Text

Forwards Scenario Package for Scheduled 920528 NRC Evaluated Exercise,Including Scope & Objectives,Schedules,Contingency & Simulation Info,Controller & Player Info,Exercise Rules, Radiation Levels & Release Rates & Data/Messages
	ML20094M628
Person / Time
Site:	Pilgrim
Issue date:	03/26/1992
From:	Richard Anderson; BOSTON EDISON CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	92-033, 92-33, NUDOCS 9204010222
	Download: ML20094M628 (207)
	v • d • e

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10CfR50 App.E g Section IV f.2 BOSTON EDISON r 7 , e,<.; y re ur. ,

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Roy A. Anderspra t.ew v<:e vmw: - uxw March 26, 1992 PECo Ltr.92-033 U. S. Nucienr Argulatory Commbston Document Control C?sk Washington, DC 206 %

DocLet No. 50-293 Licent,e No. OPR-35

Subject:

1992 NRC Evaluated Evertise Scenario submittal Enclosed i D000.*, Edison's scenario package for the scheduled Hay 28, 1992, NRC Evaluated Exercise for Pilgrim Nuclear Power Station. The enclosures adhere to FEMA's Guidance Memorandum EX-3, dated February 26, 1988, that stipulates the esercise scenario be submitted at least 60 days in advance of the exercise. The scenario package includes:

Scope and Objectives

Schedules a Contingency & Simulation Information

Controller and Player Information

Exercise Rules

Radiation Levels & Release Rates

Data / Messages (Plant, Radiochemhtry, Radiological)

If you have questions or require additional information, please contact Mr. David Landahl, Emergency Preparedness Onsite Division Manager,118 Long Pond Road, Plymouth, MA 02360, telephone (508) 747-9454.

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Page 2 j U. S. Nuclear Regulatory Commission i March 26,1992 BECo Ltr. No.92-033 ,

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cc: Mr. E. B. McCabe, Chief (2 copies)

Emergency Preparedness Section United States Nuclear Regulatory Commission ;

Region I 475 Allendale Road King of Prussia, PA 19405 Hr. R. B. Eaton, Project Manager - w/o Division of Reactor Projects - 1/II Offire of Nuclear Reactor Regulation Mali Stop: 14D1

0. e. Nuclear Reoulatory Commission -

1 White Flint sorth

11555 Rockville Pir.e .

Rockville HD 02852 U. S. Nuclear Regulatory Commission - w/o Region I 475 Allendale Road King of' Prussia, PA 19406 Senior NRC Resident inspector - w/o Pilgrim Nuclear Power Station

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BOSTON EDISON COMPANY PILGRIH NUCLEAR P0HER STAi!ON NRC EVALUATED EXERCISE 92-05-B TABLE Of CONTENTS -

1.0 INTRODUCTION

1.1 Schedule 1.2 Scope and Objectives 2.0 GUIDE!.INES 2.1 General Guidelines 2.2 Participant / Observer Guidelines 2.3 Controller Guidelines 2.4 Organization and facilities 2.5 Abbreviations 3.0 SCENARIO 3.1 Narrative 3.2 Event Timeline 4.0 OPERATIONAL INFORMATION 4.1 Messages 4.2 Plant Parameters 5.0 RADIOLOGICAL INFORMATION 51 Assumptions 5.2 Hessages and Trend Data

-5.3 Dose A;sessment 5.4 Count Room Data 5.5 In-Plant Radiation Data 5.6 Environmental Data 6.0 ti!NI-SCENARIO 6.1 .ou blic Information Summary

'2 . Public Information Messages 6.3 Corporate Scenario l

l EOF 4147-1

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BOSTON EDISON COMPANY PILGRIH NUCLEAR POWER STATION NRC EVALUATED EXERCISE 92- 05-B

1.0 INTRODUCTION

1.1 SCHEDULE A. Controller Briefina Date: Tuesday, May 26, 1992 Time: 0900 - 1600 hours0.0185 days 0.444 hours 0.00265 weeks 6.088e-4 months Place: Emergency Operations facility (EOF)

B. NRC/ Observer Briefina Date: Wednesday, May 27, 1992 Time: 1300 - 1500 hours0.0174 days 0.417 hours 0.00248 weeks 5.7075e-4 months Place: Emergency Operations facility (EOF)

C. Exercise Date: Thursday, May 28, 1992 Time: Unannounced D. Exercise Criticut Date: Friday, May 29, 1992 Time: 0900 - 1100 hours0.0127 days 0.306 hours 0.00182 weeks 4.1855e-4 months Place: Chiltonville Training Center Conference Rooms 6A and 6B E. Particicanti All designated PNPS personnel assigned to the following locations:

o Control Room (CR) o Control Room (Simulator) o Technical Support Center (TSC) o Operations Support Center (OSC) o Emergency Operations Facility (EOF) o Technical Assessment Group (TAG) o Media Center (HC) o Corporate Information Ctater (CIC) o Station Security o Town and Commonwealth 24 Hr Notification Points o Massachusetts Emergency Management Agency (HEMA) and Hassachusetts Department of Public Health (HDPH)

Representatives in the PNPS EOF l

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EOF 4147-2

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BOSTON EDISON COMPANY PILGRIH NUCLEAR POWER STATION NRC EVALUA1EO EXERCISE 92-05-B 1.2 SCOPE AND OBJECTIVES l

1.2.1 EXERCISE JCEE

- The 1902 Pilgrim Nuclear Power Station (PNPS) Emergency i Pres

redness Exercise, to be conducted on May 28, 1992 will ;

test :nd provide the opportunity to cvaluate the Boston Edison '

Emergency Plan and Emergency Plan Implementing Procedures. It will also test the emergency response organization's ability to assess, identify, classify and respond to emergency conditions and take appropriate actions to protect the health and safety of the public. In most cases, participants in this Exercise vary from those who participated on December 12, 1991.

The scenario will simulate a sequence of events resulting in a potential radiological accitent. The scenario has been developed to provide a more realistic sequence of events allowing for maximum " free play" and devi: ion making on the part of the PNPS imergency Response Organization (ERO).

The Exercise will limit the events that test the effectiveness of the integrated capabilities of Boston Idison's Emergency Responce Organization with the Commonwealth and local governments to protective action decision making related to emergency action levels and communication capabilities.

- The Cxercise will also interporate the Station's semi-annual health physics drill.

1.2.2 Q MITE OB2[Cl M S A. Exercise Plannina

1. Conduct an exercise of the Pilgrim Nuclear Power Station Emergency Plan (EP-AD-200. A.1).

2. Provide an opportunity for the Commonwealth of Massachusetts and the Towns of Carver, Ouxbury, Kingston, Marshfield, Plymouth, Bridgewater, and the City of Taunton <

to partially participate in an exercise (EP-AD-200, A.2).

3. Prepare an exercise information package to include:

a. The objectives of the exercise and appropriate evaluation criteria.

b. The date, time period, place and a list of participating organizations. ,

c. The sequence of simulated events,

d. The time schedule of real and simulated initiating events.

t e. The narrative summary (EP-AD-200, A.3). ,

EOF 4147-3

BOSTON EDISON COMPANY PILGRIM NUCLEAR P0HER STATION NRC EVALUATED EXERCISE 92-05-B A. Exercise Plannina (Continued)

4. Conduct a critique of the exercise (EP-AD-200, A.4),

b. Write the exercise report (EP-AD-iDO, A.4).

6. Identify open items (EP-AD-200, A.5).

B. Emftgency Organizations. Smp,J_ Land Resounn

1. Demonstrate the prompt activation, adequacy of the staffing and activation, as appropriate, of emergency -

response facilities as follows:

o Control Room (CR) (Simulator) o Technical Support Center (TSC) o Operations Support Center (OSC) o Emergency Operations facility (EOF) o Technicant Assessment Group (TAG) o Corporate Information Center (CIC) o Media Center (HC) (EP-AD-200, B.1)

2. Demon $trate the capability of the PNPS Emergency Responso Organi2ation to implement their Emergency Plan Impitmenting Proc 9dures (EP-AD-200, B. 2).

3. Demonstrate the ability of the Emergency Director to provide overall dirt >ction, including " command and control" '

by initiattni;, coordinatinc and implementing timely and effective decisions during 9 radiological emergency (EP-AD-200, B.3). -

4. Demonstrate the ability to effectively transfer command and control of emergency response functions from the Control Room to the EOF (EP-AD-200, B.4).

5. Demonstrate the ability to contrci access to emergency response facilities (EP-AD-200 B.7).

6. Demonstrate tne ability of corporate personnel to augment and support the plant staff (EP-/sD-200, B.12).

7. Demonstrate the ability to notify on-call emergency response personnel and document acceptable response times (EP-AD-200, B.13).

C. Lrd;ideatliit1Fent ani_GAu11RLthri

1. Demonstrate the availability of methods, equipment, and expertise to mate rapid assessments of the consequences of any raciological hazards, including the dispatch and

' coordination of Radiation Monitoring Teams (RHT)

(EP-Ad-200, C.1).

EOF 4147-4

BOSTON EDISON COMPANY PILGRIM NUCLEAR POWER STATION NRC EVALUATED EXERCISE 92-05-8 C. Incident Assessment and Classification (Continued)

2. Demonstrate the ability to recognize emergency action levels (EAls, and properly classify actual or potential emergencies in accordance with the PNPS Emergency Plan Implementing Procedure EP-IP-100 (EP-AD-200 C.2).

D. Notification and Communicationi

1. Demonstrate the ability to develop and notify offsite emergency organizations within 15 minutes of each emergency classification at PNPS (EP-AD-200, D.1).

2. Demonstrate the ability to notify the NRC of any emergency classification within one hour of the declaration (EP-AD-200 D.2).

3. Demonstrate the ability to nctify PNPS Emergency Response Organization personnel (EP-AD-200. D.3).

4. Demonstrate the ability to develop and send timely information messages fc offsite authorities (EP-AD-200 D.4).

5. Demonstrate the connunications capability among the Control Room, TSC, OSC, EOF, TAG, CIC and Media Center (EP-AD-200, D.5).

6. Demonstrate the adequacy of communications capabilities between PNPS and the Radiation Monitoring Teams (EP-Ad-200, 0.8).

7. Demonstrate the operability of communication equipment between the PNPS Control Coom, EOF and NRC Region 1 (ENS)

(EP-AD-200, D.10).

E. Radioloaical Conseavence Assessment

! 1. Demonstrate methods and techniques for determining the

! source term or releases or potential releases of radioactive material (EP-AD-200, E.1).

2. Demoritrate the ability to continuously monitor and contral emergency worker radiation exposure, and implement i exposure guidelines as appropriate (EP-AD-200, E.4).

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E0F 4147-5.

BOSTON EDISON CCHPANY PILCRIM NUCLEAR POWER STATION NRC EVALUATED EXERCISE 92-05-B F. BillLlafErnlign '

l. Demonstrate the operations of the Media Center and the availability of space for the media (EP-AD-200, G.1).

2. Demonstrate the ability to brief the media in a clear, accurate and timely manner (EP-AD-200, G.2).

3. Demonstrate the ability 40 establish and operate rumor ccttrol in a e,oordinated fashion (EP-AD-200, G.4).

G. Bitsygny_ffe,ation1

1. Demenstrate the availability of procedures to support reentry and recovery:

" a. De-escalation / termination from the emergency phasa, and transition to the recovery phata.

b. Inforin the Commonwealth of the opportunity to reduce the need for protective actions (EP-AD-200, H.1).

2. Demonstratt the availability of corporate and technical support for planring and reentry / recovery opetations (EP-AD-200, H.3).

H. O_ther

1. Demonstrate the availabiitty of personnel to carry out in platit assignments, as required, by the Nuclear Operations Supervisor (NOS) in the Control Room, prior to TSC/0SC activation (Exercise Inspection 50-293/91-28, 4 !).

2. Demonstrate a formal process for the assignments and I prioritizction of TSC tasks, duties, and responsibilities by the Emergency Plant Manager (Exercise Inspection 50-293/91 28, 4.2). ,

3. Demonstrate the ability to effectively coordinate reentry teams from the OSC (Exercise Inspection 50-293/91-28, 4.3).

I EOF 4147-6

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BOSTON EDISON COMPANY PILGRIM NUCLEAR POWER STATION NRC EVAlbATED EXERCISE I 92-05-B l

2.0 GUIDE..INES 2.1 GENERAL GUIDELINES In the development of an accident sequence which is severe enough to adequately test the emergency response capabilities of participating organizations, it is necessary tc postulate extremely unrealistic situations and multiple failures of redendant reactor protection functions and systems.

The objective of this Exercise is to demonstrate the ability of the participating organizations to prctect the public, and appropriately respond to this highly improbable sequence of events.

Emergency response actions during the simulated emergency will include recognition and classification of emergency conditions, assessment of onsite/offsite radiological consequences, alert / notification and mobilization of emergency response organizations, activation / operation of emer;ency response f acilities and equipment, implementation of in-plant correcthe actions, preparation of rtports, messages, and recordkeeping, and recommendation of protective actions.

The conduct of the Exercise will demonstrate the effectiveness of organizations, personnei, emergency response functions, and PNPS Emergency Plan and Implementing Procedures.

The Control Room Simulator and the Emergency Operations Jacility are the central points for distribution of exercise messages. Simulated plc,nt parameters will be provided to the control room operators usir,g messages and plant Jata sheets should the simulator fail. Radiological and meteorolcgical data presented in Sections 8.0 is not provided to players automatically, but is distributed by controllers when players demonstrate the capability to obtain that information from appropriate sources. At no time, unless noted specifically as an exception, will information be interjected at a point where it would not be available in a real emergency. The Lead Exercise Controller may interject other information or change a message to ensure that the Exercise progresses as planned.

The contingency messages are to be delivered to the designated players upon completion of a specific action or accomplishment of certain previously specified criteria. The information contained in the controller notes in Section 6.0 and information in Sections 7.0 and 8.0 are for use by Observer / Controllers only and is to be disseminated to players only when the ability to obtain the information from actual sources is demonstrated.

EOF 4147-7 i

BOSTON EDISON COMPANY PILGRIH NUCLEAR POWER STATION NRC EVALUATED EXERCISE 92-05-B 2.1 GENERAL GUIDELINES (Continued)

The Exercise Players are expected to " free play" the scenario to the extent practical. Notifications of, and contatt with, supervisors, plant management, and corporate management will be made in accordance with the corporate and site implementing procedures.

Since it is required that the emergency Exercise test offsite emergency activities it was necessary to postulate non-credible situations. The Players should accept the Exercise Messages as written. If corretthe actions could be postulated that would terminate the emergency, they should be identified by the Players to the lead Facility Controller so that credit can be given for postulated actions.

Notifications of, and communications with, offsite agencies, including the NRC, will be made in accordance with appropriate irrplementing procedure, unless otherwise directed by the lead facility controller. The Plant Emergency Alarm shall be sounded and site-wide announcements shall be made as appropriate to the development of the Exercise scenario. If directed by these announcements, a site evacuation will be performed.

The postulated accident conditions will rcsult in a simulated radiological release which necessitates the consideration of protective actions for plant personnel and the general public, Heteorological conditions may be varied throughout the exercise.

Participants will perform appropriate radiological monitoring and dose assessment activities. Onsite BECo emergency response personnel shall use required protective clothing, if appropriate.

Participation by BECo onsite personnel directly involved in responding to an emergency shall be carried out to the fullest extent possible, including the deployment of radiological monitoring teams, emergency ,

repair teams, and other emergency workers.

Due to time and logistical constraints, it will be necessary to accelerate certain parameters, data and events that pertain to fuel damage. If required by the scenario,' reactor coolant and/or containment atmosphere

" grab" samples will be obtained and analyzed utilizing the Post Accident Sampling System (PASS) (simulated). However, resulting data will be simulated through the appropriate controller.

Since there are several off site segments of the Exercise that depend on proper messages between the Control Room, TSC, OSC, and EOF, notification messages between these contact points will be reviewed by the Controller / Evaluators prior to their issJance. The Controller / Evaluator may inject other information o, change a message to ensure that the Exercise progresses as planned. Only Lead Facility Controllers can modify Exercise Hessages or initiate Frte Play Messages.

EOF 4147-8

BOSTON EDISON COMPANY PILGRIM NUCLEAR P0HER STATION NRC EVALUATED EXERCIfF 92-05-B 2.1.1 [ELUATION AND GlllM The Exercise will be observed by Controllers / Evaluators who have the qualifications to evaluate the activity in their assigned locations. Evaluation of the Exercise will be based on the requirements containea in the Emergency Plan and Implementing Procedures. Controller / Evaluators will prepare evaluation fctms and provide recommendations on corrective actions to the Lead Exercise Controller.

Immediately following the Exercise, the Exercise Coordinator will conduct a Lead Controller de-briefing. Negative and positive items will be identified for inclusion in the Exercise Report.

2.1.2 f,1 BC13E REPORT An Exercise Report shall be issued in accordance with the Emergency Plan and Departmental Administrative Procedures for review within 30 working days following the exercise.

The designated report reviewer (s)/ author (s) will determine whether any deficiencies and/or corrective actions are required. Approval of identified corrective acticas are required.

2.2 PARTICIPANT /0BSERVER GUIDELINES 2.2.1 PLAYER INSTRUCTIONS The success of the Exercise is largely dependent on player performance. Appropriate reaction to simulated emergency conditions and demonstrated competence in the Emergency Plan and Implementing Proceduret are the key criteria by which the players are evaluated. It is imperative, therefore, that all player actions and activities are witnessed by a Observer / Controller.

Those actions that are to be simulated must be brought to the attention of the Observer / Controller to ensure that credit is awarded. Observation of response actions taken is mandatory for credit to be given for demonstration of an objective. Players are requested to observe the following guidelines:

Maintain a serious attitude throughout the Exercise; this is especially true late in the Exercise or when activity is limited.

Be courteous and professional at all times.

EOF 4147-9

BOSTON EDfSON COMPANY PZLGRTH NUCLEAR POWER STATION NRC EVALUATED EXERCISE 92-05-B 2.2.1 PLAYER INSTRUCTION 3 (Continued) -

Identify yourself by name and function to the Observer /

Controller.

Elements of Exercise play will be introduced through use of controlled Exercist messages and information generated by Players as a result of the particular Emergency activity performed. Therefore, be responsible for initiating actions in accordance with instructions and your responsibilities.

Communications should be concise and formal; always include "This is a drill."

Use and demonstrate knowledge of the Emergency Plans and Implementing Procedures.

Use all resources and equipment available, as you would in an actual emergency.

Remember, one of the main purposes of an F.rercise is for you, the player, to assure yourself that you are adequately prepared; areas for improvement or lessons learred, when identifiad, Jll improve your overall emergency preparedness; marked-up pror "res or action items can be sent to D1ve Landahl, Onsite Emergency Preparedness Division Hanager, 118 Long Pond Road, or call 747-9454

CONTROLLERS serve an active role in the Exercise by providing messages or instructions to the participants. They may also serve to initiate certain actions to assure continuity of the events described in the Exercise scenario. They also serve as EVALUATORS.

EVALUATORS will be noting all actions, both positive and negative. They will be the main source of input to the BECo critique.

NRC Evaluators will be critiquing the Exercise and the performance of the participants.

Play out all actions, as much as possible, in accorcance with the Emergency Plan and Procedures as if it were a real emergency.

EOF 4147-10

BOSTON EDISDN COMPANY PILGRIH NUCLEAR POWER STATION NRC EVALUATED EXERCISE 92-05-8 2.2.1 PLAYER INSTRUCTLOSS (Continued)

Identify your actions to the Controller, speak out loud, identifying your key actions and decisions to the Controllers and federal Evaluators. This may seem artificial, but it will assist in the evaluation process and is to your benefit, e Any messages transmitted over communication lines or radios shall be preceded and followed by the statement that "lhls ii_A Drill".

You should play as if radiation levels are actually present, in accordance with the information you have received. Unless otherwise specified, this will require normal radiological control measures including the wearing of protective clothing.

Non-participants are exempt from acting on radiation levels specified for the emergency Exercise. However, normal radiological control practices shall be followed throughout the course of the Exercise.

Several plant and radiological parameters will be available upon request at any time or at predetermined times during the Exercise. These plant parameters will be available in the Control Room.

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

QO NOT BECOME OVERLY CONCERNED HITH THE HECHANICS OF THE REACTOR OR THE CAUSE OF THE ACCIDENT. THIS EXERCISE IS DESIGNED TO TEST BECo PLANS AND PROCEDURES AND IS NOT CONCERNED HITH ESTABLISHING l THE PROEABILITY, FEASIBILITY OR DETAILFO HECHANICS OF THE i

SIMULATED ACCIDENT.

l e There will be one or more Controllers at ear.h 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. Controllers will aise observe all aspects of the Exercise to prepare an in-house evaluation of plan , proctdures and training.

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BOSTON EDISON COMPANY PILGRIH NUCLEAR POWER STATION NRC EVALUATED EXERCISE 92-05-B 2.2.1 ELAl[R INSTRU;TIONS (Continued) '

Any participants outside the Media Center or plent property who encounter members of the news media during the Exercise should avoid responding to any questions regarding the simulated events or the success of the Exercise. All press inquiries should be directed to the Media Center at Hercrial Hall, in Plymouth.

Do not take actions that would result in actual alterations of valve and switch positions in response to scenario simulations.

Any event or operation outside the scenario that results in an actual or potential danger to plant operation or safety will take precedence over Exercise activity.

Any BECo motor vehicle response to this Exercise, will observe all normal motor vehicle operating laws including posted speed limits, stop lights / signs, one way streets, etc.

Should any onsite security actions be required in response to this Exercise, Exercise Participants are to cooperate as directed by the Security Force; Security representatives are to be prudent and tolerant in their actions.

While Exercise participants are to inject as much realism into the Exercise as possible, the safety of the plant and personnel shall not be jeopardized.

2.2.2 QSSERVER GQlD1LINL1 Observers should not participate in the Exercise nor interfere in the actions taken by the Exercise Participants, Controllers or Evaluators. Questions should be directed to Controllers, not participants.

The event times and scenario are confidential and shoulc be kept so during the Exercise. Do not discuss these with the participants.

Identification badges / arm-bands /etc. are to be worn visibly by the Observers. Identification devices 5hould be returned at the erd of the Exercise or critique. Identify yourself to the Exercise Contrcliers.

Observers should enter emergency facilities via their main entrance and check in with security personnel.

Observers requiring emergency facility access during the Exercise should contact Dave Landahl, Boston Edison Onsite Emergency Preparedness Division Hanager, 118 Long Pond Road, or call 747-9455 two (2) weeks prior to the Exercise.

EOF 4147-12

BOSTON EDISON COMPANY PILGRIM NUCLEAR POWER STATION NRC EVALUATED EXERCISE 92-05-B 2.3 CONTROLLER GUIDELINES 2.3.1 LINERAL INf0RMA11QS Each Controller / Evaluator should be familiar with the following:

The basic objectives of the Exercise.

The assumptions and precautions being taken.

The Exercise scenario, including the initiating events and the expected course of action to be taken.

The various locations that will be involved and the specific items to be observed at those locations.

The evaluation checklists provided herein.

2.3.2 PRECAUTIONS AND L1HITATIONS This section provides guidance for all Exercise Controllers and Evaluators for the conduct of this Exercise. Prior to initiation of the Exercise. briefing will be held to review the entire Etercise process with all the exercise Controllers / Evaluators identified in this manual.

Should, at any time during the course of the conduct of this exercise, an actual emergency situation arise, all activities and communications related to the Exercise will be suspended.

It will be the responsibility of any Exercise Controller /

Evaluator that becomes aware of an actual emergency to suspend Exercise response in his/her immediate area and to inform the Lead Exercise Controller of the situation. Upon notification of an actual emergency, the Lead Exercise Controller will notify all other Controllers / Evaluators to suspend all Exercise activities. The Lead Exercise Controller will make a determination at that point whether to continue, place a temporary hold on, or terminate the exercise.

Should, at any time during the course of the conduct of this exercise, an Exercise Controller / Evaluator witness an exercise participant undertake any action which would, in the opinion of the Controller / Evaluator, place either an individual or component in an unsafe condition, the Controller / Evaluator is responsible for intervening in the individual's actions and terminating the unsafe activity immediately. Upon termination of the activity, the Controller / Evaluator is responsible for contacting the Lead Exercise Controller and informing him of the situation. The Lead Exercise Controller will make a determination at that point whether to continue, place a temporary nold on, or terminate the exercise.

EOF 4147-13

BOSTON EDISON COMPANY PILGRIM NUCLEAR POWER STATION NRC EVALUATED EXERCISE 92-05-8 2.3.2 PRECAUTIONS AND L1HITATIONS (Continued) -

Manipulation of any plant operating system, valves, breakers, or controls in response to this Exerciso are only to be simulated.

There is to be no altecation of any plant operating equipment, systems, or circuits during the response to this exercise.

No pressurization of fire hoses, discharging of fire extinguishers, or initiation of any fire suppression systems will be required for the exercise.

All repair activities associcted with the scenario will be simulated, with extreme caution errphasized around operating equipment.

All telephone communications, radio transmissions, and public address announcements related to the Exercise must begin and end with the statement, "This is a drill." Should a Controller /

Evaluator witness an exercise participant not observing this practice, it is the Controller / Evaluator's responsibility to remind the individual of the need to follow this procedure.

Any BECo motor vehicle response to this Exercise, should observe all normal motor vehicle operating laws including posted speed limits, stop lights / signs, one way streets, etc.

Should any onsite security actions be required in response to this Exercise, Exercise participants are to cooperate as directed by the Security Force, and security representatives are to be prudent and tolerant in their actions.

Exercise participants are to inject as much realism into the exercise as is consistent with its safe performance; however, caution must be used to prevent over-reaction.

Care must be taken to prevent any non-participating individuals who may observe Exercise activities from believing that an

actual emergency exists. Any Exercise Controller / Evaluator who is aware of an individual or group of individuals in the l immediate vicinity who may have become alarmed or confused about l the situation, should approach that individual or group and l explain the nature of the exercise and its intent.

l

If you are entering nuclear station radiation areas, observe all rules and procedures; no one (including Observer / Controllers) is exempt from normal station radiological practices and procedures.

NOTE: 00 NOT ENTER HIGH RADIATION AREAS IN THE PLANT; FOLLOH ALARA PRINCIPLES EOF 4147-14

BOSTOM EDISON COMPANY PILGRIH NUCLEAR POWER STATION NRC EVALUATED EXERCISE 92-05-8 2.3.3 [QNTROLLER/ EVALUATOR INSTRUCTIONS

Controller / Evaluators will position themselves at their assigned locations 30 minutes prior to the activation of the facility for which they have responsibility. '

Controller Communications will be tested prior to exercise commencement. All watches and clocks will be synchronized with the Lead Exercise Controller as part of the communications testing.

All Controller /Ev01uators will comply with instructions from the Lead Exercise Coatroller.

Each Controller / Evaluator will have copies of the messages controlling tne progress of the Exercise scenario. No message shall bis delivered out of sequence or other than as written unless sper.ifically authorized by the Lead facility / Functional Area Contioller.

Hesshe'es controlling the progress of the scenario are noted with -

a nu".oer and the facility designator. Contingency messages are noted with a number followed by the facility designator and the letter "X" (e.g., 1-CRX). Contingency messages are only delivered if certain conditions indicated on the message are met.

Each onsite Controller / Evaluator will have copies of plant data sheets. Data sheets will be distributed only in the Control Room should the simulator fail.

Controller / Evaluators will ng_t provide information to the Players regarding scenario progression or resolution of problems encountered in the course of the simulated emergency. The exercise participants are expected to obtain information through their own organizations and Exercise their own judgment in determining response actions and resolving problems, e Some Players may insist that certain parts of the scenario are

unrealistic. The Lead Controller / Evaluators have the sole authority to clarify any questions regarding scenario content.

2.3.4 EVALUATION INSTRUCTIONS / PACKAGES l Each Controller / Evaluator will take detailed notes regarding the

! progress of the Exercise and response of tne Exercise participants l at their assigned locations. Each Controller / Evaluator should carefully note the arrival and departure tices of participants, the times when major activities or milestones occur, and problem areas encountered.

EOF 4147-15 i

BOSTON EDISON COMPANY l PILGRIM NUCLEAR POWER STATION i NRC EVALUATED EXERCISE 92-OS-B 2.3.4 fyALUATION INSTRUCTIO15/ PACKAGES -

The standards below should be used by the controller to evaluate assigned areas pertaining to the emergency response. A dual purpose will be served by this rating system. First, the capability of each facility or response area will be evaluated and second, the system will provide a vehicle for guiding and directing improvement. The rating scale is as follows:

Satisfactory - Personnel and equipment performed as required. Any errors or problems were minor and easily correctable, litroinal - Personnel and equipment generally performed as expected. Any errort noted were not severe and could be corrected without undue labor or expense.

Unsatisfactory - Personnel and equipment generally performed below expectations and there were several significant deficiencies noted. The area's ability to carry out its functions was diminished.

!LA - Not applicable to the situation or not observed.

HQ - Not Observers 2.3.5 EVALUATION COMMENTS Controller / Evaluator comth.its should consider the demonstration of the following facility and team evaluation elements:

Facilities '

Command and Control

Accurate and timely determination of emergency action levels.

Timely activation and staf fing of each emergency facility.

Familiarity of personnel with appropriate emergency instructions, duties and responsibilities. .

Timely notification of plant, corporate, local, Commonwealth and Federal personnel / agencies (informatien updates performed).

Adequacy of internal information systems (i.e., message bandling, displays, status boards and maps).

Properly tontrolled documentation and accurate, timely record l keeping.

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! EOF 4147-16 i

i BOSTON EDISON COMPANY PILGRIM NUCLEAR POWER STATION NRC EVALUATED EXERCISE <

92-05-B 2.3.5 EVALUATION COMMENTS

Utilization of correct communications procedures and techniques.

Capability of facility supervisor / directors to interface with personnel and coordinate facility activities.

Adequacy of interface between emergency response facilities.

Adequacy of equipment snd supplies.

Timely initiation of onsite protective / corrective actions.

Development of protective action recommendations.

- Radiological surveys and assessment of plant damage and hazardous conditions performed.

Timely request of emergency support services.

Coordinated, accurate and orderly dissemination of information to the news media.

Teams

Timely notification and activation.

Adequacy of staffing.

Familiarity with appropriate emergency procedures, duties and responsibilities.

Availability and utilization of proper equipment.

Performance of contamination / decontamination control.

Proper interface with emergency support personnel.

Utilization of correct communications instructions and techniques.

Ava' lability of reference documents to team members.

Utilization of proper radiological control practices (i.e.,

access control, protective clothing, shielding, stay time).

Performance of radiological surveys.

Timely and proper performance of damage assessment.

EOF 4147-17

BOSTON EDISON COMPANY PILGRIM NUCLEAR POWER STATION NRC EVALUATED EXERCISE 92-05-B

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2.3.5 [VAWATION COMMENTS (Continued)

Properly maintained survey records and maps.

e Adequacy of briefing sessions prior to dispatch.

Direction and control by team leaders.

Timely requests for offsite assistance.

Coordination and interface between emergency response team members, e Proper interface with plant supervisory personnel.

Controllers / observers will record their comments for the purpose of reconstructing the exercise chronology and preparing a written evaluation of the exercise.

2.3,6 EVALUATION PACKAGES The following Evaluation packages are to be used by the appropriate Controllers / Observers to evaluate the 1992 NRC Exercise:

Control Room (Simulator)

Technical Support Center Operations Support Center Environmental Monitoring Team Onsite Honitoring Team Emergency Operations facility Media Center Technical Assessment Group Radiation Honitoring Teams Security-Corporate Information Center 2.3.7 EVALUATION PROCESS All evaluators shall maintain an Exercise chronology. This chronology shall be of sufficient detail to enable subsequent completion of the appropriate evaluation form. It should contain a synopsis of significant exercise events, actions taken (or not taken) by players, questions noted, and positive as well as negative assessments made ty the evaluator. This chronological record may be used to corroborate critique items that are questioned by participants.

Each Evaluator shall also complete an evaluation form for the facility or function to which he (she) is assigned.

EOF 4147-18

BOSTON EDISON COMPANY PILGRlH NUCLEAR POWER STATION NRC EVALUATED EXERCISE 92-05-B 2.3.7 EVALUATION PROCESS (Continued)

Each lead Controller shall de-brief the evaluators for whom he/she is responsible and compile en Exercise Evaluation Report Sheet for the facility. This Evaluation Report Sheet shali reflect an overall assessment of the performance of that facility, and in five (5) specific categories. Significant weaknesses or deficiencies shall be itemized in the " Report" section to ensure adequate follow-up attention is devoted to resolution of the problem, Significant positive items should be included here as well.

The formal Post-Exercise Critique shall be conducted by the Exercise Coordinator, with each Lead Controller providing an evaluation of his/her facility.

1 EOF 4147-19

BOSTON EDTSON COMPANY PILGRIM NUCLEAR POWER STATION NRC EVALUATED EXERCISE 92-05-B 2.3,8 CONTROLLER ASSIGNMENTS '

ar_ea of Resoonsibility Egne LEAD CONTROLLER Jerrie Morlino SIMULATOR Kelly Walker Leo Nichols Tom Beneduci Kathie Ar:indt CONTROL ROOH (CR1 LEAD CONTROLLER To Be Determined TECHNICAL SUPPORT CENTER (TSC)

LEAD Paul Cafarella Nancy Desmond Bill O'Keefe OPERATIONS SUPPORT CENTER (OSCl LEAD Don Pierce Mechanical Fran Coulstring Hechanical Al Hester ILC Ken Johnson I&C Joe Freeman i Electrical Don Carpeno Electrical Robert Bumpus RP Mike Christopher RP Chemistry Lisa Sabard EMERGENCY OPERATIONS FACILITY (EOF)

LEAD Dave Landahl Dose Assessment Scott McCain Communications Doug Sukanek logistics John Waters RHT Team RHT Team RHT Team Security John McEachern Public Information EOF 4147-20

BOSTON EDISON COMPANY PlLGRIH NUCLEAR POWER STATION NRC EVALUATED EXERCISE 92-05-B 2.3.8 CQ11RQLLER ASSIGNMENTS (Continued)

Area of Responsibility Etml TECHNICAL ASSESSMENT GROUP (TAG 1 LEAD Dave Long MEDIA CENTER (MC)

LEAD T. Kelley CORPORATE INFORKATION CENTER (CIC)

LEAD (20th Floor)

Media Monitor Phone Team Controller EOF 4147-21

BOSTON E0!S0h COMPANY P!LGRlM NUCLEAR POWER STATION NRC EVALUATED EXERCISE 92-05-B

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2.4 EXERCISE ORGANIZATION AND FACILITIES 2.4.1 Exercise Oraanizations The organization for this exercise will consist of the Lead Exercise Controller, the Controller / Evaluators, the Exercise Players, and the Observers, as follows:

A. Lead Exercise Controller The Lead Exercise Controller is responsible for the conduct of a successful Exercise and will coordinate Exercise preparatiors including the development of the scenario and messages. The Lead Exercise Controller will ensure the safe conduct of the Exercise and is responsible for resolution of any scenario.related interfacility questions, as well as the assurance that the conduct of the Exercise does not adversely impact the operation of the station. The Lead Exercise Controller will coordinate the preparation of a consolidated evaluation package and prepare an itemized list of corrective actions recommended as a result of the evaluation and critique.

B. Controller / Evaluators The Controller / Evaluators are personnel selected to deliver Exercise Messages to designated players at specific times and places during the Exercise. They will inject or deliver additional messages, as may be required, to initiate appropriate player response to keep the Exercise action moving according to the scenario and to ensure the demonstration of all Exercise objectives. The Controller / Evaluators will be briefed on the instructions contained in this Exercise Manual.

As Controller / Evaluators, they are assigned to observe the Exercise and to judge the effectiveness of selected organizations, personnel, functions, and activities in response to the simulated emergency situation. Selection of Controller / Evaluators is based on their expertise and qualifications to evhluate an assigned activity or area. They will record their observations using an evaluation form and

-provide recommendations on corrective actions to the Lead Exercise Controller prior to the scheduled critique. They will evaluate Exercise performance on the basi' of standards or requirements contained in the PNPS Eme*yency Plan, Emergency Operations Procedures (EOP's) and the associated Implementing Procedures. They will take steps, shenever possible, to collect data on the time-and-motion aspercs of the activities observed for post-Exercise use in designating and implementing system improvements. A Lead Controll er/ Evaluator is assigned to each emergency response facility. Each Lead Controller / Evaluator is responsible for all Controller, Evaluator, and Observer activities within that faci'ity.

EOF 4147-22

BOSTON EDISON COMPANY PILGRIH NUCLEAR POWER STATION NRC EVALUATED EXERCISE 92-05-0 2.4.1 IX BCISE ORGANIZATIONS (Continued)

C. Exercise Players The Players include BECo personnel assigned to perform emergency functions as described in the Emergency Plan and Implementing Procedures. Players from offsite organizations and agencies (Commonwealth and local) are participants as they would.be during an actual emergency situation.

The success of the exercise is largely dependent upon player reaction, and knowledge of the Emergency Plans and Implementing Procedures, and an understanding of the Exercise objectives.

Initial conditions will be provided by Controller / Evaluators as appropriate. The Exercise Players are responsible for initiating actions during the Exercise in accordance with procedures, responsibilities, and tasks outlined for their particular function in the Emergency Plan and Implementing Procedures. Each Exercise Player will advise their Controller / Evaluator prior to simJiating required emergency actions to ensure that credit is awarded. ,

Exercise Players should not to be excessively concerned with the mechanics of the scenario. This Exercise is designed to evaluate the Emergency Plan, the Implementing Procedures, and the emergency preparedness training program, and is not concerned with the probability, feasibility, or detailed mechanics of the simulated accident. Exercise Players should note any needed improvements that come to their attention during the Exercise and submit them h the appropriate Controller / Evaluator at the conclusion of the Exercise.

D. Evaluators Evaluators include members of the NRC, INPO, or FEMA evaluation teams and they will have prior knowledge of the Exercise scenario. They will observe the Exercise and evaluate the ability to protect the health and safety of the public. The NRC will be present their findings at the post-exercise critique.

E. Observers Observers from BECo and other organizations may be authorized, on a limited basis, to participate in the Exercise solely for the p_urpose of observing Exercise activity for personal education. Observers will report initially to the Onsite Emergency Preparedness Division Hanager for credential review and authorized admittance. They will be provided with Exercise information as required. Requests to participate as an Observer will be made in writing and conhin the Observer's full name, home address and phone number, and organization affiliation.

Requests to participate as Observers will be submitted to the Onsite Emergency Preparedness Division Hanager no later than two weeks prior to the exercise.

E0F 4147-23

BOSTON FDISON COMPANY PILGRIM NUCLEAR POWER STATION NRC EVALUATED EXERCISE 92-05-8 2.4.2 ENERGENCY RESPONSE FACIllIJ13 During this Exercise, the following PNPS Emergency Response Facilities will be activated to manage, assess and support the i response to the simulated emergency radiological.

A. Control Room (CR) (Simulator will be used in lieu of CR)

The Control Room is desionated to be habitable under emergency conditions. The Control Moom contains those controls, instruments, and communications equipment necessary for operation of plant under both normal and Emergency conditions.

The ventilation system, shielding, and structural integrity are designed and built to permit continuous occupancy during the postulated design basis accident.

The Nuclear Hatch Engineer (NHE) maintains the responsibility for directing operations in the Control Room. The Control Room is 'cated on the 37' level of the turbine building.

The equipment available in tE Control Room provides early c

warning of a potential emergency situation and provides for a continuir.g evaluation of the Emergency situation.

Heteorological data is available from a meteorological tower which transmits wind speed and direction data to the Control Room. Respiratory protettion equipment, anti-contamination clothing, portable survey instruments, counting equip snt, tools, and rescue equipment are readily available within the Station.

B. Technical Support Center (TSC)

The Technical Support Center is located within the Protected Area on the first floor of the Administration Building. A separate office area within the Technical Support Crnter is available for Nuclear Regulatory Commission (NRC) personnei.

This office contains telephone communications equipment. lhe TSC is of sufficient size to accommodate approximately 25 people. The TSC is equipped and staffed to provide expert technical capability to assess plant status ar, make recommendations on plant operations to the Control Room.

The TSC is activated upon declaration of an Alert, Site Area Emergency, and/or General Emergency. A closed circuit television monitor transmits pertinent instrument readings from the Control Room to the Technical Support Center. This monitor is controlled by TSC personnel and may be used to view instrumentation throughout the Control Room.

EOF 4147-24

BOSTON EDISON COMPANY PILGRIM NUCLEAR P0HER STATION NRC EVALUATED EXERCISE 92-05-3 2.4.2 EMERGENCY RESPONSE FACILITIES (Continued) -

The Emergency Plant Manager retoondt to the Techhical Support Center. Adequate commuhications with the cot rol room, other emergency facilities and offsite organications is available.

The TSC has dedicated telephone lines between the control room and TSC. Additionally, both the control room and TSC have access to the Station paging system (Gai-tronics) and the Station internal telephone system to further enhance communication. The TSC has direct communication with the Control Room, the E0F, and NRC Headquarters in Bethesda,

Maryland, and the Regional NRC Office in King of Prussia, Pennsylvania.

C. Operations Support Center (OSC)

An Operations Support Center has been established in the new Administration Building adjacent to the TSC. The Operations support function is to provide personnel (non-Control Room shift

. personnel) in support of emergency re-entry / repair teams. The l OSC Supervisor is responsible to the Shift Supervisor and/or the l

Emergency Plant Manager. Direct communication with the Technical Support Center is possible. Necessary equipment is

available throughout the Station and may be accessed by personnel assigned to the OSC.

D. Emergency Operations facility (EOF)

The EOF is located in the basement of the Sheriff's facility on the grounds of the Plymouth County House of Correction in Plymouth, approximately four (4) miles west of Pilgrim Station.

The EOF is a BECo controlled and operated facility. During an emergency, the EOF is staffed and equipped to provide the overall BECo emergency response; coordination of radiological and environmental assessment; development of protective action ricommendations for the general public; and coordination of emergency response activities with Federal, Commonwealth and l local agencies. Security personnel will be assigned to control EOF access.

The EOF consists of the Operations Room, the Communications Room, conference rooms and several office areas. In. addition to the pre-designated BECo staff, the EOF has space to accommodate nine (9) NRC representatives as well as representatives from FEMA, MDPH and H=ssachusetts Emergency Management Agency (HEMA) and key local authorities. If necessary, the EOF may be used to accommodate outside technical support groups and elements of the Recovery Center staff.

EOF 4147-25

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BOSTON EDISON COMPANY PILGRIM NUCLEAR POWER STATION NRC EVALUATED EXERCISE 92-05-B 2.4.2 EMERGENCY RESPONSE FACILITIES (Continued)

D. Emergency Operations facility (EOF) (Continued)

The primary function of the EOF is to provide management of the overall emergency response to any event at an Alert or higher classification. The E0F provides radiological and meteorological data to assess offsite radiation levels. This information is used by EOF personnel to update / inform the NRC and Commonwealth and local emergency response agencies about conditions potentially affecting the public in accordante with the Emergency Plan.

E. Media Center (HC)

The Hedia Center is located at the Memorial Hall in Plymouth, approximately five (5) miles northwest of the Pilgrim Station.

The Media Center is a joint facility, staffed and operated by Boston Edison Company, HEHA, HDPH, and the five towns located within the ten mile emergency planning zone (EPZ). The primary purpose of the facility is to provide a central locaticn for the coordination of public information prior to its release to the ,

news media. The communications capabilities include standard telephones, ring-down telephone link to the EOF, computer link to the EOF and CIC and telecopy links to all offsite agencies.

The Media Center provides the news media with a single location to receive information about the emergency developments at the Pilgrim Nuclear Station, local, commonwealth and offsite response. The Center includes work areas for BECo, each offsite agency, and the news media, there is also a briefing area for joint news conferences.

F. Corporate Information Center (CIC)

The Corporate Information Center is located at the Boston Edison Company headquarters in the Prudential Center, Boston, Massachusetts. The primary purpose of the CIC is to provide emergency information to BECo employees, customers and governmental agencies. The emergency teams responsible for rumor control are located at this facility. They include the Public Concern Team (responsible for responding to calls from the general public and the Media Phone Teams (responsible for responding to calls for monitoring the news media reports for ,

rumors or misinformation). The CIC receives information about the emergency from the Media Center and reports rumors, misinformation and trends of inquiries to the Media Center for resolution.

EOF 4147-26

BOSTON EDISON COHPANY PILGRIM NUCLEAR POWER STATION NRC EVALUATED EXERCISE 92-05-0 2.4.2 EMERGENCY RESPONSE FACILITIES (Continued)

G. Technical Assessment Group (TAG)

The Technical Assessment Group is located at the BECo Nuclear Engineering Of fices in Braintree, KA. The TAG provides technical and engineering support to the TSC staff at Pilgrim Nuclear Power Station. The TAG Coordinator is responsible for coordinating activities, including requests from the TSC. fhe TAG Coordinator reports directly to the TSC Supervisor. The TAG is equipped with nedicated communications to the EOF, TSC and the Control Room.

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EOF 4147-27

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BOSTON EDISON COMPANY PILGRIM NUCLEAR POWER STATION NRC EVALUATED EXERCISE 92-05-B i j

2.5 ABBREVIATIONS Assianment 19La AC A/E Alternating Current EAL Architect Engineer ALARA Emergency Action Level ADS APRH As low As Reasonably Achievatie ARM Automatic Depressurization System Average Power Range Monitor ATHS BOC Area Radiation Honitor Anticipated Transient Hithout Scram BWR Beginning of Cycle CAM (s) Boiling Hater Reactor CAS CFR Continuous Air Honitor(s)

CIC Central Alarm Station a Code of Federal Regulations CIV Corporate Information Center CTHT CST Combined Intermediate (Intercept) Valve Containment CRD Crsdensate Storage Tank CV C/D Control Rod Drive Control Valve CS Cooldown CSCS Core Spray CPS Core Standby Cooling Systems DOE Counts Per Second DG Department of Energy DC Diesel Generator DH Direct Current EAL(s) Drywell EBS Emergency Action Level (s)

ECCS Emergency Broadcast System ED Emergency Core Cooling System ENS Emergency Director EOF l Emergency Notification System EPIP EPZ Emergency Operations Facility EPC Emergency Plan Implementing Procedure Emergency Planning Zone EPI EOC Emergency Planning Coordinator Emergency Public Information EPA End of Cycle FEMA HP Environmental Protectic, Agency HEPA Federal Emergency Manrgement Agency Health Physics HPCI High Efficiency Participate Air (Filter)

High Pressure Coolant Injection EOF A147-28

BOSTON EDISON COMPANY PILGRIM NUCLEAR POWER STATION NRC EVALUATED EXERCISE 92-05-B

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2.5 ABBREVIATIONS (Con't.)

&$sianment Etmf HPN Health Physics Network HVAC Heating, Ventilation, Air Cor.ditioning o INPO Institute of Nuclear Power Operations IRAP Interagency Radiation Assistance Program IRH Intermediate Range Monitor KH Kilowatt KI Potassium Iodide LCO Limiting Condition of Operation LOCA Loss of Coolant Accident LPCI Low Pressure Coolant Injection LPRM Local Power Range Monitor HSIV Main Steam Isolation Valve HPC Haximum Permissable Concentration H-G Hotor-Generator NPSH Net Positive Suction Head NRC Neclear Regulatory Commission NSSS Nuclear Steam Supply System OSC Operations Support Center PCIS Primary Containment Isolation System PAG Protective Action Guide PASS Post Accident Sampling System PIO Public Information Officer RBCCH Reactor Building Closed Cooling Hater RHT Radiation Monitoring Team RCIC Reactor Core Isolation Cooling RECIRC Reactor Recirculation System RFP Reactor feed Pump RPV Reactor Pressure Vessel RPS Reactor Protection System RHCU Reactor Water Cleanup RHR Residual Heat Removal RPM Revolutions per Minute RPIS Rod Position Information System SRV Safety Relief Valve SAS Secondary Alarm System SRO Senior Reactor Operator SDV Scram Discharge Volume SRM Scarce Range Monitor S/D Shutdown SBGT Standby Gas Treatment System SBLC Standby Liquid Control SJAE Steam Jet Air Ejector SV Stop Valve TSC- Technical Support Center TAF Top of Active fuel TIP Tt. versing Incore Probe TBCCH Turbine Building Closed Cooling Hater TB Turbine Building TAG Technical Assessment Group EOF 4147-29

1992 PNPS NRC EVALUATED EXERCISE All facility Lead Controllers are to read the following drill ground rules to their

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respective facility staff as soon as they are available.

DRILL GROUND RULES All drill participants are required to observe the following Drill Ground Rules for the entire duration of the drill, if you have any questions, ask your Drill Observer / Controller for clarification.

1. Ensure that all communications indicate that this is only a drill. Make a positive statement that this is a drill related messare at the beginning and end of all messages or conversations. If communication lines are kept open for extended periods, periodically repeat the caution. This is especially critical when ;

transmitting messages over communication facilities that are monitored by non.

BECo personnel.

2. Take no actions that affect the unit or non-drill related operations.

3. Take immediate action (s) to restore safe operations if an unsafe condition exists. Ignore the drill situation if actual safety becomes a concern.

4. Use only information provided in accordance with the Drill Ground Rules or derived from from approved procedures. Do not imoroviso information.

S. Express simulations and verifications in spoken words.

PJANT CONDillONS THE DAY BEFORE EXERCISE The plant is operating at 60% power and has been operating for the past 199 days. P Surveillances in progress include: 8.5.3.11 SSW Valve Operability Test and 8.7.4.4 MSIV Quarterly Operability. Procedures 9.9 Control Rod Scram Time Evaluation and 9.11 Control Rod Pattern Exchange are ongoing. Hydrogen water chemistry is in service.

1992 PNPS NRC EVALUATED EXERCISE [

Identified drywellleakage remains constant at 2.1 gpm. High pressure is expected to dominate the area for the next few days. Winds are light from the southeast. A warm clear day is forecast for tomorrow.

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i 1992 PliPS NRC EVALUATED EXERCISE l N ARR ATIVE SUMM ARY

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92 058 Initial Conditim Power ascension to 100% is M progress and currently the reactor is operating at 90%

power. The plant has been oper#ng for the past 200 days. Main consenser backwash, screm time testing and coral rod swap were completed yesterday.

Routine surveillances have been completed. Scheduled surveillances include 8.M.2-1.5.1 Main Steam Line Isolation Valve Logic Test A Outboard and 8.M.1.24 Main Steam Line isolation Valve Logic Channels. The weather is clear and sunny with light winds out of the north northheast.

Seouence of Events The exercise !s initiated when the plant operating staff recieves indications of excessive unidentified drywellleakage. A radwaste trouble alarm wili key plant operators to direct the Radwaste Operator to pump the drywell sumps and determine the time of the last pumpouts. The Control Room Operator is expected to monitor for any inrease in drywell pressure and humidity.

When it is determined that dryweil unidentified leak rate is in excess of 5 gpm, an Unusual Event should be declared based on exceeding Technical Specification allowed leak rates (EAL# 3.3.1.1). Actions should be taken to control drywell pressura and to locate and isolate the source of the leak. Any actions to reduce the leak will be unsucessful. As a result, a controlk J shutdown should be initiated.

Approximately forty-five minutes after declaration of the Unusual Event, indicauon will be provided of increasing drywell pressure. Drywell pressure shall increase above the scram setpoint. The reactor shall sucessfully scram and appropriate isolations occur.

Actions to control Reactor Pressure Vessel (RPV) water level and pressure should be consistent with Emergency Operating Procedures (EOP-01 and EOP 03) An Alert should be declared based upon the inability to mair,tain drywell pressure less than 2.5 i

psig(EAL# 3.4.1.2). Actions to spray the torus should be taken. Once plant conditions l

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1992 PNPS NRC EVALUATED EXERCISE are stabilzed, a controlled cool down to cold shutdown should be initiated. RPV depressurization should be via main steam bypass valves at less than 100 degrees per hour, Approximately two hours aher declaration of the Alert, indication will be provided of the '

rapid depressurization of the RPV and high main steam line temperatures as the result of a main steam line rupture on the 'A' main steam line outside primary containment.

Indicaticns of a Group iisolation (high level /high temperature) signal will be provided however the Main Steam Isolation Valves (MSIV's) willindicate full open Attempts to manually isolate the MSIV's will indicate that all but the 'A' main steam line MSIV's closed. A Site Area Emergency should be declared based on either the existence of an unisolable steam leak outside primary containment (E AL# 6.2.2.3) or the inability to immediately isolate any main steam line following a valid Primary Containment isolation System (PCIS) signal (EAL# 6.2.3.3),

As a result of the main steam line break, a slight increase in Reactor Building Ventilation radiation monitors shall be provided consistent with the brief release of low activity steam into the Turbine Building.

Once plant conditions stabilize, the reactor shall be depressurized. Operators should proceed into shutdown cooling. Actions should be pursued to close the 'A' main steam line MSIV's.

The exercise will be termiriated once all exercise objectives have been demonstrated.

e 1992 Pt&S NRC EVALUATED EXERCISE I!IdEldlE ,

El posed Time Eymni

-0030 Initial condition $, established, shift turnover information provided to opera'.;ons crew. Panel watk down performed.

0005 Announcement of the 1992 NRC Evaluated Exercise 0005 Containment boundary leakage alarm indication (C!9) 0015 Indication of radwaste trouble atarm.

0037 Radwaste Operator reports drywell sump pumpout information.

Declaration of Unusual Event based on EAL#3.3.1.1. Acticas .

taken to locate and isolate source of leak.

0045 Actior.s to initlate controlled shutdown. Trip of 'A' loop RBCCW l

l pump i

012S Indication of high dryweli pressure Reactt Lerar? Operators j enter RPV anc Pnmary Containrnent Cninmt P.n s. Declare Alert I basea on EAL# 3.4.1.2 l

L 0140 Initiate cooldown via main turbine bypass valves. RPV water levc j maintained via Feec; water / Condensate.

0315 Indication provided of the rapid depressurization of the RPV and .

high main steam flow. This will be the result of the "A" main steam -

line rupturing downstream of the outboard MSIV 1

0335 A Site Area Emergency should be declared bassd on eit"ar EAL# 6.2.2.3 or F.i L# 6.2.2.3. The site should be evacuated of a!. .

non-essential pertonnel and accountability demonstrated l (simulated).

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1998 PNPS NRC EVALUATED EXERCISE 0345 RPV depressurized. Actions taken to got into Shutdown Cooling.

0350 Maintenance teams should be dispatched to attempt closure of 'A' main steam line MSI'/'s.

0400 Shutdown Cooling in service 'A' main steam line MSIV's

. Successfully closed.

I 0430 Terminate exercise if all objectives have been mot.

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l N8 Emergency Exercise Simulator Scenario 1992 NRC Evaluated Exercise 92-05B

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Exercise 92-05B Page 2 of 6 Scenario Overview: ,

The exercise begins with the plant at 90% power and the operating crew raising reactor 1%w to 100% when indicMion of a small leak inside containment develops. Upon investigation, Radwaste reports purnpout tst", nation which indicates a leak I rate of 10 gpm unidentified. This shall require the declaration of an Unusual Event. The lean later increases to the point where !

drywell pressure cannot be maintained below the high drywell pressure scram setpoint. This shall require declaration of an ;

Alert. The reactor successfutiy scrams and ECCS performance is successful. After time is allowed for emergency response facilities to be activated, a main stenm line rupture outside primary containment shall cause a rapid depressurization of the j RPV. The Group I isolation shall fait. Attempts at manual isolation oih m&, steam fines shail resuit in the failure of the l 3

MSIV's in om main steam line to close requiring declaration of a Site Area Emergency. The crew should initiate shutdown cooling and pursue getting the unisolated steam line isolated.

(

Simulator initializa' ion Conditions: Malfunctions:

l IC# 48 Malf.j! Titta !

Reactor Powcr 90 %

l Core Flow 60 E 6 lbm/hr PC-01 A(B) Recirculation system leak (0 - 100 gpm) !

Reactor Pressure 1015 osio MS-01 Steam line break inside containment (0 - SE5 Ibm /hr)

(

Moderster Temp . . , _

T-sat MS-03 MSL rupture outside containment Reactor Mode Switch Run CW-05A Trip of 'A' RBCCW loop pump Time in i_ife MOC Rod Position: !

. Group 16B [

Rod 10-19 [

Position __

48 Remote Funcuens ;

RF# Titfe i

, TFA10101 PCIS GP1 bypass (Page 610)

Stylize equipment: !

- Override AO-203 1 A & 2A to open

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Exercise 92-05B . Page 3 of 6 I Controller Activity Player Activity Scenario Notes !

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' Simulator Initialization: !

1. Initialize to IC# sl !

4-2.. i.abel TFA10101 PCIS GP1 bypass.

3. Override control switches for AO- i l 203-I A & 2A ~to open j i

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i Pre-Exercise Brief - !

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1. Bring crew into simulator. I l 2. Assign shift positions !

l_ - Nuclear Watch Engineer

- - Nuclear Opetutions Supervisor .

Reactor Operator ;

Balance ' of Plant Operator

! - Spare Operator l - Shift Technical Operator .

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3. Distribute ~ watch turnover sheets - WaRdown panels !

j-and state watcia turnover conditions - Prepa:e to assume j to crew via tc h !

s Review turnover - l 3

4. Allow time for shift to review plant sheets - l c conditions and scan their panels. - Assume the watch !

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'i Exercise 92-05B -

Page 4 of 6 l Instructor /lF Operator Activity Elapsed i Player Activity Crew Membes Sequence Time / IF Responsible Operator Notes ;

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! Initialize to IC# 48 0000 - Assume watch Crew This IC has following preset: - Conduct pre-evolution brief j GIF page 610. Label TFA10101 PCIS

Continue with power ascension GPl Bypass .

Stylize equipment: override AO- ,

i 203-1 A & 2A control switches to open I Malf.#PC-01 A @ '10 gpm 0005 - Respond to resultant C19 alarm 4 !

! Cry Wolf: 0015 - Observe rising drywell pressure

. Radwaste Trouble Alarm Panel C2 - Maximize drywell c% ling

i. (C2R-B8) - Request Radwaste operator to pump 4 DWED & DWFD sumpt

- Request last sump pump times Remove cry wolf on C2R-B8 after '0037 - Declare Unusual Event based on NWE

crew is notified that Radwaste 'is EAL#3.3.1.1 ;

i pumping DWFD ' sump. Report as - Implement EP-IP-110 ' Unusual Event' !

Radwaste Operator: ,- Attempt to identify and isolate source NOS Drywell floor drains leakage is 10 of leak j

gpm. Pumped 1200 gal. from DWFD sump. DWFD sump pumped 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ;

i ago. ;

Insert CW-05(A) Trip of RBCCW 'A' .0045 - Initiate sbuidown to cold shutdown. Crew f j loop pump - Respond to trip of 'N RBCCW loop pump.

{

Verify standby pump starts.

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__ . _ _ __.. . _ . _ _ __a

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! Exercise 92-05B Page 5 of 6 Instructor /IF Operator Activity Elapsed Player Activity Crew Member j Sequence. Time / IF Responsibic [

Operator !

l i

Notes i !

t I

, Insert Malf.#MS-01 @ 30.000 !bm/hr 0125 l - Respond to Rx scram NOS/ Crew i Ramp Icak as necessary to m intain -

Enter EOP-01 and 03 1 drywell pressure >2.5 psig but < 11.0 -

Spray torus psig. -

Declare Alert based on EAL#3.4.1.2 NWTi

- Implement EP-IP-120 ~ Alert" l I i l, Reduce MS-01 leak rate to 15.000 0140 -

Initiate corr!down(<IDO deg/hr) via NOS

, ihm/hr main turbine bypass valves j L Reduce MS 01 leak rate to 5,000 'RPV

) lbm/hr pressure !

i 600 psig Remove MS-01 Icak RPV pressure e450 psig i Insert Malf.#MS-03 Rupture of 'A' 0315 - Note rapid depressurization of RPV PD i

MSL outside primary containment -

Note failure of MSIV's to close on GPI !

isolation signal l 3

Simulate AO-203-2A mid position by -

Attempt manual isolation of MSiV's l

, overriding green position light to on -

Note failure of 'A' MSL MSIV's to close. i

(PCIS mimic and at C/S) upon ,

f operator attempt at manually I closing the valve at Panci 903 [

i l 0335 -

Declare Site Area Emergency based on NWT l EAI.#6.2.2.3 or #6.2.3.3 !

- Impicment EP-IP-130 i

..,3 s,e- . . , - - - .

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

t Exercisc 92-05.B Page 6 of 6 i

instructor /lF Operator Activity Elapsed Player Activity Crew M:mber Sequence Time / IF Responsible Operator Notes t

0345 - Initiate action to place shutdown NOS cooling in service Remos e control switch override for 0400 or - Note AO-203-2A is closed. Inform IO AO-2FJ3-2A after NOS/NWE when action taken to manually close valve Freeze simulator 0430 Exercise terminated 5

s -

. .- . _. . . - - - --______.___s -

PNPS EMERGENCY PREPAREDNESS DRILL / EXERCISE MESSAGE FORM i

SCENARIO NO. 92 05B MESSAGE NO SIM 1 :

ELAPSED TIME -0030 TIME !

THIS IS A DRILL i

.D.._Q..NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS

^

MESSAGE FOR: Watch Engineer INFORMATION: -

lNITIAL PLANT CONDITIONS I The reactoris operating at 90% power. The plant has been operating for the past 200 days, Routine surveillances have been completed. Scheduled surveillances include l 8.M.21.5.1 Main Steam Line isolation Valve Logic Test A Outboard and 8.M.1.24 Main Steam Line Isolation Valve Logic Channels. There is no significant equipment out of service.

INITIAL METEOROLOGICAL CONDITIONS The weather is clear and sunny with light winds out of the north northheast. The temperature is 56 degrees.

l l

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THIS IS A DRlLL

.D..A..N._.Q.I...INITI ATE ACTIONS AFFECTING NORMAL PL ANT OPER ATIONS

. Revision 0 l

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PNPS EMERGENCY PREPAREDi1ESS DRILL / EXERCISE FOR CONTROLLER USE ONLY l

SCENARIO NO. 92 058 MESSAGE NO. S&l1 ELAPSED TIME .0030 TIME THIS IS A DRILL ADDITIONAL CONTROLLER INFORMATION:

This message is to be presented when the Simulater Crew is in place.

ANTICIPATED PLAYER RESPONSE:

Players should become familiar with the format and content of the message sheets.

They should walk down the simulator panels and erisure they are cognizant of current plant conditions. They should compare currsnt plant conditions with the information presented yesterday as the status at the end of the day. All of the Control Room Stati should be provided with this information.

COMMENTS:

THIS IS A DRILL

..............................................t...............................

Revision 0

PNPS EMERGENCY PREPAREDNESS DRILL / EXERCISE MESSAGE FORM SCENARIO NO. 92 05B MESSAGE NO CR-2 ELAPSED TIME S105 TIME THIS IS A DRILL

.I.L.Q.1101 INITIATE ACTIONS AFFECTIN.G

................................... NORM AL PLANT OPER ATIONS MESSAGE FOR: Non drill NOS in real Control Room INFORM ATION:

Have the Control Room make the following announcement over the page system:

" Attention! Attention! This is the Control Room. Pdgrim Nuclear Power Station is commencing the 1992 NRC EVALUATED EXERCISE. All announcements preceded by "THIS IS A DRILL" are for designated Exercise Participants. All personnel are to limit the use of the Gal tronics until the exercise has been terminated.

" REPEAT MESSAGE" l

l

.........................................s....................................

THIS IS A DRILL

.I.L.Q..N..OT

. INITI ATE ACTIONS AFFECTING NORMAL PLANT OPER AT Revision 0

k PNPS EMERGENCY PREPAREDNESS DRILL / EXERCISE FOR CONTROLLER USE ONLY 9

SCENARIO NO. 92 05B MESSAGE NO. .CE2 ELAPSED TIME 10005 TIME THIS IS A DRILL ADDITIONAL CONTROLLER INFORMATION:

Provide this rnessage to the on watch NOS to initiate the 1992 NRC EVALUATED EXERCISE, ANTICIPATED PLAYER RESPONSE:

The Control Room Operator wdl rnake the announcement on the Gal tronics system.

COMMENTS:

l i

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........................................e.....................................

THIS IS A DRILL Revision 0

-_._...__y PNPS EMERGENCY PREPAREDNESS DRILL / EXERCISE MESSAGE FORM

~

SCENARIO NO 92 05R MESSAGE NO CHEM 3 ELAPSED TIME 0005 TIME l l

.................................................................s............

l THIS IS A DRILL -

.I.L.Q.. l.l.O.l...INITI

. ...... AT..E ................

..... ACT.. IONS AFFECTING... NORM AL PLANT.....

........................... OPER ATI.

MESSAGE FOR: Chem Tech sent to investigate C19 alarm INFORMATION:

i The following indications exist on C19: :

C19 westiin alarm lodine channel alarming at 3.6E5 pel/cc and increasing ,

Gas channel slowly rising

- Particulate slowly rising i Background mr/hr slowly rising

+

C19 east:In alarm is out of service r

THIS IS A DRILL D_Q NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS Revision 0 l--

t

.. ,__.,.,,.4._,_. -,-,-..--,_.,._,..,...__._._.._A.,.__..i-,__,..._....._--....-..-..-_..-.---,--------r

PNPS EMERGENCY PREPAREDNESS DRILL / EXERCISE '

FOR CONTROLLER USE ONLY SCENARIO NO. 92 05B MESSAGE NO. CHEM 3 ELAPSED TIME 02Df5 TIME THIS IS A DRILL ADDITIO!JAL cot l TROLLER INFORMATION:

Upon investigation by the Chem. Tech or whoever is sent to investigate the C19 <

alarm, provide the indication of both units in alarm and instrument readings as specified in the f,cenario rad. data for the current elapsed time.

(provide data to NOS/NWE as Chem. Tech. over Gaitronics)

At4TICIPATED PLAYER RESPONSE:

Report results to the Control Room. The CR Controller shall then relay this information to the Simulator Data Contoller who shallin turn provide the information to the NWE.

COMMENTS:

Wait approx.10 minutes to provide information.

THIS IS A DRILL Revision 0

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

PNPS EMERGENCY PREPAREDNESS DRILL / EXERCISE MESSAGE FORM SCENARIO NO. 92 05B MESSAGE NO SH&4 ELAPSED TIME 0H22 TIME THIS IS A DRILL

.D._.Q.. NOT INITI ATE ACTIONS AFFECTING NORMAL PLANT OPER ATIONS MESSAGE FOR: Watch Engineer INFORMATION:

Radwaste Operator reports that DWED sump was pumped at 0600 this mourning. The last integrator reading was 00014387, Current intergrator reading is 00015622.

THIS IS A DRILL

.D._.Q..NOT INITI ATE ACTIONS AFFECTING NORMAL PLANT OPER

..................................................................... . . ATIONS Flevision 0

PNPS EMERGENCY PREPAREDNESS DRILL / EXERCISE FOR CONTROLLER USE ONLY SCENARIO NO. 92 05B MESSAGE NO. SIM 4 ELAPSED TIME 0037 TIME THIS IS A DRILL

...........................................................................u. !

ADDITIONAL CONTROLLER INFORMATIOfJ: ,

i Provide data to NOS/NWE as Radwaste Operator on gaitronics. !

ANTICIPATED PLAYER RESPONSE:

The NOS should calculate a drywell unidentified leak rate of approximately 9 11 gpm.

Declare " Unusual Event" based on EAL#3.3.1.1 COMMENTS:

l

! THIS IS A DRILL l ..............................................................................

Revision 0 l

1 PNPS EMERGENCY PREPAREDNESS DRILL / EXERCISE MESSAGE FORM SCENARIO NO. 92 05B MESSAGE NO CR5X l

ELAPSED TIME Q21Z TIME l THIS IS A DRILL l l

.R..Q..N..OT INITIATE ACTIONS AFFECTING NORMAL PLANT OPER ATIONS MESSAGE FOR: CR Announcer INFORM ATION:

Make the following plant announcement as specified in specified in EP IP-110:

THIS IS A DRILL THIS IS A DRILL Attention all personnel; Attention all personnel: An Unusual Event has been declared due to (provide brief description of event). All on call members of the Emergency Response Organization stand-by for further instructions. All other personnel continue with your present duties unless further instruction is given.

THIS IS A DRILL THIS IS A DRILL (REPEAT MESSAGE)

THIS IS A DRILL

.R..Q..N..OT INITI ATE ACTIONS AFFECTING NORMAL PLANT OPER ATIONS Revision 0

PNPS EMERGENCY PREPAREDNESS DRILL / EXERCISE FOR CONTROLLER USE ONLY SCENARIO NO. 92 05B MESSAGE NO. CR 5X ELAPSED TIME 0125 TIME THIS IS A DRILL ADDITIONAL CONTROLLER INFORMATION:

This announcement shall be made as specified specified in EP IP 110 ' Unusual Event" ANTICIPATED PLAYER RESPONSE:

Make announcement via CR gaitronics COMMENTS:

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! THIS IS A DRILL Revision 0 l

l. - .

I PNPS EMERGENCY PREPAREDNESS DRILL / EXERCISE MESSAGE FORM i

SCENARIO NO, 92 05B MESSAGE NO CR6X j ELAPSED TIME 0110 TIME !

THIS IS A DRILL r

.E..Q..NOT INITIATE ACTIONS AFFECTING NORM AL PLANT...OPER

........................................................ .............. ATIONS

- MESSAGE FOR: CR Announcer ,

INFORMATION:

Make the following plant announcement in lieu of the announcement specified in step 5.5 of EP IP 120:

THIS IS A DRILL :

I THIS IS A DRILL Attention all personnel; Attention all personnel: Had this been an actual emergency, all non essential contract personnel, all visitors, and all handicapped personnel would be directed to leave the site at this time. For the purpose of tH drill, all non drill ,

participants are to continue with your normal duties.

THIS IS A DRILL THIS IS A DRILL (REPEAT MESSAGE)

THIS IS A DRILL

.E..Q..NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS Revision 0

Pt4PS EMERGEt4CY PREPAREDtJESS DRILL / EXERCISE FOR COf4 TROLLER USE Of4LY SCEt4ARIO tJO. 92 05B MESSAGE f40. CR-CX ELAPSED TIME 0130 TIME

..........r...................................................................

. . . . T.H I S I S A D R I L L ADDITIOt4AL cot 4 TROLLER lt4FORMATIOtJ:

This announcement shall be made in lieu of that specified in EP IP 120 " Alert" At4TICIPATED PLAYER RESPOt1SE:

Make announcement ta OR gaitronics COMMEtJTS:

THIS IS A DRILL Flevision 0

PNPS EMERGENCY PREPAREDNESS DRILL / EXERCISE MESSAGE FORM SCENARIO NO.92-058 MESSAGE NO OSC 7X l ELAPSED TIME 0200 TIME THIS IS A DRILL

.D._.Q..l.L.Q.I...INITI

. ATE ACTIONS AFFECTING NORMAL PLANT OPER AT MESSAGE FOR: OSC Maintenance Team dispatched to troubleshoot RBCCW. l INFORM ATION: ,

i The 'A' RBCCW pump pump shaft is siezed. f l

THIS IS A DRILL

.D._.Q..NOT INITIATE ACTIONS AFFECTING NORM AL PLANT OPER ATIONS Flegislon 0

PNPS EMERGENCY PREPAREDNESS DRILL / EXERCISE FOR CONTROLLER USE ONLY SCENARIO NO. 92 05B MESSAGE NO. OSC 7X ELAPSED TIME 0200 TIME THIS IS A DRILL ADDITIONAL CONTnOLLER INFORMATION:

Any attempt at manually rotating pump will indicate that the purnp shaft is seized. The pump motor is still very hot to the touch.

ANTICIPATED PLAYER RESPONSE:

Report results to the CR/TSC.

COMMENTS:

Any report should be transfered to simulator.

.............si + ............................................................

THIS IS A DRILL

........,3:e ..............................................................

Flevision 0

PNPS EMERGENCY PREPAREDNESS DRILL / EXERCISE .

MESSAGE FORM l l

r

?

SCENARIO NO, 92 05B MESSAGE NO OSC 8X .

- ELAPSED Til.:2 Q31!i TIME THIS IS A DRILL

.D._.Q..H..Q.I...INITI ATE ACTIONS AFFECTING NORM AL PLANT...OPER.ATIONS 7

MESSAGE FOR: OSC Team dispatched to investigate stearn leak in turbine building-INFORMATlON:

Steam is observed wisping in the area of the condenser bay entrance.

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l THIS IS A DRILI, D_Q NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONd

..................................... 3.......................................

Revision 0 l

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-~,____-_.__._._.____;a.. , . . _ . . _ _ _ . . . . . . . _ _ _ . _ _ _ . . . _ _ . _ . _ _ _ _ . _

PtJPS EMERGEtJCY PREPAREDtJESS DRILL / EXERCISE FOR CONTROLLER USE ONLY SCEN ARIO NO. ElMES MESSAGE IJO_ .QEG.dX ELAPSED TIME 0315 TIME THIS IS A DRILL ADDITIONAL CONTROLLER INFORMATION:

Provide indications consistent with a large steam line break inside the condenser bay.

AtJTICIPATED PLAYER RESPONSE:

Report results to CR/TSC COMMENTS:

Any report should be trant'ered to simulator.

?_

THIS IS A DRILL l............................ Revision 0

PNPS EMERGEt4CY PREPAREDNESS DRILL / EXERCISE MESSAGE FORM SCENARIO NO. 92 05B MESSAGE NO CR 9X ELAPSED TIME 0335 TIME

.........................................................+....................

THIS IS A DRILL

.D.S...NOT INITIATE ACTIONS..AFFECTING

.......................... NORMAL PLANT OPERATIONS MESSAGE FOR: CR Announcer ,

INFORMATION:

Make the follopng plant announcement in lieu of the annouricement specified in EP-IP 130:

THIS IS A DRILL THIS IS A DRILL Attention all personnel; Attention all personnel: A Site Area Emergency has been declared due to (provide brief description of event). Had this been an actual ernstgency, all personnel who are not part of the Emergency Response Orgarsication wcJld be directed to evacuate to the designated assembly area and would receive further instructions at your exit gate. For the purpose of the drill, all non drill ,

participants are to continua with your normal duties.

THIS IS A DRILL THIS IS A DRILL (REPEAT MESSAGE)

THIS IS A DRILL

.D._.Q..l.L.Q._.T. INITI ATE ACTIONS AFFECTING NORM AL PL ANT OPER ATIONS Revision 0

PtJPS EMERGEtJCY PREPAREDtJESS DRILL / EXERCISE FOR COtJTROLLER USE OtJLY SCEtJARIO NO. 92 05D MESSAGE tJO. CB 98 ELAPSED TIME 0335 ftME THIS IS A DRILL

.......................................................u......................

ADDITIOtJAL COtJTROLLER ltJFORMATIOtJ:

This announcement shall be made in lieu of that specified in EP IP 130 ' Site Area Emergencf Ai1TICIPATED PLAYER RESPOtJSE:

Make announcement via CR gaitronics COMMEtJTS:

THIS IS A DRILL Revision 0

._ - - -. .- - -- ~ . . - - .

PNPS EMERGENCY PREPAREDNESS DRILLIEXERCISE MESSAGE FORM SCENARIO NO. E235B MESSAGE NO OSC 10X ELAPSED TIME Q3.!45 TIME THIS IS A DRILL

.M....L.L.Q.I...INITI ATE ACTIONS AFFECTING NORM AL PL ANT OPER ATIONS MESSAGE FOR: OSC Team dispatched to the steam tunnel to investigate MSlV INFORM ATION:

AO-203 2A valve operator has a large bolt jammed in the yoke of the valve preventing it from fuhy closing.

THIS IS A DRILL M NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS Revision C

..____.._-__-______.7..________..

PNPS EMERGENCY PREPAREDNESS DRILL / EXERCISE FOR CONTROLLER USE ONLY L

SCENARIO 000. 22.._0 jib MESSAGE NO. OJC 10X 4

ELAPSED TIME 0345 TIME

........t.....................................................................

THIS IS A DRILL ,

ADDITIONAL CONTROLLER INFORMATION:

Provide indications which indicate that tha bolt could likely be removed if valve was cycled open.

ANTICIPATED PLAYER RESPONSE:

Report indications to CR/fSC COMMENTS:

Group 1 isolation signets must be overriden to reopen AO 203 2A.

THIS IS A DRILL Revision 0

PNPS EMERGENCV PREPAREDNESS DRILL /EXERCiSF MESSAGE FORM i

l l

SCENARIO NO. 2L.01B MESSAGE NO AI.L-11 ELAPSED TIME Q_422 TIME

....................................................................o ........ ,

THIS IS A DRILL l

.D._.Q..

.. fi.O.I...INITI ATE ACTIONS AFFECTING NORM AL PLANT OPEM

........................................................ ATiONS l

MESS AGE FOR: Senior ERO posit'.on in each facility l

l lNFORM ATlON:

The 1992 NRC Evaluated Exercise is terminated.

Assure that the following Gai tronics and/or PA ar.nouncement is made:

" Attention! Attention! The Pilgrin Nuclear Power Station 1992 NRC Evaluat< d Exercise has been completed, No further drill ann 9tocements will be made "

p F

THIS IS A DHILI.

.D.S...

....NOI...INITI ATE ACTIONS AFFECTING NORM AL PL ANT OPliH ATiONS Rsvision 0

PNPS EMERGENCY PREPAREDNESS DRILLiEXERCISE FOR- CONTROLLER USE ONLY ,

Y SCENARIO NO. 92 05B MESSAGE NO, BI-11 ELAPSED TIME DAM TIME THIS IS A DRILL ADDITIONAL CONTROLLER INFORMATION:

Provide message to person in charge of each facility only when the Lead Exercise Controller has determined that all objectives nave been tested ANTICIPATED PL'AYER HESPONSE:

All p!syers should assemble all of the writted material that was generated during the exercise for assembly by the Lead Facility Controller. All logbooks, Procedures Manuals, Armbands, and other materialt should be returned to their proper locations.

CO;.W.EN TS:

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.....................c..... $....................................................

THIS IS- A DRILL Reevision 0

.e. . _ _ . . _ _ . - . ___._., _ _ . .

PNPS EMERGENCY PREPAREDNESS DRILL / EXERCISE MESSt.GE FORM; i l

SCENARIO NO.92-05B MESSAGE NO SE:1 ELA'PSED TIME 0005 TIME THIS IS A DRILL

.R..Q.. ..... NOT. INITIATE ACTIONS AFFECTING NORMAL PLANT OPER ATIONS

. MESSAGE _FOR: NOS INFORMATION: ,

The following annunciators and Indications are recieved in the control room:

RAD LEAK DET ANALYZER TROUBLE C19 NB (903) 1 1

l d 2

THIS IS A DRILL pa

..,...l.{.Q.I...INITI ATE ACTIONS - AFFECTING NORM AL PLANT OPER ATIONS Flevision u

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

_ PHPS EMERGENCY PREPAREDNESS DRILL / EXERCISE

-MESSAGE FORM SCENARIO NO. 92 05B MESSAGE NO EE 2 ELAPSED TIME Q.023 TIME P THIS IS A DRILL

.D.S.Q..NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS

- MESSAGE FOR: NOS INFORMATION:

The following annunciators and indications are recieved in the control room:

DRYWELL Hl/LO PRESSURE (905) f-I THIS IS A DRILL p_Q NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPEHATIONS Revision 0 -

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PNPS EMERGENCY PREPAREDNESS DRILL / EXERCISE MESSAGE FORM SCENARIO NO. 92 058 MESSAGE NO SE-3 ELAPSED TIME Q113 TIME THIS IS A DRILL

.D._.Q..NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS MESSAGE FOR: NOS INFORM ATION:

The following annunciators and indications are recieved in the control room:

Radwaste Panel Troubla C 2 R A23

.............e................................................................

THIS IS A DRILL p_Q NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPER ATIONS Revision 0

i PNPS EMERGENCY PREPAREDNESS DRILL / EXERCISE MESSAGE FORM SCENARIO NO. 22a5B MESSAGE NO SE-4 ELAPSED TIME Q120 TIME THIS IS A DRILL

.D.R...NOT. INnTIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS MESSAGE FOR: NOS INFORM ATION:

The following annunciators and indications are recieved in the control room:

RBCCW LOOP A PUMP LOW DISCH PRESS (C1) 1 r

i

..............*.............e.........................e.*ee...ee..........*...

THIS IS A DRILL l

p_Q NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS

..........................................................e...................

Revision 0

.- -. . . . . - - - -- . = - . .. .- - .

PNPS EMERGENCY PREPAREDNESS'. DRILL / EXERCISE-MESSAGE FORM SCENARIO NO. 92 05B MESSAGE NO SF 5 .

ELAPSED TIME Q124 - TIM E THIS IS A DRILL

.D._.Q..NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS MESSAGE FOR: NOS INFORMATION:

The following annunciators and indications are recieved in the control room:

-+

Reactor Scram Channel A and B (905)

Drywell High Press Scram (935)

+ ' High Drywell Press CSCS Initiation (903)

Core Spray Auto Start A and B (903)

RHR Pump A/B/C/D Auto Start (903)

APRM Downscale (905) 1 t

THIS IS A DRILL '

. R..Q..f.i.Q._T_

........ INITI ATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS

................................................s............

Revision 0 F

w,

PNPS EMERGENCY PREPAREDNESS DRILL / EXERCISE MESSAGE FORM SCENARIO NO,92-05B MESSAGE NO Sf3 ELAPSED TIME 0135 TIM E THIS IS A DRILL

.D._.Q..NOT INITIATE ACTIONS

........................ AFFECTING NORMAL PLANT OPERATIOf1S MESSAGE FOR: NOS INFORMATION:

The following annunciators and indications are recieved in the control room:

IRM Downscate (905)

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THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS Revision 0

PNPS EMERGENCY PREPAREDNESS DRILL / EXERCISE MESSAGE FORM SCENARIO NO.92-05B MESSAGE NO S F-7 ELAPSED TIME 0250 TIME

...........................................................................c..

THIS IS A DRILL

.D.I..L.NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS MESSAGE FOR: NOS INFORMATION:

The following annunciators and indications are recieved in the control room

l CS & RHR Injection 400# Permissive (903)

. Air Ejector Steam Supply Low Pressure (C1) 1 1

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THIS IS A DRILL p_Q INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS

.....NOT Revision 0

PNPS EMERGENCY PREPAREDNESS DRILL /3XERCISE MESSAGEcFORM SCENAGIO NO. 92 05B MESSAGE NO SE-8 ELAPSED TIME 0315 TIME THIS IS A DRILL

.D._.Q..NOT. INITI ATE ACTIONS AFFECTING NORMAL

................................................ PLANT OPER ATIONS MESSAGE FOR: NOS J

INFORMATION:

- The following annunciators and indicatior.s are recieved in the control room:

- Steam Tunnel CH A Hi Temperature (905)

Steam Tunnel CH B Hi Ternperature (905)

Reactor Water Level Hi/Lo (905) a RCIC High Vessel Level (905)

Main Steam Line Leakage (905)

RHR Shut Cool Mode Hi Rx Press Ch A and B cleared -

HPCI Isolated (903)

RCIC isolated (904) k

\

THIS IS A DRILL D_Q NOT INITIATE ACTIONS AFFECTING NORMAL PLANT OPERATIONS Revision 0 ,

l

Js. ad - . h *S --h<5ee.dN n...M,.A44-.4Ac$ - At r 4.4A4.A4E e., E M A ,im a-.A<J.4r.d4 .- '+ms4.4.h4--ad e-a' -'

.mmad J a_h,R.4.S.me A .J.4 A a wA. 4 _4 4a.A.ma nha m Min 4 J. 4 4..a 34 hd ),,m2A a.,4 34 P

k 0

h t

I h

f i

'f.

4

+

b T

d 6 -

f

00'1 nPv nonMAt CRITICAL PLANT VARIABLES cumr nonuat EFFL HAD DRYWELL NORMAL SRy NO DG HPV H2 CONC ALL SHUT OPER CMD nony,t 2 CRAM HI 1085 k MSL RAD 0 3 -~J O2 CONC NORMAL PRESS { 1016 PSIG 42

.,, u o _

00*f. BPV 985 TT F7 "

NO MSTV ISLN CMD SCRAM HI TRIP HI 2.5f 48 GROUP PRESS 1.2 ,'SIG LEVEL 27 IN '

RECfRC SCRAM LO 9 NORMAL EOP HI 152 f

TEMP 133 l'F 90 h 1 RX MODE APRM DNSCL h LCO HI 130 k NO SCRAM TORUS i EVEL 128 4 ( j.

LCO LO 127 k EOP HI 80 k

TEMP l 73 l *F 92-05B PILGRIM *** 28-May-1992 pin,..,9 T1,. a. nnna i

00' aPv NORMAL CRITICAL PLANT VARIABLES CNmr NOnMAt EFFL RAD [ DRYWELL \)

SRV NO DG H2 CONC ALL SHUT "

" l PROC RAD %

NORMAL iCHAlaHI1085k __

MSL RAD

[ 3 '

'M O2 COffC PRESS NORMAL 1016 l PSIG J2

% LJ kJ (00% BPV 085 ) P7 71 D NO MSIV ISLN CMD SCRAM HI 2.5 TRIP HI 48 GROUP PRESS 1.2 .PSIG '"

REC lRC SCRAM LO 9k NORMAL EOP HI 152 k t TEMP R 90 %

133l*F RX MODE '

APRB4DNSCLh LCO HI 130 k NO SCRAM EVEL 128 i LCO LO 127 k .

HI O k

TEMP 73 *F 92-058 PILGRIM * *

28-May-1992 Etapsert Time: 0000

00 RPv NORMat CRITICAL PLANT VARIABLES curMr NORMAt EFFL RAD DRYWELL NORMAL RPV N SRV NO DG ,

H2 CONC ALL SHUT OPER CMD PROC RAD l %

NORMAL ICRAM HI 1085 k __

MSL RAD b 3 J O2 CONC PRESS 1015 NORMAL PSIG R 1 LA LA .

(00% BPV 985) Il Il "

NO MSIV ISLN CMD SCRAM fil TRIP fil 2.5 f 48k GROUP PRESS 1.4 PSIG '

RECIRC SCIIAM LO 9 NORMAL EOP HI 152 h

90 %

TEMP l137l'F RX MODE APRM DNSCL f I

LCO HI 130 h NO SCRAM TORUS EVEL 128 igL h 'j l LCO LO 127 EOP HI 80 TEMP 73

l*F l

92-05B PILGRIM * *

28-May-1992 Elapsed Time: 0015 '

001 HPv nonun CRITICAL PLANT VARIABLES CNMT NORMAL EFFL RAD DRYWELL NORMAL SRV l NO DG RPV H2 CONC ALL SHUT OPER CtaD PROC RAD %

ICRAM HI1085 NORMAL I MSL RAD 02 CONC 3 3 PRESS 1015 PSIG NORMAL J2 l

(00% BPV 985)

NO MSIV ISLN CMD SCRAM HI TRIP HI 2.5 k 40f PRESS 1.5 PSIG ' ISLN SCRAM LO 9k yonggt EOP HI 152 k

TEMP 140 l*F POWER 90

f. RX MODE APRM DNSCL h LCO HI 130 h NO SCHAM TORUS EVEL 128 C LCO LO 127 h EOP HI 80 h

F TEMP l 73 92-05B PILGRIM *** 28-May-1992 Elspeed Time: 0030

00' nev nonu^t !

CRITICAL PLANT VARIABLES c"mr "onu^t EFFL HAD

( DRYWELL .-

NORMAL SRV tlO DG npy 112 CONC ALL SHUT OPER CMD '

PROC RAD CHAMHI1085k NORMAL [ 3

MSL' R AD 02 CONC PRESS NORM /.L 1004 l PSIG 'J 2 g U

Il u -

[

(00% UPV 985) Il NO MSIV ISLN CMD SCRAM HI TRIP fil 48 2.5 f PRESS 1.4 PSIG ' ISLN RECIRC SCHAM LO 9 NORMAL EOP HI 152 k

TEMP POWER 80 %

135 l*F RX MODE APRMDNSCLh '

k LCO HI 130 HO SCRAM TORUS 128 EVEL. l( ( ,

LCO LO 127 h EOP HI 80 h

TEMP l 73 *F 92-05B PILGRIM * *

28-May-1992 Elapsed Time: 0045

001 Rev NORMAL CRITICAL PLANT VARIABLES c"mr noHua' EFFL RAD ORYWELL '

NORMAL SHV I NO DG HW H2 CONC ALL SHUT OPER CMD PROC RAD %

CRAM 1411085 h NORMAL O2 CONC

[

pSto

] k jg MSL RAD NORMAL PRESS l980

% LJ LJ TT U (00%BPV 985) TT NO MSly ISLN CMD SCRAM HI TRIP HI 48 2.5k GROUP PRESS LEVEL 27 ISLN 1.2 PSIG llN 8

NOR AL TEMP 125 *F POWER 61 'L RX MODE APRM DNSCL h LCO HI 130 k NO SCRAM TORUS EVEL 128 4 i

LCO LO 127 k EOP HI 80 k

TEMP 73 'F 92-05B PILGRIM * *

28-May-1992 Elspeed Time: 0100

001 nev nonu^L CRITICAL PLANT VARIABLES cnTMr nonMAt EFFL RAD DRYWELL SRV NO DG H2 CONC ALL SHUT PROC RAD %

NORMAL CRAM HI 1085 h MSL RAD E 3

02 CONC J PRESS NORMAL 976lP91G J2 k2 k2 -

(00%DPV 985) F7 T7 ^

NO MSiv ISLN CMD SCRAM HI TRIP HI 48 2.5 f GROUP PRESS 1.2 ISSIG "

RECIRC SCRAM LO 9 NOllMAL EOP HI 152 k

I TEMP 124 56 %

l'F RX MODE APRM DNSCL h '

l LCO HI 130 h NO SCRAM TORUS EVEL 128 g(

LCO LO 127 h EOP HI 80 k

TEMP 73 l'F 1

l 93-05 B PILORIM * *

28-May.1992 ...... - -- -

l

001 Rev ALARM CRITICAL PLANT VARIABLES Cumr AtARM

, i EFFL RAD I DRYWELL NORMAL SRV DG OPER H2 CONC ALL SHUT CMD PROC RAD %

NORMAL ICRAMMI1085h L ^

[ -] E3j 02 CONC g NORMAL PRESS l 898 l PSic Li LJ (00% BPV 985) TT FT

~

?-

NO MSIV ISLN CMD SCRt.M HI TRIP HI 2.5 k 48k GROUP PRESS 2.7 PSIG EVEL 21 IN D RA O 9k iOR AL TEMP 0 %

140l'F RX MODE APRM DNSCL h

/

LCO HI 130 h SCRAM LEVEL 128 i(

LCO LO 127 k OP HI 80 h

TEMP 73

} *F 92-0 5 B PILGRIM *** 28-May.1992 Elapsed Time: 0126

001 aPv Aua=

CRITICAL PLANT VARIABLES c"wr ^uaM EFFL ' RAD DRYWELL NORMAL RPV pp H2 CONC CMD ALL SHUT PROC RAD %

ICHAM HI 1085 NORMAL b MSL RAD 3 3 02 CONC PSIG NORMAL PRESS l926 J2 U k2 .

(00% BPV 985) F1 Tl "

NO MSIV ISLN CMD SCHAM HI TRIP HI 2.5f 48 PRESS 2.5 PSIG '

REClRC SCHAM LO 9 NORMAL EOP HI 152 h

TEMP 140 *F POWEB 0 %

RX MODE APRM DNSCL h i

LCO HI 130 k SCRAM TORUS 128 A

EVE iO hv LCO LO 127 k EOP HI 80 k '

TEMP 73 l*F 92-05D PILGRIM *** 28-May-1992 rs.n..A m-- a***

t 00' Rev ^LARM CRITICAL PLANT VARIABLES c"wr atARu e

^ DRYWELL SRV DG OPER RPV If2 CONC PROC RAD %

> CRAM HI 1085 h NORMAL 02 CONC NORMAL PRESS l875 psgo Jg' 00% BPV 985 NO MSIV SCRAM I!! TRIP HI 2.5 k 48k GROUP LEVEL 33 IN ISLN PRESS l 4.3 bSIGI C '

SCRAM LO gf NORMAL

~

EOP H1 152 f

TEMP 172 l*p POWER 0 %

RX MODE g

H DN APRM DNSCL h LCO HI 130 h SCRAM TORUS 128 EVEL 4 /

LCO LO 127 h EOP HI 60 TEMP)73 ) .p 92-058 PILGRIM * *

gg.y ,y,,,,, Etsoned Timer 01an

001 Rev AtARM CRITICAL PLANT VARIABLES CNTMT ALARM EFFL RAD NORMAL

[ DRYWELL- ) i (3DV H2 CONC ALL SHUT CMD PROC RAD 0.0 %

NORMAL $CRAMHI1085 E

MSL RAD 3

02 CONC PRESS _

NORMAL 500lPSIG JL 2.0 % LA LA -

(00% DPV 985 Il Fl ~

. NO MSIV ISLN CMD SCRAM HI 2.5 TRIP HI 48 GROUP PRESS 4.4 . PSIG '

RECIRC SCRAM LO 9 NORMAL EOP HI 152 k

TEMP 174 0 %

l'F RX MODE

APRM DNSCL h I g

LCO HI 130 h SCRAM 128 E V E L.

l(

j M ,

LCO LO 127 k TEMP 73 'F O2-05B PILGRIM * 28 May-1992 m . .s .. ,4 m .-- aaaa

001 nPv ^tanu CRITICAL PLANT VARIABLES c"' a r ^'^ n" EFFL RAD DRYWELL

)

HORMAL RV RPV DG OPER H2 COtlC ALL SHUT CMD PROC RAD 0.0 %

NORMAL b (,cnau ni1o85 __

MSL RAD 3 M 02 CONC PRESS NORMAL 465lPSIG J2 2*0 ~~ -

(00%BPV 985) Il Il SCRAM HI N NO MSIV ISLN CMD 2.5f TRIP HI 48k PRESS 2.1 PSIG ISLN SCRAM LO 9 NORMAL EOP HI 152 k

TEMP 0 %

147l'F POWEDl RX MODE APRM DNSCL h LCO HI 130 h SCRAM TORUS EVEL 128 ,(

h LCO LO 127 h EOP HI 80 h

TEMP 73 *F 92 058 PILGRIM *** 28-May.1992 Flanned N a. "998

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

001 laPV ^ '^ n u CRITICAL PLANT VARIABLES c" T^'^""

EFFL RAD DRYWELL NORMAL SRV NO DG H2 CONC RPV ALL SHUT OPER CMD PROC RAD '" "' '

NORMAL ::

O2 CONC PRESS 475 l PSIG R

~ LA LA -

(00% DPV 985 Vl II No MSiv ISLN CMD SCRAM lil 2.5 TRIP Hf i 43f GROUP l PRESS 8 PSIG LEVEL 29 . IN ISLH '

t

' SCRAM LO 9 NORMAL EOP HI 152 f

TEMP POWER o %

117l*l X MCDE APRMDNSCLh l l

LCO ill 130 k SCRAM

\ TORUS

l EVEL 128 pp4g '

}

LCO LO 127k EOP HI sof NTEMP 72 *F ea.oSR riton,M - 2..M _ ,,,, _.... . _ . .

001 nPV ^unu l CRITICAL PLANT VARIABLES c"mrAtaRu i EFFL RAD

[ DRYWELL SRV NO DG H2 CONC ALL SHUT '

PROC RAD 0.0 Y-NORMAL

%iCHAldHI1985k _1. MSL RAD b '3 #

J O2 CONC PRESS 424 pStG NORMAL J2 2.0 % kJ kl i (c0%BPV 985) T7 T1 "

HO MSiV ISLN CMD SCRAM HI TR!P HI 2.5 f 48f GROUP- t PRESS .5 PSIG RECIRC SCRAM LO 9 NORMAL EOP HI 152 k

TEMP 114 *F 0 %

RX MODE '

ORM DNSCL h s

LCO HI 130 h NO SCRAM d EVEL 128 l( .

LCO LO 127 k TEMP 72 *F 92-0 5 D PILGRIM * *

28-May-1992 Elapsed Time: 0245

001 RPv ti>aM CRITICAL PLANT VARIABLES cNiuT AtAnM EFFL RAD DRYWELL SRV NO DG H2 CONC ALL SHUT PROC RAD 0.0 %

{,CRAMHI1085h NORMAL E MSL RAD O2 CONC '3 J PRESS 288 PSIO jg -

NORMAL d\ 2.0 s LA LA '

(00% BPV 985 T11 FT

^

NO M31V ISLN CMD SCRAM H! TRIP HI 2.5f 48k '

).

GROUP PRESS .2 PSIG '"

9g RECIRC SCRAM LO 7 NORMAL EOP HI 152 f

TEMP 108 *F C h RX MODE APRM DNSCL - h t LCO HI 130 h NO SCRAM EVElf. 128 h( ~

LCO LO 127 h k EMP 72 O2-05D f N l *F '

PILGRIM *** 28-May-1992 pg ..a v .. nona

Section 5 RADIOLOGICAL AND METEOROLOGICAL INFORMATION llOSTON EDISON COMPANY PILGRIM NUCLEAR POWER STATION -

1992 EVALUATED EXERCISE 92-0511 SECTION , Tf1E IM.QE 5.1 Radiological Assump6cas 5-1 5.2 Messaces and Trend Data 5-3 Meteorvlogkal arid Vent now Daa TaNe 5.2.) 3. 2 ,

Furecast Metrayes Menages 1-4 ERM Trend Dsta Table 5. M PRM Trend Daa T6ble 5.2-4 ARM Trend Dua Toble 5.2 5 PRM 5tata Board Messages Messages 119 ARM Listus Board Messages Messages 119 PRM SPDS Messages Messages 119 ARM SPDS Messages Messeges 119 ERM SPDS Messagu Messeges 119 5,3 hAvenment Qua 5-106 5.4 Count Room _D2ta 5-107 Reactor Coolant Ac::vity rable 5.41 Turbine Buildmg Air Samples Table 5 4 2 5.5 Jn-Plant Radio!ocical Data 5-109 in plant Fad Sumina.>

Table 5.51 Condense e Bay 6' Fiyure 5.51 Condensow thy 23' Figure 5.5 2 Condensate Ba) 37 Figure 5.5-3 5.6 Environmental infomntion 5 113 Page 8-i

4 Section 5.1 Radiological Assumptions

i l

J.I Rittilolocleal Asstlitmljffn General

1. The release path for this scenar' -!s through the main steam piping into the condenser bay.

4 Turbine building ventilation taker, a suction on the condenser bay and discharges to the reactor building plenum. The activity is ' en tr! cased to the environment through the reactor building vent, in this exercise it is assunwd that the reactor con lamage does not occur.

2. EfDuent, Prucess, and Area Radiation Monitor data was developed on the PNPS simulator.

I Radiological infomution was mcdeled directly by the simulator to allow matimum consistency between plant and radiolo;ical conditions.

3. Radioactive material released (simulated) will consist of noble gases and halogens. Noble gas and halogen relative abundances will be consistent with the release of reactor coolant et nonnal post shut down activity. 7,;e release path does not pass through the SI3GT system and hold up .

times are negligible therefore no filtration credit is giver. for halogens.

t 4 Reactor building vent rucase concentrations are based upon a release Dow rate of 20.(XX)

CFM. This is consistent with the isolation of the reactor buliding ver.,ilation, initiation of the

Standby Gas Treatment System, and enntinued use of Radwaste building. Off. Gas building, and Turbine building (high) f ans.

, s

5. Onsite and field data will be pnvided to plant teams only where they perfonn appropriate tasks and request specific infonnation. -

Dore Assessment Datn

1. Dose assessment data is not provided in this scenario. The release rate is not su'ncient to cause ofuite dose to exceed normal background levels or require any pre:tive action recommendations.

CovHLlfacnLihtia

1. The fractions for the various rudjonuchdes are taken from historical plant data.

2. Core damage assessment was performed using EP IP-330, Core Damage". It is assumed the.

reactor has been operating at an average power of 97% for 200 days. There is no core damage ,

postulated in this scenario.

l Page 5 1 1

l 5.1 Radlological Asstiinntions

3. Dose rates from post accident samples were calculated using the Radiological licalth llendbook rule of thumb: .

R/hr at 1 foot 5.64CE w here:

C = number of curies f = energy in MeV Eis conservatively assumed to be 0.5 MeV for iodine and 0.7 MeV for noble gases. Shielded values assume a 2 inch lead pig is used.

Innlant Radiologien! Data

1. The fractions for the varioa radionuclides are taken from historical plant data.

2. Immersion dose rates were developed by calculating a center point dose in a semi ininite cloud of noble gases, utiliting the fonnula:

D =[X *i DFi where:

D = gamrna air dose Xi = concentration of nuclide i DFi = dose factce for expcsure to a semi infinite cloud of nuclide 1.

} Dose factas were obtained from Regulatory Guide 1.109, Table B 1, pp.1.l(9 21. -

3. Where appropriate, dose rates from affected plant systems are calculated using point, line, and plane source equations. The dos 3 contributions are also reflected on the affected area radiation inonitor tradings.

4. Air sample results are calculated utilizing EP IP 440. " Emergency Exposure Controls" lodine concentrations are calculated using an assumed air sample volume of 20 ft3 and a backgmund level of 50 CPM. S AM Il efficiencies are assumed to be 1.5% and RM 14 efficiencies to be 10E Environmental Data 0

1. Environmental and field survey data is not provided in this scenario. The r ocase rate is not sufficient to cause field measurements to increase beyond background levels.

4 Page 5 2

l Section 5,2 Messages and Trend Data 6

-- , . - . - - -,. - - - . . . - . - - . , , - , . . -, , . - - , -- - - - . . . . - , ,- . . , . , , - - . ~ , . < , , , - -n

058 1992 EE Meteorological Data Vent and Flow Data i

Scenari5 220' Tower 160 Tower 33' Tower Delta T Air Temp SBGT- RB Vent Mn Stack TB Vent !

Tiine *Froml MPH *From l MPH From MPH "F 'F CFM CFM CFM CFM

-00.00 018- 8.0 016 7.5 020 6.7 -1.8 56 ISOLATED 105,000 16.000 140,000 00:15 020 8.2 018 7.7 022 6.9 -1.8 56 ISOLATED 105.000 16,000 140,000 ;

i 00:30 021 8.8 019 8.3 023 7.5 -1.5 56 ISOLATED - 105,000 16,000 140,000 [

00:45 025 8.4 023 7.9 027 7.1 45 57 ISOLATED 105,000 16.000 140.000 [

01-00 ' 029 8.0 027 7.5 031 6.7 - i .5 57 ISOLATED 105.000 20,000 140,000 [

01:15 031 7.5 029 7.0 033 6.2 -1.6 57 ISOLATED 105,000 20,000 140,000 01-25 033 7.9 031 7.4 035 6.6 -1 S 58 8,000 ISOLATED 24,000 140,000 i 2

01:30 035 10.0 033 9.5 037 8.7 -1.6 58 8,000 tSOLATED 24,000 140,000 l 01:45 038 7.2 036 6.7 040 5.9 -1.6 58 4,000 ISOLATED 20,000 140,000 [

02:00 043 7.0 038 6.5 042 5.7 -1.7 59 , 4,000 ISOLATED 20,000 140,000 !

4,000 4

02:15 .

045 6.7 043 6.2 .047 5.4 -1.7 59 ISOLATED 20.000 140,000 i

. 02:30 l 049 6.4 047 5.9 051 5.1 -1.7 59 4.000 ISOLATED 20,000 140,000 02:45 052 6.6 050 6.1 054 5.3 -1.7 60 4,000 ISOLATED 20,000 140,000 03:00 055' 6.4 053 5.9 057 5.1 -1.7 60 4,000 ISOLATED 20.000 140.000 [

03:15 056 6.1 054 5.6 058 4.8 -1.8 60 4,000 ISOLATED 20,000 140,000 !

03:20 057 7.0 055 6.5 059 5.7 -1.8 61 4.000 ISOLATED 2'0,000 140.000 l

03:30 058 6.0 056 5.5 060 4.7 -1.8 S1 4,000 ISOLATED 20.000 140.000 i 062 4,000 20,000 03:45 060' 5.8 l 058 5.3 4.5 -1.8 62 ISOLATED 140.000 04:00 062 5.6 l 060 5.1 OS4 4.3 -1.7 62 4.000 ISOLATED 20.000 140,000 i

l Table 5.2-1 Table 5.2-2 i

i

' This is a Drill Page 5-3 This is a Dril! [

l

92 0511 1992 E1:

Forecast Message No.: 1 Scenano Tmse: 01tu SOUTIIERN NEW ENGLAND ZONE FORECASTS NATIONAL WEAT(IER SERVICE, llOSTON M A.

An unstable weather pattern dominates the region. Low pressurr will develop from the south causing winds 'o shift to a more westerly direction. Clouds will continue to develop with an incrrasing chance of precipitation towards evening. Rain will be ending by tomormw noming with the low pressure area gradually moving offshore by tomorrow afternoon GREAT ER llO510N MElROPOLII AN AREA NORTilEASTERN, COASTAL, AND SOUT.il.E ASTERN M A.

This moming cloudy with temperaturrs ranging 50' to $5'P. Winds from the NNE 5 to 10 MPil with gusts of up to 20 MPil. 207c chance of precipitation.

His afternoon increasing clouds with temperatures 55' to 60*. Winds from the ENE 5 to 10 MPil with gusts of up to 20 MPil. 40% chance of precipitation This evening cloudy with temperatures $5' to 60'. Winds from the East 10 to 15 MPli with gusts of up to 25 MPil. 609 chance of precipitation.

Tonight cloudy, windy, and rainy with temperatures 50' to $5' Winds fmm the East 13 to 18 MPli with gusts of up to 25 MPil. 801 chance of precipitation.

Tomorrow decreasing cloudiness with high temperatures 60* to 65*. Winds steady from the SE 8 to 13 MPil. 407c chance of ptreipitation.

' ong range forecast clear siles with high temperatures 60' to 65' and low temperatures SO' to 55' Winds wil.1 shift from the SSE 5 to 10 MPli, CAPE COD AND Tile ISL. ANDS, SOUTil COASTAL. AND CO ASTAL R.I.

This morning cloudy with temperatures ranging 50' to 55'F. Winds from the NNE 5 to 10 MPli with gusts of up to 20 MPil. 20% chance of precipitation This afternoon increasing clouds with t-mperatures 55* to 60'. Winds from the ENE 5 to 10 MPil with gusts of up to 20 MPil. 40% chance of precipitation.

This evening cloudy with temperatures 55' to 60* Winds from the East 10 to 15 MPil with gusts of up to 25 MPil. 60% chance of precipitation.

Tonight cloudy, windy, and rainy with temperatures 50' to 55' Winds from the East 13 to 18 MPil with gusts of up to 25 MPll. 80% chance of precipitation.

Toma w decreasing cloudiness with high temperaturrs 60* to 65' Winds steady from the SE 8 to 13 MPil. 40% chance of precipitation.

Long range forecast clear skies with high temperatu:rs 60' to 65* and low temperatures 50' to 55' Winds will shift from the SSE 5 to 10 MPil.

This is a Drill Page 5 I This is a Drill

l 92 0$11 1992 1:0 lorreasthsage No : f~ Scenano Tmr 02m j SOUTHERN NEW ENGLAND IONE FORECASTS NATIONAL WEATHER SERVICE, HOSTON MA. l An unstable weather pattern dominates the region. low pressure will develop from the south {

causing winds to shift to a more westerly direction. Clouds will continue to develop with an ,

increasing chance of precipitation towards evening. 8ain will be ending by tomorrow normng l

. witn the low pressure area gradually moving offshort by tomormw aftemcon '

GHEA'I ER llOSTON ME'I HOPOO'l AN~ AREA NORTilEASTERN, CO ASTAl., AND SOUTilCASTERN M A.

This moming cloudy with temperatures ranging 50' to $5'F. Winds from the NNE 5 to 10 MPH with gusts of up to 20 MPH. 20% chance of pre +

ion.

This aftemoon increasing clouds with temperat: u F i . Wi. from the ENE 5 to 10 MPil with gusts of up to 20 MPil. 40% chance of pro muur.

This evening cloudy with temperatures 55' to 60'. Wind 3 som the East 10 to 15 MP!! with gusts of up to 25 MPH. 60% chance of precipitation.

Tonight cloudy, windy, and rainy with temperatures 50' to 55' Winds fmm the East 13 to 18 MPil with gusts of up to 25 MPil. 80% chance of precipitation.

Tomorrow decreasing cloudiness with high temperaturrs & to 65' Winds steady from the SE 8 to 13 MPil. 409 chance of prreipitation.

long range forecast clear sk.ie> with high temperatur:s 60' to 65* and low temper tures 50' to 55' Winds will shift from the SSE 5 to 10 MPH.

CAPE COD AND Tile ISLANDS, SOUTil COASTAE, AND COASTAE R I.

This mominfup with gusts o to 20 MPIL 20% chance of precipitation. cloudy with temperatures l

l This afternoon increasing clouds with temperatures 55' to 60' Winds from the ENE 5 to 10 MPH l with gusts of up to 20 MPH. 40% chance of precipitation.

This evening cloudy with temperatures 55' to 60'. Winds from the East 10 to 15 MPli with gusts of up to 25 MPH. 609 chance of precipitation.

Tonight cloudy, windy, and rainy with temperatures 50' to 55*. Winds fmm the East 13 to 18 MPl! with gusts of up to 25 MPH. 80G chance of precipitation.

l Tomcnow decreasing cloudiness with high temperatures 60' to 65* Winds steady from the SE 8 I

to 13 MPfl 40% chance of prreipitation.

Long range forecast clear skies with high temperatures 60 to 65' and lov temperatures 50' to 55' Winds will shift from the SSE 5 to 10 MPH.

This is a Drill Page 5 5 This is a Drill

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

92 0511 1992 EE

~ ~'~~ ~~

Forecut hiewage NoTT _

Scenano Time: OMO SOUTHERN NEW ENGLAND ZONE FORECASTS NATIONAL WEATIIER SERVICE, BOSTON MA.

An unstable weather pattern dominates the region. lew prr:,',urr will develop from the south causing winds to shift to a mort westerly direction. Clouds will continue to develop with an increasing chance of prreipitation towards estning. Rain will be ending by tomorrow moming with the low pressure area gradually moving offshore by tomorrow afternoon GRE ATT.R IlOS I ON MEl ROPOLl~l AN~ ARL A NORTilEASTERN, CO ASTAL, ANI)

SOUTilE ASTERN M A.

This moming cloudv with temperaturrs ranging 50* to 55'F. Winds from the NNE 5 to 10 htPil with gusts of up to 20 MPH. 20% chance of precipitation.

This aftemcon increasing clouds with temperatures $5' to 60'. Winds from the ENE 5 to 10 MPH with gusts of up to 20 MPH. 40% chance of precipitation This evening cloudy with temperatures 55' to 60*. Winds from the East 10 to l$ MPil with gusts of up to 25 MPil. 60% chance of precipitation.

Tonight cloudy, windy, and rainy with temperatures 50' to 55' Winds from the East 13 to 18 hiPH with gusts of up to 25 MPil. 80% chance of precipitation. ,

Tomorrow decreasing cloudiness with high temperatures 60* to 65* Winds steady from the SE 8 to 13 MPil. 40% chance of precipitation.

long range forecast clear skies with high tempemturrs 60' to 65' and low tem;eratures 50' to 55' Winds will shift from the SSE 5 to 10 MPil.

CAPL COD AND 1IIE ISLANDS, SOUTil COASTAL, AND COASTAL R.1.

Thi3 moming cloudy with tecperatures ranging SG' to 55'F. Winds from the NNE 5 to 10 MPil with gusts of up to 20 MPil. 20% chance of precipitation.

This afternoon increasing clouds with temperatures 55' to 6(r. Winds from the ENE 5 to 10 MPil with gusts of up to 20 MPil. 40% chance of precipitation.

This evening cloudy with temperatures 55' to UP. Winds from the East 10 to 15 MPil with gusts of up tc '15 MPil. 60% chance of precipitation.

Tonight cloudy, windy, and rainy with temperatures 50' to 55' Winds frum the East 13 to 18 MPil with gusts of up to 25 MPH. SOG chance of precipitation.

Tomorrow decreasing cloudiness with high t:nperatures 6fr to 65' Winds steady from the SE 8 to 13 MPil. 40% chance of prreipitran.

Long range forecast clear dies with high temperatun s 60' to 65* and low tempentures 50* to 55' Winds will shift fmm the SSE 5 to 10 MPH.

T his is a Drill Page 5 6 This is a Drill

l 92 0511 1992 E1:

1 orecast hiessage No.: 4 Scenano 'l ime: Ntb e4 SOUTHERN NEW ENGLAND ZONE FORECASTS NATIONAL WEATHER SERVICE, IlOSTON M A.

An unstable w eather pattern dominates the region. Low prrssure will des elop from the south causing winds to shift to a morr westerly direction. Clouds will continue to develop with an increasing chance of precipitation towards evening. Rain will be ending by tomorruw morning with the low pressure area gradually moving offshort by tomonow aftemoon GRE Alf.R IlO5'l ON hlLTROPOLIT AN ARLA NORTilEASTERN, COASTAL, AND SOUTilE ASTERN 31 A. _

This morning cloudy with temperatures ranging 50' to 55'F. Winds from the NNE 5 to 10 hiPil with gusts of up to 20 htPil. 20% chance of precipitation.

This aftemoon increasing clouds with temperatures 55' to & Winds from the ENE 5 to 10 htPil with gusts of up to 20 hiPil. 40% chance of precipitation.

This evening cloudy with temperatures 55' to 60'. Winds fmm the East 10 to 15 hiPil with gusts of up to 25 h1Pil. 60% chance of precipitation.

Tonight cloudy, windy, and rainy with temperatures 50' to 55' Winds from the East 13 to 18 h1Pil with gusts of up to 25 hiPil. 80% chance of precipitation.

Tomorrow decreasing cloudiness with high temperatures 60' to 65*. Winds steady from the SE 8 to 13 hiPll. 409 chance of pn cipitation.

Long range forecast clear skies with high temperatures 60' to 65' and low tempcratures 50' to 55' Winu, will shift from the SSE 5 to 10 hiPil.

CXPL COD AND lilE ISLANDS, SOUTil CO ASTAl, AND COASTAL R.I.

This morning clout.y with temperatures ranging 50' to 55'F. Winds from the NNE 5 to 10 htPil with gusts of up to 20 hiPil. 20% chance of precipitation.

This afternoon increasing clouds with temperatures 55' to W. Winds from the ENE 5 to 10 htPil with gusts of up to 20 hiPil. 40% chance of precipitation.

This evening cloudy with temperatures 55' to 601 Winds from the East 10 to 15 h1Pil with gusts of up to 25 h1PH. 60% chance of precipitation.

Tonight cloudy, windy, and rainy with temperatures 50' to 55'. Winds fro:n the East 13 to 18 hiPil with gusts of up to 25 hiPil. 80% chance of precipitation.

Tomorrow decreasing cloudiness with high temperatures W to 65' Winds steady f:um the SE 8 to 13 hiPil 40% chance of ptrcipitation.

Long range forecast clear skies with high temperatures & to 65' and low temperaturrs 50' to 55' Winds will shift f rom the SSE 5 to 10 hiPit This is a Drill Page 5 7 This is a Drill

$245B Effluent Radiation Monitor Trend Data 1992 EE Table 5.2 3 1

1705 18 ERht 1 h1AIN STACK LOW (CPS) ST 23' l

1001-60S ERht2 hiAIN STACK ll!GH (R/IIR) ST 23' 1705-32 ERhi-3 RB VENT LOW (CPS) TB 51' 1001 609 ERht-4 RB VENTll!GH (R/ilR) TB 51' 1001-610 ERht-5 TB VENT 111011 (R/HR) TB $1' Time ERM 1 ERM 2 ERM 3 ERM 4 ERM 5 00:00 70.6 DS 37.7 DS DS 00:15 69.1 DS 37.7 DS DS l 00:30 67.2 DS 37.7 DS DS l 00:45 58.9 DS 36.7 DS DS 01:00 48.9 DS 35.1 DS DS 01:15 46.6 DS 34.8 DS DS 01:25 48.3 DS 20.4 DS DS 01:30 54.5 DS 31.9 DS DS 01:45 33.7 DS 17.6 DS DS 02:00 21.4 DS 17.7 DS DS 02:15 19.1 DS 17.5 DS DS 02:30 11.6 DS 28.8 DS DS 02:45 14.1 DS 29.4 DS DS 03:00 14.0 DS 29.2 DS DS 03:15 13.8 DS 29.4 DS DS 03:20 17.0 DS 138.6 DS DS 03:30 20.6 DS 42.2 DS DS 03:45 18.1 DS 36.6 DS DS 04:00 11.7 DS 29.3 DS DS i

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_ _ _ _ _ _ . ____._____m.___ ..___ __

1993 EVALUATED EXERCISE _Mso No: 1 PROCESS RADIATION MONITORS Tiue: 00 00 PANNEL/lD NO. MONITOR Trend READING Alarm in RANGE C 910/1705 18 6 Maln Stack Lo l I 70.6 CPS U 13 *' 10 C910/1001 608 Main Stack HI I l ,D S Rihr l l10 10 C910/1705 32 Rx Bldg Vent to l l 37.7 CPS U 10 10 C910/1001 609 Rx Bldg Vent Hi l l 08 R/hr I l10^ 10 #

C 910/1001 610 Turbine Bldg Vent Hi l 1 DS R/hr R 10*I 10 #

0910/1705 2 0 Maln Steam Line A I l 632.9 mR/hr I I 10 10 0 6 Maln Steam Line B I l 814.5 mR/hr I I 10 10 0

Maln Steam Line C l 1 545.1 mR/hr I I 10 10 0

Main Steam Line D I l 632.9 mR/hr I I 10 10 i C910/1705 3 Air Ejector Off Gas l l 23.9 mR/hr I I 10 10' C910/1705 4 RBCCW Loop A l j 4015 CPS I I10 10 4 RBCCW Loop B l l 4025 CPS 1 110 10' C910/1705 8 Refuel Floor Vent [ l 6 mR/hr l l10 10' '

C910/1705 9 SBGT Exhaust l l 3 _ mR/hr U 10 10' C910/1705 16 Control Rm Air intake l l 0 mR/hr l l 10 '# 10 C910/1705 30 R/W Discharge 1 I 4000 CPS I I10^ 10 C910/1705 5 Off Gas Post Treatment l l 4319 CPS I i10^ 10 0 C170/1001 606 Drywell CHRMS A I .I 1.1 R/hr I I 10 U

10 7

Drywell CHRMS B l l 1 R/hr I I 10 10 7

C170/1001 607 Torus CHRMS A 1 10 R/hr I I10" 10 6 Torus CHRMS B l l 0 R/hr l l10' 10 FLOW RATES PannelC7 SBOT F18126/7 ISDLATED CFM Maln Stack 16000 CFM' Rx Bldg Fl8116A 105000 CFM TB Vent 140000 CFM' MET DATA Pannel MT1 *160' 22_Q' D12' '

Delta Temp 1.8 Dog. F Dir (from) 16 16 20 Do g.

Outelde Temp 56_

Dog. F Speed 8 7.5 6.7 MPH Stability Class D

Precip None -

Not Avallable in Control Room OOS Out of Service OSH off Scale HI DS Down Scale i

This is a Drill Page 511

i 1992 EVALUATED EXERCISE ,Mso No: 2 PROCESS RADIATION MONITORS mue 00:i5 PANNEL/ID NO. MONITOR Trend READING _.Atarm in RANGE C 910/1705 18 Main Stack Lo I l 69.1 CPS I l 10 *I .10 C 910/1001 600 Main Stack Hi I I DS Rlhr U 10 10 '

C910/1705 32 Rx Bldg Vent Lo l l 37.7 CPS f~ l 10 ' .10 C910/1001 609 Rx Bldg Vent HI l l DE R/hr l l10 ' 10 C 910/1001 010 Turbine Bldg Vent Hi I J DS R/hr I l 10 10 0

C910/1705 2 Main Steam Line A I l 630.6 mRlbr I I 10 10 0 6 Main Steam Line B I l 811.6 mR/hr l I 10 10 l 0

Maln Steam Line C l l 643.1 mRlhr 1 I 10 10 0

Main Steam Line D 1 1 630.6 mR/hr I l 10 10 0

C910/1705 3 Air tjector Off Gas 1 I 23.8 mR/hr I I 10 10

0 C910/1705 4 RBCCW Loop A I I 3715 CPS [ ] 10 ' .10 RBCCW Loop B l l 3728 CPS I I10^ 10 C910/1705 8 Refuel Floor Vent l l _6_ _ mR/hr I i 10 .10 3 0

C910/1705 9 SBOT Exhaust 1 I 3 mR/hr l l 10 10 C D 10/1705 16 Control Rm Air Intake l l 0 , mR/hr l l 10 ' 10 C910/1705 30 R/W Discharge l I 4000 CPS l l 10 ' .10 C910/1705 5 Off Gas Post Treatment l l 4208 CPS I I10 '.10 ,

C170/1001 606 Drywell CHRMS A I l 1.9 R/hr I I 10 10 Drywell CHRMS B l l 1.8 R/hr I I 10 10 C 170/1001 607 Torus CHRMS A l l 0 R/hr M 10 10 i

Torus CHRMS B I _l 0 R/hr I i 10 10 FLOW RATES PannelC7 SBOT Fl8126/7 ISOL ATED CFM Main Stack 16000 CFM' Rx Bldg Fl8116A 105000 CFM TO Vent 140000 CFM' MET DATA Pannel MT1 22f' *10_0 ' MJ '

Detta Temp .1.8 _ Do g. F Dit (from) 20 18 22 Dog.

Outside Temp 56 _ Dog. F Speed 8.2 7.7 6.9 MPH Stability Class D .

Precip Nons *

Not Available in Control Room OOS Out of Darvice OSH.Off Scale Hi DS Down Scale Tliis is a Drill Page 512

1992 EVALUATED EXERCISE Msa No! 3 PROCESS RADIATION MONITORS TiMr. 00,30 EANNEL/lD NO. MONITOR Trend _ READING Alarm in RANGE C 910/170 5,18 Main Stack Lo l I 67.2 CPS I I 10 ' = !O '

C 910/1001 608 Main Stack Hi I I DS R/hr I I10 .10 #

C910/1705 32 Ha Bldg Vent Lo I l 37.7 CPS I I10 '.10 0 C910/1001 609 '4x Bldg Vent Hi I I DS R/hr I i10 .10 #

C 910/1001 610 Turbine Bldg Vent Hi l l 0S R/hr l I10 .10*

C910/1705 2 Main Steam Line A l l 628.5 mR/hr I I 10 10' Main Steam Line B l l 808.9 mR/hr U 10 10' Main Steam Line C l l 541.3 mRIhr l l 10 10 0

Main Stear:1 Line D I I 628.5 mRIhr I I 10 10 0 0 C910/1705 3 Air Ejector Off Gas l I 23.6 mR/hr I I 10 10 C910/1705 4 RBCCW Loop A l l 3431 CPS I i10 .10' RBCCW Loop B l 1 3441 CPS I l10 .10 C910/1705 8 Refuel Floor Vent l l 6 mR/hr I I 10 *I .10 3 C910/1705 9 SBGT Exhaust I l 3 mR/hr l l 10 10 2

C 910/1705 16 Control Rm Air intake 1 l 0 mR/hr I i 10 ' 10 C910/1705 30 R/W Discharge l l 4000 CPS I I10 ' .10' C910/1705 5 Off Gas Post Treatment I I 4101 CPS I l10 .10' C 170/1001 606 Drywell CHRMS A 1 l 3 R/hr l l 10 10 0

Drywell CHRMS B 1 l 2.9 R/hr l l 10 10 0

C170/1001 607 Torus CHRMS A I l 0 R/hr I I 10 10 Torus CHRMS B l l 0 R/hr I I 10 10 FLOW RATES Pannel C7 SBGT Fl8126/7 ISOL ATED CFM Main Stock 16000 CFM' Rx Bldg Fl8116A 105000 _ CFM TB Vent 140000 CFM' MET DATA Pannel MT1 22D' *160' O.3.3 '

Delta Temp 1.5 Dog. F Dir (from) 21 19 23 Dog.

Outside Temp 56 Dog. F S p e e rt a.8 8.3- 7.5 MPH Stability Class D

Precip None

l

Not Aval!able in Control Room OOS Out of Service OSH Off Scale Hi DS Down Scale Tliis is a Drill Page 5 13

-~ - - . . .. _- - - . - _ - - - - . - . -.- - - . - - - - -

l 1992 EVALUATED EXERCISE _Mso No: 4 PROCESS RADIATION MONITORS .Tiue: 00,4s PANNEL/ID NO. MONITOR Trend READING Alarm in RANGE C 910/1705 18 Main Stack Lo l I 58.9 CPS I l10.10' C 910/1001 608 Main Stack HI 1 l DS R/hr U 10 .10" l C910/1705 32 Rx Bldg Vent Lo l l 36.7 CPS I l10 '.10' C 910/1001 609 Rx Bldg Vent HI I l DS Rlhr R 10 ' 10 C 910/1001 610 Turbine Bldg Vent Hi I l DS Rlhr l I10.10" l

C910/1705 2 Main Steam Line A I I 558.7 mRlbr l l 10 10' Main Steam Line B l l 719.1 mR/hr l I10' .106 0

Main. Steam Line C l l 481.2 mR/hr i 1 10 +10 0

Main Steam Line D I l 558.7 mR/hr l I 10 10 0

C910/1705 3 Air Ejector Off Gas l l 22.2 mRIhr I I 10 10 ,

C910/1705 4 RBCCW Loop A l l 3174 CPS I l10.10 '

RBCCW Loop B l l 3184 CPS I l10 ' .10" C910/1705 8 Refuel Floor Vent l l 6 mRIhr I i10 .10 8 C910/1705 9 SBGT Exhaust I l 3 mR/hr l I 10 10 C910/170 5 16 Control Rm Air intake l l ,0 mR/hr I I 10 10 C910/1705 30 R/W Discharge L l 4000 -CPS I l10 .10 C910/1705 5 Off Gas Post Treatment l I 3984 CPS I I10^ 10 0 C170/1001 606 Drywell CHRMS A 1 1 3.8 R/hr l I 10 10 0

Drywell CHRMS B l l 3.7 R/hr l l 10 10 U

C170 /1001 607 Torus CHRMS A I l 0 R/hr l l 10 10 Torus CHRMS B l l 0 R/hr b 10 0

+10 FLOW RATES Pannel C7 SBGT Fl8126/7 ISOL ATED CFM Main Ste:k 16000 CFM' Rx Bldg Fl8116A 105000 CFM TB Vent 140000 CFM' MET DATA Pannel MT1 220'. *160' 033' Delta Temp .1.5 Dog. F Dir (from) 25 23 _

27 'Deg.

Outside Temp 57 Dog. F Speed 8.4 7.9 7.1 MPH Stability Class D '

Precip None *

Not Available in Control Room OOS Out of Service OSH Off Scale Hi DS Down Scale l

This is a Drill Page 5 14

_ _ _ _ _ . . _ _ . _ . _ _ _ . _.___m__ _ _ . _ _ _ _ _ _ _ _ _ . _ . _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . _

1992 EVALUATED EXERCISE Msa No! 5 i

PROCESS RADIATION MONITORS Time! on0o P A N N E L/lD N O. MON 110R 7tene READING Alarm in RANGE C 910/1705 18 Main Stack Lo l 1 48.9 CPS I I10 .10 0 C 910/1001 608 Main Stack Hi I l D S, RIhr I i10 .10" C910/1705 32 Rr Bldg Vent Lo 1_ l 35.1 CPS I I10^ .10" C 910/1001 609 Rx Bldg Vent HI I l DS R/hr I I 10 ' 10 C 910 /1001 610 Turbine Bldg Vent Hi I I DS R/hr l I 10' 10 0

C910/1705 2 Main Steam Line A I l 448.4 mR/hr I I 10 +10 Maln Steam Line B I I $77.2 mRlhr l l 10 10 0 6 Main Steam Line C l l 386.2 mRlhr I i 10 10 0

Maln Steam Line D I I 448.4 mRlhr 1 I 10 10 0

C910/1705 3 Air Elector Off Gas l I 18.9 mR/hr U 10 10 C910!i705 4 RBCCW Loop A 1 l 2_945 CPS I l 10 10" l10 '.10' RBCCW Loop B l 1 2955 CPS I C910/1705 8 Refuel Floor Vent l l 6 mR/hr l l10.10 C910/1705 9 SBGT Exhaust l l 3 mRlhr I I 10 10 C 910/1705 16 Control Rm Air intake l I o mRIhr I l 10 *# .10 2 l10 .10 C910/1705 30 R/W Discharge 1 1-4000 CPS I C910/1705 5 Off Gas Post Treatment l l 3746 CPS I )10^ .10 C170/1001 606 Drywell CHRMS A I l 4.3 R/hr l l 10 10 ,

Drywell CHRMS B l l 4.2 Rlhr l l 10 10 C 170/1001 607 Torus CHRMS A I I o R/hr I 1 10 10 I

Torus CHRMS B I l 0 R/hr U 10 10 FLOW RATES Pannel C7 SBOT Fle126'7 ISOL ATED CFM Mein Stock 20000 CFM' Rx Bldg F:8116A 105000 CFM TB Vent 140000 ,CFM' MET DATA Pannel MT1 2E *160' D33' Dette Temp .1.5 Dog. F Dir (from) 29 27 31 Dog.

Outside Temp 57 D*D. F Speed 8 7.5 6.7 MPH Stability Class D

Precip None *

Het Avelteblo in Control Room OOS-Out of Service OSH.Off Scale Hi DS-Down Sca!e l

This is a Drill Page 515 l

l

, - . . . - , , . , . . . , , ~.- . - - . - . . . - - . , . -

1992 EVALUATED EXERCISE .Msa No; 6 PROCESS RADIATION MONITORS w e cios P ANN EL./1QE.04____ ,___EORLTOR 7 tend READING Alarm in RANGE C910/170518 Main Stack to l l 46.6 CPS i l 10 .10 C 910/1001 608 Main Stack HI l l DS R/hr l l 10 ' 10 C910/1705 32 Rx Bldg Vent Lo l l 34.8 CPS U 10.10 #

C910/1001 609 Rx Bid 0 Vent HI l l DS R/hr l l 10 .10 C 910/1001 610 Turbine Bldg Vent HI l l DS R/hr l l 10 .10 0

C910/1705 2 Main Steam Line A l l 439.9 mR/hr l l 10 10 0

Main Steam Line B I l 553.3 mR/hr l l 10 10 0

Main Steam Line C l l 370.2 mR/hr l l 10 10 6

Maln Steam Line D l l 429.9 mR/hr l l 10 10 C910/1705 3 Air Ejector Off Gas l l 17.1 mR/hr 1 I 10 10 C910/1705 4 RBCCW Loop A l l 2741 CPS I I10.10 6

HDCCW Loop B I l 2751 CPS l l 10 ' 10 C910/1705 8 Refuel Floor Vent l l e _.

mR/hr l l10'I .10 3 0 #

C910/1705 9 SBGT Exhaust I l 3 mR/hr l l 10 10 C 910/1705 16 Control Rm Air intake l l 0 mR/hr l l 10 ' 10 C910/1705 30 R/W Discharge l l 4000 CPS I l10 .10 C910/1705 5 Off Gas Post Treatment l l 3413 CPS l l10 ^ .10 C170/1001 606 Drywell CHRn A I I 4.6 R/hr l l 10 10 0

Drywell CHRMS B l l 4.5 R/hr I i 10 10 C170/1001 607 Torus CHRMS A l l 0 R/hr l l 10 10 Torus CHRMS B l l 0 R/hr l l 10 10 FLOW RATES PannelC7 SBGT Fl8126/7 ISOL ATEF CFM Main Stack 20000 CFM' Rx Bldg Fl8116A 105000 CFM TB Vent 140000 CFM' MET DATA Pannel MT1 22S' *160' 033' Delta Temp .1.6 Dog. F Dir (from) 31 29 33 Deg.

Outside Temp 57 Dog. F Speed 7.5 7 _6_. 2 MPH Stability Class C

Precip None *

Not Avallable in Control Room OOS-Out of Service OSH Off Scale Hi DS Down Scale This is a Drill

)-

Page 516

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

l 1992 EVALUATED EXERCISE Mso No; 7 <

PROCESS RADIATION MONITORS .nMe: 01:25 f-PANNEL/ID NO. MONITOR Trend READING Atarm in RANGE C 910/1705 18 Main Stack Lo l l 48.3 CPS I l 10 ' .10 0 C910/1001 608 Main Stack Hi I l DS R/hr l l 10 ^ 10 "

C910/1705 32 Rx Bldg Vent to l I 20.4 CPS I l 10 ' 10 0 C910/1001 609 Rx Bldg Vent Hi I l DS Hlhr l I10 '.10 #

C 910/1001 610 Turbine Bldg Vent Hi l l DS R/hr I l 10 10 "

l 0

C910/1705 2 Main Steam Line A l l 66.3 m R/h r [___j 10 10' Main Steam Line B l l 85.4 mRlhr R 10 10' 0

Main Steam Line C l 1 57 mRlhr i I 10 10 0

Maln Steam Line D l l 66.3 _ mR/hr l l 10 10 f 0 '

C910/1705 3 Air Ejector Off Gas l l 16.6 mR/hr l l 10 + 10 '

C910/1705 4 RBCCW Loop A l l 1557 CPS I l 10 ' 10 RBCCW Loop B I I 2567 CPS [___J 10 '.10 l10 ' 10 3 C910/1705 8 Refuel Floor Vent l l 6 mR/hr l .

C910/1705 9 SBGT Exhaust l l 3 mR/hr l l 10 ' 10 C 910/1705 16 Control Rm Alt intake l IO mR/hr l l 10 10 6

C910/1705 30 R/W Discharge l l 4000 m _

CPS I l 10 10 l10 '.10 C910/1705 5 Off Gas Post Treatment l l 3150 CPS I C170/1001 606 Drywell CHRMS A l l 4.5 R/hr l l 10 10 Drywell CHRMS B l l 4.4 R/t l l l 10 10 C170/1001 607 Torus CHRMS A I I .3 R/hr l l 10 10 Torus CHRMS B l l .2 Rlbr l l 10' 10 FLOW RATES PannelC7 SBGT Fl8126r7 8000 CFM Main Stack 24000 CFM' t Rx Bldg F18116A ISOL ATED CFM TB Vent 14o09 CFM*

MET DATA Pannel Mit 2JLO' *1fLO' E3.3 '

Delta Temp 1.6 Deg. F Dir (from) 33 31 Dag.

3_5 Outside Temp 50 Dec. F Speed 7.9 7.4 6.6 MPH Stabil!!y Class C

Precip None *

' Not Available in Control Room OOS Out of Service OSH Off Scale HI DS Down Scale This is a Drill Page 517

_-. -. _ _ _ . .._._._.._ _ _ . . _ _ __._ __ _ _ _ _ _ _.__.___a

1998 EVALUATED EXERCISE _Msa Not a _ _ _

PROCESS RADIATION MONITORS Tiue 0n30 PANNEL/lD NO. MONITOR Trend READING Alarm in RANGE C 910/1705 18 Maln Stack Lo l l 54.5 CPS I l 10 ' 10 '

C910/1001 608 Main Stack Hi I l DS R/hr l l 10 *I .10 C910/1705 32 Rx Bldg Vent to l l 31.9 CPS I I10.10 0 f C 910/1001 609 Rx Bldg Vent Hi I l DS R/hr I I10.10 I C910/1001 610 Turbine Bldg Vent HI l l DS R/hr I -l10.10" l

U 0 C910/1705 2 Main Steam Line A l l 312.5 mR/hr l l 10 10 0

Main Steam Line B l I 402.2 mR/hr l l 10 +10 Main Steam Line C l 1 268.6 mR/hr l l 10 10' Maln Steam Line D l 1 312.5 mR/hr U 10 10' l C910/1705 3 Air Ejector Off Gas l l 16.1 mR/hr I I 10 0 .10 C910/1705 4 RBCCW Loop A l l 2590 CPS I i 10 .10' RBCCW Loop B 1 1 2600 CPS I i 10'I.10 0 CS10/1705 0 Refuel Floor Vent l I 6_ mR/hr [ l 10.10 0

C910/1705 9 - SBGT Exhaust 1 I 3 mR/hr l l 10 10 l C 910/1705 16 Control Fim Air intake l 10 mR/hr l l 10 +10 C910/1705 30 R/W Discharge l l 4000 CPS I l10.10' C910/1705 5 Off Gas Post Treatment l I 2887 CPS I l 10 *I .10 0

C170/1001 606 Drywell CHRMS A I I 4.6 R/hr l l 10 10 Drywell CHRMS B l ._ l 4.5 R/hr R 10 10 0

C170/1001 607 Torus CHRMS A l l .2 R/hr U 10 10 I

Torus' CHAMS B I l .2 R/hr l l 10 10 FLOW R ATES ' Pannel C7 SBOT Fl8126/7 8000 CFM- Main Stock 24000 CFM' Rx Bldg Fl8116A ISOL ATED CFM TB Vent 140000 CFM'

! MET DATA Pannel MT1 220' *1 S_02 del' Dette Temp .1.6 Deg. F Dir (from) 35 33 37 Dog.

l Outelde Temp 5 8 Dog. F Speed 10 9.5 8.7 MPH Stability Close C

Precip Mone

L

Not Aveliable in control Room OOS Out of Service OSH Off Scale Hi DS.Down Scale This is a Drill L Page 5 18

m._______-- .__ _ _ -

I 1992 EVALUATED EXERCISE MaaNm ff i

PROCESS RADIATION MONITORS Tiut oms !

PAlif4EL/1D 110. MOf4l TOR Trend READING Alum _tn._.BAllGE 0

C 910/170 5 18 Maln Stack Lo I I 33.7 CPS I I 10 ' 10 f C 10

C 9 # 0/1001 608 Main Stack HI l ~l D S R!hr 10 6

C910/1705 32 Rx Bldg Vent to I'~l 17.6 CPS C 10 ' 10 C910/1001 609 Rx Bldg Vent HI l l DS ,

R/hr C 10 10 l

C 910/1001 610 Turbine Bldo Vent HI l l DS Rlht C 10+10 0

':910/1705 2 Main Steam Line A I l 53.4 _ rnRIhr I i 10 10 !

Main Steam Line H I l 68.7 _ mR/hr I 10 0 10 6 j Main Steam Line C l J 45 4 ,_ r13/hr I 1 10 10 -

0 Main Steam Line D l 1 53,4 mR/hr LJ 10 10 C910/1705 3 Air Elector Off Gas l l 10.7 mR/hr J ,J 10 10 C910/1705 4 RBCCW Loop A l 1 2391 __ CPS M 10 10 6

RBCCW Loop B l _ l 2401, ,, C P S I i10 10" l C910/1705 8 Refuel Floor Vent l J ,6, mR/hr R 10 10 '

C910/1705 9 SBGT Exhausi L__I .s mRihr io' 10' 2

0910/1705 16 Control Rm Air intake (~ j 0 mR/hr I 1 10 10 ' ,

C910/1705 30 R/W Discharge l J 4000 CPS I l 10 10 '

U C910/1705 5 Off Gas Post Treatment [ ] 19Y6 CPS l l 10 ' 10 0

C170/1001 606 Drywell CHRMP A [,~~] 3.4 ,,,

R/hr b 10 0 10 7

Drywell CHRMS S [~ i ,3. h R/hr l l 10 ,1g C170/1001 607 Torus CHRMS A I i .3 R/hr I ! 10 sl0 Torus CHRMS B l l .5 R/hr L,,j 10 10 FLOW RATES PannelC7 880T- Fl8126/7 4000 CFM Main Stack 20000 CFM*

Rx Bldg fl8116A ISOL ATC;D. CFM TB Vent _140000 CFM' MET DATA Pannel MT1 12D'. *15.D ' Djj' Delta' Temp 1.6 Dog. F Dit (from) ,3 8 36 40 D o g. L Outolde Temp 58 Dog. F Speed' 7.2 6.7 ,$ . 9 MPH p Stability Class C -

Precip None *

^

Not Available in Control Room OOS-Out of Service OSH-Off Scale HI DS Down Scale Tliis is a Drill Page 519 ,

__ .m..... - _ _ _ _ _ _ - _

_ . - . ~ . _ _ _

1993 EVALUATED EXERCISE .Msa Not 10 l l

PROCESS RADIATION MONITORS Time: 02 0e PANNEL/ID NO. MONITOR Ytend READING Alarm in RANGE C 910/1705 18 Main Sir ' Lo [ j 21.4 CPS I I 10 10 C 910/1001 608 Main Stsc Hi I I DS Albr I I10.10' C910/1700 32 Rx Bldg Vent Lo I i 17.7 CPS l l10^ 10 0 '

C 910/1001 609 Rx Bldg Vent Hi I 1 DS R/hr 1 -. I 10 10 e C 910/1001 610 Turblas Pldg Vent Hi l l DS Rlhr i I10^ 10 #

0 C910/1705 2 Main Sinam Line A I 1 50.9 mR/hr I I 10 10 0

Maln Steam Line B l l 65.5 mR/hr I 1 10 10 0

Main Steam Line C l l 43.8 ,, mR/hr l l 10 10 0

Main Steam Line D [_,] 5 0.9 mR/hr l l 10 10 0 6 C910/1705 3 Air Ejector Off Gas 1 I 7.7 mR/hr I i 10 ,19 C910/1705 4 RBCCW Loop A R 2241 CPS I 1 10 *I .10 6 ,

RBCCW Loop- D I I 2251 CPS I l10.10 0 C910/1705 8 Refuel Floor Vent l l 6 mR/hr I I10 10 C910/1705 9 SBGT Exhaust l l 3 mR/hr [ l 10 o 10 C 910/1705 16 Control Rm Air Intake I l 0 mR/hr l l 10 ' 10 C910/1705 30 R/W DischarDe i ! 4000 CPS I i10 .10 0 C910/1705 5 Off Gas Post Treatment I 1 1259 CPS I I10 .10 0 C170/1001 606 Drywell CHRMS A I I 3.1 R/hr 1 I 10 10 Drywell CHRMS B l _l 3 R/hr f"l 10 .10 C170/1001 607 Torus CHRMS A l l .5 R/hr l l 10 10 Vorus CHRMS B l l .4 R/hr I I 10 10 FLOW R ATES PannelC7 SDOT Fl8126T/ 4000 _ CFM Main Stack 20000 CFM*

Rx Bldg FW116A _lSOL ATED _

CFM TB Vera -140000 CFM' MET DATA Pannel MT1 210' *1fiDI 033' Delta Teing .1.7 Deg. F Dir (from) 40 38 ,

42 Dog.

Outside Temp 59 Dog. F Speed 7 6.5 __, 5.7 MPH .

Gisbility C!ssa C

Precip _Nnne _ *

Not Available in Control Room OOS.Out of Service OSH Off Scale Hi DS Down scale This is a Drill Page 5 20

(

,- . - - , - , . , . . , , , _ . , _ . - - - - _ , - - .._m,__..., ,,,~,..,-..-,,m. . . . . . - - . . . . . . . . . ~ . - _ , . - - . . - - , . . ~ . _ _ - _ _ _ _ - -

1998 EVALUATED EXERCISE Msc No: 11 PROCESS RADIATION MONITORS Tiuc. 02 is pat 4f4EL/lD t10. mot 4l TOR Trend READit4G Atarm in rat 4GE C 910/1705 18 Main Stack Lo I l 19.1 .

CPS I l 10 .10 C 910/1001 608 Main Stack Hi l l DS Rihr l l 10 .10 C910/1705 32 Rx Dldg Vent Lo 1 I 17.5 CPS I I 10 ' .10"

, C 910 /1001 609 Rx Bldg Vent Hi I l DS Rlhr 1 110 10 C 910/1001 610 Turbine Bldg Vent Hi I l DS R/hr l l10 .10 U

C910/1705 2 Main Steam Line A I ] 18.4 mRlhr l l 10 10 0

Main Steam Line B 1 l 23.6 mRIhr I I 10 10 Main Steam Line C l l 15.8 mRIhr I I 10 10 0

Main Oleam Line D l l 18.4 mR/hr l l 10 10 0

C910/1705 3 Air Elector Off Gas l l 7.4 mRIhr I i 10 10 C910/1705 4 RDCCW Loop A I l 2113 CPS I l10 .10 RBCCW Loop B l l 2123 , CPS I I10.10 C910/1705 8 Refuel Floor Vent l l 6 mR/hr I I 10 10 C910/1705 9 SBGT Exhaust l l 3 mR/hr I 1 10 10 2

C 910/1705 16 Control Rm Alt intake I ] 0 mRlhr U 10 +10 C910/1705 30 R/W Discharge l l 4000 CPS I 1 10' 10 C910/1705 5 Off Gas Post Treatment I l 659 CPS I l10.10 6 C 170/1001 606 Drywell CHRMS A l l 2.9 Albf I l 10 10 Drywell CHRMS B l l 2.8 Albr I l 10 10 C 170/1001 607 Torus CHRMS A l l .4 R/hr l l 10 10 Torus CHRMS D l l .3 Rlhr l l 10 10 FLOW R ATES PannelC7 SBGT Fl8126'7 4 000 CFM Main Stack 20000 CFM' Rx Bldg F18116A ISOL ATED CFM TB Vent 140000 _

CFM' MET DATA Pannel MT1 210' *15.Q ', QJJ' Detta Temp .1.7 Dag. F Dir (from) 45 43 47 Dog.

Outside Tamp I9 Dog. F Spesd 6.7 6.2 5.4 MPH Stability Class ,C Precip None

Hot Available in Control Room OOS.Out of Service OSH-Off Scale Hi DS.Down Scale This is a Drill Page 5 21

- _ _ . _ _ _____ . _ _ _ . _ _ _ . - . _ _ _ _ . . . _ . _ . , _ _ . _ . _ . _ ..._. _ _ _ ~ _ _

1992 EVALUATED EXERC:SE .#sa JJo; 12 PROCESS RADIATION MOiliTORS .w w mo PJJit4EL/ID NO. MOtllTOR TradEAQlNG Alum in RANGE C 910/1705 18 Main Stack Lo l I 11.6 CPS R 10 10' C 910/1001 608 Main Stack Hi I 1 DS R/hr l l 10 10 C910/1705 32 Rx Bldg Vent to l ] 28.8 CPS M 10 10 i C 910/1001 609 Rx Bldg Vent Hi l l DS R/hr R 10 10" C910/1005 610 Turbine Didg Vent Hi l l DS _ R/hr I I 10 +10 C 910 /17 0 5a 2 Main Steam Line A l l 18.1 m Rlhr 10* 10' Main Steam Ll'ie 0 [ l 23.3 mR/hr I l 10 10 0 6 Main Steam Line C l l 15.6 mR/hr R 10 ,19 0

Main Steam Line D I l 18.1 mR/hr U 10 D 10' 0

C910/1705 3 Air Ejector Off Gas I ] 7.4 mR/hr I l 10 10 6

C910/1705 4 RBCCW Loop A l l 1996 CPS I l 10 10

! RDCCW Loop B l l 2006 CPS l l 10 ^ 10 '

C910/1705 8 Refuel Floor Vent l l 6 mR/hr l l 10 .10 '

C910/1705 9 SBGT Exhaust l l 3 mRlhr R 10 10 C 910 /1705 16 Control Rm Air intake l l 0 mR/hr l l 10 ' 10 C910/1705 30 R/W Discharge l l 4000 CPS I l10^ 10 C910/1705 5 Off Gas Post Treatment l l 438 CPS I l 10 10 C170/1001 606 Drywell CHRMS A I I 2.6 R/hr l I 10 10 0

Drywell CHRMS B I l 2.5 R/hr l l 10 +10 C170/1001 607 Torus CHRMS A l l .3 R/hr I I 10 10 Torus CHRMS B l l .3 R/hr l l 10 10 FLOW R ATES Pannel C7 SDGT Fl61' 6 '7 ,4 0 0 0 CFM Mein Stock 20000 CFM' Rx Bldg FIB 116 A ISO". ATED CFM TD Vent 140000 CFM' fLET DAT.A Pannel MT1 2.20 ', *1$3' QJJ' Delin Temp 1.7 Dog. F Dh (from) 49 47 51 Dog.

Outelde Temp ,5 9 , Dog. F Speed 6.4 5.9 5.1 MPH Stability Class C

Precip None *

Not Avellebte in Control Room OOS-Out of Service OSH.0ff Scale Hi DS Down Scale This is a Drill Page 5 22 l

. . _ - . . . ~ . . _ . _ . _ - . . _ . _ _ _ _ _ . _ _ _ _ . _ _ _ _ . . _ - -

'd2

, EVALUATED EXERCISE yto No: 13

, PROCESS RADIATION MONITORS Tiur: 02ai

) PANNEL/ID NO. MONITOR Ytand READING Algrm In _ _ R ANG E C910/1705 16 Main Stack to 1 I 14.1 CPS I i10 .10' I C 910/1001 608 Main Stack HI I I 0s R/hr R 10 .

10 C910/1706 32 Rx Bldg Vent to I _] 29.4 CPS R 10.10 C910/1001 609 Rx Bldg Vent Hi I ._ ] DB R/hr l l10.10 # ;

2 C 910/1001 610 Turbine Bldg Vent Hi I I D9 RIhr U 10 .10 1

C910/1705 2 Main Steam Line A I 1 56.2 mR/hr I I 10 0 .100 Main Steam Line B 1.._ _ _ . j _7 2 . 3 mRlhr I I10' .10' Main Steam Line C 1 1 4 B.3 mR/hr I I10' .106 0

Main Steam Line D l l 56.2 mR/hr I i 10 . 10 C910/1705 3 Air Ejector Off Gas I 'l 7 3 .

_ mR/hr I i 10 * .100 C910/1705 4 RBCCW Loop A I i 1845 CPS R 10 .10' HBCCW Loop B I I 1895 ,_ CPS U 10 .10' C910/1705 8 Refuel Floor Vent I l 6 mR/hr I I10 .10 8 C910/1705 9 SBGT Exhaust l l 3 mR/hr I I 10 . 10 C 910/1705 16 Control Rm Air intake l l 0 mMihr I l 10 ' . 10 C910/1705 30 R/W Discharge 1 l 4000 CPS R 10.10' C910/1705 5 Off Gas Post Treatment l l 391 CPS I I 10 - 10 "

C170/1001+ 606 Drywell CHRMS A l l 2.4 R!hr U 10 0 .

10 Drywell CHRMS B -l l 2.3 R/hr I i 10 + 10 C170/1001 607 Torus CHRMe. A I l .2 R/hr I I 10 . 10 Torus CHRM" B I I .2 R/hr I i 10 . 1[

EL.Qy/ HATES Pannel C7 SBGT Fl8126,7 4 000 CFM Main Stack 20000 CFM' Rx Bldg F18#! ISOL ATED CFM TB Vent 140000 CFM' MET D ATA Pannet uT1 220'. *160' . del' Delta Temp .1.7 D*D. F Dir (from) 52 50 54 Do g.

Outside Temp 60 Deg. F Speed 6.6 6.1 5.3 MPH Stability Class C

Precip None .

Not Avallable in Control Room OOS Out of Servlee OSH.Off Scale HI DS Down Scale l

This is a Drill ;

l Page 5 23 b "T' 9%i w 4p- w f"'Neo e*eMswW~r*7 *P*to-rein ew-'sWt-e4-=T19u-FSt 4 -T7-amn c'M y-r8+-2 v--**- '*R- g-- eimN**7:a t e 'Paf T ' %f' 9d +4 '*"T9F' gry- yy.grivvg y-p ygveg u t- y M1-

l 1992 EVALUATED EXERCISE MacNm 14 PROCESS RADIATION MONITORS Time: o3:oo i EANNEL/lD NQ. MOtlLT.OR_nend MEADING _ Atarm in RANGE !

C 910/1705 18 Main Stack Le [_~,] 14 _ OPS I 10.10' C 910/1001 600 Main Stack Hi I I Ds R/hr R 10 -10 "

C910/1105 32 Rx Bid 0 Vent to 1 I 29.2 CPS C 10.10' C 910/1001 009 Rx Bldg Vent HI l

_] _D S R/hr R 10 .10 # .

C 910/1001 010 Turbine Bldg Vent HI DS Hlhr I il 10 .10 I 0

C910/1705 2 Main Steam Line A U 4$.2 _ mR/hr 1 i 10 10'

< in Steam Line B I I $8.1 mR/hr F -1 10 10' 6

Maln Steam Line C l[ l 38.9 m3/hr C 10 0 10 Main Steam Line D [ l 46.2 mR/hr L_j 10 ,,g 6 i C910/1705 3 Air Ejector Off Oss I I 6.9 mR/nr l I 10 10 r C910/1705 4 RBCCW Loop A U 1794 __

CPS I I10 10'

- RUCCW Loop B l 1 1804' CPS I l 10.10 0 C910/1705 8 3efuel Floor Vent I 1 _6 mR/hr R 10 .10 8 ,

C910/1705 9 SBGT Exhaust l l ,3 mR/hr R 10 10" i C910/1705 16 Control Rm Alt intake Il ,,0, mR/hr I _I 10 *.10 C910/1705 30 R/W Discharge l l 4000 CPS C 10 10 '

C910/1705 5 Off Gas Post Treatn.ent i 1 ,3_56 CPS C 10 0 -10 C170/1001 606 Drywell CHRMS A l l 2.3 R/hr l l 10 10 Drywell CHRMS B l 1 2.2 R/hr U 10 10 -

C170/1001 607 Torus CHRMS A 1 l .2 _ R!hr I I10' .10 l

Torus CHRMS- B R .2_ Rlhr U 10 0 .10 ELQ,W,H ATES PannelC7 SBG1 Fl8126f7 4 000 CFM Mstn Stack 20000 CFM' l Mx Bldg Fi8116A ISOL ATED CFM 79 Vont 140000 CFM' f MET DATA Pannel MT1 22E *160' Q13' Delta Temp .1.7 De p. P Dir (from) 55 53 57 Dog.

Outside 7emp g _ Dog. F Speed 6.4 5.9_ ___

5.1 MPH Stability Class ,C Proctp None *

Not Available in control Room ODS Out of Servic6 J?H.O'1 Scals W DS-Down Scale This is a Drill '

Page 5 24

i 1993 EVALUATED EXERCISE . Man No 's PROCESS RADIATIO.N MONITORS .Tiuc. Os ___

! PANNEL/lD NO. M_ONITOR Trena _JEA0 LNG Alarm in RANGE C 910/170 6 18 Maln Stack Lo l l _13.8 CPS R 10.10 C910/1001 608 Main Stack Hl l l DS Hlhr i I 10 .10 "

C 910/170 S*3 2 Rx Bldg Vent Lo l l 29.4 CPE I l 10 + 10

C910/1001 609 Rx Bldg Vent Hi I I DS R/hr I I10 ' 10 C 910/1001 610 Turbine Bldg Vent Hi I ,_l ,D S _

R/hr I I10 .10 ;

C910/1705 2 Main Steam Line A I I e 6.7 mR/hr I l_]10' .100 0 6 Main Steam Line B I l 111.6 mR/hr I i 10 10 Main Steam Line C l 1 .7_4.7 mR/hr I l 10 10 4 Main Steam Line D l I so.7 mR/hr I I 10 10 C910/1705 3 Air Ejector Off Gas l l 6.6 mR/hr I I 10 0 .10 i C910/1705 4 RBCCW Loop A l l 1711 CPS U 10' 10 RBCCW Loop B I I 1721 CPS I l10.10 .

C910/1705 8 Refuel Floor Vent l l _6 mR/hr l I 10 10 '

C910/1705 9 SBOT Exhaust l I 3 mR/hr I I 10 10 ,

, C 910/1705 16 Control Rm Air Intake 1 IO mH/hr l l 10 ' 10 I C910/1705 30 R/W Dicchar0e l l 4000 _ CPS I I 10 -10 C910/1705 8 Off Gas P6M Treatment l I 310 CPS I I10^ .10' .

C170/1001 606 Drywell CHRMS AR 2.2 8/hr C 10 10 Drywell CHRMS 8 I 7 2.1 ,,,, R/hr C 10 0 10 C170/'8 001 607 Torus CHRMS A l ,_j .R ,, R/hr C 10 10 Torus CHRMS B f7 1

_ R/hr I l 10 10

FLOW M PannelC7 SSGT Fl81267 - 400c CFM Main Stack 20000 CFM' Rx Bldg Fl8116A l sot. ATt!D _

CFM TB Vent 140000 CFM' MET D.ATA Pannel MT1 220' '160' Q.31' ,

L Delta Temp 4.8 D*0. F Dir (from) 56 54 58 Dag.

Outside Temp 60 Dag. F Speed 6.1 5.5 4.8 WPH l

i. $1s5181) Class B l Precip None

i

Not Available in C... trol Room OOS-Out of Service CSH.Off Serie HI DS-Down Sc6te This is a Drill Page 5 25 '

L

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

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

1992 EVALUATED EXERCISE .MIA.yo: 16 PROCESS RADIATION MONITORS Tiuc 0 00 PANNEL/lD NO. .jdQNJTOR Trend READJHG A!stm in RANGE 0

C 910/1 T05 18 Main Stack Lo l l 17 CPS I 10 10 C 910/1001 608 Main Stack HI 1 l DS R/hr I i10^ .10 C910/1705 32 Ru Bldg Vent to l l 138.6 CPS I l 10 10 C 910/1001 609 Rx Dldo Vetil Hi I I D$ R/hr I l10.10 #

C 910/1001 610 Turbine BidD Vent HI l 1 ,D S R/hr I l10 .10 6

C910/1705 2 Main Steam Line A l l 176.3 mRlhr I l 10 10 Maln Steam Line B I 1 ,22,6.9 mR/nr I l 10 10" Main Steam Line C 1 l 151.0 mRlhr l I 10 10 0 6 Main Steam Line D l l 176.3 mRlhr I 1 10 10 C010/1705 3 Air Ejector Off Gas I_ j 5.9 mR/hr U 10 10' C910/1705 4 RBCCW Loop A I l 1702 CPS I l10^ .10' 6

RDCCW Loop B l 'l 1712 CPS U 10 *I .10 3

C910/1705 8 Refuel Flocr Vent l l 6 mR/hr R 10 .10 C 910/1701 9 SBGT Exhaust 1 13 _ mR/hr l l 10 10 C 910/1705 16 Control Rm Air intake l l 0 mR/hr l l 10 10 C910/1705 30 R/W Discharge [ ] 4000 CPS I J 10 ' .10 '

C910/1705 5 Off Gas Post Treatment i l 516 CPS I I10 10 0 C170/1001 606 Drywell CHRMS A l l 2.2 R/hr 1 i 10 10 Drywell CHRMS B l l ,2 .1 R!hr l l 10 10 0 7 C 170/1001 607 Torus CHRMS A l l .2 R/hr l I 10 ,1 g Torus CHRMS B l l .1 R/hr l l 10 10 FLOW RATES Pannel C7 SBGT Tl8126r7 4000 CFM Main Stack 20000 _

CFM*

Ra Bldg Fl8116 A ISOt. AT E D CFM TB Vent 140000 CFM' MET DATA PannM MT1 220'. 1160' 033' Delta Yemp 1.8 Dog. F Dir (from) 57 55 59 Dog.

Outalde Tomo 61 Dog. F Spssd 7 6.5 5.7 MPH Stability Claes B

Precip Hone

Not Available in Control Room OCS Out of Servbe OSH Off Scala Hi DS-Down Scale This is a Drill Page 5 26

1998 EVALUATED EXERCISE .Maa No; 17 PROCESS RADIATION MONITORS _Tiur 03 30 PANNEL/lD NO. MONITOR Trand READWG Atarm in RANGE 0910/1705 18 Maln Stack Lo l l 20.6 CPS R 10 ' 10"

C 910/1001 608 Main Stack Hi I I DS R/hr l l10 10' 0

C910/1705 32 Rx Bldg Vent Lo l I 42.2 CPS l l 10 10 C910/1001 609 Rx Bldg Vent HI R 05 R/hr I I 10 ' .10 i10 ' 10 #

C910/1001 610 Turbine Bldg Vent Hi I l -DS R/hr I 6

C910/1705 2 Main Gleam Line A 1 l 103.1 mR/hr l l ) 10 0

Maln Steam Line D 1 1 132.6 mR/hr l l 10 10 Main Steam Line C 1 l 88.7 mR/hr l I 10 10 0

Main Steam Line D I l 103.1 mR/hr l l 10 10 U

C910/1705 3 Air Ejector Off Gas l l 5.3 rnR/hr I 1 10 10' C910/1705 4 RBCCW Loop A l l 1635 CPS I l10 '.10 6 RBCCW Loop B l l 164$ CPS I l 10 ' .10 "

]l 6 C910/1705 8 Refuel Floor Vent l mR/hr l l 10 ' .10 8 C910/1705 9 SBGT Exhaust LJ 3 mR/hr R 10 0 10 C 910/1705 16 Control Rm Air intake l l 0 mR/hr I i 10 *# .10 2 I '.10" C910/1705 30 R/W Dlacharge l l 4000 CPS l10

~

C910/1705 5 Off Gas Post Tiestment 1 -1 200 CPS l l10 ' .10 C170/1001 606 Drywell CHRMS A I l 2 R/hr I l 10 10 U 7 Drywell CHRMS B I i 1.9 R/hr U 10 10 C170/1001 607 Torus CHRMS A - l l .1 . _ R/hr R 10 0 .10 Torus CHRMS B l 1 .1 R/hr l l 10 10 FLOW R ATES Pannel C7 SBOT Fl8126/7 4000 CFM Main Stack 20000 CFM' Rx Bldg F181164 ISOLATED CFM TB Vent 140000 CFM'

MET DATA Pannel MT1 223' *160'. 013' Delta Temp .1.8 Dog. F - (frorn) 59 56 60 Dag.

Outside Temp 61 Dog. F # peed 6 $.5 4.7 MPH Ctability Class P

Procip - None *

Not Available in Control floom OOS Out of Service OSH Off Scale Hi DS Down Scale This is a Drill Page 5 27 l

. . s - , - - , _ . . - ~ . .. . --.-,. _ _ - ~._ , .- ,. ...

m --,.,,m. , ,-._m,-,,, .-...--m --__a

- - - .. . - ~ . - _ ~ - . . . . . - . . -.- - -. . . - . . . - - . . . . . - -

1992 EVALUATED EXERCISE Msa No 18 PROCESS RADIATION MONITORS Tiue 03:a5 PANNEL!jD NO. MQNITOR Trend REAQ1NG Alarm in RANGE C910/1705 18 Main Stack Lo l 1 _18.1 CPS l l10 10" !

0910/1001 608 Main Stack Hi I -1 DS ,_ _ R/hr l l10 10 #

CS10/1705 32 Rx Bldg Vent Lo I I sc.6 CPS R 10 ^ -10 C 910/1001 609 Rx Bldg Vent HI l l ,D S R!hr { l 10 -10 C 910/1001 610 4 4 Turbine Bldg Vent HI L I L's R/hr i 1 10 10 C910/1705 2 Malr1 Steam Linc A l l 80.7 mR/hr I i10" 106 0

Main Steam Line B l l 103.0 mR!hr C 10 -10 Main Steam Line C l l 69.5 mR/hr I l 10 10 6

Main Steam Line D 1. l 80.7 mR/hr l l 10 10 0

C910/1705 3 - Air Ejector Off Gas l l 5.8 mR/hr l l 10 -10 C910'1705 4 RBCCW Loop A l l 1568 CPS l l10 10 RBCCW Loop B l 1 1578 CPS I l10 10 6 C910/1705 8 Refuel Floor Vant l l 6 mR!hr R 10 10 3 C 910'/170 5 9 SBGT Exhaust l l 3 mRlbr I I 10 10" 2

C910/1705 16 Control Rm Air intake R 0 mR/hr I l 10 ' 10 C910/1705 30 R/W Discharge l I 4000 CPS I I10 10 0 C910/1705 5 Of! Gas Post Treatment l l 200 CPS I l 10 -10 C170/1001 606 Dr/well CHRMS A l l 1.9 R/hr j i 10 10 0

Drywell CHRMS B l~~~"l 1.8 R/hr R 10 10 C ? 70/1001 607 Torus CHRMS A L l .1 R/hr I I 10 10 '

Terus CHRMS B l l .1 R/hr I I 10 -10 ELOW R ATES PannelC/

SBGT Fl812617 4000 CFM Main Stack 20000 CFM*

Rx Bldg F18116A ,lSOt. ATED CFM TS Vent 140000 CFM' MET D ATA Pannel MTs 220' '160' 033' Delta Temp 1.8 Deg, F Dir (fre e ) 60 58 62 Da g.

Outside Temp ,6 2 Dog. F Spsed 5.8 5.3 4.5 MPH .

Stability Class B, l Precip tiene l

Not Avadabf.s in Control Rocm OOS-Out of Service OSH.Off Scale HI OS-Down mi le This is a Drill Page 5-28

1 1992 EVALUATED EXERCISE .Mtq No: 19 PROCESS RADIATION MONITORS .nME : 04:00 PANNEL/ID NO. MQUITOR 7 rend REAJJN.G Aterm in RANGE C 910/1705 18 Main Stack to I l 11.7 CPS R 10 10 6

C 910/1001 608 Main Stack Hi l ] DS _ RIhr l 1 10 10

^

C910/1705 32 Rx Bldg Vint to I l 29.3 CPS I I 1r 10' C 910/1001 609 Rx Bldg Vent HI l l DS .4thr I ] g S' C 910/t 001 610 Turbine Bldg Vent H! l l D_S__ R/hr i lC 10 C910/1705 2 Main Steam Line A I 1 17.6 mRlhr M 10 10 Main Steam Line B l 1 22.6 mRlhr I I 10 10

' 6 Main Steam Line C l l 15.1 _

mRlbr I- l 10 10 Main Ste:,m Line D l l 17.6 mRlhr I l 10 10 C910/1705 3 Air Elector Off Gas I l 5.8 mR/hr I i 10 10 C910/1705 4 RBCCW Loop A l _l 1509 CPS I I10^ 10 RBCCW Loop B I i 1519 CPS R 10 ^ -10 C910/1705 8 Refuel Floor Vent I 16 mR/hr Ll 10 -10 C910/1705 9 SBGT Exhaust I l ,3_ mRlhr l_ l 10 10 CS '0/170516 Control Rm Alt intake 1 10 ,

mR/hr I I 10' 10

6 C910/1705 30 R/W Discharge l l ,4,000 CPS I I 10 10 CD10/1705 5 Off Gas Post Treatment [ 7 200 CPS I I 10 10 0

C170/1001 606 Drywell CHRMS A 1 1 1.8 R/hr I I 10 10 Drywell CHRMS B I i 1.7 R/hr i j 10 10 C 170/1001 -607 Torus CHRMS A I I .1 ft/hr l l 10 10 Torus CHRMS B i 1 1 R/hr i ! 10 -10 FLOW R ATES PannelC7 SBGT Fl8126/7 4000 CFM Maln Stack 20000 CFM*

Rx Bidg F18116A ISCLATED CFM TB Vent 140000 CFM' '

MET D ATA Pannel MT1 22.0' *160' Dlj3' Delta Temp 1.7 ,

Seg. F Dir (frem) 62 60 64 Dog.

Outside Temp 6 2 Dog. F Speed 5.6 5.1 4.3 MPH Stability Class C

Precip None ,'

Net Available in Control Room OOS-Out of Service OSH.Off Scale HI DS-Down Scale This is a Drill Page 5-29

1992 - EV ALU ATED EXERCISE Ms0 No:1 AREA RADIATION MONITORS TiuE: 00:00 _

~

PANNEL/ID NO. MONITOR Trend READING Alarm in RANGE C910/1705 60 Charcoal Bed Vault 61J mR/hr 10' 10 ,

C911/ ARM 1 Cond. Pump Stalt 2.0 mR/hr 10 10 0 4 C911/ ARM 2 Feedwater Heaters 18.4 mR/hr 10 -10 2 2 C911/ ARM 3 Main Control Room __

0.0 mR/hr 10 10 o 4 C911/ ARM 4 Turbine Front ~a n d 10.1 mR/hr 10 10

-1 3 C911/ ARM 5 Radwaste Corridor 2.6 mR/hr 10 10 0 4 C911/ ARM 6 Redwaste Sump Area 89.9 mR/hr 10 10 '

0 4 C911/ ARM 7 Chem. Waste Tank 5.4 mR/hr 10 10 2 2 C911/ ARM 8 Rx Outside Tip Room 0.1 mR/hr 10 10 C911/AR M 9 RadWaste Ship, Lock _

0.7 mR/hr to 10 C911/AR M 10 RB Acess Area (S.E.) 4.0 mR/hr 10 10 C911/ ARM --11 New Fuel Vault 0.5 mR/hr 10 ' 10 C911/ ARM -12 New Fuel Racks 0.2 mR/hr 10 10 1 3 C911/ ARM 13 Shield Plug Area 1.0 mR/hr 10- 10 C911/ ARM 14 Spent Fuel Pool Area 10.0 mR/hr 10 10

.AL ARM SET POINTS 1705 60 = 200 mR!hr ARM 7 = 300 mR/hr ARM 1 = 55 mR/hr ARM -0 = 5 mR!hr ARM 2 = 600 mR/hr ARM -9 = 50 mR/hr ARM 3 = 1 mR/hr ARM 10 = 60 mR/hr ARM 4 = 450 rnR/hr ARM -11 = 6 mR/hr ARM 5 = 15 mR/hr ARM -12 = 40 mR/hr

ARM 6 = 6000 mRihr ARM 13 = 40 mRihr ARM 14 = 30 mR/hr DOS Out of Service OSH Off Scale Hi DS-Down Scale I

This is a Drill i

L Page 5-30

._. .. __m . ._ _ _ .

1998 EVALUATED EXERCISE Mst No:2 AREA RADIATION MONITORS Time: 00:13 PANNEL/ID NO. Mor: TOR Trend READING Alarm in RANGE C910/1705 60 Charcoal Bed Vault 60.1 mR/hr 10 10

. C911/ ARM 1 Cond. Pump Stalt 2.0 mR/hr 10' 10 0 4 C911/ ARM 2 Feedwater Heaters 18.4 mR/hr 10 10 C911/ ARM 3 Main Control Room 0.0 mR/hr 10 10 C911/AR M 4 Turbine Front Stand 10.1 mR/hr 10 10 C911/ ARM 5 Radwaste Corridor 2.6 mR/hr 10' 10 ,

o 4 C911/AR M -6 Radwaste Sump Area 89.9 mR/hr 10 10 0 4 C911/ ARM 7 Chem. Waste Tank l 5.4 mR/hr 10 10 2 2 C911/AR M -8 Rx Outside Tip Room .1 mR/hr 10 -10 C911/ ARM 3 RadWaste Ship. Lock 0.7 mR/hr 10' 10 C911/ ARM 10 RB Acess Area (S.E.) 4.0 mR/hr 10 10 C911/ ARM 11 New Fuel Vault 0.5 mR/hr 10 -10 C311/ ARM 12 1 3 New Fuel Racks _

0.2 mR/hr 10 10 1 3 C911/ ARM 13 Shield Plug Area 1.0 mR/hr 10 10 C911/AR M 14 Spent Fuel Pool Area 10.0 mR/hr 10 10 ALARM SET POINTS 1705 60: 200 mR/hr ARM 7 = 300 mn/hr ARM 1 = 55 mR/hr. ARM 8 m 5 mR/hr ARM '2 = 600 mR/hr ARM 9 = 50 mR/hr ARM -3 = 1 mR/hr ARM -10 = 60 mR/hr ARM -4 z. 450 mR/hr ARM 11 = 6 mR!hr ARM 5 = 15 mR/hr ARM 12 = 40 mR/hr ARM -6 = 6000 mR!hr ARM -13 = 40 n1R/hr ARM -14 = 30 mR/hr OOS-Out of Service OSH Off Scale Hi DS-Down Scale This is a Drill Page 5 31

~ . ~ .~.-~ -. - . _ . . . . - .

- . - - . - . . ~ . ... . _ . . - - -

l 1993 EVALUATED EXERCISE Mso No:3 -l AREA RADIATION MONITORS tim 4 n0:30 i PANNEL/lD NO. MONITOR Trend READING Alarm in rat 10,E

-+- 1 3 C910/1705 60 Charcoal Bed Vault 58.5 mR/hr 10 10 C911/ ARM 1 Cond. Pump Stalt 2.0 mR/hr 10 10

' C911/ ARM 2 Feedwater Heaters 18.3 mR/hr 10 10 2 It C911/ ARM 3 Main Control Room _,

0.0 mR/hr 10 10

--""~

o 4 C911/ ARM 4 Turbint Front Safid 10.1 mR/hr _

10 10 C911/AR M +5 Radwaste Corridor 2.6 mR/hr 10' 10 0 4 C911/ ARM 6 Radweste Sump Area 89.9 mR/hr 10 10

- ~1 0 4 .

C911/ ARM 7 Chem. Waste Tank S.4 mRlhr , 10 10 2 2.

C911/ ARM 8 Rx Outside Tip Room .1 mR/hr 10 10 C911/ ARM 9 RadWaste Sh!p. l.ock O.7 mRIhr 10 -10 1 3 C911/ ARM 10 RB Acess Area (S.E.) 4.0 mR/hr 10 10 C911/ ARM 11 New Fuel Vault 0.5 mR/hr l ~

10 10 1 3 C911/AFiM - 12 New Fuel Racks 0.2 mRIhr 10 10 C911/ ARM 13 Shield Plug Area 1.0 mR/hr 10 10 C911/ ARM 14 Spent Fuel Pool Area 10.0 mR/hr 10' -10 ALARM SET POINTS -

1705 60 = 200 mR/hr ARM 7 = 300 mR/hr ARM- 1 = 55 mR/hr ARM 8 = 5 mR/hr ARM 2 = - 600 mR/hr ARM -9 = 50 mR!hr ARM 3 = 1 mR/hr ARM -10 = 60 mRlbr ARM -4 = 450 mR/hr ARM 11 = 6 mR/hr ARM 5 = 15 mR!hr ARM 12 = 40 mR/hr ARM 6 = 6000 mR/hr ARM 13 = 40 mR/hr ARM -14 = 30 mR/hr 1

OOS-Out of Service OSH Off Scale Hi DS-Down Scale n

This is a Drill i-Page 5 32

. . _ . . ~ _ . _ .. __ _ .-. .

1993 EVALUATED EXERCISE Msa .No: 4 AREA RADIATION MONITORS Time: 00:4 s Eatit(EL/ID NO. MONITOR Trend READING Alarm in RANGE C910/1705 60 Charcoal Bed Vault 56.8 mR/hr [ 10 10 1 3 C911/ ARM 1 Cond. Pump Stalt _

2.0 mR/hr 10 10 C911/ ARM 2 Feedwater Heaters 16.3 mR/ht 10 10 C911/ ARM -3 Main Control Room 0.0 mRIhr 10 10 C911/ ARM 4 Turbine Front Stand 9.2 mR/hr 10 10 C911/ ARM 5 Radwaste Corridor _

2.6 mRlhr 10' -10 0 4 C911/ ARM 6 Radwas.te Sump Area l 89.9 mR/hr 10 10 C911/ ARM 7 - Chem, Waste Tank 5.4 raR/hr 10 10 C911/ ARM 8 Rx Outside Tip Hoom .1 mR/hr- 10' -10 C911/ ARM 9 RadWaste Ship, Lock 0.7 mR/hr 10 10 C911/ ARM -10 RB Acess Area (S.E.) 4.0 mR/hr 10' 10 1 3 C911/ ARM 11 New Fuel Vault 0.5 mRlhr 10 10 C911/ ARM 12 New Fuel Racks 0.2 mR/hr 10 -10 1 3 C911/ ARM- 13 Shield Plug Area 1.0 mR/hr 10 10 C911/ ARM 14 Spent Fuel Pool Area 10.0 mRlhr 10 -10 AL ARM SET POINTS 1706 60 200 mR/hr - ARM -7 = 300 mR/hr ARM 1 = 55 mR/hr ARM 8 = 5 mR/hr ARM 2 = 600 mR!hr ARM -9 = 50 mR/hr ARM -3 1 mR/ht- ARM 10 = 60 mR/hr

ARM- 4 = 450 mR/hr ARM 11 = 6 'mR/hr ARM 5 = 15 mR/hr ARM 12 = 40 mR/hr ARM -6 = 6000 mR/hr ARM 13 = 40 mR/hr ARM 14 = 30 mR/hr OOS-Out et Service OSH.Off Scale Hi DS-Down Scale This is a Drill Page 5 33

.~ .__ . _ . _ . . _ . _ . _ . _ _ _ _ _ . . _ . _ _ . _ . . _ .. _ _ _ . . __

o 1993 NVALU ATED EXERCISE - E}p No: 5 AREA RADIATION MONITORS TiuE: 01:00 _

PANNEL/lD NO. MONITOR Trend READING Atarm in RANGE

>: C910/1705 60 Charcoal Bed Vault 53.4 mR/hr 10 10 C911/ ARM 1 Cond. Pump Statt 1.9 mR/hr 10' 10 0 4 C911/ ARM 2 Feedwater Heaters 14.0 mR/hr 10 10 C911/ ARM 3 Main Control Room 0.0, mR/hr 10' 10 0 4 C911/ ARM 4 Turbine Front Stand 7.7 mR/hr 10 -10 C911/ ARM 5 Radweste Corridor 2.6 mR/hr 10 10 0 4 C911/ ARM 6 Radweste Sump Area 89.9 mR/hr 10 10 0 4 C911/ ARM 7 Chem. Waste Tank 5.4 mR/hr 10 10 C911/ ARM 8 Rx Outside Tip Room .1 mR/hr 10' 10 2 2 C911/AR M 9 RadWaste Ship. Lock 0.7 mRlhr 10 10 C911/ ARM -10 RB Acess Area (S.E.)- 4.0 mR/hr 10' 10 C911/ ARM 11 New Fuel Vault 0.5 mR/hr 10' 10 C911/ ARM -12 New Fuel Racks 0.2 mR/hr 10 10 1 3 C911/ ARM -13 Shield Plug Area 1.0 mR/hr 10 10 t 3 C911/ ARM -14 Spent Fuel Pool Area 10.0 mR/hr 10 10 Al. ARM SET POINTS 1705 60 = 200 mR/hr ARM -7 = 300 mR/hr ARM 1 = 55 mR/hr -ARM 8 = 5 mR/hr ARM -2 = 600 mRihr ARM 9 = 50 mR!hr ARM -3 = 1 mR/hr ARM -10 '= 60 mR/hr -

ARM 4 = 450 mR/hr ARM 11 = 6 mRlbr -

ARM 5 = 15 mR!hr ARM -12 = 40 mR/hr ARM 6 = 6000 mR/hr ARM 13 = 40 mR/hr ARM -14 = 30 mR/hr OOS-Out of Service OSH-Off Scale Hi DS-Down Scala This is a Drill Page 5 34

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

i 1993 EVALUATED EXERCISE Msa No:6 AREA RADIATION MONITORS Tiue: 01 :15 PANNEL/ID NO. MONITOR Trend READING Alarm in RANGE C910/1705 60 Charcoal Bed Vault 48 6 mR/hr _

10 10 C91t/ ARM 1 Cond. Pump Stalt 1.9 mR/hr 10 10 0 4 C911/ ARM 2 Feedwater Heaters 13.5 mR/hr 10 10 C911/ ARM 3 Main Control Room 0.0 mR/hr 10 10 0- 4 C911/ ARM -4 Turbine Front Stand 7.4 mR/hr 10 10 C911/AR M 5 Radwaste Corridor 2.6 mR/hr 10 10 0 4 C911/ ARM 6 Radweste Sump Area 89.9 mR/hr 10 10 0 4 C911/ ARM 7 Chem. Waste Tank ,

5.4 mR/hr 10 10 C911/ ARM 8 Rx Outside Tip Room .1 mR/hr 10 -10 C911/ ARM 9 RadWaste Shlp. Lock 0.7 mR/hr 10 10 C911/AR M -10 RB Acess Area (S.E.) 4.0 mR!hr 10' 10 1

C911. ARM 11 New Fuel Vault 0.5 mR/hr 10 10 C911/ ARM 12 New Fuel Racks 0.2 mR/hr 10' 10 1 3 CD11/ ARM 13 Shield Plug Area 1.0 mR/hr 10 10 .

C911/ ARM 14 Spent Fuel Pool Area 10.0 mR/hr 10' 10 ALARM SET POINTS 1705 60 = 200 mR/hr ARM 7 = J00 mR/hr ARM 1 = 55 mR/hr ARM 8 = G mR/hr ARM 2 = 600 mR/hr ARM -9 = 50 mR/hr

- ARM 3 = 1 mR/hr ARM 10 = 60 mR/hr ARM -4 = 450 mR/hr ARM 11 = 6 mR!hr ARM 5 = 15 mR/hr ARM 12 = 40 mR/hr ARM 6 = 6000 mR/hr ARM -13 = 40 mR/hr ARM 14 = 30 mR/hr OOS-Out of Service OSH.Off Sc61e Hi DS-Down Scale ,

This is a Drill Page 5-35

1992 EVALUATED EXERCISE Msa No:7 AREA RADIATION MONITORS Tiue: 01 :2 s PANNEL/ID NO. MONITOR Trend READING Alarm in RANGE C910/1705 60 Charcoal Bed Vault 44.8 mR/hr 10 10 C911/ ARM 1 Cond, Pump Stair 1.9 mR/hr 10 10 0 4 C911/ ARM 2 Feedwater_ H6aters 6.4 mRIhr 10 10 C911/ ARM 3 Main Control Room 0.0 mR/hr 10 -10 ,

0 4 C911/ ARM 4 Turbine Front Stand 3.5 mR/hr 10 10 C911/ ARM 5 Radwaste Corridor 2.6 mR/hr 10 10 o 4 C911/AR M 6 Radwaste Sump Area 89.9 mR/hr 10- 10 o 4 C911/ ARM 7 Chem Waste Tank 5.4 mR/hr 10 10 2 2 C911/ ARM 8 Rx Outside Tip Room .1 mR/hr 10 -10 C911/ ARM 9 RadWaste Ship. Lock O.7 mR/hr 10 10 C911/ ARM 10 RB Acess Area (S.E.) 4.0 mR/hr 10' -10 C911/ ARM 11 New Fuel Vault 0.5 mR/hr 10 10 C911/ ARM 12 New Fuel Racks 0.2 mR/hr 10 10 l -1 3 C91'./AR M 13 Shield Plug Area 1.0 mR/hr 10 10 C011/ ARM 14 Spent Fuel Pool Area 10.0 mR/hr 10 10 ALARM SET POINTS l 1705 60 = 200 mR/hr ARM 7 = 300 mR/hr ARM 1 = 55 mR/hr ARM 0 m 5 mR/hr ARM -2 = 600 mR/hr ARM 9 = 50 mR/hr ARM 3 = 1 mR/hr ARM 10 m 60 mR/hr ARM 4 = 450 mR/hr ARM 11 = 6 mR/hr ARM -5 = 15 mR!hr ARM 12 = 40 mR/hr ARM 6 = 6000 mR/hr ARM -13 = 40 mRlbr ARM 14 = 30 mR/hr OOS-Out of Service OSH.Off Scale Hi DS-Down Scale This is a Drill Page 5 36

l

1998 EVALUATED EXERCISE - Msa No:8 ,

I AREA RADIATION MONITORS Tiue: 01:50 PANNEL/ID NO. MONITOR Trend READING Alarm in RANGE C910/1705 60 Charcoal Bed Vault 41.0 mR/hr 10' 10 C911/ ARM 1 Cond. Pump Stalt 1.9 mR/hr 10 10 0 4 C911/ ARM 2 Feedwater Heaters 11.9 mRlhr 10 10 C911/ ARM 3 Main Control Room 0.0 mR/hr 10' 10 C911/ ARM 4 Turbine Front Stand 6.5 mR/hr 10 10 C911/AR M 5 Radwaste Corridor 2.6 mR/hr 10 10 C911/ ARM 6 Radwaste Sump Area - 89.9 mR/hr 10 10 C911/AR M 7 Chem. Waste Tank 5.4 mR/hr 10 10 2 2 C911/ ARM 8 Rx Outside Tip Room .1 mR/hr 10 10 C911/AR M 9 RadWaste Ship. Lock 0.7 mRlhr 10' 10 C911/ ARM -10 RB Acess Area (S.E.) 4.0 mR/hr 10 -10 C911/ ARM 11 New Fuel Vault 0.5 mR/hr 10 10 C911/ ARM 12 New Fuel Racks _

0.2 mRlbr 10 10 C911/AR M 13 Shield Plug Area _

1.0, mR/hr 10 -10 1 3 C911/ ARM 14 Spent Fuel Pool Area 10.0 mR/hr 10 10 ALARM SET POINTS 1705 60 = 200 mRlhr ARM 7 = 300 mR/hr ARM 1 = 55 mR!hr ARM >B = 5 mR/hr .

ARM 2 = 600 mR/hr ARM 9 = 50 mR/hr ARM -3 = 1 mR/hr ARM 10 = 60 mR/hr ARM 4 = 450 mR/hr ARM 11 = 6 mR/hr ARM 5 = 15 mR!hr ARM 12 = 40 mR!hr ARM -6 = 6000 mR/hr ARM -13 = 40 mR/hr AitM 14 = 30 mR/hr OOS-Out of Service OSH Off Scale Hi DS Down Scale This is a Drill Page 5-37

1993 EVALUATED EXERCISE Msa No:9 AREA RADIATION MONITORS Tius: 01:4 s PANNEL/ID NO. MONITOR Trend HEADING Alarm in RANGE C910/1705 60 Charcoal Bed Vault _

28.0 mR/hr 10 10 C911/ ARM 1 Cond. Pump Stair 1.8 mR/hr 10 10 C911/ ARM 2 Feedwater Healers 4.4 mR/hr 10 10 C911/ ARM 3 Main Control Room 0.0 mR/hr 10' 10 C911/ ARM 4 Turbine Front Stand 2.4 mR/hr 10 10 C911/ ARM 5 Radwaste Corridor 2.6 mR/hr 10 10 C911/ ARM 6 Radwaste Sump Area 89.9 mR/hr 10 10 C911/ ARM 7 Chem. Waste Tank 5.4 mR/hr 10 10 C911/ ARM 8 Rx Outside Tip Room .1 mRlhr 10' 10 C911/ ARM 9 RadWaste Ship. Lock 0.7 mR/hr 10 10 C911/ ARM -10 RB Acess Area (5.E.) 4.0 mR/hr 10 10 C911/ ARM 11 New Fuel Vault 0.5 mR/hr 10 10 l C911/ ARM 12 New Fuel Racks 0.2 mR/hr 10 10 C911/ ARM " 13 Shield Plug Area 1.0 mR/hr 10 10 C911/ ARM 14 Spent Fuel Pool Area 10.0 mR/hr 10 -10 ALARM SET POINTS 1705 60 = 200 mR/hr ARM -7 = 300 mR/hr ARM -1 = 55 mR/hr ARM -8 = 5 mR/hr ARM 2 = 600 mR/hr ARM 9 = 50 mR/hr ARM 3 a 1 mR/hr ARM 10 = 60 mR/hr l ARM 4 = - 450 mR!hr ARM -11 = 6 mR/hr l ARM -5 = 15 mR!hr ARM 12 = 40 mR/hr ARM 6 = 6000 mR!hr ARM 13 = 40 mR/hr ARM 14 = 30 mR/hr 00S-Out of Service OSH.Off Scalo Hi DS-Down Scale This is a Drill Page 5-38 l

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

1993 EVALUATED EXERCISE Msa No:10 AREA RADIATION MONITORS Tiue: 0 2:00 PANNEL/lD NO. MONITOR Trend READING Alarm in RANGE C910/1705 60 Charcoal Bed Vault 17.7 mR/hr 10 ' 10 ' !

C911/ ARM 1 Cend. Pump Stalt 1.8 mR/hr 10 - -10 0 4 C911/ ARM 2 Feedwater Heaters 4.4 mR/hr 10 10 C911/ ARM 3 Main Control Room 0.0 mR/hr 10 10 C911/ ARM 4 0 4 Turbine Front Stand 2.4 mR/hr 10 10 C911/ ARM 5 Radwaste Corridor 2.6 mR/hr 10 10

~

C911/ ARM 6 0 4 Radwaste Sump Area 89.9 mR/hr 10 10 o 4 C911/AR M 7 Chem. Waste Tank 5.4 mR/hr 10 10 2 2 C911/ ARM -8 Rx Outside Tip Room .1 mR/hr 10 10 C911/ ARM -9 RadWaste Ship. Lock 0.7 mR/hr 10 ' 10 C911/ ARM 10 RB Acess Area (S.E.) 4.0 mR/hr 10 ' -10 C911/ ARM -11 New Fuel Vault 0.5 mR/hr 10 10 C911/ ARM 12 New Fuel Racks 0.2 mR/hr 10 10 C911/ ARM -13 Shleid Plug Area 1.0 mR/hr 10 10 C911/ ARM 14 Spent Fuel Pool Area 10.0 mR/hr 10' 10 AL ARM SET POINTS 1705 60 = 200 mR/hr ARM 7 = 300 mR/hr ARM 1 = 55 mR/hr ARM 8 = 5 mR/hr ARM' 2 = 600 mR/hr ARM 9 = 50 mR!hr A R M -- 3 = 1 m R/h r ARM 10 = 60 mR/hr ARM -4 = 450 mR/hr ARM 11 = 6 mR/hr

- ARM 5 = 15 mR!hr ARM 12 = 40 mR/hr ARM -6 = 6000 mR/hr ARM -13 = 40 mR/hr ARM 14 = 30 mR/hr OOS-Out of Service OSH-Off Scale HI DS Down Scale i

This is a Drill l

Page 5 39

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

1993 EVALUATED EXERCISE Msa No:11 i AREA RADIATION MONITORS Tiue: 02:15-PANNEL/ID NO. MONITOR Trend READING Alarm in RANGE C910/1705 60 Charcoal Bed Vault 9.3 mR/hr 10' 10 C911/ ARM 1 Cond Pump Statt 1.8 mR/hr 10 10 o 4 C911/AR M 2 Feedwater Heaters 3.6 mR!hr 10 10 C911/ ARM 3 Main Control Room 0.0 mR/hr 10 10 C911/ ARM 4 Turbine Front Stand 2.0 mR/hr 10 10 C911/ ARM 5 Radwaste Cne*ldor 2.6 mR/hr 10 10 C911/ ARM -6 Radwaste Sump Area 89.9 mR/hr 10 10 C911/ ARM 7' Chem. Waste Tank 5.4 mR/hr 10 10 C911/ ARM 8 Rx Ouuide Tip Room .1 mR/hr 10' 10 C911/ ARM 9 RadWaste Shlp. Lock 0.7 mR/hr 10 10 C911/ ARM 10 R8 Acess Area (S.E.) 4.0 mR/hr 10 -10 C911/ ARM 11 New Fuel Vault 0.5 mR/hr 10 10 C911/AR M 12 New Fuel Racks 0.2 mR/hr 10 10 C911/ ARM -13 Shield Plug Area 1.0 mR/hr 10 10 C911/ ARM 14 Spent Fuel Pool Area 10.0 mR/hr 10 10 AL ARM SET POINTS

! .1705 60 200 mR/hr ARM 7 = 300 mR/hr l ARM 1 = 55 mR/hr ARM 8 = 5 mR/hr l: ARM 2 = 600 mR/hr ARM 9 = 50 mR/hr l ARM 3 = 1 mR/hr ARM 10 = 60 mR/hr l ARM 4 = 450 mR/hr ARM 11 = 6 mR/hr j ARM -5 = 15 mR/hr ARM -12 = 40 mR/hr l ARM 6 = 6000 mR/hr ARM 13 = 40 mR/hr ARM 14 = 30 mR/hr OOS-Out of Service OSH Off Scale Hi DS Down Scale This is a Drill Page 5-40 t

1992 EVALUATED EXERCISE Msa No:12

- AREA RADIATION MONITORS Tiue: 02:30 PANNELilD NO. MONITOR Trend READING Alarm in RANGE C910/1705 60 Charcoal Bed Vault 6.2 mR/hr 10 10 C911/ ARM 1 Cond. Pump Stalt 1,8 mR/hr 10 10 0 4 C911/ ARM 2 Feedwater Heaters 3.6 mR/hr 10 10 C911/ ARM 3 Main Control Room 0.0 mR/hr 10' -10 C911/ ARM 4 Turbine Fro;it Stand 2.0 mR/hr 10 10 C911/ AR M 5 Radweste Corridor 2.6 mR/hr 10 10 C911/ ARM 6 Radwr.sste Sump _ Area 89.9 mR/hr 10 10 0 4 C911/ ARM 7 Chem. Waste Tank 5.4 mR/hr 10 -10 C911/ ARM 8 Rx Outside Tip Room .1 mR/hr 10 10 C911/ ARM 9 RadWaste Ship, Lock ,

0.7 mR/hr 10 -10 C911/ ARM 10 RB Acess Area (S.E.) 4.0 mR/hr 10 10 C911/ ARM 11 New Fuel Vault 0.5 mR/hr 10' 10 CP' 1/AR M 12 New Fuel Racks 0.2 mR/hr 10 10 C911/ ARM -13 Shield Plug Area 1.0 mRihr 10 -10 C911/ ARM 14 Spent Fuel Pool Area 10.0 mR/hr 10 10 AL ARM SET POINTS l

1705 60 = 200 mR/hr ARM 7 = 300 mR/hr ARM 1 = 55 mR/hr ARM 8 = 5 mR/hr

- ARM 2 = 600 mRlhr ARM 9 = 50 mR/hr ARM 3 = 1 mR/hr ARM 10 m 60 mR/hr ARM 4 = 450 mR/hr ARM 11 = 6 mR/hr ARM 5 = 15 mR/hr ARM 12 = 40 mR/hr

- ARM 6 = 6000 mR/hr ARM -13 = 40 mR!hr ARM -14 = 30 mR/hr l

! OOS-Out of Service OSH-Off Scale HI DS.Down Scale This is a Drill Page 5-41

1993 EVALUATED EXERCISE Msa No:13 AREA RADIATION MONITORS we: 0n45 PANNEL/ID NO. MONITOR Trend READING Alarm in RANGE C910/1705 60 Charcoal Bed Vault 5.6 mR/hr 10 10 C911/AR M 1 Cond. Pump Stalt 1.8 mR/hr 10 ' 10 C911/ ARM -2 Feedwater Heaters 4.5 mR/hr 10 10 C911/ ARM 3 Main Control Room 0.0 mR/hr 10 10 C911/AR M 4 Turbine Front Stand 2.5 mRihr 10 10 C911/AR M 5 Radwaste Corridor 2.6 mR/hr 10 10 C911/ ARM 6 Radweste Sump Area 89.9 mR/hr 10 10 C911/ ARM 7 Chem. Waste Tank 5.4 mR/hr 10 -10 C911/AR M -8 Rx Outside Tip Room .1 mR/hr 10 -10 C911/ ARM -9 RadWaste Ship. Lock O.7 mR/hr 10 -10 C911/AR M -10 RB Acess Area (S.E.) 4.0 mRlhr 10 10 C911/AR M -11 New Fuel Vault 0.5 mR/hr 10 10 C911/AR M -12 New Fuel Racks ! 0.2 mR/hr 10 -10 C911/ ARM -13 Shield Plug Area 1.0 mR/hr 10' 10 C911/ ARM 14 Spent Fuel Pool Arta 10.0 mR/hr 10 -10 ALARM SET POINTS 1705 60 = 200 mR/hr ARM 7 = 300 mR/hr ARM -1 = 55 mR/hr ARM 8 = 5 mR/hr ARM 2 = 600 mR/hr ARM 9 = 50 mR/hr ARM 3 = 1 mR/hr ARM -10 m 60 mR/hr ARM 4 = 450 mR!hr ARM 11 = 6 mR!hr ARM 5 = 15 mRihr ARM 12 = 40 mRlbr ARM -6 = 6000 mR/hr ARM -13 = 40 mR/hr ARM .1 = 30 mR/hr OOS-Out of Service OSH-Off Scale HI DS-Down Scale This is a Drill Page 5-42

1992 EVALUATED EXERCISE Ms0 No:14 AREA RADIATION MONITORS mMe: 03:00 PANNEL/ID NO. MONITOR Trend READING Alarm in RANGE C910/1705 60 Charcoal Bed Vault 5.0 mRlhr 10 10 C911/ ARM 1 Cond Pump Stair 1.8 mR/hr 10 10 C911/ ARM 2 Feedwater Heaters 4.9 mR/hr 10 10 C911/ ARM +3 Main Control Room 0.0 mRihr 10 ' 10 C911/ ARM -4 Turbine Front Stand 2.7 mR/hr 10 10 C911/AR M 5 Radwaste Corridor 2.6 mR/hr 10 10 0 4 C911/ ARM 6 Radwaste Sump Area 89.9 mR/hr 10 10 C911/ ARM 7 Chem. Waste Tank 5.4 mR/hr 10 10 C911/ ARM 8 Rx Outside Tip Room .1 mR/hr - 10' 10 C911/ ARM 9 RadWaste Ship. Lock O.7 mR/hr 10 10 0911/ ARM -10 RB Acess Area (S.E.) 4.0 mR/hr 10 10 C9i1/ ARM 11 New Fuel Vault 0.5 mR/hr 10 10 1 3 C911/ ARM 12 New Fuel Rocks 0.2 mR/hr 10 10 C911/ ARM .-13 Shield Plug Area 1.0 mR/hr 10 10 C911/ ARM 14 Spent Fuel Pool Area 10.0 mR/hr 10 -10 ALARM SET POINTS 1705-6 0 = 200 mR/hr ARM 7 = 300 mR/hr ARM -1 = 55 mRihr ARM 8 = 5 mR!hr ARM -2 = 600 mR/hr ARM 9 = 50 mR/hr ARM 3 = 1 mR/hr ARM -10 = 60 mR/hr ARM -4 = 450 mR/hr ARM 11 = 6 mRlhr ARM 5 = .15 mR!hr - ARM 12 = 40 mR/hr ARM 6 = 6000 mR!hr ARM 13 = 40 mR/hr ARM 14 = 30 mR/hr OOS-Out of Service OSH.Off Scale HI DS-Down Scale This is a Drill Page 5 43 l

l.

l - _ _ _ _ _ _ ,

1992 EVALUATED EXERCISE Msa No: 15 AREA RADIATION MONITORS Tiue: 03 n 5 PANNEL/ID NO. MONITOR Trend READING Alarm in RANGE C910/1705 60 Charcoal Bed Vault 4.4 mR/hr 10' 10 C911/ ARM 1 Cond. Pump Stalt 1.9 mR/hr 10 -10 C911/ ARM 2 Feedwater Heaters 5.2 mR/hr 10 10 C911/AR M 3 Main Control Room 0.0 mR/hr 10 10 C911/ ARM 4 Turbine Front Stand 2.9 mR/hr 10 10 <

C911/ ARM 5 Radwaste Corridor 2.6 mR/hr 10 10 0 4 C911/ ARM 6 Radwaste Sump Area 89.9 mR/hr 10 -10 C911/ ARM 7 Chem. Waste Tank 5.4 mRlbr 10 10 C911/ ARM 8 Rx Outside Tip Room .1 mR/hr 10 10 C911/ ARM 9 RadWaste Ship. Lock 0.7 mR/hr 10 10 C911/ ARM 10 RB Acess Area (S.E.) 4.0 mR/hr _

10 -10 C911/ ARM 11 New Fuel Vault 0.5 mR/hr 10' 10 C911/ ARM -12 New Fuel Racks 0.2 mR/hr 10 -10 C911/ ARM -13 Shield Plug Area 1.0 mR/hr 10' -10 C911/ ARM -14 Spent Fuel Pool Area 10.0 mR/hr 10 10 i

ALARM SET POINTS 1705 60 = 200 mR/hr ARM -7 = 300 mR/hr ARM 1 = 55 mR/hr ARM -8 = 5 mR/hr ARM 2 = 600 mR/hr ARM 9 = 50 mR/hr

, ARM -3 = 1 mR/hr ARM 10 = 60 mR/hr ARM -4 = 450 mR/hr ARM -11 = 6 mR!hr ARM 5 = 15 mR/hr ARM -12 = 40 mR/hr ARM -6 = 6000 mR/hr ARM -13 = 40 mR/hr ARM 14 = 30 mR/hr OOS-Out of Service OSH.Off Scale Hi DS-Down Scale This is a Drill >

Page 5 44

1992 EVALUATED EXERCISE Msa No:16 AREA RADIATION MONITORS Tius: 03:20 PANNEL/ID NO. MONITOR Trend READING Atarm in RANGE C910/1705 60 - Charcoal Bed Vault . 3.6 mR/hr 10' 10 C911/ ARM 1 Cond Pump _ Stalt 1.9 mR/hr 10" 10 C911/ ARM 2 Feedwater Heaters 7.4 mR/hr 10 10 C911/ ARM -3 Main Control Room 0.0 mR/hr 10' 10 C911/AR M 4 Turbine Front Stand 4.0 mR/hr 10 10 C911/ ARM -5 Radwaste Corridor 2.6 mR/hr 10 10 0

4 C911/ ARM -6 Radweste Sump Area 89.9 mR/hr 10 10-C911/ ARM 7 Chem Waste Tank 5.4 mR/hr 10 10 C911/AR M 8 Rx Outside Tip Room .1 mR!hr 10' 10 C911/AR M 9 RadWaste Shlp, Lock O.7 mR/hr 10 10 C911/ ARM 10 RB Acess Area (S.E.) 4.0 mR/hr 10 -10 ,

C911/ ARM -11 New Fuel Vault- 0.5 mR/hr 10 10 C911/ ARM 12 New Fuel Racks 0.2 mR/hr 10 10 C911/ ARM 13 Shield PluD Area 1.0 mR/hr 10 -10 C911/ ARM -14 Spent Fuel Pool Area 10.0 mR/hr 10 -10 AL ARM SET POINTS ,

'1705 60 = 200 mR/hr ARM 7 = 300 mR/hr ARM -1 = 55 mR/hr ARM 8 = 5 mR/hr

- ARM 2 = 600 mR/hr ARM 9 = 50 mR/hr

- ARM 3 = 1 mR/hr ARM 10 = 60 mR/hr ARM -4 = 450 mR/hr ARM -11 = 6 mR/hr ARM 5 = 15 mR/hr ARM -12 = 40 mR/hr

ARM -6 = 6000 mR/hr ARM -13 = 40 mR/hr ARM -14 = 30 mR!hr OOS Out of Service OSH Off Scale Hi DS-Down Scale This is a Drill Page 5 45

. - . . . ~ . _- -. - . - - . _ .. _- . - .. - -

1998 EVALUATED EXERCISE Msc No:17

. AREA RADIATION MONITORS Time: 03:30 PANNEL/ID NO. MONITOR Trsnd READING Alarm in RANGE C910/1705 60 Charcoal Bed Vault 2.9 mR/hr 10 10 C911/ ARM 1 Cond. Pump Statt 1.9 mR/hr 10 10 0 4 C911/ ARM 2 Feedwater Heaters 5.7 mR/hr 10 10 C911/ ARM 3 Maln Control Room 0.0 mR/hr 10 10 C911/ ARM -4 Turbine Front Stand _

3.1 mR/hr 10 10 C911/ ARM 5 Radwaste Corridor l 2.6 mR/hr 10 10 0 4 C911/AR M 6 Radwaste Sump Area 89.9 mR/hr 10 -10 0 4 C911/ ARM a7 Chem. Waste Tank 5.4 mR/hr 10 10 C911/ ARM 8 Rx Outside Tip Room .1 mR/hr 10' 10 0911 17M 9 RadWaste Ship. Lock 0.7 mR/hr 10 10 C911/AR M 10 RB Acess Area (S.E.) 4.0 mR/hr 10 -10 C911/ ARM 11 New Fuel Vault 0.5 mR/hr 10 10 1 3 C911/ ARM -12 New Fuel Racke 0.2 mR/hr 10 -10 C911/ ARM 13 Shleid Plug Area 1.0 mR/hr 10 10 C911/ ARM 14 Spont Fuel Pool Area 10.0 mR/hr 10 -10 ALARM SET POINTS 1705 60 = 200 mR!hr ARM 7 = 300 mR/hr ARM 1 = 55 mR/hr ARM 8 = 5 mR/hr ARM 2 = 600 mR/hr ARM 9 = 50 mRihr -

ARM 3 = 1 mR/hr ARM 10 = 60 mR/hr ARM 4 = 450 mR/hr ARM 11 = 6 mR/hr ARM -5 = 15 mR/hr ARM 12 = 40 mR/hr ARM -6 = 6000 mR!hr ARM -13 = 40 mR/hr ARM -14 = 30 mR/hr OOS-Out of Service OSH.Off Scale Hi DS-Down Scale This is a Drill .

Page 5 46

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

i 1998 EVALUATED EXERCISE y.Lu No: 18 i

AREA RADIATION MONITORS- riu s: 0 3 a s

, PANNEL/ID HO. . _ _

mot {lIQR Trenet BfgADING Alarm in RANGE 1 3 -

C910/1705 60 Charcest Red Vault _ 23 mRihr _

10 10 1 3 C911/ ARM 1 Conti. Pump Stalt IJ mR/hr 10 -10 0 4 C91UARM 2 Feedwater Healers 5.1 mR/hr 10 10 2 2 C911/ ARM 3 Main Control Room _

0.0 mR/hr 10 10 e o 4 C911/ ARM 4 Turbine Front Utand i 2.8 mR/hr l 10 10 1 3 C911/ ARM 5 Radweste Corridor _

2.6 mR/hr 10 +10 0 .I C911/ ARM 6 Redwesto Sump Arca 89.9 mR/hr 10 10 C911/ ARM 7 Chern. Waste Tonk . S.4 mR/hr 10 -10 C911/ ARM 5 R.u Outside Tip Roum 1 k~ _

.1 mR/hf

~

10 2

-10 2

C91_1/ ARM S hadW.este Ship. Lock _ , , , 0] mR/hr l 10 ' -10 C911/ ARM 10 RB Acess Area (S.E.) 4.0, mR/h: l l 10 -10 0.5 mR/hr y- ., .r C911/ ARM 11 Now Fuel Vault ,,_

, 10 10 1 3 C911/ ARM -12 0.2 mR/hr 10 10 New Fuel Racks ] _

r-- - -1 3 CS11/ ARM -13 Shield Plug Area l 1.0 mR/hr 10 10

- C711/AR M 14 Spent Fust Fool Area _

10.0 mR/hr 10' 10 4

AL ARM SET POINTS, 1705 60 = 200 mR/hr ARM 7 x 300 mR/hr ARM 1 = 55 mR/hr ARN1 8 = 5 mR/hr ARM 2 = 600 mR/hr ARM 9 = 50 mR/hr AR M - 3 = 1 m R!hr . ARM 10 = 60 mR/hr ARM -4 = 460 mR/hr ARM -11 = 6 mR/hr ARM 5 = 15 mR/hr ARM R12 = 40 mR/hr ARM -G = 6000 mR/hr ARM /f 3 = 40 mR/hr ARM 14 = 30 mH/hr OOS Out of Setylce OSH-Off Scals HI OS Down Scale This is a Drill Page 5 47

I 1993 EVALUATED EXERCISE Mso No:19 1 l

AREA RADIATION MONITORS vme: 04 :00 PANNE1JLO NO. MONITO.B. Iting jiEADING _- Alarm in RANGE C9% 0/1105 60 Charcoal Bed Vault 2.9, mR/hr l 10 10 C911/ ARM 1 Cond. Pump Stair l 1.8 mR/hr 10 10 0 4 C911/ ARM 2 Feedwater Hesters 4.0 mR/hr 10 10 i C911/ ARM 3 Main Control Room 0.0 mR/hr 10' 10 ,

0 4-C911/ ARM 4 Turbine Front Stand 2.2 mR/hr 10 10 l C911/ ARM 5 Radweste Corridor 2.6 mR/hr 10 10

? O 4 C911/ ARM 6 - Radwaste Sump Area 89.9 mR/hr 10 -10 ,

0 4 C911/ ARM 7 Chem. Waste Tank _

5.4 mR/hr 10 -10 2 2 C911/ ARM 8 Rx Outside Tlp Room .1 m R/hr 10 -10 2 2 C911/ ARM -9 RadWaste Ship. Lock 0.7 mRihr 10 -10 1 3 C911/ ARM 10 RB Acess / rea (S.E.) 4,0 mR/hr 10 -10 ,

C911/ ARM -11 New Fuel /ault 0.5 mR/hr 10 10 C911/ ARM 12 New Fuel Racks 0.2 mR/hr 10 10 -

C911/ ARM '13 Shield Plug Area 1.0 mR/hr 10 -10 1 3 C011/AR M -14 Spent Fuel Pool Area 10.0 mR/hr 10 10 ALARM SET POINTS 170 5 60 = 200 mR/hr ARM 7 = 300 mR/hr ARM 1 = 55 mR/hr ARM 8 = 5 mR/*i-ARM 2 = 600 mR!hr ARM 9 = 50 mR/hr ARM 3 = 1 mR/hr ARM -10 = 60 mR/hr ARM 4 = 450 mR/hr ARM -11 = 6 mR/hr ARM 5 = 15 mR/hr- ARM = -12 = 40 mR/hr ARM '-G = 6000 mR!hr ARM 13 = 40 mRlhr ;

ARM 14 = 30 mR/hr-l' l

i OOS-Out of Servit.a OSH-Off Scale Hi DS.Down Sc. ale This is a Drill Page 5-48

92-05B 1992 EE 112 RPV NORMAL PROCESS RADIATION :CNTMTNORMAL MSL RAD PROC RAD NORMAL NORMAL PRO _ CESS INSTR NO. MR/HR PR_QQESS INSTR NO. CPS OFFGAS LOG RAD A R M-1705-3 A [2.39 E+01] OFFGl.9 POST-TREATMENT A R M-1705-5 A l4.32 E + 03 l OFFGAS LOG RAD D R M-1705-3 B l2.39E+01l OFFGAS POCT-TREATMENT B R M- 170 5-5 8 l l4.32 E + 03 l CARBON DED VAULT R M-1705-60 l6.16E+01l RBCCW A PROCESS R M-1705-4 A l4.02 E+ 03 l RBCCW B PROCESS R M-1705-4 B l4.03 E + 03 l MAIN STEAM LINE INSTR NO. MR/HR fHI RANGE) INSTR NO. R/HR M AIN SM AM LINE A R M-170 5-2 A l6.33E+02l DRYWELL A RIT1001 606 A l1.10 E+ 00 l MA:N STEAM LINE D R M-170 5-2 B l8.15E+02] DRYWELL B RIT1001-6068 l1.00E+00l MAIN STEAM LINE C R M-170 5-2 C l5.45E+02l TORUS A RIT1001 407 A l0.00E+00 l MAIN STEAM LINE D R M-1705-2 0 l6.33E+02l TO).US B RIT1001 607 B l0.00 E + 00 l PILGRIM 28-M AY-1992 00:00 Messace_HQ: 1 This is a Drill Page 5-49 This is a Drill

l 4

l 92-050 8992 EE 112 RPV NORMAL PROCESS RADIATION cwiu: "onu^'

MSL RAD PROC RAC NORMAL NORMAL PROCESS INSTR NO. MRTHR PROCESS _. INSTR NO. CPS ,_,

OFFGAS LOG RAD A R M-1705-3 A l2.38E+01] OFFGAS POST-TREATMENT A R M- 1705-5 A l4 21 E+03l OFFGAS LOG RAD B R M-170 5-3 8 l2.38 E+01] OFFGAS FOST-TREATMENT D R M-1705-5 B 14.21 E + 03 l CARBON BED VAULT RM-1705-60 l6.01 E+01 l RBCCW A PROCESS R M-170 5-4 A l1.72 E + 03 l ROCCW D PROCESS R M-1705-4 B l3.73 E + 03 l MAIN STEAM LINE INSTR NO. MR!HR Dil RANGE) INSTR NO. R/HR MAIN STEAM LINE A R M-1705-2 A l6.31 E + 02 j DRYWELL A RIT1001-306 A l1.90 E+ 00 l MAIN STEAM LINE B R M-1705-2 8 l8.12E+02l DRYWELL B RIT1001-60GB l1.30 E+ 00j MAIN STEAM LINE C R M-1705-2 C l5.43E+02l TORUS A RITi n01-607 A l0.00 E + 00l MAIN STFAM LINE D R M-1705-2 D [6.31 E+02l TORUS B RIT1001-6070 0.00E+00l P't..G RIM ... 28-MAY 19?2 Od:15 Messagel10: 2 This is a Drill Pace 5-50 This is a Drill

92 05D 1992 EE 112 l RPV NORMAL PROCESS RADIATION ! CNTMT NORMAt MSL RAD PROC RAD l, NORMAL NORMAL l PROCESS INSTR NO. MR!HR PROCESS INSTR NO. CPS OFFGAS LOG R AD A R M-1705-3 A l2.36E401l OFFGAS POST-TREATMENT A RM-1705-5 A l4.10 E + 03 l OFFGAS LOG RAD P R M-1705-3 8 l2.36E+01l OFFGAS POST-TREATMENT B R M-1705-5 B l4.10 E + 03 l CARDON DED VAULT R M-1705-60 l5.8SE+01l RBCCW 4 PROCESS R M-17 05-4 A l3.43 E + 03]

RBCCW B PROCESS R M-170 5-4 B [3.44 E + 03 l MAIN STEAM LINE INSTR N1_ MR/HR (HI b_ANGP INSTR NO. R/HR MAIN STEAM LINE A R M-170 5-2 A l6.29E+G2l [JIYWELL A RiT1001-606 A j3.00E+00]

MAIN STEAM LINE B 9N-1705-20 [8.095+02l DRYWELL D RIT1001-6060 l2.90E+00l MAIN STEAM LINE C RM-1705-2C l5.41 E+02] TORUS A R!TiOO1-607 A l0.00 E+00l MAIN STEAM LINE D RM 1705- JD [6,29E+02] TORUS B RIT1001-6070 l0.00E+00l PILGR!M + 28-M AY-1992 00:30 hienage No: 3 This is a Drill Page 5-51 This is a Drill

92-050 1992 EE 112 RPV NORMAL PROCESG RADIATICN Ic"Tur"onual MSL RAD PROC RAD NORMAL NORMAL ,

PROCESS INSTR NO. - MR/HR PROCESS INSTR NO. CPS '

OFFGAS LOG RAD A RM 1705-3 A l2.22E+01l OFFGAS POST-TREATMENT A R M-1705-5 A @98E+03l OFFGAS LOG RAD 8 RM-1705-30 [2.22 E+0] OFFGAS POST-TREATMENT B RM-1705-5B l3.98 E+ 03)

CARBON BED VAULT H M 1705-60 '5.68 E+0% RBCCW A PROCESS g R M-1705-4 A l3.17 E + 03 l RDCCW B PROCESS R M-1705-4 8 l2.18 E +03 l MAIN STEAMilNE ITfSTR NO. M'3/HR [Hi RANGE) !NSTR NQ. R/HR ,

MAIN STEAM LINE A R M-1705-2 A 15.59E+02l ORYWELL A RIT1001-606 A l3.80E+00 l MAlfJ STEAM LINE D R M-1705-2 B l7.19E+02] DRYWELL U RIT1001-6068 [3.70 E+00l MAiH STEAM LINE C R M- 1705-2 C l4.81 E+02] TORUS A RIT1001-607 A l0.00 E+00 l MAIN STEAM LINE D R M-170 5-70 l5.59E+02] TORUS B RIT1001-607 B l0.00 E+00l PILGRIM -. 28-M AY-1992 Ob:45 message No: 4 ,

This is a Drill Page 5-52 This is a Drill i

==

_=

- = . =

I:

92-050 1992 EE 112 RPV NORMAL PROCESS RAD!ATION lCNTMTNORMAL]

MSL RAD PROC RAD NORMAL NORMAL PROCESS INSTR NQ. MR!HR PROCESS INSTR NO, CPS OFFGAS LOG RAD A R M-1705-3 A l1.89E+01] OFFGAS POST-TREATMENT A RM 1705-5 A l3.7.5 E + 03 l OFFGAS LOG RAD 8 R M-1705-3 0 l1.89E+01l OFFCAS POST-TREATMENT B RM-1705-50 l3.75 E + 03 l CARDON BED VAULT R M-17 05-60 l5.34 E+01 l RDCCW A PROCESS R M-1705-4 A [2.95 E + 03 l ROCCW D PROCESS R M-1705-4 8 {2.96 E + 03 l MAIN STEAM LINE tr1STR NO. MR/HR (til RANGE) INSTR NO. R/HR MAIN STEAM LINE A R M-170 5-2 A h.48E+02l DRYWELL A RIT1001-606 A l4.30E+00l MA!N STEAM LINF B RM 1705-2B [5.77E+02] DRYWELL B RIT1001-6068 l4.20E+00l MAIN STEAM LINE C R M-1705-2 C [3.86E+02] TORUS A RIT1001-607 A l0.00 E+00]

~

MAIN $ TEAM LINE D R M-1705-2 D l4.48E+02] TORUS B RIT1001-6073 [0.00 E4 00 l PILGRIM - M AY-1992 01:0D Message _ tic: 5 This is a Drill 'n age 5 53 This is a Drill i

92-050 1992 EE 112 RPV NORMAL PROCESS RADIATION CNTMT NORMAL

)

'MSL RAD PROC RAD NORMAL NORMAL PROCESS INSTR NO. MR/HR- PROCESS INSTR NO. CPS ,

i OFFGAS LOG RAD ' A R M-1705-3 A l1.71 E+01l OFFGAS POST-TREATMENT A R M-1705-5 A l3.41 E + 03 l OFFGAS LOG RAD B R M-1705-3 8 l1.71 E+01l OFFGAS POST-TREATMENT B R M-170 5-5 B t

l3.41 E + 03] ;

7 CARDON BED VAULT R M-1705-60 (4.86E+01l RBCCW A PROCESS R M-1705-4 A l2.74 E +03 [

ROCCW B PROCESS R M-1705-4 B {2.75 E+ 03 l ;

MAIN STEAM _LINE INSTR NO. MR/HR (HI RANJE) INSTR NQ. R/HR f MAIN STEAM LINE A R M-170 5-2 A

{30E+02l DRYWELL A RIT1001-606 A l4.60 E+00 j '!

MAIN STEAM LINE B RM 1705-2B l5.53E+02l DRYWELL B RIT1001-6068 l4.50E+00]

~

MAIN STEAM L!NE ,C RM 1705 2C l3.70E+02l TORUS A RIT10G1-607A l0 00E+00l MAIN STEAM LINE D RM-1705-2D l4.30E+02l TORUS B RIT1001-G07 8 'O.Out+00 l i

i PILGRIM . 28-MAY-1992 01:15 ,

Messacello: 5 -

This is a Drill Page 5-54 This is a Drill

92-059 1992 EE 112 i RPV NORMAL PROCESS RADIATION CNNT NORMAL MSL RAD PROC RAD-NORMAL NORMAL PROCESS INSTR NO. MR/HR PROCESS INSTR NO. CPS OFFGAS LOG RAD A H M-1705-3 A l1.66E+01l OFFGAS POST-TREATMENT A R M-170 5-5 A y SE+03l OFFGAS LOG RAD B R M-1705-3 B l1.66E+01l OFFGAS POST-TREATMENT B R M-170 5-5 B l3.15 E+ 03 l CARBON BED VAULT R t 4-170 5-60 l4.48E401l RBCCW A PROCESS RM-1705-4 A jz.56E+03l ROCC'd B PROCESS R M-170 5-4 0 f.57 E+ 03 l MAIN STEAM LINE _ INSTR NO. MR/HR (HI RANGE') INSTR NO. R/HR MAIN STEAM LINE A RM-1705-2A l6.63E+01 l DRYWELL A RIT1001-606 A l4.50 E + 00 l MAIN STEAM LINE B R M-17 05-2 0 l8.54E+01l DRYWELL B RIT1001-6060 l4.40E +00l MAIN STEAM LINE C R M-1705-2 C l5.70E+01l TORUS A RIT1001-607 A l3.00E-01 l MAIN STEAM LINE D R M-1705-2 D l6.63E+01l TORUS B RIT1001-607B l2.00E-01 l PILGRIM -

28-MAY-1992 01:25 Message _No: 7 This is a Drill Page 5-55 This is n Drill

i 92-05 B 1992 EE PROCESS RADIATION 112 RP'/ FOHM AL c"TMT NORMA' i

i [

f l MSL RAD PIN C RAD i NORMAL NORMAL j i

PROCESS INSTR NO. MRIHR PROCESS INSTR NO. CPS

OFFGAS LOG RAD .A R M-1705-3 A l1.61 E+01 j OFFGAS POST-TREATMENT A R M-1705-5 A l2.89 E+ 03 l !

OFFGAS LOG RAD B R M-1705-3 B l1.61 E+01 l OFFGAS POST-TREATMENT B RM-1705-50 l2.89 E +03 l i

l CARBON BED VAULT R M-1705-60 l4.10E+01l RBCCW A PROCESS R M-1705-4 A l2.59 E+ 03 l ;

I RBCCW B PROCESS R M-1705-4 B [2.60 E+ 03 l i

MAIN STEAM t.INE INSTR NO. MR/HR (Hi RANQEl . INSTR NO. R/HR i

MAIN STEAM LINE A R M-1705-2 A l3.13 E+02 j DRYWELL 1: RIT1001-606 A l4.60 E+00!

MAIN STEAM LINE 'B RM-1705-2B l4.02E+02l DRYWELL 8 RIT1001-606B l4.50 E+ 00]

f MAIN STEAM LINE C RM-1705-2C [2.69E+02l TORtJS A RIT1001-607A l2.00E-01 j l MAIN STEAM LINE D R M-17 05-2 D l3.13E+02l TORu3 B RIT1001-607B l2.00E-01 l l

4

! PILGRIM -- 28-M 41f-1992 01:30 Messace_No: 8 i

l L

This is a Drill Page 5 56 This is a Drill i

i !

l 92-05B 1992 EE I l

112 RPV NORMAL PROCESS RADIATION CNTMT NORMAL ;

! MSL RAD PROC RAD i

NORMAL l HORMAL- [

I PROCESS INSTR NO. MRHR ._ PROCESS INSTR NO. CPS

]

6

OFFGAS LOG RAD A R M-1705-3 A l1.07E+91 l OFFGAS POST-TREATMENT A RM-1705-5 A l1.98 E + 03 l OFFGAS LOG RAD B R M-1705-3 B 707E+01] OFFGAS POST-TREATMENT B R M-1705-5 B 1

[1.98E+03l l CARBON BED VAULT R M-1705-60 l2.80 E + 01 j RBCCW A PROCESS R M-1705-4 A l2.39 E+03 l ;

}

RBCCW B PROCESS R M-170 5-4 8 l2.40 E + 03 l l l

AAIN STEAM LINE INSTR NO. MRIHB (HI RANGE) INSTR NO. R/HR

[ MAIN STEAM LINE A R M-1705-2 A l5.34E+0 i] DRYWELL A RIT1001-606 A l3.4 0E+ 00l MAIN STEAM LINE D R M-1705-2 8 l6.87Ee 01l DRYWELL 8 RIT1001-6060 l3.30 E+00l MAIN STEAM LINE C R M-1705-2 C l4,.59E+01 l TORUS A RIT1001-E07A l5.00E-01 l MAIN STEAM LINE D RM-1705-2D M4E+01l TOWS B RIT1001-6078 l5.00E-01 }

!t I

P!LGRIM -- 28-MAY 1992 01:45 Message _tfo: 9 I

i f

i

, This is a Drill Page 5-57 This is a Drill i t

m ..

1992 EE 92-050 CNTUT NORMAL 112 RPV NORMAL ! PROCESS RADIATION MSL RAD PROC RAD NORMAL NORMAL

!NSTR NO._,, MR/HR PROCESS INSTR NO. CPS PROCESS OFFGAS LOG RAD A R M-1705-3 A l7.70E+00j OFFGAS POST-TREATMENT A R M-170 5-5 A l1 26 E+03 l OFFGAS LOG RAD D R M-170 5-3 B l7.70E+00l OFFGAS POST-TREATMENT B R M- 1705-5 B l1.26 E + 03 )

< l CARBON BED VAULT R M-1705-60 (1.77~d+0 Q RBCCW A PROCESS RM-1705-4 A h24E+03] I 9BCCW B PROCESS R M-17D S-4 8 l2.25 E + 03 l i

l MR/HR (HI RANGE) INSTR NQ. R/HR MAIN STEAM l.INE INSTR NO.

MA!N STEAM LINE A RM-170s.2 A RIT1001-606 A l3 10 E+00 l

{.09E+01] DRYWELL A MAIN STEAM LINE B RM-1705-2B [6.55E+01l DRYWELL B RIT1001-606B l3.00 E+ 00 l MAIN STEAM LINE C RM-1705-2C l4.38E+01l TORUS A RIT1001-607 A l5.00E-01 l MAIN STEAM LINE D R M-1705-2 D l5.09E+01l TORUS B RIT1001-G078 l4.00 E-01 l PILGRIM --- 28-MAY-1992 02:00 feessanlfo: 10 Page 5-53 This is a Drill This is a Drill

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1992 EE 92-058 112 HPV NOi4 MAL PROCESS RADIATION c" tut"cau^ti MSL RAD PROC RAC NORMAL NORMAL INSTR NO. MR;E PROCESS INSTR NO. CPS PROCESS R M-1705 l6.59 E +02 l OFFGAS LOG RAD A R M-1705-2 A l7.40E+00l OFFGAS POST-TREATMENT A R M-1705-30 .,6.5 9 E + 02 l OFFGAS LOG RAD B l7.40E+00l OFFGAS FOST-TREATMENT B RM-1701 "M CARBON BED VAULT R M-1705-60 QOEA00l RBCCW A PROCESS RM-170 5-4 A l2.11 E +03 l RBCCW B PROCESS RM-1705-4B l2.12 E+ 03 l MR'HH (Hf 'R ANGE) INSTR NO. R TIR MAIN STEAM LINE INSTR NO.

MAIN STEAM LINE A RM-1705-2 A l1.84E+01l DRYWELL A Rf 71001-606 A l2 90E+00l MAIN STEAM LINE D R M-1705-2 B l2.36E+0% DRYWELL B RIT1001-6068 l2.80 E+ 00 l MAIN STEAM LINE C R M-1705-2 C l1.5BE+01l TORUS A RIT1001-607A {4.00E-01 l MAIN STEAM LINE D R M-1705-2D l1.84 E+01l TORUS B RITS001-607B l3.00E-01 l l

l PILGRIM M AY-1992 02:15 Messanelic: 11 This is a Drill Pane 5 59 This is a Drill

I i 92-059 1992 EE i

112 RPV NORMAL PROCESS RADIATION c"T=T "ca=^' '

} MSL RAD PROC RAD NORMAL NORMAL [

4 t

, PROCESS INSTR NO. MR/HR PROCESS INSTR NO. CPS !

OFFGAS LOG RAD A R M-1705-3 A l7.40E+00l OFFGAS POST-TREATMENT A R M-1705-5 A l4.38 E + 02 l I

4 OFFGAS LOG RAD B R M-1705-3 8 l7.40E+00] OFFGAS FOST-TREATMENT B R M-1705-5 8 l4.38 E+ 02 l CARBON BED VAULT R M-170 5-60

[6.20E+00l RBCCW A PROCESS R M-170 5--4 A l2.00E403l t

RDCCW B PROCESS R M-1705-4 B l2.01 E + 03 l l

[

MAIN STEAM LINE INSTR NO _ Mrt/HR fHIRANGEL INSTR NO. RIHR i

j MAIN STEAM LINE A RM 1705-2 A l1.81 E+01l DRYWELL A pit 1001-606 A l2.60 E+ 00l MrstN STEAM LINE B R M-1705-2 B l2.33E+01] DRYWELL B i

RIT1001-6068 l2.50E+00 l -

MAIN STEAM LINE C R M-1705-2 C l1.56E+01l TORUS A f RIT1001-607 A l3.00E-01 l t

l MAIN STEAM LINE D RM-1705-2D l1.81 E+01l TORUS B RIT1001-607B l3.00 E-01 l ,

I i i

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4 PILGRIM --- 28-MAY-1992 02:3 0

! MenaceEo: 12 i

This is a Drill Page 5-60 This is a Drill

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92-05B 1992 EE ,

112 RPV NORMAL PROCESS RADIATION c"T=T "cau^t :

i :

MSL 9AD PROC RAD -

NORMAL NORMAL i

PROCESS INSTR NO. MR!HR PROCESS INSTR NO. CPS OFFGAS LOG RAD A R M-1705-3 A l7.30E+00l OFFGAS POST-TREATMENT A R M-170 5-5 A l3.91 E + 02 l OFFGAS LOG RAD B R M-1705-30 l7.30E+00l OFFGAS POST-TREATMENT B R M-170 5-5 B p.91 E +02 l CARDON BED VAULT RM-1705-60 t

' l5.60E+00] RBCCW A PROCESS RM-170s-4 A l1.89 E +03 )

RBCCW B PROCESS R M-170 5-4 B [1.90 E + 03 l }t MAIN STEAM LINE INSTR NO. MR:HR (HIRANGET INSTR NO. R;HR i i

MAIN STEAM LINE A R M-1705-2 A l5.62E+01l DRYWELL A RIT1001-606 A l2.4 0 E+00]

MAIN STEAM LINE B R M-1705-2 8 l7.23E+01l DRYWELL B RIT1001-606B l2.30 E+00j MAird STEAM LINE C RM-1705-2C l4.83 E+ 01 j TOR'US A RtT1001-607A ]2.00E-01 l MAIN STEAM LINE D R M-1705-2 D l5.62E+01l TORUS B RIT1001-607B l2.00E-01 l

, PILGRIM --- 28-MAY-1992 02:45 4

MCS3DQtliZ 13 '

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This is a Drill Page 541 This is a Drill

i 92-05B. 1992 EE l l

112 RPV NORMAL PROCESS RADIATION CNTMT NORMAL l 1

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lMSLRAD PROC RAD j NORMAL NORMAL PROCESS INSTR NO. MR/HR PROCESS INSTR NO. CPS OFFGAS LOG RAD A R M-1705-3 A l6.90E+00l OFFGAS POST-TREATMENT A R M-1705-5 A [3.56 E +02 l OFFGAS LOG RAD B R M-1705-3 0 l6.90E+00! OFFGAS POST-TREATMENT E R M-17C 5-58 l3.56 E+ 02 l CARBON BED VAULT R M-1705-60 j5.00E+00l RBCCW A PROCESS R M-170 5-4 A l1.79 E+ 03 l l RBCCW 9 PROCESS R M-170 5-4 8 l1.80 E+ 03 l MAIN STEAM UNE INSTR NO. MRIHR fHI RANGE) INSTR NO. R/HR i i MAIN STEAM LINE A R M-1705-2 A 14.52E+01l DRYWELL A RIT1001-606 A l2.30 E+00l l MAIN STEAM LINE B R M-1705-2 B l5.81 E+01l DRYWELL 8 RIT1001-60GB l2.20 E+00 l

) MAIN STEAM LINE C R M-1705-2 C l3.89E+01l TORUS A RIT1001-607A ]2.00E-01 l

MAIN STEAM LINE D RM-1705-20 l4.52E+01l TORUS B RIT1001-6078 l2.00 E-01 l i . .

PILGRIM .-- 28-M AY-1992 03:00

Mc: :Sace No: 14 i .

j This is a Drill Page 5-62 This is a Drill

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92-0S8 1932 EE 112 RPV NORMAL PROCESS RADIATION c"T*T"onwa'l i

MSL RAD PROC RAD NORMAL NORMAL PROCESS INSTR NO. MR/HR PROCESS INSTR NO. CPS i

OFFGAS LOG RAD A R M- 1705-3 A l6.60E+00l OFFGAS POST-TREATMENT A R M-170 5-5 A l3.10 E+ 02 l OFFGAS LOG RAD B RM-1705-3B [6.60E+00] OFFGAS POST-TREATMENT B R M-1705-5 B l3 10 E+02l

i CARBON BED VAULT R M-1705-60 [4.40E+0C} RBCCW A PROCESS R M-1705-4 A l1.71 E + 03 l ;

I RBCCW B PROCESS R M-170 5-4 8 l1.72 E + 03 l i j _ MAIN STEAM LINE INSTR NO. MR/HR _ (HIRANGE) INSTR NO. RHR MAIN STEAM LINE A R M-1705-2 A l8.67 E+01 j DRYWELL A RIT1001-606 A l2.20 E+00j i MAIN STEAM LINE B R M-1705-2 B l1.12E+0?] DRYWELL B RIT1001-606 B l2.10 E+ 00 }

MAIN STEAM LINE C RM-1705-2C l7.47E+01l TORUS A RIT1001-607A l2.00E-01 l MAIN STEAM LINE D RM-1705-20 l8.67E+D] TORUS B RIT1001-6078 l1.00E-01 l ;

i PILGRIM --- 28-M AY-1992 03:15 Memage No: 15 i

This is a Drill Pace 5-63 This is a Drill '

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92-058 1992 EE 112 RPV Nonu^' PROCESS RADIATION CNTMT NORMAL MSL RAD PROC RAD NORMAL NORMAL PROCESS INSTR NO, MR/HR PROCESS INSTR NO. CPS OFFGAS LOG HAD A R M-1705-3 A l5.90E+00l OFFGAS POST-TREATMENT A R M-1705-5 A l5.76 E+ 02 l OFFGAS LOG RAD B RM-1705-38 l5.90E+00l OFFGAG POSTeTREATMENT B R M-170 5-5 B l5.76 E + 02 l CARBON BED VAULT R M-1705-60 l3.60E+00l RBCCW A PROCESS R M-1705-4 A l1.70 E + 03 l !

RBCCW B PROCESS R M-1705-4 8 l1.71 E + 03 l MAIN STEAM LINE INSTR NO. MR/HR (HIRANGE) INSTR NO. R/HR MA!N STEAM LINE A R M-1705-2 A l1.76E+02l DRYWELL A RIT1001-606 A l2.20 E +00 l t

MA!N STEAM LINE B R M-1705-2 B l2.27E+02l DRYWELL B RIT1001-6060 l2.10 E+ 00l MAIN STEAM LINE C R M-1705-2 C l1.52E+02l TORUS A RIT1001-607 A l2.00E-01 l MAIN STEAM LINE D R M-1705-2 D l1.76E+02l TORUS B RIT1001-607B l1.00E-01 l PILGRIM - 28-MAY-1992 03:20 Message _110: 16 1

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This is a Drill Pa;:e 5-64 This is a Drill

, _ . _ - _ _ . - _ _ - _ _ _ _ _ _ - - _ _ . _ _ _ _ _l

92-058 1992 EE i 112 RPV NORMAL PROCESS RADIATION CNTMT NORMAL i

I i

MSL RAD PROC RAD s

NORMAL NORMAL PROCESS INSTR NO. MR/HR PROCESS INSTR NO. CPS i

l- OFFGAS LOG RAD A R M-1705-3 A l5.30E+00l OFFGAS POST-TREATMENT A R M-170 5-5 A l2.00 E + 02 ] l OFFGAS LOG RAD D R M-1705-3 8 l5.30E+00l OFFGAS F7ST-TREATMENT B BM-1705-5B l2.00 E + 02 l CARBON BED VAULT R M-1705-60 l2.90E+00l RBCCW A PROCESS R M-1705-4 A l1.64 E +03l RBCCW B PROCESS R M-170 5-4 8 l1.65 E + 03] ,

MAIN STEAM LINE INSTR NO. MRMR fHIRANGE) INSTR NO. RIHR '

MAIN STEAM Lil!E A R M-1705-2 A l1.03E+02] DRYWELL .A RIT1001-606 A [2.00 E+00] ;

MAIN STEAM LIP $E B R M- 1705-2 8 l1.33E+02l DRYWELL 8 RIT1001-606B j1.90E+00l

[

MAIN STEAM tlNE C R M-1705-2 C [8.87E+0T] TORUS A RIT1001-507A l1.00 E-01 l MAIN STEAM LINE D R M-1705-2 D l1.03E+02l TCRUS B RIT1001-6078 l1.00E-01 l 1 I

PILGRIM --- 28-M AY-1992 03:30 i

4 MESSaSe No: 17

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i

, t This is a Drill Page 5-tis This is a Drill [

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92-05B 1992 EE c"TMr uCRunt 112 RPV NORMAL PROCESS RADIATION MSL RAD PROC RAD NORMAL NORMAL PROCESS INSTR NO. MR/HR PROCESS INSTR NO. CPS R M-1705-3 A RM-1705-5 A l2.00 E + 02 l OFFGAS LOG RAD A lS.80E+06} OFFGAS POST-TREATMENT A OFFGAS LOG RAD B R M-1705-3 B [5.80E+00l OFFGAS POST-TREATMENT B R M- 170 5-5 8 l2.00 E+ 02 l CARBON BED VAULT R M-1705-60 [2.90E+00l RBCCW A PROCESS RM-1705 4 A l1.57E + 03]

RBCCW B PROCESS R M- 170 5-4 8 l1.58 E + 03 l MAIN STEAM LINE INSTR NO. MR/HR (HI RANGE) INSTR NO. RHR MAIN STEAM LINE A R M-170 5-2 A 18.07E+01l DRYWEtt A RIT1001-606 A l1.90E+00l MA!N STEAM LINE D R M-1705-2 B l1.04E+02l DRYWELL B RIT1001-6060 l1.80 E +00 l MAIN STEAM LINE C R M-1705-2 C [6.95E+01l TORUS A RIT1001-607A l1.00E-01 l MAIN STEAM LINE D P M-1705-2 D l8.07E+01l TORUS B RIT1001-607B l1.00E-01 l PILGRIM .-. 28-M AY-1992 03:45 Message No: 18 This is a Drill Page 5-66 This is a Drill

1 92-058 1997 EE 112 RPV NORMAL PROCESS RADIATION CNTMT NORMAL l

j MSL RAD PROC RAD NORMAL NORMAL PROCESS INSTR NO. MR/HR PROCESS INSTR NO. CPS l

OFFGAS LOG RAD A R M-1705-3 A l5.80E+00l OFFGAS POST-TREATMENT A R M-1705-5 A l2.00 E+02l OFFGAS LOG RAD- B R M-1705-3 B l5.80E+00l OFFGAS POST-TREATMENT B RM-1705-58 l2.00 E + 02 l CARBON BED VAULT R M-1705-60 l2.90E+00l RBCCW A PROCESS R M-170 5-4 A l1.51 E+ 03 l

)

) RBCCW B PROCESS R M-1705-4 B l1.52 E+03 l l

i 4

MAIN STEAM LINE INSTR NO. MR/HR (HI RANGE) INSTR NO. R/HR i

MAIN STEAM LINE A R M-1705-2 A l1.76E+01l DRYWELL A RIT1001-606 A {1.80E+00l MAIN STEAM LINE B - R M-1705-2 B l2.26E+01l DRYWELL B RIT1001-6068 l1.70E+00l MAIN STEAM LINE C R M-1705-2 C l1.51 E+01l TORUS A RIT1001-607A l1.00 E-01 l MAIN STEAM LINE D R M-1705-2 D l1.76E+01] TORUS B RIT1001-607B l1.00E-01 l i

l PILGRIM --- 28-MAY-1992 04:00 i Message No: 19 l

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This is a Drill Pace 5-67 This is a Drill

92-05D 1992 EE 413 NORMAL AREA RADIATION _

NOnuAL !

EFFL HAD MSL RAD AREA RAD NORM'AL NORMAL NORMAL AREA (HI RANGE) INSTR NO. R/HR AREA INSTR NO. MR HR r DRYWELL A RIT1001-606 A l1.10E+00l NEW FUEL RACKS RE-12 l2.00E-01 l j DRvWELL G. RIT1001-606 B ' l1.00E+00l REFUEL FLR-NEW FUEL VAULT RE-11 l5.00E-01 l TORUS A RIT1001-607A [0.00E+00l REFUEL FLR-SPENT FUEL POOL R E-14 l1.00 E + 01 l TORUS B RIT1001-6070 [0.00E+00l REFCEL FLR-SHIELD PLUG R E-13 l1.00 E + 00)

AREA INSTR NO. MR'HR j MAIN CONTROL ROOM R E-3 l0.00E+00l RADWASTE SUMP R E-6 l8.99 E + 01 l 3

MAIN CONTROL ROOM INTAKE RM-1705-16l0.00E+00l RADWASTE CHEM WST REC TANK RE-7 l5.4 0 E + 00 l RX BLDG OUTSIDE TIP RM R E-8 l1.00E-01 l RADWASTE CORRIDOR RE-5 l2.60 E + 00 l RXBLDG ACCESS-SE R E-10 R E-9 l7.00 E-01 l r

. l4.00E+00l RADWASTE SHIPPING DOCK r

TURB BLDG COND PMP STAIRWAY RC-1 l2.00 E+ 00 l [

TURBINE FRONT STANDARD R E-4 l1.01 E+ 01 l ;

FW HEATER STAIRWAY R E-2 l1.84 E+ 01 l PILGRIM ---

28-MAY-1992 00:00 l

j PJSage No: 1 l I

r This is a Drill Page 5-68 This is a Drill

I 92-05B 1992 EE 413 NORMAL AREA RADIATION mRMAL i

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i EFFL RAD MSL RAD AREA RAD !

NORMAL NORMAL NORMAL AREA (HI RANGE) INSTR NO. R/HR AREA INSTR NO. MRIHR DRYWELL A RIT1001-606 A l1.90E+00l NEW FUEL RACKS R E-12 l2.00E-01 l DRYWELL B RIT1001-606 8 R E-11 l1.80E+00l REFUEL FLR.NEW FUEL VAULT l5.00E-01 l '

TORUS A RIT1001-607A l0.00E+00l REFUEL FLR-SPENT FUEL POOL R E-14 [1.00 E+ 01 l TORUS B RIT1001-6078 l0.00E+00l REFUEL FLR. SHIELD PLUG R E-13 l1.00 E+ 00 l pf ~ A INSTR NO. MRHR MA.ri CONTROL ROOM R E-3 l0.00E+00l RADWASTE SUMP R E-6 l8.99 E + 01 l MAIN CONTROL ROOM INTAKE RM-1705-16l0.00E+00l RADWASTE CHEM WST REC TANK RE-7 l5.4 0 E + 00 l t RX BLDG OUTSIDE TIP RM R E- 8 R E-5 l2.60 E + 00 l

l1.00E-09 RADWASTE CORRIDOR t

RX8 LOG ACCESS-SE R E-10 R E-9 [7.00E-01 l l4.00E+00l RADWASTE SHIPPING DOCK l t

TURB BLDG COND PMP STAIRWAY RE-1 l2.00 E+ 00 l ,

TURBINE FRONT STANDARD R E-4 l1.01 E+ 01 l r

4 FW HEATER STAIRWAY R E-2 l1.84 E+ 01 l P!LGRIM --- 28-MAY-1992 00:15 Message No: 2 i

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This is a Drill Page 5-69 This is a Drill l

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i 92-008 1992 EE

-413 Noa"^' AREA RADIATION NORMAt i

i EFFL RAD MSL RAD AREA RAD j NORMAL NORMAL NORMAL i

AREA (Hi RANGE) INSTR NO. R/HR AREA INSTR NO. MR/HR !

I '

DRYWELL A RIT1001-606 A l3.00E+00l NEW FUEL RACKS R E-12 l2.00 E-01 l j DRYWELL B RIT1001-6068 l2.90 E+00j REFUEL FLR-NEW FUEL VAULT R E-11 l5.00E-01 l TORUS A RIT1001-607 A l0.00E+0ttl REFUEL FLR-SPENT FUEL POOL R E-14 l1.00 E+ 01 l TORUS B l RIT1001-607B l0.00E+00l REFUEL FLR-SHIELD PLUG R E-13 l1.00 E+ 00 l 3-AREA INSTR NO.' MR/HR i .

l MAIN CONTROL ROOM R E-3 l0.00E+00l RADWASTE SUMP R E-6 l8.99 E+ 01 l l t

MAIN CONTROL ROOM INTAKE RM-1705-16l0.00E+00l RADWASTE CHEM WST REC TANK RE-7 l5.40 E+ 00 l l Rx BLDG OUTSIDE,TIP RM R E-8 R E-5 l2.60 E + 00 l

'l l1.00E-01 l RADWASTE CORR! DOR R E-9 [7.00E-01 l !

) RXBLDG ACCESS-SE R E-10 l4.00E+00l RADWASTE SHIPPING DOCK

! I

=

TURB BLDG COND PMP STAIRWAY RE-1 l2.00 E+ 00l l TURBINE FRONT STANDARD R E-4 l1.01 E+01 l l

FW HEATER STAIRWAY R E-2 l1.83 E+ 01 l PILGR!M 28-MAY-1992 00: 30 l.

Message No: 3 1

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,. This is a Drill Pace 5-70 This is a Drill !

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, i 92-058 1992 EE i

4 413 NORMAL AREA RADIATION mRMAL j

! I EFFL RAD MSL RAD AREA RAD i NORMAL NORMAL NORMAL [

AREA (HIRANGE) INSTR NO. R/HR AREA. INSTR RO. MR/HR DRYWELL A RIT1001-606 A l3.80E+00l NEW FUEL RACKS R E-12 [2.00E-01 l . !

t DRYWELL B

~

RIT1001-606B l3.70E+00l REFUEL FLR-NEW FUEL VAULT R E-11

[5.00E-01 l TORUS A RIT1001-607 A l0.00E+00l REFUEL FLR-SPENT FUEL POOL R E-14 l1.00 E+ 01 l TORUS B RIT1001-607B l0.00E+00l REFUEL FLR-SHIELD PLUG R E-13 l1.00 E + 00 l t

i, AREA INSTR NO. MR/HR !

MAIN CONTROL ROOM R E-3 l0.00E+00l RADWASTE SUMP R E- 6 [8.99 E+ 01 l MAIN CONTROL ROOM INTAKE RM-1705-16[0.00E+00l RADWASTE CHEM WST REC TANK RE l5.40 E+00 l l

RX BLDG OUTSIDE TIP HM R E-8 R E-5 l2.60 E+ 00 l j l1.00E-01 l RADWASTE CORRIDOR RXBLDG ACCESS-SE R E-1 G [4.00E+00l RADWASTE SHPPING DOM R E-9 j7.00E-01 l TURB BLDG COND PMP STAIRWAY RE-1 l2.00 E4 00l l

. i TURBINE FRONT STANDARD R E-4 l9.20E+30l i

FW HEATER STAIRWAY R E-2 l1.6'I E + 01 l PILGRIM -- 28-MAY-1992 00:45 l

i- McS3 age No: 4 i i

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This is a Drill- Page 5-71 This is a Drill i !

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92-05B 1992 EE 413 NORMAL AREA RADIATION NORMAL I

i EFFL RAD MSL RAD AREA RA~" I i NORMAL NORMAL NORMA g.

J j

AREA (HI RANGE) INSTR NO. R/HR AREA INSTR NO. MR/HR j DRYWELL A RIT1001-606 A l4.30E+00l NEW FUEL RACKS R E-12 [2.00E-01 l DRYWELL B RIT1001-606B l4.20E+00l ' REFUEL FLR-NEW FUEL VAULT R E-11 l5.00E-01 l j TORUS A l RIT1001-607 A l0.00E+00l ' REFUEL FLR-SPENT FUEL POOL R E-14 l1.00 E+0% _

RIT1001-607B l0.00E+00l REFUEL FLR-SHIELD PLUG R E-13

. l1.00E+00l j I j AREA INSTR NO. MR/HR MAIN CONTROL ROOM R E-3 l0.00E+00l RADWASTE SUMP R E-6

[8.99 E+ 01 ]

MAIN CONTROL ROOM INTAKE RM-1705-16j0.00E+00l RADWASTE CHEM WST REC TANK RE-7

l5.40 E + 00l RX BLDG 'OUTSIDE TIP RM R E-8 RE-5 l1.00E-01 l ' RADWASTE L CORRIDOR l2.60 E + 00l t j RXBLDG ACCESS-SE R E-10 R E-9 l7.00 E-01 l

[4.00E+00l RADWASTE SHIPPING DOCK 1

TURB BLDG COND PMP STAIRWAY RE-1 l1.90 E+00 l I

TURBINE FRONT STANDARD R E-4 l7.70 E+00 l FW HEATER STAIRWAY R E-2 l1.40 E+ 01 l PILGRIM ~ 28-MAY-1992 01:00

AMEce No: 5 This is a Drill Page 5-72 This is a Drill 1

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l 92-05B 1992 EE 413 NORMAL AREA RADIATION NORMAL EFFL RAD MSL RAD AREA RAD NORMAL NORMAL NORMAL a

AREA (HI R ANGE) INSTR NO. R/HR AREA INSTR NO. MR/HR

! DRYWELL A RIT1001-606 A [4.60E+00l . NEW FUEL RACKS R E-12 l2.00E-01 l DRYWELL B - RIT1001-606B R E-11 l4.50E+00l REFUEL FLR-NEW FUEL VAULT l5.00E-01 l TORUS A RIT1001-607 A

, l0.00E+00l REFUEL FLR-SPENT FUEL POOL R E-14 l1.00 E+ 01 l TORUS B l RIT1001-6078 [0.00E+00l REFUEL FLR-SMIELD PLUG R E-13 l1.00 E + 00 l AREA INSTR NO. MR/HR f MAIN CONTROL ROOM R E-3 l0.00E+00l . RADWASTE SUMP R E-6 l8.99 E+ 01 l i

MAIN CONTROL ROOM INTAKE RM-1705-16l0.00E+00l RADWASTE CHEM WST REC TANK RE-7 l5.40 E+ 00 l n

! RX BLDC OUTSIDE TIP RM R E-8 R E-5 l2.60 E+ 00 l l1.00E-01 l RADWASTE CORRIDOR RXBLDG ACCESS-SE R E-10 RE-9 l7.00 E-01 l l4.00E+00l RADWASTE SHIPPING DOCK

j. TURB BLDG COND PMP STAIRWAY RE-1 l1.90 E+00l TURBINE FRONT STANDARD R E-4 l7.40 E+ 00 l i FW HEATER STAIRWAY R E-2 l1.35 E+ 01 l PILGRIM ~ 28-MAY-1992 01:15

! Message No: 6 4

l This is a Drill Page S-73 This is a Drill

92-05B 1992 EE 413 NORMAL AREA RADIATION NORMAL EFFL RAD MSL RAD AREA RAD NORMAL NORMAL NORMAL AREA (HI R ANGE) INSTR NO. R/HR AREA INSTR NO. MRTHR DRYWELL A RIT1001-606 A l4.50E+00l NEW FUEL RACKS R E-12 l2.00E-01 l DRYWELL B RIT1001-6068 l4.40E+00l REFUEL FLR-NEW FUEL VA'6LT RE-11 l5.00 E-01 j TORUS A RIT1001-607 A p.00E+01l l3.00E-01 l REFUEL FLR-SPENT FUEL POOL R E-14 ORUS B RIT1001-607B R E-13 l2.00E-01 l REFUEL FLR-SHIELD PLUG l1 00 E+00l AREA INSTR NO. MR/HR MAIN CONTROL ROOM R E-3 [0.00E+00l RADWASTE SUMP R E-6 l8 99E+01l MAIN CONTROL ROOM INTAKE RM-1705-16l0.00E+00l RADWASTE CHEM WST REC TANK RE-7 l5.40 E+00 ]

RX BLDG OUTSIDE TIP RM R E-8 R E-5 {2.60 E+ 00 l l1.00E-01 l RADWASTE CORAIDOR RE 9 17.00E-01 l RXBLDG ACCESS-SE R E-10 l4.00E+00l RADWASTE SHIPPING DOCK TURB BLDG COND PMP STAIRWAY RE-1 l1.90 E+00 l TURBINE FRONT STANDARD R E-4 l3.50 E+ 00 l FW HEATER STAIRWAY R E-2 [6.40 E+00l PILGRIM -- 28-MAY-1992 01:25 Messano.1!a- 7 This is a Drill Page 5-74 This is a Drill

4 9 2-05 B 1992 EE 413 NORMAL AREA RADIATION NORMAL EFFL RAD MSL RAD AREA RAD ;

NORMAL NORMAL NORMAL j ,

AREA (HI R ANGE) INSTR NO. R/HR AREA INSTR NO. MR/HR i

DRYWELL A RIT1001-606 A l4.60E+00l NEW FUEL RACKS R E-12 l2.00E-01 l DRYWELL B RIT1001-6068 l4.50E+00l REFUEL FLR-NEW FUEL VAULT R E- 11 l5.00E-01 l l i

TORUS A RIT1001-607 A '

l2.00E-01 l REFUEL FLR-SPENT FUEL POOL R E-14 l1.00.E + 01 l t

TORUS B RIT1001-6078 l2.00E-01 l REFUEL FLR-SHIELD PLUG R E-13 l1.00 E +00]

i AREA INSTR NO. MR!HR MAIN CONTROL ROOM R E-3 l0.00E+00l RADWASTE SUMP RE-6 l8.99 E + 01 l MAIN CONTROL ROOM INTAKE RM-1705-16l0.00E+00l RADWASTE CHEM WST REC TANK RE-7 [5.40 Es00 ,

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DRYWELL A RIT1001-606 A [3.COE+00l NEW FUEL RACKS R E-12 l2.00 E-01 l DRYWELL 8 RIT1001-60SB l3.30E+00l REFUEL FLR-NEW FUEL VAULT R E-11 l3.00E-01 l TORUS A RIT1001-607 A l5.00E-01 j REFUEL FLR-SPENT FUEL POOL R E- 14 l1.00 E+01 ) .

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RIT1001-607B l5.00E-01 l REFUEL FLR-SH! ELD PLUG R E-13 l1.00 E+00 l AREA INSTR NO. MR/HR

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1992 EE 92-058 NOnual 413 Honu^' AREA RADIATION EFFL RAD MSL RAD I AREA RAD NORMAL NORMAL jfNORMAL INSTR NO. R/HR AREA INSTR NO. MRMR AREA (HI RANGE)

RIT1001-606 A R E-12 l2.00E-01 l DRYWELL A {3.10E+00) NEW FUEL RACKS DRYWELL B RIT1001-6068 l3.00E+00l REFUEL FLR.NEW FUEL VAULT R E- 11 l5.00E-01 l TORUS A RIT 1001-607 A [5.00E-01 l REFUEL FLR-SPENT FUEL POOL R E-14 l1.00 E + 01 ]

TORUS B RIT1001-607 B [4.00E-01 l REFUEL FLR-SHIELD PLUG R E- 13 l1.00 E+ 00j AREA INSTR NO. MRHR R E-3 RE-6 l8.99 E + 01 )

MAIN CONTROL ROOM [0.00E+00l RADWASTE SUMP R M-1705-16%.00 E + 00 j RADWASTE CHEM WST REO TANK RE-7 l5.40 E + u D]

MAIN CONTROL ROOM INTAKE CORRIDOR RE-5 l2.60 E + 00 l RX CLOG OUTE!DE TIP RM RE-8 l1.00E-01 l RADWASTE R E-9 l7.00E-01 l RXBLOG ACCESS-SE R E-10 l4.00E+00l RADWASTE SHIPPING DOCK TURB BLDG COND PMP STAIRWAY RE-1 l1.80 E +00 l l

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FW HEATER STAIRWAY RE-2 l4.40 E +00 l PiLGR!M . MAY 1992 02:00 Messac_1fo: 10-l Pa;:e S-77 This is a Drill This is a Drill ri ssgygge

92-05B 1992 EE 413 Non"^' AREA RADIATION anuAt i

EFFL RAD MSL RAD AREA RAD NORMAL NORMAL NORMAL i

AREA (HI RANGE) INSTR NO. R!HR AREA Q'HTR NO. MRtHR DRYWELL A RIT1001-606 A l2.90E+00] NEW FUEL RACKS R E- 12 l2.00E-01 l DRYWELL B RIT1001-6060 R E-11 l2.80E+00] REFUEL FLR-NEW FUEL VAULT l5.00E-01 l TORUS A FilT1001-607 A j4.0CrE-01 l REFUEL FLR-SPENT FUEL POOL RE-14 l1.00 E+0i]

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i AREA (HI R ANGE) INSTR NO. R/HR AREA INSTR NO. MR/HR ;

DRYWELL A RIT1001-606 A l2.30E+00l NEW FUEL RACKS RE-12 l2.00E-01 l l t

DRYWELL B RIT1001-606B l2.20E+00l REFUEL FLR-NEW FUEL VAULT RE-11 l5.00E-01 l TORUS A RIT 1001-607 A l2.00E-01 l REFUEL FLR-SPENT FUEL POOL RE-14 l1.00 E+ 01 l TORUS B RIT1001-607B R E- 13 l2.00E-01 l REFUEL FLR-SHIELD PLUG l1.00 E +00 l ;

1 AREA INSTR NO. MR/HR ;

i MA!N CONTROL ROOM R E-3 l0.00E+00l RADWASTE SUMP R E-6 [8.99 E+ 0i j i

MAIN CONTROL ROOM IHTAKE RM-1705-16[0.00E+00j RADWASTE CHEM WST REC TANK RE-7 l5.40 E+00 ]

R E-8 R E-5 l2.60 E + 00 l RX BLDG OUTSIDE TIP RM lU.00E-01 l RADWA3TE CORRIDOR 9XBLDG ACCESS-SE RE-10 l4.00E+00l RADWASTE SHIPPING DOCK RE-9 l7.00E-01 l f!

TURB BLDG COND PMP STAIRWAY RE-1 l1.80E+00 [ !

TURDINE FRONT STANDARD R E-4 j l2.70 E+ 00 l t FW HEATER STAIRWAY R E-2 l4.90 E+ 00 l PILGRIM -- 28.MAY-1992 03:00

Messacolo:- 14 !

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This is a Drill PaEe 5-81 This is a Drill

I i

92-05B 1992 E2 '!

413 NORMAL AREA RADIATION NORMAL

! EFFL RAD MSL RAD AREA RAD -

NORMAL ; NORMAL NORMAL.

' AREA (HI RANGE) INSTR NO. R/HR AREA INSTR NO. MR/HR l DRYWELL. A RIT1001-606 A l2.20E+00l NEW FUEL RACKS R E-12 i l2.00E-01 l

! DRYWELL B RIT1001-6068

- l2.10E+00l REFUEL FLR-NEW FUEL VAULT R E- 11 [5.00E-01 l TORUS A' RIT2001-607A

- l2.00E-01 l REFUEL FLR-SPENT FUEL POOL R E-14 l1.00 E+ 01 l TORUS B RIT1001-607 B l1.00E-01 l REFUEL FLR-SHIELD PLUG R E-13 [1.00 E+00l l

AREA INSTR NO. MR/HR l MAIN CONTROL ROOM R E-3 l0.00E+00l RADWASTE SUMP R E-6 i l8.99 E + 01 l i

'! MAIN CONTROL ROOM INTAKE ' RM-1705-16l0.00E+00l RADWASTE CHEM WST REC TANK RE-7 l5.40 E+ 00 l t

RX BLOG OUTSIDE TIP RM R E-8 l1.00E-01 l RADWASTE CORRIDOR R E-5 l2.60 E+ 00 l RXSLDG ACCESS-SE R E-10 R E-9 l7.00E-01 l l4.00E+00l RADWASTE SHiPP!NG DOCK i

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l2.90 E+00l t FW HEATER STAIRWAY R E-2 l5.20 E+ 00 l PILGRIM MAY-1992 03: 15 I Message No: 15 t

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This is a Drill Page 5-82 This is a Drill !

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!92-058 1992. EE 1

413 _

Non"^' AREA RADIATION NORMAL EFFL RAD MSL RAD AREA RAD !

o- NORMAL NORMAL NORMAL' ~

1

-l AREA (HI R ANGE) INSTR NO. R/HR AREA INSTR NO. MR/HR i

! . DRYWELL A RIT1001-606 A l2.20E+00l NEW FUEL RACKS R E-12 [2.00E-01 l 4

DRYWELL B RIT1001-606B' l2.10E+00l REFUEL FLR-NEW FUEL VAULT R E-11 j '

[5.00E-01 l l l

l TORUS A RIT1001-607A - l2.00E-01 l . REFUEL FLR-SPENT FUEL POOL R E-14 l1.00 E+ 01 l TORUS B

{' RIT1001-607B l'3.00E-01 l REFUEL FLR-SHIELD PLUG R E-13 l1.00 E+00 l t=

i ALR EA INSTR NO. MR/HR i

{. MAIN CONTROL ' ROOM R E-3 l0.00E+00l .. R ADWASTE SUMP R E-6 [8.99 E+ 01 l MAIN CONTROL . ROOM INTAKE RM-1705-16l0.00E+00l RADWASTE CHEM WST REC TANK RE-7 l5.40 E+00 l l RX BLDG OUTSIDE TIP RM R E-8 R E-5 l2.60 E+ 00 l l1.00E-01 l RADWASTE CORRIDOR R E-9 l7.00 E-01 l RXBLDG ACCESS-SE RE-10 l4.00E+00l RADWASTE SHIPPING DOCK TURB BLDG COND PMP STAIRWAY RE-i l1.90 E+00 l l TURBINE FRONT STANDARD R E-4 l4.00 E+ 00 l J

FW HEATER STAIRWAY R E-2 l7.40 E+00] PILGRIM -- 28-MAY-1992 03:20

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92 05B 1992 EE 413 Honu^' I AREA RADIATION mRMALi EFFL RAD MSL RAD AREA RAD NORMAL i NORMAL NORMAL AREA (HI R ANGE) INSTR NQ R/HR AREA INSTR NO. MR/HR DRYWELL A RIT1001-606 A l2.00E+00l NEW F'JEL RACKS R E-12 l2.00E-01 l DRYWELL 5 RIT1001-6068 l1.90 E + 00 j REFUEL FLR.NEW FUEL t.'?838.T R E-t 1 l5.00E-01 l TORUS A RIT1001-607 A l1.00E-01 l REFUEL FLR-SPENT FUL; POOL R E-14 l1.00 E + 01 l ToRW D RIT 1001-6079 l1.05E-01 j REFUEL FLR-SHIELD PLUG RE-13 l1.00 E + 00 l AREA INSTR NO. MR/HR MAIN CONTROL ROOM RE-3 [0.00E+00l RADWASTE SifMP R E-S l8.99 E + 01 ]

MAIN CONTROL ROOM INTAKE RM.1705-16l0.00E+00l RADWASTE CHEM WST REC TANK RE-7 l5.40 E + 00 l RX DLDG OUTSIDE TIP RM RE-8 R E-5 l2.60 E+ 00 l l1.00E-01 l RADWASTE CORRIDOR R E-9 l7.00E-01 l RXBLDG ACCESS-SE R E-10 l4.00E+00l RADWASTE SHIPP NG DON TURB BLDG COND PMP STAIRWAY RE-1 l1.90 E+ 00 l TURBINE FRONT STANDARD R E-4 l3.10 E +00 l FW HEATER STAIRWAY RE-2 l5.70 E +00 l PILGRIM -- 28-MAY-1992 03:30 M e m ce_M o: 17 This is a Drill Page 944 This is a Drill

92-058 1992 EE

413 NORMAL AREA RADIATION enu^t I

EFFL RAD MSL RAD IAREA RAD $

NORMAL NORMAL l NORMAL l AREA (HI RANGE) INSTR NO. RIHR AREA INSTR _ NO. MR/HR ORYWELL A RIT1001-606 A l1.90E+00l NEW FUEL HACKS R E-12 l2.00E-01 l DRYWELL 0 RIT1001-6068 R E-11 l1.80E+00l REFUEL CLR NEW FUEL VAULT [5.00E-01 l TORUS A RIT1001-607 A l1.00E-01 l REFUEL FLR-SPENT FUEL POOL R E-14 l1.00 E v 01 l ORUS B RIT 1001-607 8 l1.00E-01 l REFUEL FLR-SHIELD PLUG RE13 l1.00 E + 00 l AREA INSTR NO. MR/HR MAIN CONTROL ROOM RE-3 l0.00E+00l nADWASTE SUMP R E-6 l8.9 9 E + 01 l MAIN CONTROL ROOM INTAK6 RM-1705-ts[0.00E+00l RADWASTE CHEM WST REC TANK RE-7 l5.40 E + 00 l RX BLDG OUTSIDE TIP RM R E-3 RE-5 l2.60 E + 00 l l1.00E-01 l RADWASTE CORRIDOR RXBLDG ACCESS-SE R E-10 R E-9 l7.00E-01 l l4.00E+00l RADWASTE SHIPPING DOCK TURD DLDG COND PMP STAIRWAY RE-1 l1.90 E+00 l TURBINE FRONT STANDARD RE-4 l2.80 E + 00 l FW HEATER STAIRWAY R E-2 l5.10 E + 00 l PILGRIM .- 28--M AY-1992 03:45 Messagelin: 18 This is a Drill Page 5-85 This is a Drill

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i 413 NORMAL AREA RADIA + y ' NORMAL' EFFL RAD MSL RAD - J' b-NORMAL _

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AREA (HI R ANGE) INSTR NO. R/HR AREA __ _ INSTR NO. MR/HR DRYWELL A . RIT1001-606 A l1.80E+ 00l NEW FUEL HACKS R E-12 l2.00E-01 l i

. DRYWFLL B RIT1001-6068 ~ R E-11

-[1.70E+00l REFUEL FLR-NEW FUEL VAULT l5.00E-01 l !

TORUS A ' RIT1001-607 A l1.00E-01 l REFUEL FLR-SPENT FUEL. POOL R E- 14 l1.00 E + 01 l TORUS B RIT1001-6078 l1.00E-01 l REFUEL FLR. SHIELD PLUG RE-13 l1.00 E + 00 l AREA INSTR NO. MR/HH i MAIN CONTROL ROOM RE-3 [0.00E+00l RADWASTE SUMP R E-6 l8.99 E+ 01 l MAIN CONTROL ROOM INTAKE RMo1705-16l0.00E+00l RADWASTE CHEM WST REC TANK RE-7 . l5.40E +00 l RX BLDG OUTSIDE TIP RM R E-8 R E-5 l2.60 E+ 00 l l1.00E-01 l RADWASTE CORRIDOR R E-9 l7.00E-01 l RXBLDG ACCESS-SE RE-10 l4.00E+00l RADWASTE SHIPPING DOCK TURB BLDG COND PMP STAIRWAY RE-1 l1.80 E+ 00 l .

TURBINE FRONT STANDARD R E-4 l2.20 E+ 00 l -[

FW HEATER STAIRWAY R E-2 l4.00 E+ 00 l PILGRIM .28-MAY-1992 04:00

flusage_Mo: 19 i

This is a Drill Page 5 86 This is a Drill

1992 EE 92-05B CNTMT NORMAL f

i 111 RPV NORMAL EFFLUENT RADIATION EFFL RAD NORMAL l

UNITS VENT INSTR NO. UNITS VENT INSTR NO.

l STACK GAS #1 RM-1705-18 A l7.06E+01 l CP S RX BLDG EXH VENT A R M-1705-32 A [3.77 E +01 l C PS RM-1705-188 l6.99 E+01 l CPS RX BLDG EXH VENT B R M-1705-32 B [3.77 E + 01 l C P S STACK GAS #2 MAIN STACK GAS RT-1001-608 l0.00E+00l RIHR RX BLDG EXH VENT RT-1001-609 l0.00E+00l R/HR REFUEL FLR VENT EXH A R M-1705-8 A l6.00 E+00l MR/HR RADWASTE EFFLUENT RM-1705-30 l4.00 E+03 l CPS REFUEL FLR VENT EXH B R M-1705-8 8 l4.00 E+00l MR/HR TURB BLDG ROOF FAH RT-1001-610 l0.00E+00l R RM-1705-9 l3.00E+00l MR/HR REFUEL FLR VENT EXH C RM-1705-8C l2.00 E + 00 l MR/HR SBGT DISCHARGE REFUEL FLR VENT EXH D RM-1705-80 l2.00E+00j MR/HR REFUEL FLR VENT EXH l NORMAL l I

PILGRIM MAY-1992 00:00 l

Page 5 87 This is a Drill gessage no: 1

92-050 1992 EE 111 RPV NORMAL j EFFLUENT RADIATION CNTMT NORMAL EFFL RAD NORMAL VENT __ INSTR NO. UNITS VENT INSTR NO. UNITS STACK GAS #1 RM-1705-18 A l6.91 E+01 l C PS RX BLDG EXH VENT A RM-1705-32 A l3.77 E+01 l CPS iTACK GAS #2 RM-1705-180 [6.84 E+01 l CPS RX BLDG EXH VENT D RM- 6 705-328 l3.77E+01 l Cos MAIN STACK GAS RT-1001-608 l0.00E+00l R/HR RX BLDG EXH VENT RT-1001-609 l0.00E+00l R/HR REFUEL FLR VENT EXH A R M-1705-8 A l6.00E+00l MRiHR RADWASTE EFFLUENT RM-1705-30 l4.00 E +03 l C PS REFUEL FLR VENT EXH B R M-1705-8 B l4.00E+00l MR/HR TURB BLDG ROOF EXH RT-1001-610 l0.00E+00l R/HR REFUEL FLR VENT EXH C RM-1705-8C l2.00 E+00l MRIH R SBGT DISCHARGE RM-1705-9 l3.00E+00l MR/HR REFUEL FLR VENT EXH D R M-1705-80 l2.00 E+ 00l MR/H R REFUEL FLR VENT EXH l NORMAL l PILGRIM - 28-MAY-1992 00:15 Messace_No: 2 Page 5-38 This is a Drill

1992 EEL 92-05B RPV NORMAL' EFFLUENT RADIATION CNTMT NORMAt

111 ,

i i

EFFL RAD NORMAL VENT INSTR NO. -. UNITS VENT INSTR NO. UNITS STACK GAS #1 RM-1705-18 A l6.72E+01 l CPS RX BLDG EXH VENT A RM-1703-32 A l3.77E+01 l CPS l STACK GAS #2 RM-1705-188 l6.65E+01 l CPS RX BLDG EXH VENT B RM-1705-32B l3.77E+01 l CPS '!

MAIN STACK GAS RT-1001-608 l0.00E+00l RIHR RX BLDG EXH VENT ' RT-1001 609 l0.00E+00l RIHR i

i l REFUEL FLR VENT EXH A R M-1705-B A l6.00 E+00l MRIHR RADWASTE EFFLUENT RM-1705-30 l4.00E+03l CPS :

REFUEL FLR VENT EXH B RM-1705-8B [4.00E+00l MR/HR TURB BLDG ROOF EXH RT-1001-610 l0.00E+00l RIHR REFUEL FLR VENT EXH C RM-1705-8C l2.00E+00l MR/HR SBGT DISCHARGE R M-1705-9 l3.00E+00l MRIHR i

REFUEL FLR VENT EXH D R M-1705-8 D l2.00 E+00l MRIHR j REFUEL FLR VENT EXH l NORMAL l PILGRIM - 26-MAY-1992 00:30 i r

i

-t Message No: 3 Page 5-89 This is a Drill

92-058 1992 EE 111 RPV NORMAL EFFLUENT RADIATION cnTMT nonMat EFFL RAD NORMAL VENT INSTR NO. UNITS VENT INSTR NO. UNITS STACK GAS #1 RM-1705-18 A l5.89 E+01 l CP S RX BLDG EXH VENT A RM-1705-32 A l3.67E+01 l CPS STACK GAS #2 RM-1705-188 l5.83E+01l CPS RX DLDG EXH VENT B RM-1705-320 l3.67E+01l CPS MAIN STACK GAS RT-1001-606 [0.00E+00l R/HR RX BLDG EXH VENT RT-1001-609 l0.00E+00l R/HR REFUEL FLil VENT EXH A R M-1705-8 A l6.00E+00l MR/HR RADWASTE EFFLUENT RM-1705-30 l4.00 E+03l CPS REFUEL FLR VENT EXH B R M-1705-8 B l4.00E+00l MRIHR TURB BLDG ROOF EXH RT-1001-610 [0.00E+00l R/HR REFUEL FLR VENT EXH C RM-1705-8C l2.00 E+00l MR/H R SBGT DISCHARGE RM-1705-9 l3.00 E+00l MR/HR REFUEL FLR VENT EXH D R M-170 5-B D l2.00 E+ 00 l MR/HR REFUEL FLR VENT EXH l NORMAL l PILGRIM --- 28.M AY-1992 00:45 MejliSage_f{0: 4 Page 5-90 This is a Drill

92-05B 19'92 : EE' RPV NORMAL 111- EFFLUENT RADIATION CNTMT NORMAL EFFL' RAD 5 NORMAL VENT INSTR NO. ' UNITS VENT INSTR NO. UNITS STACK GAS #1 R M-1705-18 A l4.89 E+01 l C P S RX BLDG EXH VENT A RM-1705-32 A l3.51 E+01 l CPS !

STACK GAS #2 RM-1705-188 [4.84 E+01 l CPS RX BLDG EXH VENT B RM-1705-32B l3.51 E+01 l CPS i

MAIN STACK GAS RT-1001-608 l0.00E+00l R/HR RX BLDG EXH VENT RT-1001-609 l0.00E+00l R/HR REFUEL FLR VENT EXH A 'R M-1705-8 A [6.00E+00l MR/HR RADWASTE EFFLUENT RM-1705-30 -l4.00E+03l CPS I

REFUEL FLR VENT.EXH B RM-1705-88 l4.00 E+00l MR/HR TURB BLDG ROOF EXH RT-1001-610 l0.00E+00l R/HR ;

REFUEL FLR VENT EXH C RM-1705-8C , l2.00E+00l MR/HR SBGT DISCHARGE RM-1705-9 l3.00E+00l MR/HR i

REFUEL FLR VENT EXH D R M-1705-8 D l2.00 E+ 00 l MR/H R I

i REFUEL FLR VENT EXH l NORMAL l i

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PILGRIM .. 28-MAY-1992 01:00 4

Message No: 5 Page 5 91 This is a Drill-

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92-050 1992 EE 111 RPV NORMAL EFFLUENT RADIATION CNTMT NORMAL I

EFFL RAD NORMAL VENT INSTH NO. UNITS VENT INSTIL NO. UNITS _

STACK GAS #1 RM-1705-1S A l4.66E+01 l CPS RX BLDG EXH VENT A RM-1705-32 A l3.48 E+01 l CPS STACK GAS #2 RM-1705-188 l4.61 E+01 l CPS RX BLDG EXH VENT B RM-1705-328 l3.48E+01 l CPS MAIN STACK GAS RT-1001-608 l0.00E+00] R/HR RX BLDG EXH VENT RT-1001-609 l0.00E+00l R/HR REFUEL FLR VENT EXH A R M-1705-8 A l6.00E+00l MR/HR RADWASTE EFFLUENT RM-1705-30 l4.00 E+03 l CPS REFUEL FLR VENT EXH B RM-1705-8B l4.00E+00l MR/HR TURB BLDG ROOF EXH RT-1001-610 l0.00E+00l R/HR REFUEL FLR VENT EXH C R M-1705-8 C l2.00 E+00 l MR/H R SBGT DISCHARGE R M-1705-9 l3.00 E+00 l MR/HR REFUEL FLR VENT EXH D R M-1705-8 D l2.00 E+00 l MR/H R REFUEL FLR VENT EXH l NORMAL l PILGRIM 28-M AY-1992 01:15 Messace_Ho: s Page 5-92 This is a Drill

92-05B 1992 EE 111 RPV NORMA'. EFFLUENT RADIATION CNTMT NORMAL EFFL RAD NORMAL VENT INSTR NQ. UNITS VENT INSTR NO. UNITS STACK GAS #1 RM-1705-18 A l4.83E+01 l CPS RX BLDG EXH VENT A RM-1705-32 A l2.04 E+01 l CPS STACK GAS #2 RPJ-1705-188 l4.71 E+01 l CP S RX BLDG EXH VENT B RM-1705-32 8 l2.04 E+01 l CPS MAIN STACK GAS RT-1001-608 l0.00E+00l R/HR RX DLDG EXH VENT RT-1001-609 [0.00E+00l R/HR REFUEL FLR VENT EXH A R M-1705-8 A l6.00E+00l MR/HR RADWASTE EFFLUENT RM-1705-30 l4.00 E+03 l CPO REFUEL FLR VENT EXH D R M-1705-8 B [4.00E+00l MR/HR TURB BLDG ROOF EXH RT-1001-610 l0.00E+00l R/HR REFUEL FLR VENT EXH C R M-1705-8 C l2.00 E+00l MR/HR SBGT DISCHARGE R M-1705-9 l3.00E+00l MR/HR REFUEL FLR VENT EXH D R M-1705-8 D l2.00 E+00 l MR/H R REFUEL FLR VENT EXH I NORMAL l PILGRIM M AY-1992 01:25 McSSage No: 7 Page 5-93 This is a Drill

92-058 1992 EE 111 RPV NORMAL EFFLUENT RADIATION CNTMT NORMAL EFFL RAD NORMAL VENT INSTR NO. UNITS VENT INSTR NO. UNITS STACK GAS #1 RM-1705-18 A l5.45 E+01 l C PS RX BLDG EXH VENT A RM-1705-32 A l3.19 E+01 l CPS STACK GAS #2 RM-1705-188 l5.40E+01l CPS RX BLDG EXH VENT B RM-1705-328 l3.19 E+01 l CPS MAIN STACK GAS RT-1001-608 l0.00E+00l R/HR RX BLDG EXH VENT RT-1001-609 l0.00E+00l R/HR REFUEL FLR VENT EXH A R M-1705-8 A l6.00E+00l MR/HR RADWASTE EFFLUENT RM-1705-30 l4.00 E+03 l CPS REFUEL FLR VENT EXH B R M-1705-8 B l4.00E+00l MR/HR TURB BLDG ROOF EXH RT-1001-610 l0.00E+00l R/HR REFUEL FLR VENT EXH C RM-1705-8C . l2.00E+00l MRIHR .SBGT DISCHARGE R M-1705-9 l3.00 E+00l MR/HR REFUEL FLR VENT EXH D R M-1705-8 D l2.00 E+00l MR/HR REFUEL FLR VFNT EXH l NORMAL l 1

PILGRIM - 28-MAY-1992 01:30 MCS$ age No: s Page 5-94 This is a Drill

92-058 .1992. EE

.111

'RPV, NORMAL EFFLUENT RADIATION CNTMT' NORMAL l

EFFL RAD ,

NORMAL. !

1 VENT INSTR NO. UNITS' VENT INSTR NO. UNITS

, STACK GAS #1 RM-1705-18A l3.37E+01l CPS RX BLDG EXH VENT A RM-1705-32 A l1.76 E+01 l CPS !

STACK' GAS #2 RM-1705-18B l3.34E+01 l CPS RX BLDG EXH VENT B RM-1705-32B l1.76 E+01 l CPS .

MAIN STACK GAS RT-1001-608 l0.00E+00l R/HR RX BLDG EXH VENT RT-1001-609 l0.00E+00 j R/HR HEFUEL FLR VENT EXH A R M-1705-8 A l6.00E+00l MR!HR RADWASTE EFFLUENT HM-1705-30 l4.00 E+03 l CPS .

REFUEL FLR VENT EXH B R M-1705-8 P l4.00E+00l MR/HR TURB BLDG ROOF. EXH RT-1001-610 l0.00E+00l R/HR REFUEL FLR VENT EXH C R M-1705-8 C l2.00 E +00] MR/H R SBGT DISCHARGE R M-1705-9 l3.00E+00l MR/HR REFUEL FLR VENT EXH D RM 1705-8D ' l2.00E+00l MR/HR REFUEL FLR VENT EXH 'l NORMAL l i t PILGRIM 28-MAY-19 2 01:45 i l

MES3aQe No: 9 Page 5-95 This is a Drill t

92-05B 1992 EE t

111 RPV NORMAL EFFLUENT RADIATION CNTMT NORMAL EFFL RAD NORMAL VENT INSTR NO. UNITS VENT INSTR NO. UNITS STACK GAS #1 RM-1705-18 A l2.14 E+01 l C P S RX BLDG EXH VENT A RM-1705-32A l1.77E+01l CPS STACK GAS #2 RM-1705-188 l2.12E+01 l CPS RX BLDG EXH VENT B RM-1705-32B l1.77E+01 l CPS MAIN STACK GAS RT-1001-608 l0.00E+00l R/HR RX BLDG EXH VENT RT-1001-609 l0.00E+00l R/HR I

REFUEL FLR VENT EXH A R M-1705-8 A l6.00 E+00 l MR/HR RADWASTE EFFLUENT RM-1705-30 [4.00 E+03 l CP S REFUEL FLR VENT EXH B R M-1705-5 B l4.00E+00l MR/HR TURB BLDG ROOF EXH RT-1001-610 l0.00E+00l R/HR !

REFUEL FLR VENT EXH C RM-1705-8C l2.00 E+ 00l MR/HFI SBGT DISCHARGE R M-1705-9 l3.00 E+00l MR/HR REFUEL FLFI VENT EXH D R M-1705-8 D l2.00 E+00 l MR/H R ,

REFUEL FLR VENT EXH l NORMAL l t

PILGRIM --- 28-MAY-1992 02:00 i

MtS3 age No: 10 Page 5-96 This is a Drill !

h 92-050 1992 EE 111 RPV NORMAL EFFLUENT RADIATION CNTMT' NORMAL EFFL RAD i NORMAL VENT INSTR HO. UNITS VENT INSTR NO. UNITS STACK GAS #1 RM-1705-18 A l1.91 E+01 l CPS RX BLDG EXH VENT A RM-1705-32A l1.75E+01l CPS STACK GAS #2 RM-1705-188 l1.89E+01 l CPS RX BLDG EXH VENT E RM-1705-32B l1.75E+01l CPS l.

MAIN STACK GAS RT-1001-608 l0.00E+00l R/HR RX BLOG EXH VENT RT-1001-609 l0.00E+00l R/HR REFUEL FLR VENT EXH A R M-1705-8 A l6.00E+00l MR/HR RADWASTE EFFLUENT RM-1705-30 l4.00 E+03l CPS !

REFUEL FLR VENT EXH B R M-1705-8 B l4.00E+00l MR/HR TURB BLDG ROOF EXH RT-1001-610 l0.00E+00l R/HR REFUEL FLR VENT EXH C RM-1705-8C l2.00 E + 00 l MR/H R SBGT DISCHARGE RM-1705-9 l3.00E+00 l Mri/HR REFUEL FLR VENT EXH D R M-1705-8 D l2.00 E+ 00l MRIHR ;

REFUEL FLR VENT EXH l NORMAL l i

PILGRIM 28-MAY-1992 02:15 I

i l

I Messa2e No 11 Page 5-97 This is a Drill '

t

92-058 1992 EE RPV NORMAL 111' EFFLUENT RADIATION CNTMT NORMAL _

s EFFL RAD NORMAL VENT INSTR NO. UNITS VENT INSTR NO. UNITS STACK GAS #1 RM-1705-16 A l1.16 E+01 l C P S RX BLDG EXH VENT A RM-1705-32A l2.88E+01l CPS STACK GAS #2 RM-1705-18B l1.15E+01] CPS RX BLDG EXH VENT B RM-1705-328 l2.88 E+01 l CPS MAIN STACK GAS RT-1001-608 l0.00E+00l R/HR RX BLDG EXH VENT RT-1001-609 l0.00E+00l R/HR REFUEL FLR VENT EXH A R M-1705-8 A l6.00 E+00l MR/HR RADWASTE EFFLUENT RM-1705-30 l4.00E+03l CPS REFUEL FLR VENT EXH B H M-1705-8 B l4.00E+00l MRIHR TURB BLDG ROOF EXH RT-1001-610 l0.00E+00l R/HR REFUEL FLR VENT EXH C RM-1705-8C l2.00 E+00 l MR/MR SBGT DISCHARGE R M-1705-9 l3.00E+00l MRIHR REFUEL FLR VENT EXH D R M-1705-8 D l2.00 E+00l MR/HR REFUEL FLR VENT- EXH l NORMAL l PILGRIM -- 28-MAY-1992 02:30 Message _Ro: 12 Page 5-98 This is a Drill

92-05B 1992 EE 111 RPV NORMAL Ei FLUENT RADIATION CNTMT NORMAL i

,n EFFL AAD NGRMAL VENT INSTR NO. UNITS VENT INSTR NO. UNITS t

STACK GAS #1 RX BLDG EXH VENT A RM-1705-18 A Q. ',1 E+01 l C P S RM-1705-32 A l2.94 E+01 l CPS STACK GAS #2 RM-1705-180 l1.40E+01 l CPS RX BLDG EXH VENT B RM-1705-328 l2.94 E+01 l CPS .

MAIN STACK GAS RT-1001-608 l0.00E+00} R/HR RX BLDG EXH VENT RT-1001-609 l0.00E+00l R/HR REFUEL FLR VENT EXH A R M-1705-8 A l6.00E+00l MR/HR RADWASTE EFFLUENT RM-1705-30 l4.00 E+03 l CPS REFUEL FLR VENT EXH B RM-1705-8B l4.00 E+00 l MR/HR TURB BLDG ROOF EXH RT-1001-610 l0.00E+00l RIHR ,

REFUEL FLR VENT EXH C RM-1705-8C l2.00 E+ 00 l MR/HR SBGT DISCHARGE RM-1705-9 l3.00E+00l MR/HR [

REFUEL FLR VENT EXH D R M-1705-8 D l2.00 E + 00 l MR/H R REFUEL FLR VENT EXH l NORMAL l ,

PILGRIM MAY-1995 02:45 i

i Message No: 13 Page 5-99 This is a Drill I

-t 92-05B 1992. EE ~ ,

111 RPV NORMAL EFFLUENT RADIATION CNTMT NORMAL l

EFFL~ RAD NORMAL

- VENT INSTR NO. UNITS VENT INSTR NO. UNITS STACK GAS #1 RM-1705-18 A l1.40E+01 l CPS RX BLDG EXH VENT A ' RM-1705-32 A l2.92E+01 l CPS STACK GAS #2 RM-1705-18B l1.39E+01l CPS RX BLDG EXH VENT B RM-1705-32B l2.92E+01 l CPS

' MAIN. STACK . GAS ' RT-1001-608 l0.00E+00l R/HR RX BLDG EXH VENT RT-1001-609 l0.00E+00l R/HR REFUEL FLR VENT EXH A R M-1705-8 A l6.00E+00l MR/HR RADWASTE EFFLUENT RM-1705-30 l4.00E+03l CPS i REFUEL FLR VENT EXH B RM-1705-8B l4.00E+00l MR/HR TURB BLDG ROOF EXH RT-1001-610 l0.00E+00l R/HR 4

REFUEL FLR VENT EXH C RM-1705-8C l2.00 E+00 l MR/HR .SBGT DISCHARGE R M-1705-9 l3.00E+00j MR/HR L F". FUEL FLR VENT EXH D R M-1705-8 D l2.00 E+00 l MR/H R REFUEL FLR VENT EXH . l NORMAL l l ;

l PILGRIM 28-MAY-1992 03:00 ,

i

! Messagn.fio: 14 Page 5-100 This is a Drill a .a - .-

92-058 1992 EE 111 RPV NORMAL EFFLUENT RADIATION CNTMT NORMAL EFFL RAD l NORMAL l VENT INSTR NO. UNITS VENT _ INSTR NO. UNITS STACK GAS 41 RM-1705-18 A l1.38 E+01 l CPS RX BLOG EXH VENT A RM-1705-32 A l2.94 E+01 l CPS STACK GAS #2 R M-1705-18 8 l1.37 E+01 l CP S RX BLDG EXH VENT B RM-1705-32B l2.94 E4 01 l CPS MAIN STACK GAS RT-1001-608 l0.00E+00l R/HR RX BLDG EXH VENT RT-1001-609 l0.00E+00l RIHR REFUEL FLR VENT EXH A R M-1705-8 A l6.00 E+00l MR/HR RADWASTE EFFLUENT RM-1705-30 l4.00E+03l CPS REFUEL FLR VENT EXH B R M-1705-8 B l4.00E+00l MR/HR TURB BLDG ROOF EXH RT-1001-610 l0.00E+00l R/HR REFUEL FLR VENT EXH C R M-1705-8 C l2.00 E+ 00 l MR/HR SBGT DISCHARGE R M-1705-9 l3.00E+00l MR/HR REFUEL FLR VENT EXH D RM-1705-8D l2.00 E+00 l MRIHR REFUEL FLR VENT EXH l NORMAL l PILGRIM 28-M AY-1992 03:15 Messane_ffo: 15 Page 5-101 This is a Drill

92-05B 1992. EE 111 RPV NORMAL EFFLUENT RADIATION iCNTMTNORMAL EFFL RAD NORMAL "

VENT INSTR NO. UNITS VENT INSTR NO. UNITS STACK GAS #1 RM-1705-18 A l1.70E+01 l C PS RX BLDG EXH VENT A RM-1705-32 A l1.39E+02l CPS STACK GAS #2 RM-1705-188 l1.69 E+01 l CPS RX BLDG EXH VENT B RM-1705-32B l1.39E+02l CPS MAIN STACK GAS RT-1001-608 l0.00E+00l R/HR RX BLDG EXH VENT RT-1001-609 l0.00E+00l R/HR t

REFUEL FLR VENT EXH A R M-1705-8 A l6.00E+00l MR/HR RADWASTE EFFLUENT RM-1705-30 l4.00E+03l CPS REFUEL FLR VENT EXH B RM 1705-8B l4.00E+00l MR/HR TURB BLDG ROOF EXH RT-1001-610 l0 00E+00l RIHR REFUEL FLR VENT EXH C R M-1705-8 C l2.00 E+00l MR!HR SBGT DISCHARGE R M-1705-9 l3.00E+00l MRIHR REFUEL FLR VENT EXH D RM-1705-8D l2.00E+00j MRIHR REFUEL FLR VENT EXH l NORMAL l PILGRIM 28-M AY-1992 03:20 t

i Message No: 1s Page 5-102 This is a Drill

w-92-05B 1992 : EE 111 RPY: NORMAL EFFLUENT RADIATION CNTMT NORMAL EFFL RAD

' NORMAL VENT INSTR NO. UNITS ' VENT INSTR NO. UNITS STACK GAS #1 RM-1705-18 A l2.06 E+01 l CP S RX BLDG EXH VENT A RM-1705-32 A l4.22E+01l CPS STACK GAS #2 RM-1705-188 l2.04E+01l CPS RX BLDG EXH VENT B RM-1705-32B l4.22E+01,1PS MAIN STACK GAS RT-1001-608 l0.00E+00l R/HR RX BLDG EXH VENT RT-1001-609 l0.00E+00l RIHR REFUEL FLR VENT EXH A R M-1705-B A l6.00 E+ 00l MRIHR RADWASTE EFFLUENT RM-1705-30 l4.00E+03l CPS REFUEL FLR VENT EXH' 8 R M-1705-8 B l4.00E+00l MRIHR TURB BLDG ROOF EXH RT-1001-610 [0.00E+00) R/HR REFUEL FLR VENT EXH C R M-1705-8 C l2.00 E+00l MRlHR SBGT DISCHARGE RM 1705-9 l3.00E+00 l MRIHR 1

REFUEL FLR VENT EXH D RM-1705 BD l2.00 E+00l MR/HR 3

REFUEL FLR VENT EXH l NORMAL l PILGRIM 28-MAY-1992 03:30 Messege No: 17 Page 5-103 This is a Drill-

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. VENT INSTR NO. UNITS VENT INSTR NO. UNITS STACK GAS #1 R M-1705-18 A l1.17 E+01 l C P S RX BLDG EXH VENT A RM-1705-32 A l2.93 E+01 l CPS STACK GAS #2 R M'-1705-18 B (1.16 E+01 l C P S RX BLDG EXH VENT B RM-1705-32B l2.93E+01 l CPS MAIN STACK GAS RT-1001-608 l0.00E+00l R/HR RX BLDG EXH VENT RT-1001-609 l0.00E+00l R/HR .

REFUEL FLR VENT EXH A R M-1705-8 A l6.00E+00l MR/HR RADWASTE EFFLUENT RM-1705-30 l4.00 E+03l CPS .

REFUEL FLR VENT EXH B R M-1705-8 B %00E+00l MR/HR TURB BLDG HOOF EXH RT-1001-610 {.00E+00l R/H REFUEL FLR VENT EXH C' RM-1705-8C ' [2.00E+00 l MR/HR SBGT DISCHARGE RM-1705-9 {3.00E+00l MR/HG REFUEL FLR VENT EXH .D RM-1705-8D l2.00 E+ 00 l MR/H R REFUEL FLR VENT EXH 'l NORMAL l PILGRIM --- 28-MAY-1992 - 04:00 t

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Page 5-106

Section 5.4 -

Count Room Data

92-05s Reactor Ceolant Activity ( Ci/cc) 1992 EE .

Isotope 00:45 01:25 01:30 01:45 02-00 02:15 02-30 02:45 03.00 03:15 03:30 03:45 04:00 Kr43m 4.95E-04 4.06E-04 3.93E-04 2.86E-04 2.60E N 2,37E-04 2.15E-04 1.?6E-04 1.78E-04 1.62E-04 1.48E 04 1.34E44 122E-04 Kr.85m 6.90E-04 5.66E-04 5 59E-04 430E-04 4.14E-04 3.98E-04 3.83E 04 3.68E-04 154E-04 3.41E44 32FE-04 3.16E-04 3.04E-04 Kr-85 1.65E-04 135E-04 1.35E-04 1.00E-04 1.08E-c4 1.08E-04 1.08E-04 1.0BE44 1.08E-04 1.08E-04 1.08E-04 1.0eE-04 1.0eE-04 Kn87 7.02E-04 5.76E-04 5.50E 04 3.84E-04 335E-04 2.92E-04 2,55E-D4 2.22E-04 1.94E-04 1.69E-04 1.47E44 128E-04 1.12E-04 Kr-88 1.48E-03 121 E-03 1.19E-03 8.94E 04 8.40E-04 7.90E-04 7.43E44 6.98E-04 G 56E-04 6.17E 04 520E-04 5.45E-04 5.12E-04 Kr 89 2.51E 02 2.06E-02 6.88E-03 2.05E 04 7.64 E-06 2.85E-07 1.06E-08 3.96E-10 1.47E-11 5 40E-13 2.05E-14 7.63E-15 2.84E-17 Xa-131 m 1.06E-04 8 69E-05 8 69E-05 6 95E-05 6.94E-05 6.94 E-05 6.94E-05 6.93E-05 693E-05 6.92E-05 6.92E-05 6.91 E-05 6,91E-05 Xe-133m 3.48E-04 2.85E-04 2.85E-04 2.27E44 227E-04 226E 04 225E-04 2.24E-04 2.24E-04 223E-04 2.22E-04 221E-04 2215-04 Xe-133 3.29E.02 2.70E-02 2.70E-02 23SE-02 2.15E-02 2.15E-02 2.15E-02 2.14E-02 2.14E-02 2.14E-02 2 t3E-02 2.13E-02 2.13E-02 Xe-135m 126E-03 1.03E-03 8.24E-04 334E 04 1.69E-04 8.58E-c3 4.35E-05 221E 05 1.12E-05 5 67E 06 2.67E-06 . 1.46E-06 7.38E 07 Xe-135 2.90E42 2.45E-02 2.445-02 1.91 E-02 1.08E-02 1.84E-02 18;E-02 177E-02 124E-02 1.71 E-02 1.68E-02 1.64E-02 1.61E-02 Xs-137 2.61 E-02 2.14E-02 8.68E43 4.63E-04 3.00E-05 2 06E-04 123E 07 9.19E-09 6.13E-10 4.09E 11 2 73E-12 1.82E-13 122E.14 Xe-138 3 09E-02 2.53E-02 1.99E-02 7.64E 03 3.C7E43 1.77E-03 8.50E-04 4.c9E-04 196E-Od 9.45E-05 4.54 E-05

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' t 58E-03 1.30E-03 1.27E-03 9.65E44 9.14E-04 8.66E-04 821E-04 7.78E44 7.37E-04 6.62E-04 1-131 6.98G-04 6 27E-04 S.94 E-04 l-132 6 03E-05 4.94E-05 1.10E-05 9.55E-08 1.04E-09 1.13E 11 123E-13 135E-15 1.47E-17 1.60E-19 1.74E.21 1.89E-23 2.06E-25 l-133 9.63E-04 7.90E-04 6.63E44 324E-04 1.97E-04 1.19E44 724E45 4.40E-05 2.67E-05 1.62E-05 9.8iE-06 5.95E-06 3.61 E-06 I-134 1.05E-05 8.6f E46 1.65E-07 938E-13 6.65E-18 4.71 E-23 3 34E-28 237E-33 1.6a E-38 t .19E-43 8.44 E-49 $ 98E-54 424E-59 l-135 3 84E-04 3.15E-04 _ 1 #6E-04 3.00E-05 6 42E-06 133E-06 2.76E-07 5.74E 48 1.19E-08 2 47E-09 5.13E 10 1.06E-10 221E-11 g 3 00E-03 2.46E-03 2.14E-03 1.32E-03 1.12E43 9.87E-04 8.93 E-04 9.22E44 7.64E-09 7.14 E-04 6.71 E-04 633E44 E.96E44 Tehte 5-4.1 This is e Orli! races.107 This is a Dritt

92-05a Turbine Building Air Samples 1992 EE Table $.4 '

ILocation Area A Arca B Area C 03:15- 03:45 N:00! 03:15 03:45 04:00[ 03:15 03:45 04:00 Condensate I-131 1.4 0 E-02 1.69E-03 4.34 E-05 1.12E-02 1.41 E-03 3.39E-05 6.26E-03 1.69E 1.89E-05 Bay 6' l-132 Not Det Not Det Not Get Not Det Not Det Not Det Not Det Not Det Not Det 1-133 2.08E-04 1.61 E-05 2.64 E-07 1.66E-04 1.34E-05 2.06E-07 9.29E-05 1.61 E-06 1.15E-07 1-134 Not Det Not Det Not Det Not Det Not Det Not Det Not Det Not Det Not Det g

-; I-135 1.09 E-08 2.87E-10 1.61 E-12 8.69E-09 2.39E-10 1.26E-12 4.85E-09 2.87E-11 7.01 E-13i Total 1.42E-02 1.71 E-03 4.36E-05 1.14 E-02 1.42E-03 3.42E-05 6.36E-03 1.71 E-04 1.90E-05h Condensato 1-131 1.59E-02 1.88E-03 4.81 E-05

. 1.03E-02 1.22E-03 3.11 E-05 5.24E-03 6.30E-04 1.60E-05i Bay 23' l-132 Not Det Not Det Not Det Not Det Not Det Not Det Not Det Not Det Not Det 1-133 2.36E-04 1.79E-05 2.92E-07 1.53E-04 1.16 E-05 1.89E-07 7.77E-05 5.98E-06 9.75E-08 l-134 Not Det Not Det Not Det Not Det Not Det Not Det Not Det Not Det Not Det i 1-135 1.23E-08 3.19E-10 1.79E-12 7.97E-09 2.07E-10 1.16 E- 12 4.06E-09 1.07E-10 5.96E-134 Total 1.61 E-02 1.90E-03 4.84E-05 1.04 E-02 1.23E-03 3.13 E-05 5.31 E-03 6.36E-04 1.61 E-05 6ndensate 1-131 1.12 E-02 1.32E-03 3.30E-05 7.10E-03 8.55E-04 2.17E-05 1.78E-03 2.07E-04 5.28E-06 Ba T-132 Not Det Not Det Not Det Nct Det Not Det . Not Det Not Det Not Det Not Det

! y 37 i-133 1.66E-04 1.25E-05 2.01 E-07 1.05E-04 8.12 E-06 1.32E-07 2.63E-05 1.96E-06 3.21 E-08 l 134 Not Det Not Det Not Det Not Det Not Det Not Det Not Det Not Det Not Det 1-135 8.69E-09 2.23 E-10 1.23E-12 5.50E-09 1.45E-10 8.06E-13 1.38E-09 3.51 E-11 1.96E _13 4

l Total 1.14 E-02 1.3o6-03 3.32E-05 7.21 E-03 8.63E-04 2.18 E-05 1.80E-03 2.09E-04 5.3] E-06 I

This is a Drlit Page 5-108 This is a Drill

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Section 5.6 Environmental Data

-____-___.______-___________m__m__ ___

Environmental lla.la Environmental and field survey data is not provided in this scenario The release mte is not sufficient to cause field __

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d Page 5-113 4

_ _ _ - - _ _ _ _ _ - - _--

ML20094M628

Contents

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1.0 INTRODUCTION

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1.0 INTRODUCTION

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