ML20077D196
| ML20077D196 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 05/25/1983 |
| From: | Daltroff S PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Allan J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| PROC-830525, NUDOCS 8307260421 | |
| Download: ML20077D196 (285) | |
Text
d.f,2 5' / I5 PHILADELPHIA ELECTRIC COMPANY [
23O1 MARKET STREET P.O. BOX 8699 v v '
PHILADELPHIA. PA.19101 SHIELDS L D ALTROFF eue mce.oouc =
May 25, 1983 Mr. James M. Allan Acting Administrator Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406
Dear Mr. Allen:
Enclosed for your review is the Detailed Scenario for the Peach Bottom A tomic Power Station 1983 Annual Emergency Exercise on June 28, 1983.
A schedule for the exercise week is included in the scenario package. This schedule includes a pre-exercise briefing at 9: 00 a.m., Monday, June 27, 1983, at the PBAPS Information Center. The post-exercise critique is scheduled for Wednesday, June 28, 1983, 9:00 a.m., at the PBAPS Emergency Operations Facility. FEMA /NRC post-exercise critique will be held on Thursday, June 29, 1983, at 3:30 p.m., at the Muddy Run News Center.
l To ensure access by NRC observers to various plant locations, the observers must be properly badged. Please provide a list of NRC observers to facilitate the badging process. This list will be used to authorize access to the PBAPS protected area.
Please forward the requested list of observers to K.W. Schlecker. Should you have any questions concerning the scenario or schedule, please contact R.A. Kankus at (215) 841-5432.
Very truly yours
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- i b Enclosure "l
cc: A.R. Blough, Site Inspector h 0
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- Exercise Manual ,
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Peach Bottom. Atomic Power Station ;
! NRC/ FEMA Observed Emergency Response Exercise 2
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,5 EXERCISE MANUAL
() PEACH B01 TOM ATOMIC POWER STATION NRC/FEMAOBSERVEDEMERGENCYRESPONSEEXERCISE JUNE 28, 1983-TABLE.0F CONTENTS SECTION 1.0 Exercise Week Schedule 2.O~ Exercise Objectives 2.1 PEco 2.2 Pennsylvania 23 Maryland 30 Exercise Guidelines and Scope 31- -Guidelines 32 Scope O 33 Participating Centers V- 3.4 Player Instructions 4.0 Controller /EvaluatorInformation-h.1 Assignments 4.2 Instructions
.h.3 Evaluation Sheets 5.0 Exercise Scenario .
5.1- Initial Conditions
- 5. 2 Scenario Abstract- '
5.3 Detailea' Scenario 5.4 -Scenario Time Line A
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. 6.0 . Scenario Data .
46.1 Messages. .
-L6.2 Headquarters Support Requests .
6.3 ' Plant and' Reactor System Values !
- 7 01 Radiological' Data i' '
71 'P1' ant Monitoring Data- !
'7 2 Chemistry Sample Data 73: Main Stack Samplo Data 7 . 14 3
Release Data-n 7.5 Field Monitoring Data
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77 In-Plant Radiation Levels Site and Field Monitoring Maps
. 8.0' References i
i 8.1 Documents 8.2 Maps L:
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SECTION 1
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Exercise Week' Schedule 1.1 on-site Controller / Evaluator Briefing Date: Monday, June 27, 1983 - -
T.ime: 9:00 a.m. ,
Locations -PBAPS Information Center 3 .
Purpose:
Pre-Exercise Scenario Briefing PEco Controller / Evaluators
. Attendees:
NRC Observer / Evaluators --
Exercise Visitors Coordinator: G. Gellrich/K. Schlecker ;
1.2 FEMA Observer Briefing Date: Monday, June 27, 1983 .. .,_
Time: 1:30 p.m.
Location: PBAPS.Information Center
Purpose:
Pre-Exercise Briefing Attendees: Federal / State Observers
^< Coordinator: K. Schlecker
- t i 1.3 Exercise ,
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Date: Tuesday, Jun's 28, 1983
- Time: Approximatel'y.5:15 a.m. to 5:00 p.m.
Location: PBAPS Purposes' Radiological Emergency Response B:ercise ~
i Attendees: Site Personnel _
Coordinator: G. Gellrich,, R. Kankus s
1.4 -Exercise Debriefing' ,
Tuesday, June 28,-1983
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Date:
Time: 5:00 p.m. aproximately
- Location: . Emergency Response Facilities Players and Controller / Evaluator Debriefing 4
Purpose ,,
Attendees: PEco Players .
PECo Controller / Evaluators Coordinator: G. Gellrich 1.5 Exercise Critique .
Date:
Wednesday, June 29, 1983 Time: 9:00 a.m.
Location: Emergency Operations Facility ~
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Purposes PEco'Exe'rcise Critique Attendees: PECo Controllers / Evaluators PEco Major Players-NRC Coordinator: G. Gellrich, K. Schlecker 1.7 ~ FEMA /NRC Public Meeting . ...- ;
Date: Wednesday, June 29, 1983 .
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T'imes 3:30 p.m.
Location: . Muddy Run News Cent er ,
Purpose FEMA /NRC Public Statements .
Attendees: FEMA States ..
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PECo Personnel Press ~
Coordinator: W.'Whitesel t .
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e O SECTION 2.1 F_j PHILADELPHIA ELECTRIC COMPANY
' OBJECTIVES FOR THE 1983 NRC/ FEMA OBSERVED PBAPS EXERCISE To demonstrate the radiological emergency preparedness of the Peach Bottom Atomic Power Station (PBAPS), the Philadelphia .
Electric Company (PECo.), the Pennsylvania and Maryland state agencies, and the county and local agencies, an integrated radiological emergency exercise will be conducted. The onsite objectives are as follows:
- 1. Emergency Detection Demonstrate the ability of site personnel to recognize an emergency initiating event, properly characterize and classify the emergency according to the pre-established Emergency Action Levels (EAL).
- 2. Emergency Assessment Demonstrate the ability of site personnel to observe pertinent instrumentation and to assess the nature, the severity, and the consequences of the emergency condition.
- 3. Emergency Classification Demonstrate the ability of site personnel to properly characterize and classify the. emergency according to the pre-established Emergency Action Levels. The demonstration shall include escalation and de-escalation of the emergency classification.
- 4. Emergency Notification and Communication
- a. Demonstrate that onsite a'nd offsite notification of staff and officials, including emergency classification escalation and de-escalation, can be accomplished in a timely manner and that all notification is documented,
- b. Demonstrate the ability to communicate with monitoring teams, rescue parties, and other site personnel as needed.
- c. Demonstrate the ability to alert the public in an effective and timely manner.
- d. Demonstrate that communications among the utility,
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states, and federal agencies is operable and adequate.
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,' e. Demonstrate that messages are transmitted in an accurate
(;j and timely manner; that messages are documented; that status boards are accurately maintained and updated; that appropriate briefings are held and incoming personnel are briefed and updated.
- f. Demonstrate that public information is coordinated between site, State, County, and Federal officials; that there are accurate and timely press releases and briefings; that designated public information personnel -
are impicmenting their procedures.
- 5. Emergency Organization and Facility Activation
- a. Demonstrate the familiarity of site and corporate personnel with the emergency response organization and associated responsibilities and duties.
- b. Demonstrate the ability of the Initial Phase Emergency Organization to activate and man the emergency response facilities as appropriate for the existing emergency, class and to transfer functional responsibilities to the appropriate emergency response facilities when escalating or de-escalating to a different emergency classification.
- c. Demonstrate the adequacy and effectiveness of emergency procedures, facilities, and equipment.
- d. "emonstrate that adequate security of facilities can be maintained.
- e. Demonstrate precise and clear transfer of responsibilities to the Recovery Phase Organization.
- 6. Radiological Assessment i
- a. Demonstrate that personnel can perform radiological accident assessment and dose projections using plant monitor readings, field monitoring data, and meteorological parameters,
- b. Demonstrate that field monitoring teams can be dispatched and deployed in a timely fashion, that communications are adequate, that radiological monitoring equipment is functional, and that simulated data are accurately obtained and transmitted to appropriate emergency response facilities.
- c. Demonstrate the ability to perform post-accident sampling and analysis.
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- 7. Protective Actions
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a.- Demonstrate the ability to account for onsite pefsonnel.
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b.' Demonstrate the ability to provide adequate radiction protection, dosimetry, personnel monitoring, and area.
surveys under emergency, conditions.
- c. Demonstrate the ability to enter a highly contaminated area for the purpose ol' rescuing casualties.
- d. Demonstrate the ability to maintain _ plant security under emergency conditions.
- e. Demonstrate the ability to perform personnel and equipment decontamination. '
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- f. Demonstrate the ability of the energency response.
organization to use Protective Action Guides.to m?;ku decisions on the taking and relaxing of protectiv'ef -
actions. -
- 8. Corrective Actions
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Demonstrate the ability to place the plant in,a mafe
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(7 condition with consideration of appropriate engineering safeguards and radiological controls.
- 9. Medical Assistance .-
Demonstrate,the ability to provide'first aid and' transport for an injured individual who hasTheen contaminated or has received a high radiation dose.
- 10. Recovery and Re-entry ,' _
Demonstrate the establishment [of a' recovery organization. <
11'. Miscellaneous Demonstrate the ability to self-critiqu'e, to identify areas
, needing improvement, and to identify future appropriate plan and procedural changes.
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- PENNSYLVASIA_-PEACll BOTTO.'l EXERCISE OBJECTIVES '-
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- The Pennsylvania objectives for the annual,' joint exercise with
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the P.sach Bottom Atomic Power Station to be held Tudsday, June 28, 1983 Fs>. are:- 1 . . ...
p y* y f; I. Test the adeqtiacy of communications links between and .
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among emergency response personnel at various levels *'
J of govern:sent, to include the state EOC, state staff .
agencies, risk counties, risk municipalities, and PEMA. ::
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- Area headquarters. .
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n II. Estabilsh emergency response personnels' understanding
' of the emergency action levels. - .
7 - III ' Test one other component of the RER plans, namely public s ...
notification with the siren system, together with the associated Emergency Broadcast System (EBS) announcements _._
,,'- IV. . Demonstrate the capability of Chester County as a risk
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county and of its only. risk municipality to impicment as much of their respective RER plans as is reasonably'
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achievable in a small-scale mode.
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I The State of' Maryland with the plume zone counties, Harford ,
and Cecil Counties, will conduct. a modiffed Radiological Emer- -
gency exercise with the Peach Bottom. Atomic Power Station on Jane ~
- u. 28, 1983.- The exercise nickname is PEACHBEX 83.
The exercise objectives are:
- a. Test the adequacy of communication links and nptifica- ,
tion procedures. .
- b. Establish that response agencies undeEs'tand the emer-gency action levels (EAL). ,
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- c. Test emergency medical services functions. - w -- . ,
- d. Test the State and Plume zone County's public informa- e tion program, and .
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- e. The area Emergency . Broadcasting System (EBS) . . ,
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,s. _ GUIDELIINES FOR CONDUCT
/ I NRC/ FEMA 0BSERVED EMERGENCY. PREPAREDNESS EXERCISE
' FOR THELPEACH' BOTTOM ATOMIC POWER STATION
'I.'- PURPOSE This document provides guidance f.oc con, ducting the PBAPS emergency preparedness-exercise. It provides methods for demonstrating .
- emergency response. capability,. conducting the exercise, and evaluating results. -
II.. CONCEPT OF OPERATIONS AND CONTROL OF THE EXERCISE Philadelphia Electric Company (PECO) will supply controllers and evaluators for'each location where an emergency response is being demonstrated. Prior to the exercise, the controllers and. evaluators will be provided with the appropriate: locations, maps, ' time periods, guidel.ines, and~an evaluator evaluation checklist corresponding to.their' assignments. -
The exercise initiating-events-will be controlled by lead controllers.
Hypothesized initiating events will consist of three. types of information: (1) plant information and data -provided to
' Control Room and Technical Support Center Personnel; (2) release rates; (3)' hypothesized environmental radiation levels. The
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lead-controllers have the authority to determine the time sequenceLof these initiating events tol ensure an orderly flow of exercise events.' All oth_er actions-during the exercise will occur through a free-play response as the plant and corporate-participants respond to the. initiating events.
Assthe initiating events are provided to the plant staff, they will determine the nature of the emergency.and the implementation of the appropriate emergency response-procedures. These procedures
_are expected to include a determination-of the emergency classifi-cation in accordance with NUREG-0654, FEMA-REP-1, Revision l'.
- Simulated notifications will be made to the appropriate federal, '
-state, and county authorities.
The. hypothesized emergency will continue to develop based on data and information provided to the Control Room and TSC personnel. ;As the situation develops, information will be forwarded to appropriate plant and corporate personnel for the determination of-actions to be taken in' response to the hypothesized emergency. Where information would normally be confirmed.via an independent source (such as National Weather Service for weather data), the confirmation data will be simulated. -If a conflict exists between the hypothesized data and the actual data, the hypothesized' data will be utilized.
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Certain inconsistencies (such as plume width, release duration, M .
technical reason for the simulated release, etc.) may be in-tentional and required to provide an exercise basis which tests the plant and corporate capabilities to the maximum extent feasible in a limited time frame. If an inconsistency is known or determined to be intentional, then the emergency response personnel will note the inconsistency'and ignore it. The lead controllers will have the authority to resolve or explain any inconsistencies or problems that may occur during the exercise.
With the exception of the already cited and potential incon-sistencies, the internal operations of the emergency response facilities will be identical with their intended operation in a real emergency.
III. GENERAL GUIDANCE FOR THE CONDUCT OF THE EXERCISE
- 1. Simulating Emergency Actions Since the exercises are intended to demonstrate actual capabilities as realistically as possible, participants should act as they.-
would during a real emergency. Wherever possible, actions should ,
be carried out. Only when it is not feasible to perform an action should it be simulated. Any orders given that for any reason cannot or should not actually be performed should begin with the word " Simulate". For example, the order to put out
- 9) a fire that is being hypothesized would state: " Simulate discharging the fire extinguisher." Where such actions are being taken, it is suggested that p.articipants inform any controllers in the area of what act. ion really would be taken had the. emergency been real.
- 2. Avoiding Violation of Laws Int'entional violation of laws is not justifiable during any exercise. To implement this guidline, the following actions must be taken:
- a. All controllers, evaluators and potentional exercise participants must be specifically informed of the need to avoid intentional violation of all federal, state, and local laws, regulations, ordinances, statutes, and other legal restrictions. The orders of all police, sheriffs, or other authorities should
'be followed as would normally be the case.
- b. Exercise participants will not direct illegal actions being taken by other exercise partici-pants or members of the general public.
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- y 7, c. Exercise participants w'ill not' intentionally t j take illegal. actions when being called out to participate in an exercise.- Specifically, local traffic laws'such as: speed laws will be observed.
- 3. Avoiding Personal and. Proper'ty Endangerment-Participants,. controllers and, eval,uator,s'will be instructed to avoid endangering property (public or private), other
-personnel responding to the exercise, members of- the general public, animals,.and the environment.
- 4. Actions to Hinimize Public Inconvenience
_It is not;the' intent, nor'is it desirable or feasible to effectively train or test the public. response during the conduct of radio-logical emergency exercises. Public inconvenience is to be' minimized.
The actions of federal, state, and county agencies and nuclear power plant-operators receive continuous public notice an.d '-
scrutiny; therefore, the conduct of an exercise could arouse public concern that an actual-emergency is occurring.
To minimize public inconvenience, the public should be informed All, communications,
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bo'th prior'and during the exercise.
particularly in the.public. relations. area,;should be prefaced with "This is a drill"..
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- 5. Maintaining' Emergency Readiness During the performance _of'an exercise the ability-to recognize a real emergency, terminate the exercise, and respond to the.
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new situation'must be maintained. Therefore, the' exercise scenario and actions of participants will not include any actions which seriously degrade,the' condition of systems, equipment or supplies, or' affect-the detection, assessment; or response capability to radiological or other emergencies.
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Actions taken by the participants will also avoid actually reducing plant or public safety. The potential for creating i
real radiological or other emergencies will-be specifically
! -avoided. ,
If an actual emergency. occurs during the exercise requiring al group to terminate its participation,.they should not-ify the lead controller. .then the exercise will be terminated.
l All messages about'real events will be. clearly identi ribd as such. For example, precede a real message with: "This is 4 NOT, repeat, NOT and exercise message".
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-w IV. EMERGENCY RESPONSE ~ IMPLEMENTATION AND OPERATIONS
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- 1. Initial Notification Initial notification will be performed in accordance with the appropriate Emergency Plan Implementing Procedures (EPIP's).
- 2. Plant Operations It should be emphasized-that the exercise will in no way in- _
terrupt normal plant operations, production, and safety. The responses of Control Room personnel and plant operators will be simulated when taking action to combat the emergency. Instead, a controller will narrate the initiating events and the postulated plant response directly to the Shift Supervisor and other Control Room personnel who will then employ the appropriate _ emergency procedures.
- 3. 'Enviornmental Monitoring Teams PBAPS will dispatch field environmental monitoring teams. . .-
The controllers-will provide hypothesized field data which will be used to determine radiation readings at pre-selected locations. However, these teams will be equi.pped with the necessary equipment which would enable them to determine actual
(~] area gamma dose rates'and airborne radioiodine' concentrations.
_/ The monitoring teams will not be suited up in anti-contamina-tion clothing, but will have such equipment at their disposal.
- 4. Public Notificationa Simulated emergency message transmissions via the Emergency Broadcast System will occur.
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i 5. , Public-Information Press releases to the general public and news media concerning the simulated emergency will be prepared. The press releases will contain all necessary information on the current status of the exercise and will be transmitted to selected locations.
- 6. Communications Communications between the exercise participants will occur in accordance with the appropriate Emergency Plan Implementing Procedures. Should any primary communication path become in-operative or prove inadequate, back-up means of communication will be utilized as appropriate. All communications should begin and end with "This is a D rill', REPEAT, This is a Drill". _
g- V. CLOSEOUT OF-THE EXERCISE
~) The exercise will be terminated by the Lead Controller when the scenario is completed.
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SECTION 3 2 SCOPE' p]:-
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' PEACH BOTTOM ATOMIC POWER STATION 3
Identification of Actual and Simulated Events I
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ACTUAL SIMULATION A. Assignment of Responsibility.
4 o To demonstrate that emergency' personnel understand and can implement their responsibilities I-9 o To demonstrate the ini.tial response of emergency personnel X
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.B. On-site Emergency Organization
- ' o To' demonstrate the response of the on-shift emergency organization X o To demonstrate the timely augmentation of.
the'on-shift emergency organization. X o To demonstrate that sufficient qualified personnel are available to respond,to the postulated events . X o To demonstrate the timely au6 mentation of I the plant staff emergency organization by -
corporate support personnel X. ,
t o -To demonstrate the ability to procure assistance from outside contractors and X private organizations o To demonstrate the ability to handle .
personnel and equipment contamination X-i.
l C. Emergency Response Support Resources.
o To demonstrate the ability to request X
i assistance from Federal resources -
o To demonstrate the ability to support X
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s Federal resources J
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M ACTUAL SIMULATION-O
=V o To. demonstrate the ability to accommodate state and local staff at the EOF X o To demonstrate the ability to obtain assistance from nuclear and other facilities, organizations or individuals j identified in the PECo Emergency Plan j o To demonstrate the ability of PEC'o' corp'o'r' ate ~
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personnel to provide support I f; D. Emergency Classification System o- To demonstrate the ability to properly classify the simulated event X
, E. Notification Methods and Procedures
. t o To demonstrate the notification of state -.
and local response organizations based ,
on the emergency classification X -
o To demonstrate the effectiveness of N notification messages and verification
, q) -of these messages X c
o To demonstrate the ability to alert, notify, and mobilize emergency .,
response personnel .
X o To demonstrate the ability to provide timely and accurate protective action recommendations to the state :I F. Emergency Communications .
o- To_ demonstrate the operation of the public alerting system X~
.o- To demonstrate the adequacy of communicai-tionswithstate/localgovernmentsduring the exercise X o . To demonstrate the adequacy of communica- i tions with federal emergency response f organizations including the NRC Regional ,
Office Emergency Operations Centers X
-* - ACTUAL SIMULATION c
o To demonstrate the adequacy of concunica-A' V- tions between the PECo emergency facilities and radiological monitoring teams X o- To demonstrate-the adequacy of communica-tions with fire-fighting support facilities X ;
G. Public Education and Infomation-
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o To demonstrate the adequacy of facilities used for dissemination of information to news media X o To demonstrate the ability of the PEco spokesperson to access and disseminate necessary infomation X
.o' To demonstrate the ability for timely exchange of information among designated spokespersons X _ _
o To demonstrate the ability to deal with rumors X i) H. Emergency Facilities and Equipment ,
o- To. demonstrate the adequacy of the. ,
physical layout and operation of the '
- -following emergency centers Technical Support Center
- l. Emergency Operations Facility .
l Operations Support Center Emergency. News Center.
l Headquarters Emergency Support Center X l~
o To demonstrate the timely-activation and staffing of all emergency facilities. X o To demonstrate the ability to maintain l Plant security,under emergency conditions X o To demonstrate the_ ability,of ERF personnel X L
o To demonstrate the assumption of N .. ,
responsibilities previously were done by interim
, personnel \ X o To demonstrate the ability to provide adequate supplies and equipment for use p by on-site teams X >
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ACTUAL SIMULATION o To demonstrate the ability to receive V(N and analyze field monitoring data and coordinate sample media at the i Emergency Operations Facility I o To'demonntrate the ability to effectively use the at Accident Sampling Station X Accident Assessment I
o To demonstrate the ability to utilize zpost accident sampling data, radi ation' -
and effluent monitor data, and containment radiation monitoring data to provide initial-
- and continuing accident assessment X -i o To demonstrate the ability to predict on-site-and off-sit. exposures for varicus meteor-ological conditions based on effluent monitor <
readings X ,
4 o To demonstrate the ability to perform field monitoring within the plume exposure Emergency
. Planning Zone X s
o To demonstrate the ability to activate, equip,
. b" deploy and communicate with off-site monitoring teams .,,
-X o To demonstrate the ability to' estimate integrated dose from projected and field monitored dose rates and compare'these estimates with protective action guides X o To demonstrate the ability to determine the cause of the emergency condition, terminate the condition with consideration of appropriate engineering safeguards,' and place the plant in a safe condition X J. Protective Respom e ,
o To demonstrate the ability to warn or advise personnel on-site of emergency -)
conditions X o To demonstrate the ability to evacuate o X /'
nonessential personnel from the site X* -
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- A pre-selected group of on-site personnel will L,/T participate in this activity.
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' ACTUAL' SIMULATION T
fs - o To demonstrate the ability for i ,
radiological monitoring of people evacuated from the site X o To demonstrate the ability to provide evacuation routes and transportation for on-site personnel to some suitable off-site location X o To demonstrate the ability to provide ~ . g
. respiratory protection, protective {
clothing and radioprotective drugs-to personnel on-site during the exercise
'when reriired. X s -
o To detea.ane the ability to assess and recommend protective actions to state and local authorities I K. Radiological Exposure Control -
.e o To demonstrate the application of on-site'
- exposure guidelines consistent with Station Protective Actions Guides and Procedures X f)V' _ o To deronstrate the procedures for permit-Lting on-site workers to exceed doses in
' excess of 100FR20 limits X o To demonstrate the ability to provide and monitor dosimeters for emergency workers X o To demonstrate the ability to evaluate the need for and provide the means for personnel decontamination X o To demonstrate the' ability to provide contamination control measures such as areas access control - X o To demonstrate the ability to estimate
. total population exposure X t
L. Fire-Fighting Support
- o. To demonstrate the ability of PECo l personnel to respond to and terminate a fire X W ,.
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33 PARTICIPATING EMERGENCY CENTERS 15~3 -
o MARYLAND-Accident Assessment Center, Baltimore
- LState of Maryland Emergency Operations Center,'Pikesville I
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Cecil County Emergency Operatio's-Ce$ter, n - Elkton ,
.g Harford County Emergency Operations Center, Hickory a I
PENNSYLVANIA i Bureau of Radiation Protection Headquarters Assessment Center, Harrisburg
- State of Fennsylvania Emergency Operations Center, Harrisburg Chester County Emergency Operations Center, West Chester York County Emergency Operations Center, York
.Lancaster County Emergenc'y Operations Center, Lancaster '
c PHILADELPHIA ELECTRIC COMPANY .
Headquarters. Emergency Support-Center,. Philadelphia, Pennsylvania Peach Bottom Atomic Power Station Emergency Operations Facility, Peach Bottom, Pennsylvania Peach Bottom Atomic Power Station Technical Support Center, Peach Bottom, Pennsylvania -
Muddy Run Recreation Park Emergency News Center, Holtwood, Pennsylvania 9
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HARRISBURG PENNSYLVANIA BRP KADQUARTERS/ASSESSPENT CENTER STATE EOC .
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-f 76 83 1.ANCASTER COUNTY EOC LANCASTER g PHILADELPIGA y
30 CHESTER COUNTY EOC WEST CHESTER YORK COUNTY EOC e YORK 10 8 ,
272 3
1 MUDDY RWi NEWS CENTER
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HARFORD C EOC CECIL C0LfrIY EOC 83 HICKORY
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I MAP OF PARTICIPATING t .e EMERGENCY CENTERS
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INSTRUCTIONS FOR~ PLAYERS
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l.- You may ask the controller / evaluator for information such as:
'A. ' Initial conditions of the plant and systems. including:
o operating history of.the" core
- o initial coolant activity o ' meteorology data such as wind, speed, direction and stability o availab'ility of systems according to the scenario B. Area radiation data of the location of emergency teams.
C. Airborne data at the location'of the plant and field survey teams after a sample has'been appropriately ,t,aken.
D. Counting efficiency of all counting equipment. ,
E. Activity from nose-swabs or skin contamination surveys.
.I N
- 2. You may not ask the following from the. controllers / evaluators:
A. Inform'ation contained.injprocedures, drawings or instructions.
, B. Judgements as to which pr'ocedures should be used.
C. Data which will be made available later in the day.
i D. What-the controller / evaluator.would do if he was a player.
E. To take an active role in helping the player in this drill.
-F. To help the player in carrying out calculations.
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s E 3. Remember-there are two clocks, the scenario time and the
(
The scenario time is mo're important actual clock time.
to you. ~ Track both times on your status boards if necessary.
This is'particularly important if the exercise becomes delayed'for any reason. . .
. 4. Know the overall Controllers organization.- Identify _your
' Controller through his identification. Some Controllers are also Evaluators.
- 5. .There will be NRC/ FEMA (Federal Agencies) Evaluators present
', June 28, 1983 only. Identify them by their identification.
They-are here.to judge your performance and approve your.
h)' -6. I.There may be visitors p, resent who' will' be so identified.
Identify.them by-their Identification. badges. -
Z
- 7. Identify yourself by'name-and' function to;the controllers / -
Evaluators and the NRC/ FEMA Evaluators.- This will be a big _
help. Always'wearyouridentifica[lonbadge. '
- 8. Play out all actions as much as'possible, in accordance with i
your Emergency Plan and procedures as if it were a real emergency. Unless authorized by the Controller, you should not simulate your, actions. If authorized to simulate an action, tell the' Controller how and when you would actually '
do them.
~
-9. Periodically speak out loud, identifying.your key actions This may
~
and decisions to the Controller and Evaluators.
seem artifical but:it will assist in the evaluation process, and is to your b'enefit.
10 . - If'you'arein' doubt-aboutdatkaskyourControllerfor' clar'ification. The Controller will not prompt or coach you.,
- 11. The~ Controller'will periodically issue messages or instructions designed to initiate response actions. You must accept these messages immediately. They are essential to your successful performance. ,
- 12. If the Controller intervenes with'your play it is for a good reason. Obey,your Controller's directions at all times.
~
This is essential to the overall success of the exercise.
- 13. If you disagree'with your controller, you can a'sk..himuto ,
reconsider-or consult' with'the lead Controller's as time i- permits. You.must however accept'his/her word as final and
~
proceed.
- 14. Respond to.the Controller's questions. .
l i.
- 15. You must not accept any messages / inst.ruction.s...from the I
i Federal Evaluators. If they want'to initiate actions, test ,
l.
i your abilities, or give you "suprise".,.. they must work through your Controller. This is essential to the overall success l
of the exercise.
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- 16. You must play as if radiation levels are actually present, r,M ,
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in accordance with the information you have received. This will require that you wear radiation dosimeters, anti-c's, observe. good radiation protection practices, be aware of and minimize your radiation expo.sure., , Identify the individuals in your emergency r'esponse organization who are responsible' -
for informing you ofs these items... Follow their instructions.
- 17. 'The Controllers and Federal Evaluators will not act as if.
simulated radiation IcVels from.the emergency exercise are e
present. They are exempt. Do not f let this confuse you or cause you to act nawisely.. -
a-
- 18. If'you are entering normal nGclear station radiation' areas,
' 77, observe all rules and' procedures.. No'one (even the Controller l (sd and Federal Evaluators)' is exempt from normal station radio-logical practices and procedures; I' NOTE: DO NOT' ENTER I HIGH RADIATION AREAS IN THE PLANT WITHOUT t
! AUTHORIZATION FROM'THE CONTROLLER. FOLLOW' ALARA -PRINCIPLES.
- 19. Demonstrate knowledge of your emergency plan, emergency operations
~
and procedures.
fe 1
- 20. Utilize Status Boards, log bobks, 3-part communication forms,
~
.- etc., as much as possible_to document and record your actions, l' This is very instructions and reports to your co-players.
important. Rei. amber "Put it in writing". -
i -A,//% 21.- Do not enter into conversations with the Visitors.
i
/~. 22. 'You may answer questions directed at you by Federal *
\. V; b '
Evaluators. If the question is misdirected to you or .
you,do 'not know the answer, refer them to your lead.
player or the Controller.
- - - ~ - .
- 23. Keep'a list of items which you' feel will improve your -
plans and procedures. Provide this to your lead player.
Lead players will ensure these are. considered. If necessary, they will identify it to the Controller. .
Remember one of the. main purposes of the exercise is, for you the player to assure yourself that you are adequately , prepared . - Areas for improvement or-lessons' ~"
learned when identified will improve'your'ove.rall ,
rw 3 emergency planning and preparedness.
~ ;Q}
- 24. A critique of the exercise wil1 occur after the exercise ,
Provide your i[nput to your lead player is terminated.
or the Controller. This will help in the overall evaluation 4 which.the Controller will present to the lead Controller.
Make sure all communicationsbegin and end'with "THIS IS A
~
25.
DRILL'. " And: repeat at frequent intervals.
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. 14 . 1 -
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,, CONTR0TJRR/ EVALUATOR' ASSIGNMENTS ,
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__ Evac / Search & Rescue /First Aid .
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Field Monitoring - Fire & Damage.
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News Center _
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-{} INSTRUCTION FOR CONTROLLERS AND EVALUATORS
- 1. personnel are assigned as controllers or evaluators at all key function areas to monitor and control the exercise.
In addition, they will accompany radiological monitoring ;
teams, repair rescue
/planthealthphysicspersonnel,andmaintaining teams.
I
~ 2. . Thecontroller/evaluatororganiza'tionisdetailedin -
Section 14. _This delineates the postion and responsibility of i ,
controllers.and evaluators.- ;
3 Messege forms and simulated Control Room data will be used to initiate, modify, and complete the events comprising the overall scenario. Selected controllers willause the messege a
forms to place the_ scenario events in effect and to trigger responses from the involved emergency response organizations.
- Each controller will have copies of the messages controlling the portion of the exercise scenario.for which he/she'is responsible.
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Two kinds of messages will be used:
Controlling Messages used as a primary means of implementing scenario events by announcing or placing an event in effect by hypothesizing conditions resulting from previous actions.
~
Contingency .
Messages used at the descretio'n of the controllers in order.
to maintain the scenario plan continuity or scliedule.
Controlling messages will be presented to.the designated exercise participant at the time specified in the event-schedule. The controller .hould follow up with an explan-l ation of the message and answer questions to ensure'that the
! participant understan'as the message.
l Controllers will not initially provide information to the participants regarding scenario development or resolution of problem areas encountered., The participants are expected to obtain information through their own organization and exercise . ,_
r.
--their own judgment in determining response actions and re-l' I- solving problems. In the event of incorrect or incomplete' responses, or if the participant' indicates lack of knowledge' of how to proceed, the controller will prompt the participant- -
with necessary instructions or contingency cards and will
- note the deficiency on his/her critique sheets.-
L
4 vA
('T h. Note that the scenario events are hypothetical. Any portions V of the scenario depicting plant system operational transients are simulated events. No; Control Room actions, or reactions involving operation of plant systems, or affecting generation capability will be initiated. All exercise scenario messages
- will be prefixed and suffixed with the words: "THIS IS A DRILL."
Controllers stationed at areas vital to maintaining generating capability should be especially aware, and take extra precautions, in issuing messages or giving instructions regarding the scenario
~
events.
~
5 Required controllers will have the time-related plant and radiological parameters of the exercise scenario. This infor-mation'should be issued upon request to the appropriate exercise participants by either the Control Room controller or controllers accompanying the radiological monitoring field teams.
- 6. Some exercise participants may insist that certain parts of t'e h scenario are unrealistic. The controllers and evaluators have the authority; with the approval from the lead controllers, to clarify any questions regarding scenario content. In some cases.
it may be necessary to exercise " controller's perogative" to preserve the continuity and objectives of the exercise.
7 Prior to commencement, all telecommunications should be tested
, f to ensure satisfactory communications between the lead controllers
' (g and all other controllers.
- 8. All controllers and evaluators will synchronize their watches to ensure that moss Mes are delivered at the proper time. Times on' messages 'are set relative .to tii'ebeginning of the exercise, with
^ '
delivery of the first message. at "T + 0:00".
'9 The Emergency Response Exercise is tentatively scheduled for termination at 1700 hrs.
- 10. Controllers will commence their assignments at assembly locations for players tha,t they are to observe or as directed by the lead
- 11. Scenario equipment problems not covered in the Exercise Events section of this manual will be handled by the controllers in the Technical Support Center.
- 12. Players are not allowed to introduce items into the exercise or . .-
scenario.
13 Lunches will be provided by PEC0; however, there are no specific lunch breaks in the exercise. Players and controllers should be ,
relieved for lunch as time pennits. Emergency team leaders should decide when team members may take a lunch break.
m
( 1h. Be sure to have a hard hat with you when entering the plant.
m
( CONTROLLER'S AND EVALUATOR'S RULES D0s
. 1. Know the overall Controller's Organization ,
- 2. Remember that there are two clocks: a scenario time and a clock .
time.
3 Identify the players by name and funtion.
14 Identify yourself at all times to all r'ayers. Wear T-shirts s or tags as provided by PECO.
5 Iaentify the phone (or radio for field teams) you will use to maintain communications with lead controllers.
- 6. Position yourself in order to maximize your effectiveness in issuing messages and observing the players. _
. 7 Be sure you understand the player's scenario script and the master scenario.
('3 8. Keep the play on schedule by checking your script.
\j 9 Issue the message on time. Make sure the players understand it.
- 10. Remeber to call the Lead Controller, George Ge11 rich or Robbie ~
Kankus'to report on status of players' actions if off schedule or if in doubt about what to do.. Call for advice if players depart significantly from the scenario script which will create a major delay. If necessary, intervene with player action and put players back on scenario track.
- 11. Allow the players' reasonable flexibility to do their functions and demonstrate their skill, knowledge, and initiative.
- 12. Identifythefederalevaluator(s). Make sure they are reasonably aware of all your actions and those of the players.
13 Make notes on good and bad points of players' actions, the strengths and weaknesses, and areas for improvement. Use the
=
Evaluator's Critique Sheets.
11 . Attend the post-exercise critique session to provide your comments 4
and recommendations to the Chief Controller on what happened.
~
15 Identify the players' leader. Work with them as appropriate.
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- 16. . If a real emergency occurs and this affects the players,
[)M N ' call off your portion of tbo exercise, and notify the lead Controller immediately.
17 Be at your post at least 20 minutes prior to any player .
action commencement. Set yourself up. ,
- 18. The federal evaluators will not issue " surprise" messages or direct " surprise" actions'a~t the ilayers. They must
~
work through the controller. This is essential for the success of the exercise.
19 Controllers and federal evaluators do not have to follow the radiation exposure control practices for the simulated radiation levels from the emergency exercise scenario.
However, the players must follow the radiation protection rules. Controllers, federal evaluators, and players entering nomal nuclear station radiation areas must observe all nomal radiation control practices.
DON'Ts I 1. Don't leave four post at key times.
- 2. Don't prompt the players to take action.
p1~'
- 3. Dont't coach the players.
- 1. Don't criticize the players' act; ions during the play.
4 _
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- 5. Don't forget to call the lead. controllers to seek -
advice or help as necessary.
- 6. Don't allow the media /other external influences <to distract the players. No interviews with players
~
are allowed.
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EVALUATION INSTRUCTIONS
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The follewing package addresses key points each controller should look for while evaluating participants at the specific location to which he/gpe is f assigned. In addition, there are general exercise .-
critique sheets to 4 be completed, as well as an attendance list. .
g The following grading standards should be utilized in the evaluation of the exercise:
Exceptional _: Personnel and equipment always functioned without E }
effor the first time, every time. There were no problems l encountered, and all personnel and equipment functioned at a ;
level much greater than could reasonably be anticipated. $
l EN Exceeds Normal Expectations: Personnel and equipment generally performed better than nor= ally expected. Any errors or problems !
were minor and easily correctable. .
s.
FM Fully Meets Expectations: Personnel and equipment perfor=ed according to expectations, with few minor exceptions. Any errors noted were not severe and could be corrected without undue labor and/or expense.
Occasionally Falls Short of Certain Expectations: Personnel f ' ' ' 0FS
- and/or equipment occasionally purformed below expectations and/or there were occasional significant deficiencies noted. ,
U* Unable to Meet Expectations: Personnel and/or equipment were unable to perform as required and/or there were nu=berous, serious deficiencies.
NO Not Observed.
- Please provide written' summary of problems observed.
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1983 PEACH BOTTOM ATOMIC POWER STATION EMERGENCY PREPAREDNESS EXERCISE ATTENDANCE LIST v'
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Observer ~
Dates _
Location:
Position:
Personnel Observed:
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f m.. 51 v: - INITIAL CONDITIONS
- E Both units are operating at continuous full power. Unit 3 has been operating.for eleven months and Unit 2 has recently completed a re--
fueling outage. The high range gas monitor of_the Main Stack Sampling-Station is being modified to rearrange the piping layout and is therefore blocked. This monitor may be placed in service within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
The 'B' gas monitor is out of service and awaits parts which are-unavailable on-site. The 'A' gas monitor failed low at 04:45 Upon
- investigation the 'A gas monitor is found to be electrically shorted.
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3 VALUATION INDEX-
. ,I.- Communications II.. . Notifications , , ,., , ,
III. Procedures IV. Material And Equipment V. Radiation Exposure Control
- ' VI . ' General Observations and Comments
. -a Attachment 1 - Event Chronology LO Attachment 2:- EOF Critique Form en e
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e GENERAL OBSERVER CHECKLIST l
NAME: DATER. ,
LOCATION OR TEAM TITLE: _ _
NOTICE TO CONTROLLER: ANSWER COMPLETELY AND CONCISELY 1 HOSE ITEMS WHICH APPLY. ENTER "N/A" IF ANY ITEM IS NOT APPLICABLE.
I. COMMUNICATION ._
- l. Were all required and specified communications ' circuits -
available and operational?. It not, identify ~ specific problems. i
- 2. Were personnel familiar with the communications circuits available and the intended use of each? ._
,, , 3. Were the communication circuits used as intended or were they misused? If misused) what specific prcblems did you note?
('l . 4 .' Were communications adequA'e t to' ensureothat the flow of information was. timely, efficient, and effective?
. s _.
- r. 5. Were there sufficient- . communicators and communications l assistants to manage all. of :the circuits? 10 not,- what specific shortfalls did you note?.
~
- 6. Were communications' personnel able to effectively pass and l-receive information and transmit that informatien to and from -
l appropriate personnel? If not, identify specific problem areas. ,
j
- 7. Were communicators familiar with their assignments? Did they. -
know communications practices? _ _ _ - ,
l 1
- 8. Did the communications personnel maintain accurate logs? Was .
sufficient detail reflected in the logs (journals) to provide a valid record of the event?. -
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Were the ' legs used effectively by personnel to review past 9.
I events and to understand the nature and trending of the event
- 3n progress?
- 10. In general, was the'ecmmunication system with all emergency "
i- _
response facilities t.~.d field elements adequate?- t c
- 11. -
Were ' communication's betveen teams and appropriate emergency I U l,
facilities clear and understood?- w t <,
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- f[*- II. NOTIFICATION
~ - 1. Were notification messages- (i.e., energency class notifications) accurately logged in and quickly disseminated to appropriate personnel?
~ -
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- 2. Were notification messages verifie'd according to procedures? -
l
- 3. Were messages and information sent out accurately and in -
accordance with appropriate forms (i.e., notification message ;
forms, follow-up message ' forms, etc)?
- 4. Did messages contain, "THIS IS AN EXERCISE MESSAGE" or some [
similar statement?
- 5. Were appropriate organizations (i.e., Federal, state, local, '
or private) with response requirements notified according to l/
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procedure?
In general, did personnel " know who to notify and when to 6.
notify them?
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- II
I. PROCEDURE
S
- 1. Were personnel generally familiar with the relevant procedures -
. and did they follow them?
- 9
- 2. Were there situations which required personnel t,o vary from established procedures? .If so, be specific. '
(
- 3. Did procedures give adequate guidance or were they confusing?
Explain. i
- 4. Was the person in charge assisted by someone familiar with procedures?
c
- 5. Was adequate .and timely guidance provided by senior .
management?
<(] 6. In your judgment, was the~ general flow of information
(/ appropriate and was consultation concerning the assessment of information and actions to be taken continuous and effective?
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r- IV. MATERIALS AND EQUIPMENT ,
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- 1. Were all the materials and equipment required for this activity available?
- 2. Was all the equipment functional? ;
- 3. If a specific amount and type of equipment (i.e., offsite Radiation Monitoring Team Kits) was required, was there an inventory list available to facilitate a check of the equipment?
- 4. Did personnel check to insure that all equipment was available and functional early in the activation process?
- 5. Were provisions made to accommodate missing or inoperative _ .
equipment?
- 6. Was there any situation during which the lack of equipment, inoperative equipment, or inability to operate equipment, left
(.(/x
_) personnel unable to properly perform assigned. tasks? Be .
specific.
- 7. In' your opinion, was the equipment and materini available, If not, l
. appropriate and adequate for the tasks ' assigned?
explain.
- 8. Did all personnel use or s'imulate using equipment as required l
(i.e., survey meter, dosimetry, anti-C's, respirators)? -
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/q V. RADIATION EXPOSURE CONTROL V ^ personnel ent'ering radiation areasprovidedwithI
- 1. Were all TLDs, dosimeters, KI, and communications equipment as appropriate?
- 2. Were all emergency response per,sonnel briefed on the accident '
status and recommended stay times prior to a mission? Were .
they provided with updates during the mission?
- 3. Were all emergency response persor.nel effectively rotated as applicable to prevent overexposure?
- 4. Were emergency response persennel doses properly recorded and were appropriate actions taken in the event of contamination (i.e., decontaminatien or restrictier.s on any further nevement into controlled areas or both)? .
4
~
- 5. Were records regarding contamination levels before and after
(( ) contamination kept for emergency response personnel?
- 6. Were contaminated wastes in' general (clothes, towels) properly -
stored for later disposal?
- 7. ' Did emergency response personnel know limits and restrictions en receiving emergency exposure doses?
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VI. GENERAL OBSERVATIONS AND COMMENTS D 1. Were personnel generally aware of the overall situation and the role they were playing in the assessment and mitigation of the accident?
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- 2. Was the person in charge clearly identifiable and was proper leadership shown? . .. '
- 3. Was there an adequate exchange of information?
- 4. Did personnel involved understand the changing situation and l were they able to contribute to the overall mitigation and accident assessment?
- 5. Was there. any confusion or lack of understanding on the part
of the participating personnel concerning the role each was to play in the overall emergency response?
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!(n -' 6. Were teams and/or participating personnel familiar with their responsibilities and perform their duties adequately?
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- ATTAODENT No.1 Remarks and Chronological order of Significant Events ,
Time Remarks / Events e
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ATTAODENT NO.1 .
4 Remarks and Chronological order of Significant Events . .
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EMERGENCY CPERATIONS FACILITY (EOF) s.
Name s- Date:
- l Team Descriptions ,
~
Note,: Keep a chronological log of important e'vents on the attached
' sheets. Enter times where necessary.
f Key itetas to check are listed below
- 2. Was the EOF organization and initiation of activities efficient and well organized?
<~-
- 3. Were the EOF status boards and log books updated frequently?
T 4. Was definite and effective leadership shown in the EOF 7 -
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- 5. Were 20F personnel familiar with their responsibilities and did -
- they carry out their- duties effectively?
j l
- 6. Were the radiological trends of the accident established?
(
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- 7. Did personnel work well together to provide data and perform all -
dose assessment calculations? -
- 8. Was there a good turnover of information as personnel arrived at l
the E0'F7
- 9. General Comments 1
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' DERGDICY OPERATIONS FACIIITY CCt!TD.
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- j. 10. ~ Suggestions for Improvement: -
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- Abstract of 1983 Peach Bottom Annual Exercise Scenario
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The' initial condition for the scenario at 04:45 places the plant at'100% power. .The plant has been operating at this level for eleven months. The.high-range gas monitor at the Main Stack Sample System is being modified to rearrange the piping layout and is therefore unavailable. The 'B' gas monitor is out.-of service and awaits parts which are unavailable on-site. The gas 'A' gas monitor has failed down i scale.- -Upon investigation, the 'A' monitor is found to be elsctri- .
cally shorted. At 5:45 repairs are underway to' repair the gas monitor, but due to a failure to. meet a Limiting Condition of Operation and the lapse of the allowable period for operation, a shutdown should be initiated.
Shift begins a gradual' reduction in power, planning to be
- shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.- An Unusual Event should then be declared based on an unplanned controlled shutdown due to. failure to meet a Limiting Condition of Operation. During initial stages of-the shut-down, at approximately 06
- 00, an " 'A'.Recircula. tion Pump recirculation High Seal '
Leakage" alarm is received in the Control Room. The 'A' pump seal flow indicates slight seal wear. Within. one hour, both::. .
Drywell Pressure and Sump Pump-out rates have become high. At 07:15, the "Drywell-Hi-Lo Pressure" alarm annunciates in the Control Room.
These problems are corrected when the operators backseat the main At this time , the process computer is lost for
-(s,J'steamlinedrain.
. .l.25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br />.
At approximately 08:00,.the bonnet of the Reactor Water
~
Clean-Up outboard isolation valve (suction) develops a small steam A Health Physics Technician, leak due to stress corrosion crackin~g.
performing routine plant surveys, reports high air borne activity near the RWCU pump rooms on El.evation 165', Reactor Building. In-vestigation initiated by shift indicates the source is from the .RWCU isolation valve pit. Attempts to isolate.the leak fail and the MO-15 breaker is found to be severely damaged. . .
At 09:15, . annunciators in 'the Co'ntrol Room indicate a n .
Operating-Basis, Earthquake. The earthquake caused the line between the RWCU outboard isolation valve and containment to shear resulting Fifteen rods; in a reactor scram:and release to the Reactor Building.
fail to fully insert, but the reactor-is sub-critical. Level is r
maintained by normal:. Emergency.corecCooling. Systems.
L Also'at this time the expansion joint on the condensate
< pump. suction line ruptures,. draining the hotwell, flooding the con-densate pump pit (iscapacitating the pumps), and contaminating.the Moisture. Separator Area. An Alert should be declared due to an -
( .
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- -. --+-,m- ,, 9 ,- . , - --. - . e-i--m- ,-,-e, . , . - -
l o 1 At 09:45, the Test Engineers Gro'up reports a missing l
()3 -
Test Engineer, last known to be working on a condensate problem.
The individual is found uninjured but contaminated. No off-site i
. medical assistance is required. At 10:00, the Main Stack Monitoring l System is returned to service.. .
At 10:30, the.Back-Up Instrument Nitrogen System Low Pressure Alarm, annunciates in the Control Room. Investigation reveals 1that the problem is due to.a failed pressure regulator and
- cracked pipe. -
At 10:45, a report from an operator reveals a crack near Motor Ooerated Valve 14-llB of the Core Spray System. This causes one loop of Core Spray to be inoperable.
At approximately,ll:00,. all rods are fully inserted and at 11:30Lreactor water clean-up of the MO-15 breaker is repaired and the valve-isolates.
Level recorder (red pen only) 3085.begins to drift low at
, 'approximately 12:15.. . Investigation reveals a malfunctioning- ~ ^~
recorder.. All other level indications remain constant.
A report of. fire in ths vicini~ty of Motor Control Center 30B38 (E334R-B) occurs at 12:45. The. fire in the c'able traysHowever, is
' extinguished and no off-site fire assistance is necessary. The a fire brigade member is, injured while fighting the fire. injury
'( ) is' serious and. con.tamination is suspected.- Off-site medical assistance is requested. ,
Damage to the Motor Control Center includes destruction' -
- of M014-12A breaker.- A Site Emergency should be declared due to a
' fire which makes an Emergency Core Cooling System inoperable.
~ ~
Delayed' effects of the earthquake ' cause the fuel pool filter demineralizer discharge line to shear in the Fuel Pool Filter Valve Room on Elevation 116', Radwaste Building at 14:00. Failure of the Vacuum Relief Valve and Check Valve cause a syphon effect on the fuel pool, which therefore begins to drai'n. .
Investigation into the Fuel Pool-Trouble Alarm is inhibit 6d by high radiation. Fuel is uncovered for a sufficient amount of time -
to allow radiation effluent levels to exceed the General Emergency Action Levels. A General Emergency should be declared.
The fuel' pool is flooded by the Residual Heat' Removal System
' within. forty minute's'and the release is terminated. The General
- Emergency is de-escalated and the Recovery Phase is initiated.
At 16:00 the exercise is terminated due to stabilization of the plant conditions.
4
, ,/ .-
9 " *= vew se-- , ,
(
9 Detailed Scenari.o .for Unit 3 5: 65 The Instrument and Control that the 'A' gas T e c i.n i c i a n reports electrical repair.
monitor needs initiate a Operators extensive shutdown in expected to Technical Specificctions.accordance with should be declared.
6:00 Unusual Event
'A' recirculation pump high Jeal leakage 6:30 annunciated
'A' in the Control Room.
slighrecirculation seal Lrywell wear aspump Unit seal "iow indicates is pump outpressurerate is is .25 psig. reduced in power.
75 pgm. Drywell sump 6: 45
~
Drywell pressure 7:00 Drywell reaches .35 psj g.
sump pump out
.ncreasing. ate ts 3.5 gpm and O'. 7:15
" Dry.<ll Hi-Lcw Pressure" psig) in the drain MO 74 isControl annunciates (.75 begins to back Room. When s t ea.a iine decrease. seated, drywell pressure 7:30 Drywell '
sump pump Process Computer out rate begins te is dumped.
8:00 decrease.
Heal th Physics reports high airborne near the rooms, Reactor 165' Water actjvity elevation, Clean-Up (RWCU) pump reactor b RWCU shows slight f1c e decrease.uilding.
8:15 Airborne 165' activity lecels in Reactor [
el eva tion have Building 6:30 increased to 1x10 -8 ci/cc Investigation reveals a steam
!)3) hiF' airborne b ist with of the RWCU valve activity, pit. higi.es t in the associated vicinity MO-15 Fail because A t temp ts to backseat the valve bonnet. the leak is located at 8:35 C ;'e r a t o rs valves, MO-18 attempt to close RWCU i sol a ti on MO-15 loses inuand MD-15.
i ca tion MO-18 closes.
tc close it.
bonnet The steam when operttor attempts and backseating t'aleaki ] s is at the valve
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-Detailed Scenario for Unit 3 5:45 The Instrument and. Control Technician reports that the 'A' gas monitor needs-extensive electrical repair. . Operators expected to initiate.a shutdown in accordance with Technical' Specifications. Unusual Event
- should be declared..
6:00 'A' recirculation pump =high seal. leakage is annunciated 'in ..the Control Room.
6:30 'A' recirculation;pumpiseal flow indicates sligh sealLwear as Unit is reduced in power.
Drywell. pressure is .25 psig. Drywell sump
. pump out rate is .75 pgm.
6:45 Drywell pressure reaches .35 psig.
7:00- Drywell sump pump-out rate.is 3.5 spm and increasing..
/"i 7:15 "Drywell Hi-Low Pressure" annunciates (.75
(-) psig) in the Control Room. When steam line drain M0-74 is backseated, drywell pressure begins to decrease.
I .
7:30 Drywell sump pump out rate begins to decrease.
~
Process Computer is dumped.-
8:00 Health ~ Physics reports high airborne activity near the' Reactor Water. Clean-Up (RWCU) pump rooms, 165' elevation, reactor building.
RWCU shows slight flow decrease.
8:15 Airborne activity levels in Reactor Building 165' elevation have increased to 1x10~0 ci/cc I 131.
8:30' Investigation ' reveals a steam mist with associated
'high airborne activity, highest in'the. vicinity of the RWCU valve pit. Attempts to backseat M0-15 fail because the leak is located at the1 valve bonnet.
8:35 Operators attempt to'close RWCU isolation E valves, MO-18 and M0-15. MO-18 closes.
MO-15 : loses . indication when operator attempts i ), to close it. The steam leak is at the valve
bonnet and backseating rails.
't
-2 1-
4'E' f fc V-8:45 . Investigation reveals the breaker compartment in which the MO-15 breaker la located has'been blown.out. Damage-is catastrophic, including terminals. Approximately two hours.are required to repair the breaker. Process Computer is
. regained.
' A t tempts to r'epair the breaker are initiated.
9: 00 9: 15; An Operating-Basis Earthquake occurs at.the site.
9:15:05 The RWCU line-shears outside containment prior to the MO-18 valve, releasing steam to the Reactor Building. The expansion joint on the condensate pump suction line has also f ailed.-
The' Reactor Feedwater Pumps attempt to maintain, level but trip due to low suction pressure.
- The reactor scrams on low level end HPCI is initiated. Vacuum is lost and the turbine
- trips.-~Drywell pressure exceeds 2.0 psig.
The Main Steam Isolhtion Valves close on a Group I isolation resulting from low reactor.
, - rdc .
level. Thelreactor depressurizes to the point
~
X,/: where.HPCI trips on low steam pressure and LPCI is initiated to maintain level. The water from the exp.ansion joint has incapacitated theicondensate pumps. An Alert should be H - declared.
L9: 20 'Drywell pressure.has now reached 2.4 psig as a result of a packing leak on the.HPCI MO-15 valve.
- Fifteen rodo have failed to insert.. They are:
- 1. 22-03 6. 14-31 11. 10-23 a 2. 22-59 7 42-55 12. '26-31 3.- 38-03 8. 50-27 113. 34-35 14 . 38-59 9 54-43 14. 16-11 :
li . 34-23 10. 06-43 15. 18-47
' Radiation levels increase in the condensate
~
9:30s pump area (ARM 1.9), Moisture Separator Area (ARM 2.10), and'the Reactor Building (ARM 2.11).
Low' level in the condenser hot wells is annunci-ated'due to the crack-in the condensate pump line expansion joint.
P, y~
i ..
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I Detailed Scenario for Unit 3 j
'9i45'. Condensate. pump room is flooded-to 8 feet due
-to drainage of the hotwells. Results Engineer reports a missing Test Engineer last known to,be. working on a problem. dealing with high oxygen in the condensate system.
Airborne activity 10:00 Torus water is 15.6 feet.
-6 in the condensate pump area is 10 ci/cc I.
The Stack Monitoring System has now been repaired and is put back in service.
-10:15 Test Engineer found in Moisture Separator Area uninjured but contaminated.
10:30 SRM's and IBM's indicate reactor is still sub-critical. Attempts to insert the rods locally ,
from the hydraulic control units is successful H on 11 of 15 rods. Low pressure alarm on the Back-Up Instrument Nitrogen System is received in the Control Room.
10:45 Investigation reveals pressure regulator f ailure and a crack in the Nitrogen line just as it if;
Ns enters the isolation valve room. While working on the HCU's, operator notices water coming from the North Isolation Valve Room. Crack is reported near the MO-11B valve of the Core Spray Sub-System.
10: 50 'B' Core Sub-System'is shutdown and repairs a are initiated.
11:00 .All.-rods are inserted. .
11:15 Airborne activity in the Reactor Building 165'
-6 elevation continues'to increase.to 5x10 ci/ccI, due to RWCU line shear.
. 11:30 Attempts to' repair the RWCU MO-15 isolation breaker are successful and the valve is closed.
Level is maintained by CRD.
12:15' Level Recorder (Red Pen) 3085 begins to drift low. Airborne activity in the Reactor Building
-6 are 4.5x10 ci/ccI. Efforts continue-to repair the Core Spray line and' mitigate problems i associated with the condensate pump room flood.
M(j; 12:20 -Investigation reveals malfunctioning recorder.
All_other level indications remain constant.
~
g:
Detailed Scenario for Unit 3
- 1'2:45 Fire reported at MCC 30 B 38 in Cable Trays. '
No off-site assistance is required. Fire is caused by electrical short.
1:05. Fire is under control. Indication of Core Spray MO-12A valve is lost. Investigation reveals severe breaker and cable damage.
.1:15 . Site Emergency is declared.
.1:30 Fire is extinguished. Fireman is_ injured while insuring no recurrence of.the fire. Serious cut to'right leg with possible contamination.
Off-site medical assistance is requested.
1:45 Repairs are initiated to restore the 'A' Core Spray System to operability.
2:00 -Fuel pool filter demin injection line shears on 116' elevation. Vacuum relief and check valve have failed.
P:06 Fuel pool filter demin trouble alarmEis received p in Control Room. RHR to fuel pool spool piece
(^g s_ is not installed.
g
,:10 2 Fuel pool filter demin pumps trip on low suction.
2:15 Investigation.on refuel floor is halted due to radiation levels from jet pumps stored in fuel pool. ARM's have alarmed. Investigation on 165' elevation reveals that moisture from the RWCU has electrically shorted'the annunciator panel. ..
2:20 Operators request fuel pool spool piece'to be installed. Attempts to open door to South isolation valve room-to open locked closed RHR valve, find it j ammed due. to maintenance equipment _which has fallen on it. Operators initiate efforts to look for water from fuel pool. Any' attempts to close injection valve _.
fails due to a misplaced valve handle on a siezed valve.
2:30 Refuel Slot- Area ARM Of f-Scale; Refuel Bridge ARM Off-Scale; Fuel Pool Area ARM Off-Scale; Radwaste Filter Pump-Area ARM 10 mr/hr.
13 LJ i
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- g. Detailed Scenario for Unit 3
}u,I -
-2:36 A--report :is received in the Control Room that 91' elevation isfrilling with water and'some
- wat er- is coming from
- the Laundry Alley on
'116' elevation.- Fuel pool 1demin injection line should be closed. . Locked closed valve on RHR to fuel pool line in N.I. Valve Room is found-to be-hard to turn.
2:40- RHR_. fuel pool spool-piece is_ installed. Locked closed.R11R valve-is open.
.2:45 operators'rlood fuel pool with RHR.
2:55' Fuel. Pool is flooded.
3:00 Radiation effluent levels rea'ch Ge'neral' Emergency
. levels.
'3:15 . Radiation effluent levels are:
4
, ., . g 5-lxl ci/second noble: gas 6
- xe 1.1x10 ci/second, I-
~
General Emergency is declared.
3:20 3:30. Radiation-effluent levels reach alert conditions.
~
-3:45 Recovery Phase discussion commences.
-4:00 Exercise is-terminated.
h.
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,1 '
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,-~c DETAILED SCENARIO-FOR UNIT 3-Initial Conditions Both-Units-are operating at continuous full power. Unit 3 has-beenLoperating for eleven
. months and Unit 2 has ' recen tly comple tod ia refueling outage. .The high. range-gas monitor-
> of1the. Main Stack-Sampling Station is being modified to rearrange the' piping' layout and 1s-therefore blocked. This monitor may tur placed in service within 4fhours. The 'B' gas monitor is out of service and awaits parts
!which~are unavailable on-site. The.A' gas monitor failed low at 04:45.. U pon inves ti.ga tion ,
theE'A' gas monitor is found to berelectt1cally shorted.
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- TIME S'CENARIO EVENT PBAPS EXPECTED ACTIONS 4:45 'A' Gas-Monitor fails Operator sent to investigate.
downscale. The high range and 'B' gas monitors are out-of service. The 'A' gas monitor is electically shorted, 5: 45- Shift is informed that ' Operators initiate shutdown to meet repairs-are extensive. Tech. Spec. 3.8.C.8.
Unusual Event declared.
~
Internal communications commence.
- Off-site communications, initiated from Control Room.
6:00 'A' recirculation pump-high seal leakage is f-()
t,_ annunciated.
6:30 'A' recirculation pump seal pressure indicates slight seal wear. Dry-well. pressure is .25 psig.
-_ D ryw ell sump pump out rate is,.75.gpm.
6: 45- Drywell pressure reaches Operators increase drywell cooling.
.35 psig.
7: 00 Drywell sump pump out rate None is-3.5 spm.
~
~
7 : 15. . "D'rywell Hi-Low Pressure" Operators follow normal procedures to annunciates. reduce drywell pressure. As MO-74 (Main Steam-Line Drain) is closed, pressure begins to decrease.
~(r~)N C
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TIME SCENARIO EVENT PBAPS. EXPECTED ACTIONS
. f's, .
^ -l:30 Drywell sump pump out rates begin to decrease.
Process: computer is dumped.
-8:00 *
'H.P. "ech, performing H.P. field office notifies shift.
routine surveys reports
.high airborne activity Further' surveys conducted on Rx near RWCU pump rooms bldg. 165'.
165'.
~* RWCU shows slight flow-
- Accident analysis begins.
increase.
- LShift' dispatches operator to investigate leak.
8:30 -Investigation reveals steam
- Shift attempts to isolate RWCU both leak in RWCU isolation valve in Control Room and locally at pit. breakers.
Evacuation of Rx Bldg. 165' el.
- Investigation continues, r%
- t j
- . Accident analysis continues.
- Damage Repair Group dispatched.
~* MO-18 closes 8:35 MO-15 will not close.
- Breaker and terminals are .
damaged due to explosion.
e (Loss of indication in Control Room).
i H8:45 Process computer is regained.
9: 15
- Annunciator indicates
- Accident Analysis begins.
I- Operating Basis Earth-quake.
- Operators follow standard procedures <
RWCU line is sheared. Maintain level by LPCI.
- Condensate pump room is Evacuation of both areas.
- ('N flooded due to crack in r ( /- Cond. PP. expansioR
- Accountability initiated.
joint.
~ "
-ScramEon low level..
- Investigation'for other damage
. (g. ) *
. due to earthquake begins..
Radiation--levels
- increas @-Rx. b1dg. .
135'Jel and Turb.
- Evacuation Assembly Group dis-
' Bldg.: 98' el. -
patched.'
-Condensate Pump ,
- Alert declared.
Room.
- Severalorods fail to
" insert'(Rx subcritical).
Internal and Of f-site notifications Commence.
Loss - or ' vacuum.
~
o
- Personnel-Safety' Team activated.
l
S team leak on 'MO-15 HPCI.
- Plant Surveys initiated.
- Field Surveys initiated.
- Dose Assessment begins.
9:45 .Results Engineer reports. ~ Dispatch.' interim Search and missing test engineer Rescue. Squad.
last known to be @ Cond.
= Pumps.
- 10 : 15 .- RWCU leak floods 165' el
- Operators dispatched tct investi-down'to:135-el. zContaminates gate'HCU's. Attempts to' manually
' H .' C . U . area. insert, rods fail.-
- - . Test' Engineer found.
- Investigation reveals one core;
' standing on piping loop inoperable due.to crack'ed.
in moisture. separator line near MO-11B (water coming.-
1 area unin~jured, from-North isol. valve room),
contaminated.
- Damage Repair Group dispatched.
to repair core spray line.
'- Operators maintain level with C RD . .
i 110:30 Low pressure on.Back-up.
Opera, tor sent to investigate. Reports instrument nitrogen; failed' pressure regulation and system is annunciated cracked pipe.
in Control Room.- .
e
11:00 Rods insert. Radiation levels in Rx bldg.
> increasing.
11:30 RWCU isolates, MO-15 Breaker Operators maintain level with CRD.
repaired.
12:15 Level Recorder (red pen) Operators check other level indicationse 3085 begins to drift low.
12:20 All other level indications Investigation reveals malfunctioning are stable. recorder.
Fire near Core Spray MO-12
- Fire Fighting Group activated.
12:45 BKR in cable tray, system No off-site assistance required.
inop.
Site Emergency is declared.
EOF manned, notifications commence.
805 Fire continues, but is under control.
1:30 Injured fireman in fire First/ Aid Search and Rescue Team area, Serious cut to dispatched. Off-site ambulance right leg with possible requested. Hospital and RMC contamination. Possible notified.
broken left leg.
- Site evacuation and accountability initiated.
- Access Control Group activated.
2:00 Fuel Pool Line shears Accident assessment begins.
VRV fails Check Valve fails 2:05' Alarm in Control Room Operator sent to investigate, indicates fuel pool trouble.
2:16 A t temp ts to flood
- Operator reaches fuel floor.
fuel pool fail.
- Fuel floor ARM's
- Operators' attempt various methods alarm to till fuel pool radiation
(~)' '
mm . levels inhibit their attempts.
2:36 Jammed door _ lock to North
- Operators close fuel pool Isolation Valve Room and demineralizer inspection jammed valve stem prevent line_(165' el).
opening of locked RHR valve at 135' el.
2:45
- Operators use BHR to begin flood of Spent Fuel Pool.
2: 55' Spent Fuel Flooded.
3:00 Radiation effluent levels Level in fuel' pool maintained increase. by RHR.
- Notifications commence.
3:20 General Emergency is declared (radiological effluent exceed .
General Emergency levels
- Dose protection estimates greater than 20 minutes). continue.
- Field sampling continues.
- Dose projections should indicate shelter is. warranted to 10 miles for areas within the plume.
- State representatives at EOF recommend protective actions.
-4:00 Releases are terminated.
- De-escalation of recommended protective actions to be discussed after Plume passes.
- De-escalation to Alert should be considered.
.~
- Recovery Phase begins.
- Recovery Activities commence.
'i: 15 -Recovery Phase to be entered.
- Exercise will be terminated when Recovery Phase entry k'm/ is complete.
C
3
. . ~ s' L_ e MESSAGE NO. 32_
2 TIME: 12:45 1
LOCITION: Southwest Corner, Reactor Building, 135' elevation.
MESSAGE: Fire engulfing cable above MCC 30B38 and smoldering in Breaker Compartments.
EXPECTED ACTION: Fire Extinguishing efforts are iriitlated in:accordance with EP206A.
O -
CONTaOttEa LOCATION: MCC 30B38 en O
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-q,.9 MESSAGE NO. 33 In 1- TIME: 1:05 .
LOCATION: ,
MCC 30B38' MESSAGE: Damage-due to fire includes' loss of M012A Valve of the Core Spray 'A'.
. subsystem. Fire hais destroyed cable '
and Breaker. cabin'ti. e Fire is under,,
control but contin ~ues to burn stubbornly EXPECTED ACTION: Fire Fighting conti.nues, Control Itoom
" . updated. ,
l' A Site Em'ergency should be declared
' ~
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J CONTROLLER t V
MCC 30B38 1
7 LOCATION: -
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- C.e MESSAGE NO. 38
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TIM 3:
2:20 ,
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< LOCATION: South Isolation Valve Room
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I MESSAGE: Door is jammed due to mechanical equipment -
~ .
l E'XPECTED ACTIONS 2 Operators attempt to unjam door Q _
~ .. ,
CONTROLLER '_
~
, LOCATION:- *
, South Isolation Valve Room
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5% d' MESSAGE NO. 39
- 2
- 36
- . TIME:
L. - -
LOCATION: Turbine Building 116' elevation or: Radwaste 91.6' or 116 el.
MESSAGE: There is water in the fuel pool demin. valve room,-91' elevation _ ,, ,
- - radwaste, and in the t
i- Laundry Room Alley.
h ys .
.(,) EXPECTED ACTION: This information is reported to the Control
..~ Room and Operators close-
.j f0el:poolsdemin inspection -
d l'i'nes.
- 4
~ CONTROLLER LOCATION: Turbine' Building 116'
. elevation.(Common Area.
near Laundry Room) and'
' R.adwaste 91.6' or 116'
~
24 elevation.
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'A~ - MESSAGE NO.'1
- --L)-
TIME:- 5:30 LOCATIONS. Control Room
~
MESSAGE: Initial Conditions c
U ni t ~-3 :
~
- _ Operating at full power.
Finished refueling 11 months:ago.
' -* 3A' Heater and SB Heater leak at 1 liter / min.-
1 . .
. Conductivity .574, PH 7.4, 02:A 0.105,.
-B 0.075, C10.072.
71G base-to body flange slight._
. drip @ 350 psig.
- mod.. completed.
- 3 89A internals destroyed - valve closed to act as pipe - Engrg^
~
reviewing - (motor--went to 3B).
- 21 D~ pre-op,upon completion.
- U/3 89D key way rounded, valve open and blocked feed off.
' 'a U/3 HPCI TSV oil' relay possibly sticky (ship parts 4/28).
o U/3 HPCI TSV balance chamber
' to be ndjusted.
', P
~
! [ MESSAGE NO. 2
-Time:- 5:40
~~
L'o cation: Control Room p
[ Message:- Instrument an'd. Control Technician reports that theA' gas moni.,or is electrically shorted in a manner which will require extensive repair.
' (Approximately 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />).
Expected Action: -Unusual Event should be declared.
Initiate GP-3 Normal Plant Shutdown.
i l~ D Controller Locations: Control Room
(
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. _ ,_ .- _. . _ .. _ _= _ . _ _ _ _ . _~ . . -. .
,' MESSAGE No. 3
' Time - ~6:00 f
. Control Rcom
,; .'I.o c a t i -o'n : ,
A l
. Messages- 'A' recirculation pump seal pressure annunciated. ,
Shutdown begins slowly due to various minor problems associated with pre-requisites of GP-3 t
.- ..n,
~~yected Ex Action: Follow Procedure GP-3 (Normal Plant l Shutdown),
t
~_
! Controller-Locations: Control. Room
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- MESSAGE NO. 4
.. v .
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5 Time:
~
'6:30 .
L . . .-
..Lo c a t i o n :.'- Control Room ,
- g. a r
~
k Messages: Drywell sump pump out rete is U .75'spm.
~
! l c , 3 Expected-Action: Continued Shutdown -f h
Initiate Corrective' Actions.
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Contholler Locations: "
' Control-Room L0 l .V ..
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MESSAGE'NO.15: -
'..J' 1
,8 '
Eve'nt No..3
. *, g
$~ ,
i' f.
ff ' r "a k
W l Time 7: 00 , ,e ;
b.
4
' Loca ti'on t~
Control Room -
la ,
i 2 Message: ,
Drywell Sump Pump out rate'is 3.5'spm.-
I.
t' g- ,
. i
- -3 .....
f2 Expected ~' Action: Continued Shutdown.--
f e s
n
'~-_ ~ '
-9 . f. -Controller Location: Control. Room. ;
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e
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... . . . ..~.- . . - . . . - - . . - , . ~ - . . - . . . . .. .--. .- ... _.
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t I:V 11 MESSAGE NO. 6 t'. .
8 ~
i- Times <7: 15'
)+ .
1: ;
i,'
1
. ~
l~ ~
'. Lo' cation: - -
Control ~ Room '
_ -j i
4
^i .
Message: .Drywell-Hi-Lo Pressure Annunciates.~.
[- h
)
1' '--
F p1 1
. Expected Action: ' Operators--rollow Procedure OT-101 p ,
- . 4
~ " '~
Controller Location: Control' Room' i
,- 6
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7'
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ll .
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r i i c; < +
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+ ' t Y2 ;- - ., , _ . - , . .
s , w w- - *
- er s *r+ v * *= v w t-t yt w ,- vwre f
- s' .et eP 7W werciv-w vw. wwwtee,-+ m ev ,.+e d.-es_ - -
-we= w .+-e ,-i ~mvwe=,=*e**w -= ._ _ _narse.-,-..c- -m*
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- I 4 . .- -
4 .,
- ~ ~
MESSAGE NO. 7
-Times ..7: 20 Location:- Control Room 4
I Message: Drywell pressure is now decreasing.
k Expected' Action: Operators verify continued decrease-
,!- in Drywell Temperature and Pressure.
p-
- f. Controller Location: Control Room ._
4 0..
!HO!
9 et 'd 9
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f
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- a 9
t s l -
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e*
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, .. . . . ~. - . . .
3: --( . ,
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.j MESS A GE NO. -- .
.O, .
h LTime:. - 7:30- )
1: . . .a' 3'
Location: -
Cont'rol Room 1 . .
- .a
- t
- ' Message: ;Drywell sump pump out rates have-3
. decreased toc.5 gpm. - Process
'Corputer has just dumped.
1 I
r- ,
f Expected Action: Operators or.STA' attempt to reload process _ corapu ter . in _
- Cable ' Spreading-_ Room. R eac tdr ~'"
Engineer-is called in.
f' t
.. Controller Location:- Con t rol ~-' R oom 49 J
e ls ,
O y q, e r
i_'.-c ,
i 1
._ s N
a 5 A,.
, . L.1 s w . .. . _, :,-, ,, a., ....a.. , , , , , _ _ . . . _ _ _ . _ , , _ _ , _ , , . _ _ _ , _ , _ , _ ,
,---~
MESSAGE NO. 9 e
Approximate Time: 8:00
'~
Location: Health Physics Office Message: Routine surveys have shown that there is high airborne activity _
on 165' elevation, Reactor Building.
RCA form is handed to Health Physics Technician.
l Eb Expected Action: Health Physics Technician reports information to Control Room.
Investigation is initiated.
! i n_,
Controller Location: Health Physics Office e
} S-
-J
1.
. - MESSAGE NO. 10 9
fApproximate Time:- 8 .30-Location: Reactor Water Clean-Up Isolation Valve Pit.
Message: A mist is coming from the Reactor Water Clean-up Valve Pit.
. Expected Action: Operators shall attempt to.back-seat valves ~ located in RWCU Pit and then isolate RWCU.
m Rea'ctor Water Clean-Up Is51ation 1 -
Controller Locations:
Valve Pit, 165' el. Reactor
- Building. -
e .
'a 4 s c
- O,e k
w
+
- w - > ,w .- - 4 , , - --
-e%a we- e,ee- -.e--ecam+ yw,,g.
~,ye.. ,w-- +- -9 4+w T -e t-w-"r r-=v -v~'*w=e f
.. .- - . ~ _ . .
1 -
.r
- MESSAGE NO. 11- -
- o 4 '
Time: - 8:30 (When MO-18 backseat is attempted) 1 Location: Control Room J
f .
i I
Message:- MO-18 backseats but, steam. leak continues.
jl Expected Actio n: Continue attempts to solve problem.
i.
1 i~
! Contrbiler Locations:- Control Room M A I
I ..
r
,g- ',
/' I
=
a 9' Y e
e
' r pe l_
, . . . . . .. -- ., . -- - - , . - . . ~ - . .. , - . .- . .. .
La-w .
e MESSAGE NO. 12 1
Time:- 8:40 (When Operator attempts to ,
clos'e M0415.) .
l Location: - Control Room. _. ,
e i
Message: - Indication has just been lost on MO-15.
i i
! Expected Action:I Operator sent to investigate breaker.
O .
l Controller Location: . Control Room .
I
) - .
o r
i .
@ _I .
S
! 4 L
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1
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3
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4
. - . . . -.... - .. , _ , . . . . , _ . . . . . . ,...-._.,,.._.,_..,..._._._s.._. . . . . . ..-..__.....,_.,__,._._o__ . . _ .,, , . ._, . _ . . . . - . . . .. . . . ,
. s i -- . -MESSAGE NO. 13 li s
Times' - 8:45
~ -
Location: Reactor: Building 165 ' elevation.
.at:M0-15 breaker.
E Message: Breaker compartment looks as if-it were blown out violently.
Breaker cabinet: is - destroyed ~
and terminals are badly damaged.
-(Approximately 2-hours are required to' repair the breaker.)- .- .,
a i
Expected Action: ' Damage repair is initiated..
~
, Controller' Location: ' Reactor. Building 165!-elevation. -
.Mo b reake r . -
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+ ,
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' MESSAGE NO.-14
. s.
t _'
.3 g-
's
- 5) , Time's. 8:45 i-
. Lo'ca t io n : Control Room
+
. Message:- Process Computer'is regained.-
IL. .
and reloaded.
i 1
4 i ..
Expected Action: ' None Required -
f-J f
- ., - ~
m n.
' Controller Location: Control Room h
- - g k,... f.
y, js -
f- - -
.e
% './"+p e + -
4 i
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l -: .
4 f
i '~ . .
h F =-
3..
1 -
s E 1! _
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. 4
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b ,
c L
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t': z i *
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i" 4 e ~ ~w- v v w w w, m- w n-w w ewn w.g w e ,-re.,,r=wrees*m ve-s+ .e +s-+w w u-e,w 3 m e sse ,+ .e- - e e w w**, e - - e, -s re.e e-w-. - e w -r e =w s- w eewees.. reme .--t w - -e www +- -- -+w+'*
A4e-ME? SAGE NO. 15 O
Time: ,9: 15
~
Location: Contro1.Rpom
~
I Message: 0.B.E. annunciated'in Control Room, The building has just been jolted by an 0.B.E. earth-quake. .RFPT tripped on low suction, the Rx scrammed on. low level, HPCI maintained' level till tripped on low steam pressure, s GP/I on low level, level is now maintained by LPCI. Rx is sub-critical. The.following fifteen' rods have failed to' insert:
- 1. - 22-03 6. 14 11. '10-23
- 2. 22-59 7 42 12, 26-31
'38-03 8.. 50-27 34-35
- 3. 13.
('7hx 4. 38-59 9.. 54-43 14. 26-11
- 5. 23 10. 06-43 15. 18-47
~
The following. annunciators _ _
are alarming ~
Low Hotwell Level Los.s of Vacuum
- - Drywell Hi-Lo-Condensite Pump Overload'
' Group I, II, III isolations
- Turbine Low Vacuum Trip .
L .
l.
Expected Action:
Operators will follow Trip -
procedures and~ associated GP's (3, 8, 11E). An Alert should be declared.
Controller Location: Control Room t-l
s
.g MESSAGE NO. 16 Time:.
This information will be verbally
- given as the operators proceed through-the Steps of the Trip-Procedures..
~ Control Room
-Loc a t i on :
~ Message: Trip Proc'edure Step Message T-100 2 ' Scram and GP II and III are verified.
. T-100 4 SRM~&-IRM's indicate ,
.sub-critical.
- T-100. 5 13 kv ' transferred.4~
T-100 7&8 Turbine - tripped' and-generator' locked out.
- lf'%
'As
~
T-100. 9 Level:is maintained tur LPCI af ter HPCI
. ' dropped below minimum.
- operating criteria. _:
T-100 '10 'DW' Inst.-N2 can be
, restored.:
T-100' 12-1.4 . NocSRV's; cycling ,
s
.or open.- .
- i
- i T-100 16 V'acuum .
T-99' PSR 3- Level. +.30" l
No-indications on .
T-99 PSR 5
.the .' Condensate pumps.,
T-99 PSR 7 All rods not past 06 - Go to T101 RC / 0-9. -
~
(Go to GP-11E).
T-99 PSR 5 1.
, . . _ , , . ~ - . . - . . .
4 i
~
l
,. l
~
Trip Procedure Step Message ;
j Y 's v-T-99 PSR 9 GP'I, II and III can be reset, q M0-15 still open.
T-99 PSRll- Can start any recirculation
^'
.'~ p u m p'.
g.
-. , m
~
T-99 PSR14 Reactor Temperatur.
(RPV-Pressurization
- Curve) is in' safe Zone.
T-99 PSR16 S/D cooling inter-locks'can be cleared out'and S/D cooling
' established, j T-99 PSR17 . Depressurization_
not required.
4- T-101 RC/Q 9 All scram' valves are not open.
'O 3sjf ' T-101 HC/Q . 1. 4 All. rods are not inserted.to.06.
T-101 RC/Q 26 Scram.willc reset. ~
SDV radiation levels are. normal I (GP llE).
~
T-101 RC/O 21 .'All SDV vents and ,
+
' ,.- drains are open. ,
T-101 RC/Q - 17' - Rod motion is observed" *
- but very slow.
Operators will follow Trip' Procedures-Expected Action: ,
and associated-GP's (3, 8, llE). . An operator will be utilized to operate the Hydraulic Control Units of.the l -- ',
Control Rod Drive System. -Operator .
is'sent to investigate Hotwell low level.
Control Room; HCU Area; Condensate-Controller Locations: '
es . Area 116' el.
A
--+; . , - - , e., e. .- ., . , + . , ,rm, e,,,-, , ,, ,, wwe , e ~ ~ ,,.-,m,
r Fu MESSAGE NO. 17 DJ
' Time: . 9:45 L6'ca. tion : ~ Control Room (shift superintendent)
Message: The Results Engineer has just reported a missing Test Engineer, known to have been working on an oxygen leak into the. Condensate B System. He is suspected to have been in the condensate pump room.
i EXPECTED ACTION:_ Personnel Safety Team is' notified -
and the Search and Rescue Group i
'h ,
dispatched..
CONTROLLER- ' Control' Room LOCATION:
l 6
i l
I 4-v-
i . k./
+
e-.-. - - - - ~ - - - - - . , - - - ,s,-, _,,-,,,--n+ . .,.-w.-..._,. ,e---n,._- . - - .,- , , + --
I' J
s MESSAGE NO. 18 i
.\
-l l
TIME: .
~
When operator reach'es' moisture separator. -
~
. area or condensate Pump Room.-
LOCATION: Condenser-Area. >
+
MESSAGE: There.is water below the steam bypass
-7y piping down to the Condensate Pump Room.
. (,b' The Condensate Pump suction expansion joint is-catastrophically. broken and-the
- room is-flooded.
'Y w
-' EXPECTED ACTIONS: - Operator reports information back to Control Room.,
CONTROLLER
. . LOCATION: Control Room (accompanies operator from Control Room).
N e
. . . - , , . %+
/
kln I MESSAGE NO. 19 TIME: When a search and rescue squad has ,
covered the southwest corner of condenser, i-LOCATION: Southwest corner of condenser
~
MESSAGE: The Test Engineer is.found'trapp'e'5 Setween the condenser and concrete wall.
He is contaminated (see body sketch)'but not injured. Minimum effort'is required to dislodge him.
) Search and Rescue squad rescues Test EXPECTED ACTION:
Engineer and decontaminates at treatment
- facilities. _
CONTROLLERS: Southwest corner of condenser near
" conductivity cell 1'
e NOTE:- A person will be' u' sed as'a test Engineer at the location.
Q' I - -
1 9 -
~ . , - .. , , , - , - - , < - a w s , e,-- <-,w e , , - . - - , - - ,.---r-, 6 -er, e -,m, v+~ '
. - - . - . ~. .... ._ . _ . . . . . . . . . . ..
4 d
)
MESSAGE NO. 20 j.
I
~ '
- TIME:- , 10:00 .
LOCATION: Control Room 4
~
MESSAGE: 'A' Stack Monitor is back in Service
~
E t
i i: .. -
EXPECTED ACTION: Opera' tors utilize' data to determine l- i- release rates.
- t. - '
CONTROLLER LOCATION: . Control Room 4
4 t
+ e w *
- y l i
. i I e
e
'l 4
t s
)
j \-
e + a-
--rmarve,<---v v v s =we~-v~,-r-+ = e v e n- we ,N wa,e- - w r - Nw-- a , m , v v e m --- - .-- , vs e-- w w. ,-s e-o e s 6m-nw wwwrer--w w sr w w - w,me m e e st , r
. . . _ . . . _ . _ _ . .- _ __ _ -_ . . . _ - i _. .
4
+
, e i
, s. +
MESSAGE NO. 21
. i
- - TIME
- 10:30 . .,
'r
- LOCATION: - Control Room MESSAGE: Back-up Instrument nitrogen low pressure
Annunciated.
1 -
_ e b EXPECTED ACTION: Operator Sent to investigate o
1
'~
O CONTROLLER i . LOCATION:-
Control l Room- ,
8
' O $
N n--+-"
4 4 j-
- g i
(
4 * .
[.
.h 4
e 3.,
i t
, e
-l .
t i
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. . *.*i f
.I f
t ,
e r - w w,,- my-- .we., ,y.. p- -w....e.,e,., . . . .,m,-,,- y.,%=c.-esie -.,ww.. .w.,e, s5.,.,-.,n-,,,,....mww.- m+ , . e.,....w,.p,.,,m,,.w e i. v., - - - + .ww.n-w.- y- - ---e- -- -
f
- 7
- A MESSAGE NO. 22 b
~
TIME:- .
When 'opei ator' reaches Inst. N2 ~ Rock. .
~
LOCATION: Back-up instrument nitrogen Rack (135
elevation, North east Corner Reactor Building).
. u-MESSAGE: Pressure Regulator has f. ailed and pipe
~
$ is cracked where .it enters the: isolation
~.
Valve Room. ,
e,-
' EXPECTED ACTIONS: Operator reports to control. Room and Damage Repair.is-initiat'ed.-
9 4
- CONTROLLER LOCATION: Northeast Corner of Reactor building, 135' elevation.
4
- c. .
. . - - .. , -. - .. . ~ . . - . . . .
6
.\/'
MESSAGE NO. 23 f
1 TIME: 10:30 ,
l LOCATION: Control Room i : MESSAGE: Rods- 22 14-31 10-23 22-59 42-55 .
38-03 50-27 .
~ "
38-59 .54-43 34-23 ~ 06-43 .
have inserted. The remaining rods
- .' are still not inserted but-moving-
- slowly. R e a c t o r~ i s 's u b c r i t i c a l .'.
{~ .
44 -8hb
~
EXPECTED ACTION: Continue efforts to insert remaining '
l rods using procedure T-101-I l
^
V .
^
- - CONTROLLER .
l LOCATION: Control Room-j-_
l ..
O .
i t ,
J g* o e v- - r .,,-g-yesa w-+- --,,-e ,, . . . , . , = ,,-=. ,-y ~,..,,e v - , ,-,. - = - -,e,w. e . - . - - ,u-,. ,
l r
o .
I g/s r-
' MESSAGE NO. 24 l I
i
. 1 1
. . TIME: 10i45 L
LOCATION: North ' Isolation . Valve ' Room (operator at HCU's working on rod insertion.)
l ~
~ Water is running under the door l MESSAGE: !
-(approximately 25 gpm) of the North- !
isolation Valve room and over. floor l of Reactor building'.
~
i .\
.sJ 1
EXPECTED ACTION: Operator reports this to Contr'ol Room :
I and investigation is initiated
~
=
CONTROLLER' - '-
. ~ Nohthi.Isd1ationl Valve' room LOCATION: '
[ - -
L l
< x l
i-T .
_g e
N e
~ , - ,
/
N MESSAGE NO.-25 -
4
. 3 TIME:
When key is obtained and North ~
Isolption Valve room is entered. ,
- j LOCATION:' North Isolation Valve Room-
- T
~
MESSAGE: Crack in Core Spray.line near MOllB. -
Crackvis.1 foot long and is inch '
'across at its widest point. ,Th e 'B' Core Spray System-is not operational- '
i with this crack . .,
Activate _ Damage Repair Group.
'B' l g- EXPECTED' ACTIONS:
(a Core Spray system shut down and blocked.
CONTROLLER . . ~
LOCATION:
North Isolati~on Valve Room. , .
t
% M a
l F'9- (
.t,' '
O m
. s _
9 a",
. '#5 w
\ *
.5 D
~~
s n =~-r ~ ~ , , . . , .
,,_w.,_.,__,_,,,,j,,____,_,_,,"
'* . 4
. E s
k? ,
e.,"
6,-
- y ;j ,
u r~ . ,, .-
,. 3 .-
+-
rn,., .
,/1 j ,
MESSAGE NO. 26 sc, p,
n..
p -
=
l TIME:- --
11:00 .
_ 4 t -- .
~
LOCATION: Control Room- l 7- .
s.
..x L.
I~ :) .m i~
f' MESSAGE: All rods are inserted
- y. .
j 4 -
4 .,
- t. '
EXPECTED ACTION: 4 F b. ..' CONTROLLE_R_ .
LOCATION: - . Control Room e q-
' - .se
- W
- 6 4 5
=-
3-
-h e v u.] #
^
J
[ */ r 9, .c a .
3
=
4
- s - ,
'e 9 .. -
b q "
I 'S
$- c I e .
, r -
g-
. ~
4 i '
- 9
-\
(
(
+
, e * ~
i.
S 4
7 A*
I' ..
s E. =
d m (
+. I i T 4
4 w
e 4 # e .
{. .. -
e
}
g..n N i wa, , s -w- , ,- ,,- N .r~ e ,-n,-,% w~. ,.,,n,-wm--,-- -mes,.,,,----~ne.,.,,-e--m-n--.--,.,,.n m.-...w..,.--~,.---wn--~-i.s..,.-.-,~ - - ~ ~
/
MESSAGE NO. 27
- TIME: 11:30
- .- l LOCITION
- , MO 15 Breaker l
MESSAGE: The Breaker hits now been repaired Repair' Group r'eports-in formation -
~
EXPECTED ACTION:
to Control Room. Control Room closes _
MO15. . ,
lo 7
CONTROLLER '
M015 Breaker LOCATION:
I e l . .
I -
g a 1
+p
' a 4
e 4
L ..
I p. .
-q f .
i'a
- l ._
! . '[1 4 "
+
! i t
.-- , - y.- , , , , _ _ , . ,-...-~~..,.J,l_.. -,, ,...,,.,_m...-.,-.,,2s.,. _ . . ... ...,.._...&.,-.,,,,%...r. .-_.m_,--m-- . -. -. . + _ _ , . -
!- 7-
' f i 1
. :i s .
l~
MESSAGE NO. 28 :
_-J-i
?
I i
!= TIME: -
when MO 15.is closed j 5 . . s i ,
t-4, . .
!- LOCATION: Control Room i
r t- t p, s j - MESSAGE: Level is maintained by CRD. .; -
F i
i t-i-
- EXPECTED. ACTIONS: ,
- 4 i
i i.
4 L. .
t J CONTROLLER- 'l I'.-#, .
~
LOCATION:- - Control Room' i .
I; ( . f 4
6 em - .
l 4 . .
P L' - . 6 r
F
[ , , , .m .
+ -
y +.
l
[ ~; .
e -~ #
~
~ ._#. '
i _
. 4 4
r r 2 l
t i
, 9 _. f t-f.
U . .
- 1 3
+
r r-
_v'
- o. :
j '. '
. g .--
9 h e
gj
- \ .
i b - .
- f -e t 'r e b + ,
a : .,, h-, p,ym- 4 p,", -
, p , ,, ,. , .
u- _ .__._.._._,;_______,, , _ .
- -y MESSAGE NO. 29 s
p
- r. . ,
TIME:- when operators notice downscale pen and
- i I. and ..
C. Technician is called in. ,
P LOCATION: Control Room (level Recorder 3085)
MESSAGE: Investigation reveals malfunctioning *
- recorder.
~ '
EXPECTED ACTION: Initiate repair of' recorder J
. CONTROLLER ,.
LOCATION: Control Room
\ -
g .
1 I.
er e
f O
b 9
I
'l i
l MESSAGE NO. 30 ,
' TIME: . 12:45 1 LOCA' TION:_
North Isolation Valve Room (Damage Repair Team) or first person seen MESSAGE:_
Smoke is coming from a fire in the Southwest corner of the Reactor Building.
EXPECTED ACTIONS: Follow procedure 206A. Fire brigade ^
activated.
CONTROLLER '
D LOCATION:_ MCC 30B38
-.m /
O e
O
?
o e
b s O e
o O ,
9 3 w O
e
.. _~ . - . - . _ - - _ - . - - -.- _ .- _ _ . - _. -..-..-- .. - - ...._.. . - . _ -
t < >
. r 4
1
~- . .
3 i-MESSAGE NO. 31 f ,
e e '
t i
i
-t
- TIME: 12:45 >
f y
- . t
. .~
1-t .
J i
Control Room i LOCATION: !
i,-
4 ..
Core Spray MO 12 A indication is lost. j I MESSAGE: i nw i- '
L EXPECTED ACTION:- _
Send operator to breaker _. .
t j
I- -
1
' :.V6 CONTROLLER'
- LOCATION: Control Room .
- A e -'*a. s i
- z e d g # p ['*^ s
+ * 'e >^*-'
- V o f & ,. >- 4
" 1 (
"3--
= .,-.l
- 9
+
v I
, 4 ' t
.* f[ i 2 _ .
G h A 3 ' ~# my.
c 9, 6-l
]
4.- ,
f
, 9-l:
l . .
F 9
e r L L r s , ,
j +
- g. s a
.5 4 -
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+
5
=
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- f* M'*P #*'N4 @ M' C W S"'-d wMrm '- N
_ . - - - . . _ _ - . _ = - . -- . ~.
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'.QJ MESSAGE NO. 34 TIME: - 1:10 i- ,
LOCATION: MCC30B38 ,
7
(
l MESSAGE: ' Fire'is oUt. Severe damage to Breaker and j over head cable.-
EXPECTED ACTION: Follow procedure-206A,-Operators Post -
Fire watch and begin' clean-u'p and
' Damage R'epair.
IV CA CONTROLLER -
LOCATION: MCC 30B38
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1,'
s MESSAGE NO. 35
-TIME: 1:30 ,
, LOCATION: MCC 30838 MESSAGE: Auxiliary Operator is :.njured. Severe cut to right leg. Off site assistance
' is necessary. Unable'to walk. P.oss_ible '
contamination.
EXPECTED' ACTIONS:. First Aid / Search and Rescue Group activated.
~
O .
i CONTROLLER .- .' .
'~
LOCATION': . MCC.30B38' .
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4
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L f
T i
lO MESSAGE NO. 36 TIME: -
- 2:06 -
> LOCATION: Control Room-A -
i
~ -
MESSAGE: Fuel Pool Filter Domin. Trouble
' annunciated .
EXPECTED ACTIONS: Operator sent to investigate e . .
- t I i
! CONTROLLER-
', LOCATION: Control Room t
a .
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E
-r
~
O MESSAGE NO.-37 TIME: When any. operator reaches fuel pool annunciator panel on 165'
. elevation.
LOCATION: Reactor. Building 165' elevation, Fuel Pool Panel
-- ~
v MESSAGE:- The panel has been electrically
. shorted.due to moisture.from RWCU line break.. Fuel pool-spool piece is not_ installed.
[~m l
4 -
Operators request! Fuel Pool.
- EXPECTED ACT O'NS: *- -
- Spool-Piece to be' installed.
CONTROLLER I Reactor Building 165' elevation, -
.v -
LOCATION:' ,-Fuel Pool Annunciator Panel i -
l o .
% e v ,, ,- r p , = - ,,+w . - - - - . . - 6 ,e - * - - - -+e .-, - - - , --+t-* -
t -
v s- - - - h , w 4
/,
'%)
MESSAGE NO. 40
. 2:36 TIME: .
~
LOCATION: South Isolation Valve Room MESSAGE: Door is now open. Valve stem is stiff and turning slowly EXPECTED ACTIONS:
r~g
( )
CONTROLLER -
LOCATION: South Isolation Valve Room _
l 6
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i.
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- j.
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MESSAGE NO. 41 E
i h
I f TIME: - 2:40 -
~
LOCATION: South Isolation Valve Room
.t
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5, MESSAGE: Valve.is now open i.
1 ..w ,
h' r
EXPECTED ACTION:
f i.
CONTROLLER .- ..
LOCATION: -
South Isolation Valve Room.
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, y, , , _ '_ _t _
Ot MESSAGE NO. 42 1
TIME: - 2:15 - .
LOCATION: Fuel Floor Door MESSAGE: Raliation levels prohibit entry to j ~~
Fuel Floor i
I i EXPECTED ACTIONS:_ Investigate 165'. el.. annunciator-i: pannel
, +
CONTROLLER LOCATION: . Fuel Floo'r door, i-i e
s
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J MESSAGE NO. 43 TIME: 2:00 to.2:36 ,(contingency)
~
LOCATION: 165' elevation Reactor Building
-(if, attempt.is made to close the Demincralizer to Fuel Pool manual valve)
MESSAGE: Valve handle is misplaced. Valves cannot be closed til 2:36 1.
EXPECTED ACTIONS: 'At 2:36 operators will'close valve d
CONTROLLER- ..
LOCATION: Fuel-Pool Demin Pumps T
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b.
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n,w~,- e s.,-...,,, .- , e--+.,,,y--p,r-, . , , e +
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)
MESSAGE NO. 44
(-
~
TIME: ,
- 2:40' ,
- s. ,
> LOCATION: ,
- 165' elevation, Reactor Building 6
? ~ ~
MESSAGE: Fuel Pool spool is installed 4
Begin injection with LPCI EXPECTED ACTIONS:_
=e ,
' =
b e ' s t
- CONTROLLER
> LOCATION: Fuel Pool Spool Piece r
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1 -
I D
6 9
d
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- 6 0
w gree w -, y-- y 9 -y,w,verss=---,.t wv* ,, w y e = =vy--.-vve ,,v- .,v.ew,--,-c.w- r v m i--, w m me ce ar - se m e-- - e e n -- W % m+e --+ e asco w--e e v em e n ww M - - r % --revM'* eta
4 s
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i-
- o MESSAGE NO. 45 TIME 2:55 I' LOCATION:. Rx Building
- .e 4
MESSAGE: Water is cascading from 234' elevation.
O -
EXPECTED ACTION: This information is reported to' i'
' - control room where RHR'is shut down to' m. ,
4
- minimum. -
[ , CONTROLLER '
LOCATION: Reactor ~ Buildilig - ,
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1 1 W-4 M--WrT*gdr'-~y-*g.--i 3vw trw4 g-ev 'tMrT't 1-ebWWW'ww'-w*P*W4 ram-N 7 wW r e43=ryp rYW i m y' +F ' e e*' W w m F ew w ww W 7r7e ff-f' Yu w v my-N'9Nb- P -t P-WeW'F F"g--T T 9e-nf*'N9'W % F
_ ... _ _ ._- _ . _ _ ... ._.. . . _ . . _ _ . . .. _ _ . _ . _ _ _ _ . -_._....._..._._,..__.__c_ -
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MESSAGE NO. 46 d
4' > . ..
.i . -
' - ~
t TIMda. 4:00 l
4 J
LOCATION: All' >
l.
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t MESSAGE:.- . Exercise is terminated
- -J s -
. .sj
~
, L
~ EXPECTED ACTIONS:
.- b b s
}
s
.'1
. 4. ;
.~ CONTROLLER LOCATION: ' All' .
R?
4 0 - 8 4
S e
b
(
L '. 4 *
- . a
I a M0-3-10-33 Limits to be checked
/3 out. <
NJ-a U/3 M0-20 bkr tripped (to be investigated),
a U/3 A0-23-18 doesn't stroke.
Unit 2
- Operating at full power.
- Operating for 3 months con-secutively since last refuel outage.
Common: The High Range gas monitor of the Main Stack Monitoring System is being modified to rearrange the piping and will.be blocked for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
The 'B' Gas Monitor is out of service and awaits parts which are unavailable on site. The
'A' Gas Monitor failed low at 7s 04:45. An Instrument and Control
() Technician is at the Stack.
Action Expected: Dispatch an Instrument and Control Technician to the Stack.
e S
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4
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1 l
DATE~ T.L MM IlEADQUARTERS SUPPORT MESSAGE MESSAGE FOR: EMERGENCY DIRECTOR-Thoro is an immediato need for 20 RO-2 Friskers at PDAPS. Units should be purchased or borrowed from supporting organizations.
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- 3. - . .
TIMM-
~DATE
',. !!HADQUARTERS SUPPORT MESSAGE- - - .
J
< t
. 1 1 _
LEMERGENCY DIRECTOR N MESSAGE FOR: -I F
- A Seismic lEngincor -is iteeded "to evaluato possible -delayed ef facts - ~t
. the cartliquake may have on plant systems.
?
p 4
f-l-
.4 i;
3 ACTIONS EXPECTED:
1 '
- Submit request'to-Site Emergency Coordinator.
f" '
i 4
4 ?
po..
4 l '
FOR CONTROLLER.USE ONLY
,< .l
- 1. ')
e y
i -(JUNE 28,: 1983)
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O
. IIEADOUARTERS SUPPORT MESSAGE DATE TINi:
8 e
- MESSAGE FOR: EMERGENCY. DIRECTOR j A Seismic Engineer is needed to evaluate possible delayed effects
! the eartliquake may have on plant systems. .
t O
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S P
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IIEADQUARTERS. SUPPORT MESSAGE DATE TIME _ _ _
4 I MESSAGE FOR: ' EMERGENCY DIREC' TOR' ;
i
!!cadquarters support.is needed-to diagnose problems'with the procoon compu tcr .",
i
' I l-i . ACTIONS EXPECTED:
Submit request to Site Emergency Coordinator.
4
~
! FOR CONTROLLER USE ONLY-t
.(JUNE 28, 1983)
I:
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4 O
4 HEADQUARTERS SUPPORT MESSAGE DATE TIblE _ _ , _
MESSAGE FOR: EMERGENCY DIRECTOR.
'lloadquartors support is nooded to diagnoso probicilia wil-lo tile 1:n os t on computer.
9 5
0-TO
- h. .
. llEADQUARTF.RS . SUPPORT- MESSAGE DATE T I M M _ ,__.__
MESSAGE'FOR:' EMERGENCY DIRECTOR
!!eadquarters 'OA/QC . support is needed at PBAPS to inspect emergency re' pair methods and approve welding in process.
ACTIONS EXPECTED:
~ Submit request'to Site Emergency Coordinator, f
FOR CONTROLLER USE ONLY (JUNE 28, 1983)-
W e
O
4 i
l.
TIMM IlEADOUARTERS SUPPORT MESSAGg unTu _ __
MESSAGE FOR: EMERGENCY DIRECTOR
!!cadquarters QA/QC support is needed at PBAPS to inspect emergency l
repair methods and approve' welding in process.
1 i
9 i
l l
l S
s o^re r si O iii^i>ou^nrens soevoar "essacs --
MESSAGE FOR: EMERGENCY DIRECTOR
!!cadqua"rbers support is needed to expedite the following purchasing requirements:
o 300 Anti- contamination suits and hoods o 500 Pairs of rubber gloves o 1,000 Rolls of 2 in masking tape ACTIONS EXPECTED:
Submit request to Site Emergency Coordinator, j
FOR CONTROLLER USE ONLY (JUNE 28, 1983)
S 0
f O .
O DATH _ TJMH
!!!4AIJOUAl(TERS SUPPO!(T MisSSAGM , _ ,
MESSAGE FOR: EMERGENCY DIRECTOR
!!cadquirters support is needed to expedito the followissy tstarclicit:Intu requirements:-
o 300-Anti-contamination suits and huuds o 500; Pairs of rubber gloves o 1,000 Rolls of 2 in, masking tape o
O f-I I
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l DATE TIMM.
IlEADOUARTERS SUPPORT MESSAGE
'. J ,
a .
MESSAGE FOR: EMERGENCE DIRECTOR ..' ,
/ .
Investigate' arrangements for feeding. eiabfgency center, and plant personnel on an extended basis.
- s. .
5' c ::; *- .,
./ ~' , ,
4
. ACTIONS EXPECTEDt ,
t-Submit request.to' Site Emergency Coordi$ator. ,
1 - , ,
~
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,=
-,'(
FOR CONTRdLLER USE ONLY i ,g (JUNE 28, 1983) - -
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4 DATE - _ _ _ ,
'TINM
, llEADOUARTERS SUPPORT MESSAGE .
4 e .,
- ' ' ~ - MESSAGE FOR . EMERGENCY DIRECTOR 1, y f
t
- Investigate arrangenents for feeding. emergency conter and plant personnel on,an. extended basis.'
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..DATE TIME-llEADQUNRTERS SUPPORT' MESSAGE-
.N MESSAGE FOR: EMERGENCY DIREC' TOR. _
i-
~
A Licensing' Support Coordinator should be reviewing the plant
-status.and sequence of ovents-to develop reports for the NRC.
.a.
+
1.,. ?;r 3 J.
p .2 L ACTIONS EXPECTED:
- w. .
S- :g.
Submitfrequest'to Sito Emergency gCoordinator, p . h.
FOR CONTROLLEkk USE ONLY
)
' 't ;
. (JUNE '28, 1983) "
. - 'it., ;.;
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4 .
ilEAD00ARTERS SUPPORT MESSAGE ogyg _
.733g , _ _ , _ .
MESSAGE FOR: EMERGENCY DIRECTOR P . A Licensing Support Coordinator tihould bo reviewing the plant
'1 status and sequence of events to develop reports for the NRC.
f f
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t DATE TIME
!!EADQUARTsRS SUPPORT MESSAGE __
1
' MESSAGE FOR: EMERGENCY DIRECTOR
- There is an.immediate need for 20 RO-2 Friskers at PBAPS. ' Units should be purchased or borrowed from supporting organizations.
O. ACTIONS EXPECTED:
Submit request to Site Emergency _ Coordinator.
FOR CONTROLLER USE ONLY (JUNE 28, 1983)
J' D
_s+ --m,,e, -- --,,g.mm-w. -
r-r.,-u-ac.- -- ,-.a n -a, -,m,
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- i. .. -
it TIME g 030 nours rtine inn ReiCToR sysren viLuus s'
ti h
. Reactor Yessel Water Level I inches Drywell Pressure
- peig t.
f, Reactor Pressure // /d psig Drywell Temperature / T. V F
Ii ReactorPowerAPRM(avg.) 70 % Full Power Drywell Radiation M R/hr. 1; l
/D Core Plate Diff. Pressure paid Containment 02.Concentratio @
4 ~
)' Containment H Concentration d %. ((
Recire. Loop A Water Temp fM F 2 '
- Recire. Loop 3 Vater Temp f3d i Torus Vater Level /V 7 reet I
//. 7 Torus Temperature k8 F f Main Steam Line Flow LB/HRx10 767) mR/hr.
Main Stack High Range Rad../ mR/hr.
Main Steam Lhae Radiation
'2- 0 cps l Main Stack flow dd#ro Cat Stack Gas Rad. Mon.
/[ inches Refuel Floor Vent Exh. Rad. Mon./,4mR/hr-j Condenser Hotwell Level
! Condenser Vacuum
- d inches Hg. Vent Stack Exh. Mon. b cpm M Total Core Flow 77 Lbs/HR x 10' i Condensate Storage Tank level feet
- E"" *" * * * * '
Air Ejector Off-Gas Radiation Y/ mR/hr.
ag. Vent h ust Rad. M or M d / h.
l Rx. P211&ing Pressure 7[ inches Drywe ent Rad. Monitor (Gaseous / M cpm j Radwaste Duct Rad. Mon. I7/ cpm 1
4
?
l-I
O . o +o .
a ,
4
! TIME 8 [ *' Ecurs PLANT AND REACTOR SYSTEM VALUES d'
Reactor Yessel Water Level do75' inches Drywell Pressure - reig ,
Reactor Pressure /d /d usig Drywell Temperature !dd F .
.ReactorPower-APRM(avg.) [d % Full Power. Drywell Radiation b4 R/hr. l 1,
f Core Plate Diff. Pressure /[ veid Con +mhnnent20 Concentration 2 7%
Recirc. Loop A Water Temp Od F ContainmentgH Concentration g Recire. Loop 3 Water Temp 53d F Torus Vater Level / Y. 7 feet (
4 Main Steam Line Flow
//. ~/ LB/RRx10 Torus Temperature [0 F ,
f a
Tv-O Main Stack High Range Rad. ./ mR/hr.
i Main Steam Line Radiation "
mR/hr.
Main Stack flow dd #ct? CPM Stack Gas' Bad. Mon. . 20 cps l
Condenser Hotwell Level /[ inches RefuelFloorVentExh. Rad. Mon.AdmR/hr-Condenser Vacuum O I* d inches Hg. Vent Stack Exh. Mon. [/d cpm i, 4
Condensate Storage Tank level 20 feet Total Core Flow 7? Lbs/RRx10' f
- ""**# " (* ** } //, 7 Lbs/hR x 10 Air Ejector Off-Gas Radiation V/ mR/hr.
Rx b1dg. Vent Exhaust Rad. Monitor /dmR/hr.
Rx. Building Pressure iI inches i
Drywe ent ad. Monitor (Gaseous)M cpm Radwaste Duct Rad. Mon. [7/ cpm l .- II t I i
~
9
O ,o s
- t TIME O f.* W Hours PLANP AND REACTOR SYSTEM VALUES _
i Reactor Vessel Vater Level FOS' inches Drywell Pressure
- 2.{ vaig l Reactor Pressure /d /d usig Drywell Temperature /88 F ReactorPower-APEM(avg.) ~/d % Full Power. Drywell Radiation Y R/hr.
i -
Core Plate Diff. Pressure // Veid Con +m4 =an_t 2 0 Concentration EZ
~
Recize. Loop A Water Temp Md F Containment H 2 Concentration C %
Recire. Icop 3 Water Temp [3d F Torus Water Level ' N. 7 feet Main Steam Line Flow /d- [ IB/HR x 10 Torus Temperature fd F I
, Main Steam Line Radiation 78"O mR/hr. MainStackHighRangeRad../ mR/hr.
Main Stack flow h CMi Stack Gas Rad. Men. D cps Condenser Hotwell Level /( inches Refuel Floor Vent Exh. Rad. Mon./ A mR/hr i
4 Condenser Vacuum 2 E-[ inches Hg. Vent Stack Exh. Mon. Dd cpm {
Condensate Storage Tank level 20 feet Total Core Flow dY Lbs/HR x 10 '
1 6
Air Ejector Off-Gas Radiation 3I mR/hr. ,
Rx. Building Pressure ~f inches Drywen Vent Rad. Monitor (Gaseous)/edo cpm
[7/ cpm
-l Radwaste Duct Rad. Mon.
l I
l
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) -
1 O e o po: T i
l 4 1
- 3
-l l TIMs of /i nours rum An ReiCTOR Sysem vuuss jj Reactor Vessel Water Level I25 inches Drywell Pressure
- vsig h
Reactor Pressure /0 /d usig Drywell Temperature / " jut F i, i
ReactorPover-APRM(avg.) 7/) % Full Power. Drywell Radiation Y R/hr. [
Core Plate Diff. Pressure /V void ' Con +mi==mt 20 Concentration 2 T % !
~
Recire. Icop A Vater Temp bd F Containment H 2 Concentration N % !
Recire. Icop 3 Water Temp IM F Torus Water Level /// ~/ feet Main Steam Line Flow /8- [ LB/HRx10' Torus W mperature 98 F ,
]
i i
Main Steam Line Radiation '7(3 mR/hr. Main Stack Righ Range Rad.d / mR/br.
! Main Stack flow d d #1r0 CFM Stack Gas Rad. Mon. 24 cps l ,
i Condenser Hotwell Level /( inches Refuel Floor Vent Exh. Rad. Mon./ 4 mR/hr Condenser Vacuum o7 I. I inches Hg.- Vent Stack Exh. Mon. Do epm 6
Condensate Storage Tank level ~24 feet Total Core Flow $I Lbs/ERx10 Air Ejector Off-Gas Rarliation M FeedwaterFlow(total)/O.9 Lbs/IIR x 10 .
mR/hr.
Rx b1dg. Vent Exhaust Rad. Monitor /d mR/hr.
Rx. Building Pressure 9f inches
}
rywell Vent Rad. Monitor (Gaseous)httf cpm Radwaste ' Duct Rad. Mon, s 7/ cpm l
O O O i
i TIME ()[.1 Hours , PLANT AND REACTOR-SYSTDI VALUES t
Reactor Yessel Water Level 80 inches Drywell Pressure 2.S veig i
Reactor Pressure d reig Drywell Temperature /f<~ F l i ReactorPower.APRM(avg.) d % Full Power.. Drywell Radiation <
> 7_ R/hr. {.
j Core Plate Diff. Pressure d raid Containment2 0 Concentration $ l 1
Recize. Icop A Water Temp 3ro y Containment2 n C " *"t""ti " # % !
! Recire. loop 3 Water Temp 5fO r Torus water Level /c reet !i Main Steam Line Flow O IB/HR x 10 Torus Temperature R)% F ,
Main Steam Line Radiation I mR/hr. Main Stack High Range Rad.4 ./mR/hr.
! Main Stack flow M err) CIM Stack Gas Rad. Mon. //<~ eps
{
f Condenser Hotwell Level o inches Refuel Floor Vent Exh. Rad. Mon. d mR/hr 1
Condenser Vacuum O inches Eg. Vent Stack Exh. Mon. 29 cpm f i
! Condensate Storage Tank level 20 feet Total Core Flow 0 Lbs/HRx10 !
' 6 Air Ejector Off-Gas Radiation 2 2. mR/hr. '
Rr blag. Vent Exhaust Rad. Monitor mR/hr. ;
Rr. Building Pressure 7[ inches rywellVentRad. Monitor (Gaseous) cpm l i Radvaste Duct Rad. Mon. N/ cpm 1
l I i .
o
O e O DO j I
^
l-
- i
.i I
TIME f. Hours PLANT AND REACTOR SYSTEM VALUES M inches Drywell Pressure 2' vsig Reactor Vessel Water Ievel Reactor Pressure 2 78 maig Drywell Temperature /f5~~ F ii ReactorPower-APRM(avg.) d % Full Power. Drywell Radiation 72 R/hr. l
~
I Core Plate Diff. Pressure paid Containment20 Concentration M i;
- I Recirc. Loop A Water Temp 3 771 F Containment 2n Concentration o % -
i Recire. Icop B Water Temp 8 Td F Torus Water Level /36 feet Main Steam Line Flow O IB/HR x 10 Torus Temperature /d/ F , f Main Steam Line Radiation 2-[ mR/hr.
Main Stack Righ Range Rad. . / mR/hr.
I Main Stack flow O kevD CIM Stack Gas Rad. Mon. ' W cps Condenser Hotwell Level O inches Refuel Floor Vent Exh. Rad. Mon. / mR/hr Condenser Vacuum inches Hg. Vent Stack Exh. Mon. 2 5"b cpm ;
i Condensate Storage Tank level D feet Total Core Flow d Ibs/HRx10 !
l eedwater M ow ho % M DsM x 10 l
Air Ejector Off-Gas ParHation 2 2- mR/hr.
- ag. Vent h ust M . & n h or Mr. j r
Ex. Building Pressure - ZI
. inches .
E7/ cpm "r7"*ll V*"t Rad M "it "CG^** "") *P" !
i, Raavaste auct Raa. Mon. :
'l i
O .O .
PO ..
j TIME //) 60
_: Hours PLANT AND REACTOR SYSTEM VALUES ;'
I
- Reactor Vessel Water Level M inches ,
Drywell Pressure 'd vaig .{
i Reactor Pressure 27d weig Drywell Temperature /6 F *{i 7 2- j ReactorPower-APRM(avg.) O % Full. Power. Drywell Radiation R/hr.
i
! Core Plate Diff. Pressure C veid Contah = mt 02 Concentration 2 I%
~
Recire. Icop A Vater Temp 370 F Containment H 2 Concentration O % l Recire. Icop 3 Water Temp 370 F Torus. Water Level /Sb feet !
O
! Main Steam Line Flow d LB/RR x 10 Torus Temperature /d-O F ,
! Main Steam Line Radiation 2I mR/hr. Main Stack High Range Rad. / mR/hr. ..
Main Stack flow 2.Vd-ac CrM Stack Gas Raa. Mon. FZ- cps i 4
l Condenser Hotwell Level C inches . Refuel Floor Vent Exh. Bad. Mon. / mR/hr' l Condenser Vacuum O inches Hg. Vent Stack Exh. Mon. Zs7) cpm condensate Storage Tank level M feet Total Core Flow o Lbs/HR x 10'
- 0"" *" * *
- Air Ejector Off-Gas h A4ation 2 1 mR/hr.
'- Z s' bl4. Vent hust hd. EnMor 2/.W. ;
Ex. aunaing Pressure inches l
Drywen Vent Rad. Monitor (Gaseous) cpm i
Radwaste Duct Rad. Mon. I7/ cpm '
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s O o no '
1 4
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Tm /d//f sours run m mCTOR SMM VAWS inches Drywell Pressure weig ,!
Reactor Vessel Water Level. '8o Reactor Pressure 276 veig Drywell Temperature /JO F
- I ReectorPower-APRM(avg.) O % Full Power. Drywell Radiation > 2. R/hr. {
j :
1 Core Plate Diff. Pressure d veid Containmentp o concentratior2E , j
{'
Recirc. Loop A Water Temp 3GC r Containment 23 Concentration o %
MI /$ $
i Recirc. loop 3 Water Temp ' F Torus Water Level feet 1 Main Steam Line Flow 0 LB/ERx10 Torus Temperature 97 F ,
Main Steam Line Radiation 2.( mR/hr. Main Stack High Range Rad. / mR/br.
Main Stack flow M#&9 CM Stack Gas Rad. Mon. D'f. cps l, f
- Cendenser Hotwell level O inches Refuel Floor Vent Exh. Rad. Mon. / mR/hr 1
n inches Eg. Vent Stack Exh. Mon. 2O cpm i I
Condenser Yacuum __
O
! Condensate Storage Tank level 20 feet Total Core Flow- Lbs/HR x 10' eedwater Mow @otal) O DsM x 10 Air Ejector Off-cas Radiation 2 2- mR/hr.
)
~
25 ag, en us ad. Mon hor 2/h.
l Rx. Building Pressure inches DrywellVentRad. Monitor (Caseous) cpm Radwaste Duct Rad. Mon. $~7/ cpm s !
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nxs /o:3o sours Pun um RuCm srse was Reactor Vessel Water Level 30 inches Drywell Pressure !' peig Reactor Pressure 2 7d usig Drywen Temperature N[ F i
Reactor Power-APRM (avg.) O % Full Power. Drywell , Radiation > 2- R/hr. ;
i Core Plate Diff. Pressure d raid Containment 02 Concentration 2*T%
~
Recize. Loop A Water Temp 360 F Containment H 2 Concentration O %
Recire. Loop 3 Water Temp Md F Torus Water Level / *I~. d feet 6
Torus Temperature a'
75 y Main Steam Line Flow O IB/HR x 10 2C' Main Stack High Range Rad. / mR/br. j Main Steam Line Radiation mR/br.
Stack Gas Rad. Mon. __ W cps Main Stack flow 2Clatfd CIM Condenser Hotwell Level o inches Refuel Floor Vent Exh. Rad. Mon. / mR/hr Condenser Vacuum O inches Eg. Vent Stack Exh. Mon. 2s3 cpm Condensate Storage Tank level feet Total Core Flow O Lbs/BRx10' {
eedwater now @otal) d ros$ x M Air Ejector Off-Gas Radiation 7 2. mR/hr.
Rx blag. Vent Exhaust Rad. Monitor mR/hr. ;
Rx. Building Pressure 92I inches Drywen Vent Rad. Monitor (Gaseous) cpm Radwaste Duet Rad. Mon. -f7/ cpm l
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//1.*l/I 1
Hours PLANT AND REACTOR SYSTEM VATRES TIME 1 i
Reactor Yassel Water Level 3M inches Drywell Pressure !. M veig ;
I Reactor Pressure 27d neig Iryve n Temperature /N F t
1 ReactorPower-APRM(avg.) 0 % Full Power. Drywell Radiation 7L R/hr. !
Core Plate Diff. Pressure C veid Containment 02 Concentration 7+T%
~
i Recire. Loop A Water Temp 7W F Contaiment H2 C n entration d '%
i - :
Recire. Loop 3 Water Temp 3 IS F Torus Water Ievel /S0 feet j Main Steam Line Flow O Ia/RRx10 6
Torus Temperature 9C F .
Main Stack High Range Rad. / mR/hr.
Main Steam Line Radiation mR/hr.
Stack Gas Rad. Mon. ' 36d cps [
I Main Stack flow 29#FD CIM t
1 l Condenser Hotwell Level O inches Refuel Floor Vent Exh. Rad. Mon. / mR/hr 2 C E) cpm Condenser Vacuum O inches Eg. Vent Stack Exh. Mon. l l 6 I
condensate Storage Tank level 20 feet Total Core Flow d Lbs/ERx10 l i 6 Air Ejector Off-Gas Radiation 2 Z- mR/hr. '
Rx b1dg. Vent Exhaust Rad. Monitor mR/hr.
l Rr. Building Pressure <ZI inches cpm Drywen Vent Rad. Monitor (Gaseous)
Radvaste Duct Rad. Mon. f7/ cpm n
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l l TIME // N Hours PLANT AND REACTOR SYSTEM VALifES O inches Drywell Pressure !* Deig !
Reactor Pressure- 27 meig Drywen Temperature /YC F !,
?
Drywell Radiation M R/hr.
i ReactorPower-APRM(avg.) d % Full Power.
' (-
Core Plate'Diff. Pressure A raid Con +.aiment 0 2 Concentration 2 7% '
Recize. Loop A Water Temp 3G F Containment H 2 Concentration O %
f.,
39 F Torus Water Level /5 S/ feet f
-Recire. Loop 3 Water Temp - I 6 f5 F i.
O LB/HR x 10 Torus Temperature
- Main Steam Line Mow 2[ mR/hr.
MainStackHighRangeRad../~mR/br.
Main Steam Line Radiation I Main Stack flow O[9FC CFM Stack Gas Rad. Mon. VV6 cps .j u
i Condenser Hatwell Level O inches Refuel Moor Vent Exh. Rad. Mon. / mR/hr Vent Stack Exh. Mon. 2 57) cpm Condenser Vacuum O inches Eg.
O Lbs/ER x 10' !
Condensate Storage Tank level D feet .. Total Core now N ** ""**" * *
- l Air Ejector Off-Gas Radiation mR/hr.
~ E' *" "8
- Rx. Building Pressure -
inches-DrywellVentRad. Monitor (Gaseous) cpm f Radwaste Duet Rad. Mon. N/ cpm f i
i i
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TIME // .*/O Hours PLANP AND REACTOR SYSTEM VALUES Reactor Yessel Water Level dd inches Drywell Pressure Deig ,
t Reactor Pressure O 70 veig Drywen Temperature ,/,4$ F }
ReactorPowerAPRM(avg.) O % Pull Power. Drywell Radiation >ob R/hr.
Core Plate Diff. Preesure O psid Contahnnent 02 Concentration 2.7% !
~
Recire. Loop A Water Temp 3 F Containment2H Concentration d l.
Recire. Icop R Water Temp i3k5 F Torus Water Level' /b feet !
Main Steam Iine Flow 0 IB/HR x 10 Torus Temperature 7[ F
. [
Main Steam Line Radiation 2( mR/hr. Msin Stack High Range Rad. +/ mR/hr. l Main Stack flow d V#fd CPM Stack Gas Rad. Mon. Vfd cps l Condenser Hontal' Level O inches Refuel Floor Vent Exh. Rad. Mon. /mR/hr Condenser Vacuum O inches Hg. Vent Stack Exh. Mon. 2SD cpm Condensate Storage Tank level feet Total Core Flow 0 Lbs/HR x 10 ee wa r w a sM x Air Ejector Off-Gas RaMation mR/hr.
Rx b1dg. Vent Exhaust Rad. Monitor mR/hr. j Rx. Building Pressure " 3 I
. inches Drywen Vent Rad. Monitor (Gaseous) cpm Radwaste Duct Rad. Mon. (7/ cpm s i.
. i.
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TIMS //.* 30 ' Hours PLANP AND REACTOR SYSTEM VALUES l i
Reactor Vessel Water Level 80 inches 'Drywell Pressure '/* Deig .I j Reactor Pressure .2 7 d veig Drywell Temperature, /.98 F i
ReactorPowe>APHM(avg.) 6 % Full Power Drywell Radiation >2 R/hr. .,
l Core Plate Diff. Pressurs d void Con +mi -ant2 0 Concentration M l Recire. Loop A Water Temp d F Cont.aiment 2H Concentration g l Recire. Icop 3 Water Temp 3 YO F Torus Vater Level ' /$6[ feet Main Steam Line Flow d IB/HR x 10 Torus Temperature 95 'F .
Main Steam Line Radiation 25' mR/hr. Main Stack High Range Rad. . / mR/hr. j l i, I JVM CIM Stack Gas Rad. Mon. [/M cps [
Main Stack flow Condenser Hotwell Level 6 -inches Refuel Floor Vent Exh. Rad. Mon. / mR/hr Condenser Vacuum O inches Hg. Vent Stack Exh. Mon. '2, al cpm Condensate Storage Tank level D feet Total Core Flow d Lbs/HR x 10 Air Ejector Off-Gas Radiation b.2. mR/hr. ,
- x b1dg. Vent Exhaust Rad. Monitor mR/hr.
~. 5 inches l Rx. aunding Pressure
' nrywellVentRaa. Monitor (caseous) cpm Raavaste Duct Raa. Mon. .f 7 / cpm l . !.
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TIMS //.* Y[ Hours PLANT AND REACTOR SYSTEM VALUES Reactor Vessel Water Level 8d inches Drywen Pressure /.N vaig ,
27n weig Drywen Temperature /3 d . , F
- Reactor Presaure
} ReactorPowerwAPRM(avg.) O % Full Power. Drywell Radiation M R/hr.
I i
Core Plate Diff. Pressure O veid Contairnnent 20 Concentratio8*6% '
., ~
i Recize. Loop A Water Temp ' U[ F Containment 2H Concentration o%
Recire. Loop 3 Vater Temp 33I F Torus Water Level /54- feet ,
l 8 Torus Temperature F Main Steam Line Flow IB/HR x 10 I MainStackHighRangeRad.O./mR/br. j Main Steam Line Radiation mR/hr.
Main Stack flow 2.Vd?T77 CPM Stack Gas Rad. Mon. Mv3 cps j l
'I j Condenser Hotwell Level n inches Refuel Floor Vent Exh. Rad. Mon. / mR/hr i
O inches Eg. Vent Stack Exh. Mon. & cpm 1
', Condenser Yacuum I 6
Total Core Flev 0 Lbs/HRx10 l' f Condensate Storage Tank level M feet Air Ejector Off-Gas. Radiation '>l mR/hr.
- ""**" "(* *} *
- f
~
^ Rx b1dg. Vent Exhaust Rad. Monitor- mR/hr.
l h. aunding Pressure ~*S inc~nes f7/ cpm
""3"* H V'"t R^^ " "it "C ^** "") P" l Raavaste Duet Raa. Mon. !-
i -
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4 i
O O 4o TIME /O/# C Hours PLANT AND REACTOR SYSTEM VALUES Reactor Vessel Water Level $ inches Drywell Pressure /. C usig ,
Reactor Pressure 2 7d veig Drywell Temperature /30 F i
l I ReactorPower-APRM(avg.) o % Full Power Drywell Radiation 7 2. R/hr. ,
t 8 veid Containment go Concentratior2 9% l Core Plate Diff. Presoure
~
Recire. Loop A Water Temp 83d F Containment H 2 Concentration O % f Torns Vater Level / S /, feet Recirc. Icop 3 Water Temp 93d F Main Steam Line Flow o IB/RR x 10 Torus Temperature 7C F .
Main Steam Line Radiation 2C mR/hr. Main Stack Righ Range Rad. / mR/hr. l, t
Main Stack flow O Y8#d CliM
~
Stack Gas Rad. Mon. ' V7/D cps !
l J
Condenser Hotwell Level O inches Refuel Floor Vent Erh. Rad. Mon. / mR/hr l
Condenser Vacuum O inches Rg. Vent Stack Exh. Mon. 2SD cpm l Condensate Storage Tank level D feet Total Core Flow O Lbs/HR x 10' !
Air Ejector Off-Gas Radiation > M mR/hr. !
- g. en ust hd. Modor Wh. i Rr. Building Pressure '. E inches Drywell. Vent Rad. Monitor (Gaseous) cpm l
Radwaste Duct Rad. Mon. [7/ cpm i
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4 TIME /2.'/( Hours PLANT AND REACTOR SYSTEM VALUES Reactor Yessel Water Level bd inches Drywell Pressure !*0 vaig f.
Reactor Pressure d78 veig Drywell Temperature /3d F ReactorPowewAPEM(avg.) A % Full Power. Drywell Radiation M R/hr. [
Core Plate Diff. Pressure d void Containment 02 Concentration 2 7 % j Reciic. L>cp i Vater Temp 330 F Contaiment H2 Concentration O % l Recire. Icop 3 Water Temp 3%
~
F Torus Water Level /$0 feet f.
6 0-Main Steam Line Flow 0 LB/HR x 10 Torus Temperature /b- F .
I s
Main Steam Line Radiation 2( mR/hr. Main Stack High Range Rad. / mR/hr. l l Main Stack flow n(/077(') CFM Stack Gas Rad. Mon. kIOC cps i
! Condenser Hotwell Level O inches : Refuel Floor Vent Exh. Rad. Mon. /mR/hr Condenser Vacuum O inches Hg. Vent Stack Exh. Mon. M cpm Total Core Flow- I Condensate Storage Tank level 2D feet C' Lbs/HR x 10' FeedwaterFlow(total) o Lbs/hR x 10 Air Ejector Off-Gas Radiation > '2 - mR/hr.
Rx blag. Vent Exhaust Rad. Monitor mR/hr.
Rx. Building Pressure "S . inches DrywellVentRad. Monitor (Gaseous) cpm l Radwaste Duct Rad. Mon. ('7/ cpm 1 !
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/O*30 Hours PLANT AND REACTOR SYSTDI VALUES TIME So inches Drywell Pressure J. f neig j Reactor Vessel Water Level .s Drywell Temperature /3# F ll Reactor Pressure d7O peig !I O % Full Power. Drywell Radiation >cP- R/hr.
ReactorPower-APRM(avg.) ;'
t
' 1.
Core Plate Diff. Preasure O paid Con +mirmant2 0 Concentration).I%
T'4a F Containment2R Concentration g
}- Recirc. Icep A Water Temp ~
'330 F Torus Water Level / 5. 6 feet f Recire. Loop 3 Water Temp 1 Main Steam Line Flow 6 IB/HR x 10 6
Torus Temperature fD- F c7 f/dFO mR/hr.
Main Stack High Range Rad. / mR/hr. ,
Main Steam Line Radiation Stack Gas Rad. Mon. -EfaM cps Main Stack flow cO I CM t
i Condenser Hotwell Level /J inches Refuel Floor Vent Exh. Rad. Men. /mR/hr Condenser Vacuum O inches Eg. Vent Stack Exh. Mon. 2 ST cpm ;;
l Condensate Storage Tank level D feet Total Core Flow O Lbs/HR x 10 Air Ejector Off-Gas Radiation 7% mR/hr.
- " #8 #
- 8*
- i Rx. Building Pressure 7I inches rywellVentRad. Monitor (Gaseous) cpm Radwaste Duct Rad. Mon. C7 / cptn i s
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Tm /o? ? V5 Hours PImT m RMCTOR SYSTEM VALUES Reactor Yessel Water Level 80 inches Drywell Pressure !'Y veig ,
Reactor Pressure .D 70 vaig Drywell Temperature /dd F 1
22 4
I ReactorPower.APRM(avg.) /5 -% Full Power Drywell Padiation R/hr. !
i Core Plate Diff. Pressure O veid Containment 02 Concentration 2.8%
Recirc. Loop A Vater Temp S3o y Contai-nent 2n ConcentrationE j Recire. Loop 3 Vater Temp 3.3d F Torus Water Level /57 d feet Main Steam Line Flow d IB/HR x 10 Torus Temperature 75' F ,
Main Steam Line Radiation c2 f mR/hr. Main Stack High Range Rad. . / mR/hr. !
I Main Stack flow J7atrO CIM Stack Gas Rad. Mon. F7d3 eps Condenser Hotwell Level O inches Refuel' Floor Vent Exh. Rad. Mon. / mR/hr Condenser Vacu.a -6 inches Eg. Vent Stack Exh. Mon. d525 cpm Condensate Storage Tank level 26 feet Total Core n ow d Lbs/HRx10 6 l eedwater Mow ho% 0 MsM x 10 i Air Ejector Off-Gas Radiation > 52 - mR/hr.
. ent ust ad. Modtor mR/h. t Rx. Building Pressure ~I~ inches rywellVentRad. Monitor (Gaseous) cpm Radwaste Duct Rad. Mon. [7/ cpm :
6*
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.D TIME M.'6D Hours PLAN" AND REACTOR SYSTEM VALUES t
j e
/ *O' /
s Reactor Yessel Water Level 30 inches Drywell Pressure vaig ,
4 Reactor Pressure d70 veig Drywen Temperature /3O F j !
ReactorPower-APHM(avg.) O % Full Tower. Drywell Radiation N R/hr. !
Core Plate Diff. Pressure O void Conta1 =ent 02Concentration 2. 7% '.
Recire. Loop A Water Temp 3Mo F Contniment 2H Concentration d
. f.
Recirc. Icop B Water Temp 880 F Torus Water Level /I 4 feet {
Main Steam Line Flow d LB/HR x 10 Torus Temperature 9f F
- i M
Main Steam Line Radiation mR/hr. Main Stack High Range Rad. . /' mR/hr. {;
i 4
Main Stack flow c2 [d'6D CIM Stack Gas Rad. Mon. Y@ cps f,
- l' L
Condenser Hotwell Level o inches Refuel Floor Vent Exh. Rad. Mon. / mR/hr i Condenser Vacuum O inches Hg. Vent Stack Exh. Mon. / cpm l i Condensate Storage Tank level cPd feet Total Core Maw Kd Lbs/HR x 10 6
Air E,1ector Off-Gas Raaintion M mR/hr.
- * " " * " "(* -
O s x 0 Rx. Building Pressure 7 6~ inches
. en ust hd. Monhor d 2/h. k rywen Vent Rad. Monitor (Gaseous) cpm
! Radwaste Duct Rad. Mon. 67/ cpm i
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TIME [$ .* /[ Hours' PLANT AND REACTOR SYSTEM VALUES :
b inches Drywell Pressure !' I usig Reactor Yessel Water Level Reactor Pressure D 7M peig Drywell Temperature /$ F ReactorPowerAPRM(avg.) O % rail Power. Drywell Radiation M R/hr. {.
j Core Plate Diff. Pressure O paid Containment 02 Concentration?.T% ;
Reciro. Loop A Water Temp 336 F Containment2H Concentration g .
Recire. Loop 3 Water Temp MO F Torus Water Level / $$ $ feet f, Main Steam Line Flow O IB/BR x 10 6
Toms Temperature [5 F ,
i Main Steam Line Radiation df mR/hr. Main Stack High Range Rad. / mR/hr.
dVd2r0 Stack Gas Rad. Mon. YT2f7) cps l Main Stack flow CliM i Condenser Hotwell Level O inches Refuel Floor Vent Erh. Rad. Mon. / mR/hr Condenser Vacuum O inches Hg. Vent Stack Exb. Mon. OG cpm 6 i i
! Condensate Storage Tank level M feet Total Core Flow O Lbs/BR x 10 a
' 6 2 eedwater Mov @otal) a MsM x 10 Air Ejector Off-Gas Radiation mR/hr.
ag. Vent h ust Rad. Mo m or 2/h. j(
! Rx. Building Pressure I inches rywen Vent Rad. Moniter(Gaseous) cpm Radwaste Duct Rad. Mon. f 7/ cpm l'
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1 TIME / 3 ** hd Hours PLANT AND REACTOR SYSTEM VALUES Reactor Vessel Water Level t3d inches Dryve11 Pressure // 5' usig .
I Reactor Pressure d7d neig Drywen Temperature /3d F i
i ReactorFowe>APRM(avg.) O % Full Power Drywell Radiation 7} R/hr. {
,i Core Plate Diff. Prensure /) Veid Con +mi m ent2 0 Concentration M
~
- Recirc. Loop A Water Temp- .3.$M F Containment'H2 ConcentrationO % !
Recire. Icop 3 Water Temp SM F Torus Vater Level /N (o feet ..
1 Main Steam Line Flow O IB/HR x 10 Torus Temperature /I F I
Main Steam Line Radiation Of mR/hr. Main Stack High Range Rad.. / mR/hr. !
I Main Stack flow _ J/d7TD CM Stack Gas Bad. Mon. ' kV/8 cps
- Condenser Hotwell Level C inches Refuel Floor Vent Exh. Rad. Mon. / mR[nr
!' Condenser Vacuum O inches Rg. Vent Stack Exh. Mon. Os'O cpm I Condensate Storage Tank level M feet Total Core Flow O Lbs/HR x 10 Air Ejector Off-Gas Radiation '7 > mR/hr. <
Rx b1dg. Vent Exhaust Rad. Monitor mR/hr.
l Rx. Building Pressure 'I. inches Drywen Vent Rad. Monitor (Gaseous) cpm
! Radwaste Duct Rad. Mon. [7/ cpm I - i i !
l :
d .
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O PO ,
ms /Jifs' R- run m RucTOR sys- vuoRS ;
l ,
30 inches Drywell Pressure -[ $ veig Reactor Yessel Water Level Reactor Pressure O 7/) usig Drywell Tenperature /bd F .
i Drywell Radiation >& R/hr. [
l ReactorPowewAPRM(avg.) O % Full Power. i Containment20 Concentration M
~
Core Plate Diff. Pressure a paid ;
7 T/') F Containment R Concentration g Recirc. Loop A Water Temp 2 - t Recire. Icop 3 Water Temp MO F Torus Water Level / 57 6 feet j m IB/HR x 10 Torus Temperature f5' F ,
Main Steam Line Flow ~
i Main Stack Righ Range Rad. d. / mR/hr. I Main Steam Line Radiaticu *>X"~ mR/hr. i Y V/d cps j Main Stack flow eM6D C1M Stack Gas Rad. Mon. }
Condenser Rotwell Level /) inches Refuel Floor Vent Exh. Rad. Mon. / mR/hr *(
inches Rg. Vent Stack Exh. Mon. 2N cpm
- Condenser Vacuum O Total Core Flow O Lbs/BRx10' l Condensate Storage Tank level M feet 6- I; Air Ejector Off-Gas Radiation 2 8 - mR/hr.
- "" *# * } O
- f l
Rx blag. Vent Exhaust Rad. Monitor mR/hr.
Rx. Building Pressure f _ inches epn well Vent ma. M m r(Gaseous) l Raavaste Duct Raa. Mon. <7e epm 4
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T1xs /Vero Rours run m ReiCTOR SysTm vmso Reactor Vessel Water Level c30 inches Drywell Pressure /', S' veig Reactor Pressure dN valg Drywell Temperature /30 ?
ReactorPower-APRM(avg.) O % Full Power. Drywell Radiation M R/hr.
t
~
Core Plate Diff. Pressure g usid Cont =1 m t 02Concentration 2 7%
l !
Containment H Concentration d % I, Recize. Icop A Vater Temp 2So F 2 .
.~
I 330 Torus Vater Level /f. A F feet j Recire. Icop 3 Water Temp )
Main Steam Line Flow o IB/HRx10 Torus Temperature 97 F ,
Je Main Stack High Range Rad /* /d mR/hr. - lt 4 Main Steam Line Radiation mR/hr. i Stack Gas Bad. Mon. Z / >< fo Icps Main Stack flow cNM Cm
}
Condenser Hotwell Ievel <> inches Refuel Floor Vent Exh. Rad. Mon. mR/hr Condenser Vacuum O inches Rg. Vent Stack Erh. Mon. 2 SM cpm Condensate Storage Tank. level 20 feet Total Core riow- O Lbs/HRx10 f 6 1' eedder Mow bow d WMx% j:
Air Ejector Off-Gas br11ation M 1 mR/hr.
l
. en ust M . M or ~ 2/h. j; Rx. Building Pressure "O . inches rywell Vent Rad. Monitor (Gaseous) cpm
. Radwante Duct Rad. Mon. W/ cpm i-i 5
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4 1
4 1 i TIME / Hours PLANT AND REACTOR SYSTEM VALUES
(
a i
.j, Reactor Vessel-Water Level 80 inches Drywell Pressure /. [ esig Reactor Pressure 17/1 3sig Drywell Temperature /30 F' I
il O % F:C1 Power - Drywell Radiation jA R/hr. !
f
. Readpor Power.-APRM (avg.) !
Core Plate Diff. PrrArrute O' . paid Contniment Op Concentratior2.f% i l ~
j Recire. Loop A Water 'Iemp - 00' F- Contniment 2H Concentration D Recire. Icop 3 Water Temp .
'b F Torus Water Level (, _ feet Main Steam Line Flow d' LB/HRx10 Torus Temperature 97 F .
s f,
+
1 .
~
Main Steam Line Radiation 2S 'NmR/hr. Main Stack High Range Bad. M mR/hr. ;
i Main Stack flow O ([6ETO CMI Stack Gas Rad. Mon. '7./ J/d 86ps
,, Condenser Hotwell Level d inches Refuel Floor Vent Exh. Rad. Mon. mR/hr i t- ,
! E'" Condenser Vacuum O inches Eg. Vent Stack Exh. Mon. AS7f cpm
- I '- ,
!' Con 2ctsate Storage' Tank level MU feet Total Core Flow d Lbs/HRx10'. ,
M eedwater Mow (total) n nsM x 10 y Jir Ejector Off-Gas Ba?lation mR/hr.
h ' Rx b1dg. Vent Exhaust Rad. Monitor mR/hr. ;;
- - s - c Rx. Building Pressure .
" 3' inchesq,<
e f' - * 'i -
7 e5 DrywellVentRad. Monitor (Gaseous) cpm lr~)
+ , Radwaste Duct Rad. Mon. [7/ cpm p?e' . . i h
- l i e- / ,, -
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9 TIME
/ k.* 3d ; Hours PLANP AND RCACTOR SYSTEM VALUES
/. s'~
Od inches Drywell Pressure ' usig .
['
Reactor Yessel Water Level .
I
, Reactor Pressure 2-7d usig Drywen Temperature /M F i ReactorPower-APRM(avg.) /) % Full Power Drysell Radiation ).'2. R/hr. # ' {.
t Containment20 Concentrationdfj 1 .
8 paid '!
- Core Plate Diff. Pressure Recize. Loop A Water Temp Md F Containment2 H CnentrationfM
~
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Recire. loop 3 Water Temp 3 30 F Torun Water Level /56 reet l
. Main Steam Line Flow d LB/HR x 10 Torns Temperature Nf' F F Main Steam Line Radiation d7 mR/hr. Main Stack High Range Ead. d . /mR/hr. ;
Main Stack flow c9 Vd M 7) CIM Stack Gas Rad. Mon. / 'IX /05' cps -
I Condenser Hotwell Level O inches Refuel Floor Vent Erh. Rad. Mon. mR/hr i Condenser Vacuum inches Eg. Vent Stack Exh. Mon. O S'O cpm l Condensate Storage Tank level M feet Total Core Flow d Lbs/HR x 10 O !
FeedwaterFlow(total) Lbs/IIR x 10 Air Ejector Off-Gas Radiation }2 mR/hr. ,
{
Rx blag. Vent Exhaust Rad. Monitor / 'mR/hr.
i Rx. Building Pressure
-[ inches !
rywen Vent Rad. Monitor (Gaseous)/N cpm Radwaste Duct Rad. Mon. r7/ <
cpm i i i Il j g.
!t j -
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i TIME /7W Hours PLANT AND REACTOR SYSTEM VAIRES, L Reactor Vessel Water Level M inches Drywell Pressure /-[ taig .
j 1 Reactor Pressure ,0 7d vsig Drywell Temperature / 80 ^F i ,
2 . Reactor Power-APRM (avg.) O % Full Power Drywell Radiation ,
>1 R/hr. l
~
Core Plate Diff. Pressure M void Con +=4=umt 20 Concentratio2- 8 % v l ~ ~
Recize. Loop A Water Temp 33n y Con +=i -ent H2 Concentration O % ;
f '
I Recire. Icop 3 Vater Temp 3.30 F Torus Vater Level /5b feet !
Main Steam Line Flow O IB/HR x 10 Torus Temperature I F ,
Main Stack High Range Rad.27.VmR/hr. j
! Main Steam Line Radiation OC mR/hr. !
OIN CIM Stack Gas Rad. Mon. Msca}& cps !
Main Stack flow
- d inches Refuel Floor Vent Exh. Rad. Mon. mR/hr h Condenser Hotwell Level .
O inches Eg. Vent Stack Exh. Mon. 8 5~O cpm j
Condenser Vacuum 6
Condensate Storage Tank level feet Total Core Flow O _ Lbs/HR x 10 6
t Air Ejector Off-Gas Radiation 7A mR/hr.
7I inches
. ent ust M MorMb/h.
Rr. Rullding Pressure e en d. Mo s or @aseous M c p
! Radwaste Duct Rad. Mon. C ~7 / cpm i
e.
' I i.
i -
i 1 -
t I ..
O , O .
rO
]
i 2
TIME [O N Hours PLANP AND REACTOR SYS'EM VALUES Reactor Yessel Water Level dd inches Drywell Pressure /. [ vaig ,
I Reactor Pressure J70 usig Drywen Temperature /30 F !
i ReactorPower-APRM(avg.) () % Full Power Drywell Radiation- ':PJL-- R/hr. ;
~
Core Plate Diff. Pressure o void Contaiment 02Concentration 2 7% :
~ ~
l Recize. Loop A Water Temp 33d F Contniment 2R Concentration g Recire. Icop 3 Water Temp () F Torus Water Level /V y feet i,
Main Steam Line Flow 0 IB/RR x 10 Torus Temperature PA' F Main Steam Line Radiation dI mR/hr. Main Stack High Range Rad. I72.b/hr. i' Main Stack flow @ YvFO CPM Stack Gas Rad. Mon. offsmit eps j Condenser Hotwell Level C inches Refuel Floor Vent Exh. Rad. Mon. nR/hr Condenser Yacuum d inches Rg. Vent Stack Exh. Mon. NN cpm Condensate Storage Tank level c'Lo feet Total Core Flow O Lbs/RRx10 'f 2 FeedwaterFlow(total) () Lbs/hR x 10 Air E,1ector Off-Gas Radiation mR/br.
E* D'^3g. Vent Exhaust Rad. Monitor / mR/hr. f{
Rx. Eni m y Pressure ~. 7 inches Drywell Vent Rad. Monitor (Gaseous)/gyr) cpm
! Radwaste Duct Rad. Mon. cpm !
r i
i-L
~
9
O ,
O PO i
.i, ,
. .r I.'
.i I
TIME /[*/[ Hours PLANT AND REACTOR SYSTEM VALUES ,
Reactor Yessel Water Level .3d inches Drywell Pressure /Y vaig ,
Reactor Pressure o2 74 meig Drywell Temperature /30 F ReactorPowe>APHM(avg.) 0 % Full Power. Drywell Radiation Jo7 R/hr. {I
~
A usid Con += h nt Op Concentration 2 8% f Core Plate Diff. Pressure Recirc. Loop A Water Temp 3~2A F Containment2R Concentration g f Recire. Icop 3 Vater Temp 6 F Torus Water Level /I/ feet i
Main Steam Line Flow O LB/HR x 10 Torus Temperature M F ,
f Main Steam Line Radiation dI mR/hr.
Main Stack High Range Rad. N mR/hr.
i, Main Stack flow M f(f20 CFM Stack Gas Pad. Mon. 8 &etfs cps i fe Condenser Hotwell level g inches Refuel Floor Vent Erh. Rad. Mon. mR/hr Condenser Yacuum O inches Hg. Vent Stack Exh. Mon. 7 <7) cpm ;
Condensate Storage Tank level N feet Total Core Flow C Lhs/ERx10 f, 6 i~
Air Ejector Off-Gas Radiation N mR/hr.
- Rx. Building Pressure " s'
. inches DrywellVentRad. Monitor (Gaseous)l4 cpm Radwaste Duct Rad. K9n. cpm I,
i i, l
- i i , .
i .
4 O O .
rO !-
jr l l i
4 TIME /$ .'3d Hours PLANT AND REACTOR SYSTEM VALUES 8D inches Drywell Pressure / " S~ veig I
Reactor Vessel Water Level t Reactor Pressure d 70 voig Drywen Temperature / Frd _
y l t
Reactor Power-APIM (avg.) d % Full Power. Drywell Radiation >1 R/hr. !.
Con +=4==mt2 0 Concentration M '.
Core Plate Diff. Pressure O void Recizc. Loop A Water Temp 32 y .
Con +><---t n2 Concentratiod .
{-
Torus Water Level . /If feet Recire. Icop 3 Water Temp d F- f Main Steam Line Flow O IB/HR x 10 Torus Temperature f F . !
f - ,
Main Steam Line Radiation dC mR/hr. Main Stack High Range Rad.5M fmR/hr. l 7 l t
Main Stack flow cDVd2TD CFM Stack Gas Rad. kn. 8Sc.ft cps
- Cendenser Hotwell Level O inches Refuel Floor Vent Exh. Rad. Mon. mR/hr *l l
5 Condenser Vacuum C inches Rg. Vent Stack Erh. N n. *2 S7) cpm j 6 i Condensate Storage Tank level cP O feet Total Core Flow O Lbs/HR x 10 i 1
Air Ejector Off-Gas haintion 2o2. mR/hr.
inches
- g. en ust Rad. E m or ^ d./h.
Rx. Building Pressure 1 epm "r7*11 V'"t B*d * "it "CC^** "") P" I L
- Raawaste auct Raa. Mon. _ .
- o i
. c 1
J
O o ey 1 I
TIME !O IS Hours PLANT AND REACTOR SYSTEM VAIRES
. Reactor Vessel Water Level 80 inches Ihywell Pressure /. S veig Reactor Pressure J 70 veig Drywell Temperature /So F f 1
ReactorPowewAPEM(avg.) M % Full Power. Drywell Radiation M R/hr. [.
Core Plate Diff. Pressure O paid Contaiment 02Concentration 2* 8% !
i .
Recire. Icop A Water Temp 4 FM F Containment2H Concentration M {
- Recire. Icop 3 Water Temp /> F .
Torus Water Level / f V feet i
Main Steam Line Flow n IB/HR x 10 Torus Temperature N.5~ F ..
Main Steam Line Radiation df mR/hr. Main Stack High Range Rad./M/mR/hr. !;
Main Stack flow e9 V47D CIM Stack Gas Bad. Mon. c8M cps l; Condenser Hotwell Level _ o inches Refuel Floor Vent Exh. Rad. Mon. mR/hr *f1.
1 Condenser Vacuum o inches Hg. Vent Stack Exh. Mon. 1 9 cpm ll Total Core Flow O !'
Condensate Storage Tank level M feet Lbs/HR x 10' 2b eedwater M ow (to M ) Q_ DsM x 10 Air Ejector Off-Gas Radiation mR/hr.
Ex. Building Pressure C5 inches
[
he ent ad. htor(GaseousMA cr l Radwaste Duct Rad. Mon. cpm i
l ?
1 l %
o o .
.go i
4 4
TIMs /61(8 Hours PLm AND REACTOR SYSTM VAWES
'h Reactor Yessel Water Level N inches Drywell Pressure !* I vaig [
Reactor' Pressure .d 7d usig Drywell Temperature /% F i
- ReactorPower-APRM(avg.) 0 % Full Power. Drywell ram ation N R/hr. {,
i Core Plate Diff. Pressure veid Con +=i==t 02Concentration 2 8%
~
Recirc. Icop A Water Temp ya F Containment 2H CcncentrationO % f Recire. Icop 3 Water Temp M F Torus Water Level NV feet 6
I Main' Steam Line Flow /) D/HRx10 Torus Temperature 25' F 1
Main Steam Line Rediation dI mR/br. Main Stack High Range Rad./ ImR/hr. -]
- E e
I Main Stack flow c2 /d'dZ? CPM Stack Gas Rad. Mon./*fx u, y cps l,
- I j Condenser Hotwell Level C inches Refuel Floor Vent Exh. Rad. Mon. mR/br - l Condenser Vacuum d inches Hg. Vent Stack Exh. & n. 2 M cpci Condensate Storage Tank level ZO feet Total Core Flow d Lbs/HR x 10 1
Air Ejector Off-Gas RaMation >_2. mR/br.
- "***" " " O # # "*M * ' 6 l ag. Yent M-4 M. Ndor / d/h. l, Rx. Building Pressure ~[ -
inches ,
e ent ad. Mo m or(Gaseous Y M cpm Radwaste Duet Rad. Mon. cpm u
l' i,
i ;1 1
tl .
a w
l O .o eo i
TIME '8 Hours PLAIE AND REACTOR SYSTEM VATEES d
4 Reactor Yessel Water Level D[ inches Drywell Pressure /I peig h Reactor Pressure /0 Id neig Drywell Temperature /30 F b !i ReactorPower-APBM(avg.) /$0 % Full Power. Drywell Radiation _R/hr. :! '
Core Plate 3iff. Pzessure /I usid Con +=ir-mt 02Concentration 2.T% .
dO Con +nirunent H Concentration 8 j !!
Recirc. Icop A Vater Temp F 2 '
Recirc. Ioop 3 Vater Temp [.30
^
F Torus Water Level /M7 feet !.f
/ 3. Y IB/RRx10 Torus Temperature 98 F Main Steam Line Flow
/070 Main Stack High Range Rad.. / mR/hr.
Main Steam Line RaAintion mR/hr.
)8 ieO CFM Stack Gas Rad. Mon. 2.0 cps !
Main Stack flow' '
4 Condenser Hotwell Ievel /[ inches Refuel Floor Vent Erh. Rad. Mon. / #mR/hr -
l l EI.[ inches Rg. Vent Stack Exh. Mon. 2 SD cpm Condenser Vacuum l
Condensate Storage Tank level c70 feet Total Core Flow /o2.59 Ibs/RRx10' !
l Feedwater Flow (total) /.I Y Lbs/hR x 10 Air E,iector Off-Gas Radiation mR/br.
Rx b1dg. Vent Exhaust Rad. Monitor /# mR/hr.
Rx. Bui1 % h a m ~I~ inches .
Drywell Vent Rad. Monitor (Gaseous)/Mcpm li
. Radwaste Duct Rad. Mon. 67/ cpm
! l1 j .- !
~
+
f.
( .,
' :)
4 % !
- ?
i s !
[
TIME I*hI Hours PLANT AND REACTOR SYSTEM VALUES ,l
- I
^
Reactor Vessel Water Level 8 inches Drywell Pressure c?I usig ;i
,I
- Reactor Pressure /d/d usig Drywell Temperature /Jd F l!,
RoactorPower-APRM'(avg.) / #"O % Full Power. Drywell Radiation d R/hr. [,. ,
l '
Con +=iv- mt 20 Concentration 2 8 i Core Plate Diff. Pressure /7 paid :s
~
I.!,
- Recire. Loop A Water Temp .
63d F Con +=imnent2H Concentration d 95 .g j
Recire. Icop 3 Water Temp 636
^
F Torus Vater Level /'A 7 feet jI Main Steam Line Flow /3,4 IB/BR x 10 Torus Temperature 90 F ,
Main Stack High Range Rad. - / mR/hr. f Main Steam Line RaAintion / d-tP--tS mR/hr.
Main Stack flow d.,y CPM Stack Gas Rad. Mon. ' 2d cps l!
s l Condenser Hotwell Invel /( inches Refuel Floor Vent Erh. Rad. Mon. / 8 mR/hr ,,,
ff Condenser Vacuum c2 U [ inches Hg. Vent Stack Exh. Mon. "2.f'8 cpm llI 6
/d2.Jf Condensate Storage Tank level 20 feet Total core Flow Lbs/HR x 10 l
- E " * ~
- Air Ejector Off-Gas RaAintion I mR/hr.
l Rx. Building Pressure ' 5'
- inchee Drywell Vent Rad. Monitor (Gaseous) /Mcpm Radwaste Duct Rad. Mon. 5"// cpm i
j i
?
\ ,
_ _____. - , _ _ _ .___ _ __ ___ - - . L_
4
, -O t O -O
- a 4
i i TIME dd*d Hours FLANT AND REACTOR SYSTEM VALUES Reactor Vessel Water Level I inches Drywell Pressure ~ 25 maig Reactor Pressure /d/d usig Drywell Temperature /3d F
] Reactor Powoo-APEM (avg.) T % Full Power. Drywell Radiation OS R/hr. {
i Core Plate Diff. Pressure /I usid Con +=4==nt 20 Concentration 2 I% k, Recire. Loop A Water Temp 43d F Containment H2 Concentration 8 %
l Recire. Icop 3 Water Temp 690 F Torus Water Level /N 7 feet I Main Steam Line Flow / Z,. I IB/HR x 10 Torus Temperature _ [8 F Main Steam Line hAintion M mR/hr. Main Stack High Range Rad.*/ mR/hr. l<
i Main Stack flow cpd #F1f CPM Stack Gas Bad. Mon. -
M cps ',
j i.
i Condenser Hotwell Level /*s"~ inches Refuel Floor Vent Ihh. Rad. Mon./ # mR/hr l Condenser Vacuum 8 I-[ inches Eg. Vent Stack Exh. Mon. 253 epa Condensate Storage Tank level M feet Total Core Flow / 0 / 2- Lbs/HR x 10 l Air Ejector Off-Gas haintion Feedwater Flow (total) /Z. T Lbs/hR x 10 l mR/hr.
! Rx. Building Pressure 7f inches Rx b3dg. Vent Exhaust Rad. Monitor / #mR/hr. j' i
Drywen Vent Rad. Monitor (Gaseous)N#Depm l j Radwaste Duct Rad. Mon. 6~7/ cpm e
, f a
!i
. j-
- i; a
l
!=
I _
O 7 O 20
! s.
TIME C[ .*/I Hours PLANT AND REACTOR SYSTEM VATES s
Reactor Yessel Water Level f=7( inches Drywell Pressure */D vaig. ,
t Reactor Pressure /d /d _Deig Drywell Temperature /38 F .
i l ReactorPower-APHM(avg.)_ f8 % Full Power. Drywell Radiation <3 R/hr. ;
I
- Core Plate Diff. Pressure /7 Vsid Conw mt0 C2 ncentration2 T% ,
Recirc. Icop A Water Temp [dd F Containment H 2 Concentration d % l
!. Recire. Icop 3 Water Temp d3d F Torus Vater Leve] /k7 feet j Main Steam Line Flow /2 [ LB/HRx10 Torus Temperature F .
I Main Steam Line hMation mR/hr. Main Stack High Range Rad. ./ mR/br. l
- i Main Stack flow d d, M CPM Stack Gas Rad. Mon. 2O cps
{
1 Condenser Hotwell Level /[ inches Refuel Floor Vent Erh. Rad. Mon./* OmR/hr Condenser Yacuum d7.7 inches Hg. Vent Stack Exh. Mon. 2.50 cpm ,
Condensate Storage Tank level _ O feet Total Core Flow fb 7 Lbs/HR x 10' !r i Air Ejector Off-Gas Radiation k mR/br.
- d""** * *) * *'
E* *" #
- Rx. Building Pressure .[ inches Radwaste Duct Rad. Mon. C7/ cpm rywell Vent Rad. Monitor (Gaseous)/aTo cpm l' s !
i l !
- I
.- l l i I
1 i .
O O nO l
1 TIME d38 Hours PLAW AND REACTOR SYSTDI VALUES M 5' inches Drywell Pressure .I usig Reactor Yessel Water Level .
/d /0 veig Drywell Temperature /30 F .
Reactor Pressure ReactorPower-APRM(avg.) T5' % Full Power. Drywell Radiation 5' R/hr.
j '
Con +=1 - t 0 2Concentration 2 T%
Core Plate Diff. Pressure /d void ~
Recirc. Loop A Water Temp 6'3d F Containment 2H C n entration d %
f / 7 i Torus Water Level feet Recire. Loop 3 Water Temp 63d F
/ 2. / IB/HRx10 Torus Temperature fd F .
Main Steam L be Flow M Main Stack High Range Rad. / mR/br. l I
Main Steam Line Radiation mR/hr. e Stack Gas Rad. Men. 20- cps [
?
Main Stack flow Q0#78 CFM ; ,
j Condenser Hotwell Invel /( inches Refuel Floor Vent Exh. Rad. Mon. / O mR/hr '{
Condenser Yacuum E T* I inches Hg. Vent Stack Exh. Mon. 2@ cpm Total Core Flow 77 Lbs/HR x 10 l Condensate Storage Tank level cPO feet '
Feedwater Flow (total) /2 / Lbs/IIR x 10 .
l Air Ejector Off-Gas RaMation N mR/hr.
ag. Vent hust Rad. MonMor AM/E ,
I inches Rx. Building Pressure rywell Vent Rad. Monitor (Gaseous /#26 cpm f, Radwaste Duct Rad. Mon. f7/ cpm i
! i
. i i
.O v O . cO i;
. i t
i i
. i-I TIME [* Hours PLANT AND REACTOR SYSTEM VALUES _ ,,
1 Reactor Vessel Water Level I inches Drywell Pressure W psig - ;
i!
Reactor Pressure /0/8 psig Drywell Temperature /3I F l ReactorPower-APRM.(avg.) Tf % Pull Power. Drywell Radiation [ R/hr. ll 4
/le Con +=4==nt2 0 Concentration M 4
veid Core Plate Diff. Pressure '
Recirc. Loop A Water Temp (5d r Con +=< - t R2 ConcentrationA_%
ll.
Recire. Icop 3 Water Temp 53d
~
r Toru Water level N7 feet {!
/2 / Torus Temperature 8 F ,
Main Steam Line Flow IB/RR x 10 75D Main Stack High Range Rad. / mR/hr.
Main Steam Line Radiation mR/hr.
i J,M CIM Stack Gas Rad. Mon. 24 cps [
! Main Stack flow <
- l
] ~
j i
Condenser Hotwell Ievel /$ inches RefuelFloorVentExh. Bad. Mon./dmR/hr
- l
' i l Condenser Vacuum inches Hg. Vent Stack Exh. Mon. 2 N ~ cpm N Total Core Flow 7T Lbs/FRx10' f Condensate Storage Tank level feet 6 1 eedwater Mow (total) U. / MsM x 10 Air Ejector Off-Gas Radiation N mR/hr.
{.
Rx b1dg. Vent Exhaust Rad. Monitor !*#mR/hr.
Rr. Building Pressure 'I '
inches e en ad. Mo d or(Gaseous V M . cpm l Radvante Duct Rad. Mon. 8'7/ cpm k
4 l
O O -
c.o
~ -
I i
I ms 07 ro sours runr un EmCroa sys- muss .
t O- veig i ,
Reactor Yessel Water Level Nf e2 inches Drywell Pressure MY weig Drywell Temperature F Reactor Pressure //)/o 1 l ReactorPowewAPRM(avg.)
W % Full Power Drywell Radiation [ R/hr.
I i
l Core Plate Diff. Pressure /4 veid Containment 02 Concentration 27%
O F Containment 2H Concentrationd %
Recire. Icop A Vater Temp N /M 7 i F Torus Water Level feet Recire. Loop 3 Water Temp Main Steam Line Flow /2 / LB/HRx10 Torus Temperature fd F !
1 Main Stack High Range Rad.* / mR/hr. !
! Main Steam Line Radiation 75'8 mR/hr. ,
9 Stack Gas Rad. Mon. 20 cps !
Main Stack flow Jo dec CFM
! Condenser Hotwell Level b' inches RefuelFloorVentExh. Rad. Mon./#mR/hr *l ,
I I
Condenser Vacuum o27-[ inches Hg. "ent Stack Exh. Mon. 2 O
< cpm {
Condensate Storage Tank level cPd feet Total Core Flow N Lbs/HR x 10 l 6
Air Ejector Off-Gas Radiation //d eedwater Mow hoW 4 / DsM x 10 mR/hr.
ag. Vent hust hd.' Ndor /M/h. ;
Rr. Building Pressure I inches I. Raavaste auct Raa. Mon. I7/ epm
""J"*H V'"t R*d " "it "CG*** "")/#t" P" [e 1
i !-
t,
O -
O oo i x
l
! l i
ms 4 7//r Hours run inn RsiCToR Swm vituss -
n
- (
Reactor Vessel Water Level #52 inches Drywell Pressure Y veig ,,
o Reactor Pressure /d /d usig Drywell Temperature /II F e,
Reactor Powe> APEM (avg.) _ IO % Full Power. Drywell Radiation M4 R/hr. ;
Con +mi m t20 Concentratio @
Core Plate Diff. Pressure /C void
~
Recize. Loop A Water Temp 9 F Containment2H Concentration M -
GO / 7. ~7 F Torus Water Level feet Recire. Icop 3 Water Temp Main Steam Line Flow // 7 IB/HR x 10 Torus Temperature fd ._
F -
76"O mR/hr.
Main Stack High Range Rad.. / mR/hr.
l Main Steam Line Radiation ,
Stack Gas Rad. Mon. ' 2d cps f-Main Stack flow On d.t:rd Cm ;
Condenser Hotwell Level /I inches RefuelFloorVentExh. Rad. Mon.AdmR/hr *l -
l Condenser Vacuum c2 T. 5 inches Hg. Vent Stack Exh. Mon. FIO cpm i
-7 f !
Condensate Storage Tank level M feet Total Core Flow Lbs/HR x 10 Air Ejector Off-Gas Radiation Y/ mR/hr.
{,
ag. Vent hust hd. MomorM O.'
Rx. Building Pressure ~I-inches Drywen Vent Rad. Monitor (Gaseous)/rSO cpm Radwaste Duct Rad. Mon. S 7/ cpm t 5 .
i
} .
1 .
3 .
O ,
O
-O 4
ens n 7e38 Hours FMM AND RMCTOR SHMM VALUES ;
Reactor Yessel Water Level /8 inches Drywell Pressure S# Deig Reactor Pressure /d/0 maig Drywell Temperature /N F j ReactorPower.APRM(avg.) Td % Full Power. Drywell Radiation Y. 0 R/hr.
Core Plate Diff. Presaure /[ veid Con +=4v= ant 0 Concentration 2, I% j' 2
Recirc. Icop A Water Temp ,5 3d F Containment2H Concentration M !
Recire. Icop 3 Water Temp g3d F Torus Vater Ievel / Y. 7 ' feet l Main Steam Line Flow //. 7 IB/HR x 10' Torus Temperature b F I
l Main Steam Line Radiation X#D mR/hr. Main Stack High Range Rad. . / mR/hr.
t .
i Main Stack flow ZNO CIM Stack Gas Rad. Mon. Ad cps l Condenser Hotvell Level /6 inches Refuel Floor Vent Erh. Rad. Mon./.8 mR/hr l
Condenser Vacuum 2II inches Hg. Vent Stack Exh. Mon. D cpm l l
- Condensate Storage Tank level M feet Total Core Flow ~7 / Lbs/HRx10' i 6
6// Feedwater F1 w (total) //. 7 Lbo/hR x 10 Air Ejector off Gas m m ation mR/hr.
5f inches x ag. Vent hust M. mom 8 2/h. i Rr. Building Pressure rywen Vent Rad. Monitor (Gaseous)/at2f cpm Radwaste Duct Rad. Mon. g 7/ cpm : 1
(
l i !
l-
.O ;o PO !
'i 1
E TIMs 47:W nours PL m m M OTOR SYSTEM VALUES Reactor Yessel Water Level 25 inches Drywell Pressure 60 veig
/d/8 veig Drywell Temperature YO F Reactor Pressure :
'L ReactorPower-APRM(avg.) 78 % Full I.w r. Drywell Radiation b la R/hr. ,
/ 5' veia Containment 0 Concentration 2 P g j Core 11 ate Diff. Pressure 2
~
' Recire. Loop A Water Temp [3d F Containment H 2 Concentration O % .
Recire. Loop 3 Water Temp [38 F Torus Water Level /N7 feet [
a Main Steam Line Flow / /. 7 IB/ER x 10' Torus Temperature [o F Main Steam Line Radiation 74 mR/hr.
Main Stack High Range Rad. / mR/hr. l t ,
c2d r#C Stack Gas Rad. Mon. 2-6 cps l
Main Stack flow CFM Condenser Hotweh Level 6 inches RefuelFloorVentExh. Rad. Mon./8mR/hr Condenser Vacuum d' inches Hg. Vent Stack Exh.' Mon. 2rD epn 6
Condensate Storage Tank level 2-0 feet Total Core Flow 7/ Lbs/HRx10 l l 6 Air Ejector Off-Gas RaMation Y/ mR/hr.
- d""**" "(* ) //,
s x 10 f ag. Vent hust Rad. Momor [M/h.
Rx. Building Pressure I inches rywen Vent Rad. Monitor (Gaseous)/M cpm ,
Radwaste Duct Rad. Mon. 57/ cpm i
j . ;1 1,
j .
j . !:
co o
O ; -
l TIME O *D - Hours PLANP AND REACTOR SYSTDI VALUES '
Reactor Yessel Water Level oY inches Drywell Pressure . EI usig ,
Reactor Pressure- /#/# veig Drywell Temperaturo /3( r i l ReactorPowe>APRM(avg.) 78 % Pull Power. DrywellRakiation Yd R/hr. l i
t Core Plate Diff. Pressure / veid Con +=4mnant20 Concentration 2 I%
! ~
4 Recire. Icop A Water Temp D F Containnent H2 Concentration O %
i Recire. Icop 3 Water Temp [OO F Torus Water Level /b 7 feet _
Torus Temperature d8 F f' i Main Steam Line Flow //.7 LB/ER x 10 k in Steam Line Radiation [fD mR/hr. Main Stack High Range Rad. */mR/hr.
1 Jd,#PC CPM Stack Gas Rad. Mon. U cps l Main Stack flow Condenser Hotwell level /[ inches RefuelFloorVentExh. Rad. Mon 2 mR/hr 27 7 inches Hg. Vent Stack Exh. Mon. 8dC cpm i l Condenser 7acuum '
Condensate Storage Tank level 2d feet Total Core Flow 7/ Lbs/HRx10' ,
l eedwater Mow (tom) N.7 WM x 10 j Air Ejector Off-Gae Radiaticu Y/ mR/hr.
x ag. Vent hust Rad. Enhed.d mR/h. {
i Rx. Building Pressure 75 inches he en ad. Mo s or(Gaseous M cpm f Radwaste Duct Rad. Mon. U/ cpm i
l' e
i i . t-
! e e f
.O .
- O :
O i
.t i
!- -l TIME O I'/I Hours PLANT AND REACTOR SYSTEM VALUES i
Reactor Yessel Water Level Y 7f inches Drywell Pressure d vaig
/d/d vaig Drywell Temperature /85 F !
Reactor Pressure I ReactorPower-APRM'(avg.) [8 % Full Power. Drywell RaMation d6 R/hr. ,!
' i Core Plate Diff. Preesure /6 veid Con +=1 - t 0 2Concentration 2 T%
~
Recirc. Loop A Water Temp 570 F Contahnnent2 H Concentration d f Recire. Icop 3 Water Temp O F Torus Water Level / v. 7 feet {
l
' Main Steam'Line Flow //,7 IB/RR x 10 Torus Temperature fo F ,
7rd mR/hr.
MainStackHighRangeRad,d*/mR/br.
Main Steam Line Radiation '
Stack Gao Had. Mon. 20 cps Main Stack flov Z G uG-0 CPM i Condenser Hotwell Level /s' inches RefuelFloorVentExh. Rad. Mon./4mR/hr 3 (O j 1
Condenser Vacuum O I* 5^ inches Eg. Vent Stack Exh. Mon. cpm i
D Total Core Flow 7f Lbs/HR x 10' f j Condensate Storage Tank level feet FeedwaterFlow(total) // 7 Lbs/lIR x 10 f.
f Air Ejector Off-Gas Radiation V/ mR/hr.
i Rx b1dg. Vent Exhaust Rad. Monitor d# mR/hr.
Rx. Building Pressure 7 $' inches DrywellVentRad. Monitor (Gaseous)dr# cpm Radwaste Duct Rad. Mon. [7/ cpm i
' I
- i
\
i -
i
. - . .- . . = . .. .-. . -- - , ~ ,
m.
Juuu 2H,-1903
. (d RADIOMX;ICAl. ' I,)ATA, A. Plant Monotoring. Data Drywell and' Torus Air Space Concentrations (7tCi/cc. )
~
- 1. .
- 2. Turbine Building Air Concentration' (mci /cc.)
- 3. Reactor Building Air Concentrations (l(Ci/cc. )
- a. 135'. elevation
- b. 165' elovation
- c. 195'.olevation I d. 234' elovation
, B. Chemistry Sampling Data
( .
Reactor Coolant Activity 1.
~
4 2 .- .Inplant Sampling Systems (PASS System) Exposure Ratos (mr/hr.)
- 3. 'Same'as above for Regular Liquid Sampling Station
- 4. Same as abovo for Regular Drywell Air Sampling Station C. Main Stack Sampling Data and Doso Assessment Recults.
- 1. : Iodine Sample Data
'c. Charcoal
- cartridge exposure rates (nr/hr.) shielded /unshicIdod
- at
(
I Contact l:
I ft.
[, '
-3 ft.
( .
L F
e
.. .- .,, . _. . .. ., 4 - .. ,- ,_...~._. . . - - - _ - . _ . - . . . -. -
._.c ,
. .a. , ,
jm. Exposuro rates at the base of. he stack d.
t] .
-inside at the outsido door . .
- 2. Activity Released and Calculated Doses
- a. .TJmo of roloaso-
, ~
- b. Source of release and flow rate (cfm)>
- c. Monitor count rate and release rates (HCi/s for NG and I .)
Lab analysis results (% abundance for NG and I )
6 d.
f
- c. Projected dose rates (NG, -I inhalation, and I ingostion) at:
site boundry (S.B. ) -
o r, 1 mi, 2 mi.
3 mi.
4 mi.
l.
5 mi.
'- 6 mi.
I
. 8 mi.-
[
f r .~10 mi.
- f. Meteorological data l
D. Field Monitoring Data l
p.
- .l.
.Whole Body Dose Rates-(mr/hr) r' I- 2. Sam II Readings (cpm) -
i
~
L.:
!-' 3 . -- Iodine. Air Concentrations (Itci/cc.)
l .
L 4. Offsite Field Sampling _ Data f'. .
.a. Deposition for I-131.(mci /m2). for pasture grass, vegetation,
}
(U ~ and soil samples. 1 6
- b. I-131 milk concentration (P /A)
N
..e,.ww , we,.., , - . , .,.m., ,,,.--w -,, ,-,vew-.m,,-c,-. -
,-w- . + , , - - v., r,-,-,,,-y- #c-, - -
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, , . .. . .., ....~ .. - - .- - . - .... ~ -.-- - . .- . - - . _. ... - .. _.-. . . - . ---
- ~ ..
6 L
1.' .
kl E. ' Area Radiation' Levels -
i'
- l. : Area-Radiation' Levels.By. Region 4
1 i 2.- Maps showing Plant Areas and Regidns
- 3. Area Radiation Monitor Trip' Times e
h ~ 4. 20 Minute Monitor Readings for Control. Room of-Al1 Unit 3, ,
1 a,
Common Building, and Turbine Building Areas: ,
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'71*
Plant Monitoring I)ata
- 1. Drywell and Torus Air Space Concentrations During the duration of this senario the drywoll and torus air -space concentrations will remain consistant with normal operating values.
Health Physics technicians.should use actual values. .
- 2. Turbine Building Air Concentrations.
- During the duration of this senario the Turbine Building. air con-Ilcalth ,
I centrations will remain'consistant with normal values.
. Physics technicians should use actual. values.
i 4-4 r
f 4
I I
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i . l e
1 T
1
--. . ~ . . . - - . . .. . . - . . . . . . . . . . . _ . _ . _ _ _ . . . . . . _ . _ . _ , _ , . _ - _ .
REACTOR BUILDING AIR CONCENTRATIONS s
O All Air Concentrations Are In
. }1Ci/cc
- Denotes activity not detectable l
l l
l l
l l
O
o]3IMdo biEIdW 1030 800 13 0
' " '27
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g 9.4 N10 9.6 Hlo 1.1 N9 1.3 N9 9.9 Hlo
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- 2.5 N9 3.2 N9 tn 2 1.3 N8 3.4 N8 3.6 N8 3.7 N8 3.9 N8 3.4 N8
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- O
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1 l3I 9.1 N7 8.9 N7 z
- 4.3 N8 1.1 N8 s.3 NS 2.7 N9 O w 1.6 N7 9.7 N8 8 N8 D [ 1l33 2.4 N7 2.3 N7 1.1 N9 7.9 N10 4.2 NIO 2.1 N10 6.3 N11 4.8 Hll 4.3 N9 4.2 N9 3.4 N9
($lk 2.2 N10 9.8 Nll 8.7 Hll 3.3 N9 1.6 N9 8.1 N10 I6.6 N10 4.2 N9 4 N9 o E Cs137 2 > 8.1 N10 1.6 N7 3.8 N7 7.9 H8 1.4 N9 E M * *
- 4.7 N10 I
s u - - -
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- 4 N1o 7 N1o 8.2 N9 8.3 N9 8.s N9 8.6 N9 8.1 N9
- 2.1 N10 3.9 N1o 4.1 N1o 7.6 N9 (R 5 i 9.7 N8 9.8 N8 1.1 N8 1.3 N8 9.7 N9 (O58
- 9.3 N9 1.8 NB 2.1 N8 8.8 H8 7.s N2 7.7 N7 8 N2 8.2 N7 7.6 N7 (O60 . 7.33 N9 9.7 N, 1 N8 s.4 u2 m
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- 1.13 N8 2.3 N8 2.9 N8 3.4 N6 4.2 N6 u s 1 l3I 1 -
O 2.6 N7 2.9 N7 3.3 N7 4.1 N7 4.6 N7 3.9 N7 I 13 3 5.1 N9 Y
- 2.4 N9 4.7 N9 1.4 N8 1.9 N8 2.2 N8 2.9 N8 1.8 He 2 2.1 N1o 4 u1o 4.7 N1o 9.8 Ne j 0 Cs134 -
6.3 N8 7.1 N8 7.4 N8 7.9 N8 7.2 N8 1.3 N9 3.1 N9 4.2 N8 o E Cs137 - 2.4 ue 2 >
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' 6.9 ? 7 6.1 N7; 3.4 N7 6.9 M8 1.3 N9 8.9 N10 5.2 N10 (O6O 7. 3 N7 7.2 N7
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1.6 N9 3.3 N9 4.2 N9 9.8 N9 ,
L Co 58 .
1.4 N8 1.6 N8 2.1 N8 2.3 N8. 1. 7 '
3.4 N9 4.7 N9 j 8.3 N9 Co6O
- l.5 N9 r v,
2 2.2 N8 2.3 N8 2.5 N8 2 N8 2.1 N8 2g45
- i 1.6 N9 2.9 N9 3.1 N9 8.2 N9 _
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- p,
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1.3 ulo ' 2.9 Nic' 3.1 N1o 3. n lo 3.3 hio 2.81
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- z : 6.2 tiB 6.7 N8 - 6,1 s O 6.2 N9 4.8 NB 5.1 N8 5.5 N8 4.1 N9 5.8 N9 D
S 1l33 .
3.2 N9 3.6 N9 3.9 N8 4.6 N8 3.51 2 4 31o 6,3 310 s.3 u1o , 1.1 N9 9
gg g34 ,
l 4.2 N8 4.5 N8 5 N8 4.3 i 1.3 N8 3.6 N8 2.4 N9 3.1 N9 738 N9
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2 > - -
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- LD ga gs .
oc - - - - - -
9 Xel33 -
a . . . .
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w O - - -
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'T noE 3300 i 33o 1400_ ino i 1 NIO 6.1 Ull 3.4 W1:
1.1 N9 9.9 N1C 4.6 NIC NAN 3.5 N9 3.4 N9 3.1 N9 2 N10 4.8 N10 8.3 N 1] 6.2 Nll, 4.3 Nll 8 N10 7.5 N10 5. 3 N10 (R 6I 9 N10 3.7 N9 1.1 N9 8.9 N10 6.7 Nio 4.5 Nio 8 N9 7.8 N9 7.4 N9 5 8 N9 Co58 2.7 N9 9.7 N10 7.5 N10 4.4 N10 i
9.7 N9 8.9 N9 6.2 N9 i
(06O 1.1 N8 1 NB un 4.1 N11 2.1 N11 2.1 N1o 1 N1o z t 7 "8 1.1 N8 9.7 N9 8.3 N9
- 1. 5 N8 O_
2N 65 l- 7,1 N11 1.3 N12 8.7 N11 .7.8 N11) 3.5 N11 2.6 N10 2.5 Nio 2.1 Nio 9.8 N11 IC 99M e 8.5 N7 5.2 N7 4.6 N7 2.3 N7 z 6.6 N9 6.5 N9 5.9 N9 5.5 N8 3.2 N7 o g e
1 l3I 6.5 N7 1 7.9 N7 4.6 N7 8.7 N7 5.8 N8 4.9 N8 3.6 N7 1.8 N6 O 5.6 N8 b I I13 3 6.4 N1o 5.1 N1o e.7 N9 3.4 N9 1.3 N9 2 3.1 Ne 2.3 Ne 9.9 Ne j 0 Cs134 3. 3 -
1.7 N9 8.4 N10 8.1 N10 8.2 N9 5.9 N9 o <[ ($l)7 4 N8 3.9 N8 3.2 N8 1.9 NB x ,
e.5 N1 3.2 N2 5.4 N4 2.1 Ne 4.1 e.3 2 N2 5 5 Ka85m . .
s u 1.8 5.1 7.6 N1 2.1 N2 2.7 N4 9.9 N6 lg h h *
- 7.4 N2 e.e N1 e.3 N4 3.1 Ne oc s.2 91 4.1 ,1 3.5 r1
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1.8 N1 2.4 N4 9.3 N6 U 4.2 P1 6.4 6.8 N2 1 XE 133 '*
4 Ld CC _
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i o rdN 1.5 N9 1.8 N9 2.1 N9 1.7 N9 6.3 N1C 9.4 N10 1.3 N9 -
NA24
- 4.5 Nic 6 N10 6.2 N1o 2.4 Nio 7.5 Nic 7.7 Nic 7.8 Nio 7.3 Nic
- 2.6 N1o 3.4 N1o 3 8 N1o (R 51 6.7 N9 6.8 N9 6.2 N9
- 2. 3 N9 5.6 N9 7.1 N9 7.3 N9
- 9.4 N10 1.C N9 Co 58 .
8.8 N9 8.9 N9 8.6 N9 6.2 N9 8 N9 8.3 N9 1.2 N9 2.5 N9 3.8 N9 O6O
- tn e.e Ne e.e N9 9.3 Ne 7.5 Ne e.4 Ne e.5 He Z
- 1.1 N9 1.8 N9 2 Ne :
O .
2N 65
- 2. 9 N10 3 N10 2.8 NM 3.9 N H 1 N10 2.6 N10 2.8 N10
< IC 99 M
- 1.1 NH 3.7 N H (2
v 5.7 N9 6.1 N9 5.8 N9 Z 4.4 N9 5.1 N9 5.6 N9 3.7 N9 4.1 N9
$ g 1 I3I
- 1.8 N9 1 1.8 N8 2.2 N8 1.5 N8
'n 9.4 N9 1.1 N8 1.4 N8 O 5.6 N9 I133
- 3.6 N9 5.2 N9 1.9 N9 2.3 N9 3.2 N-9.9 Nio 1.2 N9 1.6 Ns
- 3.4 Nio 5.7 N1o e.3 N1o j $ Cs134 2.4 N8 2.9 N8 2.6 N8 8.5 N9 1.1 N8 2.1 N8
- 1.8 N9 2.5 N9 3.7 N9 o 7 Cs137 ~
1 > * * * * * * *
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cc .
o xgIs3 . . . .
e * * *
- u * * * * *
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CC -
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uwe - - --
1 i 2 30- 1300- i-330 I 1400-TH30- mmW- vr@xar--
- 600 1630'
- EN' T iioE i3oo is3o 1400 ' 430 1 500 1530 4.1 N1o 3.8 N11 5.9 N11 2.6 N11 2.4 N9 1.0 N9 9.4 N10 NA24 1. 5 N9 2.7 N9 2.5 Na 1.9 Na 9.7 N9 4.5 N9 1.3 N9 7.1 N1o 2.2 N1o 6.7 Nio 1.3 N9 (R 51 5.5 N8 3.4 N8 L.2 N8 9.6 N9 5.4 N9 5.9 N9 5.7 N9 3 9 N9
$$ 6 N9 5.4 Na 3.7 Ne 2.3 Na 1.1 Na 8.6 N9 81 N9 8 N9 7 4 N9 2.1 Na Co60 m
Z e.1 Ne 4.9 No 3.e Ne 2.1 Ne e.7 Ne O -
Zs65 9 N9 o > N9 7.9 Ne 3.2 He 8.8 N9 4.4N9 4.7 N9 2.2 N9 gg } gC) 2.7 N10 2.6 N10 1.1 N10 9.8 N10 1.2 N8 w
2 6.7 N7 4.3 N7 3.7 N7 3. 5 N7
- 5. 5 N9 5.4 N9 4.3 N9 1.6 N7 7.4 N7 l
g g I l3l z .
- O % 2.1 N6 1.6 N6 9.4 N7 6.8 N7 6.6 N7 1k3 9.8 N9 9.6 N9 8.7 N9 3.4 N7 1.e N7 z Cs134 2.7 Na 1. 5 N9 9.8 ua 5.6 N7 4.4 N7 3.6 N7 2.1 N7 i
j o 2.7 N9 5.2 N7 4.1 N7 3.4 N7 1.e N7 1.4 N7 1.3 Ne e.e Ne o a vcs137 2.2 He 2 Ne
- 2 > '
5.9 N1 4.7 N1
- 4.2 N2 3.o 1.1 e.7 N1 5 0 Ka85m *
- s u 3. 2 9.3 N1 8.6 N1 7.5 N1 9.6 N2 1.2 P1 h$Q * *
- oc s4 39
- *
- 6 8 N1 7 s et 3 4 v1 99 p Xe133
- a 9.7 N1 7.8 N1 6.9N1 e.4 N2 9.5 5.6 4 XE 135 * *
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O 1, -_
72 CHEMISTRY SAMPLIIG DATA s i .
NA ,
- 1. REACTOR COOLANT ACTIVITY Due to the nature of'this sernario, the activity of reactor coolant samples will be within the normal v.ilues of ' the plant. The dose rates from these sample'will be minimal and can be simulated by using normal sample values.
- 2. PASS SYSTEM When the PASS system is used for sampling the reactor building atmosphere, the dose rate from the sample will be minimal and the activity will be estimated from the Reactor Building Air ConcentraLion 135' elevation data listed in Plant Monitoring data. For all other-samples from the PASS sample system, dose-rates and activity can bc simulated by.using normal sample values.
- 3. REGULAR SAMPLE STATIONS AND DRYWELL AIR SAMPLE STATION The dose rates at the regular sample stations and the drywoll air sample station can be estimated for each time frame from the Area Radiation Levels for each area. The dose rates from those samples will be minimal and again the chemistry parameters will be
(
normal values.
e
(!
<~ ,
I
(,
i i
MAINSTACK IODINE SAMPLE DATA TIME 1600 1300 1400 1500 1000 -1100 1200 ~
1700
. Main Stack 1300 1400 1500 ~1600 1100 1200
~ Air Concentrations
](Ci/cc 6.25 N5 7.23 N4 3.24 N2 1.85 H5 4.86 N6 6.81 NS 6.69 N5 3.71 N5 I-131 2.88 N6 1.92 N6 2.48 N3 6.47 N2 I-133 3.51 N7 4.26 N6 6.44 N5 2.21 N3 9.71'N2 5.56 NS 5.21 N6 7.24 H5 6.97 NS Total Icdine .
Nota: Above assumes 24,000 CFM = 1.1328 P7 cc/sec Stack Flow Rate
' Total Activity i Collected (/(C1) 2.12 P2 2.46 P3 1.10 P5 6.29 Pl 1.65 P1 2.31 P2 2.27 P2 1.26 P2 I-131 6.52' 5.03 P3 2.20 P5 I-133 1.19 2.45 P1 9.79
}
- 7.51 P3 3.30 P5 1.89 P2 2.46 P2 2.37 P2 2.19 P2 Total Iodine 1.77 P1 .
,-Nota: Assumptions: Sample Flow = 2 CFM, cartridge 100% efficient, sample time = 1 hr Sample Volume = 120 ft3 = 3.3984 P6 cm3 .
I Exposure Rates (Based on " Rule of Thumb" R/HR = 6 CE: E = 0.5 M'eV)'
(US-unshielded; S-Shielded ( 1/10 US Value)
(
- carrying Dose Rate)
US 750 MR/HR US 100R/IIR US 70 MR/HR Us 90 MR/HR US 90 MR/MR US 80 MR/HR S 7 MR/HR, Contact US US 6 MR/HR S 75 MR/HR S 10 R/HR i
S 0.6 MR/HR S 9 MR/HR S 9 MR/HR S 8 MR/HR S US 1.-R/HR US 0.7 MR/HR US 0.9 MR/HR US 0.9 MR/HR US 0.8 MR/HR US 7.5 MR/HR
- 1 Foot US US (.1 MR/ilR S 4.1 MR/HR S 0.8 MR/HR S 100 MR/HR S 4.1 MR/IIR S ( 0.1 MR/HR S40.1 MR/HR S (.1 MR/HR S
US (.1 MR/HR Us 0.9 MR/HR US 110 MR/HR US ( .1 MR/HR Us US ( .1 - Mr/IIR US (0.1 MR/HR US 4.1 MR/HR S 11 MR/HR S ( .1 MR/HR 3
3 Foot S ( 0.1 MR/HR S 4 1 MR/HR Sa(.1 MR/HR S (.1 MR/HR S S ( .1 MR/HR Building Exposure Rates 5 MR/HR 700 MR/HR 0.5 MR/HR-0.6 0.6 0.5 MR/HR At Door < .1 MR/HR 5 MR/HR 50 MR/HR 7 R/HR 4.5 MR/HR
- J.4 MR/HR 6 MR/hr 6 MR/HR 1
Inside
. . .- . .. . -.. - --. .. . . . - - . ~ . , . . . . . . ~ . . . . . - . .
. ~ - . - - . .. .
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1 RADIOLOGICAL RELEASE
( ,
t i< * ;
I . DATA AND CALCULATED i i
DOSE RATES-
+
e, -
.t i .
N 2 -NOTE: Dose' Rates' Include Plume Shine
. s 9
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i j
3
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i s
s s l
t t
r k
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t' i
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1 4
4 3
4.
4
- $ w MrTW-#yd -9 9 N(-yaq 47W e' WyMWT yp tytF m W=rtghTp g g*NWWp p"WW
RADIOLOGICAL RELEASE DATA EMERGENCY DRILL 6-28-83 Wind Directions from 110 .
Wind Spoed: 3 0 mph @ 320' Stability Class: Stable Timo of Roloauo: 0800-0620 #
- Flow Rate
- 2.0 x/0 cfm Gource of Release 0/3 RV
- Normal Range Monitor Count Rate: 3.0 510 CPM High Range Monitor Count Rate M01/s; Iodine Release Rate / d a/o' f(01/s N. G. Release Rate 3 9 4/0 ABUNDANCES ou.: % xE 138 ung g KR 85 uun % xE 133 our % XE 133m our %
KR 85m % I-131 e s.s %
KR 87 uux %
XE 135 x= 135-our e-
- I-133 +>
- xn 88 ~-
.O XE 131m ou s. % XE 137 oux %
DOSERATES(mr/hr) IODIE INHALATION INGESTION NOBLE GAS O o o e S.B.
o 0.4 1 mi. O
- o 2. 6
%.5 2 mi. O I.3 115.8 ,'
3 mi. o 1.5 to7 8 8 la mi. o 1.g H o.5 5 mi. o c.9 621.3 6 mi. o 4 '3
o.6 8 mi. o .
192 3 o - 0.+
10 mi.
O
= ,-e < -,,,,wr-vn,. ,- w~..---..-,..e.,.--,-emrw,,~.-.-.,r.__.--..,-m.---+-e,.-ev--w-, - - - .
RADIOLOGICAL RELEASE DATA r
O EMERGENCY DRILL 6-28 83 Wind Dirootions from 110 .
Wind Spood: 3 0 mph @ 320' Stability Class: Stable Time of Roloauos 08Z0-o840
-Source of Releases u/3 AV i Flow Rate: 2. 0 A / * # cfm .
Normal Range Monitor Count Rate: 3 6 x to" cFM High Range Monitor Count Rate:
M0i/ag Iodine Release Rates /.ox/o# #01/a N. G. Release Rates v.tuo' ABUNDANCES l
our % XE 138 oux 35 oux % XE 133 l KR 85 our %
KR 85m una % XE 133m
% I-131 93.3 %
l XE 135 ou
! KR 87 uw %
- xE ,3sm --
- I-,33 .., 95 O xR 88 XE 131n.
on % XE 137 onw. %
DOSERATES(mr/hr) IODIE INGESTION INHALATION NOBLE GAS o o S.B. O o.y I
o o 1 mi.
l* 6 s o 2 t>
2 mi. O
- 8. 3 925.6 .
3 mi. o '
l 1
I.C to i 8,8 h mi. o
- s.: 790 5 5 mi. o '
03 6213 6 mi. e o.6~ m36 8 mi. o 292.2
- c .+
10 mi, o
1' l
RADIOLOGICAL RELEASE DATA O EMERGENCY DRILL 6-28-83 Vind Directions from 110 .
Wind Spoed: 3 0 mph @ 320' Stability ' Class: Stable Timo of Halonso 0 8 410 - 09 o o '
- Flow Rate
- 2.o xio # cfm Source of Releases uls EV- ,
f l
Normal Range Monitor Count Rates 6.9 x/o* cre High Range Monitor Count Rate:
M01/s; Iodine Release Rates t.ox/o' N0i/s N. G. Release Rate: 9.zuso#
ADUNDANCES XE 133 uwx %- XE 138 onx %
- KR 85 on % %
% XE 133m our
! KR 85m our
% I-131 es 3 %
KR 87 ou( %
XE 135 xs 135- e-
=<
- 1-,33 *.,
- r
)
O xn 88 XE 131m m--
our % XE 137 un %
DOSERATES(mr/hr)
INHALATION INGESTION NOBLE GAS e o S.D. O e o.H 1 mi. o l-a.C soth 2 mi, o
- s
- i. 3 92s. ,
3 mi. o t 607 8,4 I.(
h mi, o .
- s. r tio.C 5 mi. n .
a.9 621 3 6 mi. o
'I83.1 o o.6 8 mi.
o,q 292.1 10 mi, o -
4
---,-,w,,-,w-,,,-w-w--,-,n-,---m ,+- , , , , - -
RADIOLOGICAL RELEASE DATA EMERGENCY DRILL 6-28-81 Wind Directions from 110 .
Wind Speed: 3 0 mph @ 320' Stability Class: Stablo Timo of Rolonuos 0900- o92.o #
Source of Releases v/s RV i Flow Rates 7 0 */8 cfm Normal Range Monitor Count Rates t9m/**cem High Range Monitor Count Rates
- M01/s; Iodine Release Rate: 1.3 5 to
- RC1/s N. G. Release Rate: 2.n so ADUNDANCES o % XE 133 80r % XE 138 o %
KR 85 96 KR 85m o % XE 133m 9. r 913 %
o % XE 135 s. o % I-131 KR 87 % I-133 o %
a % XE 135m a KR 88 Q- XE 131m o % XE 137 o %
DOSERATES(mr/hr)
INHALATION INGESTION NOBLE GAS o 3 S.B. o o , sl e
1 mi.
o c is ootb 2 mi. _
s
- s. 3 9;r R ,
3 mi. O n o , t. Y o a.1 h mi. .
,90.5 5 m1. o i.
9 o.e 62i.3 6 mi. o 0.6 40.1 8 mi. o ,
- o. 4 2 ci t .9 10 mi. o 0
p , -~ -~,-..-y--w,--,---n - - , - , . - - - - ,, , , - - . , - -,w- em-am-n,n-w----,-,m,m..n-,,wra,e,-a-w,.,- -,,,,--m,-,,.,.n.-,,,wna., , - - ,
j - ... ,
e l
h RADIOLOGICAL RELEASE DATA EMERGENEY DRILL l
l 6-28 83 ,
i i
Wind Directions from 110 .
Wind Spoed: 3 0 mph @ 320' l
Stability Class: Stable l
Timo of Rolcacos 0920- 094o Source of Release: MS ; Flow Rate: 2.v x /o # cfm I Ncrmal Banco Monitor Count Rate: 4. S nio ' ces High Range Monitor Count Rate l
N. G. Release Rate: 2 9 s so# MC1/s; Iodine Release Rate: S t eio ' RC1/c ABUNDANCES 81.4 % XE 138 o %
KR 85 o %. XE 133 o.3 % XE 133m i. 9 - %
KR 85m~ %- I-131 93.3 %
t o % XE 135 e.r. 9 KR 87 % I-133 6i %
o % XE 135m o. 4 KR 88 XE 131m o % XE 137 o %
L'0SERATES(mr/hr) IODIE INHALATION INGESTION NOBLE GAS o o S.B. O i o o 1 mi. o o o 2 mi. o o o 3 mi. o o 7. '/
L mi. o o.z / z 6. 9 6 mi. o t
o.8 514.2 6 mi, o IT6. t 8 mi. o o. 8 J
- 0. S S32.8 10 mi. o 1
t
,,--,,..-,e- .----,.--------,--,,,--,,,--,-,,-w,,,... .--,w,, -.-,-~.#-,+w---.---- ,- ,-,r...---vw-- - , - - , .- +
RADIOLOGICAL RELEASE DATA
{4 EMERGENCY DRILL 6-28-83 Wind Directions from 110 .
Wind Spaads 3 0 mph @ 320' Stability Class: Stable Timo of Roloauo: 0940 sooo 4 cfm Source of Release: MS I Flow Rate:J. V r to Normal Ran6e Monitor Count Rate: 4.V x /O ' cn liigh RanSe Monitor Count Rate:
3 N. G. Release Rate: 2. 8
- s o mci /a; Iodine Release Rate: 4 9n eo ' RCi/a ABUNDANCES o % E 133 88.4 % E 138 o %
KR 85 i. 9 -%
KR 85m o.3 % XE 133m
- <> 1-,31 esa O xR 87 KR 88 o
o %
= 3s XE 135m o. 4 94
% I-133 e7 S; XE 131m o % E 137 e %
l LCSERATES(cr/hr) IODIE INHALATION INGESTION NOBLE GAS O o o S.D.
o o o 1 mi.
2 mi, o o o l
o o o j-3 mi, o 7. 4 i h mi, o l
0.z /26.9 5 mi. o 0.8 59 V. Z 6 mi, o -
o c.8 5s68 8 mi.
o o.8 532.8 _ ,,,,3 10 mi.
0
--w,-r -..e --,,e-- -, , , - - < , ,y ,n, ,,,,,-,,_,,,.,.v. r,,,,,,,.~. ,.w, ,-n..--,,..-,-,.,--.-.,,,,,-,--.~,,,e. - , ,-,,-a.,--- n,
O nin10 toc 1 cat nE12^sE nort IEERGEN5Y DRILL 6-28 83 .
Ylind Directions from 110 .
ilind Spood: 3 0 mph @ 320' Stability Class: Stablo Timo of Roloauos toco toZo Source of Release: MS 1 Flow Rates E.Vx/of ofm Normal Ranco Monitor Count Rates yz zio ' ces High Range Monitor Count Ratos N. G. Release Rate: 7.7 x s o
- mci /s; Iodine Release Rater r ? x /O' f(Ci/c l' .
A30EANCES i
XE 133 &n4 % XE 138 o %
KR 85 o %
t o.3 % XE 133m s.9 %
p KR 85m
% XE 135 er. e % I-131 es. 3 %
KR 87 o %
KR 88 o % XE 135m o. u % I-133 6a XE 131m o % XE 137 o %
DOSE RATES (cr/hr) IODIE INHALATION INGESTION NO3LE GAS o o o S.B.
o o 1 mi. O o o 2 mi. o o o j mi. o o 7. 4 b mi. o 0.t 126.9 5 mi. o o.g S94.2 6 mt. o _
Sis. i 8 mi. o o. 3
- 0. 8 532 6 10 mi. o
.O
~ -
e.
RADT0 LOGICAL RELEASE DATA
{-
EMERGENbYDRILL
- 6-28 83 ,
4 Wind Directions from 110 .
Wind Speed: 3 0 mph @ 320' Stability Class: Stablo .
Timo of Boloauos 1020-1040 Source of Release MS ; Flow Rates ?.</ x /o 4 cfm Normal Range Monitor Count Rate 4.Yxto' cpi High Rango Monitor Count Rate N. G. Release Rate: 2. S s to # M01/a Iodine Release Rate: 5. 9 = / o ' f(Ci/a ASUNDANCES XE 133 si. 4 % XE 138 o %
Kn 85 o %
- o. s % E 133m <9 %
KR 85m
- 1-131 >>
- O xR 87 KR 88 o
o %
xE 135 XE 135m
<. e o.* % I-133 6.7 %
i XE 131m o % XE 137 o %
DOSERATES(mr/hr) ODIE INHALATION INGESTION NOBLE GAS o c 0 S.B.
l-o o 1 mi. o o o 2 mi. o c~ o 3 mi. o o 7. #
b mi. o 0.2 /26.9
$ mi. o 0.8 s94.2 j 6 mi. o 8 mi, o c. e tr6. t
- 0. 8 S3 z. 8 10 mi. o O
ninTotoo cat astress name O
EMERGENbYDRILL 6-28-83 .
Wind Directions from 110 .
Wind Spood: 3 0 mph @ 320' Stability Class: Stable Timo of Holouuos r o to- s ooo Source of Releases v.s 1 Flow Bate: 2.v x to # cfm Nom.a1 Hango ;bnitor Count Rato: 3 6 wso* CPS Iligh Rango Monitor Count Ratos N. G. Release Rate: 2. V x t o ' mci /s; Iodine Release Rato: 5. 9 /o ' Nei/c ADUUDANCES fe. 4 % XE 138 o %
KR 85,_ _ o % XE 133
- o. 3 % XE 133m i. 9 %
KR 85m % I-131 93 3 %
o % XE 135 e r. 9 KR 87 % I-133 6. > %
s KR 88 o % XE 135m o.*
XE 131m o % XE 137 . %
DOSE RATES (mr/hr) IODIE INHALATION INGESTION NODLE GAS O o G.D. O o- 0 1 mi, o O O 2 mi. O o o 3 mi. o o 7. 4 h mi, o
- 0. 2 t z 6.9 5 mi, o 08 59 v.2 6 mi, o
- o. 8 fr6 i 8 mi. e
- o. S 532.6 10 mi, o
- o
- _.2 .-- . ,
RADIOLOGICAL RELEASE DATA EMERGEN Y DRILL 6-28 83 Wind Directions from 110 .
Wind'Spood: 3 0 mph @ 320' Stability Class: Stable ,
Timo Of HO10acO: /e00-is2o Dource of Release: MS ; Flow Rate: 2. </ x /o Y cfm Normal Rango Monitor Count Rato: </.Yaeo# ces i
! IIigh Rango Monitor Count Rator N. G. Release Rate: 2. t = t o # mci /s; Iodine Release Rate: 8.z x eo
- f(ci/c ABUNDANCES' l
KR 85 o % XE 133 F/. 4 % XE 138, o %
Kn 65m n3 % XE 133m i. 9 %
(]
KR 87,,_
KR 88 e,
o
..XE 135 XE 135m
/.r. 9
- o. 4 o
I-131 I-133 9 v. /
ev XE 135m o % XE 137 DOSE MTES (mr/hr)
IODIE INGESTION KOBLE GAS INHALATION
- o. 8 i o 0 S.B.
O./ T o o 1 mi.
2 mi. O.19 o a
- o. M o o. #
3 mi.
o o.s 103.1 h mi.
6 mi. O 2. f J. !
- 10 6'mi. 0.84' is. 9 f.3 x to 8 mi. o.83 /e./ 7. f X /0 3
t o. G 7 f " <*
, 1C mi. o.st O
, . - , - ..w.---n-w.---.-,. n-,,,--r.e ,,,,,,..,--r,,cr.,-,,,--,-,,--v
..w.v,,v.. -
RADIOLOGICAL DELEASE DATA EMERGENUY DRILL 6-28-83 ,
Wind Directions from 110 .
Wind Spoed: 3 0 mph @ 320' Stability Class: Stable .
Timo of Roloauos u2o-o 4o Source of Release M6 ; Flow Rate: 2. 4 w to V cfm 3
Normal ihmgo Monitor Count Ratos s. / x f o cps Ilich Rango Monitor Count Ratos N. G. Release Rate: 3.3 xto # MC1/s; Iodine Releaso Rator f.2 =so* f(C1/o ADUNDANCES 88 4 % XE 138 o 96 KR 85 o 96 XE 133 o.s % XE 133m s.9 %
KR 85m xE ,3s
- 1-13, e, u O xR 87 KR 88 e
o-96
% XE 135m
- r. ,
- o. 4 % I-133 r9 9 ',
XE 131m o % XE 137 o %
DOSE RATES (mr/hr) IODIE INHALATION INGESTION NOBLE GAS o o G.B. o.22 o o 1 mi. o.22 o o 2 mi. o.11 o o. 4 3 mi. o.22 o.: 10 3.1 L mi. o 2.c t. 8 m to 6 mi. o e s. 9 f. 3 = / o 6 mi. o.n
<<.' 7. 8 s e o" 8 mi. o. i w e o. 6 7.8'uso 10 mi. c. i s Mv
_ _ . - . . . ~ . . . - . _ - _ . _ _ _ . _ _ . _ _ _ _ . _ _ _ - ~ _ . _ . . - . . . _ _ - _ _ _ - - - _ _ _ . _ .._ ._... _ __.___.__.._ _ ____
a O na m o'oo1c^' nutz^sa u^m^
EMERGENCY DRI_LL, 6-28 03 ,
Wind Directions from 110 .
Wind Spoed: 3 0 mph @ 320' Stability Class: Stablo .
Timo cf Rolcacos n40-1100 V cfm Source of Release: AA 5 i Flow Rate 2. y x /o Normal Rango Monitor Count Rate: I. i = eo 3 e es f, High Range Monitor Count Rates
> N. G. Release Rate: 3.3 x s o # M01/s Iodine Belease Ratos t.Z ='o
- f(C1/u ADUDDANCES 8/. 4 % XE 138 0 %
KR 85 o % XE 133 KR 65m o.s % XE 133m e9 %
O xn 87 e
- xE ,3s ,<.,
o.4 1-13, I-133 e.* ,
s9 w
KR 88 o % XE 135m XE 131m o % XE 137 o %
LCSERATES(ar/hr) ION INHALATION INGESTICU
. NOBLE GAS o.22 o o C.B.
1 ai, o.21 o a o.zz o o 2 mi.
O.20 o 04 3 mi.
- o. / 0 3.2-h mi. O o 1.c 1.!*10 6 mi.
O 8 'i 88.9 8.3 510 6 mi.
~3
- .t 7. # n to 8 mi. O. # 6 80.6 ~1. S > '
- 10 mi. 0. !!
O r----+y--ww. ---~ - w w w ,-,ww ,,--c,w------*>,.y-,---,.,--,,-y, --e,o. , w w ,,-w,,-gc,pw+- ,.--.-e-- y,,- ,v.- - - . , - -n-g-
h RADIOLOGICAL RELEASE DATA DERGENbY DRIL'g 6-28-83 ,
1/ind Directions from 110 .
Wind Spood: 3 0 mph @ 320' Stability Class: Stable .
Timo of Roloaco: 110 0- il2 o Source of Release: MS i Flow Rate: 2. 4 x /o " ofm 3
Normal Rango Monitor Count Rates % 9 x /0 cps High Range Monitor Count Rato:-
N. G. Release Rate: 3.15 3 e ~ mci /a; Iodine Releaso Rate 7. 9 x /o
- f(C1/c ADUNDANCES
% XE 133 f t. 4 % XE 138 o %
KR 85 o o.3 % XE 133m i. 9 %
KH 85m vr v %
O KR 87 Im 88 o
o XE 135 XE 135m
/ r. 9
- o. 4 I-131 I-133 v./ %
f XE 131m o % XE 137 o %
DOSERATES(mr/hr) IODIE INHALATION INGESTION NOBLE GAS 0.It o o _
S . D .-
f o 0 1 mi. O. 2 s o o 2 mi. o.17.
0.10 o o l 3 mi.
o o.l 104.3 b mi.
Z. f 17 ^ /0 5 mi. O 0t6 11. 6 8.7*
6 mi.
s o. t i., u /o '
8 m1, o sS
/ 0. # 7 3 *'o 10 mi. O. t 4 l
I
}
I ~
RAD 10 LOGICAL RELEASE DATA ICERGENCY DRILL 6-28-83 Wind Direction: from 110 .
Wind Spood: 3 0 mph @ 320' Stability Class: Stable .
Time of Ituloauo t 2 2 0- 24o Suurce of Release: AA S 3. Flow Rate 2.'/w/0 Y cfm Haruc1 Ranco Monitor Count Rate: t/. 9 u s o ' C PS
. High Range Monitor Count Rate:
N. G. Release Rate: J. Z x to # MC1/s; Iodine Release Rato: 7. 9 x io mci /c ABUNDANCES o % XE.133 ti. 4 % E 138 o 95 KR 85 %
o.s % XE 133m /. 9 KR 85m
- xs '3s < <. e
- 1-43' <<.**
O xn 87 KR 68-e o % XB 135m o. 4 % I-133 e/. / 95 XE 1311:1 o % XE 137 o %
LOSERATES(mr/hr) OME INHALATION INGESTION NOBLE GAS-o o S.D, c.z!
o o 1 mi. O. 2 i o o 2 ini. ' O . 2 2.
o o a 3 mi. o.z o 0.1 /o'.3
.h mi. o 2.C 4.15'O 5 mi. o s s. b e' {,
6 rai. O.t6 J o. I 1 7 *80' 8 mi. o. i f
'O.4 7.3580 10 rai, o . t *t 1
O
RADIOLOGICAL RELEASE DATA p' .
EMERGENCY DRILL 6-28 83 Wind Directions fr.om 110 .
Wind Speed: 3 0 mph @ 320' I' Stability Class: Stablo Time of Holoauos _ 1240-:300 Source of Release: MS ; Flow Rate: 2.Vx/a# cfm Normal Rango Monitor Count Rato: 4.7 x io# cp.s Iligh Rango Monitor Count Rate:
N. G. Rolease Rate: 3.i w 4o # mci /s;IodineReleaooRate: 7.9 x eo
- f(Ci/a i
ABUNDANCES
- 81. V % XE 138 o %
KR 85 o % XE 133
(
o.3 % XE 133m i9 %
KR 65m % I-131 mY %
o % XE 135 er 9 g KR 87 a I-133 4/ %
KR 88 o % XE 135m o. v 4 v XE 131m- o % XE 137 o %
7 l 110SE RATES -(mr/hr) IODIE INHALATION INGESTION NOBLE GAS f o o S.B. o.2o o o 1 mi. o .2 i o o 2 mi. o.2i o o 3 mi. o.i9 c.: t o t. 3 L mi. o 3
- 2. r i.7 510 5 mi. o 3
//. 6 T. 2 x to 6 mi. o. i e e o. B _1. *'o' 8 mi. o. i r 3
s o. 4 7.3 580 10 mi. o. i q 0
RADIOLOGICAL RELEASE DATA
{,
IEERGENdY DRILL 6-28-83 tlind Directions from 110 .
Vlind Spoed: 3 0 mph @ 320' Stability Claas: Stablo .
Timo of Rolcaco: 3300 1320 Source of Release: MS Flow Rate: 2. d/ x t o # cfm Homal Rango Monitor Count Rato: 4r.4 x/o'ces High Rango Monitor Count Rates '
- 7. 3 x / o
- f(C1/o N. G. Rolease Rate: 3. o v. t o
- mci /s Iodine Release Rate
' ABUNDANCES
% XE 133 ti. 4 % XE 138 o %
KR 85 o
- o. 3 % XE 133m <1 %
KR 85m
- xs '35 < <. 4
- 1-'3' >e a
.O xn 87 KR 88 o
o % XE 135m o.* % I-133 ro %
XE 131m o % XE 137 o %
D0saRATES(mr/hr) IODIE INHALATION INGESTION NO3LE GAS o
- g,n, o. 2 l o o 1 mi. 0. 2 o O . ~L s o o 2 mi.
- o. L 6 o o f 3 mi, h mi, o c.t 9'/. 6 o 7. 3 t. 6 x to 5 mi.
o 85' t o. Y 7. 6 * /
6 mi.
3 so./ 7. I " ' O 8 mi. 0. t H 3
- 9. ~1 6A " #
10 mi, o.13 O
RADIOLOGICAL RELEASE DATA IFERGEN5Y DRILL 6-28-83 ,
tlind Directions from 110 .
Wind Spood: 3 0 mph @ 320' Stability Class: Stable ,
i Timo of Roloauos i 3Z o- i3 40 Y
Source'of Release: MS ; Flow Rate: 2.4xto cfm 3
Normal-Rango Monitor Count-Ratos v.v x eo en Iligh Rango Monitor Count Rate:
N. G. Release Rate: 2.9 x !o # MC1/s; Iodine Releaso Rates 7.34/o# RC1/a ADUNDANCES I y/. V % XE 1,16 o %
- KR 85 o % XE 133
% XE 133m i. 9 %
- KR 65m o.3
- xs '3s 's. e
- 1-'3' *>
- i l
O xn 87 KR 68 e
o % XE 135m o. 4 % I-133 3o %
XE 131m o % XE 137 o %
l DOSERATES(cr/hr) IODIE INHALATION INGESTION NOBLE GAS o.2o o o s.B.
0.s9 o o 1 mi.
o.zo o o 2 mi.
Q.I E o o 3 mi.
o a.e 9s/. 6 1.t mi.
23 1. 6 x / 0 6 mi, o 10.8 7. 6 m to C mi. 0.rS I o. 8 7. / A / 0 8 mi. o. I'f 3
- 9. 7 4. 7 x #8 10 mi. o.a3 l
. _ . _ =
RADIOLOGICAL RELEASE "ATA O EMERGENbYDRILL 6-28 83 ,
Wind Directions from 110 .
Wind Speed: 3 0 mph @ 320' Stability Class: Stable .
Timo of Rolcaco: l'340-8'600 Source of Release: MS ; Flow Rate: 2. 'v x /o f ofm f
Normal Range Monitor Count Rates v. V x /o ces High Rango Monitor Count Rate:
N. G. Release Rate: 2. t x / o # mci /s; Iodine Release Rate: 7. 3 = / o *1(C1/c ADUNDANCES 0 % XE 133 ti. V % XE 138 o %
Kn 85 KR 85m o.3 % XE 133m i. S %
/ r. 9 % I-131 97 o 'A l
l n
V Im 87 le 88 o
o XE 135 XE 135m o. 4 % I-133 3. o 5' l XE 131m o % XE 137 o %
I DOSE RATES (mr/hr)
! NOBLE GAS INHALATION INGESTION o o S.B. o.i9 1 mi. o.iq o o
- o. q O o 2 mi.
0 o 3 mi. o.87 h mi. 0 0.8 9 '/. 6 2.3 s.6 x to 5 mi. 0 6 mi, os4 /o. 8 7.6xto 8 mi. o.n3 s o.s 7.1 x t o l 3 6.TEto
! 10 mi. o. t 2. 9.1 lO
~
n^"'o'oo o^' n8'n^su "^T^
O EMERGENbY DRILL 6-28 83 Wind Directions from 110 .
Wind Spood: 3 0 mph @ 320' Stability C' Jass: Stable Timo of' Roloauo :Hoo- 9 zo Source of Release M5 ; Flow Rate: 2. '/ x t o # cfm 4
Normal Rango Monitor Count Rato: 7. 8 x t o ces High Ranco Monitor Count Rates _ i.54 **/na N. G. Release Rate: 9. -i x , o ' M01/si Iodine Release Rate: 2.s = n RC1/c ADUNDANCES XE 133 81 4 % XE 138 o 9's KR 85 o 96 96 XE 133n i.9 96 KR 85m e.3 x8 '3s >>e
- 1-'3' 31. , 9s O xn 87 KR 88 e
o s'
90 XE 135m o.9 96 I-133 6r3 %
XE 131m o 96 XE 137 o 96 LCSE RATES (mr/hr)
ODIE INGESTION NOBLE GAS INHALATION o o
!3. D . 3.1 3.i e o 1 mi.
'2 mi. 3.2 o o 4 c.1 2.7 3 mi, 2.9
- l. I x, l o h mi, o 2. 3 Y
5 mi, o. 5;; 39.0 /.9 x /o
/ f2.2 9. 0 x / 0 6 mi. 2.4 Y
e 6 9. 7 8.'t = / o
. 8 mi. 21 10 mi, # 6 /. 8 f 0 ^ 'O 2.)
O
RADIOLOGICAL DELEASE DATA-EMERGENdY DRILL 6-28 83 Wind Directions from 110 .
Wind Spood: 3 0 mph @ 320' Stability Class: _ Stable .
Timo of Rolonuoi /420-/440 Source ci Release: M5 i Flow Rate: 2. V x /o # cfm Normal Rango Monitor Count Rato /. r x e o # cAs High Rango Monitor Count Rate: 16. 4 ** A/wg N. G. Release Rate: 9.6 x to ' M01/s; Iodine Release Rate 7.r x/o # (C1/o f ABUNDANCES IG 85 o.3 % XE 133 s 7. 2 % XE 138 z.3 9l, KR 85m r. r % XE 133m z.2 %
KR 87 ,. % XE 135 9.7 % I-131 32.7 %
pV KR 88 13. 5 % XE 135m 6.9 % I-133 67.3 %
XE 131m o.z % XE 137 o %
DOSE RATES (mr/hr)
IODIE 1NGESTION NO3LE GAS INHALATION S.B. 26.6 o o 1 mi. 24.9 o o 2 mi. 22.6 o o 3 mi. 10% t o. : 21 h mi. O.27 2.3 /, / x /o 4.3 39.0 1. 9 x to g m1, I f. P / T2.2 9,o x /o #
6 mi.
8 mi.
/ r. 7 e69.7 1. V * '#
10 mi. /3.3 i 6 /. # f. o d l' O
x nin'otooto^t astr^ss >^m^
.O EMERGENCY DRILL 6-28 83 .,
~~
Wind Directions from 110 ' ,
Wind Speed: 3 0 mph @ 320' Stability Class: Stable .
Timo of Ro1cano / 490- I foo Y cfm Source of Release: MS i Flow Rate: 2.We/0 Normal Rango Monitor Count Rates High Rango Monitor Count Rates' 2 7. Y '" "/es,c N. G. Release Rates I.hvio' mci /s;IodineReleaseRate: 2.fsso"1(C1/o ABUNDANCES (2. z, % XE 138 2.3 %
KR 85 o. 3 % XE 133
- r. r % XE 133m z.z %
, x3 85m v. 7 % I-131 22.7 %
KR 87- 7.s % XE 135 %
s 3. 5 % XE 135m 6.9 % I-133 67.3 KR 88 XE 131m o. 2 % XE 137 o %
l IcsE RATES (mr/hr) IODIE INHALATION INGESTION NO3LE GAS o o S.B. 4 4. Y o o 1 mi. 4/. f o O 2 mi. 37.6
< o. 2.7 3 mi. 32.o 2.3 //*/8 L mi. O. y 4 3 9. O t. 9
- IO g mi, -3.,
/ JZ. Z 9.0x/O 6 mi. 33.3
/69.7 I. 4 " #'
8 mi, 26.1 Ibl. B 8.0 K ib
.10 mi. 22.2.
O
RADIOLOGICAL RELEASE DATA
{ DERGEN0i DRILL 6-28-83 .
Wind Directions from 110 .
L'ind Speed: 3 0 mph @ 320' Stability Class: Stable ,
Timo of Ro1caso: tro o - siz o Source of Release: MS i Flow Rate: 2. $f x /8 Y cfm Normal Rango Monitor Count Rate High Rangc Monitor Count Rates ( 7 2.9 " 5/w e.
N. G. Release Rate s_ I/ x/o # M01/s; Iodine Release Rates _j.I xeo' hC1/s ABUNDANCES KR 85 c.3 % XE 133 52 2. % XE 138 2.3 95 KR 85m r. r % XE 133m 2.z %
KR 87 7.i % XE 135 v. 7 % I-131 33.3 55 O xR 88 2.<
- xE 135m /. . e
- 1-133 4c> 95 XE 131m o.I % XE 137 o %
ICSE RATES (cr/hr)
NO3LE GAS INHALATION IODIE INGESTION S.B. I414 e o 1 ci, 1322 o o 2 ci, li % 8 o o 3 mi. 01 0. Z B 2 2.1 L mi, S H. I l o o . ~1 S. o s t o #
6 mi, 3 L n . 't I.~l s to g,(, y 10 b 6 mi, 996.6 F. I x t o go x to 6 8 mi, 8.7/ i 7.5xto 3.Y y/0 10 mi, 707.6 7.2y/o' 3. (, X / 0 '
i
RADIOLOGICAL RELEASE DATA cxsaoesor uartt O 6-28-83 Wind Directions from 50* .
Wind Spood: 3 0 mph @ 320' '
Stability Class:, Stable .
Time of Rol'oauoi 1520-swo Y ofm Bource of Reloanos kA . R. ; Flow Dato: 2N x /0 Normal Rango Monitor Count Rato:
509.5 */ng
- High Rango Monitor Count Rate:
s Mai/ag Iodine Release Rate: /./ a/0 #01/s N, G. Release Rate: 3.2*Io ADUNDANCES Sv. / % XE 138 /./ %
o.3 % XE 133 Kn 85 XE 133m y3 %
KR 85m^ e. 2 % % I-131 33.s %
XE 135 ei. 2 KR 87 6. ( % % I-133 6 6. / %
XE 135m 67 KR 88 is. 6 %~
% XE 137 o %
Os XE 131m o.z l
l DOSERATES(mr/hr). IOD M INGESTION
' ' INHALATION NOBLE GAS o o S.B. 6 06.3 .
o n
1 mi. 819.o
- i. o o
2 mi. v r e . 6- , \
? . Cl t I o U s
- 't .*l _
3 mi. 4. G 8.9 247%
l.4 % f 0 b mi. 475.2
- 6
- 1. 5 5 5 s o'1
- i.7 % t o ,
$ mi. font.3 0
r . *< 9 v I D N t. t v 90 .
6 mi. So c. c 30BA t t, m e; x so b 8 mi. 367.6
- .44 = e 3 4.2 = s o "
10 mi, 2 '. ;. o O
.v ,,--,--._-a., ..y.,,.. .,.,,_n 7, ,.,,,,._,,.,_,_.._,._,,.,.,,,,..w,__ , , , , . _ , , . , , . , . , , . , ,,,,,,._,__.,_,,,y.,_.,_,-e...,n,n, . _ , -
RADIOLOGICAL RELEASE DATA EMERGENCY DRILL s
6-28 83 Wind Dirootions from 50' ,
Wind Spood: 3 0 mph @ 320' .
Stability Clas: . Stable .
J
/0 0 0 Timo of Rol'oauoi /5~'/o M5 i Flow Date: 2.'/xto
- cfm Sourco of Releano:
Normal Rango Monitor Count Rates High Range Monitor Count Rates / 9 /. / "'%:
8 N. G. Release Rate s /.2 x /o M01/s) Iodine Release Rates /./ = /0 ' #01/s ADUNDANCES r v.' % XE 138 /. / %
0.3 % XE 133 KR 85 s. 7 %
- r. z % XE 133m %
KR 85m XE 135 < /. 2 % I-131 ss. 2 KR 87 6E % % I-133 66 7 %
XE 135m 6. 7 KR 88 n.6 %
% XE 137 o %
C XE 131m o. 2 DOSERATES(mr/hr). IOD M INGESTION
' INHALATION NOBLE GAS o o ,
S.B. Soo.s a n
o <
1 mi. so i.: .
/. o o
2 mi. ver.2 5 9. ~I
- z. s n so Y ,
3 mi. 2 1,.1
- 1. Al y t o ij b.~L 192.I h mi,
/ IT * /* 17A/0 ,
$ mi. 2 7 '/. 6 s.3'iE10 6 R a 10 ,
eqq 6 mi. ,<2,
/. O J'
- to 6. </ x /0 O mi. i -a,q e b .
3 e/. 7 y j o
.) y, c V. '/'/ x 10 10 mi.
O .
4 j .
RADIOLOGICAL RELEASE DATA EMEI1 GEN 0Y DITILL 6-28 83 .
a Wind Directions from 50* ,
7 Wind Spood 3 0 mph @ 320' i
Stability Class: Stable ,
Timo of Rolonso _ 1600 ic 70 V< g Flow Bate s 7. '/ x to V ota Source of Boloanos
- Normal Rango Monitor Count'Rator /. 5 x to 'l c es
/. 5 High Rango Monitor Count Rates N. G. Release Rate 9. (,, x /0 # M01/sl Iodine Release Rater 43 = /o
- hC1/a ABUNDANCES re/ % XE 138 /. / %
KR 85 0.3 % XE 133
.r. 2 % XE 133m 23 %
- KR 85m n.z % I-131 33.9 %
KR 87 6. r % XE 135 66 7 %
% XE 135m 6.7 % I-133 KR 88 n.6 o . z. % XE 137 o %
XE 131m Q.
- DOSERATES(mr/hr).
' INHALATION INGESTION NOBLE GAS
- o o
S.B. 2.4 o o .
1 mi. 2.E 0 O 2 mi. 2 . *3 .
i o
- Id 9 g, 3 mi. 2. o
/. 7 807.4 h mi. o. 3 J .
s.9 44os ,
,. e i 5 mi.
i */ , 9 3947 ,
b mi. /. I
- 6. z aono
- 8 mi. i.,
W. S 2425 .
10 mi. d. 8 O
-.- . ,-.+, . - .
r , e--. <--,-.4-. ,, . - , . , , - - - - - - ~ - - - - , - . - , _ , , , , , , - , , - - . . , , , , , , , , - - . , , , - - - . . - - - - , _ , - - . - , - , - - , - _ . , - -
4 RADIOLOGICAL RELEASE DATA EMERGENCY DRILL 6-28-83 NIElk Wind Directions from 50' .
Wind Spood: 3 0 mph @ 320' Stability Classt. Stable ,~,
, Timo of Rol'oauo 16 7 0. /6 t/o Source of Release: MG i Flow Rate: 2 </ x / o 'I ofm Normal Rango Monitor Count Rate: 3 F =/0* ces High Rango Monitor Count Bato:
- ~
N. G. Release Rate: 2. .rx / o 'l MC1/as Iodine Release Rates 6.3 = io
- f(01/s ABUNDANCES KR 85 o.7 % XE 133 N/ % XE 138 e1 %
L KR 85m r. 2 % XE 133m 7. 3 %
! KR 87 6. I % XE 135 e i. 2 % I-131 ss 3 %
KR 88 / 2. 6 % XE 135m t. i % I-133 66. r %
XE 131m o . 2. % XE 137 o %
DOSERATES(mr/hr).
' INHALATION I I# INGESTION NOBLE GAS S.B. < o., o o .
1 mi. < 0.i o o ,
2 mi. <o.i o n 1
e 3 mi. e... o e6. 9 s la L11. O t. 7 427.6 ,,
si mt. o 8.9 t/4os .
6 mi, o 79 3942. .
8 mi. o 6. 2 soso 10 mi. o it.
- 2 atz .c O .
RADIOLOGICAL RELEASE DATA .
EMERGENCY DRILL 6-28-83
' Wind Directions from 50' ,
Wind Spood: 3 0 mph @ 320' Stability Classa. Stable ,
~
Timo of Rol'gauos 16 e/o - / 7 o o M5 ; Flow Rate s 7.. 'I x /0 4 cfm Source of Releaaos Normal Rango Monitor Count'Ratos /. 2 x / 0
- c a s > .
High Rango Monitor Count Ratos "
3 N. G. Release Rate 1,0 = / 0 M01/s) Iodine Release Rate: 4.35/0* #01/s ADUNDANCES r v. / % XE 138 /' %
KH 85 0. 3 % XE 133 rz % XE 133m 7.3 %
Kn 05m % I-131 33.4 %
KR 87 6. r % XE 135 , i. z s7 6 % XE 135m 6a % I-133 66.r KR 88 x"
- xs '37 - %
O '3'= '
l DOSERATES(mr/hr). #IE
' INHALATION INGESTION NOBLE CAS o o l S.B. O o o .
1 mi. O o o 2 mi. O
- s o e6 9 g 3 mi. o
/. l P 2 7 . (,
b mi. o
- f. 9 vvo< .
5 mi. n ..
- . 9 fa 9 4/ 2. .
6 mi. o 6.2 c4n e.o 8 mi. o vV 2 vi ('
10 mi. n <
O
- , , . , - - . - - , . , .-...--.v,. . . , . , _ , , . , , , . , ..-,_-.._._-.,,._,,--__.,,,...-,,,,..,e._,. ,,.,,,-,__.-%w_m_ - - , , - , , - , . ,
-. . - - . . - . ~
._- -. a.,a ..- ,
n b
~
l Midn:OROliXdICAL CONDITIONS
. +.
0 4
.DATE: . June-28, 1983 TIME: O (o 00 ,
The wind-is from the East South East (110') to the Wcat North West' (290*)' at 3.0 mph. ' Meteorological conditions are expected to fromain constant-for the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />..
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. . . ... . . . . . __. . . - . . . _ . _. .. . . _ _ . . _ . . . _ _ , . . . . . _ _ . . . _ . _ . . _ . ..__..m,____ ._..- ._
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l METEOROLOGICAL CONDITIONS.:
t 1:
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i-G t
7
- DATE: June 28, 1983. TIME: 0700 1 .
.L l'
The wind _in from the East South East (110') to the West North-West-(290*) :at 3.0 mph. Meteorological conditions are expected to i
r-
- remain constant for the next 12 Lours.
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METEOROLOGICAL CONDITIONS It a .
j: .
~
!- DATE: Juno 28, 1983 TIME: O F.> o o i
i
- i. -
4 f; The wind is from the East South East (110') to the Wout North I ! West (290') at 3.0 mph. Meteorological conditions are expected to n
i.
l- remain constant.for the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
4 5
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-,; . u- .= a. ;_:.~ :- - ~ , . _ , - - ~ . . , - . . . . . . ~ . , . . -
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. . t METEOllOLCX;ICAL CONDITIONS :
f J
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.DATE: . June 28,.1983 . TIME: '0900 F- .
1 i
t
, The wind ~is from the-East' South East (110*) toithe Wcat North West (290*) . at 3.0 mph. . Meteorological conditions aro expected to i.
._ remain-constant for the next 12. hours.
1-
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.----- -na- __ _ -~...-.-n-~ ., _.a__ _-,w,~,-wm. .m. m-
. .,. . ... ; -. . .. . - . . . . . = . - . . .- . . - - . - . - - . . - . . . . . . . . . ~ . - . . - . - - . - . - - . . . . -
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.t i MifrCOROLOGICAL' CONDITIONS i
I~
j' ,
i.
-! l 'DATE: Junu : 28, 1983 ' TIME: -IOOO f
- t. i i-f2 --
r to the Wout. North
_Tho; wind lu from the East South East.(110')
~
1-
. ;y f
West! .(290') eat'3.0 mph. Meteorological conditions are expected to l
, , . romain constant for the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
im 3 5
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- METEOHOLOGICM, CONDITIONS
,4.- ;
- j. . l-s i .
I~ 'DATE:. ' June 28, 1983 TIME: Ii O o i .
c i'
i l';
I.
- The wind is from the East South East'(110') to the West North l West (290') at~.3.0 mph. Meteorological conditions are expected to i<
I 1;
remain constant for the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. .'.'
t.
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t hQ 1-l' METEORO.l.i._XIICAT, C.ON_D,ITIONS t u >
t jo t ..
l DATES. June'28, 1983= TIME: 1 2.O O 3
!~ ,, .
1
?
The wind lu frorn the East South Eact (110') to the West North West ;~ (290') _ at 3.0 mph. . Meteorological conditions are expected to-l I
romain constant for the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
L 4
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.+,-...a.,4...,__-,___-_ _ _ , _ . _ . . _ _ _ _ ., --
. . _ , . - _ . -.._ _ _ . . . . . , . . .. . . . .-- . . _ _._m.. ._. _ _ . . . . .._m.._.~
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I MMTEOROLOGICAI. CONDITIONS i
- e t
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' -DATE: June 28, 1983 TIME: i 3OO~ .
i' to-the West North ;
,' Tho wind is frorr the East South East (110')
h l-Meteorological conditions are expected to j .
. West-(290') at 3.0 mph. {
P i.
remain' constant for the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. ,
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METEOROLOGICAI. CONDITIONS
-e e
l DATE: . June 28, 1983 TIME: 1400 4
I .
t-i; d
L i f
Tho wind is from the East South East (110') to the Wcat North-t West . (290') 'at 3.0 mph. Meteorological conditions'are expected to 1
I, romain constant for the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
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METEOROLOGICAL CONDITIONS i
DATE: June 28, 1983 TIME: /430 ," ,
The wind is from the East South East (110 ) to the West-North West (290 ) at 3.0 mph. A shift in wind direction is expected
' to' occur within the next hour.
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- . - . . . .- . .. - . . .- ~_- - - - - . .
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METEOROLOGICAL CONDITIONS .
i i
June 28, 1983 TIME: / 520 DATE:
i The wind is from the North East (50 ) to the South ;
West (230 ) at 3.0 mph. Meteorological conditions are expected -
to remain constant for the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
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-,--,--,,~,e ,,,--ren,w,, .,.,,,,,-~~m.--g-a-- m., ,,,--e
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METEOROLOGICAL CONDITIONS 8
' TIME: /li c o DATE: June 28, 1983
, The wind is from the North East (50 ) to the South West (230 ) at 3.0 mph. Meteorological. conditions are expected to remain constant for the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
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~-,,v r-ym,--n-+---,-,,e- -,-,meme,,,- -.,,e-nn-w,r,an.,,, , . . . -m,-e,.-~.n,,-,,nm--n-,-----n---,e,-w,-,__-w.,--ne
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l f4ETEOROLOGICAL CONDITIONS ,
l l
DATE: June 28, 1983 TIME: noo i
l The wind is from the North East (50j to the South West (230 ) at 3.0 mph. Meteorological conditions are expected to remain constant for the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
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I
- 7.3 FIELD MONITORING DATA
- NOTES:-
- 1) All field data is-time phased for-plume arrival'and departurc
- 2) Field survey dose rates include 3l plume shine c.
I' O
O Fiet.o Suavey De
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DEPOSITION FOR I-131XCi/M2 FOR' PASTURE GRASS, VEGETATION, AND SOIL SAMPLES 920-1100 1100-1200' 1200-1300 1300-1400 1400-1500 _1500-1600 1600-1700 S.B. 0: 0 0 0 0 O O 1 mi 4.4 N34 5.0 N34 5.6 N34 6.1 N34 2.5 N33 8.5 N32 8.5 N32 2 mi 1.3 NIO 1.2 N9- 2.3 N9~ 3.3 N9 3.8.N8 e 1.6 N6 1.6 N6
, .3 mi 6.6 N7 6.1 N6 1.1.N5 1.6 N5 1.8 N4 7,.4 N3 7.4 N3 -
4 mi 3.7 N4- 3.4 N3 6.4 N3 9.l'N3 1.0 N1 4.1 4.1.
5 mi 6.6 N3 6.4 N2 1.2 N1 1.7 N1 1.9 7.8 P1 7.8 P1 6 mi 3.2 N2 3.0 N1 5.6 N1 8.0 N1 8.7 3.6 P2 3.6 P2 7 mi 3.1 N2 2.9 N1 5.4 N1 7.7 N1 8.7 3.6'P2 3.6 P2 8 mi 2.9 N2 2.8 N1 5.2 N1 7.4 N1 8.3 3.4 P2 3.4 P2 9 mi 2.8 N2 2.6 N1 4.8 N1- 6.9 N1 7.5 3.2.P2 3.2 P2 .
10 mi 2.8 N2 2.7 N1 5.0 N1 7.1 N1 7.9 3.3 P2 3.3 P2 t
i i
NOTE: All values are-in ,uCi/M2
- 1. Depostion velocity is assumed to be 0.01 M/S i
4
- 2. All values are for 100% plume centerline. Values off this centerline can be calculated by using the offsite survey naps and mulitplying by the appropriate
~
i factors.
l 1
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u' .
- l-131 MILK CONCENTRATION The following equation was used to calculate the milk concentrationi.
(
Reference:
P f : fQC/y (g~h i8f I-6~c Ie e
f = Stable elementi transfer function (assume 6.0 N3 day /1 Q = Consumption factor (assume 50 KG/ day) j C = Ground level concentration (PCi/m2)
Yp =, Foliage Density (Assumed 0.7 KG/M2)
A,= 1/Tl I-131 = 1/8.06 = 0.124 day -I I
-f.(= 2 day Ae= 5.775' N3 hr-1
, 'te = 720 hr Maximum concentrations are calculated for each distance for 100t plume centerline concentration. Off Centerline values can be calculated using the-offside survey maps and multiplying by the appropriate factors.
I-131 MILK CONCENTRATION- ( pCi/l) '
S.B. O.
1 mile 4.8 N36 i 2 mile. 9.1 Nll 3 mile 4.2 N7 4 mile- 2.3 N4 5 mile' 4.4 N3
.6 mile 2.1 N2 7 mile 2.1 N2 8 mile 1.9 N2 9 mile 1.8 N2 l; 10 mile 1.9 N2 l-(
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' AREA' RADIATION LEVELS BY REGION-(MR/HR)
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. TIME REGION I REGION II REGION III REGION IV REGION V REGION VI (Cond. Pp) (Rx 135) (Rx-165)- (Rx 195) (F.F)' '(R/W 116) l 0800-0915 NORMAL NORMAL NORMAL. NORMAL NORMAL . NORMAL-0915-0930 50 NORMAL NORMAL NORMAL NORMAL 1
NORMAL 0930-1100 50 NORMAL NORMAL NORMAL . NORMAL NORMAL 1100-1400. 50 -20 20 20 NORMAL NORMAL 1400-1430 50 200 1000 5000 5000-125000 i NORMAL.
1430-1445 -50 200 1000. 5000 100000-125000 10 3 1445-1500 50 200 1000 5000 75000-100000 10
. 1500-1600 50 120 600 2000 5000-100000 4 10 1600-END 50 NORMAL 20 50 500 10 - -
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(in MR/HR)
A.R.M. (NUMBER AND LOCATION) . TRIP READING TRIP TIME 1.2 RX. BLDG. SUMP AREA 88' EL. 40 - - -
1.3 ToHUS COMPT. (BY B & D CORE SPRAY) 40 ---
1.4 HPCI PUMP RMM 88' EL. 6 ____
l 1.5 RCIC PUMP ROOM 88' EL. 5 .___
1.7 RHR PUMP ROOM 'A' 91.6' EL. 100 ..__
1.8 CORE SPRAY ROOM 'B' 91.6 EL. 5 ,___
1.9 COND. PUMP AREA (COND. PUMP. - 91.6' EL.) 5 0920 1.6 RHR PUMP ROOM 'D' 116' EL. 90 ._
1.10 RECIRC. PUMP INST. RACK AREA (TRIANGLE ROOM 116' EL. SOUTH) 5 ----
1.11 STEAM FLOW INST. RACK AREA (TRIANGLE ROOM 116' EL. NORTH) 5 --
1.12 COOLING WATER PUMP AREA (RBCCW ROOM 116' EL.) 5 - --
, 2.1 .COND. SERVICE PUMP AREA (T.B. ACROSS l FROM SAMPLE SINK 116' EL. 5 ----
l 2.3 COND. SERVICE PUMP AREA (T.B. 2 NEAR CRD FILTER 116' EL.) 60 - - -
2.4 H.P. TURBINE AREA (MOISTURE SEPARATOR 116' EL. SOUTH) 3000 ___
2.5 RX BLDG. PERSONNEL ACCESS l
-(SOUTH) (STAIRWELL 135' EL.) 5 ----
2.6 RX BLDG. EQUIP. RACK & TIP CONTROL
'(R.P. ACESS DOORS 135' EL.) 12 iioo 2.7 RX. BLDG. PERSONNEL ACCESS (NORTH) (DRYWELL C.P. 135' EL.) 5 ---
2.8 TIP WITHDRAWAL AREA (INSIDE TIP ROOM 135' EL.) 3000 _ . -
2.9 TURBINE BLDG. ACCESS (BOWLING ALLEY 135'. EL.) 5 . . . .
n (in MR/HR)
A.R.M. (NUMBER AND LOCATION) '
TRIP READING TRIP TIME 2.10 MOIST. SEP. AREA (MEZZANINE ROOM 135' EL.) 1500 ----
2.11 RX. BLDG. OP. AREA (SAMPLE SINK 165' EL.) 15 ---
2.12 RX. BLDG. ACCESS (STAIRWELL 165' EL.) 5 nt oo 3.1 HEATER & RFPT AREAS (SOUTH) 165' EL. 5 ----
3.2 HEATER & RFPT AREAS (NORTH 165' EL. 5 ----
3.4 H.P. TURBINE AREA (TURBINE DECK 165' EL.) 100 ----
3.6 RX. BLDG. EXHAUST FANS p., (FAN ROOM 195' EL.) 5 #10 0 t 1
) ' 5.2 SOURCE VAULT (195' EL.) RX. BLDG. 10 ----
3.7 STEAM SEPARATOR POOL AREA 234' EL. 30 pyo 3.8 RX. FUEL POOL AREA 234' EL. 15 1405 3.9 FUEL POOL AREA 234' EL 15 g405 3.10 REFUELING BRIDGE 234' EL. 15 1406 3.12 PIPE TUNNEL SUMP AREA (T.B. NEAR R.W. DOOR 91.16' EL.) 20 ----
4.6 RADWASTE SUMP AREA (SUMP PUMP 91.6' EL.) 60 ----
4.1 R-R ACCESS (T.B. ENTRANCE 116' EL.) 5 ----
4.7 RADWASTE FILTER PUMP AREA (LAUNDRY FOOM 116' EL.) 5 1430 4.8 RADWASTE SAMPLE R-R AREA (COND. PHASE SEP. ROOM 116' EL.) 60 ----
(D
\ 4.9 CONVEYOR OP. ACCESS AREA
!> (R.W. 135' EL.) 30 ----
(in MR/HR)
A.R.M._(NUMBER AND LOCATION) ,
TRIP READING TRIP TIME 4.10 DRl:M STORAGE AREA (R.W. 135' EL.) 60 ----
4.11 RADW/.STE FILTER HATCH AREA (R.W. 135' EL.) 80 ----
4.2 TURBINE BLDG. ACCESS AREAS '
(135' EL.) HATCH 5 ----
4.12 WASTE SAMPLE TANK AREA (R.W. 150' EL.) 10 ----
4.3 TURBINE BLDG. ACCESS AREAS (165' EL.) HATCH 5 ----
4.5 MAIN CONTROL ROOM 5 ----
[l u
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99 ed O
AREA RADIATION MONITORING SYSTEM DATA i
l l
ALL READINGS ARE IN MR/uR l
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9 ,
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TIME APao ,
A.R.M. (NUMBER AND LOCATION) READING 1.2 RX. BLDG. SUMP AREA 88' EL. j3 1.3 TORUS COMPT. ,,
(BY B & D CORE SPRAY) .
j3 1.4 HPCI PUMP ROOM 88' EL. ,, y 1.5 RCIC PUMP ROOM 88' EL. y 1.7 RHR PUMP ROOM ' A' 91.6' EL. 33 1.3 CORE SPRAY ROOM 'B' 91.6' EL. 3 1.9 COND. PUMP AREA (COND. PUMP PIT - 91.6' EL.) 7
. 1.6 RHR PUMP ROOM 'D' 116' EL. g 1.10 RECERC. PUMP INST. RACK AREA
- ? (TRIANGLE RCOM 116' EL. SCLOi) 2 1.11 STEAM FLOW INST. RACK AREA (TRIANGLE ROOM 116' EL. NORTH) 7 1.12 COOLING WATER PUMP AREA (R3CCW ROOM 116' EL.) 7
, 2.1 COND. SERVICE PUMP AREA (T.B. 2 ACPOSS FROM SAMPLE SINK 116' EL.)
2
, 2.3 COND. SERVICE PUMP AREA (T.B. 2 NEAR CRD FILTER 116' EL.) g 2.4 H.P. TUR3 INS AREA (MOISTURZ SEPARATOR 116' EL. SOUTH) jggg 2.5 RX BLDG. PERSONNEL ACCESS (SOUTH) (STAIRWELL 135' EL.) 7 2.6 RX BLDG. EQUIP. RACK & TIP CON-TROL (R.P. ACCESS DOORS 135' EL.)
4 TIME
()20D READING A.R.M. (NUMBER AND LOCATION) 2.7 RX. BLDG. PERSONNEL ACCESS
~
(NORTH) (DRYWELL C .P . 135 ' EL .) L 2.8 TIP WITHDRAWAL AREA (INSIDE TIP ROOM 135' EL.) jgg .
2.9 TURB. BLDC. ACCESS (BOWLING ALLEY 135' EL.)
2.10 MOIST. SEP. AREA (MEZZANINE ROOM 135' EL.)
g 2.11 RX. BLDG. OP. AREA (SAMPLE SINK 165' EL.) g 2,12 RX. BLDG. ACCESS (STAIRWELL 165' EL.) 7
[\ HEATER & RFPT AREAS 3.1
~Z
/ (SOUTH) 165' EL.
3.2 HEATER & RFPT AREAS
-(NORTH) 165' EL. 1 3.4 H.P. TURBINE AREA (TURBINE DECK 165' EL.) ]
I -
3.6 RX. BLDG. EXHAUST FANS (FAN ROOM 195' EL.) .
f / 5.2 SOURCE VAULT (195' EL.) RX. BLDG. }
' 3.7 -STEAM SEPARATOR POOL AREA
234' EL. ,
/g g
3.8 RX. REFUEL SLOT AREA 234' EL.
< 3.9 FUEL POOL AREA 234' EL. g e 3.10 REFUELING BRIDGE 234.' EL. g P .
G
. - - - _ . _, - _- --. , , . - . . , ,- . . . , . , _.mi e-... . - - -
TIME , .
N d k/k3
'w
/]
A.R.M. (NUMBER AND I.0 CATION) READING 3.12. PIPE TUNNEL SUMP AREA (T.B. NEAR R.W. DOOR 91.b' EL.)
4.6 RADWASTE SUMP AREA
~
(SUMP PUMP 91.6' EL.) -
~2 o 4 .1' R-R ACCESS (T.B . - ENTRANCE 116 ' EL. ) ;
E 4.7 RADWASTE FILTER PUMP AREA (LAUNDRY ROOM 116' EL.) 3 l 4.8 RADWASTE SAMPLE R-R AREA (COND. PHASE SEP ROOM 116' EL.) 7g
-4.9 CONVEYOR OP. ACCESS AREA l _
( R.W. 135' EL.) jg l 4.10 DRUM STORACE AREA (R.W. 135' EL.)
7 4.11 RADWASTE FILTER HATCH AREA l
(R.W. 135' EL.) 2. 5' 4.2- 'lIIRll! NK 131.DG. ACCESS AREAS
( l *J 5 ' EL. ) II ATCll 7-l 4.12 WASTE SAMPLE TANK AREA I -
(R.W. 150' EL.) _.
U' 4.5 MAIN CONTROL ROOM 05' l
l ..
-?
I
_. ,_ . _ . - _ . _ - ._, - - . , _ . - . _ _ . .. .-~ . . . _ - . - - - - - - -~ _ ~ _ . -
~
TIME OR2A READING A.R.M. (NUMBER AND LOCATION)_
1.2 RX. BLDG. SUMP AREA 88' EL. 73 1.3 TORUS COMPT. .,
(BY B & D CORE SPRAY) ,
j3 1.4 HPCI PUMP ROOM 88' EL. , , y 1.5 RCIC PUMP ROOM 88' EL. 7 .
1.7 RHR PUMP ROOM 'A' 91.6' EL. y3 1.8 CORE SPRAY ROOM 'B' 91.6' EL. 3 1.9 COND. PUMP AREA (COND. PUMP PIT - 91.6' EL.) 7
. l.6 RHR PUMP ROOM 'D' 116' EL.
1.10 RECIRC. PUMP INST. RACK AREA
/ (TRIANGLE ROOM 116' EL . S C'. M) 1.11 STEAM FLCW INST. RACK AREA (TRIANGLE ROOM 116' EL. NORTH) 7 1.12 COOLING WATER PUMP AREA (RBCCW ROOM 116' EL.) 7
- 2.1 COND. SERVICE PUMP AREA (T.B. 2 ACROSS FR0M SAMPLE SINK 116' CL.) L
, 2.3 COND. SERVICE PUMP AREA (T.B. 2 NEAR CRD FILTER 116' EL.) 7g f 2.4 H.P. TURBINE AREA (MOISTURE SEPARATOR 116' EL. SOUTH) /o0O ,
2.5 RX BLDG. PERSONNEL ACCESS (SOUTH) (STAIRWELL 135' EL.) 7 2.6 RX BLDG. EQUIP. RACK & TIP CON- .
TROL (R.P. ACCESS DOORS 135' EL.)
TIME Ofzd A.R.M. (NUMBER AND LOCATION) READING 2.7 RX. BLDG. PERSONNEL ACCESS (NORTH) (DRYWELL C.P. 135' EL.) 2, 2.8 TIP WITHDRAWAL AREA (INSIDE TIP ROOM 135' EL.) jgg 2.9 TURB. BLDG, ACCESS (BOWLING ALLEY 135' EL.) Z 2.10 MOIST. SEP. AREA (MEZZANINE ROOM 135' EL.)
g 2.11 RX. BLDG. OP. AREA (SAMPLE SINK 165' EL.) g 2.12 RX. BLDG. ACCESS -
(STAIRWELL 165' EL.) 7 3.1 HEATER &.RFPT AREAS
, (SOUTH) 165' EL. 1 3.2 HEATER & RFPT AREAS
.(NORTH) 165' EL. g l
l 3.4 H.P. TURBINE AREA (TURBINE DECK 165' EL.) 3 3.6 RX. BLDC. EXHAUST FANS (FAN ROOM 195' EL.) 7,
/ 5.2 SOURCE VAULT (195' EL.) RX. BLDG. ]
3.7 STEAM SEPARATOR POOL AREA "
234' EL. ,
/g 3.8 RX. REFUEL SLOT AREA 234' EL. g
' 3.9 FUEL POOL AREA 234' EL. g 3.10 REFUELING BRIDGE 234' EL.. g o
)'uJ l
I
~
l TIME .
1 O TT& _ '
. - l A.R.M. (NUMBER AND !.OCATION) READING 3.12 PIPE TUNNEL SUMP AREA (T.B. NEAR R.W. DOOR 91.6' EL.)
4.6 RADWASTE SUMP AREA (SUMP PUMP 91.6' EL.)
4.l' R-R ACCESS (T.B. ENTRANCE 116' EL.) ;
g _
4.7 RADWASTE FILTER PUMP AREA (LAUNDRY R00M. ll6 ' EL.) g 4.8 RADWASTE SAMPLE R-R AREA (COND. PHASE SEP. ROOM 116' EL.) 7g 4.9 CONVEYOR OP. ACCESS AREA
( R.W. 135' EL.) /0 4.10 DRUM STORAGE AREA (R.W. 135' EL.) g 4.11 RADWASTE FILTER HATCH AREA (R.W. 135' EL.) 2. 5 4.2 TilRilI NE Bl.DG. ACCESS AHEAS (135' EL.) IIATCli
! 4.12 WASTE SAMPLE TANK AREA (R.W. 150' EL.) _
]
1 6 EL HkTCH 7
4.5 MAIN CONTROL ROOM 05' 1
I "- 's 1
1 (~)'\
c.-. ,, -. , - , - - . -
..----,.,.n,-- --,---.---r <--, - . - --
y . _ - _ .
TIME O P40 A.R.M. (NUMBER AND LOCATION) READING 1.2 RX. BLDG. SUMP AREA 88' EL. f3 1.3 TORUS COMPT. ,,
(BY B & D CORE SPRAY) ,
73 1.4 HPCI PUMP ROOM 88' EL. ,, y 1.5 RCIC PUMP ROOM 88' EL. y 1.7 RER PUMP ROOM 'A' 91.6' EL. 33 1.8 CORE SPRAY ROOM 'B' 91.6' EL. 7 1.9 COND. PUMP AREA (COND. PUMP PIT - 91. 6' EL.) 7
. 1.6 RHR PUMP ROOM 'D' 116' EL. g l 1.10 RECIRC. PUMP INST. RACK AREA
~~-
(TRIANGLE ROOM 116' EL. SCU3) 1.11 STEAM FLOW INST. RACK AREA (TRIANGLE ROOM 116' EL. NORTH) 7 1.12 COOLING WATER PUMP AREA (RBCCW ROOM 116' EL.) 7
, 2.1 COND. SERVICE PUMP AREA (T.B. 2 ACROSS FROM SAMPLE SINK 116' EL.) L
, 2.3 COND. SERVICE PUMP AREA (T.B. 2 NEAR CRD FILTER 116' EL.) g
,- 2.4 H.P. TURBINE AREA (MOISTURE SEPARATOR 116' EL. SOUTH) / g g cy 2.5 RX BLDC. PERSONNEL ACCESS (SOUTH) (STAIRWELL 135' EL.) l 7
2.6 RX BLDG. EQUIP. RACK & TIP CON- '
TROL (R.P. ACCESS DOORS 135' EL.)
l .
(~ ~N, TIME
.O$Y0 A.R.M. (NUMBER AND LOCATION) READING 2.7 RX. BLDG. PERSONNEL ACCESS (NORTH) (DRYWELL C.P. 135' EL.) L 2.8 TIP WITHDRAWAL AREA (INSIDE TIP ROOM 135' EL.) j g 2.9 TURB. BLDG. ACCESS (BOWLING ALLEY 135' EL.)
2.10 MOIST. SEP. AREA (MEZZANINE ROOM 135' EL.)
g 2.11 RX. BLDG. OP. AREA (SAMPLE SINK 165' EL.) g j 2.12 RX. BLDG. ACCESS l m (STAIRWELL 165' EL.) 7 3.1 HEATER & RFPT AREAS (SOUTH) 165' EL. 1 3.2 HEATER & RFPT AREAS (NORTH) 165' EL. g 3.4 H.P. TURBINE AREA
.(TURBINE DECK 165' EL.) ]
3.6 RX. BLDG. EXHAUST FANS (FAN ROOM 195' EL.) 3
{ / 5.2 SOURCE VAULT (195' EL.) RX. BLDG. 3
.' 37 STEAM SEPARATOR POOL AREA ..
234' EL. ,
jg 3.8 RX. REFUEL SLOT AREA 234' EL. g
< 3.9 FUEL POOL AREA 234' EL. g
< 3.10- REFUELING BRIDGE 234' EL. D l
l
TIME .
DSk0 .
A.R.M. (NUMBER AND 1.OCATION) READINO 3.12 PIPE TUNNEL SUMP AREA (T.B. NEAR R.W. DOOR 91.b' EL.)-
4.6 HADWASTE SUMP AREA (SUMP PUMP 9t'.6' EL.)
- 20. -
4.1' R-R ACCESS (T.B. ENTRANCE 116' Lt.) ;
4.7 RADWASTE FILTER PUMP AREA (LAUNDRY ROOM .116 ' EL.) 3 4.8 RADWASTE SAMPLE R-R AREA (COND. PHASE SEP. ROOM 116' EL.) 7g 4.9 CONVEYOR OP. ACCESS AREA
( R.W. 135' EL.) /g 4.10 DRUM STORACE AHEA (h.W. 135' EL.) g 4.11 RADWASTE FILTER HATCH AREA
!- - (R.W. 135' EL.) 2. 5' 4.2 TilHillNK lli.lX;. ACCESS AHEAS
( l'J 3 ' EL . ) 11 ATCll
! 7L.
l 4.12 WASTE SAMPLE TANK AREA l (R.W. 150' EL.) ]
4.3 TURBINE BLDC. ACCESS AREAS (165' EL.) HATCH 7 4.5 MAIN CONTROL ROOM 05' l
l i
l -
l e E' . . ,
i -
.= . . - _ . . . . . _ . . _ - _ . . _ . _ - . . - - . . . . - . _ . _ . , . . _ . - . , . . . _ , . _ _ _ . . -
TIME f(TO .
A.R.M. (NUMBER AND LOCATION) READING 1.2 RX. BLDG. SUMP AREA 88' EL. j3 1.3 TORUS COMPT. ,,
(BY B & D CORE SPRAY) ,
j3 1.4 HPCI PUMP ROOM 88' EL. ,
, 7 1.5 RCIC PUMP ROOM 88' EL. 2 .
1.7 RHR PUMP ROOM 'A' 91.6' EL. 33 1.8 CORE S PRAY ROOM 'B ' 91. 6 ' EL. 7 1.9 COND. PUMP AREA
( (COND. PUMP PIT - 91.6' EL.) 7 l
. 1.6 RHR PUMP ROOM 'O' 116' EL. g 1.10 RECIRC. PUMP INST. RACK AREA I
(TRIANGLE ROOM 116' EL. SCL~ni) 2 l
l 1.11 STEAM FLCW INST. RACK AREA l (TRIANGLE ROOM 116' EL. NORTH) 1.12 COOLING WATER PUMP AREA (R3CCW ROOM 116' EL.) 7
, 2.1 COND. SERVICE PUMP AREA (T.B. 2 ACROSS I FROM SAMPLE SINK 116' EL.) 2.,
, 2.3 COND. SERVICE PUMP AREA (T.B. 2 NEAR CRD FILTER 116' EL.) 7g f 2.4 H.P. TURBINE AREA (MOISTURE SEPARATOR 116' EL. SOUTH) jgy 2.5 RX BLDG. PERSONNEL ACCESS l (SOUTH) (STAIRWELL 135' EL.) l 7
2.6 RX BLDG. EQUIP. RACK & TIP CON- ~ tf
/
TROL (R.P. ACCESS DOORS 135' EL.)
l
)
l l .. . ..
-.u.-
-. a. - ,
O TIME ~
09/M ,
A.R.M. (NUMBER AND LOCATION) READING 2.7 RX. BLDG. PERSONNEL ACCESS (NORTH) - (DRYWELL C.P . 135 ' EL.) L 2.8 TIP WITHDRAWAL = AREA (INSIDE TIP ROOM 135' EL.) j gg 2.9 TURB. BLDG. ACCESS (BOWLING ALLEY 135' EL.) 7 2.10 MOIST. SEP. AREA (MEZZANINE ROOM 135' EL.)
g 2.11 RX. BLDG. OP. AREA (SAMPLE SINK 165' EL.) g 2.12 RX. BLDG ACCESS
. (STAIRWELL 165' EL.) 7 3.1 HEATER & RFPT AREAS 7 (SOUTH) 165' EL. "2,.
3.2 HEATER & RFPT AREAS (NORTH) 165' EL. g 3.4 H.P. TURBINE AREA '
(TURBINE DECK 165' EL.) ]
f 3.6 RX. BLDG. EXHAUST FANS l (FAN ROOM 195' EL.) ,
l / 5.2 SOURCE VAULT (195' EL.) RX. BLDG. } ~
- /
.' 3.7 STEAM SEPARATOR POOL AREA ~~_
- " ~
234' EL. , /g ,
3.8 RX. REFUEL SLOT AREA 234' EL. g ,
e' 3.9 FUEL POOL AREA 234' EL. g _
r 3.10 REFUELING BRIDGE 234' EL.
.O -
- . - ,, ..n,
.-m, , , .-,--,,,--,.-e., -, - - ,, - -- ,. -- -. - , ~~ , . . . . - ,- - - , .,.,
, --,- r , . - - - - ., , - , - _ r-.
-3 _
TIME .
g nsaa .
A.R.M. (NUMBER AND I.0 CATION) READING 3.12 PIPE TUNNEL. SUMP AREA (T.B. NEAR R.W. DOOR 91.6' EL.)
4.6 RADWASTE SUMP AREA (SUMP PUMP 91.6' EL.) -
4.1 R-R ACCESS (T.B. ENTRANCE 116' EL.) ;
7 ._
4.7 RADWASTE FILTER PUMP AREA (l.AUNI)RY ROOM .116 ' EL.) g 4.8 RADWASTE SAMPLE R-R AREA (COND. PHASE SEP. ROOM 116' EL.) 7g 4.9 CONVEYOR OP. ACCESS AREA
- ( R.W. 135' EL.) /g 4.10 DRUM STORACE AREA (R.W. 135' EL.)
- 2. 0
-4.11 RADWASTE FILTER HATCH AREA (R.W. 135' El..). 2. 5'
!~ 4.2 TilHBINE Ul.1)G. ACCESS AHEAS
' (135' EL.) IIATCil
~2.-
4.12 WASTE SAMPLE TANK AREA (R.W. 150' EL.) }
! 16 EL HATCH
_ 7 4.5 ' MAIN CONTROL ROOM ' ,,
C . of
, . p '
s<- --
j .
- r'
-r. -
l s r' ,
Y , ,p . =
- s. . y ,. -
e'. . . %
,..,,. . et t *
%E- %
l
~
3 * ,,
t'
! +9e*
\,, ,___'^l.dk---,_... - - - . , , - , + . , --.-.- -..,- ,+ !.~ 1 -~- ,<-- - - - - - , - - - - - - - ~ ~ ~ = - - - * - - - - - ~ - ~ - - - - ' - - - -'
l 1
I p 1 A.j '
TIME 21 O #i 2.,0. l l
A.R.M. (NUMBER AND LOCATION) READING 1.2 RX. BLDG. SUMP AREA 88' EL. j3 1.3 TORUS COMPT. .,
(BY B'& D CORE SPRAY) j3 1
1.4 HPCI PUMP ROOM 88' EL. -e 2 .
'l.5 RCIC PUMP RCCM 88' EL. 2- 1
- I l.7 RHR FIRIP ROOM ' A' 91.6' EL. 35 _
l.8 CORE S? RAY ROOM 'ad 91.6' EL. ;
1.9 CCND. PUMP AREA (COND. PD'P FIT 'Al. 6' E!. .) g _.
g
- 1,6 RHR PDfP F00M D' 116' EL.
g U 1.10 RECIRC. EU}C' INST. RACK AREA i J (TRIANGLE'ROCM 1*6' EL. 3CUTH) 7 1.11 STEAM FLOW INST. RACK V.EA
~(TRIANGLE RCGM .116' EL. NORTH) g 1.12 COOLING WATER PCMP AREA (RBCCW ROOM 116' EL.) g I- , 2.1 COND. SERVICE PUMP AREA (T.B. 2 ACROSS
( FROM SAMPLE SINK 116' EL.) {
j , 2.3 COND. SERVICE PUMP AREA (T.B. 2 NEAR CRD FILTER 116' EL.)
, 2.4 H.P. TURBINE AREA (MOISTURE l SEPARATOR 116' EL. SOUTH) /odO l 2.5 RX BLDG. PERSONNEL ACCESS (SOUTH) (STAIRWELL 135' EL.) ;
7 2.6 RX BLDG. EQUIP. RACK & TIP CON-TROL (R.P. ACCESS DOORS 135' EL.)
h 3
a
,r TIME 092-0 A.R.M. (NUMBER AND LOCATION) READING
-2.7 RX. BLDC. PERSONNEL ACCESS-(NORTH)-' (DRYWELL C.P. 135 ' EL.) g ,
2.8 TIP WITHDRAWAL AREA )
(INSIDE TIP ROOM 135' EL.) /ddA 2.9 TURB. BLDC. ACCESS (BOWLING ALLEY 135' EL.) 7 2.10 MOIST. SEP. AREA (ME2ZANINE ROOM 135' EL.)
gg j 2.11 RX. BLDG. OP. AREA (SAM?LE SINX 165' EL.) g-2.12 RX BLDG. ACCESS (STAIRWELL 165' EL.) 7 d 3.1 ilEATER & RFPT AREAS l
(F _
(SOUTH) 165' EL. ~L,
, . '3.2 HEATER & RFFT AREAS
'(NORTH) 165' EL.
( 3.4 H.P. TURBINE AREA f' (TUR3INE DECK 165' EL.) 33 3.6 RX. BLDG. EXHAUST FANS l- (FAN ROOM 195' EL.)
1 1
/ 5.2 SOURCE VAULT (195' EL.) RX. BLDG. }
i- .' 3.7 STEAM SEPARATOR POOL AREA "
234' EL. , jg ,
j < 3.8 RX. REFUEL SLOT AREA 234' EL. g j
e' 3.9 ' FUEL POOL AREA 234' EL. f
< 3.10- REFUELING BRIDGE 234.' EL. g
u _,
~ -
TIME ,
\- ' 092.0.
A.R.M. (NUMBER AND I.OCATION) -
READING 3.12 PIPE TUNNEL SUMP AREA (T.B. NEAR R.W. DOOR 91.o' EL.) g 4.6 RADWASTF. SUMP AREA *
(SUMP PUMI' _91.6' EL.)
4.1 k-R e.CCESS (T.B . ENTRAliCE 116' EL.) ;
4.7 PADWASTE FILTER PUMP AREA (LAUtiDRY E00}! 116' EL.) ~2, ;
4,8 RAD'4ASTE SAMPLF' R-R AREA (CLN9. PHASE SEP. R00:4 116' EL.) gg L.9 CONVEYOR CP. ACCESS AREA
, ( II . W . 135 ' EL . )
fg 4.10 DRLM STORAGE i.REA (it.W.135' EL.) 20
', 4.Il RADWASTE FILTER HATCH AREA (R.W. 13$' EI..) ~J, 7 4.2 Tim's i NH !;l.DG. At: CESS AREAS C 1'D ' I;L . ) "! ATCl!
2 i
- c.12 WAMS 5.'.hPLE TANK AREA (n.W . - 150 ' EL . )
3
~ 4.5 MAIN CONTROL ROOM
, of 4
w w -- - ,--e-- - ~ - - , , , - , .- --. e n .--,
TIME OCf 30 -IlOD A.R.M. (NUMBER AND LOCATION) READING 1.2 RX. BLDC. SUMP AREA 88' EL. f3 1.3 TORUS COMPT. ..
(BY B & D CORE SPRAY) j3 1.4 HPCI PUMP ROOM 88' EL. ,
, y _
l.5 RCIC PUMP ROOM 88' EL. 7 .
1.7 PJiR PUMP 300M 'A' 91.6' EL. y3 1.8 CCRE SPRAY ROOM 'B' 91.6' EL. 3 1.9 COND. PUMP AREA (COND PUMP PIT - 91.6' EL.) g()
. 1.6 RHR PUMP ROOM 'D' 116' EL. g l.10 7.ECIRC. PUMP INST RACK AREA gTRI ANGLE RCOM 116 ' 32., SC'.*Df)
-_ ._2 1.11 STEAM FLCV IN3T. RACK AREA (TRTANG:.E ROOM 116' IL. NORTE) 7 1.12 CCOLI 'G VATEP PUMP AP.EA l (R3CCW .100M 116' EL.) 7
, 2.1 COND. SERVICE PUMP AREA (T.3. 2 ACROSS FROM SAMPLE SINK 116' EL.) 2, I w -
, 2.3 COND. SERVICE PUMP AREA (T.B. 2 NEAR CRD FILTER 116' EL.) g
'- 2.4 H.P. TURBINE AREA (MOISTURE SEPARATOR 116' EL. SOUTH) 2 l 2.5 RX BLDG. PERSONNEL ACCESS l (SOUTH) (STAIRWELL 135' EL.) <
7 2.6 RX BLDG. EQUIP. RACK & TIP CON-TROL (R.P. ACCESS DOORS 135' EL.)
Y -- ~ - :- =- -. _ - - . . _
TIME 01,%) - // ro A.R.M. (NUMBER AND LOCATION) READING 2.7 RX. BLDC. PERSONNEL ACCESS
~'
(NORTH) (DRYWELL C.P. 135 ' EL.) L 2.8 TIP WITHDRAWAL AREA (INSIDE TIP ROOM 135' EL.) j, 2.9 TURB. BLDG, ACCESS (BOWLING ALLEY 135' EL.)
2.10 M3!ST. SEP. AREA (MEZZUiINE Ro0M 135' EL.) 2 l 2.11 RX. BLEG. OP. AREA (SMG'LE SINK 165' EL.) g 2.12 RX. BLDC. ACCESS
-(STAIRWELL 165' EL.) 'l 7
' q) 3.1 HEATER & RFPT AREAS (SOUTH) 165' EL.
L a . .? LFATER & RF?T A.1EAS f (NCRIE) 165' LL. l 7 3.6 H.P. TURBINE AREA (TURBINE DECK 165' EL.) 3 3.6 RX. BLDG. EXHAUST FANS (FAN ROOM 195' EL.) ,
/ 5.2 SOURCE VAULT (195' EL.) RX. BLDG. ]
.' 3.7 STEAM SEPARATOR POOL AREA
234' EL. ,
/g 3.8 RX. REFUEL SLOT AREA 234' EL. f
' 3.9 FUEL POOL AREA 234' EL. g
< 3.10 REFUELING BRIDGE 234' EL. g n]
~
TIME t b1.$G-l/tJo_
V E
A.R.M. (NUMBER AND !.0 CATION) READING 3.12 PIPE TUNNEL SUMP AREA -
(T.B. NEAR R.W. DOOR 91.6' EL.)
4.6 'RADWASTE SUMP AREA (SUMP PUMP 91.6' EL.)
4.1 R-R ACCESS (T.B. ENTRANCE 116' EL.) ;
7 _
'4.7 RADWASTE FILTER FUMP AREA (LAUNf1RY ROOM-116' EL.) 3 4.8 RADWASTE SAMPLE R-R AREA (COND. ?HASE SEP. RGOM 116' EL.) 7g 4.9 CONVEYOP OP. ACCESS AREA
( R.W. 135' Ei.) _
jg 4.10 GPUM STORAGE AREA (R.W. 135' EL.) g r .-
' 4.11 RADWASTE P!LTER HATCH AREA
, (R.W. 133' El..)
'2 [
- l. 2 'l ';h!! ! NF !)l.i'G . ACCESci A1FNs ,
(135 ' HL. ) JATCli 4.12 WAbTE SAMPLE TANK AREA (R.V. 150' EL.) } -
4.5 MAIN CONTROL ROOM 05^
l i
l l
F
I TIME
// 00 -/Vod A.R.M. (NUMBER AND LOCATION) READING 1.2 RX. BLDG. SUMP AREA 88' EL. /3 1.3 TORUS COMPT. .,
(BY.B & D CORE SPRAY) .
/3 1.4 HPCI PUMP ROOM 88' EL. ,
, g 1.5 RCIC PUMP ROOM 88' EL'. g 1.7 RHR PUMP POOM 'A' 91.6' EL. 33 ._
1.8 CORE SFRAY ROOM 'B' 91.6' EL. g l.9 CCND. PUMP AREA (COND. PUMP PIT - 91.6' EL.) -
. 1.6 RhR PUMP ROOM 'D.ll6' EL. yg
!4 1.10 RECIRC. PUN. NST. RACK AREA f (TRIANGLE ROOM 116 ' E*.. SCL"!H) 7 1.11 STEAM FLOW INST. RAC: AREA
-(TRIANCLE ROCM 116' EL. . NORTH) 1.12 COOLING WATER PLMP LV.A (RBCCW ROOM 116' EL.) .g
- 2. l' COND. SERVICE PUMP AREA (T.B. 2 ACROSS FROM SAMPLE SINK 116' EL.) 1
, 2.3 COND. SERVICE PUMP AREA (T.B. 2 NEAR CRD FILTER 116' EL.) y
,- 2.4 H.P. TUR3INE AREA (MOISTURE SEPARATOR 116' EL. SOUTH) 2 .
2.5 RX BLDG. PERSONNEL ACCESS (SOUTH) (STAIRWELL 135' EL.) ,
1 2.6 RX BLDG. EQUIP. RACK & TIP CON- 7g TROL (R.P. ACCESS DOORS 135' EL.)
.)O
p.
!. TIME-lI O D -]L/0 0
~
.~ A . R . M . (NUMBER AND LOCATION) READING 2.7 RX. BLDG. PERSONNEL ACCESS (NORTH) - (DRYWELL C.P.135' EL.) 2,.
2.8 TIP WITHDRAWAL AREA (INSIDE TIP ROOM 135' EL.) gg i 2.9 TURB. BLDC. ACCESS (BOWLING ALLEY 135' EL.) 2.
2.10 MOIST. SEP. AREA l (MEZZANINE 200M 135' EL.)
g 2,11 RX. BLDG, OP. AREA (SAMPLE SINK 165' EL.) [
2.12 RX. BLDG. ACCESS
- - (STAIR'n' ELL 165' EL.) gg
)
3.1 HZATER & RFPT AREAS (f 0UTH) '165' EL. _ _
~2._
3.2 riEATER & RFPT AREAS
'(NORTH) 165' EL. 2 3.4 H.P. TURBINE AREA (TURBINE DECK 165' EL.) g 3.6 RX. BLDG. EXHAUST FANS (FAN ROOM 195' EL.) 2g
/ 5.2 SOURCE VAULT (195' EL.) RX. BLDG. !
]
.- 3.7 STEAM SEPARATOR POOL AREA "
234' EL. , /g
+
3.8 KX. REFUEL SLOT AREA 234' EL. f
< 3.9 FUEL POOL AREA 234' EL. f e 3.10- REFUELING BRIDGE 234.' EL.. [
)O
- , --~, e e- m - - - - - - ,-- ,---w--- , --g- m- --w- - -r-,w,---,,w- -- , . -w ~,--w-w-m - , - - ,e--
TIME ,
A D // Gd-/5/OO
~
A.R.M. (NUMBER AND I.0 CATION) READING 3.12 PIPE TUNNEL SUMP AREA (T.B. NEAR R.W. DOOR 91.6' EL.)
4.6 RADWASTE SUMP AREA (SUMP PUMI' 91.6' EL.)
- 4.1 R-R ACCESS (T.B. ENTRANCE 116' EL.) ;
7 4.7 ilADWASTE FILTER PUMP AREA (l.AUNisRY ROOM 116' EL.)
4.8 RADWASTE SAMPLE R-R AREA !
(CONC. PHASE SEP. ROOM 116' EL.) g 4.9 CONVEY 0h OP. ACCESS AREA
( R.W. 135' El..) /g 4.10 DRUM STORAGE ARTA (R.W. 135' EL.)
4.11 RADWASTE FILTER HATCH AREA (R.W. 135' El..) ~g, (
4.2 Ti.H81NE Bl.in;. ACCESS AHSAS
( l '35 ' El. . ) II ATCll ,
4.12 WASTE SAMPLE TANK AREA (R.W. 150' EL.) --
3
'3 gpidiT ^ccess ^ae^$ z 4.5 PAIN CONTROL ROOM
.DC O
O V TIME
/Vos~
READING A.R.M. (NUMBER AND LOCATION) 1.2 RX. BLDG. SUMP AREA 88' EL. j}
1.3 TORUS COMPT. .,
(BY B &' D CORE SPRAY) j3 1.4 HPCI PUMP ROOM 88' EL. , , 7 1.5 RCIC PUMP ROOM 88' EL.' g 1.7 RHR PUM? ROOM 'A' 91.6' EL. 33 1.8 CORE SPRAY ROOM 'B' 91.6' EL. 2 1.9 COND. PUMP AREA
-(COND. PUMP PIT - 91.6' EL.) 50 1.6 RHR PUMP ROOM 'D' 116' EL. g
' 1.10 RECIRC. PUMP INST. RACK AREA (TR ~ ANGLE ROOM 116' E2.. SCC"?f) g 4
1.11 STEAM FLOW INST. P.ACK AREA
-(TRIANCLE ROGM 116' EL. NORTH) 1.12 COOLING VATLR PUMP AREA (RBCCW ROOM 116' EL.) g
- 2.1 COND. SERVICE PUMP AREA (T.B. 2 ACROSS FROM SAMPLE SINK 116' EL.) 1
, 2.3 COND. SERVICE PUMP AREA (T.B. 2 NEAR CRD FILTER 116' EL.) g f 2.4 H.P. TURBINE AREA (MOISTURE SEPARATOR 116' EL. SOUTH) 2 2.5 RX BLDG. PERSONNEL ACCESS (SOUTH) (STAIRWELL 135' EL.)
s g
2.6 RX BLDG. EQUIP. RACK & TIP CON- 2O TROL (R.P. ACCESS DOORS 135' EL.)
O 1
- -~
( >
' TIME
/MI) S A.R.M. (NUMBER AND LOCATION) READING 2.7 RX. BLDG. PERSONNEL ACCESS (NORTH) (DRYFFLL C.P. 135' EL.) 7 2.8 TIP WITHDRAWAL AREA (INSIDE TIP ROOM 135' EL.) ggg 2.9 TURB. BLDG. ACCESS (BOWLING ALLEY 135' EL.) 7 2.10 MOIST. SEP. AREA (MEEZANINE ROOM 135' EL.) g 2.11 RX. BLDG, OP. AREA (SAMPLE SIFK 165' EL.) f 2.12 RX. BLDG, ACCESS (STAIRWELL 165' EL.) g O
CJ 3.1 HEATER & RFPI AREAS (SOUTH) 165' EL. 7 3.2 HEATER & RFPT AREAS (NORTH) 165' EL. 3 3.4 H.P. TURBINE AREA (TURBINE DECK 165' EL.) {
! 3.6 RX. BLDG. EXHAUST FANS j (FAN ROOM 195' EL.) zo
/ 5.2 SOURCE VAULT (195' EL.) RX. BLDG. 3 234' EL.
/[
f
< 3.8 RX. REFUEL SLOT AREA 234' EL. ]3 3.9 FUEL POOL AREA 234' EL. f[
< 3.10 - REFUELING BRIDGE 234' EL. {
l y,9 1
=-
TIME .
O / Vosi .
A.R.M. (NUMBER AND 1.0 CATION) . .
READING 3.12 PIPE TUNNEL. SUMP AREA (T .B . NEAR R.W. DOOR 91.6' EL.) f lo 4.6 RADWASTE SUMP AREA (SUMP PUMP 91.6' EL.)
- 4. l' R-R ACCESS (T.B. ENTRANCE 116' EL.) ;
7 4.7 RADWASTE FILTER PUMP AREA (LAUNDRY ROOM 116' EL.) 2 -
4.8 RADWASTE SAMPLE R-R AREA I
(COND. PHASE SEP. ROOM 116' EL.) y 4.9 CONVEYOR OP. ACCESS AREA
( R.W. 135' EL.) /O 4.10 DRUM STORACE AREA (R.W. 135' EL.) 7g I 4.11 RADWASTE FILTER HATCH AREA (R.W. 135' El..) ~2. 5~
~
. 4.2 TilRillNi.131.DG. ACCESS AREAS (135' El..) IIATCl! 1 l' 4.12 WASTE SAMPLC TANK AREA (R.W. 150' EL.) 3 4.3 TURBINE BLDG. ACCESS AREAS (165' EL.) HATCH 2 4.5 MAIN CONTROL ROOM
. o 5' l
l l
l l
lO
-.,- - - - , . . - - . . . , - - , - - - - . , , . - - - . . . - - , - - - - - ~ . . , , - - - , . .- ---- e,, - . . . ,
m - - - -
rm TIME r/t o A . R . M .' (NUMBER AND LCCATION) _ READING 1.2 RX.. BLDG. SUMP AREA 88' EL. f]
1.3 -TORUS COMPT. ,,
(BY B & 'D CORE SPRAY) j3 _
l.4 HPCI PUMP ROOM 88' EL. , , 7 1.5 RCIC PUMP ROOM 88' EL. 3
'l.7' RHR PUMP ROOM 'A' 91.6' EL. y 1.8 CORE SPRAY ROOM 'B' 91.6' EL. g 1.9 COND. PUMP AREA (COND. PUMP PIT - 91.6' EL.)
. 1.6 RHR PUMP ROOM 'D' 116' EL. g 1.10 RECIRC. PUMP INST. RACK AREA l )C
, (TRIANGLE ROOM 116' EL. SCUTH) 7 f 1.11 STEAM FLOW INST. RACK AREA f (TRIANGLE ROOM 116' EL. NORTH) 7 1.12 COOLING WATER PUMP AREA (RBCCW ROOM 116' EL.) 7
, 2.1 COND. SERVICE PUMP AREA (T.B. 2 ACROSS FROM SAMPLE SINK 116' EL.)
. g
, 2.3 C0' ' . SERVICE PUMP AREA (7 . 2 NEAR CRD FILTER 116' EL.)
,- 2.4 H.?. TURBINE AREA (MOISTURE SErABATOR 116' EL. SOUTH) 1 .
2.5 RX BLDG. PERSONNEL ACCESS (SOUTH) (STAIRWELL 135' EL.) g 2.6 RX SLDG. EQUIP. RACK & TIP CON- 7g TROL (R.P. ACCESS DOORS 135' EL.)
O l'
l l
i l
L
, =-
n i
~
TIME
/ Y/b A.R.M. (NUMBER AND LOCATION) READING 2.7 RX. BLDG. PERSONNEL ACCESS (NORTH) - (DRYWELL C.P.135' EL.)
2 2.8 TIP WITHDRAWAL AREA (INSIDE TIP ROOM 135' EL.) / 0 2.9 TURB. BLDC. ACCESS (BOWLING ALLEY 135' EL.) 7 2.10 MOIST. SEP. AREA (MEZZANINE ROOM 135' EL.) 7 2.11 RX. BLDG, OP. AREA (SAMPLE SINK 165' EL.) f 2.12 RX. BLDG, ACCESS (STAIRWELL 165' EL.) 7, o
(_)s 3.1 HEATER & RFPT AREAS (SOUTH) 165' EL. 2 3.2 HEATER & RFPT AREAS (NORTH) 165' EL. 2 I 3.4 H.P. TUR3INE AREA '
(TURBINE DECK 165' EL.) f 3.6 RX. BLDG. EXHAUST FANS (FAN ROOM 195' EL.) 2_c
/ 5.2 SOURCE VAULT (195' EL.) RX. BLDG, ]
' 3.7 STEAM SEPARATOR POOL AREA "
234' EL. [(fly 6 RX. REFUEL SLOT AREA 234' EL. OAF 5 CALC 3.8
/ 3.9 FUEL POOL AREA 234' EL. oFFSCALE
! < 3.10 REFUELING BRIDGE 234' EL. o F r s c ALE.
l
y ,
e TIME , .
/Y/O . i A '. R . M . (NUMBER' AND bOCATION) -
READING 3.12 PIPE TUNNEL SUMP AREA
'(T.B. NEAR R.W. DOOR 91.6,' EL.)
4.6 RADWASTE SUMP AREA (SUMP PUMP 91.6' EL.)
-. 4 .1- R-R ACCESS (T.B. ENTRANCE 116' EL.) ;
4.7 RADWASTE FILTER PUMP AREA l (LAUNDRY ROOM 116' EL.)
L 4.8 RADWASTE SAMPLC R-R AREA
, (COND. PHASE SEP. ROOM 116' EL.) 10 i
4.9 ' CONVEYOR OP. ACCESS AREA
( R.W. 135' EL.) /g 4.10 -DRUM STORACE AREA (R.W. 135' EL.)
4.11 RADWASTE FILTER HATCH AREA (R.W. 135' EL.) 2. 6, 4.2 TI!RillNK lil.U(;. ACCESS AREAS (l 'J 5 ' EL . ) II ATCll 4.12 WASTE SAMPLE TANK AREA.
(R.W. 150' EL.) -- ]
5 EL HkTCH g 4.5 MAIN CONTROL ROOM-
. 05, l
1
n TIME I430 A.R.M. (NUMBER AND LOCATION) READING
- 1. 2_ RX. BLDG, SUMP AREA 88' EL. g 1.3 TORUS COMPT. .,
(BY B &'D CORE SPRAY) ,
g 1.4 HPCI PUMP ROOM 88' EL. , , g __
l.5 RCIC PUMP ROOM 88' EL.' 7 1.7 RHR PUMP ROOM 'A' 91.6' EL. JJ 1.8 . CORE SPRAY ROOM 'B' 91.6' EL. 2, 1.9 COND. PUMP AREA (COND. PUMP PIT - 91.6' EL.)
. 1.6 RHR PUMP ROOM 'D' 116' EL. g
~ l.10 RECIRC. PUMP INST. RACK AREA
/ (TRIANGLE ROOM 116' EL. SCUTH) 1.11 STEAM FLOW INST. RACK AREA (TRIANGLE ROOM 116' EL. NORTH) 1.12 COOLING WATER PUMP AREA (R3CCW ROOM 116' EL.) 1
- 2.1 COND. SERVICE PUMP AREA (T.B. 2 ACROSS FROM SAMPLE SINK 116' EL.) 2,
, 2.3 COND. SERVICE PUMP AREA (T.B. 2 NEAR CRD FILTER 116' EL.) g
,- 2.4 H.P. TURBINE AREA (MOISTURE SEPARATOR 116' EL. SOUTH) '2.-
2.5 RX BLDC. PERSONNEL ACCESS (SOUTH) (STAIRWELL 135' EL.) g 2.6 RX BLDG, EQUIP. RACK & TIP CON- g TROL (R.P. ACCESS DOORS 135' EL.)
ba
\
~,
t .,
O TIME
/Y30.
'A.R.M. (NUMBER AND LOCATION' READING 2.7 RX. BLDG. PERSONNEL ACCE.,S (NORTH)-(DRYWELL C.P. 135' EL.) 1 2.8 TIP WITHDRAWAL AREA (INSIDE TIP P.00M 135' EL.) j 2.9 TURB. BLDG. ACCESS (BOWLING ALLEY 135' EL.) g 2.10 MOIST. SEP. AREA (MEZZANINE ROOM 135' EL.)
7 2.11 RX. BLDC. OP. AREA "
(SAMPLE SINK 165' EL.) {
2.12 RX. BLDG, ACCESS -
(STAIRWELL 165' EL.)
i g 3.1 dEATER & RFPT AREAS lp (SOUTd) 165' EL. 2 3.2 HEATER & RFPT AREAS l (NORTH) 165_' EL. 7 i 3.4 H.P. TURBINE AREA (TURBINE DECK 165' EL.) {
3.6 RX. BLDG, EXHAUST FANS (FAN ROOM 195' EL.) '20 l
/ 5.2 SOURCE VAULT (195' EL.) RX. BLDG. ]
3.7 STEAM SEPARATOR POOL AREA 234' EL. OFFSCALE
< 3.8 RX. REFUEL SLOT AREA 234' EL. 0F F SC ALEI e' 3.9 FUEL POOL AREA 234' EL. orrscALE
< 3.10 REFUELING BRIDGE 234' EL. orF5CALE v
TIME ,
O /YbO. .
A.R.M. (NUMBER AND 1.0 CATION) - -
READING 3.12 PIPE TUNNEL SUMP AREA-(T . B . NEAR R .W . DOOR 91. 6 ' EL . )
4.6 RADWASTE SUMP AREA
.(SUMP PUMP 9L.6' EL.)
-- 20 _-
4.1 R-R ACCESS (T.B. ENTRANCE 116' EL.) ;
4.7 RADWASTE FILTER PUMP AREA (LAUNDRY RCOM '116' EL.) jg 4'. 8 RALWASTE SAMPLE R-R AhEA (COND. PHASE SEP. ROOM 116' EL.) 7 4.9. CONVEYOR OP. ACCESS AREA
( R.W. 135' EL.) /g 4.10 DRUM STORACE AREA (R.W. 135' EL.)
Zo 4.11 RADW/.STE FILTER HATCH AREA (R.W. 135' EI..) 2.7 4.2' TilHlilNE 131.lH;. ACCESS AHEAS (135' KL.) IINICl!
Z 4.12 WASTE SAMPLE TANK AREA (R.W. 150' EL.) }
'*3 " ^ ^ ^
fl6 IL HTH 7 4.5 MAIN CONTROL ROOM
.o5'
~
_q
(/
sr- w y --------,y4a e. .,,.,9 .my -y-= - --- y, 9,w. . ---. - . * -- .- --w--p ,e ,-
- TIME -
/NSO A.R.M. (NUMBER AND LOCATION) READING 1.2 RX. BLDG, SUMP AREA 88' EL. g
-1.3 TORUS COMPT. .,
(BY B- & D CORE SPRAY) j]
1.4 HPCI PUMP ROOM 88' EL. , , -7 1.5 RCIC PUMP ROOM 88' EL'. g 1.7 hHR PUMP ROO.i 'A' 91.6' EL. ))
- 1. 8 CORE SPRAY ROOM 'S' 91.6' EL. g 1.9 C0.9. PUMP AREA (COND PUMP PIT - 91.6' EL.)
1.6 RHR PUMP' ROOM 'D' 116' EL.
39 n
3. l.10 RECIRC. PDIP INST. RACK AREA l j (TRI A%LE ROOM 116' TL. SC!.Td) g 1.11 STEAM FLOW INST. RACK AREA
! (TRIANGLE h0')M 116' EL. NORTH) g l
1.12 COOLING WATER PCMP AREA
'(RBCCW ROOM 116' EL.) 2,
< 2.1 COND. SERVICE PUMP AREA (T.B. 2 ACROSS FROM SAMPLE SINK 116' EL.) g
,, 2.3 COND. SERVICE PUMP AREA (T.B. 2 NEAR CRD FILTER 116' EL.) 2n l ,,- 2.4 H.P. TURBINE AREA (MOISTURE I SEPARATOR 116' EL. SOUTH) 1 .
l
! 2.5 RX BLDG. PERSONNEL ACCESS (SOUTH) (STAIRWELL 135' EL.)
L l
) 2.6 RX BLDG. EQUIP. RACK & TIP CON- g l TROL (R.P. ACCESS DOORS 135' EL.)
( 4 I .J i
TIME HSD .
A.R.M. (NUMBER AND LOCATION) READINC 2.7 RX. BLDG, PERSONNEL ACCESS (NORTH) - (DRYWELL C.P. 135' EL.)
z 2.8 TIP WITHDRAWAL AREA (INSIDE TIP_ ROOM 135' EL.) j 2.9 TURB. BLDG. ACCESS (BCMLING ALLEY 135' EL.) g 2.10 M0IST. SEP. AREA (ME7,ZANINE ROOM 135' EL.) 2, 2.11 RX. BLLG. OP. AREA (SAMP' E SINK 165' EL.) g 2.12 RX. BLDG. ACCESS (STAIRWELL 165' EL.) 7g 3.1 HEATER & RFPT AREAS p' (SOUTII) 165' EL. --
2.
3.2 HEATER & RFPT AREAS
-(NORTH) 365' EL. 7 3.4 H.P. TURBINE AREA (TURBINE DECK 165' EL.) {
3.6 RX. BLDG. EXHAUST FANS (FAN ROOM 195' EL.) 79g
/ 5.2 SOURCE VAULT (195' EL.) RX. BLDG. ]
.' 3.7 STEAM SEPARATOR POOL AREA
- 234' EL. , /g
. 3.8 RX. REFUEL SLOT' AREA 234' EL. g
/ 3.9 FUEL POOL AREA 234' EL. g
< 3.10 REFUELING BRIDGE 234' EL. [
P
TIME ,
l O
Lc /Wo .
A.R.M. (NUMBER AND l.0 CATION)
- READING 3.12 PIPE TUNNEL SUMP AREA
'(T.B. NEAR R.W. DOOR 91.6' EL.) g 4.6 -RADWASTE SUMP AREA
.(SUMP PUMI' 91.6' EL.)
2O _
4.1 R-R ACCESS (T.B. ENTRANCE 116' EL.) 7 __
4 '. 7 RADWASTE FILTER PUMP AREA (l.AUNDKY ROOM 116' EL.) /g 4.8 11ADWASTE SAMPLE R-R AREA (COND. FHASE SEP ROOM 116' EL.) 7g 4.9 CONVEYOR OP. ACCESS /.REA
( R.W. 135' EL.) /g _
4.10 DRUM STORAGE ..REA (R.W. 135' EL.)
20 4.11 RADWASTE FILTER HATCH AREA (R.W. 135' El..) 2,[
4.2 TilR!$ 1NE Ill.lJG. ACCI:SS AREAS
( 1 *J 5 ' El. . ) II ATCll -
4.12 WASTE SAMPLE TANK AREA (R.W. 150' EL.) -3 ,
4.3 D ^ ^ ^
hBfNE nt, HkTH 7 4.5 MAIN CONTROL ROOM
.O e
O
'O
/
TIME N3D A.R.M. (NUMBER AND LOCATION) READING 1.2 RX. BLDG. SUMP AREA 88' EL. f3 1.3 TORUS COMPT. ,,
(BY B & D CORE SPRAY) /3 1.4- HPCI FUMP ROOM 88' EL. , , 2- _
l.5 RCIC PUMP ROOM 88' EL'. 7 1.7 RHR PUMP R90M ' A' 91.6' EL. 1.8 CORE SPRAY ROOM 'E' 31.6' EL. 7 1.9 CCND. Pt/MP AREA (COND. PUMP PIT - 91.6' EL.) 50
. 1.6 RHR PUMP ROOM 'D' 116' EL. 30 n<
F> 1.10 RECIRC. PUMP INST. RACK AREA t
) _ .__.
(TRIANGLE R00:1 116' EL. SC';Tli) 7 1.11 S1EAM FLOW INST. RACK AFIA (TRIANGIE ROOM 116' EL. NORTH) 1 (' .. l 1.12 COOLING WATER PUMP APIA l (RBCCW ROOM 116' EL.) 1
- 2.1 COND. SERVICE PUMP AREA (T.B. 2 ACROSS FROM SAMPLE SINK 116' EL.) g
, 2.3 COND. SERVICE PUMP AREA (T.B. 2 NEAR CRD FILTER 116' EL.) y
- f. 2.4 H.P.' TURBINE AREA (MOISTURE SEPARATOR 116' EL. SOUTH) 1 -
f
- 2.5 RX BLDG. PERSONNEL ACCESS (SOUTH) (STAIRWELL 135' EL.) ,
7 2.6 RX BLDG. EQUIP. RACK & TIP CON-TROL (R.P. ACCESS DOORS 135' EL.)
?_. 0 b
b . l 1 I ._.__ _ _ . _ _ . -, _ _ _ . . ,_, - _ _ - . _ , _ .
O \\ N. TIME -
/$.3 0 A.R.M. (NUMBER AND LOCATION) READING 2.7 RX. BLDG PERSONNEL ACCESS (NORTH) - (DRYWELL C.P.135' EL.) {
2.8 TIP WITHDRAWAL AREA (INSIDE TIP ROOM 135' EL.) j y_g 2.9- TU.tB. BLUG. ACCESS (BO'AING t.LLEY 135' EL'.) 7 2.10 MOIST. SEP. AREA (MEZZANINE ROOM 135' EL.) ! 7 2.11 RX BLDG. OP. AREA (S.VD'LE SINK 165' EL.) { 2.12 RX. SLDG. ACCESS (STAIRWELL 165' EL.) 20 3.1 HEATER & RFPT AREAS (SOUTH) 163' IL. - - - - - 2
-3.2 HEATE:1 s RFPT AREAS (NoaTH) 165' EL. 2 3.4 H.P. TURBINE AREA (TURBINE DECK 165' EL.) {
l 3.6 RX. BLDG. EXHAUST FANS (FAN ROOM 195' EL.) 7, l / 5.2 SOURCE VAULT (195'. EL.) RX. BLDG. } l '. ' 3.7- STEAM SEPARATOR POOL AREA " 234' EL. , jg
< 3.8 RX. REFUEL SLOT AREA 234' EL.
f
< 3.9 FUEL POOL AREA 234' EL. -
f
< 3.10 REFUELING BRIDGE 234' EL.
f (
TIME , 153Q . i 1
- I A.R.M. (NUMBER AND !.0 CATION) *
- READING 3.12 PIPE TUNNEL SUMP AREA (T.B. NEAR R.W. DOOR 91.6' EL.) g 4.6 RADWASTE SUMP AREA
.(SUMP PUMP 91.6' EL.)
4.1 R-R ACCESS (T.B. ENTRANCE 116 ' ' EL.) g _ _ 4.7 RADVASTE TILTER PUMP NIEA (LAUNDRY ROOM 116' EL.) 2 1 4.8 RADWASTE SAMPLZ R-R /REA , (COND. FHASE SEP. - POOM 116' El..) 10 c- l 4.9 CONVEYOR OP. ACCESS AREA ( R.W. 135' EL.) j o i p- 4.10 DRUM STORA0E AREA (n.W. 135' EL.) 7 ! 4.11 ..ADWASTE FILTER HATCH AREA - Ah (R.W. 135' El..) ,
)
4.2 T;:3P!NF fil.UG. ACCESS AliEAS ( l"35 ' EL . ) li ATCil g 4.12 WASTE SAMPLE TANK AREA (R.W. 150' EL.)
'J i
l 4.3 TURBINE BLDG. ACCESS AREAS (165' EL.) HATCH g l 4.5 MAIN CONTROL ROOM , i . Ch i l l O
-+i .,-mr -
. e yw -- ---,,.---p,,,,-w w--r--y-rgn-s,.-ww -p-- -w- -,$e.--e-w_ . , ,,,-m-r,. ..%-.
REFERENCE DOCUMENTS ~ FOR THE PHILADELPHIA ELECTRIC COMPANY 4
' 1 PEACH BOTTOM ATOMIC POWER STATION NRC/ FEMA OBSERVED EMERGENCY RESPONSE EXERCISE
- 1. Peach Bottom Atoraic Power Station, Emergency Plan
- 2. Peach Bottom Atomic Power' Station, Emergency Procedures i
l 3. Peach Bottom Atomic Power Station, Final Safety Analysis Report
- 4. Title 10, Code of Federal Regulations, Part 50, Appendix E
- 5. NUREG 0654/ FEMA-E2P-1, Revision 1 l
I l l l-i' - \ l I-l l r ? O
q HARRISBURG W SYLVANIA BRP NVU TERS/A3SESSifNT rMER
-- / *A, u
83 L3P:CAStEn cotprTY EOC m 1ANCASTER PHILADELPHIA
,pg g'
*%30 CHESTER COUNTY EOC WEST CHESTER q
' YOPK COLNTY EOC e YORK f1 see LM 3 g tirOY RtN NEMi CENTM
\ /* 7
/,e %
FCACH BOTTOM ATOPIC [ f""5"^"l^ / _ " " S'1 " ' " _ - - _ f T N l2?? E MAPTLAND 83 _ k HICKORY b-CECIL C0tfrTY EOC
*\
i t 1
, s 95 i.a l4 PIKESVILLF GM g I U !
- '.5 hARYL/M) STATE EOC - -
l SCALE - MILES _l k
- ACCIDENT ASSES 5tOIT CENTER '
\ ll l
/ I NBALTIMDRE i l
1 MAP OF PAR CIPATING g i I I EMERGENCY TERS
.1 a
DOCU V1ENT' ' PAGE . l j
~
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