an unsafe condition exists. Ignore exercise situation if safety becomes a concern.

D. All simulations and verifications will be expressed in spoken words.

Exercise events will be initiated by the exercise controllers issuing message cards, plant status sheets, and verbal instructions as appropriate.

Controllers will provide appropriate information at the location where that information would normally be available (e.g., Reactor status at the Control Room, dose rate readings with field teams, etc.).

Only selected parameters and readings will be provided. The selected information will be sufficient to make decisions in accordance with Nine Mile plans and procedures.

H. The purpose of the exercise is to test Emergency Implementing Procedures and major aspects of the Site Emergency Plan. DO NOT BECOME OVERLY CONCERNED WITH THE MECHANICS OF THE REACTOR OR THE CAUSE OF THE ACCIDENT. THIS EXERCISE IS DESIGNED TO TEST SELECTED NINE MILE POINT NUCLEAR STATION EMERGENCY PROCEDURES AND IS NOT CONCERNED WITH ESTABLISHING THE PROBABILITY, FEASIBILITY OR DETAILED MECHANICS OF THE SIMULATED ACCIDENT.

There will be one or more Observer/Controllers at each important location. Controllers will provide information and clarification on which actions are to be simulated or are outside the scope of this exercise in order to keep the exercise progressing in accordance with the scenario.

Observer/ Controllers will also observe all aspects of the exercise to prepare an in-house evaluation of plans, procedures and training.

5.2-1

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 All communications will begin and end'with the statement, "THIS IS A DRILL. THIS IS A DRILL"...

If samples inside or outside the site are deemed necessary, they will actually be collected, if possible, and their analysis conducted or simulated, as directed by a Controller.

Observer/Controllers will accompany the survey teams, both onsite and offsite.

The exercise is also a training vehicle for members of the Nine Mile Point Emergency Response Organization to practice working together and with outside organizations. Please make note of any improvements in any area that you observe as a participant and submit them to the Observer/Controller at the conclusion of the exercise.

The Control Room Controllers will answer questions from Control Room Staff regarding the exercise before proceeding to Scenario Initial Conditions, Message OC-1.

Control Room players should only generate one (the first) set of data from the SPDS display consoles. All subsequent data generation should be simulated.

A controller will accompany any operator dispatched from the Control Room for exercise purposes. A controller should be present at any briefings given to an operator prior to this dispatch.

All exercise participants, observers and controllers should ensure that they do not interfere with normal plant operations.

5.2-2

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 5.3 EVALUATION PACKAGES

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 5.3 EVALUATION PACKAGES Evaluation Packages have been developed for each key observer/

controller position and are cross-referenced to ..the Objectives.

Along with each objective is the observable which must be demonstrated to satisfy that objective.

The evaluation packages are handed out at the pre-exercise briefing and should be inserted into this binder behind Table 5.2.

To identify the appropriate checklist to use, each Observer/

Controller should first refer to the "Observer/Controller Assignment Sheet", Table 5-1, to determine his/her specific "Controller Number". Using this number the Observer/Controller should select they have the appropriate checklist listed on Table 5-2.

5.3-1

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 TABLE 5-2 EVALUATION PACKAGES Package Descri tion Title CR 1-3 Unit 2 Control Room TSC 1-5 Technical Support Center OSC -1 Operational Support Center DCT 1-5 Damage Control Team PAC -1 Personnel Accountability AA 1-4 Assembly Area EOF 1-4 Emergency Operations Facility JNC 1-2 Joint News Center SCP -1 Security Control Point SAM -1 Station Survey/Sample Team ENV 1-3 Environmental Survey/Sample Team EOC -1 Corporate Emergency Operators Center NRC -1 NRC Inquiries 5.3-2

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 6.0 SCENARIO ASSUMPTIONS

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 6.0 SCENARIO ASSUMPTIONS 1.0 Radiolo ical Release A. Radiological data is provided in 15 minute time intervals to include meteorological, radiochemistry, in-plant dose rates, and onsite and offsite plume data for the duration of the drill. GEMS data, although not retrievable every 15 minutes, is presented every 15 minutes to ensure data is available when appropriate.

B. The release path of radioactive material is from the Drywell through the Unit 2 stack'o the environment.

C. The release occurs during emergency containment venting which is initiated in accordance with Procedure N2-OP-61A due to primary containment pressure greater than 45 psig.

D. The release is unfiltered due to valve line ups associated with the Emergency Containment Venting 'Procedure to ensure SBGTS filter trains are not damaged due to high differential pressures.

E. The release rate for drill time (05:00) is based on a flow rate of 82,570 CFM. The components of this flow rate includes the Turbine Building (82,170 CFM) and 400 CFM from the emergency venting of the primary containment and suppression pool atmosphere.

F. The NMPNS Class A dispersion model was utilized to determine centerline dose rates and CHI/Q values.

G. The radiological and meteorological parameters are such that the integrated dose obtained during the duration of the simulated release during the drill will not exceed the recommended Protective Actions for whole body doses or child thyroid found in E.P.A. 520.

2.0 In-Plant A. Stack and vent effluents prior to the release were calculated utilizing activities from Expected Airborne Radioactivity Concentrations at In-plant Areas during Reactor Shutdown, Nine Mile Point Unit 2 FSAR, Table 12.2-15B.

B. The dose rates in the Drywell were calculated utilizing methodology by Shapiro, 2nd edition, "Radiation Protection".

6-1

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 (uCi/cc) X 1 cc x 1.32E08 dis/uCi-hr x MeV/dis x lmR 0.0012g 62400 MeV/g x 0.5 (semi-infinite plume) mR/hr C

Beta (uCi/cc) x 1 cc x 1.32E08 dis/uCi-hr MeV/dis x lmR 0.0012g 62400 MeV/g x 1.13 mass stopping power tissue/air x 0.5 mRad/hr C. The following,radionuclides and energies from NUREG/CR-3365 PNL-4758, "Report to the NRC or Guidance for Preparing Scenarios for Emergency Preparedness Exercises at Nuclear Gen'crating Stations", were utilized for calculations.

Avera e Beta Ener Avera e Gamma Ener Nuclide er Disinte ration er Disinte ration Kr-85 0.251 0.0022 Kr-85m 0.226 0.18 Kr-87 1.33 0.79 Kr-88 0.249 2.2 Xe-133 0.102 0.030 Xe-133m 0.0 0.020 Xe-135 0.310 0.26 Xe-135m 0.0 0.53 W-131 0.185 0.39 I-132 0.525 2.2 I-133 0.417 0.60 I-134 0.691 2.6 l-135 0.394 1.5 D. Dose rates from the post accident sample were calculated using:

Dose rate Q 1 ft. (rem/hr) 6 CEN/R2 Where:

E - average gamma energy in Mev C number of curies in the sample 6-2

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 N - gamma quanta/dis R distance from source of radiation A. "Real-time" meteorological data used during the exercise has been taken from October 1985 historical data. Some minor changes were made to the existing historical data - i.e.,

wind speed, wind direction, stability class and temperature in order to facilitate scenario requirements; however, the remaining data will allow accurate forecasting.

B. Survey Team maps and tables were developed utilizing the following initial data:

Stability Class SvD, ShG Wind Speed (Upper or 200 ft) 10 mph.

Wind Speed (Lower or 30 ft) 9 inph Wind Direction 292 Ambient Temperature 57o Lake Temperature 55o Precipitation 0 inches/hr 4.0 Offsite A. Radioactive decaying during the release period and plume travel was not considered in offsite radiological release calculations.

B. The open window meter readings are the summation of the closed window and plume beta dose rates. The open window dose rates contribution due to iodine deposition is considered only at contact and is negligible.

C. The Iodine deposition values were calculated as follows:

W g

(X) (Vd) (t) (10 cm /m )(10 Ci/uCi)

Where:

the ground deposition for Iodine, Ci/m Vd the deposition velocity 0.1 cm/sec release time interval in seconds Iodine concentration (uCi/cc) in plume at the location of interest 6-3

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 and X Q ~ X~u us Where Q Iodine release rate, Ci/sec, Xu/Q - concentration dispersion coefficient for any given point, (Sec/m ) (Miles/hr) u average wind speed, Miles/hr.

D. The count rates associated with the deposition values were found to be negligible and determined as follows:

Gamma contribution at 3 feet:

mR/hr Wg ; 3.6E+06 mRad sec (If 'Dgi)

Rad hr is'otope 2

, mRad sec , Rad , M QC M Rad hr sec ci Where

- Isotopic iodine fraction I uCi/cc/ .

Q Ii uCi/cc'sotopic Dgi gamma )eposition factor (Rad/sec)/(Ci/m )

Isotope gamma deposition factors were obtained from Figure 7.24 and Equation 7.65 of Meteorology and Atomic Energy 1968, David H. Slade, Editor.

Gamma Deposition

~Isoto e Factor at 3 Feet I-131 2.00E-03 I-132 7.50E-03 I-133 2.80E-03 I-134 7.50E-03 I-135 6.20E-03

2. Gamma contribution on contact:

mR/hr - (3.8) (3 ft gamma dose rate)

Where 3.8 assumed contact to 3 foot gamma dose rate ratio 6-4

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 Beta contribution at contact (it was assumed that there were no dose contributions from beta particles at the 3 foot level):

mR/hr - W . 1 CB

, 3.6E+06 mRad-sec Rad - hr

. p~ (Ifiisotope DBi)

Where CB - beta correction factor of 2.5 If. Isotopic iodine fraction

- Ii uCi/cc/ Ii LLCi/cc DBi - Isotopic Beta dep~sition factor (Rad/sec)/(Ci/m )

Isotope beta deposition factors were obtained from Figure 7.6 of Meteorology and Atomic Energy 1968, David H. Slade, Editor.

Beta Deposition

~Isoto e Factor at 10 cm I-131 1.00E-02 I-132 1.00E-01 I-133 7.00E-02 1-134 1.50E-01 I-135 7.00E-02 Open window does rates due to the noble gas clouds were calculated as follows:

Cloud gamma dose rate (mR/hr) 0.25

• 3.6E+06 mRad sec '/Q Rad hr isotope fi 'GIi + QNG isotope NGFi ~

EGNGi (Based on Equation 7.36 from Meteorology and Atomic Energy 1968, David H. Slade, Editor) 6-5

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 Cloud beta dose rate (mR/hr)

'

0.23 + 3.6E+06 mRad sec X/Q Rad hr CB QI If- ~ EBIi + QNG NGFi ~ EBNGi isotope isotope (Based on Equation 7.36 from Meteorology and Atomic Energy 1968, David H. Slade, Editor)

Where X/Q dispersion c~efficient for any given point, sec/m CB Beta correction factor - 2.5 Qz Iodine release rate, Ci/sec Isotopic iodine fraction QI Xg UG1/Cc/ ~ llG1/CC EGIi Average Gamma isotopic iodine energy, MeV EBI.i Average Beta isotopic iodine energy, MeV QNG Noble gas release rate, Ci/sec NGF ~ Isotopic noble gas fraction NGg/

g NG~

EGNG-i Averge Gamma isotopic noble.gas energy, MeV i

EBNG ~ Averge Beta isotopic noble gas energy, MeV F. All survey values are rounded-off to provide realistic survey meter responses.

G. The exposure rates, as required, were converted to equivalent count rate units through use of the relationship of 3600 cpm per one MR/hr or MRad/hr.

6-6

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. le H. The Downwind Survey Team members shall use "as found" values for all offsite radiological data prior to the release.

I. Air sample results (iodine and particulate gross CPM) are calculated utilizing Niagara Mohawk Procedure EPP-7, Figure

2. Iodine and particulate coycentration are calculated with an air sample volume of 15 ft by NMPC Downwind Survey Team members.

J. The total integrated iodine deposition values for the entire release were calculated assuming the complete passage of the simulated release during the exercise. Iodine concentrations utilized were as calculated by the Class A Model.

K. Outside the given isopleths is considered to be background (60 cpm). All readings should be 60 cpm in this area.

L. Plume width was determined using the following formula:

Yp- (2 Oy 2 ln 100 P

)

Where: (Ty - horizontal diffusion coefficient (m)

P 0.5 (percentage the concentration has dropped from the plume centerline)

Yp - distance off the centerline of plume where the concentration has dropped to P% of its value

[Based on Equation 3.148 from Meteorology and Atomic Energy, 1968, David H. Slade, Editor]

M. Values of lateral diffusion coefficient 0 y were determined using Figure 3.10 in Meteorology and Atomic Energy, 1968, David H. Slade, for Pasquill stability Class F.

Downwind Distance miles iiiies miles 1,609 1 50 .03 162 .10 3,218 2 100 .06 325 .20 4,827 3 150 .09 488 .30 6,436 4 200 .12 651 .40 8,045 5 250 .16 813 .51 9,654 6 300 .19 976 .61 11,263 7 350 .22 1,130 .71 12,872 8 400 .25 1,302 .81 14,481 9 450 .28 1,465 .91 16,090 10 500 .31 1,627 1.01 6-7

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 7.0 SCENARIO

SUMMARY

AND TIMELINE

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1

7. 1 NARRATIVE

SUMMARY

Nine Mile Point, Unit 2 Emergency Preparedness Drill Scenario No. 19, Rev. 1 7.1 NARATIVE

SUMMARY

INITIAL CONDITIONS Nine Mile Point Unit 2 is operating at 100% power near the end of the cycle on the present core. The plant has been on continuous run for

'he past 189 days with an average power of 93.4%. The last plant shutdown was for a scheduled maintenance and refueling outage which took 48 days. All systems are operating normally with the following exceptions:

o RCIC is out of service for repair of a failed turbine support bearing. The RCIC turbine is dismantled and the bearing is expected to be repaired and be ready for testing within 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />. The RCIC System was declared INOP 7 days ago. The LCO of Tech Spec 3.7.4 is in effect allowing a total of 14 days to restore it to service or shutdown.

With RCIC out-of-service, it was decided that maintenance would rebuild RCIC outboard steamline isolation valve, MOV-121, since it has a badly leaking valve seat. The RCIC inboard steamline isolation valves are closed and marked-up since MOV-121 is dismantled. It is expected that repairs to the valve will be completed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

o CRD Pump A is out-of-service for failed motor replacement.

o Condensate Pump C is out-of-service for pump bearing replacement.

o RHR Pump A out-of-service for electrical fault in the motor. The motor breaker tripped on overload during a surveillance test and a megger showed a phase to ground fault. The pump was declared inoperable 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ago and is isolated mechanically and electrically. Motor replacement has commenced by a simulated maintenance crew and is expected to be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. Tech Spec LCO 3.5.1 allows continued operation for a total of seven days with this pump out-of-service.

7.1-1

Nine Mile Point Unit 2 Emergency Preparedness Drill Scenario No. 19, Rev. 1 SCENARIO The drill will be initiated when a drywell unidentified leak exceeds 5 gpm. The leak is postulated to be from a crack on one of the jet pump risers. As such, there will be no conclusive information that will tell the operator exactly what the leakage source is. This will require an UNUSUAL EVENT to be declared per EAP-2. Notifications will be made and the NMP-2 Control Room Emergency Response Organization will activate. The Station Shift Supervisor (SSS) will assume the duties of Site Emergency Director.

The operators will commence a controlled reactor shutdown due to the high leak rate. Approximately 45 minutes into the exercise Condensate Pump A trips due to a motor winding short. Since the plant is at 45%

power at this time, there is no immediate transient due to this failure.

At 1:10 minutes into the exercise a fire will break out and be detected in the DIV I 125 VDC switchgear. The Unit 2 Fire Department will respond and after approximately 15 minutes the fire will be extinguished. Damage from the fire will be extensive, causing DIV I 125 VDC bus to be inoperative. With the fire causing a failure of DIV I 125 VDC power, the Site Emergency Director (SSS) will-upgrade the emergency to an ALERT. The TSC, EOF, OSC, CORP. EOC and JNC will be activated and notifications will be made.

Of significant importance with the failure of DIV I 125 VDC power is the loss of control power to ADS DIV I and loss of recirculation flow, loss of containment cooling systems and loss of Train A of SBGT System.

Upon identification of the loss of recirculation flow the operators will manually trip the plant in accordance with the "Sudden Decrease in Core Flow" Section of N2-0P-101D.

Upon Reactor and Turbine Trip the following transients will occur o The Turbine Exhaust Hood rupture diaphragm will fail causing a rapid air leak and subsequent vacuum loss. This will also cause the MSIVs and Turbine Bypass Valves to close.

o The existing crack in the jet pump riser will increase to a leak rate of greater than 50 gpm (a small break LOCA). This will not be large enough to depressurize the vessel but will increase Drywell pressure causing a Containment Isolation.

At this point only one means remains to depressurize the reactor, i.e., ADS or manual SRV control. RCIC and RHR Steam Condensing has been out of service since the beginning of the drill, the Main Condenser is unavailable due to loss of vacuum and ADS DIV I is without power.

7 0 1 2

Nine Mile Point Unit 2 Emergency Preparedness Drill Scenario No. 19, Rev. 1 As the small break LOCA causes Drywell pressure to rise, HPCS will be given a start signal on, high, Drywell pressure. HPCS will automatically trip on start-up due to a failed bearing causing an overcurrent condition. The only means of high pressure makeup water to the reactor at this time is the B train of feedwater and the B CRD Pump. Therefore, although Reactor pressure remains high, adequate makeup water is available.

Fifteen minutes after the Turbine Trip, a complete loss of DIV II 125V DC occurs due to a dead short on the supply line from the battery chargers. DIV II 125V DC provides control power to ADS DIV II. With both divisions of ADS inoperative, the reactor cannot be depressurized.

By Ol:50 both DIV I and DIV II 125V DC Buses will have been INOP for 15 minutes. This will require upgrading the event to a SITE AREA EMERGENCY per EAP-2. In addition, 125V DC DIV I power will have been failed due to the fire for 45 minutes while both RCIC and the A loop of Suppression Pool Cooling are failed. This would also require a SITE AREA EMERGENCY to be declared per EAP-2, Figure 2D.

At 02:30 the B CRD pump fails when a faulty low suction pressure interlock trips the pump. One half hour later, the only remaining high pressure water to the reactor, the B Feedwater train fails when the B Condensate pump trips due to bearing failure. This requires a GENERAL EMERGENCY to be declared.

With no means to depressurize the vessel and no high pressure makeup capability, reactor level will gradually decrease, until the core becomes uncovered. As the fuel overheats, percent of fuel failure gradually increases. Simultaneously, Containment pressure gradually increases.

Attempts to control Containment pressure are hampered by the loss of 125 VDC control power. If "B" RHR is manually aligned for Containment Spray RHS Valve 2RHS*MOV15B will not open due to stripped gears in the Valve Actuator and Suppression Pool Spray Valve 2RHS*MOV33B is also inoperable because it is mechanically jammed in the closed position.

It is anticipated that restoration of 125V DC DIV II power will be completed by 5:00 hours into the exercise. Upon restoration, the Reactor can be depressurized and the core recovered. The DC operated Drywell isolation valves will be repowered and the drywell can be vented via the SGTS. This venting will initiate a controlled radioactive release to the atmosphere and allow dose assessment and environmental monitoring to be demonstrated.

7.1-3

Nine Mile Point Unit 2 Emergency Preparedness Drill Scenario No. 19, Rev. 1 The Emergency Operating Procedures, EOP-PC, direct that the Primary Containment be vented when suppression chamber pressure exceeds 45 psig. When the suppression chamber pressure increases to this value a controlled venting of Primary Containment will commence. The vent path will be through the Standby Gas Treatment System bypassing the filters to the Main Stack.

A Damage Repair Team dispatched from the OSC to restore the Suppression Pool Spray Valve, 2RHS+MOV33B will be successful at approximately 06:30 into the drill. Suppression Pool Spray will be initiated and Primary Containment pressure will be reduced. The venting of the Drywell will be stopped and the release to the environment will be terminated.

After stabilizing the plant and containment venting is stopped the emergency will be terminated at 07:00, the exercise will be suspended for approximately 15 minutes. During this time, the clock will be advanced two days. After the time shift, exercise participants will be permitted to enter recovery. Once recovery has been demonstrated, the exercise will end.

7.1-4

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No.'9, Rev. 1 7.2 EVENT TIMELINE

NEVISION No.i NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT UNIT N0.2 1990 ANNUAL GRADED EXERCISE SCENARIO No. 19, REV.

-00: 30 00: 00 00: 25 00: 45 01: 10 ~ 01:20 01:25 01: 35 01: 50 (06: 00) (06: 30) (Os:SS) (07:16) (07: 40) (071 50) (O7JSS) (08: 05) (081 20) niJIIAL CONDmONS DRHL BEGDIS DRYNEJL UNIDENTHTED CONDENSATE PUMP A HRE IN DIVJSION I MANUAL REACTOR TIUP DIVISION H ADS IDSS OF DC POJJER IZAK RATE TMPS DUE To MOTOR 125VDC SIICHGEAR 125VDC CONTROL FOR GREATER TBLI

~ NDiE LHLE POINT mJDJNG SHORT ~ LOSS OF CONDENSER PolfER FANS 15 MINUTES UhTT 2 OPERATING

~ > 5 GPM ~ IDSE CONTROL FOYER VACUIDI AT 100>> POJJER To ADS DIVISION H ~ ADS INOPERABIZ SAE DECLARED DUE To

~ BEGIN CohTROLIED INOPERABHITY OF

~ IZAK RATE > 50 GPM

~ RCJC 0/S HJR SHUTDolJN ~ IDSE CONTROL POIR ~ UNABLE To RCIC. HPCS AND RHR REPAIR OF FAHZD To RHRB AC DEPRESSUMZE IDOP B POOL COOUNG TURBINE SUPPORT REACTOR FOR A TDJZ SPAN BEARDJG UNUSUAL ~ ACTIVATE HRE > 45 MJNUTEL EAP-2 DEPARTMENT HGURE 2D EVENT

~ RHR STEAM CONDENSING O/S ~ ACIIVATZ TSC. OSC, EOF. JNC AND

'CRD PUMP A 0/S CORPORATE ZOF SITE AREA FOR FAHZO MOTOR EMERGENCY REPLACELJEhT CONDENSATZ PUMP C 0/S FOR PUMP BEAMNG REPLACEMEhT

'RHR PUMP A 0/S FOR MOTOR REPLACEMENT 02: 30 03: 00 04: 00 04: 30 05: 00 06: 30 07: 00 SUSPEND 071 15 08: 00 (o9:oo) (09: 30) (10: 30) (111 00 111 30) (12:oo) (1R30) D~R~SM~R(13:45) (14:SO)

CRD PUlJP B TMPS CONDENSA'IZ PUMP B CORE BEGINS To DC POIJER CONTADJMENT VENT PLANT JN STADIA 2 DAYS LATER TERMINATE DRHL DUE To SUCTION TRIPS DUE To BEAMNG UNCOVER RESTORATION TZRMDJATED SP CONDIIION ENTER RECOVERY PRESSURE INTERIDCK FAILURE SUCCESSHJL SPRAY DJIIIATZD TER%NATE EMERGENCY FAHIJRE ~ FUEL BEGINS To IDSS OF FZEDYATZR OVERHEAT ~ RX DEPRESSUMZATION

'XSID VAIZR IZVEL JJLY DECREASES ~ DRYLJEtL PRESSURE ~ CORE COVERED GENERAL CONTDJUES To INCREASE ~ DRYlEJL VENTED EMERGENCY VIA SOTS DUE To

~ DOSE RATES JN HIGH PRESSURE DRYRML BEGIN To INCRELSE 0/S - OUT OF SERVICE

0 Nine Mile Point Unit 2 1990 Annual" Exercise Scenario No. 19, Rev. 1 7.3 SUPPLEMENTAL SCENARIOS

P, Nine Mile Point Unit 2 1990 Annual Exercise Scenario No.19 Rev.1 CR/OSC CONTROLLER PLAN SCENARIO TIME O

O 0v) O 0 O O

O n O O

Vl O

O v>

O O

O O O

O Vl O O O Ol e Q Q 0 O O O O O O O Q, O CONDENSATE PUMP 2CNM-PIA E,c(CR)

FIRE DIV I SWOR D(CR)

, c LOSS OF VACUUM 8(CR) 4 HPCS PUMP 2CHePI e(osc)

O DRYWELL SPRAY 2RHS'MOVI SB sLs 8(OSC)

SUPPRESION-POOL SPRAY 2RHS'MOV338 8(osc)

X 4J DIV 8 E(osc)

LLt 0 CRD PUMP 8 M(OSC)

Irt CONDENSATE PUMP 2CNM-PIG'S e,c(osc) c 10 PASS A(OSC) a = earliest dispatch b = earliest camplettan c = latest camplettan A = pass C Electrtcal/l&C CR) =. Dispatched from CR DRT Legend . D = Fire Brigade OSC) = Dispatched from OSC B M h I E = E Operator PC) = Power Control Scriba 345KV Yard 7.3-1

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 Su lemental Scenario No. 1 Failure of Condensate Pum 2CNM-PlA Time: 00:45 (07:15)

Location: At Condensate Pump A and Normal Switchgear, 2NNS-SWG011 INSTRUCTIONS A. Initial Notification The Control Room will first learn of a failure of Condensate Pump A via message number OC-4 at 00:45.

B. Postulated Event This failure is defined as a motor winding failure causing a phase-to-phase short tripping the motor via a differential phase overcurrent relay. The motor windings are sufficiently melted to require motor replacement.

Personnel responding to investigate the failure of Condensate Pump A observe the following:

o At normal switchgear, 2NNS-SWG011 the Condensate Pump A breaker indicates a flag on the differential phase overcurrent relay.

o At the Condensate Pump itself, the motor smells of an electrical burn and the motor is exceptionally hot.

C. Restoration Guidelines The loss of this pump is necessary to,support other events in the drill. The Controller must not allow the pump to be repaired prior to 05:00 to support data provided in the drill. At this time, if the Damage Repair Team has demonstrated that they could have restored the pump to operability, it can be declared "fixed". Otherwise, it can remain failed because it need not (and is not expected to be) fixed within the time frame of this drill.

7.3-2

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 Su lemental Scenario No 2 Fire in DIV I 125V DC Switch ear Time: 01:10 (07:40)

Location: DIV I Swgr Rm, El. 261'Fire Zone 333XL)

INSTRUCTIONS A. Initial Notification The Control Room will first learn of the fire via message number OC-5 at 01:10.

B. Postulated Event It is postulated that a loose piece of the metalclad switchgear contacts the 125V DC bus bars causing an extreme overcurrent condition. The cabling and paint on the cubicle walls start to burn.

The overcurrent causes the battery chargers to trip while the battery banks breaker fails to isolate the fault. Voltage on the batteries is drawn down rapidly.

The fire is sensed by smoke and heat detection systems causing an actuation of the CO~ Fire Suppression System. The C02 automatic isolation valve fails to open after the time delay times out.. The valve is mechanically hung up. Once the Fire Brigade arrives at the scene, should they attempt to manually open the valve it will respond normally.

The short circuit and fire cause extensive damage to the switchgear and all associated cables, metering and controls. Damage should be estimated as requiring replacement of the switchgear entirely. Damage is confined to switchgear internals and no other equipment except DC is affected.

C. Restoration Guidelines The purpose of this failure is to lose control power to all DIV I emergency equipment but especially to DIV I Solenoids of the ADS valves.. DC power to DIV I equipment is assumed to be failed for the remainder of this drill. Under no circumstances should the controller allow DIV I DC power to be restored prior to 06:30 when Containment pressure is under control and the reactor core is covered so restoration of DIV I DC would not affect remaining scenario data.

OSC response to this damage repair is expected to attempt to run temporary cabling and/or portable DC power supplies to equipment that the CR and TSC desperately need. Examples would be to run cables from DIV III batteries to a DIV I distribution panel; another attempt may 7.3-3

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 be to power the ADS valve solenoids directly by attaching a portable DC power source to the control power terminal blocks behind the main control room panels.

Whatever method is attempted, the Controller should allow the technicians to actually demonstrate that they could find the necessary equipment and properly walk through their procedure. If the Controller is satisfied that they could have energized the desired component, he should note this but fail the equipment being used for the repair thus preventing successful operation of the equipment."

After 06:30, any attempts that the Controller deems to be successful can be allowed to work.

7.3-4

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 Su cmental Scenario No 3 Loss of Condenser Vacuum Time: Ol:20 (07:50) or when the operators manually trip the plant.

Location: At the Condenser INSTRUCTIONS A. Initial Notification The Control Room will be made aware of the loss of Condenser Vacuum via message number OC-6 at approximately Ol:20.

B. Postulated Event The Turbine Exhaust Hood rupture diaphragm will fail causing a rapid air leak and subsequent vacuum loss. This will also cause the MSIVs and Turbine Bypass Valves to close.

The loss of vacuum is necessary to prevent the use of Turbine Bypass to depressurize the Reactor.

C. Restoration Guidelines, Vacuum will be lost for the duration of the exercise.

7.3-5

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 Su lemental Scenario No. 4 Failure of HPCS Pum 2CSH*P1 Time: 01:25 (07:55)

Location: Main Control Room and in the HPCS Pump Room, Elevation 175'NSTRUCTIONS A. Initial Notification The operators will be made aware of the HPCS pump trip at 01:25 via message OC-8.

B. Postulated Event When the HPCS Pump, 2CSH*P1, is automatically started on high drywell pressure, it will trip. It is theorized that the pump thrust bearing has failed mechanically and caused excessive binding and a motor overcurrent trip. The thrust bearing will have to be replaced.

C. Restoration Guidelines This thrust bearing failure requires major work on the motor and as such should extend beyond the end of the drill. Manual"pump shaft rotation will be impossible if attempted. The Controller must not allow this pump to be repaired prior to 05:00. Anytime after this the pump may be repaired if the Damage Repair Team demonstrates that it could have repaired it. It does not have to be repaired during the drill to support other scenario events or'ata.

D. Investi ation of Possible Electrical Problem

1. The breaker on 4KV 2ENS*SWG102 is in the "trip free" position.

2. If the pump is attempted to be restarted, the breaker will close immediately trips on overcurrent.

3. A megger of the pump will prove no grounds exist.

7.3-6

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 Su lemental Scenario No 5 Failure of Dr ell S ra Valve 2RHS*MOV15B Time: 01:30 (8:00) (time approximate)

Location: Main Control Room and DW Spray Valve 2RHS*MOV15B, Elevation 281'NSTRUCTIONS A. Initial Notification The CSO is first made aware of the problem with the Drywell Spray Valve, 2RHS*MOV15B via message OC-9C at 01:30 when he attempts to use it when initiating Drywell Spray following the small break LOCA.

B. Postulated Event When the CSO attempts to open 2RHS*MOV15B from the Control Room in order to initiate Drywell Spray, the valve will not respond to control switch operation. When local manual operation is attempted by using the handwheel, the handwheel is found to turn without opening the valve. This occurs when the clutch is engaged or disengaged. When the handwheel is turned some resistance is felt and a grinding noise is heard to come from the drive gear area. If an operator is standing by to observe operation of the limitorque motor, he will hear the motor spin to a high pitch sound and hear a crunching sound coming from the operator gearing. The valve stem of 2RHS+MOV15 will never be observed to move during any of the efforts by the operators. The limitorque failure is due to a stripped worm gear and a stripped worm shaft in the valve operator.

C. Restoration Guidelines With the failure of 2RHS*MOV15 to open, the 'B'oop of RHR cannot be used for Drywell Spray. With the 'A'oop of RHR previously out-of-service, no capability of Drywell Spray exists. Drywell pressure will then increase. 2RHS*MOV15 must not be opened or fixed until 06:30 to allow the Drywell pressure to increase.

7.3-7

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 Su lemental Scenario No. 6 Failure of Su ression Pool S ra Valve RHS*MOV33B Time: 01:30 (08:00) (time approximate)

Location: Main Control Room and at S.P. Spray Valve 2RHS*MOV33B, Elevation 230'NSTRUCTIONS A. Initial Notification The CSO is first made aware of the problem with the Suppression Pool spray valve 2RHS*MOV33B via message OC-9C at 01:30 when he attempts to use it when initiating Suppression Pool Spray following the small break LOCA.

B. Postulated Event When the CSO attempts to open 2RHS~MOV33B from the Control Room in order to initiate Suppression Pool Spray, the valve will not respond to control switch operation. If attempted to be opened manually, it is jammed in the closed position. The motor-open torque switch de-energizes the motor. The motor driving too hard on a previous closure during a valve stroke timing test surveillance caused a chipped tooth on one of the reduction gears. The open attempt caused the gear piece to become lodged between the gears. This will preclude both manual and electric operation of the valve and will required opening the limitorque to remove the piece of gear which is wedged in between the gears.

C. Restoration Guidelines With the failure of 2RHS+MOV33B to open, the 'B'oop of RHR cannot be used for Suppression Pool Spray. With the 'A'oop of RHR previously out-of-service, no capability of Suppression Pool Spray exists.

Suppression Pool pressure will then increase. 2RHS*MOV33B must not be opened or fixed until 06:30 to allow the Suppression Pool pressure to increase. In order to preserve scenario data integrity, this spray valve must be repaired and opened at 06:30. The operators will be made aware of the successful repair via message DR-2.

D. Investi ation of Possible Mechanical Problem

1. The valve, when attempted to be operated manually, cannot be moved and is apparently frozen in place.

2. If the Limitorque gear casing is opened for inspection, will it reveal a piece of metal lodged between the drive gear and the valve operating gear. This piece of metal will be a piece of gear 7.3-8

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 tooth chipped off the valve operating gear. The Limitorque

.reduction gears will be operable upon the removal of the chip of gear tooth.

7.3-9

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 Su lemental Scenario No. 7 Division II Control Power Fails Time: 01:35 (08:05)

Location: Division II Swgr. Room INSTRUCTIONS A. Initial Notification The operators will be made aware of the Division II power failure at 01:35 via message OC-10.

B. Postulated Event It is postulated that a dead short occurs on the supply line from the battery chargers, the in line 800A breaker fails to open and draws an overcurrent on the Swgr. which trips the Battery Supply Breaker to the Swgr. Both Battery Charger Breakers trip open. This results in a complete loss of Division II 125V DC.

C. Restoration Guidelines The loss of Division II power is necessary to prevent the use of ADS to depressurize the Reactor. The Controller must not allow repair teams to re-establish power until 05:00. At this time, power must be restored to be capable to depressurize, re-establish RPV level and Vent the containment to begin the Radioactive Release to the environment. Controller will allow the damage repair team to re-energize ADS at 05:00. The operators will be made aware of the successful repair via message DR-1.

7.3-10

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 Su lemental Scenario No. 8 Failure of Control Rod Drive Pum B Time: 02:30 (09:00)

Location: At CRD Pump B INSTRUCTIONS A. Initial Notification The operators will be made aware of the CRD pump trip at 02:30 via message OC-12.

B. Postulated Event It is theorized that the interlock that causes the CRD Pump to trip on low suction pressure is actuated when the pump suction strainer becomes clogged. Once the pump trips the suction pressure switch fails and will not reset.

C. Restoration Guidelines The purpose of this failure is to cause a loss of high pressure sources of makeup water to the reactor. It must remain-failed until at least 05:00 at which time the reactor will be depressurized and CRD will no longer be required anyway.

OSC Damage Repair Team response to this failure is expected to first attempt'o manually valve out the block suction strainer while placing in service the standby strainer. At that time, if the CRD pump is attempted to be started, it will not respond since the low suction pressure interlock is still actuated. A broken terminal keeps the circuit open. This must be traced down and fixed or jumped prior to clearing the interlock.

If the repair team can successfully demonstrate repair of this failure prior to 05:00, the Controller should note this but declare the effort failed due to repair equipment failure. After 05:00, it can be declared operable upon successful demonstration of repair procedures.

7.3-11

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 Su lemental Scenario No. 9 Failure of Condensate Pum 2CNM-P1B Time: 03 00 (09:30)

Location: At Condensate Pump B INSTRUCTIONS A. Initial Notifications The Control Room will first learn of a failure of Condensate Pump B via message number OC-13 at 03:00.

B. Postulated Event It is theorized that a Condensate Pump Motor overload is caused by a seized lower motor bearing. It is postulated that the motor bearing is a candidate for replacement during the next refueling outage due to increased operating temperatures.

C. Restoration Guidelines The lower motor bearing seizure cannot be repaired during the time frame of the exercise. Complete removal of the motor tb the maintenance shop is required for the bearing replacement.

D. Investi ation of Possible Electrical Problem

1. The breaker on 2NNS-SWG011 is in the "trip free" position.

2. If the pump is attempted to be restarted, the breaker will close and immediately trips on overcurrent.

3. A megger of the pump will prove no grounds exist.

7.3-12

Nine Mile Point Unit: 2 1990 Annual Exercise Scenario No. 19, Rev. 1 Su lemental Scenario No. 10 PASS Time: 05:00 (11:30) (time approximate)

Location: PASS NOTE: This message is to be given to the PASS team as part of the initial briefing.

M~essa e'he Emergency Director requests that a PASS sample be taken the Reactor Coolant System for isotopic analysis.

off 7.3-13

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 Radiological SurveU and Conditions of PASS Access/Earess Rout.e RDS HCU'S 0 RR TRACK P ERSOINEL AND EQUIP HATCH

~

M IY RX H20 R 0 CLEANUP PIPE CHASE

~ EQUIP HATCH EMERG. ESCAPE CRD HATCH t

ELEY. HATCH'OIS YELL RDS na DOSE RATES AS FOUND 7.3-14

~ ~

~

~ II III I II I

~ ~

.~

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. le In-Line Monitor

'ASA Radiation Detectors Rl-507 Area Radiation Monitor Rl-665 Liquid Radiation Monitor O Rl-704 Cartridge Radiation Monitor ~t Lu From N2-CSP-13 A CL W ca Q~

(

CQ Rl-704 Readings:

During sample flow - 236 R/Hr After sample purge - 2000 mR/Hr

7. 3-16

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Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. le SAMPLE "DROP OFF" AND "TRANSPORT" CONSIDERATION UNSHIELDED SHIELDED (in DOSE RATE TRANSPORT i SAMPLE CONTACT 2 FOOT CONTACT 2 FOOT Undiluted RCS 236 R/hr 409 mR/hr 214 mR/hr 1 mR/hr Diluted RCS 23.6 R/hr 41 mR/hr 21 mR/hr 1 mR/hr All appropriate normal station radiological precautions to be observed assuming the radiological conditions present in this PASS scenario.

7.3-18

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. le

• NIAGARA MOHAWK POWER CORPORATION *

• NINE MILE POINT NUCLEAR STATION *

• RADIONUCLIDE ANALYSIS PROGRAM *

• GE-4 *

RUN DESCRIPTION: REACTOR WATER SAMPLE DATE TIME Sampling: 10/02/90 05:45 (12:15)

Counting: 10/02/90 06:30 (13:00)

Elapsed hrs 0.75 LIBRARY: LIB SAMPLE VOLUME: 10ml(cc)

COUNTING TIME: 150 sec QUANTITATIVE ANALYSIS ISOTOPE QUANTITY STD. DEVIATION 0 REL ERROR I-131 2.28E+04 uci/unit 2.912E+03 uci/unit 12.754 I-132 2.69E+03 uci/unit 3.790E+02 uci/unit 14.099 I-133 1.55E+04 uci/unit 2.058E+03 uci/unit 13.257 I-134 2.90E+03 uci/unit 3.849E+02 uci/unit 13.271 I-135 8.11E+03 uci/unit 9.320E+02 uci/unit 11.498 Total Iodine 5.20E+04 uci/unit Kr-85m 7.12E+00 uci/unit 8.999E-Ol uci/unit 12.636 Kr-87 5 '1E+00 uci/unit 7.027E-01 uci/unit 12.991 Kr-88 1.43E+01 uci/unit 1.732E+00 uci/unit 12.089 Xe-133 2.82E+02 uci/unit 3.556E+01 uci/unit 12.590 Xe-135m 4.72E+00 uci/unit 5. 320K-Ol uci/unit 11.276 Xe-135 4.25E+01 uci/unit 5.317E+00 uci/unit 12.521 Xe-138 2.64E+00 uci/unit 3.322E-01 uci/unit 12.594 Total Noble Gas 3.59E+02 uci/unit Te-132 4.07E+03 uci/unit 5.231E+02 uci/unit 12.854 Cs-134 4.29E+03 uci/unit 5.464E+02 uci/unit 12.735 Cs-137 6.50E+03 uci/unit 7.270E+02 uci/unit 11.193 Co-58 6.42E-05 uci/unit 7.157E-06 uci/unit 11.152 C0-60 1.45E-04 uci/unit 1.995E-05 uci/unit 13.758 Ce-141 1.09E-05 uci/unit 1.599E-06 uci/unit 14.645 Ba-140 1.45E-04 uci/unit 1.817E-05 uci/unit 12.555 La-140 9.98E-05 uci/unit 1.196E-05 uci/unit 11.991 Total Particulates 1.49E+04 uci/unit 1.0 MilliliterPASS Sample:Contact 236 Rem/Hr;Q2 ft. 409 mRem/Hr 0.1 MilliliterPASS Sample:Contact - 23.6 Rem/Hr;Q2 ft. 41 mRem/Hr Data to be provided to chemistry personnel. These data are not available for for use until T + 06:45 or until satisfactory acquisition andanalyses of sample has been demonstrated.

7.3-19

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rem. 1 8.0 DRILL MESSAGES

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 8.1 CONTROL AND CONTINGENCY MESSAGES

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 8.1 CONTROL AND CONTINGENCY MESSAGE

SUMMARY

Exercise Time Message Clock Time Number Messk e Summar 00 00 OC-1 Initial Conditions (06:30)

NMP2 is presently operating at 100% power.

The plant has been operating for a continuous run of 189 days with an average power of 93.4%. The last plant shutdown was for a refueling and maintenance outage which took 48 days.

The following operational considerations are active:

o RCIC is out-of-service for repair of a failed turbine support bearing. The RCIC turbine is dismantled and is expected to be repaired and ready for testing within 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />. RCIC was declared INOP 7 days ago. The LCO of Tech Spec 3.7 ' is in effect allowing a total of 14 days of continued operation.

' o With RCIC out-of-service, that maintenance would it rebuild was decided block valve MOV-121, since it has a badly leaking valve seat. The RCIC steamline isolation valves are closed and marked-up since MOV-121 is dismantled. It is expected that repairs to the valve will be completed within 24 hours.

o CRD Pump A is out-of-service for failed motor replacement.

o Condensate Pump C is out-of-service for pump bearing replacement.

o RHR Pump A out-of-service for electrical fault in the motor. The motor breaker tripped on overload during a surveillance test and a megger showed a phase to ground fault. The pump was declared inoperable 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ago and is isolated

'mechanically and electrically. Motor 8.1-1

~-

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 Exercise Time Message Number Messa e Summa 00:00 OC-1 repairs have commenced by a simulated (06:30) (Continued) maintenance cre'w and is expected to be completed within .48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. Tech Spec LCO 3.5.1 allows continued operation for a total of seven days with this pump out-of-service.

Weather conditions at this time are fair with seasonable temperatures. The wind is out of the NW at 10 mph.

The following alarms are presently active:

o 601305, "RCIC SYSTEM INOPERABLE" o 601431, "RHR A SYSTEM INOPERABLE" The following RCIC valves are isolated:

ICS*MOV128 ICS*MOV121 ICS*MOV129 ICS%'MOV136 ICS*MOV126 ICS*MOV143 0 The following RCIC valves are marked-up:

ICS*MOV128 ICS*MOV129 ICS*MOV136 ICS%'MOV126 ICS%'MOV143 00:25 OC-2 Unidentified Drywell Leakage High (06:55)

The Drywell Leak Rate Recorder indicate 6 gpm.

The following alarms are received in the Control Room:

o 851254, "PROCESS AIRBORNE RADN MON ACTIVATED" o 873115, "DRYWELL FLR. DRN. LEAK RATE HIGH" Drywell Floor Leakage Trip Unit in Trip Condition 8.1-2

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 Exercise Time Message Number Messa e Summar 00:25 OC-2 DRMS (06:55) (Continued)

CMS10A & 10B Red High Rad Alarm Number Name Location Current Alarm Level Type 74 CMS10A-1 RX289E 5.29E Red 83 CMS10B-1 RX289SW 5.31E Red ANTICIPATED RESULTS Station Shift Su ervisor SSS o Evaluate plant conditions and declare an UNUSUAL EVENT based upon the reactor coolant leakage greater than 5 gpm per S-EAP-2 "Classification of Emergency Conditions".

o Assume the duties of the Site Emergency Director (SED).

o Implement S-EAP-l, "Activation and Direction of the Emergency Plan".

o Implement S-EPP-20, "Emergency Notifications" and complete Part I of the Notification Fact Sheet.

o Identify the LCO of Tech Spec 3.4.3.2.

o Commence preparation for plant'hutdown per N2-0P-101D.

00'40 OC-3C If not already done, an UNUSUAL EVENT should (07:10) 'be declared at this time based upon reactor coolant leakage exceeding 5 gpm.

00:45 OC-4 Condensate Pump A Trips (07:15)

The following alarms are received in the Control Room:

o 851456, "CNST SYSTEM TROUBLE/NO BACK-UP PMP AVAILABLE" 8.1-3

b II

4 Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 Exercise Time Message Number Messa e Summar 00:45 OC-4 o 851511, "CONDENSATE PUMP 1A/1B/1C AUTO (07:15) TRIP FAIL TO START" o 851521, "CONDENSATE PUMP lA/1B/1C MOTOR ELECTRIC FAULT" o 851533, "CONDENSATE BOOSTER PUMP SUCT HEADER PRESS LOW" Condensate Pump 1A red 1'ight "off", green light "on" Antici ated Results o Identify failure of Condensate Pump and secure corresponding Condensate Booster Pump and Feed Pump.

CONTROLLER'S NOTE: SEE SUPPLEMENTAL SCENARIO NO. 1.

01:10 OC-5 Fire in DIV I 125V DC Switchgear - Pnl 128 (07:40) (Fire Zone 333XL, DIV I Swg. Rm 261)

-0 The SGTS The activates.

following alarms are received in the Control Room:

Fire Detected Pnl 128 W Wall/261 FPL-AOV 106 Red Discharge o 852103, "EDGl SYSTEM INOPERABLE" o I 852106, "DIVISION LOAD CENTER EJS SYSTEM INOPERABLE" o 852108, I "DIVISION EHER BUS BYS 002A 125 VDC SYSTEM TROUBLE" o 852111, "EDGl ELECTRICAL SYSTEM TROUBLE/TRIP" o 852116, I "DIVISION UPS 2A SYSTEM TROUBLE" o 852119, "EDG1 DC CONT POWER FAILURE" o 852123, "4KV BUS 101 DC CONT POWER FAILURE" o 601503, "DIVISION I ADS SYSTEM INOPERABLE" o 601538, "SAFETY/RELIEF VALVES POWER FAILUREH o 852345, "DIV I/II/III125 VDC BATTERY BREAKER OPEN" 8.1-4

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 Exercise Time Message Number Messa e Summar 01:10 OC-5 o 601721, "DIVISION I SLCS STOR TANK LVL (07:40) (Continued) LOW" o 842101, "BOP DIV I ISOLATOR CARD OUT-OF-FILE/LOSS OF POWER" o 602218, "DIV I NSSSS ISOL SIGNAL" o I 870104, "DIVISION RAD MON ABOVE REFUELING FLR AIR FLOW LOW" o 870112, "DIVISION I RAD MON BELOW REFUELING FLR AIR FLOW LOW" o 603440, "DIVISIONS I/II RRCS OUT OF SERVICE" o 602101, "RECXRC FCV A HYDRAULICS INOPERABLE" o 602102, "RECIRC FCV B HYDRAULICS INOPERABLE" o 602103, "RECIRC FCV A BACKUP HYDR INOPERABLE" o 602104, "RECIRC FCV B BACKUP HYDR INOPERABLE" o 602105, "RECIRC FCV A MOTION INHIBIT" o 602106, "RECIRC FCV B MOTION INHXBIT" o 601124, "SERVICE WATER SYSTEM TROUBLE" o 601538, "SAFETY/RELIEF VALVES POWER FAILURE" o 842204, "REACTOR BLDG VENT/GLYCOL SYSTEM TROUBLE" ANTICIPATED RESULTS Chief Shift 0 erator o Identify the fire and implement N2-OP-47 "Fire Detection".

o At the direction of the SSS, sound the station fire alarm and announce the emergency condition over the page system.

o Identify loss of Recirc flow and trip the plant manually in accordance with N2-OP-101 "Sudden Decrease in Core Flow".

o Identify loss of Div I Station Shift Su ervisor SED o Evaluate plant conditions and declare an ALERT based upon a fire potentially affecting safe shutdown equipment per S-EAP-2, Classification of Emergency Conditions.

8.1-5

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 Exercise Time Message Number Messa e Summar 01:10 OC-5 o Implement S-EPP-2, "Fire Fighting".

(07 40) (Continued) o Implement S-EPP-20, "Emergency Notifications".

o Complete Part I of the Notification Fact Sheet.

o Oversee activation of the TSC and'the OSC.

Site Emer enc Director o Report to the TSC.

o Oversee activation of the EOF and the JNC.

OSC Coordinator o Report to the OSC.

o Coordinate and supervise emergency response operations in the OSC.

o Establish communications with the TSC.

o Assign personnel to emergency functions as directed by the TSC.

Cor orate Emer enc Director Recover

~Mana ar o Report to the EOF.

o Activate and direct the nearsite emergency support organization and coordinate its response with the onsite emergency organization.

o Direct and coordinate corporate support activities.

o Provide advice and guidance to the Site Emergency Director.

JNC Director o Report to the JNC.

8.1-6

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 Message Number Messa e Summar 01:20 OC-6 o Provide news releases to the media, (07:50) public officials and the general public as necessary.

CONTROLLER'S NOTE: SEE SUPPLEMENTAL SCENARIO NO. 2.

Control Room Operators manually trip the plant.

o Loss of Condenser Vacuum o Leak rate increases The following indications are observed in the Control Room:

o Pilot Scram Valve Solenoids'hite lights all go out.

o The Full Core Display indicates the following:

All blue "SCRAM" lights ON.

All amber "ACCUM" lights flashing.

All red "DRIFT" lights ON.

All green "FULL IN" ligHts ON.

o APRMS indicate downscale.

The following alarms are received in the Control Room:

o 603101, "RPS A DRYWELL PRESSURE HIGH TRIP" o 603105, "RPS A REACTOR WTR LEVEL LOW TRIP" o 603109, "RPS A DISCH VOLUME HIGH LEVEL TRIP" o 603110, "RPS A -AUTO TRXP" o 603111, "RPS A MANUAL TRIP" o 603112, "RPS A CONT 6 STOP V CLOSURE BYPASSED" o 603116, "RPS A MSIV CLOSURE TRIP BYPASSED" o 603124, "RPS A MODE SWITCH SHUTDOWN SCRAM BYPASS" o 603130, "SDV LEVEL HIGH" o 603202, "APRM TRIP SYSTEM A UPSCALE/

INOPERABLE"

8. 1-7

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 Exercise Time Message Number Messa e Summar 01:20 OC-6 603208, "APRM TRIP SYSTEM UPSCALE" (07:50) (Continued) 603211, "LPRM DOWNSCALE" 603213, "IRM DOWNSCALE" 603214, "APRM TRIP SYSTEM DOWNSCALE" 603302, "APRM TRIP SYSTEM B UPSCALE/

INOPERABLE" 603306, "CRD SCRAM VALVE PILOT AIR HDR PRESS HIGH/LOW" 603402, "RPS B NMS TRIP" 603405, "RPS B REACTOR WTR LEVEL LOW TRIP" 603409, "RPS B DISCH VOLUME HIGH LEVEL TRIP" 603410, "RPS B AUTO TRIP" 603411, "RPS B MANUAL TRIP" 603412, "RPS B CONT & STOP V CLOSURE BYPASSED" 603416, "RPS B MSIV CLOSURE TRIP BYPASSED" 603424, "RPS B MODE SWITCH SHUTDOWN SCRAM BYPASS" 603433, "SDV DRAIN AOV 123 CLOSED" 603434, "SDV DRAIN AOV 130 CLOSED" 603435, "SDV VENT AOV 124 CLOSED" 603436, "SDV VENT AOV 132 CLOSED" 603440, "DIVISION I/II RRCS OUT-OF-SERVICE" 603441, "ROD DRIVE ACCUMULATOR TROUBLE" 603442, HCONTROL ROD OUT ROD DRIFT" BLOCK/'CONTROL 603443, 603104, "RPS A TURB CONT VLV FAST CLOSE TRIP" o . 603106, "RPS A TURB STOP VLV CLOSURE TRIP" 603404, "RPS B TURB CONT VLV FAST CLOSE TRIP" 603406, "RPS B TURB STOP VLV CLOSURE TRIP" 851109, "TURBINE TRIP" 851358, "TURBINE CNSR A/B/C VACUUM LOW" 852217, "EDG 3 RUNNING" 852317, "EDG 2 RUNNING" 852540, "13.8KV BUS NPS 001 ACB 1-1/1-3/

1-18 AUTO TRIP/FTC" 852560, "13.8KV NPS 003 ACV 3-1/14/18 AUTO TRIP/FTC" 603108, "RPS A MSIV CLOSURE TRIP" 8.1-8

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 Message Number Messa e Summar 01:20 OC-6 o 603401, '"RPS B DRYWELL PRESSURE HIGH (07:50) (Continued) TRIP" o 603408, "RPS B MSIV CLOSURE TRIP" o 601402, "DIVISION I RHR/LPCS DRYPELQ PRESS HIGH" o 601426, "LPCS SYSTEM ACTUATED" o 601602, "DIVXSION II RHR DRYWELL PRESS HIGH" ANTICIPATED RESULTS Chief Shift 0 erator o Identify loss of Condenser Vacuum o Identify increased RCS leakage Station Shift Su ervisor o Implement EOPs for Containment Control and RPV Control CONTROLLER'S NOTE: SEE SUPPLEMENTAL SCENARIO NO. 3.

01:25 OC-7C If not already done, an Alert should be (07:55) declared at this time based upon a fire potentially affecting safe shutdown equipment.

01:25 OC-8 HPCS starts and immediately trips.

(07:55)

The following indications are received in the Control Room:

o 601707, "HPCS DRYWELL PRESSURE HIGH" o 601710, "HPCS PUMP 1 MOTOR ELECT FAULT" o 601728, "HPCS PUMP 1 AUTO TRIP/OUT-OF-SER" CONTROLLER'S NOTE: SEE SUPPLEMENTAL SCENARIO NO. 4.

01:30 OC-9C Efforts to Spray the Drywell or Suppression (08:00) Pool fail. If the operators attempt to line up Sprays the following indications are received in the Control Room:

o Drywell Spray Valve 2RHS4'MOV15B Red Light "OFF", Green Light "ON".

8.1-9

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 Exercise Time Message Number Messa e Summar 01:30 OC-9C o Suppression Pool Spray Valve 2RHS*MOV33B (08:00) (Continued) Red Light "OFF", Green Light "ON".

CONTROLLER'S NOTE: SEE SUPPLEMENTAL SCENARIO NOS. 5 & 6.

01:35 OC-10 Division II 125 VDC Control Power fails.

(08 05)

The following alarms are received in the Control Room:

o 842107, "BOP DIV II ISOLATOR CARD OUT-OF-FILE/LOSS OF POWER" o 852203, "EDG 3 SYSTEM INOPERABLE" o 852206, "DIVISION II LOAD CENTER EJS SYSTEM INOPERABLE" o 852208, "DIV II EMER BUS BYS 002B 125VDC SYSTEM TROUBLE" o 852211, "EDG 3 ELECTRICAL SYSTEM TROUBLE/

TRIP" o 852216, "DIVISION II UPS 2B SYSTEM TROUBLE" o 852219, "EDG 3 DC CONT POWER FAILURE" o 852223, "4KV BUS 103 DC CONT POWER FAILURE" o 852345, "DIV I/II/III125 @DC BATTERY BREAKER OPEN" o 602224, "DIV II NSSSS ISOL SIGNAL" o 603440, "DIVISION I/II RRCS OUT-OF-SERVICE" o 602314, "RWCU PUMP 1A/1B AUTO TRIP" o 602317, "RWCU FILTER DEMIN 1 TROUBLE" o 602321, "RWCU DISCHARGE PRESSURE HIGH/

LOWN o 601124, "SERVICE WATER SYSTEM TROUBLE" o 601504, "DIVISION II ADS SYSTEM INOPERABLE" o 601601, "RHR C SYSTEM INOPERABLE" o 601631, "RHR B SYSTEM INOPERABLE" o 601653, "DIVISION II RHR ISOLATOR 125V POWER FAILURE" o 601722, "DIVISION II SLCS STOR TANK LVL LOW" o 871107, "REACTOR BLDG UNIT CLR 413B AIR FLOW LOW" 8.1-10

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 Exercise Time Message Number Messa e Summar 01:35 OC-10 o 871104, "DIVISION II RADN MON ABOVE (08:05) (Continued) REFUELING FLR AIR FLOW LOW" o 871112, DIVISION II RADN MON BELOW REFUELING FLR AIR FLOW LOW" ANTICIPATED RESULTS Chief Shift 0 erator o Continue implementing actions directed by the SSS per Primary Containment Control EOP.

o Identify loss of Div II.

Station Shift Su ervisor Station Su erintendent o Inform SED of new plant conditions.

o At the direction of the SSS announce the emergency condition over the Gai-Tronics.

Site Emer enc Director o 'nform the CED and TSC staff of the changing plant status' Evaluate plant conditions and declare a Site Area Emer enc based on loss of Div I and Div II DC Power for greater than 15 minutes.

o Implement S-EPP-5 Station Evacuation and S-EPP-20, "Emergency Notifications".

o Direct the Maintenance Coordinator to initiate restoration operations.

Ma ntenance Coordinator o Direct the OSC Coordinator to assemble a damage repair team to investigate and repair Div II.

CONTROLLER'S NOTE: SEE SUPPLEMENTAL SCENARIO NO. 7.

8.1-11

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 Exercise Time Message Number Messa e Summar 01:55 DC-1C If not already done,.a Site Area Emergency (08:25) should be declared at this time.

02:00 OC-11 Safety Relief Valves lift for RPV Control.

(08:30)

The following alarms are received in the Control Room:

o 601537, "ADS VALVES/SAFETY VALVE LEAK" o 601548, "SAFETY/RELIEF VALVES OPEN" 02:30 OC-12 CRD Pump "B" Trips (09:00)

The following alarms are received in the Control Room:

o 603308, "CRD PUMP lA/1B AUTO TRIP" o 603310, "CRD PUMP 1A/1B TROUBLE" o 603315, "CRD PUMP 1B SUCTION PRESSURE LOW" o 603311, CRD CHARGING WTR PRESSURE LOW" ANTICIPATED RESULTS Station Shift Su ervisor Station Su erintendent o Inform SED of new plant conditions.

Site Emer enc Director o Direct the Maintenance Coordinator to initiate restoration operations.

o Initiate onsite and offsite radiological monitoring.

Maintenance Coordinator o Direct the OSC Coordinator to assemble a damage repair team to investigate and repair CRD Pump.

CONTROLLER'S NOTE: SEE SUPPLEMENTAL SCENARIO NO. 8.

03 00 OC-13 . Condensate Pump B Trips (09 30)

The following alarms are received in the Control Room:

8.1-12

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 Exercise Time Message Number Messa e Summar 03:00 OC-13 o 851456, "CNST SYSTEM TROUBLE/NO BACKUP (09:30) (Continued) PUMP AVAILABLE" o 851503, "CNST BSTR PMP 2A/2B/2C SUCTION PRESS LOW" o 851511, "CONDENSATE PUMP 1A/1B/1C AUTO TRIP FAIL TO START" o 851512, "CNST BSTR PMP 2A/2B/2C AUTO TRIP FAIL TO START" o 851513, "CNST BSTR PMP 2A/2B/2C SUCTION PRESS LOWN o 851521, "CONDENSATE PUMP lA/1B/1C MOTOR ELEC FAULT" o 851533, "CONDENSATE BOOSTER PUMPS SUCT HDR PRES LOW" o 851539, "REAC FEED PMP lA/1B/1C SUCTION PRESS LOW/LO-LO" Chief Shift 0 erator o Identify loss of condensate pump.

o At the direction of the SSS announce emergency over the Gai-Tronics.

Station Shift Su ervisor Station Su erintendent o Inform SED of new plant conditions.

Site Emer enc Director o Inform the Maintenance Coordinator of the trip of the condensate pump.

o Evaluate plant conditions and declare a GENERAL EMERGENCY based upon a LOCA with failure of decay heat removal systems per S-EAP-2.

o Initiate onsite and offsite radiological monitoring activities.

o Consider declaration of a Site Evacuation per S-'EPP-19.

o Implement S-EPP-7 Downwind Radiological monitoring and S-EPP-8 onsite and offsite Dose Assessment.

8.1-13

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 Exercise Time Message Number Messa e Summar 03:00 OC-13 CED (09 30) (Continued) o Brief JNC Director.

o Advise State and local agencies.

o Cooperate with NYS Department of Health officials in the collection of and analysis of sampling data.

o Collaborate with NYS Department of Health officials in determining the need for and the extent of protective actions to be taken and/or recommended to the general public.

Station Surve Sam le Team Coordinator o Assemble Station Survey/Sample and Environmental Sample/Survey teams from available personnel.

JNC Director o Provide press releases to public officials, the press and the general public.

CONTROLLER'S NOTE: SEE SUPPLEMENTAL SCENARIO NO. 9.

03:15 DC-2C If not already done, a General Emergency (09:45) should be declared at this time.

03:22 OC-14 RPV level continues to decrease. The (09:52) following alarms are received in the Control Room:

o 601708, "HPCS REACTOR WATER LEVEL LOW" o 603125, I "DIVISION REACTOR WATER LEVEL LO-LO" o 603425, "DIVISION II REACTOR WATER LEVEL LO-LO" 03:50 OC-15 RPV level continues to decrease. The (10:20) following alarms are received in the Control Room:

o 601403, "DIVISION I RHR/LPCS REAC WTR LVL LOW" 8.1-14

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 Exercise Time Message i Number Messa e Summar 03:50 OC-15 ' 601539, "ADS A LPCS/RHRA PERMISSIVE" (Continued), o 601540, "ADSB RHRB/RHRC PERMISSIVE" o 601603, "DIV II RHR REAC WTR LVL LOW" 05:00 DR-1 Division II Power restored. RPV (11:30) depressurized and Containment Vent is initiated.

CONTROLLER'S NOTE: SEEE SUPPLEMENTAL SCENARIO NO. 7 ANTICIPATED RESULTS Station Shift Su ervisor o Request RCS sample from PASS system 06:30 DR-2 , Repairs to Suppression Pool Spray Valves (13:00) 2RHS+MOV33B are complete.

CONTROLLER'S NOTE: SEEE SUPPLEMENTAL SCENARIO NO. 6 ANTICIPATED RESULTS SSS o Directs CSO to spray the Suppression Pool.

CSO o Initiate Suppression Pool Spray to reduce Containment Pressure.

o Secure Containment Purge.

07:00 OC-16 The plant is in stable condition.

(13:30) o RPV Level 200" o Reactor Coolant Temp 213 F o Containment Purge is secured.

o Containment Pressure is 3.5 psig and

'ecreasing ANTICIPATED RESULT SSS Station Su erintendent o Inform the SED of the new plant conditions.

8.1-15

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 Message Number Messa e Summar 07:00 OC-16 SED (13:30) r o Confer with the CED on the positive turn of events.

07:01 DC-3 At this point, the exercise will be (13:31) suspended for 15 minutes. When drill resumes at 07:15, it is assumed to be October 4, 1990.

When drill is resumed, plant conditions will be as follows:

o The reactor is shutdown and cooled down and is being maintained using shutdown cooling.

o Release rate to the environment have been reduced to pre-emergency levels.

o Containment isolation has been ensured.

o Drywell pressure is normal.

o Other status is as listed on plant data sheets.

07:15 DC-4 It is now October 4, 1990 (13:45)

ANTICIPATED RESULTS

~CED RN o Enter recovery phase per S-EPP-25.

o Confer with NRC on all matters relating to emergency termination and recovery.

o Review PARs and modify as appropriate.

o Convene meeting of SORC and Safety Review and Audit Board to obtain concurrence that emergency situation is resolved.

o Declare the Emergency Phase terminated.

o Inform the EOF staff of the positive turn of events and notify offsite emergency management agencies.

8.1-16

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 Exercise Time Message i Number Messa e Summar 07:15 DC-4 o Inform the JNC Director.

(13:45) (Continued) o Advise State and local agencies.

o Amend PARs as required.

JNC Director o Amend news releases to inform the media and the public.

SED o Make notifications as appropriate.

o Establish recovery priorities in conjunction with the CED/RM.

08:00 DC-5 The exercise is terminated once recovery has (14:30) been demonstrated.

8.1-17

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 8.2 RUMOR CONTROL

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 8.2 RUMOR CONTROL/INQUIRY MESSAGE SUMMARIES TABLE OF CONTENTS Section Title ~Pa e 8.2 Rumor Control/Inquiry Message Summaries 8.2-1 Rumor Control A. General Inquiries 8.2-1 B. Potassium Iodide Inquiries 8.2-2 C. Howard Stern's Misinformation 8.2-3 D. Trapped Men Rumor 8.2-4 8.2-2 Financial Inquiries 8.2-5 8.2-3 Media Inquiry Calls 8.2-7 8.2-4 NRC Inquiries 8.2-9

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 8.2.1 Rumor Control A. General Inquiries (G Series)

This is Helen Winters of the Minetto Nursery Program, should I call the parents and tell them not to bring the children in for the afternoon sessions?

Hi, my name is Father Sullivan at the Fulton Catholic School. Should we cancel this afternoon's after school programs because of the problem over there at the plant?

Good morning.

troopers gave This is me this Tom number King of King Construction.

to call for information. I'e state The got a bunch of heavy equipment over on the Route 29 in South Scriba . How much time do it I have to get out of there before it gets crapped up?

This is Barbara Brown of the Oswego County Farm Bureau. I always knew that plant was going to be the death of us all. What can I tell the farmers'? Is this problem going to get worse or is it going to be brought under control shortly?

My name is Bill Sheenan. I represent the Nuclear Information and Resource Service. When are you going to make available an accurate accounting of the fuel inventory you'e pumping out into the environment and where can I get a copy?

This is the Post Person in Lycoming. I heard about the problem at the plant, is there going to be a release? If there is, I don't want to start the mail runs.

8.2-1

Nine Mile Point Unit 2 e 1990 Annual Exercise Scenario No. 19, Rev. 1 8.2.1 Rumor Control B. Potassium Iodide Inquiries (KI Series)

This is Joe Giuffre. The fire house gave me your number, I heard about the accident, if we have to evacuate and I have to leave my dogs behind, can I give them Potassium Iodide? Where can I get some?

My cousin called me from Rockland County down by Indian Point and told me that I should get some Potassium Iodide to protect me from the noble gases. Where can I buy it?

My brother used to be in the Civil Defense and sent me a bottle of Potassium Iodide about 2 years ago. How long is its shelf life?

Hi, this is Merna Shampanire. My vitamins have extra iron in them.

Can I take an extra dose of them to protect myself from the gases instead of the Potassium Iron Tablets?

Where can I get some of those pills to protect you from radiation sickness?

8.2-2

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 8.2.1 Rumor Control C. Howard Stems'isinformation (HS Series)

My brother called me from NYC and told me that he heard a WXRX interview with the Control Room Operator and they said to look for the mushroom cloud at about noon. Are they going to send the buses out before then?

My mother called me from Long Island. She was very upset, some jerk on the radio down there is saying that a cloud of noble gases melted the tires on all the cars at the speedway. Is there anything you can do to stop that kind of stuff? It was Howard Stern on WXRX 92.3 FM.

This is Joe Keller, in Purchasing at Salina Meadows, I was just on the phone with a vendor in White Plains and they told me that Howard Stern on WXRX announced that the NY State Police were quarantining everyone leaving the Oswego area so that they don't spread radiation sickness and advising everyone to get their radiation vaccines. Can we get the FCC or NRC to stop this guy?

My name is Tom Lake. I'm listening to a New York FM radio station WXRX and they made a statement to the effect that NMPC is controlling the release of radiation to the environment, that you are "Nuking" the public and why don't you just lock the door and walk away for 10 years or maybe 20,000 years from the plant. Can he get away with saying that? Are you really deliberately releasing the radiation?

My cousin called me from New York City and said he heard on a radio interview with the control room operators that they were scramming.

Do they really abandon the power plant during an accident?

8.2-3

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 8.2.1 Rumor Control D. Trapped Men Rumor (T Series)

(To be called in after fire in the switchgear room is announced)

This is Steve Baker of the International Brotherhood of Electrical Workers Union. One of our members called in and said that there were men trapped in the control building where that fire is. Do you have the names of the trapped men, were any of them electrical contractors?

2. My name is Cindy Greens. I heard at the supermarket that NMPC sealed a switchgear room with men inside and flooded it with C02. My if husband is an RP tech at that plant. Can I find out he is OK, that he's not one of the ones trapped behind those locked doors in the room?

This is Rosemary Pooler of Atlantic States Legal Foundation. Is it true that the NMPC closed the automatic locking fire doors on a switchgear room sealing a bunch of workers inside, like that Cher movie about Karen Silkwood. That's not legal you are violating those worker legal rights.

This is Rocco of Cataract. Can I find out if any of Cataract's I&C tech's were involved in the lock up at the control building? One of my guys called and said that two tech's were locked in the fire area.

8.2-4

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 8.2.2 Financial In uiries Most insurance policies exclude coverage in the event of a nuclear accident and Price Anderson has a determination clause before it kicks in. Does NMPC plan to cover the losses incurred that are not covered by insurance'?

With the history of problems at Unit 1 and now this at Unit 2, does NMPC plan to retire the station or do they intend to try to restart it after clean up?

The NRC kept Metropolitan Edison and GPU from operating their second unit at the site for a number of years after the accident. Do you anticipate the NRC allowing you to restart Unit 1?

Do you foresee any lawsuit involving equipment manufacturers to recover the costs of the accident? Who manufactures the pumps that failed? Who installed those pieces of equipment?

How long can NMPC meet its cash flow commitments with the loss of revenues due to the accident before declaring Chapter XI?

How does NMPC intend to finance their recovery effort?

Are any of the investors of Unit 1 liable for any of the site related recovery costs?

I hear the Joint Owners of Unit 2 are unhappy. Do you foresee any management reorganization at Nine Mile 2 due to the way NMPC has managed Unit 2?

Do you anticipate that the Security and Exchange Commission will suspend trading of NMPC stock?

10. What do you foresee as your immediate cash flow needs within the next few weeks and how does NMPC plan to cover these costs'?

Does NMPC foresee an emergency rate increase request going to the PSC?

12. How long before the accident impacts the electric bills?

13. Does NMPC plan to ask Oswego County for tax relief based on the reduction in value of Unit 2.

Was the fire due to a lack of maintenance'?

15. How much does NMPC project it will cost to clean up Unit 2?

16. How long before NMPC has developed a business plan for the recovery effort?

8.2-5

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1

17. Is it true that NMPC has laid off most of the Unit I and II support result of the accident?

staff as a cash conservation measure as a

18. How much will the use of replacement power impact the rate payer?

19. Does NMPC have to bear the cost of supplying replacement power for Unit 1 being off line?

20. I understand that the joint owners of Unit 2 are unhappy and are blaming NMPC for the accident. Can you confirm that LILCO (the Long Island Lighting Company) has been designated by the joint owners to head the management of the recovery efforts?

8.2-6

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 8.2.3 Media In uir Calls This is Ted Dancing of the Herald Journal, can you give us any information on the fire fighters that were fighting the fire in the plant? Can we talk to the fire fighters?

This is John Dar'ing of the Post Standard, can you explain to me the differences between a filtered and unfiltered release?

This is the Nuclear Information and Resource Service. Why don't they stop the ventilation systems and stop the release?

My name is Harry Johnson of the Red Creek Journal. When you attempt to depressurize the reactor, do you anticipate a TMI type Hydrogen bubble?

How much waste water storage capacity do you have on Site?

Are you planning to building TMI style hold up tanks?

How much low level waste will the accident generate?

Where are you going to store this low level waste?

Is the Nine Mile Site going to become a de facto low level waste storage facility as a result of the accident?

10. At TMI, they eventually dumped all the low level waste into the river. Are you going to eventually dump the water in the turbine building back into the lake?

This is Paul Jacobs of the Palledium Times. What is the difference between an elevated release and a ground level release?

12. This is Channel 9 News, as the local station, we would like to be designated as the lead station for pool coverage, who do we talk to?

Bonjour. Je m'apple Jean-Louis Fougard de Radio Canada. On vondrait

.demande'uelques question au sujet de 1'accident a'a centrale nucleaire chez vous.

This is the Wayuaga Community News, how do you foresee the accident impacting the jobs at the plant?

15. This is Betty Davis of Channel 10 News, how much of the core was damaged? How does that relate to the TMI accident?

Has anyone been hurt?

17. Has NMPC sealed the turbine building?

8.2-7

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 John Wells, WSIR Radio. Can we get a fly over of the site? Can we get an aerial picture of the plume?

This is the Herald American. Can I get some background information to do a feature on the guys who fixed the valves?

8.2-8

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 8.2.4 NRC In uiries What were the results of the last reactor coolant sample, and when was it taken?

(After the Alert)

Specifically where is the fire2 Was any safety related equipment damaged by the fire?

Specifically, were any system functions compromised?

Why didn't the CO> system work2 (If the CO~ isolation valve is identified as the source of the problem) Do you know the specific make and model of the valve2 What is Reactor Pressure and Level?

When do you anticipate being in cold shutdown?

What is your prognosis for emergency termination?

Do you require any federal support at this time?

Is there any release?

What protective action recommendations have been made to the offsite people?

What is the County doing?

After 01:30 (08:00), when contacted by control room with status change 0 What is the condition of the core?

0 What caused the decrease in core flow?

0 Do you have control of the reactor2 0 Do you have adequate make-up water for the reactor?

0 Have you postulated the source of drywell pressure increase?

0 Are the areas you have to get to for damage control accessible?

0 What type of dose commitment are you projecting for the damage control teams?

What is your prognosis for emergency termination?

Do you require any federal support at this time'2 What is the reactor level?

What is the magnitude of release?

What protective action recommendations have been made to the offsite people?

~ 0 What is the County doing?

After 03:00 (09:30)

Have you determined how you can depressurize the vessel?

What is your prognosis for emergency termination?

Do you require any federal support at this time?

What is the reactor level?

When do you project reaching the top of the core?

8.2-9

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 After 03:00 (continued)

Have you detected any releases to the environment?

What protective action recommendations have been made to the offsite people?

What is the County doing?

After 04:00 (10:00)

What is your prognosis for emergency termination?

Do you require any federal support at this time?

What is the reactor pressure?

What is the magnitude of release?

What protective action recommendations have been made to the offsite people?

What is the County doing?

After 06:00 (12:30)

What is the status of the repairs?

What is Reactor Pressure and Level doing?

What was the de-escalation criteria used?

When can we discuss your first draft of the incident report?

What is the status of offsite protective action implementation?

8.2-10

0 Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 9.0 PLANT PARAMETERS DATA TABLES

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 9.0 PLANT PARAMETERS DATA TABLES TABLE OF CONTENTS Section Title ~Pa e 9.1 Plant Parameters Data and Equipment Status 9.1.1 Plant Parameters Data 9.1-1 9.1.2 Plant Equipment Status 9.1-5 9.2 DRMS Data 9.2.1 Area Radiation Monitors 9.2-1 9.2.2 Continuous Air Monitors 9.2-7 9.2.3 Process Monitors 9.2-12 9.2.4 Monitor Information 2 Days Later 9.2-22

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 9.1 0 erational Data

Nine Hile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 TABLE 9.1.1 PLANT PARAMETER DATA TIME 00:00 00:15 00:30 00:45 01 00 01:10 01 15 01:20 01:25 01:30 01:35 (06:30) (06:45) (07:00) (07:15) (07:30) (07:40) (07:45) (07:50) (0? 55) (08:00) (08:05)

~REACTOI! CORE Level inches 182.3 182.3 182.3 182.3 182.3 182.3 182.0 141.0 180.0 190.0 185.0 Pressure pslg 1005.0 1005.0 1000.0 950.0 945.0 940.0 938.0 930.0 920.0 800.0 700.0 Power )ps 100% 100% 85% 45% 38% 31% 26% 1.0 2000 cps 1500 cps 1000 cps Rx Recirc Flow Loop A x 106lbm/hr 54.0 54.0 41.0 24.3 24.1 24.0 23.9 8.0 8.0 8.0 8.0 Rx Recirc Flow Loop B 10 ibm/hr 54.0 54 ' 41.0 24.3 24.1 24.0 23.9 8.0 8.0 8.0 8.0

~

Recirc Suction Temperature F 532.0 532.0 530.0 527.0 525.0 524.0 524.0 524.0 536.0 520.0 505.0 PRIHARY SECONDARY CONTAINHENT Drywall Pressure ps 1 g 0 0.7 0.7 0.7 0.7 0.7 0.7 0.7 1.0 2.0 3.0 4.0 Drywell Temperature max. F 130.0 130.0 130.0 130.0 130.0 130.0 130.0 132.0 155.0 175.0 200.0 avg. F 120.0 120.0 120.0 120.0 120.0 120.0 120.0 122.0 150.0 175.0 195.0 Drywell Oxygen / 1 ~ 0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 Drywell Hydrogen 0.1 0.1 0.1 0.1 0.1 0.1 0.1 0.1 0.1 0.1 0.1 Suppression Pool Level feet 200.0 200.0 200.0 200.0 200.0 200.0 200.0 200.0 200.0 200.0 200.0 Suppression Pool Temp. F 78.0 78.0 78.0 78.0 78.0 78.0 78.0 78.0 79.0 86.0 93.0 Suppression Pool Pressure Pslg 2 0.5 0.5 0.5 0.5 0.5 0.5 0.5 0.5 0.5 1.0 2.0 Reactor Building dP in. HO -0.5 -0.5 -0.5 -0.5 -0.5 -0.5 -0.5 -0.25 -0.25 -0.25 -0.25 SBGTS sejm 0.0 0.0 0.0 0.0 0.0 2600. 2600. 2600. 2600. 2600. 2600.

Total Station Stack Flow 103scfm 82.17 82.17 82.17 82.17 82.17 84.77 84.77 84.77 84.77 84.77 84.77 Total Station Vent Flow 10 scfm 232.99 232.99 232.99 232.99 232.99 92.99 92.99 92.99 92.99 92.99 92.99 BALANCE OF PLANT Hain Generator Power MWe )gross) 1170.0 1170.0 995.0 527.0 445.0 362.7 304.2 0.0 0.0 0.0 0.0 Total Feedwater Flow x 106 ibm/hr 14.3 14.3 12.2 6.4 5.4 4.4 3.7 2.0 1.0 0.1 0.1 Total Steam Flow x 10 ibm/hr 14.3 14.3 12.2 6.4 5.4 4.4 3.7 0.0 0.0 0.0 0.0 Hain Condenser Vacuun " Ng vac. 28.5 28.5 28.8 29.1 29.2 29.2 29.2 29.0 22.0 15.0 7.0 ECCS RCIC Flow gpm 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 MPCS Flow x 10 gpm 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 RHR A Flow x 100 gpm 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0 '

RHR B Flow x 100 gpm 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 74.5* 74.5*

RHR C Flow x 100 gpm 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 LPCS Flow x 100 gpm 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 MAKEUP STORAGE CST A Level Feet 37.6 37.6 37.6 37.6 37.6 3?.6 37.6 37.6 37.5 37.5 37.4 CST B Level Feet 37.6 37.6 37.6 37.6 37.6 37.6 37.6 37.6 37.5 37.5 37.4 Motwell Level Inches 24.0 24.0 24.0 24.0 24.0 24.0 24.0 24.0 24.0 24.0 24.0 Suppression Pool Cooling Hode

• • LPCI Hode

• • • CSL Throttled to Control Level

++ SP Cooling Hode I

9.1-1

Nine Hile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 TABLE 9.1.1 PLANT PARAMETER DATA T IHE 01:45 02 00 02:15 02:30 02:45 03100 03:05 03:10 03:15 03:30 03:45 (08:15) (08:30) (08:45) (09:00) (09:15) (09:30) (09:35) (09:40) (09:45) (10:00) (10:15)

~REACTOR CORE Level inches 183 ~ 0 185.0 185.0 184.0 184.0 180.0 163.8 147.6 131.4 82.8 34.2 Pressure psig 1015.0 1150 ~ 0 1145.0 1150.0 1150 ~ 0 1150.0 1140.0 1150.0 1140.0 1150.0 1150.0 Power )ps 600 cps 575 cps 550 cps 525 cps 525 cps 520 cps 520 cps 520 cps 520 cps 520 cps 515 cps Rx Recirc Flow Loop A x 106lbm/hr 8.0 8.0 8.0 8.0 8.0 8.0 8.0 8.0 8.0 8.0 8.0 Rx Recirc Flow Loop 8 x 10 ibm/hr 8.0 8.0 8.0 8.0 8.0 8.0 8.0 8.0 8.0 8.0 8.0 Recirc Suction Temperature OF 549.0 563.0 562.0 563.0 563.0 563.0 563.0 563.0 563.0 563.0 563.0 PRIMARY SECONDARY CONTAINMENT Drywell Pressure ps 1 g 6.0 9.0 12.0 15.0 18.0 21.0 22.0 23.0 24.1 27.0 31.0 Drywell Temperature max. F 225.0 237.0 244.0 250.0 256.0 260.0 262.0 264.0 266.0 271.0 275.0 avg. F 222.0 235.0 243.0 250.0 255.0 259.0 260.0 262.0 265.0 270.0 274.0 Drywell Oxygen )l 1.0 1.0 1.0 1.0 1.0 1.0 1.0 '1.0 1.0 1.0 1.0 Drywell Hydrogen )l 0.1 0~1 0.1 0.1 0.1 0.1 0.1 0.1 0.1 0.1 0.1 Suppression Pool Level feet 200.0 200.1 200 ~ 1 200.1 200.2 200.2 200.3 200.3 200.4 200.5 200.7 Suppression Pool Teap. F 100 ' 110.0 120.0 130.0 138.0 146.0 148.5 151.0 153.0 159.0 165.0 Suppression Pool Pressure Psig 2 4.0 7.0 10.0 13.0 16.0 19.0 20.0 21.0 22.0 25.0 29.0 Reactor Building dP in. H 0 -0.25 -0.25 -0.25 -0.25 -0.25 -0.25 -0.25 -0.25 -0.25 -0.25 -0.25 SBGTS 2600. 2600. 2600. 2600. 2600. 2600. 2600. 2600. 2600. 2600. 2600.

s cpm Total Station Stack Flow 103scfm 84.77 84.77 84.77 84.77 84.77 84.77 84.77 84.77 84.77 84.77 84.77 Total Station Vent Flow 10 scfm 92.99 92.99 92.99 92.99 92.99 92.99 92.99 92.99 92.99 92.99 92.99 BALANCE OF PLANT Hain Generator Power HWe Ilgross) 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Total Feedwater Flow x 106 Ibm/hr 0.1 0.1 0.1 0.1 0.1 0.0 0.0 0.0 0.0 0.0 0.0 Total Steam Flow x 10 ibm/hr 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Hain Condenser Vaclx111 " Hg vac. 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 ECCS RCIC Flow gpm 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 HPCS Flow x 10 gpm 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 RHR A Flow RHR 8 Flow x 100 gpn x 100 gpm 74.5*

0.0 74.5* 74 '* 74 '*

0.0 0.0 74.5*

0.0 74.5*

0.0 74.5*

0.0 74.5*

0.0 74 '* 0.0 74.5>>

0.0 74.5*

RHR C Flow x 100 gpm 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 LPCS Flow x 100 gpm 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 MAKEUP STORAGE CST A Level Feet 37.3 37.3 37.3 37.2 37.2 37.2 37.1 37.1 37.1 37.1 37.0 CST B Level Feet 37.3 37.3 37.3 37.2 37.2 37.2 37.1 37.1 37.1 37.1 37.0 Hotwell Level Inches 24.0 24.0 24.0 24.0 24.0 24.0 24.0 24.0 24.0 24.0 24.0 Suppression Pool Cooling Mode

• • LPCI Hode

• • • CSL Throttled to Control Level

++ SP Spray Hode 9.1-2

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 'I TABLE 9.1.1 PLANT PARAMETER DATA TIME 04 F 00 04:15 04:30 04:45 05 00 05:05 05:10 05:15 05:30 05:45 06:00 (10:30) (10:45) (11:00) (1'I:15) (11:30) (11:35) (11:40) (11:45) (12:00) (12:15) (12:30)

REACTOR Level inches -14.0 -63.0 -111.6 -160.2 OSL OSH OSH OSH OSH OSH OSH Pressure psig 1140.0 'I150.0 1140.0 1150.0 1140.0 200.0 52.0 51.5 50.0 48.5 47.0 Power X - (ps 515 cps 515 cps 515 cps 515 cps 515 cps 510 cps 510 cps 510 cps 510 cps 510 cps 510 cps Rx Recirc Flow Loop A x 106lbm/h 6.0 4.0 0.0 , 0.0 0.0 0.0 8.0 8.0 8.0 8.0 8.0 Rx Recirc Flow Loop B x 10 lbm/hr 6.0 4.0 0.0 0.0 0.0 0.0 8.0 8.0 8.0 8.0 8.0 Recirc Suction Temperature OF 563.0 563.0 563.0 563.0 563.0 388.0 302.0 300.0 298.0 296.0 295.0 PRIMARY SECONDARY CONTAINMENT Drywell Pressure ps I 9 35.1 39.0 43.2 > 48.1 53.0 52.5 52 ~ 0 51.5 50.0 48.5 47.0 Drywell Temperature max. F 280.0 286.0 290.0 296.0 301.0 300.0 300.0 300.0 298.0 296.0 295.0 avg. F 280.0 285.0 289.0 295.0 300.0 300.0 300.0 300.0 298.0 296.0 295.0 Drywel l Oxygen y 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 Drywell Hydrogen 0.1 1.0 4.0 7.0 10.0 10.0 10.0 10.0 10.0 9.0 8.0 Suppression Pool Level feet 200.8 201.0 201.1 201.3 201.4 200.6 200.1 200.1 200.1 200.1 200.1 Suppression Pool Temp. F 170.0 174.0 177.0 180.0 182.0 180.8 181.4 184.0 186.0 187.5 188.5 Suppression Pool Pressure Psig 2 33.0 37.0 41.1 46.0 51.0 51.0 51.0 51.0 50.0 48.5 47.0 Reactor Building dP in. HO -0.25 -0.25 -0.25 -0.25 -0.25 -0.15 -0.10 0.0 0.0 0.0 0.0 SBGTS sgm 2600. 2600. 2600. 2600. 2600. 0.0 0.0 0.0 0.0 0.0 0.0 Total Station Stack Flow 10 scfm 84.77 84.77 84.77 84.77 84.77 84.77 84.77 84.77 84.77 84.77 84.77 Total Station Vent Flow 10 scfm 92.99 92.99 92.99 92.99 92.99 92.99 92.99 92.99 92.99 92.99 92.99 BALANCE OF PLANT Main Generator Power MWe )gross) 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Total Feedwater Flow x 106 ibm/hr 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Total Steam Flow x 10 ibm/hr 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Main Condenser Vacua " Hg vac. 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 ECCS RCIC Flow gpm 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 HPCS Flow x 10 gpm 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 RHR A Flow x 100 gpm 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 RHR B Flow x 100 gpm 74.5* 74.5* 74.5* 74.5* 0.0 70.0'>> 75.0** 75.0** 75 0>>>> 75.0** 75.0*>>

RHR C Flow x 100 gpm 0.0 0.0 0.0 0.0 0.0 70.0 75.0 75.0 75.0 75.0 75.0 LPCS Flow x 100 gpm 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 I

MAKEUP STORAGE CST A Level Feet 37.0 37.0 37.0 37.0 37.0 37.0 37.0 37.0 37.0 37.0 37.0 CST B Level Feet 37.0 37.0 37.0 37.0 37.0 37.0 37.0 37.0 37.0 37.0 37.0 Hotwell Level Inches 24.0 24.0 24.0 24.0 24.0 24.0 24.0 24.0 24.0 24.0 24.0

• Suppression Pool Cooling Mode

• " LPCI Mode

• • • CSL Throttled to Control Level

++ SP Spray Mode 9.1-3

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 TABLE 9.1.1 PLANT PARAMETER DATA 2 DAYS LATER T I ME 06:15 06:30 06:35 06:40 06:45 07 00 07:15 07:30 07:45 08:00 (12:45) (13:00) (13:05) (13:10) (13:15) (13:30) (13:45) (14:00) (14:15) (14:30)

REACTOR Level inches OSH OSH OSH OSH OSH OSH 200.0 200.0 200.0 200.0 Pressure Pslg 45 ' 44.0 28.0 14.0 7.0 3.5 1.5 0.5 0.5 0.5 Power gPS 510 cps 510 cps 510 cps 510 cps 505 cps 505 cps 505 cps 500 cps 500 cps 500 cps Rx Recirc Flow Loop A x 106ibm/hr 8.0 8.0 8.0 8.0 8.0 8.0 8.0 ~ 8.0 8.0 8.0 Rx Recirc Flow Loop B g 10 lbm/hr 8.0 8.0 8.0 8.0 8.0 8.0 8.0 8.0 8.0 8.0 Recirc Suction Temperature F 293.5 292.0 272.0 248.0 234.0 224.0 150.0 150.0 150.0 150.0 PRIMARY SECONDARY CONTAINMENT Drywell Pressure PS1g 45.5 44.0 28.0 14 ~ 0 7.0 3.5 0.5 0.5 0.5 0.5 Drywall Tecperature max. F 293.5 292.0 278.0 258.0 246.0 224.0 110.0 110.0 110.0 110.0 avg. F 293.5 292.0 272.0 248.0 234'.0 220.0 110.0 110.0 110.0 110.0 Drywall Oxygen y 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 Drywell Hydrogen . 7.0 6.0 5.7 5.3 5.0 4.0 0.1 0.1 0.1 0.1 Suppression Pool Level Feet 200 F 1 200.1 200 ' 200.1 200.1 200.1 200 ' 200.1 200.1 200.1 Suppression Pool Temp. OF 190.0 191.0 191.2 191.3 191.5 191.2 90.0 88.0 86.0 80.0 Suppression Pool Pressure Pslg 45.5 44.0 28.0 15.0 8.0 4.5 0.5 0.5 0.5 0.5 Reactor Building dP in. H 2

0 0.0 0.0 -0.25 -0.25 -0.25 -0 '5 -0 '5 -0.25 -0 ~ 25 -0.25 SBGTS scfm 0.0 0.0 2600. 2600. 2600. 2600. 2600. 2600 2600. 2600.

'Iotal Station Stack Flow 103scfm 84.77 84.77 84.77 84.77 84.77 84.77 84.77 '4.77 84.77 84.77 Total Station Vent Flow 10 scfm 92.99 92.99 92.99 92.99 92.99 92.99 92.99 92.99 92.99 92.99 BALANCE OF PLANT Main Generator Power Mwe )gross) 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Total Feedwater Flow x 106 ibm/hr 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Total Steam Flow x 10 ibm/hr 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0

'pll Main Condenser Vacuun " Hg vac. 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 ECCS RCIC Flow 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0:0 HPCS Flow x 10 gpm 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 RHR A Flow x 100 gpm 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 RHR B Flow x 100. gpm 75.0* 74 '++ 74.5++ 74.5++ 74.5++ 74.5++ 74.5>> 74.5* 74.5* 74 '>>

RHR C Flow x 100 gpm 75.0 75.0 75.0 75 ' 75.0 75.0 75.0 75.0 75.0 75.0 LPCS Flow x 100 gpm 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 MAKEUP STORAGE CST A Level Feet 37.0 37.0 37.0 37.0 37.0 37.0 37.0 37.0 37.0 37.0 CST B Level Feet 37.0 37.0 37.0 37.0 37.0 37.0 37.0 37.0 37.0 37.0 Hotwell Level Inches 24.0 24.0 24.0 24.0 24.0 24.0 24.0 24.0 24.0 24.0

• Suppression Pool Cooling Mode

• • LPCI Mode

"** CSL Throttled to Control Level

++ SP Spray Mode 9.1-4

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 TABLE 9.1.2 - PLANT EDUIPMENT STATUS PARAMETERS Drill Time 00:00 00:15 00:30 00:45 01:00 01 10 01:15 01:20 Clock Time (06:30) (06:45) (07:00) (07:15) (07:30) (07:40) (07 45) (07:50)

MODES OF INJECTION Condensate Pumps (A/8/C) 0/0/I 0/0/I 0/0/I I/O/I I/O/I I/O/I I/O/I I/O/I Condensate Booster Pimps (A/8/C) 0/0/S 0/0/S 0/0/S S/0/S S/0/S S/0/S S/0/S S/0/S Reactor Feedwater Pumps (A/8/C) 0/0/S 0/0/S 0/0/S S/0/S S/0/S S/0/S S/0/S S/0/S RCIC/HPCS/LPCS I/S/S I/S/S I/S/S I/S/S I/S/S I/S/I I/S/I I/S/I RHR (A/8/C) I/S/S I/S/S I/S/S I/S/S I/S/S I/S/S I/S/S I/S/S Control Rod Drive (A/8) I/O I/O I/O I/O I/O I/O I/O I/O STATUS OF ENGINEERED SAFEGUARDS Standby Liquid Control (A/8) S/S S/S S/S S/S S/S S/S S/S S/S ADS (DIV I/DIV II) S/S S/S S/S S/S S/S I/S I/S I/S Standby Gas Treatment System (A/8) S/S S/S S/S S/S S/S 0/S 0/S 0/S Hydrogen Recombiner System (A/8) S/S S/S S/S S/S S/S S/S S/S S/S Service 'Mater System (A/8/C/0/E/F) 0/0/0/0/S/S 0/0/0/0/S/S 0/0/0/0/S/S 0/0/0/0/S/S 0/0/0/0/S/S 0/0/0/0/S/S 0/0/0/0/S/S 0/0/0/0/S/S ELECTRICAL SYSTEMS 13.8KV Switchgear (001/002/003) 0/0/0 0/0/0 0/0/0 0/0/0 0/0/0 0/0/0 0/0/0 0/0/0 4.16KV Switchgear (11/12/13/14/15) 0/0/0/0/0 0/0/0/0/0 0/0/0/0/0 0/0/0/0/0 0/0/0/0/0 0/0/0/0/0 0/0/0/0/0 0/0/0/0/0 Emergency SMitchgear ('101/102/103) 0/0/0 0/0/0 0/0/0 0/0/0 0/0/0 0/0/0 0/0/0 0/0/0 115-KV RSST (A/8) 0/0 0/0 0/0 0/0 0/0 0/0 0/0 0/0 Diesel Generators (EG1/EG3/EG2) S/S/S S/S/S S/S/S S/S/S S/S/S I/O/0 I/O/0 I/O/0 125VDC Batteries 0/0/0 0/0/0 0/0/0 0/0/0 0/0/0 I/O/0 I/O/0 I/O/0 (A/8/C)(DIV I/DIV II/DIV 111)

MISCELLANEOUS SYSTEMS 8 COMPONENTS MSIVs Open Open Open Open Open Open Open Open Rx Mater Cleanup System 0 0 0 0 0 0 0 0 I

0 = Operating, S = Standby; I = Inoperative 9.1-5

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 TABLE 9.1.2 - PLANT EOUIPHENT STATUS PARAHETERS Drill Time 01:25 01:30 01:35 01:45 02:00 02:15 02:30 02:35 Clock Time (07:55) (08:00) (08 05) (08:15) (08:30) (08:45) (09:00) (09:05)

MODES OF INJECTION Condensate Pcs (A/8/C) I/O/I I/O/I I/O/I I/O/I I/O/I I/O/I I/O/I I/0/I Condensate Booster Pumps (A/8/C) S/0/S S/0/S S/0/S S/0/S S/0/S S/0/S S/0/S S/0/S Reactor Feedwater Pumps (A/8/C) S/0/S S/0/S S/0/S S/0/S S/0/S S/0/S S/0/S S/0/S RCIC/HPCS/LPCS I/I/I I/I/I I/I/I I/I/I I/I/I I/I/I I/I/I I/I/I RHR (A/8/C) I/S/S I/O/S I/O/S I/O/S I/O/S I/O/S I/O/S I/O/S Control Rod Drive (A/8) I/O I/O I/O I/O I/O I/O I/I I/I STATUS OF ENGINEERED SAFEGUARDS standby Liquid Control (A/8) S/S S/S S/S S/S S/S S/S S/S (DIV I/DIV II)

S/S'/I ADS I/S I/S I/I I/I I/I I/I I/I Standby Gas Treatment System (A/8) 0/S 0/S 0/S 0/S 0/S 0/S 0/S 0/S Hydrogen Recombiner System (A/8) S/S S/S S/S S/S S/S S/S S/S S/S Service Water System (A/8/C/D/E/F) 0/0/0/0/S/S 0/0/0/0/S/S 0/0/0/0/S/S 0/0/0/0/S/S 0/0/0/0/S/S 0/0/0/0/S/S 0/0/0/0/S/S 0/0/0/0/S/S ELECTRICAL SYSTEHS 13.8KV Switchgear (001/002/003) 0/0/0 0/0/0 0/0/0 0/0/0 0/0/0 0/0/0 0/0/0 0/0/0 4.16KV Switchgear (1'I/12/13/14/15) 0/0/0/0/0 0/0/0/0/0 0/0/0/0/0 0/0/0/0/0 0/0/0/0/0 0/0/0/0/0 0/0/0/0/0 0/0/0/0/0 Emergency Switchgear (101/102/103) 0/0/0 0/0/0 0/0/0 0/0/0 0/0/0 0/0/0 0/0/0 0/0/0 115-KV RSST (A/8) 0/0 0/0 0/0 0/0 0/0 0/0 0/0 0/0 Diesel Generators (EG1/EG3/EG2) I/O/0 I/O/0 I/I/O I/I/O I/I/O I/I/O I/I/O I/I/O 125VDC Batteries I/O/0 I/O/0 I/I/0 I/I/O I/I/O I/I/O I/I/O I/I/O (A/8/C)(DIV I/DIV II/DIV III)

HISCELLANEOUS SYSTEHS 8 COMPONENTS HSIVs Open Open Closed Closed Closed Closed Closed Closed Rx Water Cleanup System 0 0 0 0 0 0 0 0 0 = Operating; S = Standby; I = Inoperative 9.1-6

Nine Mi le Point Unit 2

'1990 Annual Exercise Scenario No. 19, Rev. 1 TABLE 9.1.2 - PLANT EOUIPMENT STATUS PARAHETERS Drill Time 02 40 02:45 03:00 03:05 ~ 03:10 03:15 03:30 03:45 Clock Time (09:10) (09 15) (09:30) (09:35) (09:40) (09:45) (10:00) (10:15)

MCOES OF INJECTION Condensate Pumps (A/B/C) I/O/I I/O/I I/I/I I/I/I I/I/I I/I/I I/I/I I/I/I Condensate Booster Pumps (A/B/C) S/0/S S/0/S S/S/S S/S/S S/S/S S/S/S S/S/S S/S/S Reactor FeedNater Pumps (A/B/C) S/0/S S/0/S S/S/S S/S/S S/S/S S/S/S S/S/S S/S/S RCIC/HPCS/LPCS I/I/I I/I/I I/I/I I/I/I I/I/I I/I/I I/I/I I/I/I RHR (A/B/C) I/O/S I/O/S I/O/S I/O/S I/O/S I/O/S I/O/S I/O/S Control Rod Drive (A/8) I/I I/I I/I I/I I/I I/I I/I I/I STATUS OF ENGINEERED SAFEGUARDS Standby Liquid Control (A/B) S/S S/S S/S S/S S/S S/S S/S S/S ADS (DIV I/DIV II) I/I I/I I/I I/I I/I I/I I/I I/I Standby Gas Treatment System (A/8) 0/S 0/S 0/S 0/S 0/S 0/S 0/S 0/S Hydrogen Recombiner System (A/B) S/S S/S S/S S/S S/S S/S S/S S/S Service Mater System (A/B/C/D/E/F) 0/0/0/0/S/S 0/0/0/0/S/S 0/0/0/0/S/S 0/0/0/0/S/S 0/0/0/0/S/S 0/0/0/0/S/S 0/0/0/0/S/S 0/0/0/0/S/S ELECTRICAL SYSTEMS 13.8KV Switchgear (001/002/003) 0/0/0 0/0/0 0/0/0 0/0/0 0/0/0 0/0/0 0/0/0 0/0/0 4.16KV Switchgear (11/12/13/14/15) 0/0/0/0/0 0/0/0/0/0 0/0/0/0/0 0/0/0/0/0 0/0/0/0/0 0/0/0/0/0 0/0/0/0/0 0/0/0/0/0 Emergency Switchgear (101/102/103) 0/0/0 0/0/0 0/0/0 0/0/0 0/0/0 0/0/0 0/0/0 0/0/0 115-KV RSST (A/B) 0/0 0/0 0/0 0/0 0/0 0/0 0/0 0/0 Diesel Generators (EGI/EG3/EG2) I/I/O I/I/O I/I/O I/I/O I/I/O I/I/O I/I/O I/I/O 125VDC Batteries I/I/O I/I/0 I/I/O I/I/O I/I/O I/I/O I/I/O I/I/0 (A/B/C)(DIV I/DIV II/DIV III)

MISCELLANEOUS SYSTEMS & COMPONENTS MSIVs Closed Closed Closed Closed Closed Closed Closed Closed Rx 'Mater Cleanup System 0 0 0 0 0 0 S S I

0 = Operating, S = Standby; I = Inoperative 9.1-7

Nine Mile Point Unit 2 1990 AnnuaL Exercise Scenario No. 19, Rev. 1 TABLE 9.1.2 - PLANT EQUIPMENT STATUS PARAMETERS Drill Time 04:00 04:15 04:30 04:45 05:00 05:05 05:10 05:15 Clock Time (10:30) (10:45) (11:00) (11:15) (11:30) (11:35) (11:40) (11:45)

MODES OF INJECTION Condensate Pcs (A/B/C) I/I/I I/I/I I/I/I I/I/I I/I/I I/I/I I/I/I I/I/I Condensate Booster Pumps (A/B/C) S/S/S S/S/S S/S/S S/S/S S/S/S S/S/S S/S/S S/S/S Reactor FeedNater Putys (A/B/C) S/S/S S/S/S S/S/S S/S/S S/S/S S/S/S S/S/S S/S/S RCIC/HPCS/LPCS I/I/I I/I/I I/I/I I/I/I I/I/I I/I/I I/I/I I/I/I RHR (A/B/C) I/O/0 I/O/0 I/O/0 I/O/0 I/O/0 I/O/0 I/O/0 I/O/0 Control Rod Drive (A/B) I/I I/I I/I I/I I/I I/I I/I I/I STATUS OF ENGINEERED SAFEGUARDS Standby Liquid Control (A/B) 0/S 0/S 0/S 0/S 0/S 0/S 0/S 0/S ADS (DIV I/DIV II) I/I I/I I/I I/I I/O I/O I/O I/O Standby Gas Treatment System (A/8) 0/S 0/S 0/S 0/S S/S S/S S/S S/S Hydrogen Recombiner System (A/B) S/S S/S S/S S/S S/S S/S S/S 0/S Service Water System (A/8/C/D/E/F) 0/0/0/0/S/S 0/0/0/0/S/S 0/0/0/0/S/S 0/0/0/0/S/S 0/0/0/0/S/S 0/0/0/0/S/S 0/0/0/0/S/S 0/0/0/0/S/S ELECTRICAL SYSTEMS 13.8KV Suitchgear (001/002/003) 0/0/0 0/0/0 0/0/0 0/0/0 0/0/0 0/0/0 0/0/0 0/0/0 4.16KV SNI tchgear (11/12/13/14/15) 0/0/0/0/0 0/0/0/0/0 0/0/0/0/0 0/0/0/0/0 0/0/0/0/0 0/0/0/0/0 0/0/0/0/0 0/0/0/0/0 Emergency SNi tchgear (101/102/103) 0/0/0 0/0/0 0/0/0 0/0/0 0/0/0 0/0/0 0/0/0 0/0/0 115-KV RSST (A/B) 0/0 0/0 0/0 0/0 0/0 0/0 0/0 0/0 Diesel Generators (EG1/EG3/EG2) I/I/O I/I/O I/I/0 I/I/O I/S/0 I/S/0 I/S/0 I/S/0 125VDC Batteries I/I/O I/I/O I/I/0 I/I/O I/O/0 I/O/0 I/O/0 I/O/0 (A/B/C)(DIV I/DIV II/DIV III)

MISCELLANEOUS SYSTEMS B COMPONENTS MSIVs Closed Closed Closed Closed Closed Closed Closed Closed Rx Mater Cleanup System S S S S S S S S I

0 = Operating, S = Standby; I = Inoperative 9.1-8

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 TABLE 9.1.2 - PLANT EOUIPMENT STATUS 2 DAYS LATER PARAHETERS Drill Time 05:30 05:45 06:00 06:15 06:30 06 45 OT:00 07 15 Clock Time (12:00) (12:15) (12:30) (12:45) (13:00) (13:15) (13:30) (13:45)

HODES OF INJECTION Condensate Pubs (A/8/C) I/I/I I/I/I I/I/I I/I/I I/I/I I/I/I I/I/I I/I/I.

Condensate Booster Pumps (A/8/C) S/S/S S/S/S S/S/S S/S/S S/S/S S/S/S S/S/S S/S/S Reactor Feedwater Punps (A/8/C) S/S/S S/S/S S/S/S S/S/S S/S/S S/S/S S/S/S S/S/S RCIC/HPCS/LPCS I/I/I I/I/I I/I/I I/I/I I/I/I I/I/I I/I/I I/I/I RHR (A/8/C) I/O/0 I/O/0 I/O/0 I/O/0 I/O/0 I/O/0 I/O/0 I/O/0 Control Rod Drive (A/8) I/I I/I I/I I/I I/I I/I I/I I/I STATUS OF ENGINEERED SAFEGUARDS Standby Liquid Control (A/8) 0/S 0/S I/S I/S I/S I/S I/S I/S ADS (DIV I/DIV II) I/O I/O I/O I/O I/O I/O I/O I/O Standby Gas Treatment System (A/8) S/S S/S S/S S/S S/S 0/S 0/S 0/S Hydrogen Recombiner System (A/8) 0/S 0/S 0/S 0/S 0/S 0/S 0/S 0/S Service Water System (A/8/C/D/E/F) 0/0/0/0/S/S 0/0/0/0/S/S 0/0/0/0/S/S 0/0/0/0/S/S 0/0/0/0/S/S 0/0/0/0/S/S 0/0/0/0/S/S 0/0/0/0/S/S ELECTRICAL SYSTEMS 13.8KV Switchgear (001/002/003) 0/0/0 0/0/0 0/0/0 0/0/0 0/0/0 0/0/0 0/0/0 . 0/0/0 4.16KV Swi tchgear (11/12/13/14/15) 0/0/0/0/0 0/0/0/0/0 0/0/0/0/0 0/0/0/0/0 0/0/0/0/0 0/0/0/0/0 0/0/0/0/0 0/0/0/0/0 Emergency Swi tchgear (101/102/103) 0/0/0 0/0/0 0/0/0 0/0/0 0/0/0 0/0/0 0/0/0 0/0/0 115.KV RSST (A/8) 0/0 0/0 0/0 0/0 0/0 0/0 0/0 0/0 Diesel Generators (EG1/EG3/EG2) I/S/0 I/S/0 I/S/0 I/S/0 I/S/0 I/S/0 I/S/0 I/S/0 125VDC Batteries I/O/0 I/O/0 I/O/0 I/O/0 I/O/0 I/O/0 I/O/0 I/O/0 (A/8/C)(DIV I/DIV II/DIV III)

MISCELLANEOUS SYSTEMS 8 COMPONENTS MSIVs Closed Closed Closed Closed Closed Closed Closed Closed Rx Water Cleanup System S S S S S S S S 0 = Operating, S = Standby; I = Inoperative 9.1-9

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 TABLE 9.1.2 - PLANT EOUIPHENT STATUS PARAMETERS Drill Time Clock Time

'7:30 (14:00) 07:45 (14:15) 08:00 (14:30)

HODES OF INJECTION Condensate Pumps (A/8/C) I/I/I I/I/I I/I/I Condensate Booster Pwps (A/8/C) S/S/S S/S/S ,S/S/S Reactor Feedwater Pcs (A/8/C) S/S/S S/S/S S/S/S RCIC/HPCS/LPCS I/I/I I/I/I I/I/I RHR (A/8/C) I/O/0 I/O/0 I/O/0 Control Rod Drive (A/8) I/I I/I I/I STATUS OF ENGINEERED SAFEGUARDS Standby Liquid Control (A/8) I/S I/S I/S ADS (DIV I/DIV II) I/O I/0 I/O Standby Gas Treatment System (A/8) 0/S 0/S 0/S Hydrogen Reccmbiner System (A/8) 0/S 0/S 0/S Service Mater System (A/8/C/0/E/F) 0/0/0/0/S/S 0/0/0/0/S/S 0/0/0/0/S/S ELECTRICAL SYSTEHS 13.8KV Switchgear (001/002/003) 0/0/0 0/0/0 0/0/0 4.16KV Swi tchgear (11/'12/13/14/15) 0/0/0/0/0 0/0/0/0/0 0/0/0/0/0 Emergency Swi tchgear (101/102/103) 0/0/0 0/0/0 0/0/0 115-KV RSST (A/8) 0/0 0/0 0/0 Diesel Generators (EG1/EG3/EG2) I/S/0 I/S/0 I/S/0 125VDC Batteries I/O/0 I/O/0 I/O/0 (A/8/C)(DIV I/DIV II/DIV III)

HISCELLANEOUS SYSTEHS 8 COHPONENTS MS I Vs Closed Closed Closed Rx Water Cleanup System S S S I

0 = Operating, S = Standby; I = Inoperative 9.'1-10

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 9.2 DRMS DATA

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 9.2 DRMS DATA TABLE OF CONTENTS Section Title ~Pa e 9.2.1 Area Radiation Monitors 9.2.2 Continuous Air Monitors 9.2-7 9.2.3 Process Monitors 9.2-12 9.2.4 Monitor Information 2 Days Later 9.2-22

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 9.2.1 Area Radiation Monitors

Nine Mi le Point Unit 1990 Annual Exercise Scenario No. 19, Rev. 1 TABLE 9.2.1 AREA RADIATION MONITORS Reading (mR/hr) at:

Monitor 00:00 00:15 00:30 00:45 0'I:00 01:15 01:30 01:45 02 00 02:15 Name Location~ (06:30) (06:45) (07:00) (07:15) (07:30) (07:45) (08:00) (08:15) (08:30) (08:45)

RMS-1A DW 261'W 4.DOE+03 4 ~ OOE+03 4.DOE+03 4.DOE+03 4.DOE+03 4 ~ OOE+03 1.40Ei03 1.10E+03 1.10E+03 RHS-18 261' 4.DOE+03 4.DOE+03 4.DOE+03 4.DOE+03 4.00E+03 4.DOE+03 4.DOE+03 1.40E+03 1.10E+03 1.10E+03 RHS-1C DW 261'W 4 '0E+03 4.20E+03 4 '0E+03 4.20E+03 4.20E+03 4.20E+03 4 '0E+03 1.42E+03 1.30E+03 1.30E+03 RHS-1D 261'X 4.DOE+03 4.DOE+03 4.DOE+03 4.00E+03 4.DOE+03 4.DOE+03 4.DOE+03 1.40E+03 1.10E+03 1 ~ 10E+03 RHS-2A 215'X 9.67E-01 9.67E-01 9.67E-01 9.67E-01 9.67E-01 9.67E-01 9.67E-01 9.67E-01 9.67E 9.67E-01 RHS-28 215'B 1.95E-01 1.95E-01 1.95E-01 1.95E-01 1.95E-01 1.95E-01 1.95E-01 1.95E-01 1.95E-01 1.95E-01 RHS-3A 250'B 1.18E+01 1.18E+01 1.18E+01 1 ~ 18E+Ol 1.18E+01 1.18E+01 1.18Et01 1.DOE+01 1.DOE+01 1.DOE+01 RHS-3B 250'B 1.36E+01 1.36E+01 1.36E+01 1.36E+01 1.36E+01 1.36E+01 1.36E+01 1 'OE+01 1.DOE+01 1.DOE+01 RHS-3C 250'X 1.DOE+01 'I.DOE+01 1.DOE+01 1.DOE+01 1.DOE+01 1.DOE+01 1 'OE+01 1 AB ODE+01 1.DOE+01 1.DOE+01 RHS-101 175'X 1.44E-01 1 '4E-01 1.44E-01 1.44E.01 1.44E-01 1.44E-01 1.44E-01 1.44E-01 1.44E-01 1.44E-01 RMS-102 261'.DOE+03 175'X 9.50E-02 9.50E-02 9.50E-02 9.50E-02 9.50E-02 9.50E-02 9.50E-02 9.50E-02 9.50E-02 9.50E-02 RHS-103 175'X 4.99E.01 4.99E-01 4.99E-01 4.99E-01 4.99E-01 4.99E-01 4.99E-01 4.99E-01 4.99E-01 4.99E-O'I RMS-104 175'X 8.39E-02 8.39E-02 8.39E-02 8.39E-02 8.39E-02 8.39E-02 8.39E-02 8.39E-02 8.39E-02 8.39E-02 RMS-105 240'X 1.20E+00 1 '0E+00 '1.20E+00 1.20E+00 1.20E+00 1.20E+00 1.20E+00 1.20E+00 1.20E+00 1.20E+00 RHS-106 261'X 2.03E-01 2.03E-01 2.03E-01 2.03E-01 2.03E-01 2.03E-01 2.03E-01 2.03E-01 2.03E-01 2 '3E-01 RHS-108 289'X 1 '6E-01 1.06E-01 1.06E-01 1.06E-01 1.06E-01 1.06E-01 1.06E-01 1 '6E-01 1.06E-01 1.06E-01 RHS-109 316'X 6.23E-02 6.23E-02 6.23E-02 6.23E-02 6.23E-02 6.23E-02 6.23E-02 6.23E-02 ~ 6.23E-02 6.23E-02 RHS-111 353'X 4.72E-02 4.72E-02 4.72E-02 4.72E-02 4.72E-02 4.72E-02 4.72E-02 4.72E-02 4.72E-02 4.72E-02 RHS-112 353'X 5.57E-02 5.57E-02 5 '7E-02 5.57E-02 5.57E-02 5.57E-02 5.57E-02 5.57E-02 5 '7E-02 5.57E-02 RHS-113 353'X 6.00E-02 6.00E-02 6.00E-02 6.00E-02 6.00E-02 6.00E-02 6.00E-02 6.00E-02 6.00E-02 6.00E-02 RHS-114 353'B 9.31E-02 9.31E-02 9.31E-02 9.31E-02 9.31E-02 9.31E-02 9.31E-02 9.31E-02 9.31E-02 9.31E-02 RHS-116 250'B 3.97E-01 3.97E-01 3.97E-01 3.97E-01 3.97E-01 3.97E-01 3.97E-01 3.97E-01 3.97E-01 3.97E-01 RMS-117 250' 1. 17E-0'I 1.17E-0'I 1.17E-01 1.17E-01 1.17E-01 1.17E-01 1.17E-01 1.17E-01 1 '7E-01 '1.17E-01 RHS-118 TB 261'B 8.85E-02 8.85E-02 8.85E-02 8.55E-02 8.85E-02 8.85E-02 8.85E-02 8.85E-02 8.85E-02 8.85E-02 RHS-'119 250'B 1.30E+01 1.30E+01 1.30E+01 1.30E+01 1.30E+01 1.30E+01 1.30E+01 1.30Et01 1.30E+01 1.30E+01 RHS-120 277'B 3.52E-01 3 '2E-01 3.52E-01 3.52E.01 3.52E-01 3.52E-01 3.52E-01 3.52E-01 3 '2E-01 3 '2E-01 RHS-121 279'B 5.69E-02 5.69E-02 5.69E-02 5.69E-02 5.69E-02 5.69E-02 5.69E-02 5.69E-.02 5.69E-02 5.69E-02 RHS-123 306W 2.30E+01 2.30E+01 2.30E+01 2.30E+01 2.30E+01 2.30E+01 2.30E+01 4.DOE+00 4 AB ODE+00 4.DOE+00 RHS-125 6.36E-01 6.36E-O'I 6.36E-01 6.36E-01 6.36E-01 6.36E-01 6.36E-01 6.36E-01 6.36E-01 6.36E-01

• RX = Reactor Building; TB = Turbine Building; RW Rad Waste Building; CB = Control Building; DW = Dr~eil; HS = Main Stack 9.2-1

/

Nine Hile Point Uni 1990 Annual Exercise Scenario No. 19, Rev. 1 TABLE 9.2.1 AREA RADIATION HONITORS Reading (mR/hr) at:

Monitor 00:15 00:30 00:45 01:00 01:15 01:30 01:45 02:00 02:15 Location~ (06:30) (06:45) (07:00) (07:15) (07:30) (07 45) (08:00) (08 15) (08:30) (08:45)

RHS-129 CB 306'B 3.07E-02 3.07E-02 3.07E-02 3.0?E-02 3.07E-02 3.07E-02 3.07E-02 3.07E-02 3.0?E-02 3.07E-02 RHS-130 261'W 3.98E-02 3.98E-02 3.98E-02 3.98E-02 3.98E-02 3.98E-02 3.98E-02 3.98E-02 3.98E-02 3.98E-02 RHS-132 265'W 4.36E-02 4.36E-02 4.36E-02 4.36E-02 4.36E-02 4.36E-02 4.36E-02 4.36E-02 4.36E-02 4.36E-02 RHS-'133 279'W 1.5?E-01 1.57E-01 1 ~ 57E-01 1.57E-01 1.57E-01 1.57E-01 1 '7E-01 1.57E-01 1.57E-01 1.57E-01 RHS-134 261'B 3.85E-02 3.85E-02 3.85E-02 3.85E-02 3.85E-02 3.85E-02 3.85E-02 3.85E-02 3.85E-02 3.85E-02 RHS-135 250'B 1.03E-01 1.03E-01 1.03E-01 1.03E-01 1 '3E-01 1.03E-01 1.03E-01 1.03E-01 1 '3E-01 1.03E-01 RHS-136 288'B 8.81E-02 8.81E-02 8.81E-02 8.81E-02 8.81E-02 8.81E-02 8.81E-02 8.81E-02 8.81E-02 8.81E-02 RHS-137 261'B 6.97E-02 6.97E-02 6.97E-02 6.9?E-02 6.97E-02 6.97E-02 6.97E-02 6.9?E-02 6.9?E-02 6.9?E-02 RHS-138 250'X 1.50E-01 1.50E-01 1.50E-01 1 '0E-01 1.50E-01 1 '0E-01 1 '0E-01 1.50E-01 1.50E-01 1.50E-01 RHS-139 215'X 1.78E+00 1.78E+00 1.78E+00 1.78E+00 1 '8E+00 1.78E+00 1.78E+00 4.09E+02 4.28E+02 4.44E+02 RHS-140 353'B 6.91E-02 6.91E-02 6.91E-02 6.91E-02 6.91E-02 6.91E-02 6.91E-02 6.91E-02 6.91E-02 6.91E-02 RHS-141 250'W 2.01E-01 2.01E-01 2.01E-01 2.01E-01 2.01E-01 2.01E-01 2.01E-01 2.01E-01 2.01E-01 2.01E-01 RHS-142 RHS-143 261'0:00 279'X 261'X 5.12E-02 1.67E-01 5.12E-02 1.67E-01 5.12E-02 1.67E-01 5.12E-02 1.67E-01 5.12E-02 1.67E-01 5.12E-02 1.67E-01 5 '2E-02 1.67E-01 5.12E-02 1.67E-01 5.12E-02 1.6?E-01 5.12E-02 1.67E-01 RHS-144 261'X 1.95E-01 1.95E-01 1.95E-01 1.95E-01 1.95E-01 1.95E-01 1.95E-01 1.95E-01 1.95E-01 1.95E-01 RHS-145 240'W 5.76E-01 5.76E-01 5.76E-01 5.76E-01 5.76E-01 5.76E-01 5.76E-01 5.?6E-01 5.76E-01 5.?6E-01 RHS-146 279'W 5.67E-01 5.67E-01 5.67E-01 5.67E-01 5.67E-01 5.67E-01 5.67E-01 5.67E-01 5.67E-01 5.67E-01 RHS-147 291'W 1.DOE+01 1.DOE+01 1.DOE+01 1.00E+01 1.DOE+01 1.DOE+01 1 'OE+01 1.00E+01 1.DOE+01 1.00E+01 RHS-148 279'X 3.32E-01 3.32E-01 3.32E-01 3.42E-01 3.45E-01 3.49E-01 3.52E-01 3.55E-01 3.59E-01 3.62E-01 RHS-149 328'B 1.DOE+01 1.00E+01 1.DOE+01 1 AD OBE+01 1.DOE+01 1.DOE+01 1.DOE+01 1.DOE+01 1.00E+Ol 1.DOE+01 RHS-150 250'B 1.DOE+01 1.00E+01 1.00E+01 1 ~ OOE+01 1.DOE+01 1.DOE+01 1.00E+01 1.00E+01 1.DOE+01 1.DOE+01 RHS-151 306'W 3.11E+01 3.'11E+01 3 ~ 11E+01 3.11E<01 3.11E+01 3.11E+01 3 '1E+01 1.DOE+01 1.DOE+01 1.DOE+01 RHS-152 240'W 7.88E-02 7.88E-02 7.88E-02  ?.dSE-02 7.88E-02 7.88E-02 7.88E-02 7.88E-02 7.88E-02 7.88E-02 RHS-153 240'B 2.16E-01 2.16E-01 2.16E-01 2.16E-OIt 2.16E-01 2.16E-01 2.16E-01 2.16E-01 2.16E-01 2.16E-01 RHS-154 250'B 9.90E-02 9.90E-02 9.90E-02 9.90E-02 9.90E-02 9.90E-02 9.90E-02 9.90E-02 9.90E-02 9.90E-02 RHS-190 288~ 5.77E-02 5.7?E-02 5.77E-02 5.77E-02 5.77E-02 5.77E-02 5.77E-02 5.7?E-02 5.7?E-02 5.7?E-02 RHS-191 TB 306'B 2.55E-01 2.55E-01 2.55E-01 2.55E-01 2.55E-01 2.55E-01 2.55E-01 2.55E-01 2.55E-01 2.55E-01 RMS-192 306'S 5.07E-01 5.0?E-01 5.07E-01 5.0?E-01 5.0?E-01 5.0?E-01 5.07E-01 5.07E-01 5.07E-01 5.07E-01 RMS-193 1.05E-01 1.05E-01 '1.05E-01 1.05E-01 1.05E-01 1.05E-01 1.05E-01 1 '5E-01 1.05E-01 1.05E-01

• RX = Reactor Building; TB = Turbine Building; RW Rad Waste Building; CB = Control Building; DW = Drywall; MS = Hain Stack 9.2-2

Nine Hile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 TABLE 9.2.1 AREA RADIATION MONITORS Reading (mR/hr) at:

Monitor 02:30 02:45 03:00 03:15 03:30 03:45 04 00 04:15 04:30 04 45 Name Location~ (09:00) (09:15) (09:30) (09:45) (10 00) (10:15) (10:30) (10:45) (11:00) (11:15)

RHS-1A DW 261'W 1 ~ 10E+03 1.10E+03 1.10E+03 1.10E+03 1.10E+03 1.10E+03 1.50E+07 3.05E+07 1.02E+08 RHS-1B 261'W 1.10E+03 1 ~ 10E+03 1 ~ 10E+03 1 ~ 10E+03 1.10E+03 1.10E+03 1.10E+03 1.50E+07 3.05E+07 1.02E+08 RHS-1C 261'W 1.30E+03 1.30E+03 1.30E+03 1.30E+03 1.30E+03 1.30E+03 1.30E+03 1.50E+07 3 '5E+07 1.02E+08 RHS-1D 261'X 1.10E+03 1.10E+03 1.10E+03 1.10Et03 1.10E+03 1.10E+03 1.10E+03 1.50E+07 3.05EiO? 1.02E+08 RHS-2A 215'X 9.67E-01 9.67E-01 9.67E-01 9.67E-01 9.67E-01 9.67E-01 9.67E-01 3.DOE+00 4.DOE+00 1.DOE+01 RHS-2B 215'B 1.95E-01 1.95E-01 1.95E-01 1.95E-01 1.95E-01 1.95E-01 1.95E-01 3.DOE+00 4 'OE+00 1.00E+01 RHS-3A 250'B 1.DOE+01 1.00E+01 1 'OE+01 1.DOE+01 1.DOE+01 1.00E+01 1 ~ OOE+01 1.00E+01 1.DOE+01 1.DOE+01 RHS-3B 250'B 1.DOE+01 1.DOE+01 1.DOE+01 1.DOE+01 1.DOE+01 1.DOE+01 1.DOE+01 1.DOE+01 1.DOE+01 1.DOE+01 RHS-3C 250'X 1.DOE+01 1.DOE+01 1.DOE+01 1 'OE+01 1.DOE+01 1.DOE+01 1 ~ DOE+01 1.DOE+01 1.DOE+01 1.00E+01 RHS-101 175'X 1.44E-01 1.44E-01 1.44E-01 1.44E-01 1.44E-01 1.44E-01 1 '4E-01 3.DOE+00 4.DOE+00 1.00E+01 RHS-102 261'.10Ei03 175'X 9.50E-02 9.50E-02 9.50E-02 9.50E-02 9.50E-02 9.50E-02 9.50E-02 3.00E+00 4.DOE+00 1.DOE+01 RHS-103 175'X 4.99E-01 4.99E-01 4.99E-01 4.99E-01 4.99E-01 4.99E-01 4.99E-01 3.DOE+00 4.DOE+00 1.DOE+01 RHS-104 175'X 8.39E-02 8.39E-02 8.39E-02 8.39E-02 8.39E-02 8.39E-02 8.39E-02 3.DOE+00 4.DOE+00 1.DOE+01 RHS-105 240'X 1.20E+00 1 '0E+00 1 '0E+00 1.20E+00 1.20E+00 1.20E+00 1.20E+00 3.DOE+00 4.DOE+00 1.DOE+01 RHS-106 261'X 2.03E-01 2.03E-01 2.03E-01 2.03E-01 2.03E-01 2.03E-01 2.03E-01 3.DOE+00 4 'OE+00 1.DOE+01 RMS-108 289'X 1.06E-01 1.06E-01 1.06E-01 1.06E-01 1.06E-01 1.06E-01 1.06E-01 3.DOE+00 4.00E+00 1.DOE+01 RHS-109 316'X 6.23E-02 6.23E-02 6.23E-02 6.23E-02 6.23E-02 6.23E-02 3.DOE+00 4 ~ OOE+00 1.00E+01 6.23E-02'.?2E-02 RHS-111 353'X 4.72E-02 4.72E-02 4.72E-02 4.72E-02 4.72E-02 4.72E-02 3.DOE+00 4.DOE+00 1.DOE+01 RHS-112 353'X 5 '?E-02 5 '7E-02 5 '7E-02 5.57E-02 5.57E-02 5 '7E-02 5.57E-02 3.DOE+00 4.DOE+00 1.DOE+01 RHS-113 353'X 6.00E-02 6.00E-02 6.00E-02 6.00E-02 6.00E-02 6.00E-02 6.00E-02 3.00E+00 4.DOE+00 1.00E+01 RHS-114 353'B 9.31E-02 9.31E-02 9.31E-02 9.31E-02 9.31E-02 9.31E-02 9.31E-02 3.DOE+00 4.DOE+00 1.00E+01 RHS-116 250'B 3.97E-01 3.9?E-01 3.97E-01 3.97E-01 3.9?E-01 3.97E-01 3.97E-01 3.97E-01 3.9?E-01 3.97E-01 RHS-117 250'B 1.17E-01 1.17E-01 1.17E-01 1. AE-01 1.1?E-01 1.17E-01 F 1?E-01 1.1?E-01 1 '7E-01 1.1?E-01 RHS-118 261'B 8.85E.02 8.85E-02 8.85E-02 8.85E-02 8.85E-02 8.85E-02 8.85E-02 8.85E-02 8.85E-02 8.85E-02 RHS-119 250'B 1.30E+01 1.30E+01 1.30E+01 1.30E+01 1.30E+01 1.30E+01 1.30E+01 1.30E+01 1.30E+01 1.30E+01 RHS-120 277'B 3.52E-01 3.52E-01 3.52E-01 3.52E-01 3.52E-01 3.52E-01 3.52E-01 3.52E-01 3.52E-01 3.52E-01 RHS-121 279'B 5.69E-02 5.69E-02 5.69E-02 5.69E-02 5.69E-02 5.69E-02 5.69E-02 5.69E-02 5.69E-02 5.69E-02 RHS-123 306'W 4.DOE+00 4.DOE+00 4 'OE+00 4.DOE+00 4.DOE+00 4.DOE+00 4.DOE+00 4.DOE+00 4.DOE+00 4.00E+00 RHS-125 6.36E-01 6.36E-01 6.36E-01 6.36E-01 6.36E-01 6.36E-01 6.36E-01 6.36E-01 6.36E-01 6.36E-01

• RX = Reactor Building TB = Turbine Building; RW = Rad Waste Building; CB = Control Building; DW = Orwell; HS = Hain Stack 9.2-3

0 Nine Hile Point Unit 1990 Annual Exercise Scenario No. 19, Rev. 1 TABLE 9.2.1 AREA RADIATION HONITORS Reading (mR/hr) at:

I Monitor 02:30 02:45 03:00 03:15 03:30 03:45 04 00 04:15 04:30 04:45 Locat ion~ (09:00) (09r15) (09:30) (09:45) (10:00) (10:15) (10:30) (10 45) (11:00) (11:15)

RHS-129 CB 306'B 3.07E-02 3.07E-02 3.07E-02 3.07E-02 3.07E-02 3.07E-02 3.07E-02 3.07E-02 3.07E-02 RHS-130 261'W 3.98E-02 3.98E-02 3.98E-02 3.98E-02 3.98E-02 3.98E-02 3.98E-02 3.98E-02 3.98E-02 3.98E-02 RHS-132 265'W 4 '6E-02 4.36E-02 4.36E-02 4.36E-02 4.36E-02 4.36E-02 4.36E-02 4.36E-02 4.36E-02 4.36E-02 RHS-133 279'W 1.57E-01 1.57E-01 1.57E.01 1.57E-01 1.57E-01 1.57E-01 1.57E-01 1.57E-01 1.57E-01 1.57E-01 RHS-134 261'B 3.85E-02 3.85E-02 3.85E-02 3.85E-02 3.85E-02 3.85E-02 3.85E-02 3.85E-02 3.85E-02 3.85E-02 RHS-135 250'B 1.03E-01 1.03E-01 1.03E-01 1.03E-01 1.03E-01 1.03E-01 1.03E-01 1.03E-01 1.03E-01 1.03E-01 RHS-136 288'B 8.81E-02 8.81E-02 8.81E-02 8.81E-02 8.81E-02 8.81E-02 8.8'IE-02 8.81E-02 8.81E-02 8.81E-02 RMS-137 261'B 6.97E-02 6.97E-02 6.97E-02 6.97E-02 6.97E-02 6.97E-02 6.97E.02 6.97E-02 6.97E-02 6.97E-02 RHS-138 250'X 1.50E-01 1.50E-01 1.50E-01 1.50E-01 1.50E-01 1.50E-01 1 '0E.01 1.50E-01 1.50E-01 1.50E-01 RHS-139 =

215'X 4.89E+02 5.?3E+02 5.44E+02 6.24E+02 6.98E+02 7.42E+02 8.02E+02 1.00E+05 1.DOE+05 1.00E+05 RHS-140 261'.07E-02 353'B 6.91E-02 6.91E-02 6.91E-02 6.91E-02 6.91E-02 6.91E-02 6.91E-02 6.91E-02 6.91E-02 6.91E-02 RMS-141 250'W 2.01E-01 2.01E-01 2.01E-01 2.01E-01 2.01E-01 2.01E-01 2.01E-01 2.01E-01 2.01E-01 2.01E-01 RHS-142 279'X 5.12E-02 5.12E-02 5.12E-02 5.'12E-02 5.12E-02 5.12E.02 5.12E-02 5.12E-02 5.12E-02 5.12E.02 RHS-143 261'X 1.67E-01 1.67E-01 1.67E-01 1.67E-01 1.67E-01 1.67E-01 1.67E-01 1.67E-01 1.67E-01 1.67E-01 RHS-144 261'X 1.95E-01 1.95E-01 1.95E-01 1.95E-01 1.95E-01 1.95E-01 1.95E-01 1.95E-01 1.95E-01 1.95E-01 RHS-145 240~ 5.76E-01 5.76E-01 5.76E-01 5.76E-01 5.76E-01 5.76E-01 5.76E-01 5.76E-01 5.76E-01 5.76E-01 RHS.146 RW 279'W 5.67E-01 5.67E-01 5.67E-01 5.67E-01 5.67E-01 5.67E-01 5.67E-01 5.67E-01 5.67E-01 5.67E-01 RHS-147 291'W 1.DOE+01 1.DOE+01 1.00E+01 1 ~ OOE+01 1.DOE+01 1.DOE+01 1.DOE+01 1.00E+01 'I.DOE+01 1.DOE+01 RHS-148 279'X 3.65E-01 3.69E-01 3.72E-01 3.75E-01 3.78E-01 3.82E-01 3.85E-01 3.88E-01 3.92E-01 3.95E-01 RHS-149 328'B 1.DOE+01 1.DOE+01 1.DOE+01 1.DOE+01 1.DOE+01 1.DOE+01 1.DOE+01 1 'OE+01 1.DOE+01 4.10E+03 RHS-150 250'B 1.DOE+01 1.DOE+01 1.DOE+01 1.00E+01 1.DOE+01 1 ~ OOE+01 1.DOE+01 1.00E+Ol 1.DOE+01 1 ~ OOE+01 RHS-151 306'W 1.DOE+01 1.DOE+01 1.DOE+01 1.00E+Ol 1.DOE+01 1.DOE+01 1.DOE+01 1 ~ OOE+01 1 'OE+01 1.DOE+01 RMS-152 240'W 7.88E.02 7.88E-02 7.88E-02 7.88E-02 7.88E-02 7.88E-02 7.88E.02 7.88E-02 7.88E-02 7.88E-02 RHS-153 240'B 2.16E-01 2.16E-01 2.16E-01 2.16E-01 2.16E-01 2.16E-01 2.16E-01 2.16E-01 2.16E-01 2.16E-01 RHS-154 250'B 9.90E-02 9.90E-02 9.90E-02 9.90E-02 9.90E-02 9.90E.02 9.90E-02 9.90E-02 9.90E-02 9.90E-02 RHS-190 288'B 5.77E-02 5.77E-02 5.77E-02 5.77E-02 5.77E-02 5.77E-02 5.77E-02 5.77E-02 5.77E-02 5.77E-02 RHS-191 306'B 2.55E-01 2.55E-01 2.55E-01 2.55E-01 2.55E-01 2.55E-01 2.55E-01 2.55E-01 2.55E-01 2 '5E-01 RHS-192 306'S 5.07E-01 5.07E-01 5.07E-01 5.07E-01 5.07E-01 5.07E-01 5.07E-01 5.07E-01 5.07E-01 5.07E-01 RHS-193 1.05E-01 1 '5E-01 1.05E-01 1.05E-01 '1.05E-01 1.05E-01 1.05E-01 1.05E-01 1.05E-01 1.05E-01

• RX = Reactor Building; TB = Turbine Building; RW Rad Waste Building; CB = Control Building; DW = Orwell; HS = Hain Stack 9.2-4

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 TABLE 9.2.1 AREA RADIATION HONI TORS Reading (mR/hr) at:

Monitor 05:00 05 15 05:30 05:45 06:00 06:15 06:30 06:45 07:00 Location" (11:30) (11:45) (12:00) (12:15) (12:30) (12:45) (13:00) (13:15) (13:30)

RHS-1A DW 261'W 1.70E+08 1.45E+08 1.29E+08 1.16E+08 1.DOE+08 9.50E+07 9.20E+07 8.96E+07 RHS-18 261'W 2.DIE+08 1.70E+08 1.45E+08 1.29E+08 1.16E+08 1.DOE+08 9.50E+07 9.20E+07 8.96E+07 RHS-1C 2.01E+08 1.70E+08 1.45E+08 1.29E+08 1. 16E+08 1.DOE+08 9.50E+07 9.20E+07 8.96E+07 261W RMS-1D 261'X 2.01E+08 1.70E+08 1.45E+08 1.29E+08 1.16E+08 1.DOE+08 9.50E+07 9.20E+07 8.96E+07 RHS-2A 215'X 1.20E+01 9.67E-01 9.67E-01 9.67E-01 9.67E-01 9.67E-01 9.67E-01 9.67E-01 9.67E-01 RHS-2B 215'B 1.20E+01 1.40E+01 1.80E+01 2.DOE+01 2.10E+01 2.30E+01 2.20E>01 2.10E+01 2.DOE+01 RHS-3A 250'B 1.DOE+01 1.DOE+01 1 AB ODE+01 'I.DOE+01 1 'OE+01 1.DOE+01 1.DOE+01 1.DOE+01 1.DOE+01 RHS-38 250'B 1.DOE+01 1.00E+Ol 1.DOE+01 1 'OE+01 1.DOE+01 1.DOE+01 1.DOE+01 1.DOE+01 1.DOE+01 RHS-3C 250'X 1.DOE+01 1.DOE+0'I 1 ~ OOE+01 1.00E+01 1.25E+01 1.26E+01 1.27E+01 '1.28E+01 1 ~ 29E+01 RMS-101 175'X 1.47E+02 1.49E+02 1.53E+02 1.55Ei02 1.56E+02 1.58E+02 1.57E+02 1.56E+02 1.55E+02 RHS-102 261'.01E+08 175'X 1.20E+01 1.40E+01 1.80E+01 2.00E+01 2.10E+01 2.30E+01 2.20E+01 2.10E+01 2.DOE+01 RMS-103 175'X

1. 20EIO'l 1.40E+01 1.80E+01 2.DOE+01 2.10E+01 2.30E+01 2.20E+01 2.10E+01 2.DOE+01 RMS-104 175'X 1.20E+01 1.40E+01 1.80E+01 2.DOE+01 2.10E+01 2.30E+01 2.20E+01 2.10E+01 2.DOE+01 RHS-105 240'X 1.20E+01 1.40E+01 1.80E+01 2.DOE+01 2.10E+01 2.30E+01 2.20E+01 2 ~ 10E+01 2.DOE+01 RHS-106 261'X 1.20E+01 1.40E+01 1.80E+01 2.10E+01 2.30E+01 2.20E+01 2.10E+01 2.DOE+01 2.DOE+01'.DOE+01 RHS-108 289'X 1.20E+01 1.40E+01 1.80E+01 2.10E+01 2.30E+01 2.20E+01 2.10E+01 2.DOE+01 RHS-109 316'X 1.20E+01 1.40E+01 1.80E+01 2.DOE+01 2.10E+01 2.30E+01 2.20E+01 2.10E+01 2.DOE+01 RMS-111 353'X 1.20E+01 1.40E+01 1.80E+01 2.DOE+01 2.10E+01 2.30E+01 2.20E+01 2.10E+01 2.DOE+01 RMS-112 353'X 1.20E+01 1.40E+01 1.80E+01 2.DOE+01 2.10E+01 2.30E+01 2.20E+01 2.10E+01 2.DOE+01 RHS-113 353'X 1.20E+01 1.40E+01 1.80E+01 2.DOE+01 2.10E+01 2.30E+01 2.20E+01 2. '1 DE+01 2.DOE+01 RMS-114 353'B 1.20E+01 1.40E+01 1.80E+01 2.DOE+01 2. 'I DE+01 2.30E+01 2.20E+01 2.10E+01 2.DOE+01 RHS-116 250'B 3.97E-01 3.9?E-01 3.97E-01 3.9?E-01 3.97E-01 3.9?E-01 3.9?E-01 3.97E-01 3.9?E-01 RHS-117 250'B 1.17E.01 1.17E-01 1 '7E-01 1.1?E-OI 1.17E-01 1.17E-01 1.17E-01 1.17E-01 1.17E-01 RHS-118 261'B 8.85E.02 8.85E-02 8.85E-02 8.85E-02 8.85E-02 8.85E-02 8.85E-02 8.85E-02 8.85E-02 RHS-119 250'B 1.30E+01 1 ~ 30E+01 1.30E+01 1.30E+01 1.30E+01 1.30E+01 1.30E+01 1.30E+01 1.30E+01 RHS-120 2?7'B 3.52E-01 3.52E-01 3.52E-01 3.52E-01 3.52E-01 3.52E-01 3.52E-01 3.52E-01 3.52E-01 RHS-121 279'B 5.69E-02 5.69E-02 5.69E-02 5.69E-02 5.69E-02 5.69E-02 5.69E-02 5.69E-02 5.69E-02 RHS-123 306'W 4.DOE+00 4.DOE+00 4.DOE+00 4.DOE+00 4.00E+00 4.DOE+00 4.DOE+00 4.00E+00 4.DOE+00 RMS-125 6.36E-01 6.36E-01 6.36E-01 6.36E-01 6.36E-01 6.36E-01 6.36E-01 6.36E-01 6.36E-01

• RX = Reactor Building; TB = Turbine Building; RW = Rad Waste Building; CB = Control Building; DW = Dr~eli; HS = Main Stack 9.2-5

Nine Hile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 TABLE 9.2.1 AREA RADIATION HONITORS Reading (mR/hr) at:

Honitor 05:00 05:15 05:30 05 45 06:00 06:15 06:30 06:45 07:00 Location<< (11:30) (11:45) (12:00) (12:15) (12:30) (12:45) (13:00) (13:15) (13:30)

RHS-129 CB 306'B 3.07E-02 3.07E-02 3.07E-02 3.07E-02 3.07E-02 3.07E-02 3.07E-02 3.07E-02 RMS-130 261'W 3.98E-02 3.98E-02 3.98E-02 3.98E-02 3.98E-02 3.98E-02 3.98E.02 3.98E-02 3.98E-02 RHS-132 265'W 4.36E-02 4.36E-02 4.36E-02 4.36E-02 4.36E-02 4.36E-02 4.36E-02 4.36E-02 4.36E-02 RHS-133 279'W 1.57E-01 1.57E-01 1.57E-01 1.57E.01 1.57E-01 1 '7E-01 1.57E.01 1.57E-01 1.57E-01 RHS-134 261'B 3.85E-02 3.85E-02 3.85E-02 3.85E.02 3.85E-02 3.85E-02 3.85E.02 3.85E-02 3.85E-02 RHS-135 250'B 1 '3E-01 1 '3E-01 1.03E-01 1.03E-01 1.03E-01 1.03E-01 1.03E-01 1.03E-01 1.03E-01 RMS-136 288'B 8.81E-02 8.81E-02 8.81E-02 8.81E.02 8.81E-02 8.81E-02 8.81E-02 8.81E-02 8.81E-02 RHS-137 261'B 6.97E-02 6.97E-02 6.97E-02 6.97E.02 6.97E-02 6.97E-02 6.97E-02 6.97E-02 6.97E-02 RHS-138 250'X 1.50E-01 1 '0E-01 1.50E-01 1.50E-01 1.50E-01 1.50E.01 1.50E-01 1 '0E-01 1 '0E-01 RMS-139 215'X 1.00E+05 1 'OE+05 1.00E+05 1.00E+05 1.00E+05 1.00E+05 1.00E+05 1.00E+05 1.00E+05 RHS-140 261'.07E-02 353'B 6.91E-02 6.91E-02 6.91E-02 6.91E-02 6.91E-02 6.91E-02 6.91E-02 6.91E-02 6.91E-02 RHS-141 250'W 2.01E-01 2.01E-01 2.01E-01 2.01E-01 2.01E-01 2.01E-01 2.01E.01 2.01E-01 2.01E-01 RHS-142 279'X 5 '2E-02 5.12E-02 5.12E-02 5.12E.02 5.12E-02 5.12E-02 5.12E.02 5.12E-02 5.12E-02 RHS-143 261'X 1.20E+01 1.40E+01 1.80E+01 2.00E+01 2.10E+01 2.30E+01 2.20E+01 2.10E+01 2.00E+01 RMS-144 261'X 1 '0E+01 1.40E+01 1.80E+01 2.00E+01 2.10E+01 2.30E+01 2.20E+01 2 '0E+01 2.00E+01 RHS-145 240'W 5.76E-01 5.76E-01 5.76E-01 5.76E-01 5.76E-01 5.76E-01 5.76E-01 5.76E-.01 5.76E-01 RHS-146 279' 5.67E<<01 5.67E-01 5.67E-01 5.67E-01 5.67E-01 5.67E-01 5.67E-01 5.67E-01 5.67E-01 RHS-147 RW 291'W 1 ~ OOE+01 1.00E+01 1 ~ OOE+01 1.00E+01 1.00E+01 1.00E+01 1.00E+01 1 ~ OOE+01 1.00E+O'I RHS-148 279'X 3.98E-01 4.02E-01 4 '5E-01 4.08E-01 4.12E-01 4.12E-01 4 '2E-01 4.12E-01 4.12E-01 RMS-149 328'B I ~ 20E+01 1.40E+01 1.80E+01 2.00E+Ol 2.10E+01 2.30E+01 2.20Et01 2.10E+01 2.00E+01 RMS-150 250'B 1.00E+01 1.00E+01 1.00E+01 1.00E+01 1.00E+01 1.00E+01 1.00E+01 1.00E+01 1.00E+01 RHS-151 306'W 1.00E+01 1.00E+01 1.00E+01 1.00E+01 1 ~ OOE+01 1.00E+0'I 1 AD OBE+01 1.00E+01 1.00E+01 RHS-152 240'W 7.88E-02 7.88E-02 7.88E-02 7.PATE-02 7.88E-02 7.88E-02 7.88E-02 7.88E-02 7.88E-02 RHS-153 240'B 2.16E-01 2.16E-01 2.16E-01 2.16E-01 2 ~ 16E-01 2.16E-01 2.16E-01 2.16E-01 2.16E-01 RHS-154 250'B 9.90E-02 9.90E-02 9.90E-02 9.90E-02 9.90E-02 9.90E-02 9.90E-02 9.90E-02 9.90E-02 RHS-190 288'B 5.77E-02 5.77E-02 5 '7E-02 5.77E-02 5.77E-02 5.77E-02 5.77E-02 5.77E-02 5.77E-02 RMS-191 306'B 2.55E-01 2.55E-01 2.55E-01 2 '5E-01 2.55E-01 2.55E-01 2 '5E-01 2.55E-01 2 '5E-01 RHS-192 306'S 5.07E-01 5.07E-01 5.07E-01 5.07E-01 5.07E-01 5.07E-01 5.07E-01 5.07E-01 5.07E-01 RHS-193 1.00E+04 1.00E+04 1.00E+04 1.00E+04 1.00E+04 1.00E+04 1.00E+04 1.05E-01 1.05E-01

<<RX = Reactor Building; TB = Turbine Building; RW = Rad Waste Building; CB = Control Building; O'W = Orwell; HS = Main Stack 9.2-6

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 9.2.2 Continuous Air Monitors

Nine Hile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 TABLE 9.2.2 Continuous Air Honitors 00:00 00:15 00:30 00:45 01:00 01:15 Continuous Air Monitors (06:30) (06:45) (07 00) (07:15) (07:30) (07:45)

Radwaste Equipment Exhaust Vent HVM 195 Gas (1E-07 to 1E-01 uCi/cc) 4.91E-OT 4.91E-07 4.91E-07 4.91E-07 4.91E-07 4.91E-07 Partic. (1E-17 to 1E-05 uCi/cc) 2.36E.12 2.36E-12 2.36E-12 2.36E-12 2.36E-12 2.36E-12 Radwaste Tank Vent HVM 196 Gas (1E-07 to 1E-01 uCi/cc) 4.10E-07 4.10E-07 4.10E-07 4.10E-07 4.10E-OT 4.10E-07 Partic. (1E-11 to 1E-05 uCi/cc) 3.17E-12 3.17E-12 3.17E-12 3.17E-12 3.17E-12 3.17E-12 Radwaste Building Vent HVN 197 Gas (1E-07 to 1E-01 uCi/cc) 1.00E.OT 1.00E-07 1.00E-07 1.00E-07 1.00E-07 1.00E-07 Partic. (1E-11 to 1E-05 uCi/cc) 1.00E-11 1.00E-11 1.00E-11 1.00E-11 1.00E-11 1.00E-11 R.B. N. Aux Bay El. 196'; RHR Heat Exch.

HVR 237 Gas (1E-07 to 1E-Ol uCi/cc) 1.25E-OT 1.25E-07 1.25E-07 1.25E-07 1.25E-OT 1.25E-07 Partic. (1E-11 to 1E-05 uCi/cc) 3.01E-11 3.01E-11 3.01E-1'I 3.01E-11 3.01E-11 3.01E-11 R.B. S. Aux Bay El'96'; RHR Heat Exch.

HVR 238 Gas (1E-07 to 1E-01 uCi/cc) 2.11E-07 2.11E-07 2.11E-OT 2.11E-OT 2.11E-07 2.11E-07 Partic. (1E-11 to 1E-05 uCi/cc) 1.18E-'l1 1.18E-11 1.18E-11 1.18E-11 1 ~ 18E-11 1.18E-11 Radwaste Building El ~ 279'; Swgr Room HVN 199 Gas (1E-07 to 1E-01 uCi/cc) 3.80E-07 3.80E-07 3.80E-07 3.80E-OT 3.80E-07 3.80E-07 Partic. (1E-11 to 1E-05 uCi/cc) 1.10E-11 1.10E-11 1 '0E-11 1.10E-11 1.10E-11 1.10E-11 Turbine Building Vent HVT 206 Gas (lE-07 to 1E-01 uCi/cc) 2.01E-07 2.01E-07 2.01E-OT 2.01E-07 2.01E-07 2.01E-07 Partic. (1E-11 to 1E-05 uCi/cc) 8.88E-11 8.88E-11 8.88E-11 8.88E-11 8.88E-11 8.88E-11 Reactor Building Recirculation HVR 229 Gas (1E-07 to 1E-01 uCi/cc) 1.00E-07 1.00E-07 1.00E-07 1.00E-07 1.00E-07 1.00E-07 Partic. (1E-11 to 1E-05 uCi/cc) 1.00E-11 1 ~ OOE-11 1.00E-11 1.00E-1'I 1 'OE-11 1.00E-11 TCS CAH (CPH) 50 s 50 50 50 50 50 EOF CAH (CPH) 50 50 50 50 50 50

• The ranges shown indicate possible detection limits. If a mininun or maxinxxn value is shown in this table, it indicates what the instrwent would read in "real-life" and not necessarily the true activity in the process stream.

9.2-7

Mine Mile Point it 2 1990 Annual Exercise Scenario Ho. 19, Rev. 1 TABLE 9.2.2 Continuous Air Monitors 01:30 01:45 02:00 02:15 02:30 02:45 Continuous Air Honitors (08:00) (08:15) (08:30) (08:45) (09:00) (09<15)

Radwaste Equipment Exhaust Vent HN 195 Gas (1E-07 to 1E-01 uCi/cc) 4.91E.07 4.91E-07 4.91E-07 4.91E-07 4.91E-07 4.91E-07 Partic. (1E-17 to 1E-05 uCi/cc) 2.36E-12 2.36E-12 2.36E-12 2.36E-12 2.36E-12 2.36E-12 Radwaste Tank Vent HVM '196 Gas (1E-07 to 1E-01 uCi/cc) 4.10E.07 4.10E-07 4.10E-07 4.10E-07 4.10E.07 4.10E-07 Partic. (1E-11 to 1E-05 uCi/cc) 3.17E-12 3.17E.12 3.17E-12 3.17E-12 3.17E-12 3.17E-12 Radwaste Building Vent HN 197 Gas (1E-07 to 1E-01 uCi/cc) 1.00E-07 1.00E-07 1.00E-07 1.00E-07 1.00E-07 1.00E-07 Partic. (1E-11 to 1E-05 uCi/cc) 1.00E-11 1.00E-11 1.00E-11 1 'OE-11 1.00E-11 1.00E-11 R.BE H. Aux Bay El. 196'; RHR Heat Exch.

HVR 237 Gas (1E-07 to 1E-01 uCi/cc) 1.25E-07 1.25E-07 1.25E-07 1.25E-07 1.25E-07 1.25E-07 Partic. (1E-11 to 1E-05 uCi/cc) 3.01E.11 3.01E-11 3.01E-11 3.01E-11 3.01E-11 3.01E-11 R.B. S. Aux Bay El. 196<; RHR Heat Exch.

HVR 238 Gas (1E-07 to 1E-01 uCi/cc) 2.11E-07 2.11E-07 2.11E-07 2.11E-07 2.11E-07 2.11E-07 Partic. (1E-11 to 1E-05 uCi/cc) 1.18E-11 1.18E-11 1.18E-11 1.18E-11 1 ~ 18E-11 1.18E-11 Radwaste Building El'79'; Swgr Room HN 199 Gas (1E-07 to 1E-01 uCi/cc) 3.80E-07 3.80E-07 '3.80E-07 3.80E-07 3.80E-07 3.80E-07 Partic. (1E-11 to 1E-05 uCi/cc) 1.10E.11 1.10E-11 1.10E-11 1.10E-11 1.10E-11 1.10E-11 Turbine Building Vent

'HVT 206 Gas (1E-07 to 1E-01 uCi/cc) 2.01E-07 2.01E-07 2.01E-07 2.01E-07 2.01E-07 2.01E-07 Partic. (1E-11 to 1E-05 uCi/cc) 8.88E-11 8.88E-11 8.88E-11 8.88E-11 8.88E-11 8.88E-11 Reactor Building Recirculation HVR 229 Gas (1E-07 to 1E-01 uCi/cc) 1.00E-07 1.00E-07 1.00E-07 1.00E-07 1.00E-07 1 ~ OOE-07 Partic. (1E-11 to 1E-05 uCi/cc) 1.00E.11 1 'OE-11 1.00E-11 1.00E-11 1.00E-11 1.00E-11 TCS CAM (CPM) 50 50 50 50 50 50 EOF CAM (CPM) 50 50 50 50 50 50

• The ranges shown indicate possible detection limits. If a miniimsn or maximmi value is shown in this table, it indicates what the instrunent would read in "real-life" and not necessarily the true activity in the process stream.

9.2-8

0 Nine Nile Point nit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 TABLE 9.2.2 Continuous Air Honitors 03:00 03:15 03:30 03:45 04:00 04 15 Continuous Air Monitors (09:30) (09:45) (10:00) (10:15) (10:30) (10 45)

Radwaste Equipment Exhaust Vent HVN 195 Gas (1E-07 to 1E-01 uCi/cc) 4.91E-07 4.91E-07 4.91E-07 4.91E-07 4.91E-07 4.91E-07 Partic. (1E-17 to 1E-05 uCi/cc) 2.36E-12 2.36E-12 2.36E-12 2.36E-12 2.36E-12 2.36E-12 Radwaste Tank Vent HVM 196 Gas (1E-07 to 1E-01 uCi/cc) 4.10E-07 4.10E-07 4.10E-07 4.10E-07 4.10E-07 4.10E-07 Partic. (1E-11 to 1E-05 uCi/cc) 3.17E-12 3.17E-12 3.17E-12 3.17E-12 3.17E-12 3.17E-12 Radwaste Building Vent HVW 197 Gas (1E-07 to 1E-01 uCi/cc) 1.00E-07 1.00E-07 1.00E-07 1.00E-07 1.00E-07 1.00E-07 Partic. (1E-11 to 1E-05 uCi/cc) 1.00E-11 1.00E-11 1.00E-11 1.00E-11 1.00E-11 1.00E-11 R.B. N. Aux Bay El. 196'; RHR Heat Exch.

HVR 237 Gas (1E-07 to 1E-01 uCi/cc) 1.25E-07 1.25E-07 1.25E-07 1.25E-07 1.25E-07 1.72E-05 Partic. (1E-11 to 1E-05 uCi/cc) 3.01E-1'I 3.01E-11 3.01E-11 3.01E-11 3.01E-11 2.12E-10 R.B. S. Aux Bay El. 196'; RHR Heat Exch.

HVR 238 Gas (1E-07 to 1E-01 uCi/cc) 2.11E-07 2.11E-07 2.11E-07 2.11E-07 2.11E-07 1.72E-05 Partic. (1E-11 to 1E-05 uCi/cc) 1.18E-11 1.18E-11 1.18E-11 1.18E-11 1.18E-11 2.12E-10 Radwaste Building El. 279'; Swgr Room HVN 199 Gas (1E-07 to lE-Ol uCi/cc) 3.80E-07 3.80E-07 3.80E-07 3.80E.07 3.80E-07 3.80E-07 Partic. (1E-'I'I to 1E-05 uCi/cc) 1.10E-11 1.10E-11 1.10E-11 1.10E-11 1.10E-11 1.10E-11 Turbine Building Vent HVT 206 Gas (1E-07 to 1E-01 uCi/cc) 2.01E-07 2.01E-07 2.01E-07 2.01E-07 2.01E-07 2.01E-07 Partic. (1E-11 to 1E-05 uCi/cc) 8.88E-11 8.88E-1'I 8.88E-11 8.88E-11 8.88E-11 8.88E-11 Reactor Building Recirculation HVR 229 Gas (1E-07 to 1E-01 uCi/cc) 1.00E-07 1.00E-07 1 ~ OOE-07 1.00E.07 1.00E-07 1.72E-05 Partic. (1E-11 to 1E-05 uCi/cc) 1.00E-11 1.00E-11 1 ~ OOE-11 1.00E-11 1.00E-11 2.12E-10 TCS CAH (CPH) 50 g 50 50 50 50 50 EOF CAH (CPH) 50 50 50 50 50 50

• The ranges shown indicate possible detection limits. If a mininun or maximra value is shown in this table, it indicates what the instrment would read in "real-life" and not necessarily the true activity in the process stream.

9.2.9

Mine Mile Point t2 1990 Annual Exercise Scenario Ho. 19, Rev. 1 TABLE 9.2.2 Continuous Air Monitors 04:30 04:45 05:00 05:15 05:30 05 45 Continuous Air Monitors (11:00) (11:15) (11:30) (11:45) (12:00) (12:15)

Radwaste Equipment Exhaust Vent HVH 195 Gas (1E-07 to 1E-01 uCi/cc) 4.91E-07 4.91E-07 4.91E-07 4.91E-07 4.91E-OT 4.91E-OT Partic. (1E-17 to 1E-05 uCi/cc) 2.36E-12 2.36E-12 2.36E-12 2.36E-12 2.36E-12 2.36E-12 I

Radwaste Tank Vent HVH 196 Gas (1E-OT to 1E-01 uCi/cc) 4.10E-07 4.10E-07 4.10E-07 4.10E-07 4.10E-07 4.10E-07 Partic. (1E-11 to 1E-05 uci/cc) 3.17E-12 3.17E-12 3.17E-12 3 ~ 17E-12 3.17E-12 3.17E-12 Radwaste Building Vent HVH 197 Gas (1E-07 to 1E-01 uCi/cc) 1.00E-07 1.00E-07 , 1.00E-07 1.00E-07 1.00E-07 1.00E-07 AROSE-03 Partic. (1E-11 to 1E-05 uCi/cc) l.OOE-11 1.00E-11 1.00E-11 1 ~ OOE-11 1.00E-11 1.00E-11 R.B. H. Aux Bay El. 196'; RHR Heat Exch.

HVR 237 Gas (1E-07 to 1E-01 uCi/cc) 5.16E-05 1.67E-04 3.97E-04 6.21E-04 8.34E-04 1 Partic. (1E-11 to 1E-05 uCi/cc) 6.17E-10 2.10E-09 5.06E-09 1.10E-08 1.98E-08 3.10E-OS R.B. S. Aux Bay El. 196'; RHR Heat Exch.

HVR 238 Gas (1E-07 to 1E-01 uCi/cc) 5.16E-05 1.67E-04 3.97E-04 6.21E-04 8.34E-04 'l.05E-03 Partic. (1E-11 to 1E-05 uCi/cc) 6.17E-10 2.10E-09 5.06E-09 1.10E-08 1.98E-OS 3 ~ 10E-08 Radwaste Building El. 279'; Swgr Room HVM 199 Gas (1E-07 to 1E-01 uCi/cc) 3.80E-07 3.80E-OT 3.80E-07 3.80E-07 3.80E-07 3.80E-OT Partic. (1E-11 to 1E-05 uCi/cc) 1.10E-11 1.10E-11 1.10E-11 1.10E-11 1.10E-11 1 ~ 10E-11 Turbine Building Vent HVT 206 Gas (1E-07 to. 1E-01 uCi/cc> 2.01E-07 2.01E.07 2.01E-OT 2.01E-07 2.01E-07 2.01E-07 Partic. (1E-11 to 1E-05 uCi/cc> 8.88E-11 8.88E-11 8.88E-11 8.88E-11 8.88E-11 8.88E-11 Reactor Building Recirculation HVR 229 Gas (1E-07 to 1E-01 uCi/cc) 5.16E-05 1.67E-04 3.97E-04 6.21E-04 8.34E-04 1.05E-03 Partic. (1E-11 to lE-05 uCi/cc) 6.17E-10 2.10E-09 5.06E-09 1 ~ 10E-08 1.98E-08 3.10E-OS TCS CAM (CPM) 50 s 50 50 50 50 50 EOF CAM (CPM) 50 50 50 50 50 50

~The ranges shown indicate possible detection limits. If a minimsm or maxinun value is shown in this table, skat the instrunent would read in "real-life" and not necessarily the true activity in the process stream.

it indicates 9.2-10

Nine Hite Point nit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 TABLE 9.2.2 Continuous Air Honitors 06:00 06:15 06:30 06:45 07:00 Continuous Air Honitors (12:30) (12 45) ('I3:00) (13:15) (13:30)

Radwaste Equipment Exhaust Vent HVM 195 Gas (1E-07 to 1E-01 uCi/cc) 4.91E-07 4.91E-07 4.91E-07 4.91E-07 4.91E-07 Partic. (1E-'17 to 1E-05 uCi/cc) 2.36E-12 2.36E-12 2.36E-12 2.36E-12 2.36E-12 Radwaste Tank Vent HVN 196 Gas (1E-07 to 1E-01 uCi/cc) 4.10E-07 4.10E-07 4.10E-07 4.10E-07 4.10E-07 Partic. (1E-11 to 1E-05 uCi/cc) 3.17E-12 3.17E-'12 3.17E-12 3 ~ 17E-12 3.17E-12 Radwaste Building Vent HVII 197 Gas (1E-07 to 1E-01 uCi/cc) 1.00E-07 1.00E-07 1.00E-07 1.00E-07 1 ~ OOE-07 Partic. (1E-11 to 1E-05 uCi/cc) 1.00E-11 1.00E-11 1.00E-11 1.00E-11 1.00E-11 RE B. N. Aux Bay El. 196'; RHR Heat Exch.

HVR 237 Gas (1E-07 to 1E-01 uCi/cc) 1.26E-03 1.47E-03 1.45E-03 1.43E-03 1.42E-03 Partic. (1E-11 to 1E-05 uCi/cc) 4.45E-OB 6.00E-08 6.00E-08 6.00E-08 6.00E-08 R.B. S. Aux Bay El. 196'; RHR Heat Exch.

HVR 238 Gas (1E-07 to 1E-01 uCi/cc) 1.26E-03 1.47E-03 1.45E.03 1 ~ 43E-03 1.42E-03 Partic. (1E-11 to 1E-05 uCi/cc) 4.45E-OB 6.00E-08 6.00E-08 6.00E-08 6.00E-08 Radwaste Building El. 279'; Swgr Room HVW 199 Gas (1E-07 to 1E-01 uCi/cc) 3.80E-07 3.80E-07 3.80E-07 3.80E-07 3.80E-07 Partic. (1E-11 to 1E-05 uCi/cc) 1.10E-11 '1.10E-11 1 ~ 10E-11 1.10E-11 1.10E-11 Turbine Building Vent HVT 206 Gas (1E-07 to 1E-01 uCi/cc) 2.01E-07 2.01E-07 2.01E-07 2.01E-07 2.01E-07 Partic. (1E-11 to 1E-05 uCi/cc) 8.88E-11 8.88E-11 8.88E-11 8.88E-11 8.88E-11 Reactor Building Recirculation HVR 229 Gas (1E-07 to 1E-01 uCi/cc) 1.26E-03 1.47E-03 1.45E-03 1.43E-03 1.42E-03 Partic. (1E-11 to 1E-05 uCi/cc) 4.45E-OB 6.00E-OB 6.00E-08 6.00E-08 6.00E-08 TCS CAH (CPH) 50 g 50 50 50 50 EOF CAN (CPH) 50 50 50 50 50

• The ranges shown indicate possible detection limits. If a minimua or maximm value is shown in this table, it indicates what the instrunent would read in "real-life" and not necessarily the true activity in the process stream.

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 9.2.3 Process R'adiation Monitors

4 Nine Hile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1e TABLE 9.2.3 Process Radiation Honitors 00:00 00:15 00:30 00:45 01:00 01:15 Honitors* (06:30) (06:45) (07 00) (07 15) (07:30) (07:45)

Drywell Contairment Atmosphere CHS 10A Gas (1E-07 to 1E-01 uCi/cc) 1.13E-07 1.13E-07 1.13E-07 5.29E-04(A> 5.35E.04(A) 5.40E-04(A)

Partic. ('IE-11 to 1E-05 uCi/cc) 7.3'IE-11 7.31E-11 7.31E-11 2.42E-09(A) 2.42E-09(A) 2.42E.09(A)

CHS 108 Gas (1E-07 to 1E-01 uCi/cc) 1.11E.07 1.11E-07 1.11E-07 5.31E-04(A) 5.37E-04(A) M42E-04(A)

Partic. (1E-11 to 1E-05 uCi/cc) 7.31E-11 7.31E-11 7.31E-11 2.60E-09(A) 2.60E-09(A) 2.60E-09(A)

Reactor Building Vent Effluent Honi tor NVR 14A Gas (1E-07 to 1E-01 uCi/cc) 1.00E-07 1.00E-07 1.00E-07 1.00E-07 1.00E-07 1.00E-07 Partic. (1E-11 to 1E-05 uCi/cc) 1.00E-11 1.00E-11 1 ~ OOE-11 1.00E-11 1.00E-11 1.00E-11 HVR 148 Gas (1E-07 to 1E-01 uCi/cc) 1.15E-07 1.15E-07 1.15E-07 1.15E-07 1.15E-07 1.15E-07 HVR 32A Gas (1E-07 to 1E-01 uCi/cc) 2.77E-07 2.77E-07 2.77E-07 2.77E-07 2.77E-07 2.77E-07 Partic. (1E-11 to 1E-05 uCi/cc) 1.23E-11 1.23E-11 1.23E-11 1.23E-11 1.23E-11 1.23E-11 NVR 328 Gas (1E-07 to IE-01 uCi/cc) 1. 18E-07 1.18E-07 1.18E-07 1.18E-07 1.18E-07 1 '8E-07 Hain Control Room Air Intake NVC 18A Gas (1E-07 to 1E-01 uCi/cc) 4.38E-07 4.38E-07 4.38E-07 4.38E-07 4.38E-07 4.38E-07 NVC 188 Gas (1E-07 to 1E-01 uCi/cc) 2.47E.07 2.47E-07 2.47E-07 2.47E-07 2.47E-07 2.47E-07 HVC 18C Gas (1E-07 to 1E-01 uCi/cc) 3.58E-07 3.58E-07 3.58E-07 3.58E-07 3.58E-07 3.58E-07 HVC 180 Gas (1E-07 to 1E-01 uCi/cc) 2.17E-07 2.17E-07 2.17E-07 2.17E-07 2.17E-07 2.17E-07 RHR Neat Exchanger Service Water SWP 23A Liquid (1E-07 to 1E-01 uCi/cc) 1.29E-06 1.29E-06 '1.29E-06 1.29E-06 1.29E-06 1.29E-06 SWP 238 Liquid (1E-07 to 1E-01 uCi/cc) 1.35E-06 1.35E-06 1.35E-06 1.35E-06 1.35E-06 1.35E-06 Hain Steam Line HSS 46A (1E+00 to 1E+06 mR/hr) 4.30E+02 4.34E+02 4.39E+02 4.43E+02 4.47E+02 4.52E+02 HSS 46B (1E+00 to 1E+06 mR/hr) 4.30E+02 4.34E+02 4.39E+02 4.43E+02 4.47E+02 4.52Ei02 HSS 46C (1E+00 to 1E+06 mR/hr) 4.35E+02 4.39E+02 4.44E+02 4.48E+02 4.52E+02 4.57E+02 HSS 46D (IEt00 to 1E+06 mR/hr) 4.10E+02 4.14E+02 4.'18E+02 4.22E+02 4.26E<02 4.31E402 Service Water Discharge SW 146A Liquid (1E-07 to 1E-01 uCi/cc) 1.55E-06 1.55E-06 1 '5E-06 1.55E-06 1.55E-06 1.55E-06 SW 1468 Liquid (1E-07 to IE-01 uCi/cc) 1.61E-06 1.61E-06 1.6'IE-06 1.61E-06 1.61E-06 1.61E-06

• The ranges shown indicate possible detection limits. If a mininun or maxinxm value is shown in this table, it indicates what the instrunent would read in "real-life" and not necessarily the true activity in the process stream.

(A) - Denotes an alarming monitor 9.2-12

Nine Hile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 TABLE 9.2.3 Process Radiation Honitors 00:00 00:15 00:30 00:45 01:00 01:15 Honitors* (06:30) (06:45) (07 00) (07:15) (07:30) (07 45)

Solid Radwaste El. 279'outh

'WSS 207 (1E-01 to 1E+04 uCi/cc) 1 ~ OOE-01 1 'OE-01 1.00E-01 1.00E-01 1.00E-01 1.00E-01

'MSS 208 (1E-01 to 1E+04 uCi/cc) 1.00E-01 1.00E-01 1.00E-01 1.00E-01 1.00E-01 1.00E-01 Fuel Pool Cooling Pwy Discharge SFC 142 Liquid (1E-07 to 1E-01 uCi/cc) 1.24E-07 1.24E-07 1.24E-07 1.24E-07 1 '4E-07 1.24E-07 Reactor Building Closed Loop Cooling Hater CCP 115 Liquid (1E-07 to 1E-01 uCi/cc) 4.46E 07 4 '6E-07 4.46E-07 4.46E-07 4.46E-07 4.46E-07 CCP 131 Liquid (1E-07 to 1E-01 uCi/cc) 1.07E-06 1.07E-06 1 '7E-06 1.07E-06 1.07E-06 1.07E-06 Turbine Building Closed Loop Cooling Llater CCS 152 Liquid (1E-07 to 1E-01 uCi/cc) 5.85E-07 5.85E-07 5.85E-07 5.85E-07 5.85E-07 5.85E-07 Liquid Radwaste Lug 206 Liquid (1E-07 to 1E-01 uCi/cc) 8.56E 06 8.56E-06 8.56E-06 8.56E-06 8.56E-06 8.56E-06 I

Cooling Tower Blowdown Cus 157 Liquid (1E-07 to 1E-01 uCi/cc) 1 '8E-06 1.78E-06 1.78E-06 1.78E-06 1.78E-06 1.78E-06 Standby Gas Treatment G'IS 105 Gas (1E-07 to 1E-01 uCi/cc) 1.02E-07 1 '2E-07 1.02E-07 1.02E-07 1.02E-07 1.02E-07 Offgas OFG 13A Gas (1E-03 to 1E+02 uCi/cc) 6.50E-03 6.50E-03 6.50E-03 5.41E-03 4.01E-03 2.56E-03 OFG 138 Gas (1E-03 to 1E+02 uCi/cc) 2.45E-03 2.45E-03 2.45E-03 2.30E-03 1.98E-03 1.46E-03

• The ranges shown indicate possible detection limits. If a minimm or maximsn value is shown in this table, it indicates what the instrunent would read in areal-life" and not necessarily the true activity in the process stream.

9.2-13

Mine Mile Point Unit 2 1990 Annual Exercise Scenario Ho. 19, Rev. 1e TABLE 9.2.3 Process Radiation Monitors 01:30 01:45 02 00 02:15 02:30 02:45 Monitors* (08:00) (08:15) (08:30) (08:45) (09:00) (09:15)

Drywell Containment Atmosphere CMS 10A Gas (1E-07 to 1E-01 uCi/cc) 5.45E-05(A) 4.10E-05(A) 9.60E-06(A) 1.86E-06 1.00E-OT 1.00E-07 Partic. (1E-11 to 1E-05 uCi/cc) 7.42E 09 9.10E-10 6.50E-10 1.40E-10 1.00E-11 1.00E-11 CMS 108 Gas (1E-07 to 1E-01 uCi/cc) 5.47E.04(A) 4.22E.05(A) 9.62E-06(A) 3.88E-06 1.00E-07 1.00E-07 Partic. (1E-11 to 1E-05 uCi/cc) 2.60E-09 9.00E-10 6.68E-10 1.58E-10 1.00E-11 1.00E-11 Reactor Building Vent Effluent Monitor HVR 14A Gas (1E-07 to 1E-01 uCi/cc) 1.00E-07 1.00E-07 1.00E-07 1.00E.07 1.00E.OT 1.00E 07 Partic. (1E-11 to 1E-05 uCi/cc) 1.00E-11 1.00E-11 1.00E-11 1.00E-11 1.00E-'l1 1.00E-11 HVR 14B Gas (1E-07 to 1E-01 uCi/cc) 1.15E-07 1.15E-07 1.15E-07 1.15E-OT 1.15E-OT 1.15E-OT HVR 32A Gas (1E-07 to 1E-01 uCi/cc) 2.77E-07 2.77E-07 2.77E-07 2.77E-07 2.77E-07 2.77E-07 Partic. (1E-11 to 1E-05 uCi/cc) 1.23E-11 1.23E-11 1.23E-11 1.23E-11 1.23E-11 1.23E.11 HVR 328 Gas (1E-07 to 1E-01 uCi/cc) 1.18E-OT 1.18E-07 1.18E-07 1.18E-07 1.18E-07 1.18E-07 Main Control Rocm Air Intake HVC 18A Gas (1E-07 to 1E-01 uCi/cc) 4.38E-OT 4.38E-07 4.38E-07 4.38E-07 4.38E-07 4.38E-07 HVC 188 Gas (1E-07 to 1E-01 uCi/cc) 2.47E.07 2.47E-07 2.47E-07 2.47E-07 2.47E-OT 2.47E-07 HVC 18C Gas (1E-07 to 1E-01 uCi/cc) 3.58E-07 3.58E-07 3.58E-07 3.58E-07 3.58E-DT 3.58E-07 HVC 180 Gas (1E-07 to 1E-01 uCi/cc) 2.17E-07 2.17E.07 2.17E-OT 2.17E-07 2.17E-07 2.17E-07 RHR Heat Exchanger Service Water SWP 23A Liquid (1E-07 to 1E-01 uCi/cc) 1 '9E-06 1.29E-06 1.29E-06 1.29E-06 1.29E-06 1.29E-06 SWP 23B Liquid (1E-07 to 1E-01 uCi/cc) 1.35E-06 1.35E-06 1.35E-06 1.35E-06 1.35E-06 1.35E-06 Main Steam Line MSS 46A (1Et00 to 1E+06 mR/hr) 4.56E+02 4.60E+02 4.64E~02 4.69E>02 4.73E+02 4.77E+02 MSS 46B (1E+00 to 1E+06 mR/hr) 4.56E+02 4.60E+02 4.64E+02 4.69E+02 4.73EI02 4.77E+02 MSS 46C (1E+00 to 1E+06 mR/hr) 4.61E~02 4.65E+02 4.70E+02 4.74Ei02 4.79Ei02 4.83E+02 MSS 46D (1E+00 to 1E+06 mR/hr) 4.35E+02 4.39E+02 4.43E+02 4.47E+02 4.51E+02 4.55Ei02 Service Water Discharge SW 146A Liquid (1E-07 to 1E-01 uCi/cc) 1.55E-06 1.55E-06 1.55E-06 1.55E-06 1.55E-06 1.55E.06 SW 1468 Liquid (1E-07 to 1E-01 uCi/cc) 1.61E-06 1.61E-06 1.61E-06 1.61E.06 1.61E-06 1.61E-06

• The ranges shown indicate possible detection limits. if a minimm or maxieun value is shown in this table, it indicates what the instrunent would read in "real-life" and not necessarily the true activity in the process stream.

(A) - Denotes an alarming monitor 9.2-14

Nine Hile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 TABLE 9.2.3 Process Radiation Honitors 01:30 01:45 02 00 02:15 02:30 02 45 Honitors* (08:00) (08:15) (08:30) (08:45) (09:00) (09:15)

Solid Radwaste El. 279'outh MSS 207 (1E-01 to 1E+04 uCi/cc) 1.00E-01 1.00E-01 1.00E-01 1.00E-01 1.00E 01 1.00E-01 MSS 208 (1E-01 to 1E+04 uCi/cc) 1.00E-01 1.00E-01 1-OOE-01 1.00E-01 1 'OE-01 1 'OE-01 Fuel Pool Cooling Pump Discharge SFC 142 Liquid (1E-07 to 1E-01 uCi/cc) 1.24E-07 1.24E.07 1.24E-07 1.24E-07 1.24E-07 1.24E-07 Reactor Building Closed Loop Cooling 'Mater CCP 115 Liquid (1E-07 to 1E-01 uCi/cc) 4 '6E-07 4.46E 07 4.46E-07 4.46E-07 4.46E-07 4 '6E-07 CCP 131 Liquid (1E-07 to 1E-01 uCi/cc) 1.07E-06 1.07E-06 1.07E-06 1.07E-06 1.07E-06 1.07E-06 Turbine Building Closed Loop Cooling Mater CCS 152 Liquid (1E-07 to 1E-01 uCi/cc) 5.85E-07 5.85E-07 5.85E-07 5.85E-07 5.85E-07 5.85E-07 Liquid Radwaste LMS 206 Liquid (1E-07 to 1E-01 uCi/cc) 8.56E-06 8.56E-06 8.56E-06 8.56E-06 8.56E-06 8.56E-06 Cooling Tower Biowdown CMS 157 Liquid (1E-07 to 1E-01 uCi/cc) 1.78E-06 1.78E-06 1.78E-06 1.78E-06 1.78E-06 1.78E-06 Standby Gas Treatment GTS 105 Gas (1E-07 to 1E-01 uCi/cc) 1.02E-07 1.02E-07 1.02E-07 1.02E-07 1.02E-07 1.02E-07 Offgas OFG 13A Gas (1E-03 to 1E+02 uCi/cc) 1.42E-03 1.00E-03 1.00E-03 1.00E-03 1 ~ OOE-03 1 ~ OOE-03 OFG 13B Gas (1E-03 to 1E+02 uCi/cc) 1.19E-03 1.00E-03 1.00E-03 1.00E-03 1 ~ OOE-03 1.00E-03

• The ranges shown indicate possible detection limits. If a minimm or maximan value is shown in this table, it indicates what the instrunent would reed in "real-life" and not necessarily the true activity in the process stream.

9.2-15

Hine Hile Point Unit 2 1990 Annual Exercise Scenario Ho. 19, Rev. 1 TABLE 9.2.3 Process Radiation Honitors 03:00 03:15 03:30 03:45 04:00 04:15 Konitors* (09:30) (09:45) (10:00) (10:15) (10:30) (10:45)

Drywcll Containment Atmosphere CHS 10A Gas (1E-07 to 1E.01 uCi/cc) 1.00E-07 1.00E-07 1 ~ OOE-07 1 ~ OOE-07 1.00E-07 1.00E-07 Partic. (1E-11 to 1E-05 uCi/cc) 1.00E-11 1.00E-11 1.00E-11 1.00E-11 1.00E-11 1.00E-'I'I CHS 108 Gas (1E-07 to 'IE-01 uCi/cc) 1.00E-07 1.00E-07 1.00E-07 1.00E-07 1.00E-07 1.00E-07 Partic. (1E-11 to 1E-05 uCi/cc) 1.00E-11 1.00E-11 1.00E-11 1 ~ OOE-11 1.00E-11 1.00E-11 Reactor Building Vent Effluent Honitor HVR 14A Gas (1E-07 to 1E-01 uCi/cc) 1 ~ OOE-07 1.00E-07 1.00E-07 1.00E-07 1.00E-07 1.00E-07 Partic. (1E-11 to 1E-05 uCi/cc) 1.00E-11 1.00E-11 1.00E-11 1 ~ DOE-11 1.00E-11 1 ~ OOE-11 HVR 148 Gas (1E-07 to 1E-01 uCi/cc) 1.15E-07 1.15E-07 1 '5E-07 1 ~ 15E-07 1.15E-07 1.15E-07 HVR 32A Gas (1E-07 to 1E-01 uCi/cc) 2.77E-07 2.77E-07 2.77E-07 2 ~ 77E-07 2.77E-07 2.77E-07 Partic. (1E-11 to 1E-05 uCi/cc) 1.23E-11 1.23E-11 1.23E-11 1.23E-11 1.23E-11 1.23E-11 HVR 328 Gas (1E-07 to 1E-01 uCi/cc) 1 ~ 18E-07 1.18E-07 1.18E-07 1.18E-07 1.18E-07 1.18E-07 I

Hain Control Room Air Intake HVC 18A Gas (1E-07 to 1E-01 uCi/cc) 4.38E-07 4.38E-07 4.38E-07 4.38E-07 4.38E-07 4.38E-07 HVC 188 Gas (1E-07 to 1E-01 uCi/cc) 2.47E-07 2.47E-07 2.47E-07 2.47E-07 2.47E-07 2.47E-07 HVC 18C Gas (1E-07 to 1E-01 uCi/cc) 3.58E-07 3.58E-07 3.58E-07 3.58E-07 3 '8E-07 3.58E-07 HVC 180 Gas (1E-07 to 1E-01 uCi/cc) 2.17E-07 2.17E-07 2.17E-07 2.17E-07 2.17E-07 2.17E-07 RHR Heat Exchanger Service Mater SMP 23A Liquid (1E-07 to 1E-Ol uCi/cc) 1 '9E-06 1.29E-06 1.29E-06 1.29E-06 1.29E-06 1.29E-06 SMP 238 Liquid (1E-07 to 1E-01 uCi/cc) 1 '5E-06 1.35E-06 1.35E-06 1.35E-06 1.35E-06 1.35E-06 Hain Steam Line HSS 46A (1E+00 to 1E+06 mR/hr) 4.82E+02 4.86E+02 4.90E+02 4.95E+02 4.99E+02 5.03E+02 MSS 468 (1E+00 to 1E+06 mR/hr) 4.82E+02 4.86E+02 4.90E+02 4.95E+02 4.99E+02 5.03E+02 HSS 46C (1E+00 to 1E+06 mR/hr) 4.87E+02 4.92E+02 4.96E+02 5.DOE+02 5.05E+02 5.09E+02 HSS 460 (1E+00 to 1E+06 mR/hr) 4.59E+02 4.63E+02 4.67E+02 4.72E+02 4.76E+02 4.80E+02 Service Mater Discharge SM 146A Liquid (1E-07 to lE-01 uCi/cc) 1.55E-06 1.55E-06 1.55E-06 1.55E-06 1.55E-06 1.55E-06 SM 1468 Liquid (1E-07 to 1E-Ol uCi/cc) 1.61E-06 1.61E-06 1.61E-06 1.61E-06 1.61E-06 1.61E-06

• The ranges shown indicate possible detection limits. If a miniaxsn or maximm value is shown in this table, it indicates what the instrment would read in "real-life" and not necessarily the true activity in the process stream.

9.2-16

Nine Hiie Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 TABLE 9.2.3 Process Radiation Monitors 03:00 03:15 03:30 03:45 04:00 04:15 Monitors* (09:30) (09:45) (10:00) (10:15) (10:30) (10:45)

Solid Radwaste El. 279~ South

'MSS 207 (1E-01 to 1E+04 uCi/cc) 1.00E-01 1.00E-01 1.00E-01 1.00E-01 1.00E-01 1.00E-01

'MSS 208 (1E-Ol to 'IE+04 uCi/cc) 1.00E-01 1 ~ OOE-01 1.00E-01 1.00E-01 1.00E-01 1.00E-01 Fuel Pool Cooling Pump Discharge SFC 142 Liquid (1E-07 to 1E-01 uCi/cc) 1.24E-07 1.24E-07 1.24E-07 1 ~ 24E-07 1.24E-07 1.24E-07 Reactor Building Closed Loop Cooling Mater CCP 115 Liquid (1E-07 to 1E-Ol uCi/cc) 4.46E-07 4.46E-07 4.46E-07 4.46E-07 4.46E-07 4.46E-07 CCP 131 Liquid (1E-07 to 1E-01 uCi/cc) 1 '7E-06 1.07E-06 1.07E-06 1.07E-06 1.07E-06 1.07E-06 Turbine Building Closed Loop Cooling Mater CCS 152 Liquid (1E-07 to 1E-01 uCi/cc) 5.85E-07 5.85E-07 5.85E-07 5.85E-07 5.85E-07 5.85E-07 Liquid Radwaste LMS 206 Liquid (1E-07 to 1E-01 uCi/cc) 8.56E-06 8.56E-06 8.56E-06 8.56E-06 8.56E-06 8.56E-06 Cooling Tower Slowdown CMS 157 Liquid (1E-07 to 1E-01 uCi/cc) 1.78E-06 1.78E-06 1.78E-06 1.78E-06 1.78E-06 1.78E-06 Standby Gas Treatment GTS 105 Gas (1E-07 to 1E-01 uCi/cc) 1.02E-07 1 '2E-07 1.02E-07 1.02E-07 1.02E-07 1 ~ OOE-06 Offgas OFG 13A Gas (1E-03 to 1E+02 uCi/cc) 1.00E-03 1.00E-03 1.00E-03 1.00E-03 1.00E-03 1.00E-03 OFG 13B Gas (1E-03 to 1E+02 uCi/cc) 1.00E-03 1 'OE-03 1.00E-03 1 ~ OOE-03 1.00E-03 1.00E-03 "The ranges shown indicate possible detection limits. If a minimm or maximums value is shown in this table, it indicates what the instruaent would read in "real-life" and not necessarily the true activity in the process stream.

9.2-17

Nine Hile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 TABLE 9.2.3 Process Radiation Honitors 04:30 04 45 05:00 05:15 05:30 05 45 Monitors~ (11:00) (11:15) (11:30) (11:45) (12:00) (12:15)

Orwell Containment Atmosphere CHS 10A Gas (lE-07 to 1E-01 uCi/cc) 1.00E-07 1.00E-07 1.00E-07 1.00E.07 1.00E-07 1.00E-07 Partic. (1E-'11 to 1E-05 uCi/cc) 1.00E-11 1.00E-11 1.00E-11 1.00E-11 1.00E-11 1.00E-11 CHS 10B Gas (1E-07 to 1E-01 uCi/cc) 1.00E-07 1.00E-07 1.00E.07 1.00E-07 1.00E-07 1.00E-07 Partic. (1E-11 to 1E-05 uCi/cc) 1.00E-11 1.00E-11 1.00E-11 1.00E-11 1.00E-11 1.00E-11 Reactor Building Vent Effluent Honitor HVR 14A Gas (1E-07 to 1E-01 uCi/cc) 1.00E-07 1.00E-07 1.00E-07 1.00E-07 1.00E-07 1.00E-07 Partic. (1E.11 to 1E-05 uCi/cc) 1.00E-11 1.00E-11 1 'OE-11 1.00E-11 1 ~ OOE-11 1 ~ OOE-11 HVR 14B Gas (1E-07 to 1E-01 uCi/cc) 1.15E-07 1.15E-07 1.15E-07 1.15E-07 1.15E-07 1 '5E-07 HVR 32A Gas (1E-07 to 1E-01 uCi/cc) 2.77E-07 2.77E-07 2.77E-07 2.77E-07 2.77E-07 2.77E-07 Partic. (1E-11 to 1E-05 uCi/cc) 1.23E-11 1.23E-11 1.23E-11 1.23E-11 1.23E-11 1.23E-11 HVR 328 Gas (1E-07 to 1E-01 uCi/cc) 1.18E-07 1.18E-07 1.18E-07 1.18E-07 1.18E-07 1.18E-07 Hain Control Room Air Intake HVC 18A Gas (1E-07 to 1E-01 uCi/cc) 4.38E-07 4.38E-07 4.38E-07 4.38E-07 4.38E-07 4.38E-07 HVC 18B Gas (1E-07 to 1E-01 uCi/cc) 2.47E-07 2.47E-07 2.47E-07 2.47E-07 2.47E-07 2.47E-07 HVC 18C Gas (1E-07 to 1E-01 uCi/cc) 3.58E-07 3.58E-07 3.58E-07 3.58E-07 3.58E-07 3.58E-07 HVC 180 Gas (lE-07 to 1E-01 uCi/cc) 2.17E-07 2.17E-07 2 '7E-07 2.17E-07 2.17E-07 2.17E-07 RHR Heat Exchanger Service Water SWP 23A Liquid (1E-07 to 1E-01 uCi/cc) 1.29E-06 1.29E-06 1.29E-06 1.29E-06 1.29E-06 1.29E-06 SWP 238 Liquid (1E-07 to 1E.01 uCi/cc) 1.35E-06 1.35E-06 1.35E-06 1.35E-06 1.35E-06 1.35E-06 Hain Steam Line MSS 46A (1E+00 to 1E+06 mR/hr) 5.07E+02 5.12E+02 5.16E+02 5 '0E+02 5.25E+02 5.29E+02 MSS 46B (1E+00 to 1E+06 mR/hr) 5.07E+02 5.12E+02 5.16E+02 5.20E+02 5.25E+02 5.29E+02 HSS 46C (1E+00 to 1E+06 mR/hr) 5 '3E+02 5 '8E+02 5.22Ei02 5.26E+02 5.31E+02 5.35Ei02 MSS 46D (1E+00 to 1E+06 mR/hr) 4.84E+02 4.88E+02 4.92E+02 4.96E+02 5.DOE+02 5.04E+02 Service Water Discharge I SW 146A Liquid (1E-07 to 1E-01 uCi/cc) 1.55E-06 1.55E-06 1.55E-06 1.55E-06 1.55E-06 1 '5E-06 SW 1468 Liquid (lE-07 to 1E-01 uCi/cc) 1.61E-06 1.61E-06 1.61E-06 1.61E-06 1.61E-06 1.61E-06

• The ranges shown indicate possible detection limits. If a miniaun or maxiaxrn value is shorn in this table, it indicates shat the instrunent would read in "real-life" and not necessarily the true activity in the process stream.

9.2-18

Nine Hile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 TABLE 9.2.3 Process Radiation Honitors 04:30 04 45 05:00 05:15 05:30 05 45 Honitors>> (11:00) (11:15) (11:30) (11:45) (12:00) (12:15)

Solid Radwaste El. 279< South MSS 207 (1E-01 to 1E+04 uCi/cc) 1.00E-01 1.00E-01 1.00E-01 1.00E-01 1.00E-01 1.00E-01 MSS 208 (1E-01 to 1E+04 uCi/cc) 1.00E-01 1.00E-01 1 ~ OOE-01 1.00E-01 1.00E-01 I.OOE-01 Fuel Pool Cooling Pump Discharge SFC 142 Liquid (1E-07 to 1E-01 uCi/cc) 1.24E-07 1.24E-07 1.24E-07 1.24E-07 1.24E-07 1.24E-07 Reactor Building Closed Loop Cooling Mater CCP 115 Liquid (1E-07 to 1E-01 uCi/cc) 4.46E-07 4.46E-07 4.46E-07 4.46E-07 4.46E-07 4.46E-07 CCP 131 Liquid (1E-07 to 1E-01 uCi/cc) 1.07E-06 1.07E-06 1.07E-06 1 '7E-06 1.07E-06 1.07E-06 Turbine Building Closed Loop Cooling Mater CCS 152 Liquid (1E-07 to 1E-01 uCi/cc) 5.85E-07 5.85E-07 5.85E-07 5.85E-07 5.85E-07 5.85E-07 Liquid Radwaste LMS 206 Liquid (1E-07 to 1E-01 uCi/cc) 8.56E-06 8.56E-06 8.56E-06 8.56E-06 8.56E-06 8.56E-06 Cooling Tower Blowdown CMS 157 Liquid (1E-07 to 1E-01 uCi/cc) 1.78E-06 1.78E-06 1.78E-06 1.78E-06 1.78E-06 1.78E-06 Standby Gas Treatment GTS 105 Gas (1E-07 to 1E-01 uCi/cc) 1.78E-05 1.21E-04 1.00E-01 1.00E-01 1.00E-01 1.00E-01 Offgas OFG 13A Gas (1E-03 to 1E+02 uCi/cc) 1.00E-03 1.00E-03 1 'OE-03 1.00E-03 1.00E-03 1.00E-03 OFG 138 Gas (1E-03 to 1E+02 uCi/cc) 1.00E-03 1.00E-03 1.00E-03 1 'OE-03 1.00E-03 1.00E-03

• The ranges shown indicate possible detection limits. If a minimm or maximm value is shown in this table, it indicates what the Instrunent would read in "real-life" and not necessarily the true activity in the process stream.

9.2-19

Hine Hile Point Unit 2 1990 Annual Exercise Scenario Ho. 19, Rev. 1e TABLE 9.2.3 Process Radiation Honitors 06:00 06:15 06:30 06:45 07:00 Monitors* (12:30) (12:45) (13:00) (13:15) (13:30)

Drywell Containment Atmosphere CHS 10A Gas (1E-07 to 1E-01 uCi/cc) 1.00E-07 1.00E-01 1.00E-01 1.00E-01 1.00E-01 Partic. (1E-11 to 1E-05 uCi/cc) 1.00E-11 1.00E.05(A) 1.00E-05(A) 1.00E-05(A) 1.00E-05(A)

CHS 108 Gas (1E-07 to 1E-01 uCi/cc) 1.00E-07 1.00E-01 1.00E-01 1.00E-01 1.00E.01 Partic. (1E-11 to 1E-05 uCi/cc) 1.00E-11 1.00E-05(A) 1.00E-OS(A) 1.00E 05(A) 1.00E-05(A)

Reactor Building Vent Effluent Honitor HVR 14A Gas (1E-07 to 1E-01 uCi/cc) 1.00E-07 1.00E-07 1.00E-07 1.00E-07 1.00E-07 Partic. (1E-11 to 1E-05 uCi/cc) 1.00E-11 1.00E-11 1.00E-11 1.00E-11 1.00E-11 HVR 148 Gas (1E-07 to 1E-01 uCi/cc) 1.15E-OT 1.15E-07 1.15E-07 1.15E-07 1.15E-07 HVR 32A Gas (1E-07 to 1E-01 uCi/cc) 2.7TE-07 2.77E-07 2.77E-07 2.77E-07 2.77E-07 Partic. (1E-11 to 1E-05 uCi/cc) 1.23E-11 1.23E-11 1.23E-11 1.23E-11 1.23E-11 HVR 328 Gas (1E-07 to 1E-01 uCi/cc) 1.18E-07 1.18E-OT 1.18E-OT 1.18E-07 1.18E-07 Hain Control Room Air Intake HVC 18A Gas (1E-07 to 1E-01 uCi/cc) 4.38E-OT 4.38E-07 4.38E-07 4.38E-OT 4.38E-07 HVC 188 Gas (1E-07 to 1E-01 uCi/cc) 2.47E-07 2.47E-07 2.47E-07 2.47E-07 2.47E-07 HVC 18C Gas (1E-07 to 1E-01 uCi/cc) 3.58E-07 3.58E.OT 3.58E-OT 3.58E-07 3.58E-OT HVC 18D Gas (1E-07 to 1E-01 uCi/cc) 2.17E-07 2.17E-07 2.17E-DT 2.17E-OT 2.17E-OT RHR Heat Exchanger Service Mater SMP 23A Liquid (1E-07 to 1E-01 uCi/cc) 1.29E-06 1.29E-06 1.29E-06 1.29E-06 1.29E-06 S'MP 238 Liquid (1E-07 to 1E-01 uCi/cc) 1.35E-06 1.35E-06 1.35E-06 1.35E-06 1.35E-06 Hain Steam Line HSS 46A (1E+00 to 1E+06 mR/hr) 5.33E+02 5.38E+02 5.42E+02 5.46E+02 5.50E+02 HSS 46B (1E+00 to 1E+06 mR/hr) 5.33E+02 5.38E+02 5.42E+02 5.46E+02 5.50E+02 HSS 46C (1E+00 to 1E+06 mR/hr) 5.39E+02 5.44E+02 5.48E+02 5.52E+02 5.57E+02 HSS 46D (1E+00 to 1E+06 mR/hr) 5.08E+02 5.13E+02 5.17E+02 5.21E+02 5.25E<02 Service 'Mater Discharge SM 146A Liquid (1E-07 to 1E-01 uCi/cc) 1.55E.06 1.55E-06 1.55E-06 1.55E-06 1.55E-06 S'M 1468 Liquid (lE-07 to 1E-01 uCi/cc) 1.61E-06 1.61E-06 1.61E-06 1.61E-06 1.61E-06

• The ranges shown indicate possible detection limits. If a miniraxn or maximun value is shown in this table, it indicates what the instrwent would read in "real-life" and not necessarily the true activity in the process stream.

(A) - Denotes an alarming monitor 9.2-20

0 Nine 0

Hile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 TABLE 9.2.3 Process Radiation Honitors 06:00 06:15 06:30 06:45 07 00 Honi tors>> (12:30) (12:45) (13:00) (13:15) (13:30)

Solid Radwaste El. 279~ South WSS 207 (1E-01 to 1E+04 uCi/cc) 1.00E-01 1.00E-01 1.00E-01 1.00E-01 1.00E-01 WSS 208 (1E-01 to 1E+04 uCi/cc) 1.00E-01 1.00E-01 1.00E-01 1.00E-01 1.00E-01 Fuel Pool Cooling Pump Discharge SFC 142 Liquid (1E-07 to 1E-01 uCi/cc) 1.24E-07 1.24E-07 1.24E-O? 1.24E-07 1.24E-07 Reactor Building Closed Loop Cooling Water CCP 115 Liquid (1E-07 to 1E-01 uCi/cc) 4.46E-07 4.46E-07 4.46E-07 4.46E-07 4.46E.07 CCP 131 Liquid (1E.07 to 1E-01 uCi/cc> 1.07E-06 1.07E-06 1.07E-06 1.07E-06 1.07E-06 Turbine Building Closed Loop Cooling Water CCS 152 Liquid (1E-O? to 1E-01 uCi/cc) 5.85E-07 5.85E-O? 5.85E-07 5.85E-O? 5.85E-07 Liquid Radwaste LWS 206 Liquid (1E-07 to 1E-01 uCi/cc) 8.56E-06 8.56E-06 8.56E-06 8.56E-06 8.56E-06 Cooling Tower Blowdown CWS 157 Liquid (1E-07 to 1E-01 uCi/cc) 1.78E-06 1.78E-06 1.78E-06 1.78E-06 1.78E-06 Standby Gas Treatment GTS 105 Gas (1E-07 to 1E-01 uCi/cc) 1.00E-01 1.00E-01 1.00E-01 1.00E-01 1.00E-01 Offgas OFG 13A Gas (1E.03 to 1E+02 uCi/cc) 1.00E-03 1.00E-03 1.00E-03 1.00E-03 1.00E-03 OFG 138 Gas (1E-03 to 1E+02 uCi/cc> 1.00E-03 1.00E-03 1.00E-03 1.00E-03 1.00E-03

• The ranges shown indicate possible detection limits. lf a mininun or maximm value is shown in this table, it indicates what the instrunent would read in "real-life" and not necessarily the true activity in the process stream.

9.2-2'I

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 9.2.4 Monitor Information 2 Da s Later

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 Table 9.2.4 2 Days Later October 4, 1990 Process Radiation Monitors Monitors Drywell Containment Atmosphere CMS 10A Gas (1E-07 to 1E-01 uCi/cc) 1.00E-07 Partic. (1E-11 to 1E-05 uCi/cc) 1.00E-11 CMS 10B Gas (1E-07 to 1E-01 uCi/cc) 1.00E-07 Partic. (1E-11 to 1E-05 uCi/cc) 1.00E-11 Reactor Building Vent Effluent Monitor HVR 14A Gas (1E-07 to 1E-01 uCi/cc) 1.00E-07 Partic. (1E-11 to 1E-05 uCi/cc) 1.00E-11 HVR 14B Gas (1E-07 to 1E-01 uCi/cc) 1.15E-07 HVR 32A Gas - (1E-07 to 1E-01 uCi/cc) 2.77E-07 Partic. (1E-11 to 1E-05 uCi/cc) 1.23E-ll HVR 32B Gas (lE-07 to lE-Ol uCi/cc) 1.48E-07 Main Control Room Air Intake HVC 18A Gas (1E-07 to 1E-Ol uCi/cc) 4.38E-07 HVC 18B Gas (1E-07 to 1E-Ol uCi/cc) 2.47E-07 HVC 18C Gas (lE-07 to lE-01 uCi/cc) 3.58E-07 HVC 18D Gas (lE-07 to lE-01 uCi/cc) 2.17E-07 RHR Heat Exchanger Service Water SWP 23A Liquid (1E-07 to 1E-01 uCi/cc) 1.29E-06 SWP 23B Liquid (1E-07 to 1E-Ol uCi/cc) 1.35E-06 Service Water Discharge SW 146A Liquid (lE-07 to 1E-01 uCi/cc) 1.55E-06 SW 146B Liquid (1E-07 to 1E-01 uCi/cc) 1.61E-06 9.2-22

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 Table 9 2. 4 2 Days Later October 4, 1990 Process Radiation Monitors Monitors Solid Radwaste El. 279'outh WSS 207 (lE-Ol to lE+04 uCi/cc) 1.00E-01 WSS 208 (1E-Ol to lE+04 uCi/cc) 1.00E-01 Fuel Pool Cooling Pump Discharge SFC 142 Liquid (1E-07 to lE-01 uCi/cc) 1.24E-07 Reactor Building Closed Loop Cooling Water CCP 115 Liquid (1E-07 to 1E-01 uCi/cc) 4.46E-07 CCP 131 Liquid (1E-07 to 1E-01 uCi/cc) 1.07E-06 Turbine Building Closed Loop Cooling Water CCS 152 Liquid (1E-07 to 1E-01 uCi/cc) 5.85E-07 Liquid Radwaste LWS 206 Liquid (1E-07 to 1E-Ol uCi/cc) 8.56E-06 Cooling Tower Blowdown CWS 157 Liquid (1E-07 to 1E-Ol uCi/cc) 1.78E-06 Standby Gas Treatment GTS 105 Gas (1E-07 to 1E-Ol uCi/cc) 1.00E-07 Offgas OFG 13A Gas (1E-03 to 1E+02 uCi/cc) 1.00E-03 OFG 13B Gas (1E-03 to 1E+02 uCi/cc) 1 OOE-03

~

9.2-23

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 Table 9.2 4 2 Days Later October 4, 1990 Area Radiation Monitors Monitor Monitor Name Location+ Name Location+

DW 261'W RMS-129 CB 306'B RMS-1B 261'W 3.36E+07(A) RHS-130 261'W 3.98E-02 RMS-1C 261'W 3.36E+07(A) RMS-132 265'W 4.36E-02 RMS-1D 261'X 3.36E+07(A) RMS-133 279'W 1.57E-01 RMS-2A 250'MS-1A 9.67E-01 RMS-134 3.85E-02 353'.36E+07(A) 261'B 215'X RMS-2B 215'B 1.95E-01 RMS-135 250'B 1.03E-01 RMS-3A 250'B 1.00E+01 RMS-136 288'B 8.81E-02 RMS -3B 250'B 1.00E+01 RMS-137 261'B 6.97E-02 RMS-3C 1.29E+01 RMS-138 250'X 1.50E-01 RMS-101 RX 1.50E+02 RMS-139 1.14E+05 261'.07E-02 215'X 175'X RMS-102 175'X 9.50E-02 RMS-140 353'B 6.91E-02 RMS-103 175'X 4.99E-01 RMS-141 250'W 2.01E-01 RMS-104 175'X 8.39E-02 RMS-142 279'X 5.12E-02 RMS-105 240'X 1.20E+00 RMS-143 261'X 1.67E-01 RMS-106 2.03E-01 RHS-144 261'X 1.95E-01 RMS-108 RX 261'X 1.06E-01 RMS-145 240'W 5.76E-01 5.67E-01 289'MS

-109 RX 316 6.23E-02 RMS-146 279'W RX 'HS-111 4.72E-02 RMS-147 291'W 1.00E+01 RMS-112 353'X 5.57E-02 RMS-148 279'X 4.12E-01 RMS-113 353'X 6.00E-02 RMS-149 328'B

'.00E+Ol RMS-114 353'B 9.31E-02 RMS-150 250'B 1.00E+01 RMS-116 250'B 3.97E-01 RHS-151 306'W 1.00E+01 RMS-117 250'B 1.17E-01 RMS-152 240'W 7.88E-02 RMS-118 261'B 8.85E-02 RMS-153 240'B 2.16E-01 RMS-119 250'B 1.30E+01 RMS-154 250'B 9.90E-02 RMS-120 277'B 3.52E-01 RMS-190 288'B 5.77E-02 RMS-121 279'B 5.69E-02 RMS-191 306'B 2.55E-01 RMS-123 306'W 4.00E+00 RMS-192 306'S 5.07E-01 RMS-125 6.36E-01 RHS-193 1.05E-01 261'eading (mR/hr)

• RX Reactor Building; TB Turbine Building; RW Rad Waste Building; CB Control Building; DW Drywell; MS - Main Stack (A) Denotes an alarming monitor. ~

9.2-24

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 Table 9.2.4 2 Days Later October 4, 1990 Continuous Air Monitors Radwaste Equipment Exhaust Vent HVW 195 Gas (1E-07 to 1E-01 uCi/cc) 4.91E-07 Partic. (1E-17 to lE-05 uCi/cc) 2.36E-12 Radwaste Tank Vent HVW 196 Gas (1E-07 to 1E-01 uCi/cc) 4.10E-07 Partic. (1E-11 to 1E-05 uCi/cc) 3.17E-12 Radwaste Building Vent HVW 197 Gas (lE-07 to 1E-Ol uCi/cc) 1.00E-07 Partic. (1E-11 to lE-05 uCi/cc) 1.00E-11 R.B. N. Aux Bay El. 196'; RHR Heat Exch.

HVR 237 Gas (1E-07 to 1E-01 uCi/cc) 9.32E-04(A)

Partic. (1E-11 to 1E-05 uCi/cc) 9.76E-10 R.B. S. Aux Bay El. 196'; RHR Heat Exch.

HVR 238 Gas (1E-07 to 1E-01 uCi/cc) 9.32E-04(A)

Partic. (1E-ll to lE-05 uCi/cc) 9.76E-10 Radwaste Building El. 279'; Swgr Room HVW 199 Gas (1E-07 to 1E-01 uCi/cc) 3.80E-07 Partic. (1E-11 to lE-05 uCi/cc) 1.10E-11 Turbine Building Vent HVT 206 Gas (lE-07 to lE-01 uCi/cc) 2.01E-07 Partic. (1E-11 to 1E-05 uCi/cc) 8.88E-11 Reactor Building Recirculation HVR 229 Gas (1E-07 to lE-01 uCi/cc) 9 '2E-04(A)

Partic. (1E-11 to lE-05 uCi/cc) 9.76E-10 TCS CAM (CPM) 50 EOF CAM (CPM) 50 9.2-25

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 10.0 RADIOLOGICAL AND METEOROLOGICAL DATA

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 10.0 RADIOLOGICAL AND METEOROLOGICAL:INFORMATION TABLE OF CONTENTS Section Title ~Pa e 10.1 Meteorological Data 10.1.1 Meteorological Tower Data - Hourly Summary 10.1-1 10.1.2 Meteorological Tower Data - 15 Minute Summary 10.1-2 10.1.3 Forecast Information 10.1-6 10.2 Radiological Sample Information 10.2.1 Reactor Water Sample Analysis 10 '-1 10.2.2 Drywell Air Sample Analysis 10.2-4 10.2.3 Suppression Pool Water Sample Analysis 10.2-7 10.2.4 Suppression Pool Air Sample Analysis 10.2-10 10.2.5 Reactor Building Air Sample Analysis 10.2-13 10.2.6 Stack Sample Analysis 10.2-"16 10.2.7 Plant Vent Sample Analysis 10.2-19 10.2.8 Turbine Building Air Sample Analysis 10.2-22 10.2.9 Radwaste Building Air Sample Analysis 10.2-25 10.2.10 Sample Information - 2 Days Later 10.2-28 10.3 In-plant Radiological Information 10.3.1 Reactor Building EL. 175' 0" 10.3-1 10.3.2 Reactor Building EL. 196' 0" 10.3-3 10.3.3 Reactor Building EL. 215' 0" 10.3-5 10.3.4 Reactor Building EL. 240' 0" 10.3-7 10.3.5 Reactor Building EL. 261' 0" 10.3-9 10.3.6 Reactor Building EL. 289' 0" 10.3-11 10.3.7 Reactor Building EL. 306' 6" 10.3-13 10.3.8 Reactor Building EL. 328' 10" 10.3-15 10.3.9 Reactor Building EL. 353' 6" 10.3-17 10.4 Radiological Release Information 10.4.1 Release Rate Data Summary 10.4-1 10.4.2 Onsite Radiological Survey/Sample Data. 10.4-3 10.4.3 Offsite Radiological Survey/Sample Data 10.4-12

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 10.1 Meteorolo ical Information

e Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 10.1 METEOROLOGICAL DATA TABLE OF CONTENTS Section Title ~Pa e 10.1.1 Meteorological Data - Hourly Summary 10.1-1 10.1.2 Meteorological Data - 15 Minute Summary 10.1-2 10.1.3 Meteorological Forecast 10.1-6

Nine Mile Point Unit 1990 Annual Exercise Scenario No. 19, Rev. 1 Table 10.1.1 Meteorolo ical Tower Data - Houri Avera e Suer MAIN TOWER PARAMETERS NINE MILE POINT DATE WIHD SPEED WIND DIRECTION SIGMA THETA & STABILITY TEMP 8 DEW PT DELTA TEMP 8 STAB PRESSURE PRECIP TIME AVG (EST)

(10/02/90) WS 30'S 100'S 200'PH WD 30'D 100'D 200'IG 30'S SIG 100'S SIG 200'S TMP 30'PT 30'EG DT 100'S DT 200'S BARD PRECP MPH MPH OEG OEG DEG DEG OEG DEG DEG DEG F DEG F IN MG IN 06:00 8 12 13 309 314 309 7.1F 1.3G 1.5G 58 42 -0.2E -0.8D 29.90 0 F 00 07:00 4 9 10 320 322 316 11.5D 1.7G 1.5G 58 43 -0.2D -0.9D 29.89 0.00 08:00 6 11 11 312 316 310 7.90 1.2G 1.1G 58 45 -0.3D -0.9D 29.91 0.00 09:00 3 7 8 353 337 330 12.7C 2.3F 1.3G 58 41 -0.3D -0.9D 29.90 0.00 10:00 5 10 10 315 324 318 9.7C 1 ~ 5G 1.0G 58 40 -0.6D -1.3D 29.90 0.00 11:00 8 17 17 319 327 320 10.30 1.4G 'I.OG 57 38 -0.8A -1.5C 29.91 0.00 12:00 5 12 13 328 330 322 17.98 1.9G 1.3G 56 39 -2.4A -2.9A 29.91 0.00 13:00 9 11 12 294 298 293 3.9E 1.5G 1.4G 56 41 -1.4A -2.6A 29.91 0.00 14:00 11 12 12 290 293 285 2.8F 1.5G 1.3G 56 41 -0.9A -2.0A 29.91 0.00 15:00 11 12 13 281 284 277 2.3F 1.7G 'l.6G 57 40 0.3D -1.5C 29.92 0.00 16:00 10 10 11 290 294 287 2.3F 1.6G 1.6G 57 38 0.3D -1.30 29.93 0.00 17:00 9 9 10 295 299 292 2.6F 1.9G 1.8G 57 35 -0.78 -1.2D 29.94 0 F 00 18:00 13 14 14 297 301 294 2.4F 1.6G 1.5G 57 36 -0.5D -1.0D 29.96 0.00 19:00 13 13 14 294 298 290 2.0G 1.3G 'I. 1G 57 37 -0.4D -1.00 29.98 0.00 20:00 11 11 12 295 297 292 2.1G 1.5G 1.3G 57 39 -0.40 -0.9D 29.98 0.00 JAF TOWER PARAMETERS INLAND TOWER PARAMETERS DATE SPEED OIR SIGMA SPEED DIR SIGMA F S TIME AVG (EST) 10/02/90 WS 90'PM WD 90'EG SIG 90' WS WD SIG 30' 30'PH 30'EG

~ OEG DEG 06:00 12 310 1.7G 312 9.20 07 00 9 317 1.6G 328 12.8C 08:00 10 311 1.5G 327 8;60 09:00 8 332 1.8G 335 9.10 10:00 9 322 1.5G 331 11 ~ 7D 11:00 16 323 1.5G 311 8.2D 12:00 12 327 1.6G 333 14.8C 13:00 12 297 2.4F 317 8.6D 14:00 13 289 2.1G 294 6.5E 15:00 'l2 284 2.5F 299 7.0E 16:00 9 294 5.6E 301 6.0E 17:00 9 299 3.6F 300 5.7E 18:00 13 296 3.4F 288 5.9E 19:00 14 294 3.2F 293 5.4E 20:00 11 294 5.7E 295 3.4E 10.1-1

Nine Hile Point Uni 2 1990 Annual Exercise Scenario No. 19, Rev. 1 Table 10.1.2A Heteorolo ical Tower Data - 15 Hinute Avera e Swrnar HAIN TONER PARAMETERS NINE HILE POINT DATE HIND SPEED HIND DIRECTION SIGHA THETA 8 STABILITY TEHP & DEII PT DELTA TEHP EI STAB PRESSURE PRECIP TIHE AVG (EST)

(10/02/90) MS 30'S 100'8 200'PH

'IS 30'Q 100'S 200'IG 30'S SIG 100'S SIG 200'S TMP 30'PT 30'EG DT 100'S DT 200'S BARO PRECP MPH HPH DEG DEG DEG DEG DEG DEG - DEG DEG F DEG F IN MG IN 06:00 12 13 309 314 309 7.1E 1.3G 1.5G 58 42 -0.2E -0.8D 29.90 0.00 06:15 11 12 311 316 311 8.3E 1.4G 1.4G 58 42 -0.2E -0.9D 29.90 0.00 06:30 11 11 315 318 312 9.6E 1.5G 1.5G 58 42 -0.2E -0.7D 29.90 0.00 06:45 10 10 318 320 314 10.4E 1.6G 1.6G 58 43 -0.2E -0.8D 29.89 0.00 07:00 9 10 320 322 316 11.50 1.7G 1.5G 58 43 -0.20 -0.9D 29.89 0.00 07:15 9 10 313 319 315 10.90 1.6G 1.4G 58 43 -0.2D -0.80 29.89 0.00 07:30 10 11 316 318 313 9.3D 1.4G 1.3G 58 44 -0.2D -0.7D 29.90 0.00 07:45 10 10 314 317 311 8.60 1.3G 1.2G 58 45 -0.2D -0.80 29.90 0.00 08:00 11 11 312 316 310 7.90 1.2G 1.1G 58 45 .0.30 -0.90 29.91 0.00 08:15 10 10 321 320 315 8.70 1.4G 1.2G 58 44 -0.30 -0.1D 29.91 0.00 08:30 9 9 333 325 320 9.6D 1.7G 1.3G 58 43 -0.3D -0,9D 29.91 0.00 08:45 8 8 345 330 325 11.7D 2.0G 1.2G 58 42 -0.3D -0.1D 29.91 0.00 09:00 7 8 353 337 330 12.7C 2.3G 1.3F 58 41 -0.3D -0.9D 29.90 0 F 00 09:15 8 8 341 332 328 11.8C 2.1G 1.2F 58 41 -0.3D -0 ~ 1D 29.90 0.00 09:30 8 8 330 329 325 10.9C 1.9G 1.3F 58 40 -0.4D -1.1D 29.90 0.00 09:45 9 '9 324 327 321 10.3C 1.7G 1 ~ 1F 58 40 -0.5D -1.2D 29.90 0.00 10:00 10 10 315 324 318 9.7D 1.5G 1.0G 58 40 -0 '0 -1.3D 29.90 0.00 10:15 12 12 316 325 319 9.9D 1.4G 1.1G 58 39 -0.5D -1 ~ 20 29.90 0.00 10:30 14 14 317 326 318 10.00 1 ~ 5G 'I.OG 58 39 -0.6D -1.30 29.90 0.00 10:45 16 15 318 326 319 10.2D 1.5G 1.1G 57 38 -0.7D -1.4D 29.91 0.00 11:00 17 'l7 319 327 320 10.38 1.4G 1.0G 57 38 -0.8A -1.5C 29.91 0.00 11:15 16 16 321 328 321 11'.88 1.5G 1.1G 57 38 -1.0A -1.8C 29.91 0.00 11:30 14 14 324 328 322 13.68 1.6G 1.2G 57 39 -1.4A -2.0C 29.91 0.00 11:45 13 13 326 329 321 15 ~ 58 1.8G 'I.1G 57 39 -1.9A -2.5C 29.91 0.00 12:00 12 13 328 330 322 17.98 1.9G 1.3G 56 39 -2.4A -2.9A ~ 29.91 0.00 12:15 12 12 322 325 316 14 ~ 28 1.8G 1.4G 56 39 -2.1A -2.8A 29.91 0.00 12:30 11 11 314 318 310 9.68 1.7G 1.3G 56 40 -1.9A '2.9A 29.91 0.00 12:45 12 12 304 309 304 5.98 1.6G 1.2G 56 40 -'1.7A -2.7A 29.91 0.00 13:00 11 12 294 298 293 3.9E 1.5G 1.4G 56 41 -1.4A -2.6A 29.91 0.00 10.1-2

Nine Hile Point 2 1990 Annual Exercise Scenario No. 19, Rev. 1 Table 10.1.2A Heteorolo ical Tower Data - 15 Hinute Avera e Sugar HAIN TONER PARAMETERS NINE HILE POINT DATE NND SPEED NIND DIRECTION SIGMA THETA 8 STABILITY TEHP & DEW PT DELTA TEHP & STAB PRESSURE PRECIP TIME AVG (EST)

(10/02/90) MS 30'PH IIS 100'S 200'PM lS 30'ID 100'S 200'IG 30'S SIG 100'S SIG 200'S TMP 30'PT 30'EG DT 100'S DT 200'S BARO PRECP HPH DEG DEG DEG DEG DEG DEG DEG DEG F DEG F IN HG IN 13:15 10 12 293 297 290 3.7E 1.4G 1.3G 56 41 .1.5A -2.4A 29.91 0.00 13:30 9 11 12 292 295 288 3.4E 1.30 1.2G 56 41 -1.6A -2.3A 29.91 0.00 13:45 10 11 11 291 294 287 3.1E 1.4G 1.3G 57 41 -1.8A -2.2A 29.91 0.00 14:00 11 12 12 290 293 285 2.8F 1.5G 1.3G 57 41 -0.9A -2.0A 29.91 0.00 14:15 11 11 11 288 291 283 2.7F 1.6G 1.4G 57 41 -0.7A -1.9A 29.91 0.00 14:30 10 10 10 285 288 280 2.5F 1.7G 1.5G 57 40 -0.6A -1.8A 29.91 0.00 14:45 11 11 11 283 285 278 2.4F 1.6G 1.4G 57 40 -0.4A -1.6A 29.91 0.00 15:00 11 12 13 281 284 277 2.3F 1.7G 1.6G 57 40 -0.3D -1.5C 29.92 0.00 15:15 10 12 12 283 287 280 2. 1F 1.5G 1.5G 57 39 -0.3D -1.6C 29.92 0.00 15:30 10 11 11 284 289 282 2.2F 1.6G 1.4G 57 39 -0.3D -1.5C 29.92 0.00 15:45 11 11 10 287 291 285 2.1F 1.7G 1.5G 57 38 -0.3D -'1.4C 29.92 0.00 16:00 10 10 11 290 294 287 2.3F 1.6G 1.6G 57 38 -0.3D -1.3D 29.93 0.00 16:15 10 9 10 292 296 289 2.4F 1.7G 1.7G 57 38 -0.4D -1.4D 29.93 0.00 16:30 9 10 9 293 298 290 2.3F 1.8G 1.8G 57 37 -0.5D -1.5D 29.93 0.00 16:45 10 9 10 294 297 291 2.5F 1.7G 1.7G 57 36 -0.60 -1.3D 29.93 0.00 17:00 9 9 10 295 299 292 2.6F 1.9G 1.8G 57 35 -0.78 -1.2D 29.94 0.00 17:15 10 10 295 300 293 2.5F 1.8G 1.7G 57 35 -0.6B -1.3D 29.94 0.00 17:30 11 11 12 296 301 294 2.4F 1.9G 1.8G 57 35 -0.5B -1.2D 29.94 0.00 17:45 12 12 13 296 300 293 2.3F 1.7G 1.6G 57 36 -0.48 -1.1D 29.95 0.00 18:00 13 14 14 297 301 294 2.4F 1.6F 1.5G 57 36 -0.5D -1.0D 29.96 0.00

'18:15 12 12 '13 294 300 293 2.3F 1.4G 1.4G 57 36 -0.5D -1.1D 29.96 0.00 18:30 13 13 12 295 299 292 2.2F 1 ~ 5G 1.3G 57 37 -0.50 -'1.2D 29.97 0.00 18:45 12 12 13 295 298 291 2.1F 1.4G 1.2G 57 37 -0.5D -1.1D 29.97 0.00 19:00 13 13 14 294 298 290 2.0G 1.3G 1.1G 57 37 -0.4D -1.0D 29.98 0.00 19:15 12 12 13 294 297 291 2.1G 1.2G 1.2G 57 38 -0.4D -0.9D 29.98 0.00 19:30 11 11 12 295 297 290 2.2G 1.3G 1.3G 57 38 -0.40 -1.1D 29.98 0.00 19:45 12 12 13 295 298 291 2. 1G 1.4G 1.2G 57 39 -0.4D -1.0D 29.98 0.00 20:00 11 11 12 295 297 292 2.1G 1.5G 1.3G 57 39 -0.4D -0.90 29.98 0.00 10.1-3

Nine Mile Point Um 2 1990 Annual Exercise Scenario No. 19, Rev. 1 Table 10.1.28 Heteorolo ical Tower Data - 15 Hinute Avera e Swmar JAF TOWER PARAMETERS INLAND TOWER PARAHETERS DATE SPEED DIR SIGMA 8 S SPEED DIR SIGHA II S TIHE AVG (EST) 10/02/90 IIS 90'PH WD 90'IG 90' WS 30'D 30'IG 30'PH DEG DEG DEG DEG 06:00 12 310 1.76 5 312 9.20 06:15 11 312 1.6G 4 316 9.8D 06:30 10 314 1.7G 5 320 10.2D 06:45 10 316 1.6G 4 324 11.5D 07:00 9 317 1.6G 4 328 12.8C 07:15 8 315 1.5G 3 326 11.5C 07:30 8 314 1.66 4 327 10.4C 07:45 9 312 1.56 5 328 9.7C 08:00 10 311 1.56 3 327 8.6D 08:15 9 319 1.66 2 329 8.7D 08:30 10 325 1.7G 1 330 8.80 08:45 9 330 1.8G 2 332 8.9D 09:00 8 332 1.8G 3 335 9.1D 09:15 7 329 1.8G 2 334 9.9D 09:30 8 327 1.76 1 333 10.4D 09:45 8 325 '1.6G 2 332 10.9D 10:00 9 322 1.5G 3 331 11.7D 10:15 12 321 1.6G 2 326 10.9D 10:30 14 320 1 ~ 5G 4 321 9.90 10:45 15 322 1 ~ 4G 5 316 9.4D 11:00 16 323 1 ~ 5G 6 311 8.2D 11:15 15 324 1.4G 5 317 9.9D 11:30 14 325 1.5G 4 322 11 '0 11:45 13 326 1.5G 6 329 12.90 12:00 12 327 1.6G 5 333 14.8C 12:15 11 317 1.86 4 329 12.9C 12:30 10 312 2.0G 3 324 10.8C 12:45 11 307 2.2G 4 320 9.5C 10.1-4

Mine Hile Point Unit 2 1990 Annual Exercise Scenario Ho. 19, Rev. 1 Table 10.1.2B Heteorolo ical Toiler Data - 15 Hinute Avera e Signa JAF TDUER PARAMETERS IRLAND T(NER PARAHETERS DATE SPEED DIR SIGMA 8 S SPEED DIR SIGHA 8 S TIME AVG (EST) 10/02/90 iIS 90'PH IS 90'IG 90' MS 30'PH l8 30'IG 30'EG DEG DEG DEG 13:00 12 297 2.4F 5 317 8.60 13:15 11 295 2.3F 6 310- 8.1D 13:30 10 293 2.2F 5 303 7.5D 13:45 12 291 2.2F 4 299 7.5D 14 00 13 289 2 ~ 1G 5 294 6.5E 14:15 12 288 2.2G 4 295 6.6E 14:30 13 286 2.3G 3 297 6.8E 14:45 12 285 2.50 2 298 6.9E 15:00 12 284 2.5F 5 299 7.0E 15:15 10 287 3.0F 4 300 6.8E 15:30 11 289 3.5F 5 299 6.5E 15:45 10 291 4.5F 6 300 6.3E 16:00 9 294 5.6E 5 301 6.0E 16:15 8 295 5.1E 4 300 5.8E 16:30 9 297 4.6E 3 301 5.9E 16:45 8 298 4 ~ 1E 4 302 5.8E 17 00 9 3.6F 5 300 5.7E 17:15 10 298 3.5F 4 298 5.8E 17:30 11 297 3.6F 5 294 5.9E 17:45 12 296 3.5F 6 290 5.8E 18:00 13 296 3.4F 5 288 5.9E 18:15 12 295 3.5F 3 289 5.8E 18:30 13 296 3.4F 4 290 5.7E 18:45 14 295 3.3F 5 292 5.5E 19:00 14 294 3.2F 4 293 5 'E 19:15 13 295 3.6F 5 294 4.9E 19:30 12 296 4.4F 4 293 4.4E 19:45 11 295 5.2F 3 294 3.9E 20 00 11 294 5.7E 3 295 3.4F 10.1-5

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 TABLE 10.1.3 METEOROLOGICAL FORECAST Western New York Zone Forecasts National Weather Service - Buffalo, NY 06:00 EST - Tuesday, October 02, 1990 NY04 - Eastern Lake Ontario Counties NY05 - Eastern Finger Lakes Region 06:00 EST - Tuesday, October 02, 1990 Present Partly cloudy. Temperature 58 degrees. North westerly winds at 8 to 13 mph.

~To de Partly cloudy this morning. Early morning temperatures around 50 degrees. High for the day in the upper fifties.

~Wednesda Partly cloudy with seasonal temperatures. Low 52 degrees tonight. Highs Wednesday near 60.

Lake Forecast National Weather Service - Buffalo, NY 06:00 EST - Tuesday, October 02, 1990 Lake Ontario North north westerly winds 5 to 10 mph.

10.1-6

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 TABLE 10.1.3 METEOROLOGICAL FORECAST Western New York Zone Forecasts National Weather Service - Buffalo, NY 09:00 EST - Tuesday, October 02, 1990 NY04 - Eastern Lake Ontario Counties NY05 - Eastern Finger Lakes Region 09:00 EST - Tuesday, October 02, 1990 Present Partly cloudy. Temperature 58 degrees. North north westerly winds at 3 to 8 mph.

~Toda Partly cloudy this morning. Early morning temperatures around 50 degrees. High for the day in the upper fifties.

~wednesda Partly cloudy with seasonal temperatures. Low 52 degrees tonight. Highs Wednesday near 60.

Lake Forecast National Weather Service - Buffalo, NY 09:00 EST - Tuesday, October 02, 1990 Lake Ontario North north westerly winds 5 to 10 mph.

10.1-7

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 TABLE 10.1.3 METEOROLOGICAL FORECAST Western New York Zone Forecasts National Weather Service - Buffalo, NY 12:00 EST - Tuesday, October 02, 1990 NY04 - Eastern Lake Ontario Counties NY05 - Eastern Finger Lakes Region 12:00 EST - Tuesday, October 02, 1990 Present Partly cloudy. Temperature 56 degrees. North north westerly winds at 5 to 13 mph.

~Toda Partly cloudy this morning. Early morning temperatures around 50 degrees. High for the day in the upper fifties.

~Wednesda Partly cloudy with seasonal temperatures. Low 52 degrees tonight. Highs Wednesday near 60.

Lake Forecast National Weather Service - Buffalo, NY 12:00 EST - Tuesday, October 02, 1990 Lake Ontario North north westerly winds 6 to 15 mph.

10.1-8

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 TABLE 10.1.3 METEOROLOGICAL FORECAST Western New York Zone Forecasts National Weather Service - Buffalo, NY 15:00 EST - Tuesday, October 02, 1990 NY04 - Eastern Lake Ontario Counties NY05 - Eastern Finger Lakes Region 15:00 EST - Tuesday, October 02, 1990 Present Partly cloudy.

to 13 mph.

Temperature 57 degrees. Westerly winds at ll

~TO de Partly cloudy this morning. Early morning temperatures around 50 degrees. High for the day in the upper fifties.

~Wednesda Partly cloudy with seasonal temperatures. Low 52 degrees tonight. Highs Wednesday near 60.

Lake Forecast National Weather Service - Buffalo, NY 15:00 EST - Tuesday, October 02, 1990 Lake Ontario Westerly winds 12 to 14 mph.

10.1-9

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 TABLE 10.1.3 METEOROLOGICAL FORECAST Western New York Zone Forecasts National Weather Service - Buffalo, NY 18:00 EST - Tuesday, October 02, 1990 NY04 - Eastern Lake Ontario Counties NY05 - Eastern Finger Lakes Region 18:00 EST - Tuesday, October 02, 1990 Present Partly cloudy. Temperature 57 degrees. West north westerly winds at 13 to 15 mph.

~Toda Partly cloudy this morning. Early morning temperatures around 50 degrees. High for the day in the upper fifties.

W~ednesda Partly cloudy with seasonal temperatures. Low 52 degrees tonight. Highs Wednesday near 60.

Lake Forecast National Weather Service - Buffalo, NY 18:00 EST - Tuesday, October 02, 1990 Lake Ontario West north westerly winds 14 to 16 mph.

10.1-10

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 RADIOLOGICAL DATA

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 10.2 RADIOLOGICAL SAMPLE DATA TABLE OF CONTENTS Section Title ~Pa e 10.2.1 Reactor Water Sample Analysis 10.2-1 I

10.2.2 Drywell Air Sample Analysis 10.2-4 10.2.3 Suppression Pool Water Sample Analysis 10.2-7 10.2.4 Suppression Pool Air Sample Analysis 10.2-10 10.2.5 Reactor Building Air Sample Analysis 10.2-13 10.2.6 Stack Air Sample Analysis 10.2-16 10.2.7 Plant Vent Sample Analysis 10.2-19 10.2.8 Turbine Building Air Sample Analysis 10.2-22 10.2.9 Radwaste Building Air Sample Analysis 10.2-25 10.2.10 Sample Information 2 Days Later 10.2-28

1990 Annual Exercise Scenario No. 19, Rev. 1 TABLE 10.2.1-1 REACTOR IJATER SANPLE ANALYSIS TOTAL CONCENTRATION uCI/mi I 00:00 00:15 00:30 I 00:45 I 01'00 I 01:15 I 01:30 I 01:45 O2 ~ OO O2:1S I NUCLIDE (06:30) (06:45) (O7':OO) I (07:15) (07:30) I (07:45) I (08'00) I (08:15) I (08:30) I (08:45) I I-131 1.70E-03 I 1.70E-03 I 1.70E-03 I 1.70E-03 I 1.70E-03 I 1.70E-03 I 1.66E-03 I 1.66E-03 I 1.66E-03 I 1.66E-03 I

-132 3.10E-02 I 3.10E-02 I 3.10E-02 I 3 ~ 10E-02 I 3.10E-02 I 3.10E-02 I 2.81E-02 I 2.61E-02 I 2.41E-02 I 2.24E-02 I

-133 2.30E-02 I 2.30E-02 I 2.30E-02 I 2.30E-02 I 2.30E-02 I 2.30E-02 I 2.23E-02 I 2.22E-02 I 2.20E-02 I 2 '8E-02 I

-134 5.60E-02 I 5.60E-02 I 5.60E-02 I 5.60E-02 I 5.60E-02 I 5.60E-02 I 4.49E-02 I 3.68E-02 I 3.01E-02 I 2.47E-02 I

-135 2.42E-02 I 2.42E 02 I 2'42E 02 I 2 42E 02 I 2'42E 02 I 2'42E 02 I 2'31E 02 I 2 2 E 02 I 2 19E 02 I 2 14E 02 I I Iodines 1.36E-01 I 1.36E-01 I 1.36E-01 I 1.36E-01 I 1.36E-01 I 1.36E-01 I 1.20E-01 I 1.09E-01 I 9.98E-02 I 9.18E-02 I I I I I I I I I I I Kr-Bsm 1.65E-OS I 1.65E-05 I 1 65E 05 I 1 65E 0 I 1 65E 05 I 1.65E-OS I 1 54E 05 I 1 48E I 1 42E 0 I 1 E 0 I

-87 S.SOE-OS I 5.50E-05 I 5.50E-OS I 5.50E-OS I S.SOE-OS I S.SOE-OS I 4.80E-OS I 4.19E-05 I 3.65E-OS I 3.18E-OS I

-88 5 '0E-05 I 5.50E-OS I 5.50E-OS I S.SOE-OS I S.SOE-OS I S.SOE-OS I 5.17E-05 I 4.86E-OS I 4.57E-OS I 4.29E.OS I Xe-133 2.10E-OS I 2.10E-OS I 2.10E-OS I 2.10E-OS I 2.10E-OS I 2.10E-OS I 2.10E-OS I 2.10E-OS I 2.09E-OS I 2.09E-OS I 135m I 7.00E-OS I 7.00E-OS I 7.00E-OS I 7.00E-05 I 7 OOE 05 I 7 OOE-05 I 3.59E-05 I 1.84E-OS I 9.47E-06 I 4.86E-06 I

-135 I 6.00E-OS I 6.00E-OS I 6 00 -os I 6.00E-OS I 6.00E-OS I 6 00E 05 I 5 89E 05 I 5 78E 05 I 5.67E-05 I 5.56E-05 I

-138 I 2.30E-04 I 2.30E-04 I 2.30E 04 I 2 30E 04 I 2 30E 04 I 2 30E 04 I 1.27E 04 I 7 01 05 I 3 87E 05 I 2.14E-OS I I Noble GasI 5 '8E-04 I 5.08E-04 I 5.08E-04 I 5.08E-04 I 5 '8E-04 I 5.08E-04 I 3.58E-04 I 2.73E-04 I 2.22E-04 I 1.91E-04 I I I I I I I I I I I Te-'132 3.90E-06 I 3.90E-06 I 3.90E-06 I 3.90E-06 I 3.90E-06 I 3.90E-06 I 3.85E-06 I 3.84E-06 I 3.84E-06 I 3.83E-06 I Cs-134 1.10E-OS I 1.10E-OS I 1.10E-05 I 1.10E-OS I 1.10E-OS I 1.10E-05 I 1.09E-OS I 1.09E-OS I 1.09E-OS I 1.09E-OS I

-137 3.10E-OS I 3.10E-OS I 3.10E-OS I 3.10E-OS I 3.10E-05 I 3 '0E 05 I 3.07E-OS I 3.07E 05 I 3.07E 05 I 3.07E 05 I Co-58 7.80E-OS I 7.80E-OS I 7.8oE-os I 7-BoE-os I 7.8oE-os I 7.8oE-os I 7.72E-OS I 7.72E-os I 7.72E-os I 7 72E-os I

-60 1.60E-04 I 1.60E-04 I 1 60E 04 I 1.60E-04 I 1 60E 04 I 1 60E 04 I 1.58E-04 I 1.58E-04 I 1.58E-04 I 1.58E-04 I C0-141 1.20E.OS I 1.20E-05 I 1.20E-OS I 1.20E-OS I 1.20ECOS I 1.20E.OS I 1.19E-05 I 1 '9E-05 I 1 '9E-05 I 1.19E-OS I Ba-140 1.60E-04 I 1.60E-04 I 1.60E-04 I 1 60E 04 I 1.60E-04 I 1 60E 04 I 1 SBE 04 I 1.58E-04 I 1 58E 04 I 1 58E 04 I La-140 1.18E-04 I 1.18E-04 I 1 '8E 04 I 1 '8E 04 I 1 '8E 04 I 1 18E 04 I 1 '6E 04 I 1 '6E 04 I 1.15E 04 I 1 15E 04 I Partic. 5.74E-04 I 5.74E-04 I 5.74E-04 I 5.74E-04 I 5.74E-04 I 5.74E-04 I 5.68E-04 I 5.67E-04 I 5.66E-04 I 5.66E-04 I I I I I I I I I I I Total 1.37E-01 I 1.37E-01 I 1.37E-01 I 1.37E-01 I 1.37E-01 I 1.37E-01 I 1.21E-01 I 1.10E-01 I 1.01E-01 I 9.26E-02 I 10.2-1

Nine Hi le Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 TABLE 10.2.1-1 REACTOR 'MATER SAHPLE ANALYSIS TOTAL CONCENTRATION uCI/mi I 02:30 O2:4S 03:00 03:15 i 03:30 / 03:45 i 04:00 O4 ~ 1S I 04:30 I 04:45 I I NUCLIDE (09:00) I (09:15) (09:30) I (09'45) I (10'00) i (10'15) I (10'30) (1O:4S) I (11:00) I (11'15) I I -131 1.66E-03 i 1.66E-03 I 1 66E 03 I 1 65E 03 I 1 65E 03 I 1 65E 03 I 1 62E 03 I 2'97E+03 I 5'94E+03 I 2 38E+04 I

-132 2.07E-02 I 1.92E-02 I 1.78E-02 I 1 65E 02 I 1 '2E-02 I 1.41E-02 I 1.28E-02 I 3.77E+02 I 7.54E+02 I 3 02E+03 I

-133 2.16E-02 I 2.14E-02 )

2.12E-02 / 2.11E-02 / 2.09E-02 ( 2.07E-02 / 2.01E-02 / 2.03E+03 / 4.07E+03 / 1.63E+04 (

-134 2.02E-02 I 1.65E-02 / 1.35E-02 i 1.11E-02 i 9.08E-03 i 7.43E-03 i 5.96E-03 i 4.60E+02 i 9.21E+02 i 3.68E+03 i

-135 2.08E-02 I 2 03E 02 I 1 98E-02 I 1.93E-02 I 1.88E-02 I 1.83E-02 I '1.75E-02 I 1.08E+03 I 2.16E+03 I 8 65E+03 I lodines 8.50E-02 I 7.91E-02 I 7.40E 02 I 6.95E 02 I 6.56E-02 J 6.22E-02 i 5.80E-02 i 6.92E+03 I 1 38 04 I 5 54 +04 I I I I I I I I I I I ADOBE-05 Kr-85m 1.32E-OS I 1.26E-OS i 1.22E-OS I 1 17E 05 I 1.12E-05 i 1.08E-OS I 1.O4 -OS I 1.39E+00 I 2'76E+00 i 7.59E+00 I

.87 2.78E-OS I 2.42E-05 i 2.11E-OS ( 1.84E-OS i 1.61E-OS / 1.40E-05 i 1.22E-OS i 1.42E+00 i 2.81E+00 i 7.72E+00 )

-88 4 '4E-05 I 3 79E 05 I 3.57E 05 I 3.35E 05 I 3.15E-OS I 2.96E-OS I 2.78E-OS I 3 ~ OOE+00 I 5 94E 00 I 1 63E+01 I XG-133 2.09E-05 I 2.09E-OS I 2.08E-05 i 2.08E-05 I 2 i 2.07E-OS I 2.07E-05 i 6.06E+01 I 1.20E+02 i 3.30E+02 )

135m I 2.50E-06 I 1.28E-06 t 6.58E-07 i 3.38E-07 i 1.74E-07 i 8.91E-08 i 4.58E-08 i 6.06E+00 i 1.20E+01 )

3.30E+01

-135 I 5.46E-OS I 5.36E-05 I 5 26E 05 I 5 16E 05 I 5.06E-OS I 4.97E 05 I 4 87E 05 I 7.82E+00 i 1.55E 1 I 4.26E+01

-138 I 1.18E-OS I 6.51E-06 i 3.59E-06 i 1.98E-06 J 1 '0E-06 J 6.05E.07 [ 3.34E-07 i 2.73E+00 i 5.40E+00 i 1 '9E+01

)

Noble Gasi 1.71E-04 (

1.57E-04 i 1.47E-04 i 1.38E-04 (

1.31E-04 i 1.26E-04 i 1 '0E-04 i 8.30E+01 i 1.64E+02 i 4.52E+02 /

I I I I I I I .I I I Te-132 3.82E-06 I 3.81E-06 / 3.80E-06 / 3.79E-06 i 3.78E-06 i 3.78E-06 / 3.73E-06 i 5.28E+02 (

1.06E+03 i 4.24E+03 i Cs-134 1.09E-OS I 1.09E-OS i 1.09E-OS i 1.09E-05 i 1.09E-05 i 1.09E-OS [

1.08E-05 i 5.62E+02 / 1.13E+03 / 4.51E+03 i

-137 3.07E-OS I 3.07E-OS I 3.07E 05 I 3 '7E 05 I 3 '7E 05 I 3.07E-OS I 3.04E-OS I 8.43E+02 I 1.70E+03 I 6'77E+03 I Co-58 7.72E-OS I 7.72E-OS I 7.72E-OS I 7.72E-OS I 7.71E-OS I 7.71E 05 I 7.64E-05 I 6.82E-OS I 6.75E-OS I 6.68E-OS I

-60 1.58E-04 I 1.58E-04 i 1.58E-04 )

1.58E-04 J 1.58E-04 i 1.58E-04 / 1.57E-04 i 1.54E-04 /

1.52E-04 i 1.51E-04 i C0-141 1 ~ 19E-05 I 1.19E-05 I 1.19E-OS I 1.19E-05 I 1.19E-OS I 1.19E-OS I 1.17E-OS I 1 '6E-05 I 1.15E-05 I 1.14E-OS I Ba-140 1.58E-04 I 1.58E-04 I 1 '8E-04 I 1.58E 04 I 1.58E-04 I 1 58E 04 I 1 '6E-04 I 1.54E-04 I 1.53E-04 I 1.51E-04 I La-140 1.14E-04 I 1.14E-04 1 '3E 04 I 1 13E 04 I 1 12E 04 I 1 12E 04 I 1 10E 04 I 1 '9E 04 I 1.07E 04 I 1 '6E 04 I Partic. 5.65E-04 I 5.65E-04 I 5'64E 04 I 5.63E-04 I 5 63E 04 I 5.62E-04 I 5 '6E-04 I 1.93E+03 I 3.89E+03 I 1.55E+04 I I I I I I I I I I Total 8.57E-02 i 7.98E-02 I 7.47E-02 I 7.02E-02 I 6.63E-02 I 6.29E-02 I 5.86E-02 I 8.94E+03 I 1.79E+04 I 7.14E+04 I 10.2-2

Nine Hile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 TABLE 10.2.1-1 REACTOR WATER SAHPLE ANALYSYIS TOTAL CONCENTRATION uCI/ml I 05 00 05:15 05:30 I 05:45 I 06:00 I 06:15 06:30 06:45 07:00 I NUCLIDE (11:30) (11:45) (12:00) I (12:15) I (12:30) I (12:45) I (13:00) (13:15) (13:30) I I-131 3.24E+04 [ 2.70E+04 I 2 48E+04 I 2.28E+04 I 2 10E+04 I 1 95E+04 I 1.80E+04 (

1.65E+04 [ '1.48E+04 J

-132 4.12E+03 [ 3.43E+03 i 2.92E+03 i 2.69E+03 i 2.47E+03 i 2.29E+03 i 2.12E+03 J 1.95E+03 i 'l.75E+03 J

-133 2.22E+04 I 1 85E+04 i 1.69E+04 ( 1.55E+04 i 1.43E+04 i 1.33E+04 i 1.22E+04 i 1.12E+04 i 'l.01E+04 i

-134 5.02E+03 I 4 19E+03 i 3.15E+03 / 2.90E+03 i 2.67E+03 i 2.48E+03 i 2.28E+03 i 2.10E+03 i 1.88E+03 i

-135 1.18E+03 i, 9.83E+03 i 8.81E+03 / 8.11E+03 / 7.46E+03 / 6.93E+03 i 6.38E+03 i 5.87E+03 [ 5.27E+03 /

lodines 6.49E+04 I 6.29E+04 J 5.66E+04 i 5.20E+04 J 4.79E+04 i 4.45E+04 J 4.10E+04 i 3.77E+04 i 3.38E+04 i I I I I I I I I I Kr-85m 1.14E+01 (

9.10E+00 f 8.05E+00 / 7.12E+00 [ 6.30E+00 / 5.57E+00 / 4.93E+00 / 4.36E+00 J 3.85E+00 )

-87 1.16E+01 ( 8.40E+00 I 6.74E+00 i 5.41E+00 I 4.34E+00 ( 3.48E+00 I 2 79E+00 I 2.24E+00 I 1'80E+00 I 2.46E+01 i 1.92E+01 I 1 66E+01 I 1 43E 01 I 1 24E 01 I 1 07E+01 I 9.26E+00 I 8.01E+00 ( 6.93E+00 J Xe-133 4.96E+02 i 4.11E+02 / 3.41E+02 ( 2.82E+02 / 2.34E+02 / 1.94E+02 J 1.61E+02 / 1.33E+02 / 1.10E+02 /

-135m i 4.96E+01 i 2.11E+01 I 9.99E+00 I 4.72E+00 I 2.23E+00 I 1.05E+00 I 4.97E-01 i 2.35E-01 J 1.11E-01

-135 6.40E+01 i 5.21E+01 / 4.70E+01 J 4.25E+01 / 3.83E+01 I 3.46E+01 I 3 '2E+01 I 2 82E+01 I 2.55E+01 I

-138 2.23E+01 i 1.02E+01 i 5.19E+00 J 2.64E+00 i 1.34E+00 / 6.80E-O'I i 3.46E-01 i 1.76E-01 i 8.91E-02 J I Nobte Gasl 6.79E+02 i 5.31E+02 I 4.34E+02 I 3.59E+02 I 2.99E+02 I 2.50E+02 / 2.10E+02 I 1.77E+02 / 1 '9E+02 /

I I I I I I I I I Te-132 5.79E+03 i 4.80E+03 i 4.42E+03 / 4.07E+03 i 3.74E+03 i 3.44E+03 / 3.17E+03 / 2.92E+03 i 2.68E+03 /

Cs-134 6.16E+03 i 5.06E+03 / 4.66E+03 / 4.29E+03 [ 3.95E+03 [ 3.63E+03 / 3.34E+03 )

3.08E+03 / 2.82E+03 /

-137 9.24E+03 i 7.67E+03 / 7.06E+03 I 6.50E+03 I 5'98E+03 I 5 50 03 I 5 06E+03 I 4.66E+03 I 4.28E+03 /

Co-58 6.62E-05 I 6.55E-05 / 6.48E-OS i 6.42E-05 )

6.35E-05 i 6.29E-05 / 6.22E-05 i 6.16E-05 (

6.10E-05 i

-60 1.49E-04 I 1.48E-04 I 1.46E-04 I 1.45E-04 I 1.44E-04 I 1 42E-04 I 1.41E-04 I 1.39E-04 I 1.38E-04 I Ce-141 1.13E-05 I 1 ~ 11E-05 I 1 ~ 10E 05 I 1 09E 05 I 1.08E-'05 I 1.07E-05 I 1.06E-05 I 1.05E 05 I 1.04E-05 I Ba-140 1.49E-04 1.48E-04 1.46E-04 i 'l.45E-04 i 1 '3E-04 ) 1.42E-04 i 1.40E-04 / 1.39E-04 1.37E-04 J /

La-140 1.04E-04 I 1.03E-04 I 1.01E-04 I 9.98E-05 I 9.83E-05 I 9.69E-05 I 9.55E-05 I 9.42E-05 I 9.28E-05 I Partic. 2.12E+04 )

1.75E+04 I 1.61E+04 )

1.49E+04 /

1.37E+04 I 1.26E+04 I 1.16E+04 / 1.06E+04 / 9.79E+03 /

I I I I I I I - I I Total 8.68E+04 I 8 10E+04 i 7.31E+04 i 6.73E+04 i 6.18E+04 J 5.73E+04 / 5.27E+04 i 4.85E+04 / 4.38E+04 /

10.2-3

Nine Hile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 TABLE 10.2.2 DRTNELL AIR SANPLE ANALYSIS TOTAL CONCENTRATION uCI/ml I OO:OO OO ~ 1S I 00:30 I 00:45 I 01:00 I 01:15 I 01:30 I 01:45 I 02:00 I 02:15 I I NUCLIDE I (06:30) (O6:4S) I (07'00) I (07'15) I (07:30) I (07:45) I (08:00) I (08'15) I (08'30) I (08'45) I I-131 6.38E-10 I 6.38E-10 I 8.13E-09 I 3.06E-08 I 5.30E-08 I 7.55E-08 I 2.40E-07 I 4.05E-07 I 5.70E-07 I 7.34E-07 I

-132 3'86E 09 I 3'86E 09 I 1 40E 07 I 5 20E 07 I 8 99 07 I 1 28E 06 I 3 86E-06 I 6.26E-06 I 8.47E-06 I 1 05E 05 I

-133 4.77E-09 I 4.77E-09 I 1 '6E-07 I 4.08E-07 7.09E-07 I 1.01E-06 I 3.21E-06 I 5 '8E-06 7.54E-06 9.69E-06 I I I I

-134 1 '1E-08 I 1 '1E-08 I 2.58E-07 I 8.64E-07 I 1.47E-06 I 2.08E-06 I 5.72E-06 I 8.71E-06 I

'I ~ 12E-05 I 1.32E-OS I

-135 5 '3E-09 i 5.23E-09 i 1.12E-07 i 4.24E-07 [ 7.35E-07 i 1.05E-06 i 3.28E-06 i 5.45E-06 / 7.57E-06 i 9.64E-06 i Iodines 2.56E-08 I 2.56E-08 I 6.24E-07 I 2.25E-06 I 3.87E-06 I 5.49E-06 I 1.63E-05 I 2.62E-OS I 3.53E-OS I 4.37E-OS I I I I I I I I I I I Kr-Bsm 6.24E-09 I 6.24E-09 I 2.82E-OS I 2.85E-05 I 2.88E-OS I 2 90E 05 I 2 93E 05 I 2.96E-OS I 2.99E-OS I 3.02E-OS I

-87 4.37E-09 I 4.37E-09 I 9.69E-OS I 9.79E-OS I 9.89E-05 I 9.98E-OS I 1.01E-04 I 1.02E-04 I 1 '3E-04 I 1.04E-04 I

-88 7.91E-09 I 7.91E-09 I 9.69E-OS I 9.79E-OS I 9.89E-OS I 9.98E-OS I 1.01E-04 I 1.02E-04 I 1.03E-04 I 1.04E-04 I Xe-133 2.29E-07 I 2.29E-07 I 3.72E-OS I 3.76E-OS I 3.80E-OS I 3.83E-OS I 3.87E-OS I 3.91E-OS I 3.95E-OS I 3.98E-OS I 135m I 1 27E 07 I 1 27E 07 I 1.23E-04 I 1 25E 04 I 1.26E-04 )

1.27E-04 I 1.28E-04 I 1.30E-04 I 1.31E 04 I 1.32E-04 I

-135 2.71E-07 I 2.71E-07 I 1 06E 04 I 1.07E 04 I 1.08E-04 I 1.09E-04 I 1.10E-04 I 1 '1E-04 I 1 12E 04 I 1 '3E 04 I

-138 52E 08 I 1 52E 08 I 4 OSE 05 I 4.09E-05 I 4.14E-05 I 4 18E 05 I 4 22 05 I 4'26E 05 I 4 30E 05 I 4 34E 05 I I Noble Gasl 6'61E 07 I 6 61E 07 I 5'29E 04 I 5 35 04 I 5 40E-04 I 5.45E-04 I 5 50E 04 I 5.56E-04 I 5.61E 04 I 5 66 04 I I I I I I I I I I I Te-132 )

6.87E-15 i 1.37E-14 i 2.06E-14 i 2.75E-14 ( 1.80E-13 i 3.32E-13 )

4.84E-13 i 6.35E-13 i Cs-134 8.62E-13 I 8.62E-13 I 8.62E-11 I 8.63E-11 I 8.63E-11 I 8.64E-11 I 8.68E-11 I 8.73E-11 I 8.77E-11 I 8.81E-11 I

-137 8.00E-13 ) 8.00E-13 i 7.76E-10 (

7.76E-10 [ 7.76E-10 )

7.77E-10 i 7.78E-10 i 7.79E-10 i 7.80E-10 i 7.81E-10 i Co-58 4 21E 12 I 4 21E 12 I 4 49E 12 I 4 90 12 I 5 31E 12 I 5.72E-12 i 8.79E-12 I 1'18E 11 I 1'49E 11 I 1'BOE 1'I I

-60 2.00E-11 .i 2.00E-11 i 2.34E-10 i 2.35E-10 i 2.38E-10 J 2.37E-10 i 2 43E-'IO i 2.49E-10

~

)

2.56E-10 i 2.62E-10 )

Ce-141 9.00E.13 i 9.00E-13 I 9 40E 10 I 9.40E-10 I 9 40E-'Io I 9.40E-10 I 9.41E-10 I 9.41E 10 I 9'42E 10 I 9'42E 10 I Ba-140 4 ~ OOE 13 I 4 ~ OOE 13 I 3 77E 10 I 3 78E 10 I 3 79 10 I 3.80 10 I 3.86E-10 i 3.92E-10 J 3.99E-10 i 4.05E-10 /

La-140 I

---

I 2.08E-13 I 8.29E-'13 I 1.45E-12 I 2.07E-12 I 6.66E-12 I 1.12E-.11 I 1 ~ 58E-11 I 2.03E-11 I Partic. 2.72E-11 I 2.72E-11 I 2.42E-09 I 2.42E-09 I 2.42E-09 i 2.43E-09 I 2.45E-09 I 2.47E-09 I 2'49E 09 I 2 '2E-09 I

'

I I I I I I I I I Total 6.86E-07 I 6.86E-07 I 5.30E-04 I 5.37E-04 I 5 ~ 44E-04 I 5.51E-04 I 5.67E-04 I 5.82E-04 I 5.96E-04 I 6.10E-04 I 10.2-4

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 TABLE 10.2.2 DRYMELL AIR SAMPLE ANALYSIS TOTAL CONCEN'IRATION uCi/ml I 02:30 O2:4S I 03-00 I 03:15 I 03:30 I 03:45 I 04:00 I 04:15 I 04:30 I 04:45 I i NUCLIDE (09:00) I (09:15) I (09:30) I (09:45) I (10:00) I (10:15) I (10:30) I (10:45) I (11:00) I (11:15) I 1-131 1.28E-06 i 1.83E-06 i 2.87E-06 I 3.90E-06 I 4.94E-06 I 5.98E-06 I 6.99E-06 I 1.49E 01 I 4 '7E 01 I 1.64E+00 I

-132 1.69E-05 i 2.27E-05 I 3.31E-OS I 4.26E-OS I 5.15E-OS I 5.97E-OS I 6.71E-OS I 1.76E-02 I 5.27E-02 I 1.93E-01 I

-133 1.68E-OS I 2.38E-OS I 3.70E-OS I 5.01E-05 )

6.31E-OS i 7.60E-05 I 8.85E-OS I 1.01E-01 I 3 04E 01 I 1 '1E+00 I

-134 1.86E-OS I 2.31E 05 i 3.01E-OS I 3.58E-OS I 4.04E-OS I 4.42E-OS I 4.73E-OS I 1.90E-02 I 5.69E-02 I 2.08E-01 I

-135 1.63E-05 I 2 29E 05 I 3.50E-OS I 4.68E-OS I 5.83E-05 I 6.94E-05 I 8.01E-05 I 5.30E-02 I 1.59E-01 I 5.82E-01 I ADOBE-04 i lodines 6.99E-OS I 9.43E-05 I 1.38E-04 I 1 79E 04 I 2 18E 04 I 2 SSE 04 I 2 90E 04 I 3 40E 01 I 1.02E 00 I 3 74E+00 I

'

I I I I I I I I I Kr-Bsm 3 '5E-05 I 3.07E-OS I 3.10E 05 i 3.13E-OS i 3.16E-OS i 3.19E-OS i 3.21E-05 i 1.61E+00 i 3.21E+00 i 1.08E+01

-87 1.05E-04 I 1.06E-04 I 1.07E-04 / 1 (

1.09E.04 i 1.10E-04 i 1.10E-04 i 1.49E+00 i 2.96E+00 / 9.93E+00 )

1.05E-04 I 1.06E-04 1.07E-04 i 1.08E-04 I 1.09E.04 I 1.10E-04 I 1.10E-04 I 3.39E+00 I 6.75E+00 I 2.26E+01 I Xe-133 4.02E-05 / 4.06E-OS I 4.09E-OS I 4 '3E-05 I 4 '7E-05 I 4.20E-OS I 4 24E 05 I 7.28E+01 I 1.45E+02 i 4.86E+02 i

-135m / 1.33E-04 I 1.35E-04 I 1.36E-04 i 1.37E-04 / 1.38E-04 i 1.40E-04 / 1.41E-04 i 3.74E+00 / 7.45E+00 ( 2.50E+01

-135 I 1 ~ 14E-04 I 1 '6E-04 i 1.17E-O4 i 1.18E-04 i 1.19E-04 i 1.20E-04 i 1.21E-04 i 9.22E+00 / 1.84E+01 i 6.16E+01

-138 I 4.38E-OS I 4.42E-OS I 4.46E-OS i 4.50E-OS i 4.54E.05 i 4.58E-OS ) 4.62E-OS / 1.81E+00 i 3.61E+00 i 1.21E+01

/ Noble Gasi 5.72E-04 i

'S.77E-O4 I 5.82E-04 I 5.87E 04 I 5 93E 04 I 5 98E 04 I 6 03E 04 I 9 40E+01 I 1 87E+02 I 6 28E+02 I I I I I I I I I I I Te-132 1.14E-12 / 1.64E-12 I 2.59E 12 I 3.54E-12 I 4.49E-12 I 5.44E-12 I 6.37E-12 I 2.65E-06 I 7.97E-06 I 2.92E-OS I Cs-134 8.96E-11 I 9.10E-11 I 9.37E-11 i 9.65E-11 i 9.92E-11 i 1 '2E-10 i 1 '5E-10 (

2.82E-06 (

8.49E-06 i 3.12E-OS i

-137 7.85E-10 I 7.90E-10 I 7.97E-10 I 8.OS -1O I 8 13E 10 I 8 20E 10 I 8 28E 10 I 4 23E 06 I 1.27E 05 I 4 67E 05 I Co-58 2.82E-11 I 384E11 i 5.77E-11 I 7.71E-11 I 9.65E-11 I 1 '6E-10 I 1.35E-10 I 1.35E-10 I 1.35E-10 I 1.35E-'10 I

-60 2.83E-10 I 3.04E-10 I 3.44E-10 I 3 83E 10 I 4 2~E 10 I 4.63E-10 I 5.02E-10 I 5 02E 10 I 5 02 10 I S.O2E-IO i Ce-141 9.44E-10 i 9.45E-10 I 9.48E-10 I 9.51E-10 I 9.54E-10 I 9.57E-10 I 9.60E-10 I 9.60E-10 I 9.60E-10 I 9.60E-10 I Ba-140 4.26E-10 i 4.47E-10 I 4 86E 10 i 5.26E-10 i 5.65E-10 i 6.05E-'lo i 6.44E-10 )

6.44E-10 /

6.44E-10 )

6.44E-'10 i La-14O 3.54E-1'I I 5.04E-11 I 7.87E-11 I 1 07E 'Io I 1'35E 10 I 1'63E 10 I 1 91E 10 I 1 91 10 I 1 91E 10 I 1 91E 10 I Partic. 2.59E-09 I 2.67E-09 I 2 81E 09 ( 2.95E-09 i 3.09E-09 I 3.23E-09 I 3 37E 09 I 9.71E 06 I 2.92E 05 I 1 '7E 04 I

'

I I I I I I I I I Total 6.41E.04 I 6.71E-04 i 7.20E-04 I 7.67E-04 I 8.11E-04 I 8.53E-04 I 8.93E-04 I 9.44E+01 J 1.88E+02 i 6.3'IE+02 I 10.2-5

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 I

TABLE 10.2.2 DRYNELL AIR SAMPLE ANALYSIS TOTAL CONCENTRATION uCi/ml I I 05 00 I 05 15 05:30 (

05:45 (

06:00 (

06:15 (

06:30 ( 06:45 (

07:00 I NUCLIDE I (11'30) I (11'45) I (12'00) I (12r15) I (12'30) I (12'45) I (13'00) I (13'15) I (13'30) I I-131 3.27E+00 I 3.66E+00 I 4.01E+00 (

4.33E+00 (

4.61E+00 (

4.88E+00 ( 5 ~ 11E+00 (

5.16E+00 (

5.21E+00 (

-132 3.85E-01 I 4.31E-01 I 4.69E-01 I 5.03E-01 I 5.34E-01 I 5.62E-01 I 5.87E-01 I 5.93E-01 I 5.98E-01 I I

-133 2.22E+00 I 2.49E+00 I 2.72E+00 (

2.94E+00 ( 3 ~ 13E+00 (

3.31E+00 (

3.46E+00 (

3.50E+00 (

3.53E+00 (

I -134 4.15E-01 I 4.65E-01 I 5.00E-01 I 5.33E-01 I 5.62E-01 (

5.88E-01 (

6.12E-01 I 6.17E-01 I 6.22E-01 (

-135 6.40E-01 I 7.84E-01 I 9.11E.01 (

1 ~ 03E+00 (

1.13E+00 (

1.22E+00 (

1.31E+00 (

1.33E+00 (

1.34E+00 (

( Iodines 6.92E+00 (

7.82E+00 (

8.61E+00 (

9.33E+00 (

9.97E+00 ( 1 ~ 06E+01 (

1.11E+01 (

1.12E+Ol (

1.13E+01 I I I I I I I I I I Kr-85m 2.16E+01 (

2-05E+01 ( 1.96E+01 (

1.86E+01 (

1.77E+01 (

1.69E+01 ( 1.61E+01 (

1.54E+01 (

1 ~ 48E+01

-87 1.99E+01 ( 1.72E+01 ( 1.49E+01 ( 1.28E+01 (

1.11E+01 (

9.56E+00 (

8.26E+00 (

7.20E+00 (

6.28E+00 (

-88 4 '4E+01 (

4.23E+01 (

3.93E+01 I 3 66E+01 I 3 41E+01 l 3.17E+01 (

2.95E+01 I 2.77E+01 I 2.61E+01 I Xe-133 9.75E+02 I 9 64E+02 I 9 53E+02 I 9.42E+02 I 9.32E+02 ( 9.21E+02 (

9.11E+02 (

9.'IOE+02 (

9.08E+02 I

-135m ( 5.01E+01 I 2 55E+01 I 1.30E+01 I 6 59E+00 I 3 35E+00 I 1 70E+00 I 8 66E 01 I 4 45E 01 I 2 28E 01 I

-135 I 1.24E+02 ( 1.20E+02 ( 1 '7E+02 I 1.13E+02 I 1.10E+02 I 1.07E+02 I 1.04E+02 I 1.02E+02 I 1.00E+02 I

-138 I 2.42E+01 ( 1.33E+01 ( 7.24E+00 I 3 96E+00 I 2 16E+00 I 1 18E+00 I 6 47E 01 I 3 57E 01 I 1 97E 01 I

(

Noble Gas( 1.26E+03 ('1.20E+03 (

1.16E+03 (

1.13E+03 ( 1.11E+03 (

1.09E+03 l 1 07Ei03 I 1 '6E+03 I 1 '6E+03 (

-

I I I I I I I I I I I Te-132 5.82E-05 (

1 ~ 18E-04 (

1.72E-04 I 2.21E-04 I 2.66E-04 I 3.06E-04 I 3.43E-04 I 3.50E-04 I 3.57E-04 I Cs-134 6.21E-05 I 1.25E-04 I 1.82E-04 I

-2.34E-04 I 2.82E-04 I 3.24E-04 I 3.63E-04 I 3.71E-04 I 3.78E-04 =I 9.31E-OS (

1;89E-04 I 2'75E 04 I 3.54E-04 I 4.26E-04 I 4.91E 04 I 5 49E 04 I 5 61E 04 I 5'72E 04 I Co-58 1.35E-10 (

1.35E-10 (

1.34E-10 (

1 33 10 I 1.33E-10 (

1.32E-10 (

1.32E-10 I 1 32 10 I 1 32 10 I

-60 5.02E-10 I 4 99E 10 I 4 96E 10 I 4.93E-10 I 4.9I(E-10 I 4.87E-10 I 4.84E-10 I 4.84E-10 I 4.85E-10 I C6-141 9.60E-10 (

9.51E-10 (

9.41E-10 (

9.32E-10 (

9.23E-10 (

9.14E-10 (

9.05E-'IO ( 9 05 10 I 9 05 10 I Ba-140 6.44E-'IO I 6.39E-10 I 6.35E-10 I 6 31 10 I 6.26E-10 (

6.22E-10 (

6.17E-10 I 6.18E-10 I 6 18E 10 I La-140 1.91E-10 I 1.90E-10 I 1.89E-10 I 1.89E-10 I 1.88E-10 I 1 87E 10 I 1 87E 10 I 1.87E-10 I 1.87E-10 I Partic 2.13E-04 I 4.31E-04 I 6.30E-04 (

8.10E-04 (

9.73E-04 (

1.12E.03 (

1.26E.03 (

1.28E-03 (

1.31E-03 (

I I I I I I I I I I Total 1.27E+03 (

1.21E+03 ( 1.17E+03 ( 1 ~ 14E+03 (

1.12E+03 ( 1.10E+03 (

1.08E+03 (

1.07E+03 (

1.07E+03 (

10.2-6

0 kine Hiie Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 TABLE 10.2.3 SUPPRESSION POOL 'MATER SAHPLE ANALYSIS TOTAL CONCENTRATION uCi/ml I 00:00 00:15 00:30 OO:4S 01:00 I 01:15 I 01:30 I 01:45 I 02:00 I 02:15 I i NUCLIDE (06:30) (06:45) (07:00) <or:1s> / <O7:3O> / (07:45) I (08:00) I (08:15) I (08:30) I <08:45) I I-131 I I

--

--- I I I I 3.40E-05 I 3.40E-05 I 3.39E-OS I 3.39E-05 I

-132 I I I 6.20E-04 I 5.74E-04 I 5.32E-04 I 4.93E-04 I I

--- I I

-133

-134 I

I I

I

--

--

I I

I I

I I

)

I 4.60E-04 i 4.56E-04 i 1.12E 03 I 9 I E 04 I 4.52E-04 i 4.48E-04 i 7.51E 04 I 6.15E 04 I

-135 I I I 4.84E-04 I 4.72E-04 I 4.60E-04 I 4.48E-04 I Iodines I I

--- I I

I I

I I

I 2.72E-03 I 2.45E 03 I 2.23E-03 I 2.04E-03 i Kr-Bsm I

I I

I

--

--

I I

I I

I I

I i 1.6OE-06 I

)

I 1.54E-06 i 1.48E-06 )

I 1 '2E-06 I

/

-87 l I I I 5.50E-06 4.80E-06 i 4.18E-06 i 3.65E-06 I I

--- I I I

/

5.50E-06 i

5 ~ 17E-06 I 4.86E-06 I 4.57E-06

/

Xe-133 I I

--- I I

l I I

I 2.10E-06 I

I 2.10E-06 I 2.09E-06 I 2.09E-06 I

I 135m I I I

---

I I I I 7.00E-06 I 3.59E-06 I 1.85E-06 I 9.48E-07 I

-135 I I

---

I I I I 6.00E-06 I 5.89E-06 I 5.78E-06 l 5.67E-06 I

-138 I' I

---

I I I I 2.30E-06 I 1.27E-06 I 7.01E-07 I 3.87E-07 I i Noble Gas i I

---

I I I / 3.00E-05 2.44E-05 / 2.09E-05 / 1.87E-05

/ /

l~

I I I I Te-132 I I

--- I I I I

/ 3.90E-10 I

/ 3.89E-10 I

/ 3.88E-10 I

/

3.87E-10 I

/

Cs-134 I

.- I I 1 ~ 10E 09 I 1.10E 09 1 10E 09 I 1 10E 09 I

--- I I ~

I I

-137 3.10E-09 3.10E-09 3.10E-09 i I I I I I i ( i 3 ~ 10E-09 /

Co-58 7.09E-07 )

7.09E-07 I 7.09E-07 I 7.09E-07 I 7.04E 07 I 7 09E 07 I 7.17E-07 I 7.17E-07 I 7.17E-07 7.17E-07 i

)

-60 5.75E-07 ] s.rsE-or 5.75E-or 5.75E-07 5.75E-07 5.75E-07 5.91E-07 5-91E 07 5.91E-07 5.91E-07 I Ce-141 I

I

--- ~

I

) / I 1

I 20E 09 I 1 '0E 09 I

I 1 20E 09 I

1 20E 09 I Ba-140 I

I

--- I I I 1.60E-08 1.60E-08 1.60E-08 I

1.60E-08 La-140 I I

I

--- I I

I I

I I

/

I 1.18E-08

/

I 1 '7E-08

/

I 1.17E-08

/

I 1.16E-08

/

I Partic. 1.28E-06 I 1 28E-06 / 1.28E-06 / 1.28E-06 I 1.28E-06 I 1 '8E-06 / 1 '4E-06 (

1.34E-06 i 1.34E-06 / 1.34E-06 /

I I I I I I I I I I Total 1 '8E-06 I 1.28E-06 I 1.28E-06 I 1.28E-06 I 1.28E-06 i 1.28E-06 I 2.75E-03 I 2.48E-03 I 2.25E-03 I 2.06E-03 I 10.2-7

Nine Nile Point Unit 2 1990 Annual Exercise Scenario Ho. 19, Rev. 1 TABLE 10.2.3 SUPPRESSION POOL MATER SANPLE ANALYSIS TOTAL CONCENTRATIOH uCI/ml I I 02:30 I 02:45 I 03:00 I 03:15 I 03:30 I 03:45 I 04:00 I 04:15 I 04:30 I 04:45 I

(

HUCLIOE I (09:00) I (09:15) I (09:30) I (09:45) I (10:00) I (10:15) I (10:30) I (10:45) I (11:00) I (11:15) I I-131 3.39E-05 (

3.38E-05 I 3.38E-05 I 3.38E-05 I 3.38E-05 I 3.3?E-05 I 3.23E-05 I 1.52E-03 I 5.99E-03 I 2.24E-02 I

-132 4.56E-04 I 4.23E-04 (

3.91E-04 (

3.62E-04 I 3.36E-04 (

3 '1E-04 (

2.56E-04 (

4.32E-04 (

9.59E-04 (

2.89E-03 (

-133 4.45E-04 (

4.41E-04 I 4.3?E-04 I 4.33E-04 I 4.30E-04 (

4.26E-04 (

4.02E-04 (

1.42E-03 (

4.46E-03 (

1.56E-02 (

-134 5.03E-04 (

4.12E-O4 I 3.37E-04 I 2.76E-04 I 2.26E-04 I 1.85E-04 1.19E-04 I 3.09E-04 8.78E-04 2.96E-03 I I I I

-135 4.36E-04 I 4.25E-04 I 4-14E-04 I 4.04E-04 I 3.93E-04 (

3.83E-04 (

3.49E-04 (

8.79E-04 (

2.4?E-03 (

8.29E-03 (

( Iodines 1.87E-03 (

1.73E-03 I 1.61E-03 I 1.51E-03 I 1.42E-03 I 1.34E-03 I 1.16E-03 I 4.56E-03 I 1.48E-02 I 5.21E-02 I I I I I I I I I ( I Kr-85m 1.3?E-06 I 1.31E-06 I 1.26E-06 I 1.21E-06 I 1 ~ 17E 06 I 1 ~ 12E 06 I 1 ~ OSE 06 I 1-04E 06 I 9.97E 07 I 9 59E 07 I

-87 3.18E-06 I 2.78E-06 I 2.42E-06 I 2.11E-06 I 1.84E-06 (

1.61E-06 (

'1.40E-06 (

1.22E-06 (

1.0?E-06 (

9.29E-07 (

-88 4.29E-06 I 4.04E-06 (

3.79E-06 (

3.57E-06 (

3.35E-06 (

3.15E-06 (

2.96E-06 (

2.78E-06 (

2.62E-06 (

2.46E-06 (

Xe-133 2.09E-06 (

2.09E-06 I 2.08E.06 I 2 OSE-06 I 2.08E-06 I 2 07E 06 I 2 07E 06 I 2'07E 06 I 2.07E-06 I 2 06E-06 (

135m I 4.87E-O? I 2 '0E-07 (

1.28E-07 (

6.59E-OS (

3.38E-OS (

1.74E-08 (

8.92E-09 (

4.58E-09 (

2.35E-09 (

1.21E-09 (

135 I 5.56E-06 I 5 '6E-06 I 5 35E 06 I 5 25E 06 I 5 '6E-06 (

5.06E-06 (

4.96E-06 (

4.8?E-06 (

4.78E-06 (

4.69E-06 (

-138 I 2.14E-07 I'1 '8E-07 (

6.51E-OS (

3.59E-08 (

1.98E-08 I 1.10E-08 I 6.05E-09 I 3.34E-09 I 1.84E-09 I 1.02E-09 I

(

Noble Gas( 1.72E-05 1.60E-05 (

1.51E-OS (

1.43E-05 1.36E-05 (

1.30E-05 (

1.25E-05 (

1.20E-05 I 1 15 05 I 1 11 05 I I I I I I I I I I I I I Te-132 3.87E-10 (

3.86E-IO (3 85E-10 (3.84E 10 I 3.83E-10 (

3.82E-10 (

3.73E-10 (

6.62E-07 (

2.65E-06 (

9.96E-06 (

I cs-134 1 ~ 10E-09 I 1.10E-09 I 1.10E-09 I 1.10E-09 I 1'10E 09 I 1 10 09 I 1.08E-09 I 7 07E 07 I 7 92 07 I 1 10 06 I I

-137 3.10E-09 (

3.1OE-O9 I 3.10E-09 I 3.10E-09 I 3.10E-09 I 3.10E-09 I 3.04E-09 I 1.06E-06 I 1.19E-06 I 1.66E-06 I I

Co-58 7.16E-07 (

?.16E-07 I 7.16E-07 I 7.16E-07 I 7.11lE-O? (

7.16E-07 (

7.64E-09 (

7.64E-09 (

7.64E-09 (

7.64E-09 (

I

-60 5.91E-07 I 591E0? I 5.91E-O? I 5.>>E 0? I 5 91E 0 I 5 91E 07 I 1 57E 08 I 1 E 08 I 1 7E 08 I 1 57E 08 I I Ce-141 1.20E-09 I 1 ~ 20E-09 ( 1 '0E-09 (

1.20E-09 (

1.20E-09 I 1.20E-09 I 1.17E-09 I 1.18E-09 I 1.19E-09 I 1.20E-09 I I

88-140 1.60E-OS I 1.60E-08 (

1.59E-OS ( 1 '9E-08 (

1.59E-OS I 1 '9E-08 I 1 '6E-08 I 1.56E-OS I 1.56E-OS I 1.56E-OS I I

La-140 1 ~ 16E-08 I 1 15E 08 I 1.15E 08 I 1 ~ 14E 08 I 1'14E 08 I 1.14E-08 I 1.10E-08 I 1.10E-08 I 1.10E-08 I 1.10E-OS I I Partic. 1.34E-06 (

1.34E-06 (

1.34E-06 (

1.34E-06 ( 1.34E 06 I 1.34E 06 I 5 '6E 08 I 2 48E 06 I 4.69E 06 I 1.28E 05 I I I I I I I I I I I I I Total 1.89E-03 (

1.?5E-O3 (

1.63E-03 (

1.53E-03 (

1.43E-03 I 1.35E-03 I 1.1?E-03 I 4.5?E-03 I 1.48E-02 I 5.22E-02 I 10.2-8

0 Nine Nile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 TABLE 10.2.3 SUPPRESSION POOL MATER SAHPLE ANALYSIS TOTAL COHCEHTRATION uCI/ml I I 05:00 I 05:15 I 05:30 I 05:45 I 06:00 I 06:15 I 06:30 I 06:45 I 07:00 I i NUCLIDE I (11:30) I (11:45) I (12'00) I (12'15) I (12'30) I (12'45) I (13'00) I (13'15) I (13'30) I I-131 5.50E-02 [ 5.30E+00 I 5.77E+00 I 6.29E+00 I 6 86E+00 I 7 48E+00 I 8.15E+00 I 8.89E+00 I 9.68E+00 I

-132 6.74E-03 I 6.24E-01 i 6.80E-01 i 7.41E-01 i 8.08E-OI i 8.80E.01 i 9.60E-O'I i 1.05E+00 i 1.14E+00 i

-133 3.78E-02 i 3.60E+00 ( 3.93E+00 / 4.28E+00 / 4.66E+00 / 5.08E+00 / 5.54E+00 f 6.04E+00 / 6.58E+00 /

-134 . 7.11E-03 I 673E 01 I 7.34E-01 I 8.00E-01 I 8 71E 01 I 9.50E-01 I 1.04E+00 I 1 13E+00 I 1 23E+00 I

-135 1.47E-02 I 1.88E+00 I 2 05 00 I 2 23E+00 I 2.44E+00 I 2 65E+00 I 2.89E+00 ) 3.15E+00 ).3.44E+00 I Iodines 1.21E-01 i 1.21E+01 I 1'32E+01 I 1 43E+01 I 1 56E+01 I 1 70E+01 I 1 86E+01 I 2 03E+01 I 2'21E+01 I I I I I I I I I I Kr-85m 9.22E-07 / 8.86E-07 I 8.52E-07 I 8.19E-07 I 7.87E-07 I 7.57E-07 I 7.28E 07 I 7.00E-07 I 6.73E-07 I

-87 8.10E-07 I 7.07E 07 I 6.16E-07 I 5.37E-07 I 4.69E-07 I 4 '9E-07 I 3.57E-07 I 3.11E-07 I 2.71E-07 I

-88 2.31E-06 ] 2.17E-06 I 2.04E-06 I 1.92E 06 I 1.81E 06 I 1.70E 06 I 1.60E 06 I 1 '0E 06 I 1 41E 06 I Xe-133 2.06E-06 I 2.06E-06 I 2.05E-06 I 2.05E-06 I 2 OSE 06 I 2 05E 06 I 2.04E-06 I 2.04E-06 I 2.04E 06 I

-135m i 6.21E-10 I 3 '9E-10 I 1 64E 10 I 8.40E-11 I 4.31E 11 I 2.22E-11 I 1.14E-11 I 5.84E-12 I 3 'OE-12 I

-135 4.60E-06 i 4.51E-06 / 4.43E-06 / 4.35E-06 /

4.27E-06 / 4 '9E-06 / 4.11E-06 )

4.03E-06 / 3.95E-06 )

5.62E-10 i '3.10E-10 I 5 '2E-11

-138 I 1.71E-10 I 9.45E-11 I 2.88E-11 I 1.59E-11 I 8.77E-12 I 4.84E.12 I

[ Noble Gas[ 1.07E-05 I 1.03E-05 I 1.00E-05 I 9.68E-06 I 9.38E-06 I 9.09E-06 I 8.83E-06 I 8.58E-06 I 8.34E-06 I I I I I I I I I I Te-132 1.05E-05 i 1.25E+00 / 1.37E+00 (

1.49E+00 i 1.62E+00 i 1.77E+00 i 1.93E+00 I 2.10E+00 I 2.29E+00 I Cs-134 1.72E-06 i 1.33E+00 I 1'44E+00 I 1 57E+00 I 1 72E+00 I 1.87E+00 I 2.04E+00 I 2 22E+00 I 2'42E+00 I

-137 2.59E-06 J 2.01E+00 J 2.19E+00 i 2.39E+00 i 2.60E+00 ) 2.83E+00 i 3.09E+00 / 3.37E+00 i 3.67E+00 J Co.58 7.64E-09 I 1.71E-08 i 1.87E-08 J 2.04E-08 i 2.22E-08 i 2.42E.08 J 2.64E-08 i 2.88E-08 i 3.13E-08 i

-60 1.57E-08 I 3.87E-08 I 4.22E-08 I 4.60E-08 i 5.02E-08 I 5.47E-08 I 5.96E-08 i 6.50E-08 i 7.08E-08 )

Ce-141 1.21E-09 I 2 92E 09 I 3.18E-09 I 3.47E-09 I 3.78E-09 I 4.12E-09 I 4.49E-09 I 4.89E-09 I 5.33E-09 I Ba-140 1.56E-08 i 3.87E-08 I 4 22E 08 I 4 59E 08 I 5 01E 08 I 5 46E 08 I 5 95E 08 I 6 49E 08 I 7'07E 08 I La-140 1.10E-08 f 2.68E-08 I 2.92E-08 I 3.18E-08 I 3.47E-08 I 3.78E-08 I 4.12E-08 I 4.49E-08 I 4.89E-08 I Partic. 1.49E-05 i 4.59E+00 I 5.DOE+00 I 5.45E+00 i 5.94E+00, i 6.48E+00 / 7.06E+00 i 7.69E+00 i 8.39E+00 I I I I I I I I I I Total 1.21E-01 i 1.67E+01 I 1 82E+01 I 1.98E+01 I 2 ~ 16E+01 I 2 35E+01 I 2 56E+01 I 2'79E+01 I 3 05E+01 I 10.2-9

Nine Mile Point Unit 2 1990 Annual Exercise Scenario Ho. 19, Rev. 1 TABLE 10.2.4 SUPPRESSION POOL AIR SAMPLE ANALYSIS TOTAL COHCEHTRATIOH uCI/ml I 00 00 00:15 00:30 F 00-45 01:00 I 01:15 I 01:30 I 01:45 I 02:00 I 02:15 I i NUCLIDE (06:30) (06:45) (07:00) (07:15) I (07:30) (07'45) I (08'00) I (08'15) I (08'30) I (08'45) I I-131 I

--

---

I I

---

--- I I I 8 50 06 I 8 49 06 I 8 48E 06 I 8.48 06 I

-132 I I I I I I 1.55E-04 I 1.44E-04 I 1.33E-04 I 1 '3E-04 I

-133 I

---

I

---

I I 1 '5E-04 I 1.14E-04 I 1 '3E 04 I 1-128-04 I

-134 I

--- I I

I

---

I I

I i 2.80E-04 / 2.29E-04 i 1.88E-04 i 1.54E-04 i

-135 I

--- I

--- I 1

I 1.21E-04 I 1.18E-04 I 1 15E 04 I 1 '2E-04 I

[ Iodines I

---

I I I

--- I I

I / 6.80E-04 / 6.13E-04 / 5.57E-04 ( 5.09E-04 /

Kr-85m I

I

--

---

I I

I I

---

---

I I

I I

I i 1.54E-02 I

I 1 48E I I 02 I 1.42E-02 I 1.37E-02 I I

-87 I I I I I i 4.80E-02 /

4.18E-02 i 3.65E-02 i 3.18E-02 [

-88 ---- I I

---

I 5.17E-02 4.86E-02 4 '7E-02 I 4 '9E-02 I Xe-133 I

I

--- I I

"-- I I I I

)

2.10E-02 )

I 2 '9E-02 /

I 2.09E-02 / 2 '9E-02 /

-135m i I

---

---- I 3.59E-02 1.85E-02 9.48E-03 4.87E-03 I

-135 I --- I I

---

I I 5.89E-02 I

5.78E-02 I

5.67E-02 I

5.56E-02 I

---

I I

-- I I J 1.27E-02

/

7.01E-03

/

3.87E-03

[

2.14E-03

/

f 138 Noble Gas]

I I'---

I I I

I I

--- I I

I I

I

/

2.44E-01 I

I 2 09E 01 I

I 1'87E 01 I

I 1'72E 01 I

I Te-132 I

---

I I

I I

-- I I I

I I

I I I 9.75E-11 I 9.73E-11 I 9.71E-11 I 9.68E-11 I

Cs-134 I

I

--- I I

--- I I I 2.75E-10 I 2.75E-10 I 2.75E-10 I 2.75E-10 I

I

-137 I

--- I I

---

I I J I

7.75E-10 i 7.75E-10 i 7.75E-10 i 7.75E-10 i Co-58 7.09E-11 I 7.09E-11 I 7.09E-11 I 7'09E 11 I 7.09E-11 I 7.09E-11 I 7.17E-11 I 7.17E-11 I 7.17E-11 I 7.17E-11 I

-60 Ce-141 5.75E-11 /

I

--

5.75E-11

---

I 5.75E-'l1 I I

5'75E-11

---

---

I I

5.75E-II /

I 5.75E-'11 I I

5.91 11 I 5.91E-11 I 5 91E 11 I 5.91E 11 1.20E-13 I 1 ~ 20E-13 I 1.20E-13 I 1 ~ 20E 13 I

I Ba-140 I I I I I I 1.60E-12 I 1.60E-12 I 1.60E-12 I 1.60E-12 La-140 I

--- I I

--- I I I 1.18E-12 I 1.17E 12 I 1.17E-12 I 1.16E-12 I

I Partic. 1.28E-10 i 1.28E-10 i 1.28E-'10 I 1.28E-10 I 1.28E-10 I 1.28E-10 I 1.28E-09 I 1.28E 09 I 1.28E-09 I 1.28E-09 I I I I I I I I I I I Total 1.28E-10 I 1.28E-10 I 1.28E-10 I 1.28E-10 I 1.28E-10 I 1.28E-10 i 2.44E-01 I 2.10E-01 I 1.88E-01 I 1.72E-01 I 10.2-10

~:

Nine Hile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 TABLE 10.2.4 SUPPRESSION POOL AIR SAMPLE ANALYSIS TOTAL CONCENTRATION uCi/mi I I 02:30 I 02:45 I 03:00 I 03:15 I 03:30 I 03:45 I 04:00 I 04 15 I 0430 0445 I I i NUCLIDE I (09'00) I (09'15) I (09'30) I (09'45) I (10'00) I (10'15) I (10'30) I (10:45) I (11:00) I (11:15) I 1-131 8.47E-06 / 8.46E-06 i 8.45E-06 i 8.45E-06 i 8.44E-06 / 8.43E-06 i 8.08E-06 / 3.81E-04 / 1.50E-03 i 5.60E-03

-132 1.14E-04 / 1.06E-04 / 9.78E-05 /

9.06E-05 8.39E-05 7.77E-05 / 6.40E-05 1.08E-04 2.40E-04 / 7.23E-04

/ ( / / /

-133 1 '1E 04 I 1 '0E 04 I 1 '9E 04 I 1 '8E 04 I 1.07E 04 I 1 06E 04 I 1 01E 04 I 3-54E 04 I 1-11E 03 I 3.90E 03 I

-134 1.26E-04 I 1.03E-04 I 8.44E-05 I 6.91E-05 I 5.66E-05 I 4.63E-05 I 2.98E-05 I 7.73E-05 2.19E-04 I 7.40E-04 I I

-135 1.09E-04 (

1.06E-04 1.04E-04 i 1.01E-04 9.83E-05 9.58E-05 8.74E-05 2.20E-04 6.17E-04 2-07E-03 J / ( J i / J i

) Iodines 4.69E-04 (

4.34E-04 / 4.03E-04 I 3 77E 04 I 55E 04 I '3 E 04 I 90E 0 I 1 1 E 0 I 3 69E 0 1 30E I I I I I I I I I I I I Kr-85m 1.31E-02 i 1.26E-02 / 1.21E-02 [ 1.17E-02 ) 1.12E-02 1.08E-02 i 1.04E-02 ( 1.61E+00 3.21E+00 1.08E+01 J J [

.87 2.78E-02 I 2.42E-02 I 2.11E-02 I 1.84E-02 I 1.61E-02 I 1.40E-02 1.22E-02 I 1.49E+00 2.96E+00 9.93E+00 i I I I

-88 4 '4E 02 I 3 79 02 I 3 57E 02 I 3.35E-02 I 3 15E 02 I 2.96E-02 / 2.78E-02 3.39E+00 6.75E+00 2.26E+01 I / /

Xe-133 2.09E-02 ( 2.08E-02 / 2.08E-02 / 2.08E-02 / 2.07E-02 / 2.07E-02 / 2.07E-02 / 7.28E+01 / 1.45E+02 / 4.86E+02 /

-135m i 2.50E-03 / 1 '8E-03 6.59E-04 I 3.38E-04 / 1.74E-04 / 8.92E-05 4'58E 05 3 74E+00 I 7 45E+00 2.50E+01 J I I I

-135 5.46E 02 I 5.35E 02 I 5.25E-02 I 5.16E-02 I 5.06E-02 I 4 96E 02 I 4 87E 02 I 9.22E+00 1.84E+01 6 16E+01 I I I

-138 1.18E-03 i 6.51E-04 / 3.59E-04 / 1.98E-04 i 1.10E-04 i 6.05E-05 i 3.34E-05 1.81E+00 3.61E+00 1.21E+01

/ J (

I Noble Gasl 1.60E-01 i'.51E-01 / 1.43E-01 I 1.36E-01 I 1.30E-01 i 1.25E-01 I 1.20E-01 I 9.40E+01 I 1.87E+02 6.28E+02 I I

I I I I I I I I I I Te-132 9.66E-11 I 9.64E-11 I 9.62E-11 I 9.60E-11 I 9.58E-11 I 9.56E-11 I 9.32E-11 1.65E-07 I 6.63E-07 I 2.49E-06 I I Cs-134 2.75E-10 I 2.75E-10 I 2.75E-10 I 2.75E-10 I 2.75E-10 I 2.75E-10 I 2.69E-10 I 1.77E-07 I 1.98E-07 I 2.76E-07 I

-137 7.75E-10 I 7.75E-10 I 7.75E-10 I 7;75E-10 I 7.75E-10 I 7.75E-10 I 7.60E-'10 2.65E-07 I 2.97E-07 i 4.14E-07 I J Co-58 7.16E-11 I 7.16E-11 I 7.16E-11 I 7.16E-11 I 7.16E-11 I 7.16E-11 I 7.64E-13 I 7.64E-13 I 7.64E-13 I 7.64E-13 I

-60 5.91E-11 / 5.91E-11 / 5.91E-11 / 5.91E-11 / 5.9$ E-11 / 5.91E-11 1.57E-12 1.57E-12 / 1.57E-12 / 1.57E-12

[ / /

Ce-141 1.20E-13 i 1.20E-13 (

1.20E-13 1.20E-13 i 1.20E-13 / 1 ~ 20E-13 i 1.17E-13 / 1.18E-13 i 1.19E-13 i 1.20E-13 J i Ba-140 1.60E-12 i 1.60E-12 i 1.59E-12 i 1.59E-12 i 1.59E-12 / 1.59E-12 1.56E-12 i '1.56E-12 i 1.56E-12 1.56E-12

) J i La-140 1 16E 12 I 1 15E 12 I 1 15E 12 I 1 ~ 1 E 12 I 1 14E 12 I 1 14E 12 I 1 10E 12 I 1 10E 12 I 1 10 12 I 1 10E 12 I Partic. 1.28E-09 I 1 '8E-09 I 1.28E-09 I 1.28E-09 I 1.28E-09 I 1.28E-09,I 1.13E-09 I 6.08E-07 I 1.'l6E-06 I 3.18E-06 I I I I I I I I I I I Total 1.61E-01 / 1.52E-01 / '1.44E-01 / 1.37E-01 / 1.31E-01 /

1.25E-01 / 1.20E-01 / 9.40E+01 / 1.87E+02 / 6.28E+02 /

Nine Nile Point Unit 2 1990 Annual Exercise Scenario Ho. 19, Rev. 1 TABLE 10.2 '

SUPPRESSIOH POOL AIR SAHPLE ANALYSIS TOTAL CONCEHTRATIOH uCI/ml I I 05'00 I 05'15 I 05-30 I 05:45 I 06:00 I 06:15 I 06:30 I 06:45 I 07:00 I I NUCLIDE (11:30) ) (11:45) I (12:00) I (12:15) I (12:30) I (12:45) I (13:00) I (13:15) I (13:30) I I-131 1.38E-02 i 1.30E+00 f 1.42E+00 f 1.55E+00 f '1.69E+00 )

1.84E+00 f 2.DOE+00 f 2.22E+00 ] 2.42E+00 f

-132 1.68E-03 I 1 42E 01 1.69E-01 1.84E-01 I 2.62E-01 / 2.85E-01 I 1 55 01 I ( I 2 01E 01 I 2 19 01

-133 9.45E-03 ( 8.79E-01 / 9.58E-01 I 1 04E+00 I 1 14E+00 I 1'24E+00 I 1 35E+00 I 1 51E+00 1.65E+00 I /

-134 1.78E-03 [ 1.36E-01 (

1.48E-01 I 1 61E 01 I 1.76E-01 I 1.91E-01 2.09E 01 2 82E 01 I 3.08E-01

/ I I

-135 3 67E 03 I 4 51E 01 (

4.92E-01 I 5 36E 01 I 5.84E-01 I 6.37E-01 6.94E-01 7.89E-01 / 8.60E-01

/ /

Iodines 3.03E-02 ) 2.91E+00 i 3.'17E+00 i 3.46E+00 i 3.77E+00 i 4.11E+00 [ 4.48E+00 ( 5.06E+00 / 5.52E+00 i I I I I I I I I I Kr-85m 2.16E+01 i 2.02E+01 I 1.93E+01 I 1.83E+01 I 1.74E+01 I 1.66E+01 I 1.58E+01 I 1.54E+01 1 ~ 48E+01 I

-87 1.99E+01 i 1.69E+01 / 1.46E+01 / 1.26E+01 ) 1.09E+01 I 9 41E+00 I 8 13 +00 I 7.20E+00 / 6.28E+00 I

-88 4.54E+01 i 4.16E+01 ) 3.87E+01 / 3.60E+O'I I 3.35E+01 I 3 ~ 12E+01 I 2.91E+01 I 2 77E+01 I 2 61E+01 I Xe-133 9 75E+02 I 9 49E+02 I 9 38E+02 I 9 28E+02 I 9.17E+02 I 9.07E+02 I 8.97E+02 I 9 10E+02 I 9.08E+02 I

-135m i 5.01E+01 i 2.51E+01 1.28E+01 i 6.48E+00 i 3.30E+00 i 1.68E+00 i 8.52E-01 / 4.45E-01 / 2.28E-01 I 1.24E+02 i 1.18E+02 1 '2E+02 135 I 1.15E+02 I I 1.08E+02 I 1 05E 02 I 1 02E+02 I 1 '2E+02 I 1 ~ OOE 02 I

-138 I 2.42E+01 i 1.30E+01 I 7 13E+00 I 3.90E+00 I 2.13E+00 1 '6E+00 I 6.36E-01 I 3 57E 01 1 97E 01 I I

)

Noble Gas/ 1.26E+03 i'1.18E+03 I 1 '5E+03 I 1 12E+03 I 1 09E+03 I 1 07E+03 I 1 05E+03 I 1 06E+03 I 1 06E+03 I I I I I I I I I I Te-132 2.63E-06 ( 3.09E-01 / 3.36E-01 / 3.67E-01 / 4.00E-01 / 4.36E-01 )

4.75E-01 / 5.26E-01 5.73E-01

}

Cs-134 4.31E-07 f 3.26E-01 I 3.56E-01 / 3.88E-01 i 4.22E-01 / 4.60E-01 I 5'02E 01 I 5'56E 01 I 6.06E-01 I

-137 6'47E 07 I 4 94E 01 / 5.39E-01 / 5.87E-01 / 6.40E-01 [ 6.98E-01 / 7.60E-01 /

8:42E-01 9.18E-01 f

Co-58 7.64E-'13 i 4.22E-09 / 4.60E-09 / 5.01E-09 ( 5.46E-09 / 5.96E-09 6.49E-09 2.88E-12 3.13E-12

/ / / /

-60 1 57E 12 I 9.53E-09 I 1 '4E-08 I 1.13E-08 I 1.2SE-08 I 1.35E-08 1.47E-08 6.50E-12 7.08E-12 I I I I Ce-'141 21E 13 I 7.18E-10 I 7 83E 10 I 8.53E-10 I 9.30E-10 I 1.01E-09 I 1.10E-09 I 4.89E-13 I 5.33E-13 I BB-140 1.56E-12 I 9.52E-09 i 1.04E-08 i 1 '3E-08 i 1.23E-08 i 1.34E-08 i 1.46E-08 i 6.49E-12 i 7.07E-12 i La-140 1.10E-12 I 6.59E-09 I 7.18E-09 I 7.83E-09 I 8.53E-09 I 9.30E-09 I 1.01E-08 I 4.49E-12 I 4.89E-12 I Partic. 3 71E 06 I 1 13E+00 I 1 '3E+00 i 1.34E+00 i 1.46E+00 i 1.59E+00 I '1.74E+00 I 1.92E+00 I 2.10E+00 I I I I I I I I I I Total 1.26E+03 i 1.19E+03 I 1 15E+03 I 1.12E+03 I 1.10E+03 / 1.08E+03 I 1.06E+03 I 1 07 +03 I 1'06Ei03 I 10.2-12

Nine Nile Point Unit 2 1990 AnnUal Exercise Scenario No. 19, Rev. 1 TABLE 10.2.5-1 REACTOR BUILDING AIR SAHPLE ANALYSIS TOTAL CONCENTRATION uCI/ml I 00 00 I 00 15 00:30 oo:Cs 01:00 I 01:15 I 01:30 01:45 02:00 I 02:15 I NUCLIOE (06:30) (06:45> (07 00) I (07:15) I (07:30) I (07:45) I (08:00) (08:15) (08:30) I (08:45)

I-131 4.37E-12 I 4.37E-'l2 I 4.37E-12 I C.37E-12 I 4.37E-12 I 4.37E-12 I 4.42E-12 I 4.49E-12 I 4.60E-12 4.74E-12 I I

-132 8.00E-11 I 8.00E-11 I 8.00E-11 I 8.00E-11 I 8.00E-11 I 8.00E-11 8.07E-11 8.18E-11 8.33E-11 8.51E-'I'I I I I I

-133 6.00E-11 I 6.00E 11 I 6.00E-11 I 6.00E-11 6.00E-11 6.00E-11 6.06E-11 6.16E-11 6.30E-11 6.49E-11 I I I I I I I

-134 1 '0E-10 I 1.40E-'lo I 1.40E 10 I 1.40E 10 I 1 '0E 10 I 1 '0E-10 I 1.41E-10 I 1 '2E 10 I 1.44E 10 I 1 '6E 10 I

-135 6.00E-11 I 6.00E-'11 I 6.00E-11 I 6.00E-11 6.00E-11 I 6.00E-11 6.06E-11 6.16E-11 6.30E-11 6.48E-11 I I I I I I Iodines 3 44E 10 I 3.44E-10 I 3.44E-10 I 3.44E-10 I 3.44E-10 I 3.44E-10 I 3.47E-10 I 3.51E-10 I 3.58E-10 I 3.66E-10 I I I I I I I I I I I Kr-ssm 6.20E-10 I 6.20E-10 I 6.20E-10 I 6.20E-10 I 6.20E-10 I 6.20E-10 I 6.40E-10 6.60E-10 6.81E-10 7.02E-10 I I I I

-87 4.40E-10 I 4.40E-10 I 4 ~ coE-10 I 4.40E-10 I 4.40E-10 I 4.40E-10 I 4.57E-10 4.74E-10 4.91E-10 5.08E-10 I I I I

-SS 7.90E-10 7.90E-10 I 7.90E-10 7.90E-10 7.90E-10 7.90E-10 8.08E-10 8.26E-10 8.45E-10 8.63E-10 I I I I I I I I I Xe-133 I 2 29E 09 I 2.29E-09 I 2.29E-09 I 2.29E-09 I 2 '9E-09 I 2.29E-09 I 2.29E-09 I 2.29E-09 I 2.29E-09 I 2.29E-09 I

-135m I 1.27E-09 I 1.27E-09 I 1 '7E 09 I 1.27E 09 I 1 '7E 09 I 1 27 09 I 1 28E 09 I 1.30E 09 I 1.31E-09 I 1.32E-09 I

-135 2.71E-09 I 2.71E-09 I 2.71E-09 I 2.71E-09 I 2.71E-09 I 2.71E-09 I 2.73E-09 2.75E-09 2.77E-09 2.79E-09 I I I I

-138 1 '0E 10 I 1 50 10 I 1 ~ 50E-10 I 1.50E-10 I 1.50E-10 I 1.50E-10 I 1.54E-10 I 1.59E-10 I 1.63E-10 I 1.68E-10 I I Noble Gasl 8.27E.09 I 8.27E-09 I 8.27E-09 I 8.27E-09 I 8.27E-09 I 8.27E-09 I 8.36E-09 I 7.29E-09 I 8.55E-09 I 8.64E-09 I I I I I I I I I I I Te-132 I I

---

I

---

I

---

I

---

I 3.41E-20 I 9.70E-20 I 1.89E-19 I 3 ~ 09E-19 I Cs-134 8.95E-12 I 895E 12 I 8.95E-12 I 8.95E-12 I 8.95E-12 I 8.95E-12 I 8.95E-12 I 8.95E-12 I 8.95E-12 I 8.96E-12 I

-137 1 ~ 17E 11' 1 ~ 17E 11 I 1.17E-11 I 1.17E-11 I 1.17E-'l1 I 1.17E-11 I 1. 17E-11 1.17E-11 I 1.'17E-11 1 '8E-11 I I I Co-58 5.83E-13 I 5.83E-13 I 5 83E 13 I 5 83E 13 I 5 83E 13 I 5 83E 13 I 83E 13 I 5 83E 13 5 84E 13 '84E 1 I I I

-60 1.04E-11 I 1.04E-11 I 1.04E-11 I 1.04E-11 I 1.04E-11 I 1.04E-11 I 1.04E-11 I 1.04E-11 1.04E-11 1.04E-11 I I I Ce-141 1.62E"11 I 1.62E-11 I 1.62E-11 I 1.62E-11 I 1.62E-'11 I 1.62E-11 I 1.62E-11 I 1.62E-11 I 1.63E-11 I 1.63E-11 I Ba-140 2.91E-11 I 2'91E 11 I 2 91 11 I 2.91E 11 I 2.91 11 I 2.91E-11 I 2.91E-11 I 2.91E-11 I 2.91E-11 I 2.91E-11 La-140 I I

---

I

---

I

---

I

---

I 1.26E-18 I 3.39E-18 I 6.37E-18 I 1.02E-17 I Partic. 7.69E-11 I 7.69E-11 I 7.69E 11 I 7 69E 11 I 7 69E 11 I 7 69E 11 I 70E 11 I 7 70E 11 I 7 71E 11 I 'E 11 I I I I I I I I I I I Total 8.69E-09 I 8.69E-09 I 8.69E-09 I 8.69E-09 I 8.69E-09 I 8.69E-09 I 8.79E-09 I 7.72E-09 I 8.98E-09 I 9.09E-09 I 10.2-13

Nine Hile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 TABLE 10.2.5-1 REACTOR BUILDING AIR SAHPLE ANALYSIS TOTAL CONCENTRATION uCi/ml I I 02:30 I 02:45 03:00 I 03'15 I 03'30 I 03'45 04 F 00 I 04:15 I 04:30 I 04:45 I I NUCLIDE I (09:00) I (09:15) (09:30) (09:45) I (10:00) I (10:15) I (10:30) I (10:45) I (11:00) I (11:15) I I-131 4.98E-12 I 5.33E-12 I 5.87E.12 I 6.62E-12 I 7.55E-12 I 8.69E-12 I 1.00E-11 I 2.83E-08 1.13E-07 I 4.24E-07 I I

-132 8.81E-11 I 9.21E-11 I 9.79E-11 I 1.05E-10 I 1.14E-10 1.25E-10 1.37E-10 3.24E-09 1.25E-OS 4.65E-OS I I I I I I

-133 6.80E 11 I 7.25E-11 I 7.95E-11 8.89E-11 I 1.01E-10 1.15E-10 1.32E-10 I 1.92E-08 7.65E-OS 2.86E-07 I I I I I I

-134 1.49E 10 I 1.53E-10 I 1 E 10 1 63E 10 I 1.69E-10 1.76E-10 1.83E-10 3.14E-09 1.20E-OB 4.44E-OS I I I I I I I

-135 6.78E-11 I 7.21E-11 I 7.85E-11 I 8.72E-11 I 9.80E-11 I 1 ~ 11E-'lO 1 ~ 26E-10 9.93E-09 3.93E-OB 1.47E-07 I I I I I I lodines SE-10 I 3.95E-.10 I 4.19E-10 I 4 ~ 51E-10 I 4.90E-10 I 5.36E-10 I 5-BSE-10 I 6.38E-OB I 2.53E-07 I 9.48E-07 I I I I I I I I I I I Kr-85m 7.22E-10 I 7.43E-10 I 7.65E.10 I 7.86E-10 I B.OBE-10 I 8.30E-10 I 8'52E 10 I 2 95E 07 I 8'81E 07-I 2 85 06 I

-87 5.25E 10 I 5.43E-10 I 5.60E-10 I 5.78E-10 I 5-96E-10 6.14E-10 I 6.33E-10 I 2.48E-07 7.38E-07 I 2.38E-06 I I I

-SS 8.82E-10 I 9.01E-10 I 9.20E-10 I 9.39E-10 I 9.58E-10 I 9.78E-10 I 9.98E-10 I 6.07E-07 I 1.81E-06 I 5.85E-06 I Xe-133 2.29E-09 I 2.29E-09 I 2.29E-09 I 2.29E-09 I 2.29E-09 I 2.29E-09 I 2.29E-09 I 1.38E-05 I 4.13E-05 I 1.33E-04 I

-135m I 1.33E-09 I 1.35E-09 I 1.36E.09 I 1.37E-09 I 1.39E-09 I 1.40E-09 I 1.41E 09 I 3 67E 07 I 1.09E-06 I 3.53E-06 I

-135 281E 09 I 2.84E-09 I 2.86E-09 I 2.88E-09 I 2.90E-09 I 2.92E-09 I 2.95E 09 I 1.72E 06 I 5.15E-06 I 1.66E-05 I

-138 1.73E-10 I 1.77E-10 I 1.82E-10 I 1.87E-10 I 1.91E-10 I 1.96E-10 I 2.01E-10 I 1.90E-07 5.68E-07 I 1.84E-06 I I

I Noble GasI 8.73E-09 I 8.84E-09 I 8.94E-09 I 9.03E-09 I 6.58E-09 I 9.23E-09 I 7.27E-09 I 1.72E-05 I 5.15E-05 I 1.66E-04 I I I I I I I I I I I Te-132 5 25E 19 I 8.36E-19 I 1.33E-18 I 2.00E-18 I 2 85E 18 I 3 BBE 18 I 5.09E-18 I 5.02E-13 2 ~ 01E-12 7.55E-12 I I I Cs-134 8.96E-12 I 8.96E-12 I 8.96E-12 I 8.96E-12 I 8.97E-12 I 8.97E-12 I 8.97E-12 I 6.26E-11 I 2.24E-10 I 8.16E-10 I

-137 1.18E-11 .

I 1.18E-11 I 1.18E-11 I 1.18E-'ll I 1 18E 11 I 1 19E 11 I 1.19E-11 I 9.23E 11 I 3 35E 10 I 1.22E-09 I Co-58 5.85E-13 I 5.85E-13 I 5.86E-13 I 5.88E-13 I 5.90E-13 I 5.92E-13 I 5.94E-13 I 5.97E-13 I 6.00E-13 I 6.02E-13 I

-60 1 ~ 04E-11 1.04E-11 I 1.04E-11 1.04E-'ll I 1 '5E-11 I 1.05E-11 1.05E-11 1.05E-11 1.05E-11 1.05E-11 I I I I I I Ce-141 1.63E-11 I 1.63E-11 I 1.63E-11 I 1.63E-11 I 1.64E-11 I 1.64E-11 1 64E 11 I 1 64E 11 I 1 64E 11 I 1 65E 11 I Ba-140 2.91E-11 I 2.91E-11 I 2.92E-ll I 2.92E-11 I 2.92E-11 I 2.92E-11 I 2.92E-11 I 2.92E 11 I 2 92E-11 I 2 92E 11 I La-140 1.69E-17 I 2.64E-17 I 4.13E-17 I 6.15E-17 I 8.71E-17 I 1.18E-16 I 1 ~ 54E-16 I 1 90E 16 I 2.26E-16 I 2.62E-16 I Partic. 7.72E-11 7.72E-11 I 7.73E-11 I 7.73E-11 I 7.74E-11 I 7.74E-11 I 7.75E-11 I 2.12E-10 I 6.17E-10 I 2.10E-09 I I I I I I I I I I I Total 9 19E 09 I 9.31E-09 I 9.43E-09 I 9.56E-09 I 7 OBE 09 I 9 85E 09 I 7.94E-09 I 1.73E-05 I 5.18E-05 I 1.67E-04 I 10.2-14

Nine Nile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 TABLE 10.2.5-1 REACTOR BUILDING AIR SAHPLE ANALYSIS TOTAL CONCENTRATION uCi/ml I 05 00 I 05:15 I 05:30 I 05:45 I 06:00 I 06:15 I 06:30 O6:45 or:oo I NUcLIOE (11:30) I (11:45) I (12 00) I (12:15) I (12:30) I (12:45) I (13:00) I (13:15) I (13:30) I I-131 1.04E-06 I 1.74E-06 I 2.50E-06 I 3.32E-06 I 4.20E-06 I 5.12E-06 I 5.12E-06 I 5.11E-06 I 5.11E-06 I

-132 1.14E-07 I 1.90E-07 I 2 '2E-07 I 3.61E-07 I 4.55E-07 I 5.54E-07 I 5.13E-07 I 4.75E-07 I 4.40E-07 I

-133 7.05E-07 I 1 ~ 17E-06 I

'1.69E-06 I 2.24E-06 I 2.83E-06 I 3.45E-06 I 3.42E-06 I 3.39E-06 I 3.37E-06'

.134 1.09E-07 I 1.81E-07 I 2.59E-07 I 3.42E-07 I 4.29E-07 I 5.21E-07 I 4.26E-07 I 3.49E-07 I 2.86E-07 I

-135 2.66E-07 I 4.11E-07 I 9E 0 I 9E 07 I E 0 I 1'20E 0 I 1.17E-06 I 1.14E-06 I 1.11E-06 I I Iodines 2.23E-06 I 3.69E-06 I 5.30E-06 I 7.03E-06 I 8.89E-06 I 1.08E-OS I 1.06E-OS I 1.05E-OS I 1.03E-OS I I I I I I I I I I I Kr-85m 6.79E-06 I 1.05E-OS I 1.41E-OS I 1.75E-OS I 2.07E-OS I 2.38E-OS I 2 29E 05 I 2.20E-OS I 2.'12E-05 I

-87 5.68E-06 I 8.53E-06 I 1.10E-OS I

'1.31E-OS I 1.50E-OS I 1.65E-OS I 1.44E-OS I 1 26E 05 I 1 10E 05 I I 1.40E-OS I 2.15E-OS I 2.85E-OS I 3.51E-OS I 4.12E-OS I 4.68E-O I 4.4OE-OS I 4.14E-OS I 3.89E-OS I Xe-133 3.18E-04 I 5.01E-04 I 6.82E-04 I 8.61E-04 I 1.04E-03 I 1.21E-03 I 1.21E-03 I 1.21E-03 I 1.21E-03 I I -135m I 8.42E-06 I 1 '9E-05 I 1.22E-OS I 1.28E-OS I 1.31E-OS I 1.33E-OS I 6.83E-06 I 3.51E-06 I 1.80E-06 I I -135 I 3.97E-OS I 6.20E-OS I 8.38E-05 I 1.05E-04 I 1.25E-04 I 1.45E-04 I 1'43E 04 I 1 40E 04 I 1'37E 04 I I

-138 I 4.38E-06 I 5.77E-06 I 6.53E-06 I 6.94E-06 I 7.17E-06 I 7.30E-06 I 4.03E-06 I 2.22E-06 I 1.23E-06 I I Noble Gasl 3.97E-04 I 6.20E-04 I 8.38E-04 I 1.05E-03 I 1.26E-03 I 1.46E-03 I 1.45E-03 (

1.43E-03 I 1.42E-03 I I I I I I I I I Te-132 1.86E-11 I 4.09E-11 l7 E11 I115E10 I 166E101224E10 I 2.24E-10 I 2.23E-10 I 2.23E-10 I Cs-134 2.00E-09 (

4.37E-09 I 7.83E-09 I 1.23E-08 I 1.76E-OB I 2.38E-OB I 2 38E 08 I 2.38E-08 I 2.38E-08 I

-137 2.99E-09 I 6.57E-09 I 1 '8E-08 I 1.85E-OB I 2.66E-08 I 3.59E-OB I 3.59E-OB I 3 '9E-08 I 3.59E-OB I Co-58 6.05E-13 I 6.07E-13 I 6.10E-13 I 6.12E-13 I 6.15E-13 I 6.17E-13 I 6.17E-13 I 6.17E-13 I

-60 1.05E-11 I 1.05E-11 I 1.05E-11 I 1.05E-11 I 1.05E 11 I 1.06E-11 I 1.06E-11 I 1 '6E-11 I 1.06E-11 Ce-141 1.65E-11 I 1.65E-11 I 1.65E-11 I 1.65E-11 I 1.65Eiii I 1.66E-11 I 1.66E-11 I 1.66E-11 I 1.65E-11 Ba-140 2.92E-11 I 2.93E-11 I 2.93E-11 I 2.93E-11 I 2.93E-11 I 2.93E-11 I 2.93E-11 I 2.93E-11 I 2.93E-11 I La-140 2.98E-16 I 3'34E 16 I 3.70E-16 I 4.06E-16 I 4 41E 16 I 4.77E-16 I 4.75E-16 I 473E16 I 471E16 I Pattie 5.06E-09 1.10E-08 I 'l.98E-OB I 3 '0E-08 I 4.45E-OB I 6.00E-OB I 6.00E-OB I 6.00E-OB I 6.00E-08 I I I I I I I I I I Total 4.00E-04 I 6.25E-04 I 8.44E-04 I 1.06E-03 I 1.27E-03 I 1.47E-03 I 1.46E-03 I 1 44E 03 I 1.43E 03 I 10.2-15

Nine Mile Poin nit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 TABLE 10.2.6-1 STACK SAMPLE ANALYSIS TOTAL CONCENTRATION uCI/ml I 00 00 OO:1S 00:30 00:45 l 01:00 l 01:15 I 01:30 I 01:45 I 02:00 I 02:15 I l NUCLIDE (06:30) (o6:4s) I (07:00) I (07:15) I (07:30) I (07:45) (OS.OO) I (08'15) I (08:30) I (08:45)

I-131 2.64E-12 l 2.64E-12 l 2.64E-12 l 2.64E-I2 l 2.64E-12 l 2.64E-12 l 2.64E-12 I 2.64E-12 I 2.64E-12 I 2.63E-12 I

-132 4.00E-11 I 4.00E-11 I 4.00E-11 I 4.00E-11 I 4.00E-11 I 4.00E 11 I 3.71E-11 I 3.44E-11 I 3.18E-11 I 2.95E-11 I

-133 4.00E-11 I 4.00E-11 I 4.00E-11 I 4.00E-11 I 4.00E-11 I 4.00E-11 I 3.97E-11 3.94E-11 I 3.90E-11 I 3.87E-11 I I

-134 1.10E-10 I 1.10E-10 I 1.10E-10 I 1 10E 10 I 1.10E-10 I 1.10E-10 I 9.01E-11 7 38E 11 I 6 04 11 I 4 95E 11 I I

-135 4.00E-11 I 4.00E-11 l 4.0oE-11 I 4.00E-11 I 4.00E-11 l 4.00E-11 l 3.90E-11 l 3.80E-11 l 3.70E-11 l 3.61E-11 Iodines 2.33E-10 I 2.33E-10 I 2.33E-10 I 2.33E-10 l 2.33E-10 I 2.33E-10 I 2.08E-10 I 1.88E-10 I 1.71E-10 I 1.56E-10 I I I I I I I I I I I Kr-85m 1.43E-08 I 1.43E-OS I 1.43E-OS I 1.43E-OS I 1.43E-08 I 1.43E-08 I 1.43E-08 1.81E-11 I 1.74E-11 1.68E-11 I I I

-87 4.68E-08 l 4.68E-OS I 4.68E-08 l 4.68E-OS l 4.68E-OS l 4.68E-OS l 4.68E-08 1.06E-11 I 9.24E-12 8.05E-12 I I I

-88 4.68E-09 l 4.68E-09 I 4.68E-09 I 4.68E-09 I 4.68E-09 I 4.71E-09 I 4.71E-09 2.21E-11 I 2.08E-11 1.95E-11 I I I Xe-133 1.79E-09 I 1.79E-09 l 1.79E-09 l 1.79E-o9 1.79E-09 1.86E-09 l 1.86E-09 7.32E-11 I 7.31E-11 7.30E-11 I

-135m l I I I

-- l I I 4.02E-11 I 2.06E-11 I

l 1.06E-1'I l 5.44E-12 I

l 2.79E-12 l

-135 5 ~ 11E-08 I 5.11E-OS I 5 ~ 11E-08 I 5.11E-OS I 5.11E-OS I 5.12E-08 I 5.12E-08 8.26E-11 I 8.10E-11 7.95E-11 I I I

-138 I I I

---

I I 4.74E-12 I 2.62E-12 I 14E12 I 98E13 I 441E13 I l Noble Gas l 1 ~ 19E-07 I 1.19E-07 l 1.19E-07 I 1.19E.07 I 1.19E-07 I 1.19E.07 I 1.19E-07 2.19E.10 2.08E-10 2.00E-10 I I I I Te-'132 I

I I

I I

I

---

I I

I I

-- I I

I I

I I

--- I I

---

I I

Cs-134 4.22E-14 I 4.22E-14 l 4.22E-I4 I 4.22E-14 I 4.22E-14 I 4.22E-14 I 4.22E-14 I 4.22E-14 I 4.22E-14 I 4.22E-14 I

-137 2.11E-13 l 2.11E-13 l.2.11E-13 I 2 11E 13 I 2.11E-13 I 211E13 I 2 ~ 11 13 I 2'l1E 13 I 2 11E 13 I 2 ~ 11E 13 I Co.58 2.11E-13 I 2.11E-13 I 2.11E-13 I 2.11E-13 I 2.11E-13 I 2.11E-13 I 2.11E-13 2.11E-13 2.11E-13 2.11E-13 I I I I

-60 2.11E-13 l 2.11E-13 I 2.11E-13 l 2.11E-13 l 2.11E-13 2.11E-13 2.11E-13 2'11E 13 2 11E 13 2'11E 13 I I I I I I Ce-141 2.11E-12 l 2.11E-12 l 2.11E-12 l 2.11E-12 l 2.11EI12 I 2 11E 12 I 2.11E-12 I 2.11E-12 I 2.11E-12 I 2.11E-12 I Ba-140 2.11E-12 I 2.1'IE-12 I 2 11E 12 l 2.11E-12 l 2 ~ 11E-12 La-140 I I I

-- I I

I 2.11E-12

I l

2.11E-12 I I

2 ~ 11E-12

-- -

I I

2.11E-12

---

I I

2.11E-12

---

I I

Partic. 4.89E-12 I 4.89E-12 I 4.89E-12 I 4.89E-12 I 4.89E-12 I 4.89E-12 I 4.89E-12 I 4.89E-12 I 4.89E 12 I 4.89E-12 I I I I I I I I I I I Total 1 ~ 19E-07 I 1 '9E-07 l 1.19E-07 I 1.19E-07 I 1.19E-07 I 1.19E-07 I 1.19E-07 I 4.12E-10 I 3.84E-10 I 3.61E-10 I 10.2-16

Nine Nile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 TABLE 10.2.6-1 STACK SAHPLE ANALYSIS TOTAL CONCENTRATION uCI/mi I 02:30 (09:00) 02:45 (09:15) 03:00 (09:30)

I 03:15 03:30 I, 03:45 04:00 04:15 04:30 04:45 I NUCLIDE I (09:45) (10'00) I (10'15) (10:30) (10:45) (>>:00) (>>'15) I I-131 2.63E-12 I 2.63E-12 I 2.63E-12 I 2.62E-12 I 2.62E-12 I 2.62E-12 I 2.62E-12 2.61E-12 2.61E-12 2.61E-12 I I ( I

-132 2.73E->> I 2.53E->> I 2.34E->> I 2.17E->> I 2.01E->> I 1.86E->> I 1.72E->> I 1.60E->> I 1.48E-1'I (

1.37E->> (

-133 3.84E->> I 3.80E->> I 3.77E->> I 3.74E->> I 3.71E->> I 3.68E->> I 3.64E->> I 3.61E->> I 3.58E->> (

3.ssE->> (

-134 4.05E->> I 3.32E->> I 2.72E->> I 2.22E->> I 1.82E->> I 1.49E->> I 1.22E->> I 9.99E-12 I 8.18E-12 I 6.70E-12 I

-135 3 '2E->> I 3.43E->> I 3.34E->> I 3.25E->> I 3.17E->> (

3.09E->> I 3.01E->> I 2.93E->> I 2.86E->> I 2.78E->> I lodines 1.44E-10 I 1.33E-10 I 1.24E-10 I 1 '6E-10 I 1.10E-10 I 1.04E-10 I 9.86E->> I 9.40E->> I 9.00E->> (

8.64E->>

I I I I I I I I I I Kr-85m 1.61E->> I 1.55E->> I 1.49E->> I 1.43E->> I 1.38E->> I 1.32E->> I 1.27E->> I 1.22E->> I 1 ~ 18E->> I 1 ~ 13E>> I

-87 7.02E-12 6.13E-12 5.34E-12 4.66E-12 4.06E-12 3.54E-12 3.09E-12 2.70E-12 2.35E-12 05E-12 I I ( I I ( I I I 2 I

-88 1.83E->> 1.72E->> 1.62E->> 1.52E->> 1.43E->> 1.35E->> 1.27E->> 1.19E->> 1 ~ 12E-'>> 1.0SE->>

I I I I I I I I ( (

Xe-133 7.29E->> I 7.28E->> I 7.27E->> I 7.26E->> I 7.25E->> I 7.24E->> I 7.23E->> I 7.22E->> I 7.21E->> I 7.20E->> I

-135m I 1 '3E-12 I 7 37E 13 I 3 78E 13 I 1 94E 'l3 I 9 98E 14 I 5 12E 14 I 2 63E 14 I 1 3 E 14 I 6 94E 1 I 3.56E-15 I

-135 I 7.80E->> I 7.65E->> I 7.51E->> I 7.37E->> I 7.23E->> I 7.09E->> I 6.96E->> I 6.83E->> I 6.70E->> I 6.58E->> I

-138 I 2.43E-13 I 1.34E-13 I 7.42E-14 4.09E-14 I 2.26E-14 1.25E-14 6.89E-15 3.80E-15 2.10E-15 1.16E-15

( ( ( I I I I I Noble Gas( 1.94E-10 1.89E-10 I 1.85E-10 I 1.81E-10 I 1.77E-10 1.74E-10 1.70E-10 'l.67E-10 1.64E-10 1.62E-10 I

I, ---

( I ( I I

'

I I I I I I I I Te-132 I I I I I I I I I I Cs-134 4.22E-14 I 4.22E-14 I 4 22E 14 I 4.22E-14 I 4.22E-14 I 4.22E-14 I 4.22E-14 I 4.22E-14 I 4.22E-14 I 422E14 I

-137 2.>>E-13 I 2.'l1E-13 I 2.>>E-13 I 2.>>E-13 I 2.>>E-13 (

2.>>E-13 I 2.>>E-13 I 2.>>E-13 I 2.'l1E-13 (

2.>>E-13 I Co-58 2.>>E-13 I 2>>E 'l3 I 2>>E 13 I 2.>>E 13 I 2.1'IE 13 I 2>>E 13 I 2 >>E 13

~

I 2.>>E-13 I 2.>>E-13 I 2 l1E 13 I

-60 2.>>E-13 I 2'>> 13 I 2>>E 13 I 2.>>E-13 I 2>>E 13 I 2.>>E-13 I 2.>>E-13 I 2>>E 13 I 2.>>E-13 I 2.>>E-13 I Ce-141 2.>>E-12 I 2>>E 12 I 2>>E 12 I 2.>>E-12 I 2.>>E-12 I 2.>>E-12 I 2.10E-12 I 2.10E-12 I 2.10E-12 I 2.10E-12 I Ba-140 2.10E-12 I 2 10E 12 2 10E 12 2 10E 12 I 2.10E 12 I 2.10E-12 I 2 10E 12 2.10E 12 2 09E 12 I 2.09E-12 I La-140 I

---

I I

--- I I

--- I

---

I

--- I

- -

I I

--- I I I

---

I Partic. 4.89E.12 I 4.89E-12 I 4.88E-12 I 4.88E-12 I 4.88E-12 I 4.88E-12 I 4.88E-12 I 4.88E-12 I 4.87E-12 I 4.87E-12 I I I I I I I I I I I Total 3.43E-10 I 3.27E-10 I 3.14E-10 I 3.02E-10 I 2.92E-10 I 2.82E-10 I 2.74E-10 I 2.66E-10 I 2.59E-10 I 2.53E-10 I 10.2-17

Nine Mile Poin it 2 1990 Annual Exercise Scenario No. 19, Rev. 1 TABLE 10.2.6-1 STACK SAMPLE ANALYSIS TOTAL CONCENTRATION uCi/ml I 05:00 05:15 ( 05:30 05 45 06:00 I 06:15 06:30 o6:45 O7-OO I NUCLIDE (11:30) (11:45) I (12'00) I (12t15) (12:30) I (12:45) (13:00) I (13:15) I (13:30)

I-131 8.52E-04 (

1.29E-03 (

1.41E-03 (

1.53E-03 (

1.64E-03 (

1.74E-03 (

1.85E-03 (

2.59E-'l2 (

2.59E-12 (

-132 1.20E-03 (

1.78E-O3 I 1.94E-03 I 2.09E-03 I 2.23E-03 I 2.37E-03 I 2.51E-03 I 7.41E-12 6.87E-12 I I

-133 1.80E-03 I 2.71E-03 I 2.97E-03 I 3.21E-03 3.44E-03 3.67E-03 I 3.88E-03 3.32E-11 3.29E-11 I I I I I

-134 1.64E-03 I 2 36E 03 I 2.55E-03 I 2.73E-03 I 2.90E-03 I 3.07E-03 I 3.23E-03 I 1.35E-12 1.11E-12 I I

-135 1.56E-03 I 3.00E-03 (

3.40E-03 (

3.79E-03 4'.16E-03 4.52E.03 (

4.87E-03 2.26E-11 2.20E-11

( ( ( ( (

Iodines 7.05E-03 I 1 '1E-02 I 1.23E-02 I 1.33E-02 I 1.44E-02 I 1.54E-02 (

1.63E-02 I 6.72E-11 (

6.55E-11 I I I I I I I I I I Kr-85m 3.47E-01 I 1.36E+00 (

1.20E+00 (

1.08E+00 (

9.90E-01 (

9.19E-01 (

8.50E-01 8.25E-12 7.93E-12

( ( (

-87 4.96E-01 (

1.93E+00 (

1.71E+00 (

1.54E+00 (

1.42E+00 ( 1.31E+00 (

1.21E+00 6.86E-13 5.99E-13

( ( (

-SS 8.71E-01 I 3.38E+00 3 DOE+00 I 2 TOE+00 I 2 49E+00 I 2 29E+00 I 2'12E+00 6 41E-12 6.02E-12 I I I (

Xe-133 2.84E+00 ( 1 ~ 11E+Ol I 9.80E+00 I 8.83E+00 I 8.14E+00 I 7.50E+00 I 6.94E+00 I 7.12E-11 I 7.11E-11

-135m (

4.09E-01 (

1.60E+00 I 1.43E+00 I 1.28E+00 I 1.18E+00 1.09E+00 (

1.DOE+00 I I

( I

-135 4.66E-01 (

1.81E+00 (

1.60E+00 (

1.45E+00 (

1.34E+00 1.23E+00 1.14E+00 5.65E-11 5.54E-11

( ( ( (

-138 5.73E-01 (

2.23E+00 (

1.98E+00 (

1.78E+00 (

1.65E+00 (

1.52E+00 ( 1.40E+00 (

(

Noble Gas( 6.DOE+00 ( 2.34E+01 I 2 07E+01 I 1.87E+01 I 1 72E+01 I l 59E+01 I 1 47E+01 I 1 43E 10 I 1 41E 10 I I I I I I I I I I Te-132 6.65E-04 (

7.50E-04 I 8.17E-04 I 8.91E-04 I 9.71E-04 I 1.06E-03 I 1.15E-03 I

---

I

---

I Cs-134 6.83E-04 (

7.92E-04 I 8.64 -04 (

9.42E-04 I 1.03E-03 I 1.12E-03 I 1.22E-03 I 4.22E-14 I 4.22E-14 I

-137 1.02E-03 I 1.20E-03 I 1 31E-03 I 1.43E-03 I 1 '6E-03 I 1.70E-03 I. 1.85E-03 I 2.11E-13 I 2 11E 13 I Co-58 5.40E-13 I 1.08E-11 1 ~ 17E-11 (

1.27E-11 (

1.38E-11 (

1.50E-11 ( 1.63E-11 (

2.11E-13 (

2.11E-13 (

-6o 1.43E-12 (

2.46E-11 I 2.66E-11 (

2.89E-11 I 3.14E-11 3.41E-11 ( 3.70E-11 2 '1E-13 2.'l1E-13 I I I I Ce-141 4.43E-12 I 6.15E-12 I 6.28E-12 (

6.43E-12 I 6.60E 12 I 6 78E 12 I 6 98E 12 I 2.10E-12 I 2 '0E-12 (

Ba-140 3.65E-12 I 2.67E-11 I 2.88E-11 I 3.11E-11 I 3.35E-11 I 3.62E-11 I 3.91E-11 I 2.08E-12 I 2.08E-12 I La-140 4.65E-13 I 1.65E-11 I 1.79E-11 I 1.95E-'l1 (

2.12E-11 I 2.30E-11 I 2.5'IE-11 I

---

I

---

(

Partic 2.37E-03 I 2.74E-03 (

2.99E-03 I 3.26E-03 I 3.55E-03 I 3.87E-03 ( 4.22E-03 I 4.86E-'l2 (

4.86E-12 (

I I I I I I I I I Total 6.01E+00 (

2.34E+01 I 2.07E+01 I 1.87E+Ol (

1.72E+01 I 1 ~ 59E+01 I 1.47E+01 (

2.15E-10 (

2.12E-10 I 10.2-18

Nine Mile Point Unit 2 1990 Annual Exercise Scenario Ho. 19, Rev. 1 TABLE 10.2.7 VENT SAMPLE ANALYSIS TOTAL CONCENTRATIOH uCi/ml I I 00:00 I 00:15 I 00:30 I 00:45 I 01:00 I 01:15 I 01:30 I 01:45 I 02:00 I 02:15 I I NUCLIDE (o6:3o) I (o6:4s) I (07:00) I (07:15) I (07:30) I (07:45) I (08:00) I (08'15) I (08'30) I (08'45) I I-131 4.93E-12 I 4.93E-12 I 4.93E-12 I 4.93E-12 I 4.93E-12 I s.78E-12 I s.78E-12 I 5.78E-12 I 5.78E-12 I 5.78E-12 I

-132 4.85E->> I 4.85E->> I 4.85E->> I 4.85E->> I 4.85E->> I 1.00E-12 I 1.00E-12 I 1 ~ OOE-12 I 1.00E-12 I 1.ooE-12 I

-133 3.92E->> I 3 92E >> I 3.92E->> I 3.92E->> I 3.92E->> I 7.87E-12 I 7 87E 12 I 7.87E-12 I 7.87E-12 I 7.87E-12 I

-134 8.49E->> I 8.49E->> I 8.49E->> I 8.49E->> I 8.49E->> I 1.86E-12 I 1.86E-12 I 1.86E-12 I 1.86E-12 I 1.86E-12 I

-135 3.92E->> I 3 92E >> I 3.92E->> I 3.92E->> I 3.92E->> I 7.87E-12 I 7.87E-12 I 7.87E-12 I 7.87E-12 I 7.87E-12 I Iodines 2.17E-10 I 2 17E 10 I 2.17E-10 I 2.17E-10 I 2.17E-10 I 2.44E>> I 2.44E->> I 2.44E->> I 2.44E->> 2.44E->> I

.

I I I I I I I I I I I

-

I Kr-85m 3.73E-10 I 3.73E-10 I 3.73E-10 I 373E 10 I 3.73E-10 I I

--- I I

---

I I I

-87 2.64E-10 I 2.64E-10 I 2.64E-10 I 2.64E-10 I 2.64E-10 I I

---

I

---

I I I -88 4.75E-10 I 4.75E-10 I 4.75E-10 I 4.75E-10 I 4.75E-10 I I

- -

I I I

--- I I I Xe-133 1.38E-09 I 1.38E-09 I 1.38E-09 I 1.38E-09 I 1.38E-o9 I 3.27E-13 I 3.27E-13 I 3.27E-13 I 3.27E-13 I 3.27E-13 I I

-135m I 7.63E-10 I 7.63E-10 I 7.63E-10 I 7.63E-10 763E 10 I I

--- I

--- I I

-135 I 1.63E-09 I 1.63E-09 I 1.63E-09 I 1.63E.09 I

I 1.63E-09 I I

---

I I

--- I I

I -138 9.02E->> I 9.02E->> I 9.02E->> I 9.02E->> I 9.02E->> I I

--- I I I

--- I I

I I Noble Gasl 4.97E-09 I 4 97E 09 I.4.97E-09 I 4.97E-09 I 4-97E-09 I 3.27E-13 I 3.27E-13 I 3.27E-13 I 3.27E-13 I 327E13 I Te-132 I

I I I

I I

I I

I I I I

--- I I I I

-- I I

I I

Cs-134 5.92E-12 I 5.92E-12 I 5.92E-12 I s.92E-12 I 5.92E-12 I 1.36E-12 I 1.36E-12 I 1 36E 12 I 1 36E 12 I 1.36E-12 I

-137 7.95E-12 I 7.95E-12 I 7.95E-12 I 795E 12 I 7.95E-12 I 2 29E 12 I 2.29E-12 I 2.29E-12 I 2.29E-12 I 2'29E 12 I Co-58 3.96E-13 I 3.96E-13 I 3.96E-13 I 3.96E-13 I 3.96E-13 I 1.15E-13 I 1.15E-13 I 1.15E-13 I 1.15E-13 I 1.15E-13 I

-60 7.85E-12 I 7.85E-12 I 7.85E-12 I 7.85E-12 I 7.85E-12 I 4.01E-12 I 4.01E-12 I 4 ~ 01E-12 I 4.01E-12 I 4.o1E-12 I Ce-14'I 9.74E-12 I 9.74E-'12 I 9.74E-12 I 9.74E-12 I 974E 12 I 4.01E-15 I 4.o1E-15 I 4 ~ 01E-15 I 4:01E-15 I 4.01E-15 I Ba-140 1.75E->> I 1.7sE->> I 1.75E>> I 1 75E->> 1.75E->> 2.29E-15 I 2.29E-15 I 2.29E 15 2.29E 15 I 2.29E-15 I LQ-140 I I I I

I I

I I

--- I I

I

--- I I Partic. 4.93E->> I 4.93E->> I 4'93E>> I 4.93E->> I 4.93E->> I 7.78E-12 I 7.78E-12. I 7.78E-12 I 7 78E 12 I 7.78E-12 I I I I I I I I I I I Total 5.24E-09 I 5 ~ 24E-09 I 5 '4E-09 I 5.24E.09 I 5.24E-09 I 3.2sE->> I 3.2sE->> I 3.25E->> I 3.25E->> I 3.2sE->> I 10.2-19

Nine I(lie Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 TABLE 10.2.7 VENT SANPLE ANALYSIS TOTAL COHCEHTRATIOH uCI/ml I 02:30 oz-4s I 03:00 03:15 I 03'30 I 03'45 04-00 I 04:15 I 04:30 I 04'45 I NUCLIDE I (09'00) I (09'15) (09:30) (09-45) I (10:00) I (10:15) I (10'30) I (10:45) I (11:00) I (11:15) I I -131 5.78E-12 I 5 78E-12 I 5.78E-12 I 5.78E-12 I 5.78E-12 I 5.78E-12 I 5.78E-12 I 5.78E-12 I 5.78E-12 I 5.78E-12 I

-132 1.00E-12 I 1.00E-12 I 1.00E-12 I 1 ~ OOE-12 I 1.00E-12 I 1.00E-12 I 1 'OE-12 I 1 00E-12 I 1.00E-12 I 1.00E-12 I

-133 7.87E-12 (

7.87E-12 (

r.are-lz (

7.87E-12 I 7.87E-12 I 7.87E-12 I 7.87E-12 I 7 87E 12 (

7.87E-12 (

7.87E-12 (

-134 1.86E-12 (

1.86E-12 (

1.86E-12 I 1.86E-12 I 1.86E-12 I 1.86E-12 (

1.86E-'l2 I 1.86E-12 (

1.86E-12 (

1.86E-12 (

-135 7.87E-12 (

7.87E-12 (

7.87E-12 (

7.87E-12 (

r.arE-lz (

7.87E-12 I 7.87E-12 I 7.87E 12 (

7.87E-12 (

7.87E-'l2 (

lodines 2.44E-11 I 2.44E-11 I 2 44E 11 I 2.44E-11 I 2.44E-11 I 2 '4E-11 I 2.44E-'l1 I 2.44E-11 (

2.44E-11 (

2.44E-11 I I I I I I I I I I Kr-asm I

- I I

---

I I

--- -

-ar I

- - --- I I

---

I

---

I

-88 I

I I

I

--- I I

I I

-- I I

I I

I I

I I

---

I I

---

I I

3 '7E-13 Xe-133

-135m (

3.27E-13 I I

3.27E-13 (

I 3.27E-13

---

---

(

I 3.27E-13 I I

3.27E-13

--

---

(

I 3.27E-13 I I

3.27E-13 I I

3.27E-13 I I

3.27E-13

---

---

I I

--

---

I I

-135 I I I I I

-138 I

I I

--- I I I

-- I I I I

I

---

I I

---

I I

( Noble Gas( 3.27E-13 I 3 27E 13 I 3.27E-13 I 3.27E-13 I 3.zrE-13 (

3.27E-13 I 3.27E-13 I 3.27E-13 ( 3 '7E-13 (

3.27E-13 (

I I I I I Te-132 I I

--- I I

I

--- I I I I

I I

---

I I

---

I I

Cs-134 1.36E-12 I 1.36E-12 I 1.36E-12 I 1.36E-12 I 1.36E-12 I 1.36E-12 I 1.36E-12 I 1.36E-12 I 1.36E-12 I 1.36E-12 I

-137 2.29E-12 I 2.29E-12 (

2.29E-12 (

2.29E-12 I 2.29E-12 I 2.29E-12 I 2.29E-12 (

2.29E-12 I 2.29E-12 I 2.29E-12 I Co-58 1.15E-13 I 1.15E-13 I 1.15E-13 I 1.15E-13 (

1.1se-13 (

1.15E-13 I 1.15E-13 I 1.15E-13 I 1.15E-13 I 1.15E-13 I

-60 4.01E-12 I 4.01E-12 (

4.01E-12 (

4.01E-12 (

4.04E-12 (

4.01E-'I2 I 4.01E-12 I 4.01E-12 I 4.01E-12 I 4.01E-12 I I

Ce-141 4.01E-15 I 4.01E-15 I 4.01E-15 I 4.01E-15 I 4.01E-15 I 4.01E-15 I 4.01E-15 I 4.01E-15 I 4.01E-15 I 4.01E-15 I Ba-140 2.29E-15 2.29E-15 I 2.29e-ls 2.29E-15 I 2.29E-15 I 229E15 I 2.29E-'l5 2.29E-15 I 2.29E-15 I 2.29E-15 I l.a-140 I

I I

--- (

I I

--- I I I

I I

---

I

--- I Part'Ic ~ 7.78E-12 I 7.78E-12 (

7.78E-12 (

7.78E-12 (

7.78E-12 (

7.78E-12 I 7.78E-12 I 7.78E-12 I 7.78E-12 I 7.78E-12 I I I I I I I I I I I Total 3.25E-11 (

3.zse-11 I 3.25E-11 I 3.25E-11 I 3.25E-11 I 3 25E 11 I 3.25E-11 (

3.2se->> I 3.25E-11 I 3.25E-11 I 10.2-20

Nine Nile Point Unit 2 1990 Annual Exercise Scenario Ho. 19, Rev. 1 TABLE 10.2.7 VENT SAHPLE ANALYSIS TOTAL CONCEHTRATIOH uCI/mi I os-oo OS-1S 05:30 I 05-45 I 06:00 I 06:15 I 06:30 06:45 ( 07:00 I NUCLIDE I (11:30) I (11:45) I (12:00) I (12:15) I (12:30) I (12:45) I (13:00) I (13'15) I (13:30) I ABODE-12 I-131 5.78E-12 I 5.78E-12 (

s.rsE-12 I 5.78E-12 I 5 78E-12 I 5.78E-12 I 5.78E-12 (

5.78E-12 (

5.78E-12 (

-132 1.00E-12 I 1.00E-'l2 (

1.OOE-12 I 1 1.OOE-12 (

1.00E-12 I 1.00E-12 I 1.00E-12 I 1 ~ OOE-12 (

-133 7.87E-12 I 7.87E-12 (

7.87E-12 (

7.87E-12 (

7.87E-12 (

7.87E-12 I 7.87E-12 (

r.srE-12 (

7.87E-12 I

-134 1.86E-12 (

1.86E-12 (

1.86E-12 (

1.86E-12 1.86E-12 (

1.86E-12 (

1.86E-12 (

1.86E-12 (

1.86E-12 (

-135 r.srE-12 (

7.87E-12 I 7.87E-12 (

7.87E-12 (

r.srE-12 (

7.87E-12 (

7.87E-12 I 7.87E-12 I 7.87E-12 I

( Iodines 2.44E-11 I 2.44E-11 I 2.44E-11 I 2.44E-11 I 2.44E-11 I 2.44E-11 I 2.44E-11 (

2 '4E-11 2.44E-11 I Kr-85m I

I I

I I

I I

I

---

---

I I

I I

I I

--

---

I I

I I

-87 I I I I I I I I I

-88 I I I I

---

I I I

---

I I Xe-133 135m I 3.27E-13 I I

3.27E-13 I I

3.27E-13 I I

3.27E-13 I

--

--- I 3.27E-13 I I

3.27E-13 I I

3.27E-13

---

---

I I

3.27E-13 I I

-135 I I I I I I I I I I 138 I I I I I

---

I I I

---

I I

( Noble Gas( 3.27E-13 (

3.27E-13 I 3.27E-13 (

3.27E-13 (

3.27E-13 (

3.27E-13 (

3.27E-13 I 3.27E-13 I 3.27E-13 (

I I I I I I I I I Te-132 I I I I

---

I I I

---

I I

(= Cs-134 1.36E-12 I 1.36E-12 I 1.368-12 I 1.36E-12 I 1.36E-12 I 1.36E-12 I 1.36E-12 I 1.36E-12 I 1.36E-12 I I -137 2.29E-12 I 2.29E-12 (

2.29E-I2 I 2.29E-12 I 2.29E-12 I 2.29E-12 I 2.29E-12 (

2.29E-12 ( 2.29E-12 I Co-58 1.15E-13 I 1.15E-13 I 1.15E-13 (

1.1SE-13 I 1 ~ 15E-13 I 1.15E-13 I 1.15E-13 I 1.15E-13 I 1.1SE-13 (

-60 4.01E 12 I 4.01E-12 I 4.01E-12 I 4.01E-12 I 4.01E-12 (

4.01E-12 I 4.01E-12 I 4.01E-12 I 4.01E-12 I Ce-141 4.01E-15 I 4.01E-15 I 4 ~ 01E-15 (

4.OIE-1S I 4.01E-15 I 4.01E-15 I 4.01E-15 (

4.01E-15 4.01E-15 I Ba-140 2.29E-15 2.29E-15 2.29E-15 2.29E-15 2.29E-15 2.29E-15 2.29E-15 2.29E-15 2.29E 15 La-140 I

I I

I I

I I

I

---

I I

I I

I I

-- I I

I I

Partic. 7.78E-12 I 7.78E-12 I 7.78E-12 I 7.78E-12 I 7.78E-12 I 7.78E-12 I 7.78E-12 I 7.78E-12 I 7.78E-12 I I I I I I I I I I Total 3.25E-11 I 3.25E-11 (

3.2SE-11 I 3.25E-11 (

3.2SE-11 (

3.25E-11 I 3.25E 11 I 3.25E-11 I 3 25E 11 I 10.2-21

Nine Hiie Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 TABLE 10.2.8 TURBINE BUILDING AIR SAHPLE ANALYSIS TOTAL CONCENTRATION uCi/ml I

OO.OO i OO-15 I 00:30 I 00:45 I 01:00 I 01:15 I 01:30 I 01:45 I 02:00 I 02:15 I

/ NUCLIDE (06:30) J (06:45) (O7:OO) I (07:15) I (07:30) I (07:45) I (08:00) I (08:15) I (08'30) I (08'45) I I-131 I 2 64E 12 I 2'64E 12 / 2.64E-12 I 2.64E 12 i 2.64E-12 f 2.64E-12 /

2.64E-12 i 2.64E-12 )

2.63E-12 I 2.63E-12 i

-132 I 4 ~ OOE->> I 4.00E->> I 4.00E->> I 4.00E->> I 4.00E->> I 4.00E->> I 3.70E->> I 3.43E->> I 3.18E->> 2.94E->> I

-133 J 4.00E->> (

4.00E->> I 4.00E->> I 4.00E->> I 4.00E->> i 4.00E-1'I i 3.97E->> I 3.93E->> I 3.90E->> I 3.87E->> I

-134 I 1.10E-10 I 1.10E-10 I 1 10E 10 I 1 ~ 10E-10 I

'l.10E-10 1.10E-10 9.01E->> 7.37E->> 6.04E->> 4.94E->>

I I I I I I

-135 I 4.00E->> I 4.00E->> I 4.00E->> I 4 ~ OOE->> I 4.00E->> f 4.00E-'>> I 3.90E->> I 3.80E->> I 3.70E->> I 3.61E->> I Iodines I 2.33E-10 I 2.33E-10 / 2.33E-10 I 2.33E-10 I 2.33E-10 I 2.33E-10 I 2.08E-10 / 1.88E-10 f 1.71E-10 I 1.56E-10 I I I Kr-85m I

--- I I I I

I I I

--- '

I I I

-87 I

--- I I

I I I I

I I

I I I

--- I I I

-88 I

--- I I I I I I

I I

I

--- I I

I I

I

-135m I --

Xe-133 i 9.67E-13 i 9.67E-13 I

[

I 9.67E-13 ]

I 9.67E-13 I I

967E 13 I I

9 67E 13 i 9.66E-13 I

/

I 9.64E-13

--- / 9.63E-13 i I

9.62E-13 I

-135 I -

I

--- I I

-138 I

--- I I I I

I I

I I

I I

I I

I

---

I I

I I

I I

) Noble Gas [ 9.67E-13 )

'9.67E-13 I 9.67E-13 I 967E 13 I 9.67E-13 I 9.67E-13 I 9 66E 13 / 9.64E-13 )

9.63E-13 I 9.62E-13 I I I I Te-132 I

--- I I I

I I I I I

I I

I I

--- I I

I I I I

Cs-134 I 4.22E-14 I 4.22E-14 I 4.22E-14 I 4.22E-14 I 4.22E-14 / 4.22E-14 I 4.22E-14 I422E14 I 4 22E 14 I 22E 14 I

-137 I 2.>>E-13 I 2.>>E-13 I 2>>E13 I 2.>>E-13 I 2>>E13 I 2.>>E-13 I 2.>>E-13 I2>>E13 I 2.>>E-13 I 2>>E13 I Co-58 l 2>> 13 I 2>>E 13 I 2.>>E-13 I 2.>>E-13 I 2.>>E-13 I 2.>>E-13 i 2.>>E-13 (

2.>>E-13 ] 2.>>E-13 I 2.>>E-13 I

-60 I 2>>E 13 I 2.>>E-13 I 2.'11E-13 I 2.>>E-13 I 2.11E-13 ) 2.>>E-13 I 2.>>E-13 [ 2.>>E-13 [ 2.>>E-13 I 2.>>E-13 I Ce-141 I 2>>E 12 I 2>>E 12 I 2.>>E-12 )

2.>>E-12 I 2.>>E-12 I 2>>E12 I 2.>>E-12 I 2>>E12 I 2.>>E-12 I 2>>E12 I Ba-140 I 2.>>E 12 I 2.>>E-12 i 2.'I'IE-12 / 2.>>E-12 I 2.>>E-12 ] 2.iiE-12 I 2.>>E-12 I 2>>E12 I 2>>E12 2.>>E-12 i La-140 I

- I I I I I I I

--- I I

I I Partic. I 4.90E-12 I 4.90E-12 i 4.90E-12 )

4.90E-12 I 4.90E-12 I 4.90E-12 I 4.89E-12 I 4.89E-12 I 4.89E-12 )

4.89E-12 [

I I I I I I I I I I I Total ] 2.39E-10 ] 2.39E-10 I 2.39E-10 I 2.39E-10 i 2.39E-10 I 2.39E-10 I 2.14E-10 i 1.94E-10 (

1.77E-10 ] 1.62E-10 I 10.2-22

Nine Hile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 TABLE 10.2.8 TURBINE BUILDING AIR SAHPLE ANALYSIS TOTAL CONCENTRATION uCI/mi I 02:30 J 02:45 I 03:00 I 03:15 I 03:30 I 03:45 I 04:00 I 04:15 I 04:30 I 04:45 I I NUCLIDE I (09:00) I (09:15) I (09:30) I (09:45) I (10:00) I (10:15) I (10:30) I (10:45) I (11:00) I (11:15) I I-131 2.63E-12 I 2.63E-12 I 2 62E 12 I 2 62E 12 I 2.62E-12 I 2 62E 12 I 2.61E-12 I 2.61E-12 I 2.61E-12 I 2.61E-12 I

-132 2.73E-11 I 2.52E-11 I 2 34E 11 I 2 17E 11 I 2.01E-11 1.86E-11 I 1.72E 11 I 1.59E-11 I 1.48E-11 I 1.37E-11 I

-133 3.83E-11 I 3.80E-11 i 3.77E-11 I 3.74E-11 I 3.70E-11 i 3.67E-11 f 3.64E-11 f 3.61E-11 )

3.58E-11 / 3.55E-11

-134 4.05E-11 I 3.31E-11 J 2.71E-11 I 2.22E-11 i 1.82E-11 I 1.49E-11 I 1.22E-11 I 9.99E-12 I 8.18E-12 I 6.69E-12 I

-135 3.51E-11 I 3.42E-11 I 3.34E-11 I 3.25E-11 ( 3.17E-11 I 3.09E-11 I 3 01E 11 I 2 93E 11 I 2.85E-'I1 I 2.78E-11 I Iodines 1.44E-10 I 133E10 I 1.24E-10 I 1.16E-10 I 1.10E-10 I 1.04E-10 I 9.85E-11 I 9.39E-11 I 8.99E-11 I 8.63E-11 I Kr-85m I

I I

I I

I I

I I

I I

I

---

---

I I

---

---

I I

---

---

I I

--

---

I I

-87

-88 I

I I

I I

I I

I I

I I

I

---

I I

-- I I

--- I I

---

I I

Xe-133 9.60E-13 I 9.59E-13 I 9.58E-13 9.56E-13 i 9.55E-13 9.54E-13 I 9.53E-13 I 9.51E-13 9.50E-13 I 9.49E-13 I

-135m i I I f

I I

(

I I

---

I

--- I I

---

I

- --

I

-135 I I I I

---

I

-- I

--- -

-138 I I

I I I I

I I

--- I

-- - I

--- I I

---

I I

[ Noble Gas) 9.60E-13 I 9.59E-13 /

9.58E-13 [

9.56E-13 I 9.55E-13 I 9.54E 13 I 9.53E-13 I 9.51E-13 I 9.50E-13 I 9.49E-13 I I I I I I I I I I I Te-132 I I I I I I

--- I

---

I

-

I

---

I Cs-134 4.22E-14 I 4.22E-14 I 4.22E-14 I 4.22E-14 I 4.22E-14 ] 4.22E-14 I 4 '2E 14 I 4.22E-14 )

4.22E-14 [

4.22E-14 I

-137 2.11E-13 I 2.11E-13 (

2.11E-13 I 2 ~ 11E 13 I 2.11E-13 I 2 ~ 11E 13 I 2;11E-13 I 2

'1E-13 I 2.11E-13 I 2.11E-13 I Co-58 2.11E-13 I 2.11E-13 / 2.11E-13 I 2.11E-13 i 2.11E-13 )

2.11E-13 I 2 11 13 I 2 11E 13 I 2.11E-13 / 2.11E-13 I

-60 2.11E-13 I 2.11E-13 I 211E13 I 2.11E-13 I 2.14E-13 I 2.11E-13 I 2'11E 13 I 2 11E 13 I 2 11E 13 I 2 11E 13 I Ce-141 2.11E-12 I 2.11E-12 I 2.11E-12 I 2.11E-12 I 2.11E-12 I 2 11E 12 I 2.10E-12 I 2.10E-12 I 2.10E-12 I 2.10E-12 I Ba-140 2.10E-12 I 2.10E-12 I 2 10E-12 I 2 ~ 10E-12 I 2.10E-12 2.10E-12 I 2.10E-12 I 2.10E-12 I 2.09E-12 I 2.09E-12 I La-140 I I I I

)

I I

---

I

---

I

---

I

--- I Partic. 4.89E-12 / 4.89E-12 i 4.88E-12 i 4.88E-12 i 4.88E-12 i 4.88E-12 i 4.88E-12 / 4.88E-12 i 4.87E-12 )

4.87E-12 i I I I I I I I I I I Total 1.50E-10 I 1.39E-10 I 1.30E-10 i 1.22E-10 I 1.15E-10 I 1.10E-10 I 1.04E-10 I 9.98E-11 I 9.57E-11 I 9.21E-11 I 10.2-23

Nine Hile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 TABLE 10.2.8 TURBINE BUILDING AIR SAHPLE ANALYSIS TOTAL CONCENTRATION uCI/ml I 05 00 I 05:15 05:30 I 05:45 I 06:00 I 06:15 I 06:30 I 06:45 I 07:00 I I NUCLIDE (>>:30) I (>>:45) (12:00) I (12:15) I (12:30) I (12:45) I (13'00) I (13'15) I (13'30) I 1-131 2.60E-12 I 2.60E-12 I 2.60E-12 I 2.60E-12 I 2.60E-12 (

2.59E-12 (

2.59E-12 (

2.59E-12 (

2.59E-12 (

-132 1.27E->> I 1.17E->> I 1.09E->> I 1.01E.>> I 9.32E-12 I 8.63E-12 (

7.99E-12 (

7.40E-12 I 6.86E-12 I

-133 3.52E-1'l I 3.49E->> I 3.46E->> I 3.43E->> I 3 '0E->> I 3.37E >> I 3.34E->> I 3.32E->> I 3.29E->> I

-134 5.48E-12 I 4.49E-12 I 3.67E-12 I 3.01E-12 I 2.46E-12 I 2.o2E-12 I 1.65E-12 I 1.35E-12 I 1.>>E-12 I

-135 2.71E->> I 264E>> I 2.57E->> (

2.51E->> (

2.44E-ii (

2.38E->> (

2.32E->> (

2.26E->> I 2.20E->>

(

lodines e.3oE->> I 8.01E->> (

7.75E->> I 7.50E->> I 7.28E->> I 7.08E->> I 6.89E->> I 6.71E->> I 6.54E->> I I I I I I I I I Kr-85m I I I I I I

--- I I

I I

---

-87 I I I I I I

---

I

--- I I

-ee I I I I I I

---

I I

I

--- I 9.47E-13 9.46E-13 (937E13 Xe-133

-135m I

I I

I I

I 9.45E 13 I I

9.43E-13 I I

9.42E-13 I I

9.41E 13 I I

9.40E-13

---

---

I I

9.38E-13 I

--

---

I I

-135 I I I I I I I

-138 I I I I I I

---

I I

I

--- I I

( Noble Gas( 9.47E-13 I

'9.46E-13 I 9.45E-13 (

9.43E-13 (

9.42E-13 I 9.41E-13 I 9.40E-13 I 9.38E-13 I 9.37E 13 I I I I I I I I I I I Te-132 I I I I I I

---

I I

I

--- I Cs-134 4.22E-14 I 4.22E-14 I 4.22E-14 I 4'22E-14 I 4.22E-14 I 4.22E-'l4 I 4.22E-14 I 4.22E-14 (

4.22E-14 I

-137 2.>>E-13 I 2.>>E-13 I 2.>>E-13 I 2.>>E-13 I 2>>E13 (

2.>>E-13 (

2;>>E-13 (

2.>>E-13 (

2.>>E-13 I Co-58 2.>>E-13 I 2>>E13 I 2>>E13 I 2.>>E-13 I 2.>>E-13 I2>>E13 I 2.>>E-13 I 2. >>E-13 (

2.>>E-i3 (

-60 2.>>E-13 (

2.>>E-13 I 2>>E13 I 2.>>E-13 I 2.14E-13 I 2>>E13 I 2.>>E-13 I 2.>>E-13 (

2.>>E-i3 (

Ce-141 2.10E-12 I 2.10E-12 I 2.10E-12 (

2.1OE-12 I 2.10E-12 I 2.10E-12 I 2.'IOE-12 I 2.10E-12 I 2.10E-12 I Ba-140 2.09E-12 I 2.09E-12 I 2.09E-12 I 2.09E-12 I 2.09E-12 I 2.09E 12 I 2.09E-12 I 2.08E-12 2.OSE-12 La-140 I I I I I I

--- I I

(

--- (

I Partic. 4.87E-12 I 4 87E 12 I 4.87E-12 I 4.87E-12 I 4.86E-12 (

4.86E-12 (

4.86E-12 (

4.86E-12 (

4.86E-12 (

I I I I I I I I I Total 8.89E->> I 8.59E->> I 8.33E->> (

8.09E->> I 7.86E->> (

7.66E->> I 7.47E->> 7.29E->> I 7.12E->> I 10.2-24

Nine Nile Point Unit 2 1990 Annual Exercise Scenario Ho. 19, Rev. 1 TABLE 10.2.9 RADWASTE BUILDING AIR SAHPLE ANALYSIS TOTAL COHCEHTRATIOH uCI/ml I I 00:00 I 00:15 00:30 I 00:45 I 01:00 I 01:15 I 01:30 I 01:45 I 02:00 I 02:15 I NUCLIDE I (06:30) I (06:45) (07:00) I (07:15) I (07:30) I (07:45) I (08:00) I (08:15) I (08:30) I (08:45)

I-131 5.78E-12 I 5.78E-12 I 5.78E-12 I 578E12 I 5.78E 12 I s.78E-12 I 5.77E-12 I 5.77E-12 I 5.76E-12 I 5.76E-12 I

-132 1.00E-12 I 1.00E-12 I 1 ~ OOE-12 I 1.00E-12 I 1.00E-12 I 1 ~ 00E 12 I 9.26E-13 I 8.58E-13 I 7.95E-13 I 7.36E-13 I

-133 7.87E-12 I 7.87E-12 I 7.87E-12 I 7;87E-12 I 7.87E-12 I 7.87E-12 I 7.80E-12 I 7.74E-12 I 7.67E-12 I 7.61E-12 I

-134 1.86E-12 I 1.86E-12 I 1.86E-12 I

'l.86E-12 I 1.86E-12 I 186E12 I 1.52E-12 I 1.25E-12 I 1 '2E-12 I 8.36E-13 I

-135 7.87E-12 I 7.87E-12 I 7.87E-12 I 7.87E-12 I 7.87E-12 I 7.87E-12 I 7.67E-12 I 7.47E-12 I 7.28E-12 I 7.09E-12 I lodines 2.44E-11 I 2.44E-11 I 2.44E-11 I 2.44E-11 I 2.44E-11 I 2.44E-11 2.37E-11 I 2.31E-11 I 2.25E-11 I 2.20E-11 I I I I I I I I I I Kr-85m I I I I I

---

-- -

-87 I I I I I

I I I

--- I

---

I I

-88 I I I I I I I

I

--- I I

--- I XQ-133 I 3.27E-13 I 3.27E-13 I 3 27E 13 I 3.27E-13 I 3.27E-13 3.27E-13 I 3.27E-13 I 3.26E-13 I 3.26E-13 3.25E-13 I

--- ----

I

--- I 135m I

-135 I

I I

I I

I I

I I

I

--

---

I I

I I

I

---

I I

---

I I

-138 I I I I I I I I

I

--- I

--- I I Noble GasI 3.27E-13 I

'3.27E-13 I 3 27E 13 I 3.27E-13 I 3.27E-13 I 3.27E-13 I 3 ~ 27E-13 I 3.26E-13 I 3 ~ 26E-13 I 3.25E-13 I Te-132 I

I I

I I

I I I I I

--- I I

I I

I I

---

I I

-- I I

Cs-134 1.36E-12 I 1.36E-12 I 1'36E 12 I 1'36E 12 I 1 36E 12 I 1.36E-12 I 1.36E-12 I 136E 12 I 1 36E 12 I 1 36E 12 I

-137 2.29E-12 I 2.29E-12 I 2.29E-12 I 2.29E-12 I 2'29E 12 I 2.29E-12 I 2.29E-12 I 2.29E-12 I 2.29E-12 I 2.29E-12 I Co-58 1.15E-13 I 1.15E-13 I 1.15E-13 I 1.15E-13 I 1.15E-13 I 1.15E-13 I 1 ~ 15E-13 1.15E-13 I 1.15E-13 I 1.15E-13 I

-60 4.01E-12 I 4.01E-12 I 4.01E-12 I 4 01E 12 I 4.0$ E-12 I 4.01E-12 I 4.01E-12 I 4.01E-12 I 4.01E-12 I 4.01E-12 I Ce-141 4.0'IE-15 I 4.01E-15 I 4.01E-15 I 4.01E-15 I 4.01E-15 I 4.01E-15 I 4.01E-15 I 4.01E-15 I 4 ~ 01E-15 I 4.01E-15 I Ba-140 2.29E-15 I 2.29E-1s I 2.29E-15 I 2 29E-15 2.29E-15 I 2.29E-15 2.29E-15 2.29E-15 2 29E 15 I 2.28E-15 I La-140 I I I I

I I

--- I I

I I

I I

---

I

-

I Partic. 7.78E-12 I 7.78E-12 I 7.78E-12 I 7.78E-12 I 7 78E-12 I 7.78E-12 I 7.78E-12 I 7.78E-12 I 7.78E-12 I 7.78E-12 I I I I I I I I I I I Total 3.25E-11 I 3.25E-11 I 3.25E-11 I 3.2sE-11 I 3.25E-11 I 3.25E-11 I 3.18E-11 I 3.12E-11 I 3.06E-11 I 3.0'IE-11 I 10.2-25

Nine Mi le Point Unit 2 1990 Annual Exercise Scenario Ho. 19, Rev. 1 TABLE 10.2.9 RADIJASTE BUILDING AIR SAMPLE AHALYSIS TOTAL COHCEHTRATION uCi/mi I 02'30 I 02:45 I 03:00 I 03:15 I 03:30 I 03:45 I 04:00 I 04:15 I 04:30 I 04'45 I NUCLIDE (09:00) I (09-15) I (09:30) l (09:45) I (10:00) I (10:15) I (10:30) I (10:45) I (11:00) I (11:15) I I-131 5.75E-12 / 5.75E-12 [ 5.74E-12 I 5.74E-12 [ 5.73E-12 J 5.73E-12 [ 5.72E-12 / 5.72E-12 I 5.71E-12 I 5.71E-'12 I

-132 6.82E-13 I 6.31E-13 I 5 85E-13 I 5.42E-13 I 5.02E-13 I 4.65E-13 I 4.3OE-13 ] 3.98E-13 3.69E-13 3.42E-13 I [ [

-133 7.54E-12 I 7.48E-12 I 7.41E-12 [ 7.35E-12 I 7 29E 12 I 7.23E-12 I 7.16E-12 ( 7.10E-12 I 7.04E-12 I 6.98E-12 I

-134 6.84E-13 I 5.60E-13 I 4 ~ 59E 13 I 3.76E-13 I 3.08E-13 I 2.52E-13 I 2.06E-13 i 1.69E-13 I 1.38E-13 I 1.13E-13 I

-135 6.91E-12 [ 6.74E-12 i 6.56E-12 i 6.40E-12 I 6.23E-12 I 6.07E-12 I 592E 12 I 5.76E-12 I 5.62E-12 [ 5.47E-12 f

[ Iodines 2.16E-11 I 2 12E 11 I 2.08E-11 I 2.04E-11 i 2.01E-11 i 1.97E-11 1 94E 11 I 1.92E-11 I 1.89E-11 f 1.86E-11 f I I I I I I I I I I Kr-85m I I I

---

- -

I I

---

-87 I I I

I I

- --

I I

--- I I I I I

I

---

I I

-88 I I I I

- I

--- I I I I

--- I Xe-133 3.25E-13 I 3.24E-13 / 3.24E-13 I 3.23E-13 3.23E-13 I 3.23E-13 3.22E-13 3.22E-13 l321E1 3.21E-13 135m I I

--- ---

I / I

--- I

-135 I I

I I

I I

I I

I

---

I I

-- I I

I I

I I

--- I I

-138 I I I I I

--- I

--- I I I

I I

I

--- I

/ Noble Gasi 3.25E-13 I '3.24E-13 I 3.24E-13 I 3.23E-13 i 3.23E-13 I 3.23E-13 I 3.22E-13 /

3.22E-13 I 3,21E-13 )

3.21E-13 /

I I I I I I I I I I Te-132 I I I I

-- I

--- I I I I

-- I Cs-134 1.36E-12 I 1.36E-12 [

1.36E-12 I 1.36E-12 I 1.36E-12 I 1.36E-12-I 1.36E-12 i 1.36E-12 I 1 36E 12 I 1.36E-12 I

-137 2.29E-12 I 2.29E-12 I 2.29E-12 I 2.29E-12 ] 2.29E-12 ] 2.29E-12 ] 2.29E-12 I 2.29E-12 I 2 29E 12 I 2.29E-12 I Co-58 1.15E-13 ] 1.15E-13 I I'15E 13 / 1.1SE-13 i 1.'ISE-13 i 1.15E-13 J 1 ~ 15E-13 I 1.15E-13 I 1 ~ 15E-13 [ 1.15E-13 ]

-60 4 ~ 01E-12 i 4.01E-12 i 4.01E-12 I 4.01E-12 I 4.01E-12 I 4.01E-12 I 4.01E-12 I 4.01E-12 I 4.01E-12 I 4.01E-12 I Ce-141 4.01E-15 ( 4.00E-15 I 4.00E-1 I 4 ~ OOE 15 i 4.00E-15 i 4.00E-15 4.00E-15 I 4.00E-15 I 4 OOE-15 I 4 ~ OOE-15 I Ba-140 2.28E-15 I 2.28E-15 [

2.28E-15 I 2 28E-15 I 2.28E-15 I 2.28E-15 I 2.28E-15 I 2.27E-15 I 2.27E-15 ] 2.27E-IS [

La-140 I I I I

---

I

--- I I I I

--- I Partic. 7.78E-12 I 7.78E-12 I 7.78E-12 i 7.78E-12 I 7.78E-12 I 7.78E-12 I 7.78E-'12 I 7.78E-12 I 7.78E-12 I 7.78E-12 I I I I I I I I I I I Total 2.97E.11 I 2.93E-11 i 2.89E-11 I 2.85E-11 I 2.82E-11 I 2.78E-11 I 2.75E-11 2.73E-11 I 2.70E-11 i 2.67E-11 10.2-26

~ r-Nine Nile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 TABLE 10.2.9 RADNASTE BUILDING AIR SANPLE ANALYSIS TOTAL CONCENTRATION uCI/mi I I 05:00 I 05:15 I 05:30 I 05:45 I 06:00 I 06:15 I 06:30 06:45 I 07:00 I NUCLIDE I (11'30) I (11'45) I (12:00) I (12:15) I (12:30) I (12:45) I (13:00) (13:15) I (13:30)

I -131 70E 12 I 5.70E-12 I 5-69E-12 I 5 69E 12 I s.68E-12 I 5.68E-12 I 5 67E 12 I 5.67E-12 I 5.66E-12 I

-132 3.17E-13 I 2.93E-13 I 2.72E-13 I 2.52E-13 I 2.33E-13 I 2.16E-13 I 2.00E-13 (1 85E 13 I 1.71E-13 I

-133 6.92E-12 I 6.87E-12 I 6.81E-12 I 6.75E-12 I 6.69E-12 (663E 12 6.58E-12 I 6.52E-12 6 47E 12 I I I

-134 927E14 I 7.59E-14 I 6.21E-14 I 5.09E-14 I 4.17E-14 I 3.41E-14 I 2.79E-14 I 2.29E-14 I 1.878-14 (

-135 5.33E 12 I 5.20E-12 ( 5 ~ 06E-12 I 4.93E-12 I 4 81E 12 I 4.68E-12 I 4.56E-12 I 4 '5E-'l2 I 4 33E 12 I lodines ib84E-11 (

1.81E-11 (

1.79E-11 I 1.77E-11 I 175E ll I 1.72E-11 I 1.70E-11 1.68E-11 (

1.67E-11 (

I I I I I I I Kr-85m b I

--- I

-87 I

I I

I I

I I

I I

I I

I I

I I

I

--

--

I I

-88 I I I I I I I I I Xe-133 3 ~ 20E-13 I 3.20E-13 (

3.19E-'l3 I 3.'l9E-13 I 3'19E 13 I 3.18E-13 I 3 ~ 18E-13 3.17E-13 3.17E-13 I

-135m I I I I I I I I

I I

I

---

-135 I I I I I I I I

--- I I

-138 I I I I I I I I

---

I

( Noble Gas( 3.20E-13 I 3.20E-13 I 3.19E-13 I 3 ~ 19E-13 I 3.19E-13 I 3.18E-13 I 3.18E-13 (

3.17E-13 I 317E13 I I I I I I I I I Te-132 I I I I I I I I

--- I I

Cs-134 1.36E-12 I 1.36E-12 I 1.36E-12 I 136E12 I 1.36E-12 I 1.36E-12 I 1.36E-12 (

1.36E-i2 I 1.36E-12 I

-137 2.29E-12 I 2.29E-12 (

2.29E-12 I 2.29E-12 I'.29E-12 I 2.29E-12 I 2 29E 12 I 2.29E 12 I 2'29E 12 I Co-58 1 ~ 15E-13 I 1.15E-13 I 1 ~ 15E-13 I 1.15E-13 I 115E13 I 1.15E-13 I 1.15E-13 (

1.1SE-13 I i.isE-13 (

-60 4.01E-12 I 4.01E-12 I 4 ~ 01E-12 I 4.01E-12 I 4.01E 12 I 4.01E-12 I 4 ~ 01E 12 I 4.01E-12 I 4.01E-12 I Ce-141 4.00E-15 I 4 'OE-15 I 3.99E-15 (

3.99E-15 (

3.99E-15 I 3.99E-15 I 3.99E 15 (399E 15 I 3.99E-15 I Ba-140 2.27E-15 I 2.27E-15 (

2.27E-1S I 2.27E-15 I 2.27E-15 I 2.26E-15 I 2 26E 15 I 2.26E-15 I 2.26E-15 I LB-140 I I I I I I I I

---

I Partic. 7.78E-12 I 7.78E-12 I 7.78E-12 I 7.78E-12 I 7.78E-12 I 7.78E-12 I 7.78E-12 I 7.78E-12 I 7.78E-12 I I I I I I I I I I Total 2.65E-11 I 2.62E-11 I 2.60E-11 I 2.58E-11 I 2.56E-11 I 2.s3E-ii I 2.51E-11 I 2.49E-11 I 2.48E-11 10.2-27

0 Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 TABLE 10.2.10-1 2 Days Later October 4, 1990 Su ression Pool Air Activit I-131 1.53E+00 I-132 2.19E+00 I-133 2.88E-01 I-134 4.65E-06 I-135 ~12E-02 4.03E+00 Kr-85m 3.38E-01 Kr-87 1.24E-05 Kr-88 6.86E-02 Xe-133 7.96E+02 Xe-135m O.OOE+00 Xe-135 1.62E+01 Xe-138 0 OOE+00 8.13E+02 Te-132 2.70E+02 Cs-134 3.52E+02 Cs-137 5.35E+02 Co-58, 3.10E-12 Co-60 7.08E-12 Ce-141 5.22E-13 Ba-140 6.70E-12 La-140 3 24E-12 1.16E+03 10.2-28

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 TABLE 10.2.10-2 2 Days Later October 4, 1990 Reactor Water Activit uCi ml I-131 6.79E+03 I-132 5.52E-01 I-133 1.52E+03 I-134 6.72E-07 I-135 ~95E+01 8.39E+03 Kr-85m 8.09E-02 Kr-87 3.27E-06 Kr-88 1.68E-02 Xe-133 8.04E+01 Xe-135m 0.00E+00 Xe-135 3.79E+00 Xe-138 0 OOE+00 8.43E+01 Te-132 8.39E+02 Cs-134 9.31E+02 Cs-137 2.14E+03 Co-58 2.99E-05 Co-60 6.82$ -05 Ce-141 5.03E-06 Ba-140 6.44E-05 La-140 3 04E-05 3.91E+03 10.2-29

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 TABLE 10.2.10-3 2 Days Later October 4, 1990 Su ression Pool Water Activit I-131 6.13E+02 I-132 8.75E+02 I-133 1.15E+02 I-134 1.86E-03 I-135 6 93E+00 1 61E+03

~

Kr-85m 1.53E-08 Kr-87 5.36E-13 Kr-88 3.71E-09 Xe-133 1.79E-06 Xe-135m O.OOE+00 Xe-135 6.41E-07 Xe-138 0 OOE+00 2.45E-06 Te-132 1.08E+03 Cs-134 1.41E+03 Cs-137 2.14E+03 Co-58 3.10E-08 Co-60 7.08E-08 Ce-141 5.22E-09 Ba-140 6.70E-08 La-140 3.24E-08 4.63E+03 10.2-30

'

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 TABLE 10.2.10-4 2 Days Later October 4, 1990 Dr ell Air Activit I-131 5.22E+00 I-132 5.98E-01 I-133 3.53E+00 I-134 6.22E-01 I-135 1.34E+00 1.13E+01 Kr-85m 3.38E-01 Kr-87 1.24E-05 Kr-88 6.86E-02 Xe-133 7.96E+02 Xe-135m O.OOE+00 Xe-135 1.62E+01 Xe-138 O.OOE+00 8.13E+02 Te-132 3.58E-04 Cs-134 3.79E-04 Cs-137 5.74E-04 Co-58 1.32E-10 Co-60 4.85E-10 Ce-141 9.05E-10 Ba-140 6.18E-10 La-140 1.87E-10 1.31E-03 10.2-31

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 TABLE 10.2.10-5 2 Days Later October 4, 1990 Reactor Buildin Air Activit I-131 4.30E-09 I-132 1.78E-16 I-133, 6.53E-10 I-134 0.00E+00 I-135 7.66E-12 Iodines 4.96E-09 Kr-85m 1.10E-08 Kr-87 4.29E-17 Kr-88 2.69E-10 Xe-133 9.28E-04 Xe-135m O.OOE+00 Xe-135 3.60E-06 Xe-138 O.OOE+00 Noble Gas 9.32E-04.

Te-132 1.45E-13 Cs-134 2.38E-11 Cs-137 3.59E-ll Co-58 6.05E-13 Co-60 1.05E-12 Ce-141 1.59E-13 Ba-140 2.63E-11 La-140 2.06E-16 Partic. 8.80E-11 Total 9.32E-04 10.2-32

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 TABLE 10.2.10-6 2 Days Later October 4, 1990 Turbine Buildin Air Activit I-131 2.59E-12 I-132 6.86E-12 I-133 3 '9E-11 I-134 1 ~ 11E-12 I-135 2 '0E-11 Iodines 6.54E-ll Kr-85m, Kr-87 Kr-88 Xe-133 9.37E-13 Xe-135m Xe-135 Xe-138 Noble Gas 9.37E-13 Te-132 Cs-134 4.22E-14 Cs-137 2.11E-13 Co-58 2.11E-13 Co-60 2.11E-13 Ce-141 2.10E-12 Ba-140 2.10E-12 La-140 Partic. 4.86E-12 Total 7 '2E-11 10.2-33

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 TABLE 10.F 10-7 2 Days Later October 4, 1990 Radwaste Buildin Air Activit I-131 5.66E-12 I-132 1.71E-13 I-133 6.47E-12 I-134 ,1.87E-14'.33E-12 I-135 Iodines '.67E-ll Kr-85m Kr-87 Kr-88 Xe-133 3.17E-13 Xe-135m Xe-135 Xe-138 Noble Gas 3.17E-13 Te 132 Cs-134 1.36E-12 Cs-137 2.29E-12 Co-58 1.15E-13 Co-60 '.01E-12 Ce-141 3.99E-15 Ba-140 2.26E-15 La-140 Partic. 7.78E-12 Total 2.48E-ll 10.2-34

Nine Hile Point Unit 1990 Annual Exercise 2

0 Scenario No. 19, Rev. 1 Table 10.4.3 Offsite Radiol ical Surve Sa le Data T + 07:00 (13:30)

I I I I I I I OPEN MINDOM CLOSED MINDOM I Air Sample (c) iCenteriinei i Incremental (b)i I i Location i 3 Feet Contact 3 Feet Contact Exposure [ Gross I Gross Particulate i Key i(mRad/hr) (CPH) (mRad/hr) (CPH) ( (mRad/hr) (mRad/hr) (mR) (CPH) (CPH)

I I I I I I I I I I I I A 608 1 4,246 I <1 <1 60 60 B 517 <1 3 548 I <1 <1 I <1 I 60 60 C 274 <1 1 692 I <1 <1 I <1 I 60 60 D 270 <1 1,664 (

<1 <1 I <1 I 60 60 267 <1 1 637 I <1 <1 60 60 I I F I 243 <1 1 454 I <1 <1 I

<1 I 60 60 I G I 230 <1 1 359 I <1 <1 I

<1 I 60 60 N i <1 220 <1 1 285 I

<1 <1 I <1 I 60 60 212 <1 1,221 <1 <1 60 60 x 202 <1 1 147 I <1 <1 I <1 I 60 60 (a) Data to be provided to survey/sampling team personnel at the appropriate times and locations. There is no closed window capability for count rate meters that should be used by procedure.

(b) Each time an entry into this area is made, participants will be told upon request that they have received the corresponding radiation exposure via self-reading dosimeters. This exposure will be repeated for each 5-minute period. Readings have been rounded off to reflect actual dosimetry response in the following manner: 0 mR to 5 mR = 0 mR; 6 mR to 15 mR = 10 mR; 16 mR to 25 mR = 20 mR, etc.

(c) Air sample data assunes a 15 cubic foot sample voluae and a background count rate = 60 CPH.

I

~EEGEEG IlllEE REFERENCE TIME A "-S.B F = 6.0 *EEET*EE*4%EEEEEEEEEE 8 = 2.0 G = 7.0

• 07:00

• C=3.0 N = 8.0 * (13:30)

• D =4.0 J = 9.0 E = 5.0 K = 10.0 10.4-20

Nine Hiie Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 Table 10.F 1 RELEASE RATE SUMHARY IDR ILL 00:00 I 00:15 I 00:30 I 00:45 I 01:00 I 01:15 I 01:30 I 01:45 I 02:00 I 02:15 I 02:30 I 02:45 I 03:00 I ICLOCK (06'30) I (06'45) I (07'00) I (07'15) I (07'30) I (07'45) I(08'00) I (08'15) I (08'30) I (08'45) I (09'00) I (09'15) I (09'30) I ITOTAL STACK RR I 4.61E+001 4.61E+00 I 4.61E+001 4.61E+001 4.61E+001 4.62E+00 14.62E+00 1.87E-02 I 1.88E-02 I 1.89E-021 1.90E-02 I 1.92E-02 I 1.93E-02 I NG (uCi/sec) I 4.61E+001 4.61E+00 I 4.61E+001 4.61E+001 4.61E+001 4.62E+00 14.62E+00 I 1.04E-02 I 1.05E.02 I 'l.06E-021 1.08E-02 I 1.09E-02 I '1.10E-02 I I (uCi/sec) I 9.02E-031 9.02E-03 I 9.02E-031 9.02E-031 9 02E 031 9 03E 03 IS 09E 03 I 8.09E-03 I 8.09E-03 I 8.10E-031 8.10E-03 I 8.10E-03 I 8.10E-03 I P (uCi/sec) I 1.90E-041 1.90E-04 I 1 90E 041 1 90 041 1 90 041 1 90E 04 11 90E 04 I 1.90E-04 I 1.90E-04 I 1.90E-041 1.90E-04 I 1.90E-04 I 1.90E-04 I I I I I I I I I I I I I I I I ITOTAL VENT RR I 5.76E-011 5.76E-01 I 5.76E-011 5.76E-011 5.76E-011 1 ~ 42E-03 11.42E-03 I

1.42E-03 I 1.42E-03 I 1.42E-031 1.42E-03 I 1.42E-03 I 1.42E-03 I ~

NG (uCi/sec) I 5.46E-011 5.46E-01 I 5.46E-Oll 5.46E-011 5.46E-O'll 1.43E-05 11.43E-05 I 1.43E-05 I 1.43E-05 I 1.43E-051 1.43E-05 1.43E-05 I 1.43E-05 I I (uCi/sec) I 2.38E-021 2.38E-02 I 2.38E-021 2.38E-021 2.38E-021 1.07E-03 11.07E-03 I 1.07E-03 I 1.07E-03 I 1.07E-031 1.07E-03 I 1.07E-03 I 1.07E-03 I P (uCi/sec) I 5.42E-031 5 42E-03 I 5.42E-031 5.42E-031 5.42E-031 3.41E-04 13.41E-04 I 3.41E-04 I 3 '1E-04 I 3.41E-041 3.41E-04 I 3.41E-04 I 3.41E-04 I IDR ILL 03:15 I 03:30 I 03:45 I 04:00 I 04:15 I 04:30 I 04:45 I 05:00 I 05:15 I 05:30 I 05:45 I 06:00 I ICLOCK (09'45) I (10'00) I (10'15) I (10'30) I (10'45) I(11'00) I (11'15) I (11'30) I (11'45) I (12'00) I (12'15) I (12'30) I ITOTAL STACK RR I 1.94E-02 I 1 95E 021 1 97E 021 1 98E 021 2 12E+01 16'33E+01 I 2'04E+02 I 2 34E+08 I 9 08E+081 8 06E+08 I 7 26E+08 I 6 70E+08 I NG (uCi/sec) I 1.11E-02 I 1.12E-021 1 '4E-021 1 '5E-021 2.12E+01 16.33E+01 I 2.04E+02 I 2.33E+08 I 9.08E+081 8.05E+08 I 7.25E+08 I 6.69E+08 I I (uCi/sec) I 8.10E-03 I 8 10E 031 8 17E 031 8 10E 031 9 50E 03 11 3 E 02 I 2 90E 02 I 2 4E 0 I 'E 051 4'77E 0 I 19E 05 I 5 9E 05 I P (uCi/sec) I 1.90E-04 I

'l.90E-041 1.90E-041 1.90E-041 1.90E-04 11 90E 04 I 1 90E 04 I 9 22E+04 I 1'07E+051 1'16E+05 I 1'27E+05 I 1'38E+05 I

'

I I I I I I I I I I I I I ITOTAL VENT RR I 1.42E-03 I 1 '2E 031 1 '2E 0311 42E 03 I 1 42E 03 11 42E 03 I 1 42E 03 I 1 '2E 03 I 1 42E 031 1.42E 03 I 1 42E 03 I 1.42E 03 I NG (uCi/sec) I 1.43E-05 I 1.43E-051 1.43E-0511.43E 05 I 1 43 05 Il 43E 05 I 1'43E 05 I 1.43E-05 I 1.43E-051 1.43E-05 I 1.43E.05 I 1 '3E-05 I I (uCi/sec) I 1.07E-03 I 1.07E-031 'I.07E-0311.07E-03 I 1.07E-03 11.07E-03 I 1.07E-03 I 1.07E-03 I 1.07E-031 1.07E-03 I 1.07E-03 I 1.07E-03 I P (uCi/sec) I 3.41E-04 I 3.41E-041 3.41E-0413 41E-04 I 3.41E-04 13.41E-04 I 3 ~ 41E-04 I 3.41E-04 I 3.41E-041 3.41E-04 I 3 41E 04 I 3 ~ 41E 04 I 10.4-1

Nine Hile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1e Table 10.4.1 RELEASE RATE SUHHARY I OR iLi. I 06'-15 I 06:30 I 06:45 I 07:00 I ICLOCK I (12'45) I (13'00) I (13'15) I (13'30) I ITOTAL STACK RR f 6.17E+08 f 5.71E+08/ 8.34E-03( 8.20E-03/

NG (uCi/sec) J 6.17E+08 i 5.?OE+08i 5.55E-03'.47E-03)

( I (uCi/sec) [ 5.97E+05 / 6.35E+05) 2.60E-03( 2.54E-03)

P (uCi/sec) 1.51E+05 / 1.64E+05/ 1.88E-04( 1.888-04)

I I I I I I ITOTAL VENT RR I 1.42E-03 I 1.42E-03I 1.42E-03I1.42E-03 I NG (uCi/sec) I 1.43E-05 I 1.43E-OSI 1.43E-OSI1.43E-05 I I (uCi/sec) I 1.07E-03 I 1.07E-03I 1.07E-0311.07E-03 I P (uCi/sec) I 3.41E-04 I 3.41E-04I 3.41E-0413.41E-04 I 10.4-2

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 10.4.2 Onsite Radiolo ical Surve Sam le Data

kine Hi le Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 Table 10.4.2 Onsite Radiolo ical Surya Sa le Data T + 05:00 (11:30)

I I I I I I OPEk IJIkDOM CLOSED lllkDOM I I Air Sample (c)

ICenterlineI I incremental (b)I I Location I 3 Feet Contact I 3 Feet Contact Exposure I Gross I Gross Particulate I Key I(mRad/hr) (CPH) (mRad/hr) (CPH) (mRad/hr) (nRad/hr) (mR)

"

I (CPH) (CPH) I I I I I I I I I I I I A' <1 60 <1 60 I

<1 <1 60 60.

e I 1 60 <1 60 <1 <1 60 60 ci I

<1 60 <1 60 I <1 I 60 60 Di I

<1 60 <1 60 I <1 60 60 E' <1 60 <1 60 I <1 <1 60 60

<1 60 <1 <1 I <1 I 60 60 G' <1 60 <1 60 <1 <1 60 60 I

(a) Data to be provided to survey/sampling team personnel at the appropriate times and locations. There is no closed window capability for count rate meters that should be used by procedure.

(b) Each time an entry into this area is made, participants will be told upon request that they have received the corresponding radiation'xposure via self-reading dosimeters. This exposure will be repeated for each 5-minute period. Readings have been rounded off to reflect actual dosimetry response in the following manner: 0 mR to 5 mR = 0 mR; 6 mR to 15 mR = 10 mR; 16 mR to 25 mR = 20 mR, etc.

(c) Air sample data assunes a 15 cubic foot sample volune and a background count rate = 60 CPH.

LEGEkD HILES REFERENCE TIHE As=0.2 F'='1.2 *****4***A****%

B'=0.4 G'=1.4

• 05:00 C'=0.6 * (11:30)

• 0'"-0.8 ***********A**4 E'=1.0 10.4-3

Nine Hile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 I

Table 10.4.2 Onsite Radiolo ical Surve Sa le Data T + 05:15 (11:45)

I I I I I I OPEN WINDOM CLOSED MINDOM I I Air Sample (c)

/Centerline/ i Incremental (b)I

/ Location / 3 Feet Contact i 3 Feet Contact Exposure i Gross I Gross Particulate i Key i(mRad/hr) (CPH) (mRad/hr) (CPH) i (mRad/hr) (mRad/hr) (mR) I (CPH) (CPH)

I I I I I I I I I I Ae I 8,058 OFFSCALE 8e 062 OFFSCALE i 51 51 I i OFFSCALE OFFSCALE I ge I 7e539 OFFSCALE 7,543 OFFSCALEI 33 33 3 i OFFSCALE OFFSCALE I Ce I 7,031 OFFSCALE 7,035 OFFSCALEI 25 25 I 2 I OFFSCALE OFFSCALE i 5,768 5,771 De OFFSCALE 13 13 OFFSCALEI I OFFSCALE OFFSCALE Ee i 4,765 OFFSCALE 4,767 OFFSCALEi 10 11 I <1 I OFFSCALE OFFSCALE I i 2,006 OFFSCAI.E 2,007 OFFSCALE) 4 4 I <1 i OFFSCALE OFFSCALE I Ge I 302 OFFSCALE 302 OFFSCALEI 2 2 I 5,279 OFFSCALE I (a) Data to be provided to survey/sampling team personnel at the appropriate times and locations. There is no closed window capability for count rate meters that should be used by procedure.

(b) Each time an entry into this area is made, participants will be told upon request that they have received the corresponding radiation exposure via self-reading dosimeters. This exposure will be repeated for each 5-minute period. Readings have been rounded off to reflect actual dosimetry response in the following manner: 0 mR to 5 mR = 0 mR; 6 mR to 15 mR = 10 mR; 16 mR to 25 mR = 20 mR, etc.

(c) Air sample data asswes a 15 cubic foot sample voiune and a background count rate = 60 CPH.

LEGEND HILES REFERENCE TINE A'=0.2 F'=1.2 ************0**

Be=0.4 Ge=1.4

• 05 15

• C'"-0.6 * (11:45)

• D'=0.8  %*%*I**********

E'"-1.0 10.4-4

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 Table 10.4.2 Onsite Radiolo ical Surve Sa le Data T + 05:30 (12:00)

I I I I I I OPEN WlNDOW CLOSED WINDOW I I Air Sample (c)

ICenterlineI Ilncremental (b)I I Location I 3 Feet Contact I 3 Feet Contact Exposure I Gross l Gross Particulate I Key I(mRad/hr) (CPM) (mRad/hr) (CPM) I(mRad/hr) (mRad/hr) (mR> I (CFM) (CPM>

I I I I I I I I I Ai I 7,199 OFFSCALE 7,207 OFFSCALEI 97 98 8 I OFFSCALE OFFSCALE I 8'i I 6,731 OFFSCALE 6,739 OFFSCALEI 73 73 6 I OFFSCALE OFFSCALE I I 6,265 OFFSCALE 6,272 OFFSCALEI 51 51 I OFFSCALE OFFSCALE I 0 I 5,137 OFFSCALE 5,143 OFFSCALEI 33 33 I OFFSCALE OFFSCALE I El I 4,235 OFFSCALE 4i240 OFFSCALEI 19 19 2 I OFFSCALE OFFSCALE I FI 1,782 OFFSCALE 1,784 OFFSCALEI 6 6 I OFFSCALE OFFSCALE I 269 OFFSCALE 279 OFFSCALEI 3 <1 6,375 OFFSCALE (a) Data to be provided to survey/sampling team personnel at the appropriate times and locations. There is no closed ~indow capability for count rate meters that should be used by procedure.

(b) Each time an entry into this area is made, participants will be told upon request that they have received the corresponding radiation exposure via self-reading dosimeters. This exposure will be repeated for each 5-minute period. Readings have been rounded off to reflect actual dosimetry response in the following manner: 0 mR to 5 mR = 0 mR; 6 mR to 15 mR = 10 mR; 16 mR to 25 mR = 20 mR, etc.

(c) Air sample data assunes a 15 cubic foot sample volune and a background count rate = 60 CPM.

LEGEND MILES REFERENCE TIME A'=0'.2 F '=1.2 8'=0.4 G'=1.4 05:30

• C'=F 6 * (12:00)

• D'=0.8 E'=1.0 10.4-5

Nine Hile Point Unit 2,

'1990 Annual Exercise Scenario No. 19, Rev. 1 Table 10.4.2 Onsite Radiolo ical Surve Sa le Data T + 05:45 (12:15)

I I I I I I I OPEN MINDON CLOSED MINDOM I I Air Sample (c)

ICenterlineI I Incremental (b) I I I Location I 3 Feet Contact 3 Feet Contact Exposure I Gross I Gross Particulate I Key I(mRad/hr) (CPH) (mRad/hr) (CPH) (mRad/hr) (mRad/hr) (CPH) (CPH) I I I I I I I I I I Ai I 6,468 OFFSCALE 6,481 OFFSCALEI 72 72 6 I OFFSCALE OFFSCALE I Bs 6,052 6,065 56 56 ci I

I 5,632 OFFSCALE OFFSCALE 5,644 OFFSCALEI OFFSCALEI 36 36 5

3 I OFFSCALE I OFFSCALE OFFSCALE OFFSCALE I" I

I I 4,618 OFFSCALE 4,627 OFFSCALEI 20 21 2 I OFFSCALE OFFSCALE I I 3,810 OFFSCALE 3,818 OFFSCALEI 12 12 1 I OFFSCALE OFFSCALE I I I 1 603 OFFSCALE 1,606 OFFSCALEI 4 4 <<I I OFFSCALE OFFSCALE I G' 242 OFFSCALE 242 OFFSCALEI 2 2 6,928 OFFSCALE I (a) Data to be provided to survey/sampling team personnel at the appropriate times and locations. There is no closed window capability for count rate meters that should be used by procedure.

(b) Each time an entry into this area is made, participants will be told upon request that they have received the corresponding radiation exposure via self-reading dosimeters. This exposure will be repeated for each 5-minute period. Readings have been rounded off to reflect actual dosimetry response in the following manner: 0 mR to 5 mR = 0 mR; 6 mR to 15 mR = 10 mR; 16 mR to 25 mR = 20 mR, etc.

(c) Air sample data assunes a 15 cubic foot sample volune and a background count rate = 60 CPH.

~LEGEND MILES REFERENCE TINE A'=0.2 F'"-1.2 *1********t****

8'=0.4 G'=1.4

• 05:45

• C'=0.6 (12:15)

D'"-0.8 ***%*1*********

E'=1.0 10.4-6

Nine Hile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 Table 10.4.2 Onsite Radiolo ical Surve Sa le Data T + 06:00 (12:30)

I I I I I I OPEN WINDOW CLOSED WINDOW I I Air Sample (c) iCenterlinei ilncremental (b)l

( Location J 3 Feet Contact I 3 Feet Contact Exposure i Gross I Gross Particulate i Key i(aRad/hr) (CPH) (mRad/hr) (CPH) (mRad/hr) (mRad/hr) (mR) (CPH) (CPH)

I I I I I I I I I I I A' I 5,958 OFFSCALE 5,976 OFFSCALEi 55 55 s I OFFSCALE OFFSCALE I

/ S,S40 OFFSCALE 5,557 OFFSCALEi 36 36 3 i OFFSCALE OFFSCALE I c I 5,190 OFFSCALE 5,206 OFFSCALEi 24 25 2 I OFFSCALE OFFSCALE I 0 i 4,2sr OFFSCALE OFFSCALEI 14 14 I OFFSCALE OFFSCALE I I I 3,515 OFFSCALE 3,526 OFFSCALEi 10 10 I

<1 I OFFSCALE OFFSCALE I I I 1,480 OFFSCALE 1,484 OFFSCALEi 4 4 I <1 I OFFSCALE OFFSCALE I 0 223 OFFSCALE 224 OFFSCALEI 2 2 I <1 r,4s6 OFFSCALE I (a) Data to be provided to survey/sampling team personnel at the appropriate times and locations. There is no closed window capability for count rate meters that should be used by procedure.

(b) Each time an entry into this area is made, participants will be told upon request that they have received the corresponding radiation exposure via self-reading dosimeters. This exposure will be repeated for each 5-minute period. Readings have been rounded off to reflect actual dosimetry response in the following manner: 0 mR to 5 mR = 0 mR; 6 mR to 15 mR = 10 mR; 16 mR to 25 mR = 20 mR, etc.

(c) Air sample data assunes a 15 cubic foot sample volune and a background count rate = 60 CPH.

~LEEEME MILES REFERENCE TIME A'=0.2 F'=1.2 EL*ELEI*******EI***

8'"-0.4 G'"-1.4

• 06:00 C'=0.6 * (12:30)

• D'=0.8 *********EL*****

E'=1.0 10.4-7

Nine Hile Point Unit 2, 1990 Annual Exercise Scenario No. 19, Rev. 1 Table 10.4.2 Onsite Radiol ical Surve S le Data T + 06:15 (12:45)

I I I I I I OPEN lllNDOW I CLOSED NINDOM I I Atr Sample (c)

ICenterlineI I Incremental (b) I I Location I 3 Feet Contact 3 Feet Contact Exposure Gross I Gross Particulate I Key I(mRad/hr) (CPM) (mRad/hr) (CPM) (mRad/hr) (mRad/hr) (mR> (CPH) (CPH)

I I I I I I I I I I I

A' I 5,490 OFFSCALE 5,513 OFFSCALE I 49 49 I OFFSCALE OFFSCALE I I

8' 5,126 OFFSCALE 147 OFFSCALEI 24 25 2 I OFFSCALE OFFSCALE I I c I 4,781 OFFSCALE 4,801 OFFSCALEI 20 21 2 I OFFSCALE OFFSCALE I D' 3,924 OFFSCALE 3 940 OFFSCALEI 13 13 OFFSCALE I I OFFSCALE I

E' 3,238 OFFSCALE 3,252 OFFSCALEI 7 8 I OFFSCALE OFFSCALE

. I I

F' 1,363 OFFSCALE 1,369 OFFSCALEI 3 3 I I OFFSCALE OFFSCALE '

I G' 206 OFFSCALE 207 OFFSCALEI 1 1 <<1 7,967 OFFSCALE I I (a) Data to be provided to survey/sampling team personnel at the appropriate times and locations. There is no closed window capability for count rate meters that should be used by procedure.

(b) Each time an entry into this area is made, participants will be told upon request that they have received the corresponding radiation exposure via self-reading dosimeters. This exposure will be repeated for each 5-minute period. Readings have been rounded off to reflect actual dosimetry response in the following manner: 0 mR to 5 mR = 0 nR; 6 mR to 15 mR = 10 mR; 16 mR to 25 mR = 20 mR, etc.

(c) Air sample data assunes a 15 cubic foot sample volune and a background count rate = 60 CPH.

~EGG EGG II I LEG REFERENCE TIHE A'=0.2 F'"-1.2 ***************

B'=0.4 G'=1.4

• 06:15 C'=0.6 * (12:45>

• D'=0.8 ***0***********

E'=1.0 10.4-8

Nine Hile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 Table 10.4.2 Onsite Radiol ical Surve Sa le Data T + 06:30 (13:00>

I I I I I I I OPEN NINOOW CLOSED MINDOW I I Air Sample (c)

ICenterlineI IIncremental (b)I I I Location I 3 Feet Contact 3 Feet Contact Exposure Gross I Gross Particulate I Key I(mRad/hr) (CPH) (mRad/hr) (CPH) (mRad/hr) (mRad/hr) (CPH) (CPH>

I I I I I I I .I I I I A'E I 5,064 OFFSCALE 5,093 OFFSCALEI 35 36 I OFFSCALE OFFSCALE I OFFSCALE 4,763 OFFSCALEI 22 23 I 2 OFFSCALE OFFSCALE c I 4,416 OFFSCALE 4E441 OFFSCALEI 16 17 I OFFSCALE OFFSCALE I D I 3,625 OFFSCALE 3,645 OFFSCALEI 10 11 I OFFSCALE OFFSCALE I I 2,992 OFFSCALE 3,008 OFFSCALEI 6 6 I

<1 I OFFSCALE OFFSCALE I I 1,260 OFFSCALE 1,267 OFFSCALEI 3 3 <1 I OFFSCALE OFFSCALE I GE 190 OFFSCALE 190 OFFSCALEI 1 1 I

<1 I 8,462 OFFSCALE (a) Data to be provided to survey/sampling team personnel at the appropriate times and locations. There is no closed window capability for count rate meters that should be used by procedure.

(b) Each time an entry into this area is made, participants will be told upon request that they have received the corresponding radiation exposure via self-reading dosimeters. This exposure will be repeated for each 5-minute period. Readings have been rounded off to reflect actual dosimetry response in the following manner: 0 mR to 5 mR = 0 mR; 6 mR to 15 mR = 10 mR; 16 mR to 25 mR = 20 mR, etc.

(c) Air sample data assunes a 15 cubic foot sample volune and a background count rate = 60 CPH.

~LEGGED MILES REFERENCE TIHE A'=0.2 F'=1.2 ***************

8'=0.4 G'"-1.4

• 06:30

• C'=0.6 (13:00)

D'=0.8 *0*************

E'=1.0 10.4-9

Nine Hile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 Table 10.4.2 Onsite Radiolo ical Surve Sa le Data T + 06:45 (13:15)

I I I I I I OPEN WINDOW CLOSED WINDOW I I Air Saaple (c)

(Centerline( I Incremental (b) I I Location I 3 Feet Contact 3 Feet Contact Exposure I Gross I Gross Particulate (

Key I(mRad/hr) (CPH) (mRad/hr) (CPH) (mRad/hr) (mRad/hr) (mR) I (CPH) (CPH)

I I I I I I I I I I I Ai 10 OFFSCALE 37 OFFSCALE I 10 11 827

(

e 9 OFFSCALE 34 OFFSCALE 10 I <1 I 725 3915 I I

c' 8 27,378 31 OFFSCALE 8 8 I <1 I 621 3353

(

O' 7 25,071 26 OFFSCALE I 7 8 568 3067 I I E I 3 12,426 20 OFFSCALE 4 <1 I 282 1522 I I F I 3 9,691 9 OFFSCALE 3 220 1188 Gi <1 1,614 1 4,275 <1 <1 I 96 518 (a) Data to be provided to survey/sampling team personnel at the appropriate times and locations. There is no closed window capability for count rate meters that should be used. by procedure.

(b) Each time an entry into this area is made, participants will be told upon request that they have received the corresponding radiation exposure via self-reading dosimeters. This exposure will be repeated for each 5-minute period. Readings have been rounded off to reflect actual dosimetry response in the following manner: 0 mR to 5 mR = 0 sR; 6 mR to 15 mR = 10 mR; 16 mR to 25 mR = 20 mR, etc.

(c) Air sample data assunes a 15 cubic foot sample volune and a background count rate = 60 CPH.

LEGEND MILES REFERENCE TIME A'=0.2 F'=1.2 ***************

ei=0.4 Gi=1.4

• 06 45

• C'"-0.6 * (13:15)

• D'=0.8 ***************

E'=1.0 10 '-10

Nine Hile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 Table 10.4.2 Onsite Radiolo ical Surve Sa le Data T + 07:00 (13:30)

I I I I I I OPEN MINDOM CLOSED MINDOW I I Air Sample (c)

IcenterlineI IIncremental (b)I I Location I 3 Feet Contact 3 Feet Contact Exposure I Gross I Gross Particulate I Key I(mRad/hr) (CPH) (mRad/hr) (CPH) (mRad/hr) (mRad/hr) I (mR) I (CPH) (CPH) I I I I I I I I I I I Ai 4 14,682 31 OFFSCALE I 4 5 I

<1 I 334 1801 I I 8 I 4 13,768 29 OFFSCALE I 4 5 <1 I 313 1690 I I

c' 4 '12,855 27 OFFSCALE I 4 4 I <1 I 1576 I 3 10,570 22 OFFSCALE 3 4 I <1 I 240 1296 I I E I 2 8,742 18 OFFSCALE I 2 3 <1 I 199 1074 I F 1 3,716 8 27,963 'I 1 <<1 453 I I I I I I G I

<1 1,608 1 4,275 I <1 <1 I <1 I 76 410 (a) Data to be provided to survey/sampling team personnel at the appropriate times and locations. There is no closed window capability for count rate meters that should be used by procedure.

(b) Each time an entry into this area is made, participants will be told upon request that they have received the corresponding radiation exposure via self-reading dosimeters. This exposure will be repeated for each 5-minute period. Readings have been rounded off to reflect actual dosimetry response in the following manner: 0 mR to 5 mR = 0 mR; 6 mR to 15 mR = 10 nR; 16 mR to 25 mR = 20 mR, etc.

(c) Air sanpie data assunes a 15 cubic foot sample voiune and a background count rate = 60 CPH.

LEGEND HILES REFERENCE TINE A'-"0.2 F'"-1.2 t%t*********44+

8'=0.4 G'=1.4

• 07:00

• C'=0.6 (13:30)

• D'=0.8 *'04*1**14***'t*'k E'=1.0

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 10.4.3 Offsite Radiolo ical Surve Sam le Data

Nine Mile Point Unit 2 1990 Annual Exercise Scenario Ho. 19, Rev. 1 Table 10.4.3 Offsite Radiolo ical Surve Sa le Data T + 05:00 (11:30)

I I I I I I OPEN HIHDOH CLOSED lllHDOH I I Air Sample (c)

/Centerline/ [ Incremental (b) ]

/ Location / 3 Feet Contact 3 Feet Contact Exposure [ Gross I Gross Particulate )

Key ((mRad/hr) (CPM) (mRad/hr) (CPM) (mRad/hr) (mRad/hr) I (mR) I (CPM) (CPM)

I I I I I I I I I A I 1 60 <1 60 <1 <1 I 60 60 8 /

<1 60 <1 60 <1 <1 1 I 60 60 C i <1 60 <1 60 <1 <1 <1 I 60 60 O i <1 60 <1 60 <1 <1 <1 / 60 60 I E I <1 60 <1 60 <1 <1 60 . 60 60 <1 60 <1 <1 <1 I 60 60 I G I <1 60 <1 60 <1 <1 1 I 60 60 I " I <1 60 60 <1 <1 60 60 I J I <1 60 <1 60 <1 <1 60 60 I K I <1 60 <1 60 <1 <1 <1 i 60 60 (a) Data to be provided to survey/sampling team personnel at the appropriate times and locations. There is no closed window capability for count rate meters that should be used by procedure.

(b) Each time an entry into this area is made, participants will be told upon request that they have received the corresponding radiation exposure via self-reading dosimeters. This exposure will be repeated for each 5-minute period. Readings have been rounded off to reflect actual dosimetry response in the following manner: 0 mR to 5 mR = 0 mR; 6 mR to 15 mR = 10 aR; 16 mR to 25 mR = 20 mR, etc.

(c) Air sample data assunes a 15 cubic foot sample volwe and a background count rate = 60 CPM.

LEGEND MILES REFERENCE TIME A = ST 8 F

"-6.0 **************

8 "-2.0 G=7.0

• 05:00

• C "- 3.0 H = 8.0 * (11:30)

• 0 "-4.0 J = 9.0 **************

E = 5.0 K = 10.0 10.4-12

Nine Hile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 Table 10.4.3 Offsite Rsdiolo ical Surve Ss le Dsts T + 05:15 (11:45)

I I I I I OPEN MINDOM CLOSED WINDOM Air Sample (c)

(Centerline( I I Incremental (b) I

( Location I 3 Feet Contact ( 3 Feet Contact Exposure (

Gross I Gross Particulate Key I(mRad/hr) (CPH) (mRad/hr) (CPH) I (mRad/hr) (mRad/hr) (mR) ( (CPH) (CPH)

I I I I I I A I 302 OFFSCALE 302 OFFSCALEI 2 2 <1 I 10268 OFFSCALE 8 I 251 OFFSCALE 251 OFFSCALEI <1 <1 <1 I 8534 OFFSCALE C 117 OFFSCALE 117 OFFSCALEI <1 <1 <1 I 3978 21480 0 I <1 60 .<1 60 I

<1 <1 <1 6O 60 E <1 60 <1 60 I

<1 <1 <1 6O 60 I I

<1 60 1 60( <1 <1 6O 60 G I

<1 60 <1 60 I <1 <1 <1 6O 60 I

<1 60 <1 60 I <1 <1 6O 60 I

<1 60 60 I <1 <1 <1 6O 60

<1 60 <1 60 I <1 <1 <1 6O 60 (s) Data to be provided to survey/sampling team personnel at the appropriate times and locations. There is no closed window capability for count rate meters that should be used by procedure.

(b) Each time an entry into this area is made, participants will be told upon request that they have received the corresponding radiation exposure via self-reading dosimeters. This exposure will be repeated for each 5-minute period. Readings have been rounded off to reflect actual dosimetry response in the following manner: 0 mR to 5 mR = 0 mR; 6 mR to 15 mR = 10 mR; 16 mR to 25 mR = 20 mR, etc.

(c) Air sample data asstmes a 15 cubic foot sample voiune and a background count rate = 60 CPH.

I LEGEND HILES REFERENCE TINE A = S.B F = 6.0 t************%

B = 2.0 G -" 7.0

• 05 15

• C = 3.0 N = 8.0 * (11:45)

D = 4.0 J = 9.0 ***********%*k E = 5.0 K -"10.0 10.4-13

Nine Hi le Point Un>.

1990 Annual Exercise Scenario Ho. 19, Rev. 1e Table 10.4.3 Offsite Radiolo ical Surve Sa le Data T + 05:30 (12:00)

I I I I I I OPEH MINDOW I CLOSED WINDOM I Air Sample (c)

ICenterlineI I I Incrementa I (b)I I Location I 3 Feet Contact 3 Feet Contact I Exposure I Gross I Gross Particulate I Key I(mRad/hr) (CPM) (mRad/hr) (CPH) (mRad/hr) (mRad/hr) I (mR) (CPH) (CPH)

I I I I I I I I I I A 269 OFFSCALE 269 OFFSCALEI 3 <1 6,375 OFFSCALE I I B I 227 OFFSCALE 227 OFFSCALEI 5 5 <1 5,322 27303 I c I 107 OFFSCALE 107 OFFSCALEI 3 I <1 2,523 1281O I o I 104 OFFSCALE 105 OFFSCALEI 2 2 <1 I 2,481 12592 I I E I 102 OFFSCALE 102 OFFSCALEI 1 1 <1 I 2,438 12374 I I F I <1 60 <1 60 I <1 <1 6O 6O I G I <1 60 <1 60 I <1 <1 <1 6O 6O

<1 60 <1 60 I

<1 6O 6O I J I

<1 60 60 I

<1 <1 I 60 6O

<1 60 <1 60 I <1 <1 6O 6O (a) Data to be provided to survey/sampling team personnel at the appropriate times and locations. There is no closed window capability for count rate meters that should be used by procedure.

(b) Each time an entry into this area is made, participants will be told upon request that they have received the corresponding radiation exposure via self-reading dosimeters. This exposure will be repeated for each 5-minute period. Readings have been rounded off to reflect actual dosimetry response in the following manner: 0 mR to 5 mR = 0 mR; 6 mR to 15 mR = 10 mR; 16 mR to 25 mR = 20 mR, etc.

(c) Air sample data assumes a 15 cubic foot sample voiune and a background count rate = 60 CPH ~

~LEEEEO EL LEE REFERENCE TINE A = S.B F = 6.0 ******4******A B = 2.0 G -" 7.0

• 05 30

• C "- 3.0 H -"8.0 * (12:00)

• D = 4.0 J = 9.0 **%*A*4*******

E = 5 0 K = 10.0 10.4-14

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 Table 10.4.3 Offsite Radiolo ical Surve Sa le Data T + 05:45 (12:15)

I I I I I I OPEN IIINDDM CLOSED MIND& I I Air Sample (c)

IcenterlineI IIncremental (b)I I Location I 3 Feet Contact I 3 Feet Contact Exposure I Gross I Gross Particulate I Key I(mRad/hr) (CPH) (mRad/hr) (CPH) I (mRad/hr) (mRad/hr) I (mR) I (CPM) (CPH)

I I I I I I I I I I A I 242 OFFSCALE 242 OFFSCALEI 2 2 6,928 OFFSCALE B 204 OFFSCALE 204 OFFSCALEI 4 I 5,783 29758 I c I 97 OFFSCALE 97 OFFSCALEI 4 I 2,738 13959 I 0 I 96 OFFSCALE 96 OFFSCALEI 4 <1 2,693 13721 E I 94 OFFSCALE 94 OFFSCALEI 4 <1 2,647 I 83 OFFSCALE 83 OFFSCALEI 3 2,347 11927 I G I 76 OFFSCALE 76 OFFSCALEI 1 <1- 2,191 11120 I I

<1 60 <1 60 I <1 <1 <1 60 60 I <1 60 <1 60 I <1 <1 I

<1 60 60 I <<1 60 <1 60 I <1 <1 I <1 60 60 (a) Data to be provided to survey/sampling team personnel at the appropriate times and locations. There is no closed window capability for count rate meters that should be used by procedure.

(b) Each time an entry into this area is made, participants will be told upon request that they have received the corresponding radiation exposure via self-reading dosimeters. This exposure will be repeated for each 5-minute period. Readings have been rounded off to reflect actual dosimetry response in the following manner: 0 mR to 5 mR = 0 mR; 6 mR to 15 mR = 10 iW; 16 mR to 25 mR = 20 mR, etc.

(c) Air sample data assunes a 15 cubic foot sample volune and a background count rate = 60 CPH.

i LEGEND HILES REFERENCE TIHE A = S.B F = 6.0  %%*********4**

B = 2.0 G

"-7.0 05:45

• C = 3.0 H = 8.0 * (12:15)

• D = 4.0 J = 9.0 ***%*******%**

E = 5.0 K "-10.0 10.4-15

Nine Nile Point Unit 2 1990 Annual Exercise Scenario Ho. 19, Rev. 1 Table 10.4.3 Offsite Radiol ical Surve Sa le Data T + 06:00 (12:30)

I I I I I I OPEN MIHDOM CLOSED l!IHDOM I I Air Sample (c) iCentertine) ilncrementat (b)i i Location i 3 Feet Contact 3 Feet Contact Exposure i Gross I Gross Particulate i Key ((mRad/hr) (CPH) (mRad/hr) (CPH) (mRad/hr) (mRad/hr) (mR) i (C H) (CPM) I I I I I I I I I I A 223 OFFSCALE 224 OFFSCALEI 2 I

<1 I 7,456 OFFSCALE I 8 188 OFFSCALE 188 OFFSCALEi 3 I <1 6,223 OFFSCALE c 89 OFFSCALE 90 OFFSCALEI 3 I

<1 I 2,944 15210 I 0 88 OFFSCALE 88 OFFSCALEI 3 I

<1 I 2,895 14951 I 86 OFFSCALE 87 OFFSCALEI 3 <1 2,846 14693 I F 77 OFFSCALE 77 OFFSCALEI 3 I

<1 I 2,523 12996 G 71 OFFSCALE 1 OFFSCALEI 2 I <1 2,355 12116 I 66 OFFSCALE 67 OFFSCALEI 2 I <1 2,224 11429 I 63 OFFSCALE 63 OFFSCALEI 1 I <1 I 2,111 10834 I K 59 OFFSCALE 59 OFFSCALE( 1 I

<1 I 1,980 10147 I (a) Data to be provided to survey/sampling team personnel at the appropriate times and locations. There is no closed window capability for count rate meters that shoutd be used by procedure.

(b) Each time an entry into this area is made, participants wilt be told upon request that they have received the corresponding radiation exposure via self-reading dosimeters. This exposure will be repeated for each 5-minute period. Readings have been rounded off to reflect actual dosimetry response in the following manner: 0 mR to 5 mR = 0 nR; '6 mR to 15 nR = 10 mR; 16 mR to 25'nR = 20 mR, etc.

(c) Air sample data assunes a 15 cubic foot sample volune and a background count rate = 60 CPH.

I LEGEND HILES REFERENCE TINE A = S.B F

"-6.0 4I*a*4%*&*0**

B = 2' G=7.0 06:00

• C = 3.0 H = 8.0 * (12:30)

• D = 4.0 J "- 9.0 E = 5.0 K = 10.0 10.4-16

0 0 Nine Hile Point Unit 1990 Annual Exercise 2

Scenario No. 19, Rev. 1 Table 10.4.3 Offsite Radiol ical Surve S le Data T + 06:15 (12:45)

I I I I I I OPEN WINDOW CLOSED WINDOW I I Air Sample (c)

/Centeriinef /Incremental (b)/

/ Location i 3 Feet Contact 3 Feet Contact Exposure ] Gross I Gross Particulate [

Key )(mRad/hr) (CPH) (mRad/hr) (CPH) I (mRad/hr) (mRad/hr) (CPH) (CPH)

I I I I I I I I I I I A I 206 OFFSCALE 206 OFFSCALEi I

<1 I 7,967 OFFSCALE

( 8 173 OFFSCALE 174 OFFSCALEI 6,649 OFFSCALE c I 82 OFFSCALE 83 OFFSCALE[ I I 3,144 16575 0 81 OFFSCALE 81 OFFSCALEI <1 I 3 091 16292 I E, 79 OFFSCALE 80 OFFSCALEi I 3 038 16010 I 70 OFFSCALE 70 OFFSCALE] I 2,693 14161 I G I 66 OFFSCALE 66 OFFSCALEI I

<1 2,514 13201 I I 62 OFFSCALE 62 OFFSCALE) 2,374 12453 I I I 9 OFFSCALE 59 OFFSCALEI 2,253 11804 I I K I 55 OFFSCALE 55 OFFSCALEI I

<1 2,113 11056 I OFFSCALE(a) Data to be provided to survey/sampling team personnel at the appropriate times and locations. There is no closed window capability for count rate meters that should be used by procedure.

(b) Each time an entry into this area is made, participants will be told upon request that they have received the corresponding radiation exposure via self-reading dosimeters. This exposure will be repeated for each 5-minute period. Readings have been rounded off to reflect actual dosimetry response in the following manner: 0'mR to 5 mR = 0 mR; 6 mR to 15 mR = 10 mR; 16 mR to 25 mR = 20 mR, etc.

(c) Air sample data asswes a 15 cubic foot sample volune and a background count rate = 60 CPH.

1 LEGEND MILES REFERENCE TIME A = ST 8 F = 6.0 ***0**********

8 = 2.0 G = 7.0

• 06 15

• C = 3 ' N = 8.0 (12:45) 0 = 4.0 J = 9.0 **************

E = 5.0 K = 10.0 10.4-17

Nine Hile Point Unit 2 1990 Annual Exercise Scenario ko. 19, Rev. 1 Table 10.4.3 Offsite Radiolo ical Surve Sa le Data T + 06:30 (13:00)

I I I I I I OPEN llINDOM CLOSED MINDOM I I Air Sample (c)

ICenterlineI Ilncremental (b)I I Location I 3 Feet Contact 3 Feet Contact Exposure I Gross I Gross Particulate I Key I(mRad/hr) (CPH) (mRad/hr) (CPH) (mRad/hr) (mRad/hr) I (mR) I (CPH) (CPH)

I I I I I I I I I A 190 OFFSCALE 191 OFFSCALEI 1 <1 I 8 462 OFFSCALE I e 160 OFFSCALE 161 OFFSCALEI 3 <1 I 7 062 OFFSCALE I c 76 OFFSCALE 76 OFFSCALEI I <1 I 3i337 18061 I 0 I 75 OFFSCALE 75 OFFSCALEI 2 <1 3,281 17754 I E I 73 OFFSCALE 74 OFFSCALEI 2 <1 3,225 17446 I F I 65 OFFSCALE 65 OFFSCALEI 2 <1 I 2,858 15430 I I 0 I 60 OFFSCALE 61 OFFSCALEI 2 <1 2,667 14384 I k I 57 OFFSCALE OFFSCALEI 2 <1 I 2,519 13569 I I J I 54 OFFSCALE 54 OFFSCALEI -2 I 2,390 12861 I K I 51 OFFSCALE 51 OFFSCALEI 2 <1 2,242 12045 I (a) Data to be provided to survey/sampling team personnel at the appropriate times and locations. There is no closed window capability for count rate meters that should be used by procedure.

(b) Each time an entry into this area is made, participants will be told upon request that they have received the corresponding radiation exposure via self-reading dosimeters. This exposure will be repeated for each 5-minute period. Readings have been rounded off to reflect actual dosimetry response in the following manner: 0 mR to 5 mR = 0 mR; 6 mR to 15 mR = 10 rrR; 16 mR to 25 rrR = 20 mR, etc.

(c) Air sample data assunes a 15 cubic foot sample voiune and a background count rate = 60 CPH.

LEGEND MILES REFERENCE TIHE A = S.B F = 6.0 **************

8 = 2.0 G = 7.0 06:30

• C = 3.0 H = 8.0 * (13r00)

• D = 4.0 J = 9.0 *************0 E "- 5.0 K "-10.0 10.4-18

~ i Nine Mile Point Unit 2

'1990 Annual Exercise Scenario No. 19, Rev. 1 Table 10.4.3 Offsite Radiolo ical Surve Sa le Data T + 06:45 (13:15)

I I I I I I I OPEN MINDOM CLOSED MINDOW I I Air Sample (c)

(Centerline( (

Incremental (b) ( I I Location I 3 Feet Contact (

3 Feet Contact Exposure I Gross I Gross Particulate I Key ((mRad/hr) (CPH) (mRad/hr) (CPH) (mRad/hr) (mRad/hr) (mR) I (CPH) (CPH) I I I I I I I I I A I <1 614 1 4,275 I <1 <1 6o 60 I 8 I

<1 521 <1 3,573 I <1 6o 60 I C I

<1 276 <1 1,704 I

<1 6o 60 I 0 I

<1 272 <1 1,676 (

<1 <1 6o 60 I E I 2 7 001 2 8,380 I 2 2 148 790 I F I 2 6 184 2 7,404 I 2 2 I <1 I 140 756 I G I 2 5,416 2 6,552 I 2 2 I <1 I 132 712 I N

( 1 4,506 2 5,578 ( 1 1 <1 I 128 690 I I 1 3 814 1 4,829 I 1 1 I <1 I 110 595 I K I

<1 3 408 4,359 I <1 <1 I

<1 I 100 540 I (a) Data to be provided to survey/sa'mpling team personnel at the appropriate times and locations. There is no closed window capability for count rate meters that should be used by procedure.

(b) Each time an entry into this area is made, participants will be told upon request that they have received the corresponding radiation exposure via self-reading dosimeters. This exposure will be repeated for each 5-minute period. Readings have been rounded off to reflect actual dosimetry response in the following manner: 0 mR to 5 mR = 0 mR; 6 mR to 15 mR = 10 mR; 16 mR to 25 mR = 20 mR, etc.

(c) Air sample data assunes a 15 cubic foot sample voiune and a background count rate = 60 CPH.

I

~LEGEND NILE'EFERENCE TIHE A = S.B F << 6.0 0*************

B "-2.0 G = 7.0

• 06:45

• C

"-3.0 N

"

-8.0 (13:15)

• D -" 4.0 J "

-9.0 0*************

E = 5.0 K = 10 0 10.4-19

.

.)

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. le 10.4 RADIOLOGICAL RELEASE INFORMATION TABLE OF CONTENTS Section Title ~Pa e 10.4.1 Release Rate Data Summary 10.4-1 10.4.2 Onsite Radiological Survey/Sample Data 10.4-3 10.4.3 Offsite Radiological Survey/Sample Data 10.4-12 10.4.4 Post Release Environmental Sampling Results 10.4-21

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 10.4.1'elease Rate Data Summar

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 10.4 RADIOLOGICAL RELEASE INFORMATION

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No.,19, Rev. 1 10.3 IN PLANT RADIOLOGICAL DATA

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 10.3 RADIOLOGICAL SAMPLE DATA TABLE OF CONTENTS Section Title ~Pa e 10.3.1 Reactor Building EL. 175'-0" 10.3-1 10.3.2 Reactor Building EL. 196'-0" 10.3-3 10.3.3 Reactor Building EL. 215'-0" 10.3-5 10.3.4 Reactor Building EL. 240'-0" 10.3-7 10.3.5 Reactor Buildings EL. 261'0" 10.3-9 10.3.6 Reactor Building EL. 289'-0" 10.3-11 10.3.7 Reactor Building EL. 306'-6" 10.3-13 10.3.8 Reactor Building EL. 328'-10" 10.3-15 10.3.9 Reactor Building EL. 353'-10" $ 0.3-17

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 10.3 DRYWELL AND REACTOR BUILDING DOSE RATES The following tables and maps are provided to indicate dose rates in the drywell and reactor building. Dose rates in the turbine building and radwaste building are normal through out the duration of the drill and should be given as "AS FOUND".

Nine Mile Point Unit 2 TABLE 10.3.1 1990 Annual Exercise Scenario No. 19, Rev. 1 REACTOR BUILDING ELEVATION 175'ONE TIME DOSE RATES A B 00:00 - Ol:19 4.0 R/hr

• R/hr

• R/hr 01:20 - 01:29 4.0 R/hr:

• R/hr

• R/hr 01:30 - 01:44 1.4 R/hr

• R/hr

• R/hr 01:45 - 01:59 ~ 1.1 R/hr

• R/hr

• R/hr 02:00 - 02:14 1.1 R/hr

• R/hr

• R/hr 02:15 - 02:29 1.1 R/hr

• R/hr

• R/hr 02:30 - 02:44 1.1 R/hr

• R/hr

• R/hr 02:45 - 02:59 1.1 R/hr

• R/hr

• R/hr 03:00 - 03:14 1.1 R/hr

• R/hr

• R/hr 03:15 - 03:29 1.1 R/hr

• R/hr

• R/hr 03:30 - 03:44 1.1 R/hr

• R/hr

• R/hr 03:45 - 03:59 1.1 R/hr

• R/hr

• R/hr 04:00 - 04:14 1.1 R/hr

• R/hr

• R/hr 04:15 - 04:29 15,040 R/hr 0.003 R/hr

• R/hr 04:30 - 04:44 30,500 R/hr 0.004 R/hr

• R/hr 04'45 - 04'59 102,000 R/hr 0.010 R/hr + R/hr 05:00 - 05:14 201,000 R/hr 0.012 R/hr 0.147 R/hr 05:15 - 05:29 170,000 R/hr 0.014 R/hr 0.149 R/hr 05:30: - 05:44 145,000 R/hr 0.018 R/hr 0.153 R/hr 05:45 - 05:59 129,000 R/hr 0.020 R/hr 0.155 R/hr 06:00 - 06:14 116,000 R/hr 0.021 R/hr 0.156 R/hr 06:15 - 06:29 100,000 R/hr 0.023 R/hr 0.158 R/hr 06:30 - 06:44 95,000 R/hr 0.022 R/hr 0.157 R/hr 06:45 - 07:00 92,000 R/hr 0.021 R/hr 0.156 R/hr

<Dose Rates are "AS FOUND" 10.3-1

~ ~

~

~ ~

+a~

P P

}P I ~

~ p P

1 ~

I ~

IP yP P P P P P 4

Nine Mile Point Unit 2 TABLE 10.3.2 1990 Annual Exercise Scenario No. 19, Rev. 1 REACTOR BUILDING ELEVATION 196'ONE TIME DOSE RATES 00:00 - 01:19 4.0 R/hr

• R/hr

• R/hr 01:20 - 01:29 4.0 R/hr

• R/hr

• R/hr 01:30 - 01:44 1.4 R/hr

• R/hr

• R/hr 01:45 - 01:59 1.1 R/hr

• R/hr '* R/hr 02:00 - 02:14 1.1 R/hr

• R/hr

• R/hr 02:15 - 02:29 1.1 R/hr

• R/hr

• R/hr 02:30 - 02:44 1.1 R/hr

• R/hr

• R/hr 02:45 - 02:59 1.1 R/hr

• R/hr

• R/hr 03:00 - 03:14 1.1 R/hr

• R/hr

• R/hr 03:15 - 03:29 1.1 R/hr

• R/hr

• R/hr 03:30 - 03:44 1.1 R/hr

• R/hr

• R/hr 03:45 - 03:59 1.1 R/hr

• R/hr

• R/hr 04:00 - 04:14. 1.1 R/hr

• R/hr

• R/hr 04:15 - 04:29 15,040 R/hr 0.003 R/hr

• R/hr 04:30 - 04:44 30,500 R/hr 0.004 R/hr

• R/hr 04:45 - 04:59 102,000 R/hr 0.010 R/hr

• R/hr 05:00 - 05:14 201,000 R/hr 0.012 R/hr 0.147 R/hr 05:15 - 05:29 170,000 R/hr 0.014 R/4r 0.149 R/hr 05:30' 05:44 145,000 R/hr 0.018 R/hr 0.153 R/hr 05:45 - 05:59 129,000 R/hr 0.020 R/hr 0.155 R/hr 06:00 - 06:14 116,000 R/hr 0.021 R/hr 0.156 R/hr 06:15 - 06:29 100,000 R/hr 0.023 R/hr 0.158 R/hr 06:30 - 06:44 95,000 R/hr 0.022 R/hr 0.157 R/hr Q6:45 - Qj:QQ 92,000 R/hr 0.021 R/hr 0.156 R/hr

~Dose Rates are "AS POUND".

N x.ne Male Point Unxt 2 1990 Annual Exercise REACTOR. B U ILDI N G EL 1 96 ZONE C N AUX BAY PIPE OPENING

'one YALYE PITS I

A CIC YALYE POPS ~

PIPE CHASE Zone B ELEY.

HOIST YALYE PITS YELL (Zone B)>

Reactor Bldg. only S AUX BAY lo.z-4

Nine Mile Point Unit 2 TABLE 10.3.3 1990 Annual Exercise REACTOR BUILDING ELEVATION Scenario No. 19, Rev. 1 215'IME ZONE DOSE RATES B C 00:00 - 01:19 4.0 R/hr

• R/hr

• R/hr 4

01:20 - 01:29 4.0 R/hr

• R/hr

• R/hr, 01:30 - 01:44 1.4 R/hr

• R/hr

• R/hr 01:45 - 01:59 1.1 R/hr

• R/hr

• R/hr 02:00 - 02:14 1.1 R/hr

• R/hr

• R/hr 02:15 - 02:29 1.1 R/hr

• R/hr

• R/hr 02:30 - 02:44 1.1 R/hr

• R/hr 02:45 - 02:59 1.1 R/hr

• R/hr

• R/hr 03:00 - 03:14 1.1 R/hr

• R/hr

• R/hr 03:15 - 03:29 1.1 R/hr

• R/hr R/hr 03:30 - 03:44 1.1 R/hr

• R/hr

• R/hr 03:45 - 03:59 1.1 R/hr

• R/hr

• R/hr 04:00 - 04:14 1.1 R/hr

• R/hr

• R/hr 04:15 - 04:29 15,040 R/hr 0.003 R/hr

• R/hr 04:30 - 04:44 30,500 R/hr 0.004 R/hr

• R/hr 04:45 - 04:59 102,000 R/hr 0.0010 R/hr

• R/hr 05:00 - 05:14 201,000 R/hr 0.012 R/hr 0.147 R/hr 05:15 - 05:29 170,000 R/hr 0.014 R/hr 0.149 R/hr 05:30. - 05:44 145,000 R/hr 0.018 R/hr 0 '53 R/hr 05:45 - 05:59 129,000 R/hr 0.020 R/hr 0.155 R/hr 06:00 - 06:14 116,000 R/hr 0.021 R/hr. 0.156 R/hr 06:15 - 06:29 100,000 R/hr 0.023 R/hr 0.158 R/hr 06:30 - 06:44 95,000 R/hr 0.022 R/hr 0 '57 R/hr 06:45 - 07:00 92,000 R/hr 0.021 R/hr 0.156 R/hr Dose Rates are "AS FOUND" 10.3-5

os(

~ ~ ~

~

I I

?

Iw. 7.

'4 4p

'C,

~,

~5 0

0 ~

I

~

I'7m'

~ I Cg c'

i')V.

cl+ ~ ~

f Wp j7

'Vis

+V

't~v I~V'.

~'

Vc '

'777 7 ~ ~

~ +

I

'" I

~,tv Pi 7 V.'l

TABLE 10.3.4 Nine Mile Point Unit 2 1990 Annual Exercise REACTOR BUILDING ELEVATION Scenario No. 19, Rev. 1 240'ONE TIME DOSE RATES B C 00:00 - 01:19 4.0 R/hr

• R/hr

• R/hr 01:20 - 01:29 4.0 R/hr

• R/hr

• R/hr 01:30 - 01:44 1.4 R/hr

• R/hr

• R/hr 01:45 - 01:59 1.1 R/hr

• R/hr

• R/hr 02:00 - 02:14 1.1 R/hr

• R/hr

• R/hr 02:15 - 02:29 1.1 R/hr

• R/hr

• R/hr 02:30 - 02:44 1.1 R/hr

• R/hr

• R/hr 02:45 - 02:59 1.1 R/hr

• R/hr

• R/hr 03:00 - 03:14 1.1 R/hr

• R/hr

• R/hr 03:15 - 03:29 1.1 R/hr

• R/hr

• R/hr 03:30 - 03:44 1.1 R/hr

• R/hr

• R/hr 03:45 - 03:59 1.1 R/hr

• R/hr

• R/hr 04:00 -'4:14 1.1 R/hr

• R/hr

• R/hr 04:15 - 04:29 15,040 R/hr 0.003 R/hr

• R/hr 04:30 - 04:44 30,500 R/hr 0.004 R/hr

• R/hr 04:45 - 04:59 102,000 R/hr 0.010 R/hr

• R/hr 05:00 - 05:14 201,000 R/hr 0.012 R/hr 0.147 R/hr 05:15 - 05:29 170,000 R/hr 0.014 R/hr 0.149 R/hr 05:30 - 05:44 145,000 R/hr 0.018 R/hr 0.153 R/hr 05:45 - 05:59 129,000 R/hr 0.020 R/hr 0.155 R/hr 06:00 - 06:14 116,000 R/hr 0.021 R/hr 0.156 R/hr 06:15 - 06:29 100,000 R/hr 0.023 R/hr 0.158 R/hr 06:30 - 06:44 95,000 R/hr 0.022 R/hr 0.157 R/hr 06:45 - 07:00 92,000 R/hr 0.021 R/hr 0.156 R/hr

>Dose Rates are "AS FOUND" 10.3-7

~ ~

t . ~

Nine Mile Point Unit 2 TABLE 10 3.5 1990 Annual Exercise REACTOR BUILDING ELEVATION Scenario No. 19, Rev. 1 261'ONE TIME DOSE RATES 00:00 - 01:19 4.0 R/hr

• R/hr 01:20 - 01:29 4.0 R/hr

• R/hr 01:30 - 01:44 1.4 R/hr

• R/hr 01:45 - 01:59 1.1 R/hr

• R/hr 02:00, - 02:14 1.1 R/hr

• R/hr 02:15 - 02:29 1.1 R/hr

• R/hr 02:30 - 02:44 1.1 R/hr

• R/hr 02:45 - 02:59 1.1 R/hr

• R/hr 03:00 - 03:14 1.1 R/hr x R/hy 03:15 - 03:29 1.1 R/hr

• R/hr 03:30 - 03:44 1.1 R/hr

• R/hr 03:45 - 03:59 1.1 R/hr

• R/hr 04:00 - 04:14 1.1 R/hr

• R/hr 04:15 - 04:29 15,040 R/hr

• R/hr 04:30 - 04':44 30,500 R/hr

• R/hr 04:45 - 04:59 102,000 R/hr

• R/hr 05:00 - 05:14 201,000 R/hr 0.147 R/hr 05:15 - 05:29 170,000 R/hr 0.149 R/hr 05:30 - 05:44 145,000 R/hr 0.153 R/hr 05:45 - 05:59 129,000 R/hr 0.155 R/hr 06:00 - 06:14 116,000 R/hr 0.156 R/hr 06:15 - 06:29 100,000 R/hr 0.158 R/hr 06:30 - 06:44 95,000 R/hr 0.157 R/hr-06:45 - 07:00 92,000 R/hr 0.156 R/hr

• Dose Rates are "AS FOUND".

10.3-9

gene Male Poxnt Unx< 2 1990 Annual Exercise Scenario No 19 Re~ 1 REA CTO IR 8 uf LD N G EL. 26 I

l RDS HCU'S RCS B

RR TRACK PERSONNEL AND EQUIP HATCH

~

MS IV ROON RX H2V CLEAN-UP 0 Zone A

PIPE CHASE CRD HATCH HATCH'one EQUIP HATCH EMERG. ESCAPE ELEV.

B g'

ARCS

//

rg HCU'S 10.3-10

TABLE 10.3.6 Nine Mile Point Unit 2 1990 Annual Exercise REACTOR BUILDING ELEVATION 289'ONE Scenario No. 19, Rev. 1 TIME DOSE RATES A B 00:00 - 01:19 4.0 R/hr

• R/hr 01:20 - 01:29 4.0 R/hr

• R/hr 01:30 - 01:44 1.4 R/hr

• R/hr 01:45 - 01:59 1.1 R/hr

• R/hr 02:00 - 02:14 1.1 R/hr

• R/hr 02:15 - 02:29 1.1 R/hr

• R/hr 02:30 - 02:44 1.1 R/hr

• R/hr 02:45 - 02:59 1.1 R/hr

• R/hr 03:00 - 03:14 1.1 R/hr

• R/hr 03:15 - 03:29 1.1 R/hr

• R/hr 03:30 - 03:44 1.1 R/hr

• R/hr 03:45 - 03:59 1.1 R/hr

• R/hr 04:00 - 04:14 1.1 R/hr

• R/hr 04:15 - 04:29 15,040 R/hr

• R/hr 04:30 - 04:44 30,500 R/hr

• R/hr 04:45 - 04:59 102,000 R/hr

• R/hr 05:00 - 05:14 201,000 R/hr 0.147 R/hr 05:15 - 05:29 170,000 R/hr 0.149 R/hr 05 30 ' 05 44 145,000 R/hr 0.153 R/hr 05:45 - 05:59 129,000 R/hr 0.155 R/hr 06:00 - 06:14 116,000 R/hr 0.156 R/hr 06:15 - 06:29 100,000 R/hr 0.158 R/hr 06:30 - 06:44 95,000 R/hr 0.157 R/hr 06:45 - 07:00 92,000 R/hr 0.156 R/hr

"<Dose Rate are "AS FOUND" 10.3-11

~ ~

~ ~

~ ~

Nine Mile Point Unit 2 TABLE 10.3.7 1990 Annual Exercise Scenario No. 19, Rev. 1 REACTOR BUILDING ELEVATION 306'ONE TIME DOSE RATES A B 00:00 - 01:19 4.0 R/hr

• R/hr l

01:20 - 01:29 4.0 R/hr

• R/hr 01:30 - 01:44 1.4 R/hr

• R/hr 01:45 - 01:59 1.1 R/hr

• R/hr 02:00 - 02:14 1.1 R/hr

• R/hr

'

02:15 - 02:29 1.1 R/hr

• R/hr 02:30 - 02:44 1.1 R/hr

• R/hr 02:45 - 02:59 1.1 R/hr

• R/hr 03:00 - 03:14 1.1 R/hr

• R/hr 03:15 - 03:29 1.1 R/hr

• R/hr 03:30 - 03:44 1.1 R/hr

• R/hr 03:45 - 03:59 1.1 R/hr

• R/hg 04:00 - 04:14 1.1 R/hr

• R/hr 04:15 - 04:29 15,040 R/hr

• R/hr 04:30 - 04:44 30,500 R/hr

• R/hr 04:45 - 04:59 102,000 R/hr

• R/hr 05:00 - 05:14 201,000 R/hr 0.147 R/hr

'05:15 - 05:29 170,000 R/hr 0.149 R/hr

'

05:30 05:44 145,000 R/hr 0.153 R/hr 05:45 - 05:59 129,000 R/hr 0.155 R/hr 06:00 - 06:14 116,000 R/hr 0.156 R/hr 06:15 - 06:29 100,000 R/hr 0.158 R/hr 06:30 - 06:44 95,000 R/hr 0.157 R/hr 06:45 - 07:00 92,000 R/hr 0.156 R/hr

~Dose Rates are "AS FOUND".

1

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 zs+croa BuII DIx~C eI . aO6 r

r Zone

/ qJ A I

e I

r

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I I

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LE P GRATING i OOM VALK'rr'AY,'

HOIS Rc/EI I j

ELEV.

HoiS

'ELL j NON-"" QEN I

I

~

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Zone B REGEl' HEAT EXCHANGERS 10.3-14

Nine Mile Point Unit 2 TABLE 10.3,8 1990 Annual Exercise REACTOR BUILDING ELEVATION Scenario No. 19, Rev. 1 328'ONE TIME DOSE RATES 00:00 - 01:19

• R/hr 01:20 - 01:29

• R/hr 01:30 - 01:44 + R/hr 01:45 - 01:59

• R/hr 02:00 - 02:14

• R/hr 02:15 - 02:29

• R/hr 02:30 - 02:44 02:45 - 02:59

• R/hr 03:00 - 03:14

• R/hr 03:15 - 03:29

• R/hr 03:30 - 03:44 *'R/hr 03:45 - 03:59

• R/hr 04:00 - 04:14

• R/hr 04:15 - 04:29 0.003 R/hr 04:30 - 04:44 0.004 R/hr 04:45 - 04:59 R/hr '.010 05:00 - 05:14 0.012 R/hr 05:15 - 05:29 0.014 R/hr 05:30 . - 05:44 0.018 R/hr 05:45 - 05:59 0.020 R/hr 06:00 - 06:14 0.021 R/hr 06:15 - 06:29 0.023 R/hr 06:30 - 06:44 0:022 R/hr 06:45 - 07:00 0.021 R/hr

~Do'se Rates are "AS FOUND".

10.3-15

Nine Mile Point Unit 2 1990 Annual Exercise Scenario No. 19, Rev. 1 EP CTOR BUILDlNC, EL. 328 NEV FUE!

STORAGE CHANGE VAULT ROON DECON CQNTAN.

RBCLC .VTR HP EQUIP.

PUMPS PUMP RN RVCU VALVE ROON HOIS j I I YELL I SFC I I I SFC PMP.

I I F ILTER I I I DENINS

~l 1

I 0 RESIN STRG AREA ELEV.

HOIST VELL Qo Oo RX MEAD RVCU EVACUATION PRECOAT FILTER ASSY. EQUIP.

Zone B (Entire Elevation in Reactor Bldg.)

10.3-16

Nine Mile Point Unit 2 TABLE 10.3 9 1990 Annual Exercise REACTOR BUILDING ELEVATION 353 Scenario No . 1 9, Rev. 1 TIME ZONE DOSE RATES 00:00 - 01:19

• R/hr'1:20

- 01:29

• R/hr 01:30 - 01:44

• R/hr 01:45 - 01:59

• R/hr 02:00 - 02:14

• R/hr 02:15 - 02:29

• R/hr 02:30 - 02:44

• R/hr 02:45 - 02:59

• R/hr 03:00 - 03:14

• R/hr 03:15 - 03:29

• R/hr 03:30 - 03:44

• R/hr 03:45 - 03:59

• R/hr 04:00 - 04:14

• R/hr 04:15 - 04:29 0.003 R/hr 04:30 - 04:44 0.004 R/hr 04:45 - 04:59 0.010 R/hr 05:00 - 05:14 0.012 R/hr 05:15 - 05:29 0.014 R/hr 05:30 - 05:44 0.018 R/hr 05:45 - 05:59 0.020 R/hr 06:00 - 06:14 0.021 R/hr 06:15 - 06:29 0.023 R/hr 06:30 - 06:44 0.022 R/hr 06:45 - 07:00 0.021 R/hr

<Dose Rates are "AS FOUND".

0

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