ML20064N121
| ML20064N121 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 06/29/1982 |
| From: | Corbin McNeil POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | |
| Shared Package | |
| ML20064N099 | List: |
| References | |
| PROC-820629, NUDOCS 8209080232 | |
| Download: ML20064N121 (180) | |
Text
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Power Authority of the State of New York Jarnes A.
Fitzpatrick Nuclear Power Plant Emergency Response Plan Exercise Manual uw OPERATING LICENSE NO. DPR-59 DOCKE" NO. 50- 333 egg 90 egg 2ggog2gg g
F PDR
1 POWER AUTHERITY OF THE STATE OF NEW YORK JAMrs A. FITzPATRicK NUCLEAR l'owtR PLANT CVR8tN A. fAcNEILL, JR.
P.O. BOX 41 Resident Manager Lycoming, New York 13093 315-342-3840 JAMES A. FITZPATRICK NUCLEAR POWER PLANT EXERCISE PURPOSE AND INTENT This exercise, with some exceptions, will endeavor to demonstrate by actual performance or simulation, a number of primary emergency preparedness functions.
The James A. FitzPatrick Nuclear Power Plant will demonstrate the capabilities of plant procedures, equipment and personnel to satisfactorily and officially respond to an emergency and mitigate that emergency.
Fundamentally, this exercise is designed to activate the JAFNPP Emergency Plan through it's various levels.
As the initiating events are provided to the plant staff, the staff will determine the nature of the accident and implement the appropriate plant emergency response procedures.
The appropriate Federal, State and local authorities will be notified in accordance with these procedures and integrated activities will be demonstrated.
The attached scenario is a hypothesized example of an emergency at the JAFNPP.
This scenario will adequately demonstrate the capabilities I have noted above and provide the opportunity to also additionally train individuals in their particular responses.
CORBIN A. McNEILL, JR.
CAM:NA:ls s
G 1982 FEMA-NRC Observed Exercise JAMES A. FITZPATRICK NUCLEAR POWER PLANT CONTENTS Section I
objectives and General GuidelinesSection II Scenario Overview
- 1) Time Sequence
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Section I EMERGENCY PLAN EXERCISE / OBJECTIVES AND GENERAL GUIDELINES d
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1982 FD'A-NBC Obstrved Exsrcise James A. FitzPatrick Nuclear Power Plant m
Objectives and General Guidelines A.
PURPOSES R is document provides guidance for the conduct of the 1982 Federal Dnergency Management Agency (FEMA) - Nuclear Regulatory Commission (tGC) observed radiological emergency exercise at the James A.
FitzPatrick Nuclear Power Plant (JAFtGP).
it shall be used by JAFtGP and by all participating Federal, State and local agencies.
% e scope of this exercise, with some exceptions, will endeavor to demonstrate by actual performance a number of primary emergency pre-paredness functions.
At no time will the exercise be permitted to interfere with the safe operation of JAFl@P and the plant nanagement may, at their discretion, suspend the exercise for any period of time necessary to ensure this goal.
This exercise will include the appropriate notification to the Nine Mile Point Nuclear Station (NMPNS). Active participation by the N!@NS organizations is not expected.
B.
EXERCISE OBJECTIVES 1.
Radiological Emercency Preparedness Plans a.
Evaluate the adequacy and capability of implementation of the New York SL 'te, Oswego County and the James A. FitzPatrick radiological emergency plans.
b.
Demonstrate the emergency response capabilities of State authorities, local support agencies, JAFtGP and appropriate Federal agencies, i
c.
Demonstrate the capability of Oswego County, the State and JAF!PP to implement their respective radiological emergency preparedness plans in a manner satisfying FDIA/IGC acceptance criteria.
1 2.
Notification Procedures a.
Dtanonstrate the ability of JAFtGP staff to classify actual or potential emergencies in accordance with JAFtGP Emergency Plan Implementation Procedures as to tbtification of thusual Event, Alert Dnergency, Site Area Snergency, General Dnergency.
b.
Demonstrate the capability of JAFtPP to notify the State, local and Ebderal levels of government accordance with Federal guidance and established protocols.
c.
Demonstrate the capability to comunicate technical informa-tion among JAFtPP, the State,, and Oswego County. JAFl@P will also demonstrate consnunicating technical information with the imC via the NRC Hot Line.
d.
Demonstrate the capability of the State, Oswego County and JAFtPP to notify and activate emergency response personnel.
e.
Demonstrate the capability of Oswego Cbunty and the State to alert and notify the affected permanent and transient public within the Plume Exposure EPZ of an incident at JAFl@P and to follow up with information as required.
'Ihis will include activation of the pronpt notification system (sirens and tone alert radios) and the Emergency Broadcast System (EBS).
f.
Demonstrate as appropriate the notification and request for assistance to Federal agencies such as the radiological assistance from the Department of Energy.
g.
Demonstrate as appropriate the notification to counties and provinces within the ingestion Dnergency. Planning Zone (EPZ) and to agencies such as the railroad by the State and Oswego
,Opunty.
3.
Emergency Comunications a.
Denonstrate the JAFIPP communication capabilities among the Cbntrol Room, Technical Support Center (TSC), Emergency Operations Facility (EOF), Operations Support Center (OSC) and the Dnergency tiews Center (EIC), and the ability to main-tain communications with the Federal Government.
b.
Demonstrate emergency communications capability among Oswego County, the State and JAFIPP including the Radiological Ener-gency Ctx=unications System (RECS-hot line).
c.
Demonstrate the adequacy of JAFIPP, local and State emergency communications to:
(1) Transmit instructions to activate essential staff.
(2) Disseminate essential information to assisting agen-l cies.
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(3) Operate a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day alert and notification system.
d.
Demonstrate the ability of JAFIPP and Oswego County to coor-dinate, control and deploy radiological monitoring teams via the respective field comunications system. - ~ _ -
4.,
Ebergency Resoonsa Facilities Demonstrate the adequacy of the staffing and setting-up as a.
appropriate of emergency response facilities as well as de-constrating the adequacy of space and habitability for manage-ment of radiological emergency at:
JAFNPP Cbntrol Room (CR)
JAFSPP '14chnical Support Center (TSC)
JAFIPP Operational Support Center (OSC)
JAFIPP Dnergency Operations Facility (EOF)
State Emergency Operations Center (EOC)
ODP Central District EOC Oswego (bunty EOC Special News Center b.
Demonstrate the adequacy of internal communications in the State and (bunty Emergency Operations Centers (EOC) including the use of status boards, charts, maps, diagrams or other dis-plays.
Evaluate the adquacy and competency of State, Oswego Couny and c.
JAFIGP staff to operate the emergency response facilities, d.
Evaluate the adequacy of access control and security for emer-gency re monse facilities.
5.
Direction and control Desaonstrate the ability of key emergency personnel at all a.
levels of government and JAFtPP to initiate and coordinate timely and effective decisions with respect to a radiological emergency and clearly demonstrate "who is in charge."
b.
Demonstrate that there is effective organizational control (direction and control) and integrated radiological emergency I
response including deployment of field monitors, receipt and analysis of field data and sharing of field data among the licensee, State and Oswego County for evaluation and verifica-tion.
Demonstrate the capability of Federal, State and County emer-c.
gency response agencies to identify and provide for resource requirements.
Any required Federal response activities may be simulated.
d.
Demonstrate the capability in coordinating (internally / exter-nally) actions among organizations in order to obtain support and to make appropriate decisions.
Deomonstrate the capability of elected and appointed officials e.
in implementing appropriate radiological emergency response actions.
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6.
Public Information a.
Demonstrate the adequacy of the operation of and interaction among the State, Oswego County and JAFIGP public information systems.
b.
Demonstrate the activation and manning of the Emergency News Center by utility, State and Oswego County public information personnel and provide for periodic public information re-leases and rumor control.
c.
Demonstrate that the offsite authorities and the licensee can effectively provide information to the media in the event of an accident.
7.
Accident Assessment and Evaluation a.
Demonstrate the activation, operations and reporting proce-dures of JAFl@P and Oswego (bunty field monitoring teams.
JAFtPP teams will be dispatched within and beyond the site boundary.
Field monitoring teams will be provided with simulated data at assigned times and specific locations con-sistent with the simulated release from the plant.
b.
Demonstrate the ability of JAFIPP, Oswego County and the State to receive and assess radiological data from both
, County and licensee field teams in accordance with their respective radiological emergency plans.
c.
Demonstrate the ability of JAFNPP, the State and Oswego County to calculate dos' pro]ections, conpare and projections to the Protective Action Guide (PAGs) and determine appro-priate protective actions.
8.
Protective Response a.
Demonstrate the capability of State and Oswego County emer-gency response organizations _to make decisiens and to imple-ment appropriate protective action response options. 'Ihe response options include sheltering and evacuation (simu-lated) of onsite and offsite areas, informing the public on the development of the accident, identification and provision for special populations, activation of reception and congre-gate care facilities and ingestion exposure pathway consider-ations.
b.
Denon4trate JAFNPP e:Tloyee accountability following the re-quirermnts of their Dnergency Plan Implementing Procedures.
9.
Radiological Exoosure Control a.
Demonstrate the decision process for limiting exposure of emergency workers.
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b.
Demonstrrte th: processing of St te end local emergency workers through Personnal Monitoring C:nt:rs (PIC) including monitoring and decontamination.
Evaluate the capability of offsite emergency response person-c.
nel to icplement access control procedures.
d.
Demonstrate methods and resources for distribution of dosi-metry to emergency workers.
Demonstrate the capability of emergency personnel for keeping e.
records of individuals radiation exposures.
- 10. Medical Supoort Demonstrate through the use of a scenario independent of the a.
plant offsite releases the first aid treatment of a ecntaminated casualty in the field and transpcrt to the subsequent treatment at a hospital.
b.
S e initial treatment of an injured worker with contamination at JAFIPP, transport to and subsequent treatment at a hospital will be demonstrated at a medical drill tentatively scheduled for October 1982.
- 11. Reentry and Recovery Demonstrate the capability of emergency personnel to identify a.
requirements, assess and implement procedures for reentry.
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b.
Demonstrate the capability of emergency personnel to identify requirements, programs and policies governing damage assess-ment and recovery.
C.
INTENT OF 'niE FITZPATRICK EXERCISE SCENARIO The licensee (Power Authority of the State of New York), New York State and Oswego (bunty plan a coordinated exercise of their re-spective emergency plans for both the site and offsite support agencies on August 11, 1982.
In order to minimi::e the impact on scheculing and agendas, the exercise scenario will be completed in a time frame of approximately a routine working day.
'Ih exercise is intended to demonstrate many, but not necessarily all, of the JAFtGP capabilities to respond to a wide range of emer-gency conditions.
This scenario is designed to activate the JAFIGP Emergency Plan through its various action levels. Although this scenario accurately simulates operating events, it is not intended to assess all of the operators diagnostic capabilities, but rather pro-vides sequences which ultimately demonstrate the operators ability to respond to events and which results of exercising both onsite and offsite emergency plans and procedures.
Free play is encouraged and the referees will interfere only if operator / player action pre-maturely terminates the exercise of excessively deviates from the drill schedule. -
In'ordar to provide a conservative exercise in terms of off-site doses adverse meteorology was developed since acutal meteorology would probably lead to projected radiological doses below established Protective Action Guides (PAGs).
D.
COtCEPT OF CPEPJCIONS AND COfCROL OF 'IME EXERCISE 2e licensee and the State of New York will supply official Control-1ers/ Evaluators for locations where an emergency response is being denonstrated for the exercise.
Prior to the exercise, the control-1ers and evaluators will be provided with the appropriate locations, maps, time periods, guidelines, and an observer evaluation checklist for their exercise assignments.
The exercise initiating events will be controlled by the lead referee at the JAFNPP.
Simulated initiating eevents will consist of two types of information:
(1) informnation and data provided to control room personnel by the (bntrol Room referee, (2) onsite and offsite dose rate data (dimulated gamma and iodine dose rate measurements) provided to the site, county, and Federal (if they participate) monitoring teams by controllers / referees.
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i me lead referee (onsite) and the State Exercise Director (offsite) will have the responsibility to control and coordinate the time sequence of initiating events to ensure an orderly flow of exercise events.
m e State controllers or Federal evaluators may supply "probleus" for
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return to his farm after the evacuation). All other actions during offsite participants (such as a disabled vehicle or a farmer who must the exercise will occur through a free play response as the licensee, State and County participants respond to the initiating events.
I As the initiating events are provided to the JAFNPP staff, they will i
- determine the nature off the emergency and implement appropriate plant emergency response procedures. Rese procedures include a de-tenaination of the emergency classification in accordance with the JAFtPP Dnergency Plan.
Af ter the emergency classification has been i
determined, the appropriate Federal, State and local authorities will be notified in accordance with the JAFNPP emergency response proce-dures.
Upon notification of the simulated accident at the JAFIPP, the State and Oswego County will complete their initial notifications in accor-dance with their emergency plans and procedures.
State and local personnel and facilities will be activated based on the initial acci-dent classification provided by the site and confinned by' direct communication between apptcpriate agencies and the James A.
Fitr. Patrick Nuclear Power Plant.
Se simulated accident will continue to develop based on data and information provided to the control room personnel by the control rcom referee.
As the situation develops, information will be for-warded to New York State and the county assessment teams.
These agencies will analyze and act on the information as they would in a l
real emergency.
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Whsre information would normally be confirmed via an independrnt source (such as th2 National Waather Service for weathar data), the confirmation data will be obtained.
If the confirmation data con-flicts with simulation data provided by the site, the simulation data i
7 will be utilized for accident assessment purposes.
If any inconsis-tencies are noted in the initiating events, these inconsistencies should be questioned by the accident assessment teams as they would a
be in a real emergency.
Certain inconsistencies (such as plume width, release duration, tech-nical reason for the simulated release, etc.) may be intentional and required due to the nature of simulating an accident that has never occurred and the requirement to provide an exercise basis which tests the site, State, and local capabilities to the maximum extent feas-ible in a limited time frame.
If an inconsistency is known or deter-mined to be intentional, then the accident assessment group will note the inconsistency and ignore it.
Se lead referee shall have the authority to resolve or explain any inconsistencies or problems that-may occur during the exercise.
Withh the exception of the aforementioned potential inconsistencies, the internal operation of the site, State, and local comand centers.
shall be identical with their intended operation in a real emergency.
E.
PUBLIC INFORfGTION AND A*aRENESS Prior to,the exercise, the public within the affected area will be informed of the impending conduct of a radiological emergency exer-cise through joint press releases. %e Power Authority of the State of New York, New York State and Oswego County will develop coordin-ated press releases.
Agencies should make every effort to prevent the public from being j
misinformed about the nature of the exercise.
terefore, it is inportant to inform members of the public that an exercise is in pro-gress and that their involvement is not required, whenever public contact occurs in the field.
A pre-exercise briefing will also be conducted for the news media.
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F.
PAINTAINING E??.BGEICY READINESS During the performance of an exercise the ability to recognize a real emergency, terminate the exercise, and respond to the new situation must be maintained. B erefore, the exercise scenario and actions of-participants shall not incit!de any actions which degrade the condi-tion of systems, equipment or supplies, or affect the detection, asses =cnt or respcnse capability to radiological or other emer-
- gencies, i
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Actions ttken by the participante shall also Evoid actually reducing plant er public safsty. The potintial for cr21 ting recl rcdiological or other emergencies shall be specifically avoided.
If a local emer-gency occurs during an exercise requireing the local agency to termi-7 nate its particiaption in the exercise, the agency should notify the State and Oswego County Emergency Operations Centers of the situation.
The State shall then determine whether the agency participation in the exercise is warranted and shall inform all other agencies involved in the exercise of the situation.
All messages about real events shall be clearly identified as such.
For example, precede a real message with
' tis is NOT, repeat, NOT an exercise message."
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Section II EMERGENCY PLAN EXERCISE / SCENARIO OVERVIEW 1)
Time Sequence 2)
Description 9
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FITZPATRICK EMERGENCY PLAN EXERCISE SCENARIO OVERVIEW 0700 Start of Exercise - Notification of Unusual Event 0815 Escalation to ALERT Classification 0930 Escalation to SITE AREA EMERGENCY Classification 1100 Escalation to GENERAL EMERGENCY Classification 1400 De-escalation to SITE AREA EMERGENCY Classification - Releases to Environment Secured 1430 Time Advance for Exercising Recovery Operations 1700 Secure from Exercise
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The FitzPatrick. Nuclear Power Plant is' operating at 100% power.' The Reactor Core Isolation Cooling System (RCIC) has been removed from service overnight for repair of a body crack of a turbine steam supply isolation valve.
Required High Pressure Coolant Injection System (HPCI) surveillance tests have been satisfactorily completed. Valve repair is expected to take several days. No other significant equipment problems are present at exercise commencement.
At approximately 0700 the Shift Supervisor is notified by telecopy message of a generic problem involving th'e lubricant used in the solenoid valves for the Safety Relief Valves. Apparently, when exposed to the temperature and humidity conditions f the drywell environment for a prolonged period of time, the lubricant decomposes into a cement-like substance that 1
l may prevent solenoid actuation. This condition initiates Notification of an i
Unusual Event and requires a plant shutdown to be initiated.
Shortly thereafter, a small leak is discovered in the Main Steam Tunnel (outside the Prbaary Containment).
The leak rate increases substantially during the next hour until, a few minutes before 0800, automatic Main Steam Line Isolation Valve (MSIV) closure is initiated from high steam tunnel temperatures. The transient proceeds normally with a successful re, actor scram, SRV actuations, and automatic HPCI start-up from low, low vessel 1
level. However, leakage from the Main Steam Tunnel increases during the transient to about 50 gpm. Attempts to manually (electrically) open relief valves fail, verifying their inoperability.
The Shift Supervisor upgrades I
the classification of plant conditions to the ALERT category either as the ts result of perceived steam line break with leaking isolation valves, reactor 1
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coolant leakage of 50 gpm, or as result of a situation where increased c~s awareness is required to operating staff personnel. The Technical Support Center -(TSC) and Operational Support Center are activated.
Investigation into the source of the leakage continues. Plant cool down and depressur-ization proceed using the HPCI system.
Leakage is the result of a crack in the "B" Feedwater System piping in the Main Steam Tunnel between the primary 4
containment and the outboard isolation valves of the HPCI and Feedwater System.
The HPCI System tees into this section of piping.
i At 0930 the piping crack propagates catastrophically resulting in a complete loss of HPCI and Feedwater System injection capability.
The HPCI System isolates during the transient from high steam line flow signals.
During the isolation the AC breaker supplying the inboard steam isolation valve trips its overloads with the valve in the closed position.
Vessel level remains essentially constant following the feedwater line break and reactor pressure is increasing. The Control Rod Drive Hydraulic pumps remain j
as the single source of high pressure injection to the vessel.
Turbine Building Radiation Ventilation Exhaust Monitor increases to the high level i
trip point.
Building isolation occurs automatically except that one damper on the steam tunnel exhaust duct jams in the open position.
Event classifi-cation is upgraded to the SITE AREA EMERGENCY based upon the inability to cool and depressurize the vessel to the cold shutdown condition.
Each of the j
high pressure systems is disabled.
SRV's will not function due to frozen solenoid air actuators.
RCIC steam supply valve is disassembled.
HPCI and Residual Heat Removal are isolated by a failed steam isolation valve.
Feedwater and HPCI are isolated from the vessel by the feed line break.
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Leakage from the reactor vessel through the break in "B" Feed Water line p
continues to the Turbine Building due to seat leakage from the inboard feed check valve. Vessel level is held constant by CRD injection. Attempts to reset the thermal overloads for the inboard HPCI steam isolation valve fail and repair maybe undertaken.
Investigation by the repair crew will result in l
a determination that the valve's motor operator has shorted to ground.
Vessel pressure increases until it reaches 1090 psig at which point SRV's lift to limit pressure. At approximately 1100, the leak rate through the "B"
Feed Water inboard check valve increases due to the pressure transients caused by relief valve operation.
Leakage far exceeds the capacity of CRD to makeup and vessel level begins to decrease rapidly.
Reactor pressure decreases, but not fast enough to allow injection of low pressure systems to before core uncovery.
Leakage is to the Turbine Building and out the failed
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open Main Steam Tunnel exhaust duct. Temperature in the Turbine Building increases rapidly and the roof blow out patches open.
Emergency classifi-cation is upgraded to GENERAL EMERGENCY since release of large amounts of radioactive materials is probable at this point.
4 Shortly after 1130, the core is uncovered and pressure, though decaying, is still greater than the shut-off head f the low pressure ECCS pumps. The core remains uncovered until about 1200 when pressure interlocks clear and ECCS injection begins.
The vessel is quickly refilled and by 1230 shutdown cooling is established. vessel level is maintained above the core and below the feedwater penetrations to the vessel thereby halting the release to the Turbine Building.
Releases from the Turbine Building gradually decrease as the core is cooled and steam in the Turbine Building condenses and/or t
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i disperses.
By 1400 site radiation and release levels are such that de-escalation to the SITE AREA EMERGENCY classification is justified.
Following de-escalation at time lapse to the following morning occurs.
The reactor remains in shutdown cooling with stable level and temperature.
Coolant leakage has stopped.
Recovery operations to seal the Turbine Building are demonstrated by the plant personnel.
Off-site surveys for iodine deposition and protective action evaluation are demonstrated.
At some point during the exercise, in an independent scenario, a bus accident is simulated.
A maximum of two contaminated injuries result requiring mobilization,of rescue personnel, transportation to nearby health facilities, and subsequent decontamination and health care.
L The exercise will terminate at approximately 1700 with the plant in stable conditions and concerned agencies pursuing recovery actions.
e
f Section III EMERGENCY PLAN EXERCISE /JAFNPP PLAITT DATA l
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Piga lb MESSAGE NO. 1 s
TIME:
0650 ON DAY l ISSUED TO THE CONTROL ROOM The plant is operating of 100% power.
Plant chemistry is normal.
All major systems are operable and in their normal lineup for the full power condition except RCIC.
Overnight a crack was discovered in the body of the RCIC steam inlet valve, 13-MOV-131.
The system has been isolated and a PTR 4
hung.
Repairs are expected to take several days.
Required HPCI surveillance tests have been completed satisfactorily. With the exception of RCIC, no other abnormal conditions or alarms exist.
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TIME 0650_
PLANT STATUS SHEET SHEET NO. ic vay A EDG Starts V;ssel Level 200 inches A Running Loaded / Running Unloaded / Standby /005 C Running Loaded / Running Unicadecs Standby /005 Level Trend Stable 8 Running Loaded / Running Unloaded / Standbyr005 Vessel Pressure 1005 osig Pressure Trend Stable 115KV Reserve P,cJde Available
- 3 LHH Yes/No Vsssel Bottom
- 4 HMP Yes/No Orain Temp.
501
'F
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Building Vent Rad Monitors 0
C1canuo Inlet Temp. 515 F
Rx. Building 150 cpH -
Refuel Floor AMU CPM Main Steam pressure 950 osig Turbine Building Jea CPM Radweste 11U CPM Drywell Pressure 16.5 osia Control Room 1UU CPM Off-Gas Rad Monitor 250 mR/hr.
Drywell Ave, Temp. 123
'F Stack Rad Monitor 3000 Cps Torus Ave. Water Temperature 72.5
'F High Range Effluent Monitors Stack.
A 0.7 8
0.3 mR/hr.
Torus Pressure 14.7 osia Turbire Sidg. A U.6 B
mR/hr.
Radwaste Oldg. A U.J 3
o.5 mR/hr.
Torus Level
-1.07 inches Containment High Range 5 Monitor A 70 8 20 R/hr.
Drywell F1cor Leak Rate 1_R7 opm Area Radiation Monitors 1
O2 mR/hr.
Drywell Equipment 2
O.3 mR/hr.
Leak rate 1
n opm 3
0.0a mR/hr.
4 5.O mR/hr.
Busses Energized (/)
5 1 0 mR/hr.
6' 1_O mR/hr.
10300 /10400 /
7 1 n mR/hr.
8 s n mR/hr.
! 600 j 10 9
95 mR/hr.
10500 10 in mR/hr.
A OC jB DC j 11 15 mR/hr.
12 1 n mR/hr.
Main Steam Line Radiation 13 cn mR/hr.
Monitors 1.6 R/hr.
14 g n mR/hr.
15 11 mR/hr.
Cements:
16 1 n mRihr.
17 on mR/hr.
RCIC INOP. 13-MOV-15 + 16 18 Av mR/hr.
19 Au m2/hr.
TAGGED CLOSE0 20 Au mR/hr.
21 1v mR/hr.
22 z.u mR/hr.
REACTOR POWER = 10D%
1, 25 8.0 mR/hr.
25
- 9. 0 mR/hr.
27 20 mR/hr.
t 28
- 9. 0 mR/hr.
29 30 mR/hr.
30 200 mR/hr.
Neteorology Windspeed Direction Brookhaven Class
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PAGE, 2n
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FITZPATRICK SCENARIO - August 11, 1982 MESSAGE ANTICIPATED RESULTS AND EMERGENCY TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COMMENTS CLASSIFICATION 0700 2
Control Telecopy received 1.
Review of Technical Notification day 2 Room indicating possible Specification limiting of an inoperability of Safety conditions for Unusual Relief Valve solenoid activators operation.
Event.
2.
Classification of situation using IAP-2 of the Emergency Plan.
3.
Preparation for a normal plant shutdown.
4.
Commencement of Emergency Plan notifications using IAP-1.
0 9
Ptga 2b MESSAGE NO. 2 TIME:
0700 ON DAY 1 ISSUED TO THE CONTROL ROOM The following telecopy message has just been received and brought to the Control Room by the acceptant:
11 August 82 TO:
JAMES A. FITZPATRICK NUCLEAR POWER PLANT FROM:
XYZ LABORATORIES
SUBJECT:
POSSIBLE MALFUNCTION OF TARGET ROD SAFETY RELIEF VALVE SOLENOID.
VALVES Recent environmental testing conducted at our labs suggest that the new lubricant used in the solenoid activators for your Target Rod safety relief valves may undergo degradation which could prevent proper operation of the activators. After extended operation in a high temperature, high humidity test environment sbnulate to that of the containment a cement-like by-product is formed. This effectively freezes the solenoid valves in the closed position preventing electrical activation of the relief valves.
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TIME 0700 PLANT STATUS SHEET SHEET NO. 2c Day 1 EDG Starts Yessel Level 200 inches A Running Loaded / Running UnloadecrStandbyr005 C Running Loaded / Running UnicadeorstandLf r005 Level Trend Stable 8 Running Loaded / Running Unloadeo 'Stanoby '005 V:ssel Pressure 1005 osig Pressure Trend Stable 115KV Reserve P,qnge Available
- 3 LNH Yes 'No Vessel Bottom
- 4 HMP Yes 'No Orain Temp.
502 0
~
F Building Vent Rad Monitors 0
Cleanuo Inlet Temp.516 F
Rx. Building 150 CPM Refuel Ficor Aou CPM Main Steam pressure 950 osig Turoine Building Jia CPM Radweste 1Au CPM Drywell Pressure 16.5 osia Control Room AUU CPM Off-Gas Rad Monitor 250 mR/hr.
0 Drywell Ave. Temp.123 F
Stack Rad Monitor
_3000 Cps Torus Ave. Water Temperature 72.5
- F High Range Effluent Monitors Stack AO.7 8 0.3 mR/hr.
Torus Pressure 14.7 osia Turbine Bldg. A O.6 8
mR/hr.
Radweste Oldg. A O.J B
U.3 mR/hr.
Torus Level
-1.07 inches Containment High Range 6 Monitor A70 8 20 R/hr.
Drywell Floor Leak Rate 1 A7 opa Area Radiation Monitors 1
0.2 mR/hr.
Drywell Equipment 2
0.3 mR/hr.
Leak rate 1 qg opm 3
0.08 mR/hr.
4 5.0 mR/hr.
Busses Energized (/)
5 1_o mR/hr.
6 1.0 mR/hr.
10300 /10400 7
i_o mR/hr.
8 5o mR/hr.
/
10500 Y 10600 t' 9
's mR/hr.
10 lo mR/hr.
AOCs'BDCs' 11 1s mR/hr.
12 1.0 mR/hr.
Main Steam Line Radiation 13 A n mR/hr.
Monitors 1.6 R/hr.
14 s_o mR/hr.
15 11 mR/hr.
Coments:
16 7 m mR/hr.
17 on __
mR/hr.
RCIC INOP. 13-MOV-15 + 16 18 Av mR/hr.
19 Au mR/hr.
TAGGED CLOSED 20 Au mR/hr.
21 1.v mR/hr.
22 4.u mR/hr.
h d.u mR Rx POWER = 100%
g ADS and SRV manual operation
'S 6.u mR/hr.
may be inneerative.
26 9.0 mR/hr.
27 20 mR/hr.
28 9.0 mR/hr.
29 30 mR/ha.
30 200 mR/hr.
Meteorology Windspeed Direction Brookhaven Class
PAGE s
_ 3a
)
FITZPATRICK SCENARIO - August 11, 1982 MESSAGE ANTICIPATED RESULTS AND EMERGENCY TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COMMENTS CLASSIFICATION 4
0705 3
Radwaste Increased pumpouts of the 1.
Quantify change in Unusual day ]
Control Rooni south Turbine Building Floor leakage from pump run Event Sump TK-130A.
data.
Continued 2.
Investigate the source locally.
3.
Notify the Control Roon of this situation, i
e e
T Paga 3b MESSAGE NO. 3 TIME:
- 0705 ON DAY 1 ISSUED TO THE RADWASTE OPERATOR Daily run times for P-3A, the south Turbine Building floor sump have been overaging 0.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> the last couple weeks. This morning the daily pump run time is 0.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />.
i i
l h
--,,,m,.,n,
,a-
- -.-.. - ~ - -
._.,,,-,-,,--e-.
,., ~. - -,,
PAGE 4m
\\
)
FITZPATRICK SCENARIO - August 11, 1982 MESSAGE ANTICIPATED RESULTS AND EMERGENCY TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COMMENTS CLASSIFICATION 0715 4
Control Data provided to the Control 1.
Discuss with the Unusual day ]
Room Room operator indicating Control Room referee Event increased temperature in the the implications of Continued steam tunnel near primary such data, possible containment.
causes,-and operator actions.
2.
Complete notifications required by Emergency Plan for Unusual Event Classification.
4 e
Piga 4b MESSAGE NO. 4 s
TIME:
0715 ON DAY 1 ISSUED TO THE CONTROL ROOM Auxiliary Operators have just completed Surveillance, Test-40D, Daily Surveillance and Instrument Checks.
Main Steam Tunnel temperatures are as follows. All other parameters appear normal.
DETECTOR NORMAL READING CURRENT READING TE-121A 107'F 114*F TE-122A 102*F 101*F TE-123A 103*F 102*F TE-124A 115'F 114*F TE-121B 107'F 114*F
(,,- '
TE-122B 101*F 102*F TE-123B 103*F 103*F TE-124B 117'F 118'F TE-121C 108'F 115'F TE-122C 102'F 102*F TE-123C lOl*F 101*F TE-124C 118'F 119"F TE-121D 109'F 115'F TE-122D 102*F 103'F TE-123D 10l*F 102*F TE-124D 116*F 117'F 1
i V
TIME 0715 PLAtiT STATUS SHEET SHEET NO. 4c Day 1 EDG Starts sessel Level 200 inches A Running Loaded / Running Unicaded 'StandbyJ005 C Running Loaded / Running Unloaded 'Stanos/J005 Level Trend Stable 8 Running Loaded / Running UnloadedJStanobyJ005 0 Running Loaded / Running Unloaded / S taneby, 005 Vessel Pressure 1005 osig Press::ce Trend Stable 115KV Reserve r Available
- 3 LHH
/flo V;sse) iottom
- 4 IMP
/?to 0
Drain Temp.
501 F
Building Vent Rad Monitors 0
Cisanuo Inlet Temp. 515 F
Rx. Building 150 CPM Refuel Floor 160 CPM Main Steam Dressure 950 osig Turbine Butiding
.$ / 5 CPM Radweste 110 CPM Drywell Pressure C
osia Control Room 100 CPM Off-Gas Rad Monitor 250 mR/hr.
0 Drywell Ave. Temp. 191 F
Stack Rad Monitor 3000 C"ps Torus Ave. Water 0
Temperature 72_A F
High Range Effluent Monitors Stack.
AO7 B
0.3 mR/hr.
Torus Pressure 1a 7 osia Turbine Bldg. A O _6 8
mR/hr.
Radwaste Oldg. A O. 3 B
O.5 mR/hr.
Torus Level 1 n7 inches Contai. ment High Range 6 Monitor A 70 B A R/hr.
Rate 3 on opm Area Radiation Monitors 1
n9 mR/hr.
Drywell Equipment 2
n7 mR/hr.
Leak rate
, ec
(
~'--
opm 3
n nn mR/hr.
4 4 n mR/hr.
Busses Energized (/)
5
, n mR/hr.
6 1 n mR/hr.
10300 r,j10400 7
, n mR/hr.
y y
8 e n mR/hr.
10500
- 10600 L 9
ee mR/hr.
10
~
,n mR/hr.
A DC 'l 8 OC V 11
,e mR/hr.
12
-- 3 n mR/hr.
Main Steam Line Radiatien 13 c n-~
mR/hr.
Monitors 1.6 R/hr.
14
-g n mR/hr.
15 mR/hr.
Ccmrients:
16 mR/hr.
, n 17
~~~ mR/hr.
on RCIC INOP.
18
'- Au mR/hr.
19 10 mR/hr.
20 10 mR/hr.
21 1.0 mR/hr.
l 22 2.0 mR/hr.
5.0 Rx POWER = 100%
l ADS and SRV manual opcration 25 8.0 mR/hr.
mu ko 4 mno m ino 26 9.0 mR/hr.
27 20 mR/hr.
28
- 9. 0 mR/hr.
29 10 mR/hr.
30 900 mR/hr.
l1eteorology Windspeed Direction Brooknaven Class s
PAGE, Sa
\\
)
~
FITZPATRICK SCENARIO - August 11, 1982 MESSAGE ANTICIPATED RESULTS AND EMERGENCY I
TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COMMENTS CLASSIFICATION.
715-5 Radwaste Provides results of investiga-Discussion of possible Unusual 730 Control tion of input to Turbine sources of leakage with Event day J Room Building Sump TK-130A.
Leak referee.
Continued rate is approximately 2 gpm Notification of results from the steam tunnel.
of investigation to the Control Room.
i i
i
Paga Sb MESSAGE NO. 5 R.
TIME:
ISSUED BETWEEN 0715 to 0730 WHEN THE RADWASTE OPERATOR ENTERS THE AREA SOUTH OF THE MAIN CONDENSER TO INVESTIGATE LEAKAGE SOURCE.
ISSUED TO THE RADWASTE OPERATOR A small stream of clear water is trickling into the southern Turbine Building Floor sump from the Main Steam Tunnel is about 2-3 gpm.
You cannot see the source of the leakage.
DO NOT ENTER the Steam Tunnel to investigate further.
f i
wa-n--
r n
=
NO YI CT a
NA c)
EC d
GI e
RF l
u EI a
n MS uti E
ES snt G
A uen A
L nvo P
C UEC h
D t
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f A
w f
e f o i
S no l t T
o s
ef L
i ee ri US scst h
ST sruch s EN uuauc RE cocdt g M
ss nan DM i
d owi EO dnnC n.
TC oa di s A
e ear P
uee
.t ro I
negnatt C
iraol a
2 I
t eki uhr 8
T nf at mt e 9
N o e e c ii p 1
A Crl aswo 1
1 tsu S
g T
l u
N e
A E
n N'
T n
N u
O t
O C
m, I
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a A
G es N
A t u E
S St C
S a
S E
nt M
is K
a C
F Me I
O r
R f u 9
T Y
ot A
R a
P A
er Z
M t e T
M ap I
U d m F
S pe Ut OT D
l E
o U
r S
t m S
no I
oo CR E
GR AE 6
]
E 0
eQ M
3 y I
7 a T
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Pagn 6b a
a MESSAGE NO. 6 m
i TIME:
0730 ON DAY 1 ISSUED TO THE CONTROL ROOM AND RADWASTE CONTROL ROOM Steam Tunnel Temperature Detectors, TE-121A through D have increased 7'F since the previous message. Other detectors continue to indicate normal temperatures.
The training shift operators have arrived. Conduct watch relief with these operators. They will continue the exercise activities.
The normal day shift will relieve afterward and continue normal shift activities.
I I
+
i l
TIME 0730 PLAriT STATUS SHEET SHEET T40. 6c Day 1 EDG Starts Vassel Level 200 inenes A Running Loaded / Running Unicaded 'StandbyJ005 C Running Lo# dad /ounaina tinloadeo 'StandbyJ005 Level Trend Stable B Running Loaded / Running Unloaded.'StanabyJ005 0 Running Loaded / Running Unloaded 'StanabyJ005 V&ssel Pressure 1005 osig Pressure Trend Stable 115KV Reserve P gge Available
'2
- 3 LHH Yes 'No V;ssel Bottom
- 4 T94P M 'No Drain Temp.
501
,F Building Vent Rad Monitors 0
Cleanup Inlet Temp. 515 F
Rx. Building 150 CPM Refuel Floor 160 CPM Main Steam Pressure 950 osig Turbine Building Jed CPM Radwaste 110 CPP Orywell Pressure 16.5 osia Control Room 100 CPM Off-Gas Rad Monitor 250 mR/hr.
Drywell Ave. Temp. 121 F
Stack Rad Monitor 3000 Cps Torus Ave. Water Temperature 72.6 F
High Range Effluent Monitors Stack A O.7 8
0.3 mR/hr.
Torus Pressure 1,1_ 7 osia Turbine Bldg. A O_6 8
mR/hr.
Radweste Oldg. A O_3 B O5 mR/hr.
Torus Level 1 nA inches Drywell Floor Leak Rate 1 o7 apn Area Radiation Monitors 1
n9 mR/hr.
Drywell Equipment 2
n2 mR/hr.
Leak rate 3 er opm 3
n na mR/hr.
4 m n mR/hr.
Busses Energized (/)
5 1 n mR/hr.
6 1 n mR/hr.
10300 V 10400 V 7
3 n mR/hr.
B c n mR/hr.
10500 / 10600 8' 9
ee mR/hr.
10 mR/hr.
,n A OC Y B OC W 11
,e mR/hr.
12 mR/hr.
, n Main Steam Line Radiation 13 e n - mR/hr.
M:nitors 1.6 R/hr.
14
"c n mR/hr.
15
,, -'- mR/hr.
Camnents:
16
--, n mR/hr.
17
-- mR/hr.
nn RCIC INOP.
IB
lu mR/hr.
19 10 mR/hr.
20 10 mR/hr.
21 1.0 mR/hr.
22
- 2. 0 mR/hr.
h 5.0
/
Rx POWER = 100%
ADS and SRV manual operation 25 8.O mR/hr.
mm, wo 4., nno v,
- 4 sro 26 9.0 mR/hr.
27 20 mR/hr.
2B 9.0 mR/hr.
29 10 mR/hr.
30 700 mR/hr.
fieteorology Windspeed Direction Brookhaven Class
e NO YI CT e
NA 7
EC d
)
GI e
RF l
u EI a
n MS uti E
ES snt G
A uen A
L nvo P
C UEC D
NA S
C 2
I e
8 T
n 9
N o
1 A
N 1
1 m
t a
s e
u S
t g
T s
u N
w A
E n
T i
N a
O m
O C
I g.
R E
ns A
G i e N
A sr E
S au C
S et S
E ra M
cr K
ne C
F i p I
O m
R ne n
T Y
ot A
R P
A el Z
M t e T
M an I
U d n F
S pu Ut OT D
l E
o U
r S
t m S
no I
oo CR E
GR AE 7
]
E 5
M 4 y
,(
I 7 a T
0d 1
E t
Paga 7b MESSAGE NO. 7
. m TIME:
0745 ON DAY 1 ISSUED TO THE CONTROL ROOM Steam Tunnel Temperature Detectors, TE-121A through D have increased 10*F since the last message.
Other detectors have not increased significantly.
e d
3 l
1 i
L
TIME 0745 PLANT STATUS SHEET SHEET NO. 7c w
Day 1 EDG Starts V ssel Level 200 inches A Running Loaded / Running Unicadeds Standby l'005 C Running Loaded / Running Unloadeds StandbyJ005 Level Treno Stable B Running Loaded / Running Unloaded / S tandby, 005 0 Running Loaded / Running Unloaded / Stanabys 005 Vessel Pressure 1005 asig Pressure Trend Stable 115KV Reserve e Available
- 3 LHH JNo f
Vessel Bottom
- 4 NMP sfNo 0
Drain Temp.
501 F
Building Vent Rad Monitors 0
cleanup Inlet Temp. 516 F
Rx. Building 150 CPM Refuel Floor 180 CPM Main Steam Pressure 950 osig Turbine Building 375 CPM Radwaste
.10 CPM Drywell Pressure 16.9 osia Control Room
- .00 CPM Off-Gas Rad Monitor 250 mR/hr.
O Drywell Ave. Temp, 19t F
Stack Rad Monitor 3000 CDs Torus Ave. Water 0
Temperature 72.6 F
High Range Effluent Monitors Stack AO7 B
0.3 mR/hr.
Torus Pressure 14.7 osia Turbine Bldg. A O.6 B
mR/hr.
Radwaste Oldg. A O _3 B
O.5 mR/hr.
Torus Level
-1 nA inches Containment Hign Range 5 Monitor A L B L R/hr.
Rate 1 ni apm Area Radiation Monitors 1
n?
mR/hr.
Drywell Equipment 2
n, mR/hr.
Leak rate
, cc apm 3
m nn mR/hr.
4 a n mR/hr.
Busses Enerci:ed (/)
5 1 m mR/hr.
6 3 n mR/hr.
/10400V 7
, n mR/hr.
10300
/
8
' a n mR/hr.
10500 V 10600 [
9 oc mR/hr.
/
10
-~
,n mR/hr.
A DC r B OC [
11
,e mR/hr.
12
-- 3 n mR/hr.
Main Steam Line Radiation 13
- mR/hr.
e n Monitors 1.6 R/hr.
14
~c n mR/hr.
15
-~- mR/hr.
Carnents:
16
~, n mR/hr.
17
- mR/hr.
an RCIC INCP.
18
'~ 10 mR/hr.
19 10 mR/hr.
20 10 mR/hr.
21 1.0 mR/hr.
22 2.0 mR/hr.
h 5.0 r.
j Rx POWER = 100%
l ADS and SRV manual operation 25 8_O mR/hr.
me, u 4 -no v e_4 sr.
26 9.O mR/hr.
27 20 mR/hr.
28 9.0 mR/hr.
29 30 mR/hr.
30 900 mR/hr.
iieteorology Windsoeed Direction Brooknaven Class l
.s l
1
PAGE, ja FITZPAT.%iCK SCENARIO - August 11, 1982 MESSAGE ANTICIPATED RESULTS AND EMERGENCY TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COMMENTS CLASSIFICAiION 0800 8
Control Reactor scram occurs from MSIV Carry out actions of AOP-1 Unusual day J Room and closure generated by high steam Reactor Scram and SP-3, Event Radwaste tunnel temperatures.
Relief Main Steam Break.
Continued Operator valves open to limit pressure Isolation of Control Room HPCI auto initiates on low-and Turbine Building Upgrade to level signals and restores Ventilation Systems Order Alert may level to normal.
a restricted area evacua-occur any-tion or Turbine Building time between evacuation from this time 800 and 825 until exercises end.
based upon 1.
If SRV manual opera-free play tion is attempted to information blow down vessel, exchange activation does not between the occur.
Shift Super-2.
When Turbine Building visor and ventilation isolation the Control is attempted, Room Referee isolation occurs concerning except one Steam Tunnel conditions Exhaust Damper remains in the steam open.
tunnel or based upon the SS dis-cretion that TSC activation is necessary.
Pags 8b MESSAGE NO. 8
s TIME:
0800 ON DAY l ISSUED TO THE CONTROL ROOM Main Steam Tunnel Temperatures TE-121A through D have increased to 200*F initiating Main Steam Isolation Valve automatic closure. All eight MSIV's indicate full closed.
An automatic reactor scram has occurred as the result of MSIV closure.
During the transient, vessel pressure increased to about 1100 psig.
Safety Relief Valves opened to relieve pressure and are now continuing to
(
lift periodically.
Vessel level decreased to 123 inches.
HPCI has automatically initiated and is restoring level.
The recirculation pumps have tripped as the result of low level.
Reactor Building Ventilation is isolated and the Standby Gas Treatment System has initiated.
Primary containment isolation has occurred.
1 All control rods are fully inserted and reactor power is dropping rapidly through the intermediate range.
The Reactor Feed Pumps have tripped and condenser vacuum is gone.
The Main Turbine has tripped.
Successful fast transfer of buses to the k_/
reserve 115 KV source has occurred.
4 n
m
.T!PE 0800 PLANT STATUS SHEET SHEET NO. 8c Day 1 EDG Starts VIssel Level Transient inches A Running Loaded / Running Unioaded. Standby '005 C Running Loaded / Running Unloaded, Standby l '005 Level Trend 8 Running Loaded / Running Unloadecs StancbyLOOS V:ssel PressureTransient osig Pressure Trend 115KV Reserve Po yw Available
- 3 LHH
- Yes, No Ves3a1 Ecttom
- 4 RtP gNo Orain Temp.
Transient,F Tran-Building Vent Rad Monitors O
Cleanuo Inlet Temp. sient F
Rx. Building 150 CPM Refuel Floor 160 CPM Main Steam pressure o psig Turbine Building 400 CPM Radwaste
.10 CPM Drywell Pressure 16_s osia Control Room
- .00 CPM Drywell Ave. Temp. 171 F
Stack Rad Monitor 3000+ Cps Torus Ave. Water 0
Temperature 79 A F
High Range Effluent Monitors Stack.
A O _7 B
O.3 mR/hr.
Torut pressure ta 7 osia Turbine Bldg. A O.6 B
mR/hr.
Radweste Oldg. A O _1 B
O_5 mR/hr.
Torus Level Tran=4an*
inches Containment High Range 5 Monitor A B 64 R/hr.
Drywell Floor Leak Rate 1 n7 opm Area Radiation Monitors 1
mR/hr.
Drywell Equipment 2
mR/hr.
(
Leak rate
, cc opn 3
mR/hr.
~
4 mR/hr.
Busses Enerq1:ed (/)
5 mR/hr.
/
6 mR/hr.
10300 J 10400 k,.
7 mR/hr.
8 mR/hr.
10500 E'10600 w" 9
mR/hr.
10 mR/hr.
4 A DC Y B OC 8' 11 mR/hr.
12 mR/hr.
Main Steam Line Radiation 13 mR/hr.
Monitors 0.1 R/hr.
14 mR/hr.
15 mR/hr.
Coments:
16 mR/hr.
17 mR/hr.
RCIC TMOP_
18 mR/hr.
19 mR/hr.
ny powFn 0%
20 mR/hr.
l 21 mR/hr.
ans nna spv mamini nno va t-i nn 22 mR/hr.
23 mR/hr.
may be inoperative.
24 mR/hr.
25 mR/hr.
26 mR/hr.
27 mR/hr.
ersemne ecenuurn 28 mR/hr.
29 mR/hr.
Mepp runren-r c+nern 30 mR/hr.
Cantzi: rent Irelated fieteorology Windsceed Direction l
Brooknaven Class 1
1 l
PAGE
~0a
,s
(
J FITZPATRICK SCENARIO - August 11, 1982 MESSAGE ANTICIPATED RESULTS AND
. EMERGENCY TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COMMENTS CLASSIFICATION 0815 9
Control Update of plant parameters 1.
Continue post-scram ALERT day ]
Room following the MSlV isolation procedures. Restore Plant and Reactor Scram. Expected isolated systems j
Status parameters for this transient per AOP-15, Recovery l
Sheet exist.
from isolations.
2 issued to 2.
Upgrade to the Alert TSC if classification when activated.
reports from Radwaste indicate continued leakage from the steam
- tunnel,
- b. TB evacuation may be initiated.
NOTE:
1.
S he Control Room referee will initiate the Alert Classificat Lon if the Shift Supervisor has i
- - ot done so by 0825.
2.
] f personne.. are dispatc. ied to investigate the problem with
- .lua open steam tunnel exhaust c amper, the:r will return in 10 minutes with Message No. 9, S'applement 1.
1 6
Paga 9b MESSAGE NO. 9
,m TIME:
0815 ON DAY 1 ISSUED TO THE CONTROL ROOM Plant parameters are given on the following plant status sheet.
Steam Tunnel Temperature Detectors TE-121A through D have decreased to about 180*F and are continuing on a downward trend. MSIV isolation signals have cleared.
l C
i l
- i l
,)
i
a t
TIME 0815 PLAtiT STATUS SHEET SHEET NO.
9c Day 1 EDG Starts Vessel Level 225 inches A Running Loaded / Running Unioadeds StandbyLOCS C Running Loaded / Running Unioadecs Stanc3y, 005 Level Trend Stable B Running Loaded / Running Unloadeds Staioby, 005 V:ssel Pressure 970 osig Pressure Trend decreasing 115KV Reserve P gg Available 2
- 3 LHH lyes fio V7,ssel Sottom f4 Te1P Yei'No 0
~
Orain Temo.
490' F
Building Vent Rad Monitors 0
Cleanup Inlet Temp. 525 F
Rx. Butiding 150 CPM Refuel Floor 180 CPM Main Steam Pressure O esig Turbine Building 400 CPM Radwaste
- .10 CPM Drywell Pressure 16.5 osia Control Room
- .00 CPM 0
Drywell Ave. Temp. 124 F
Stack Rad Monitor Torus Ave. Water Cps 0
Temperature 74 1 F
High Range Effluent Honitors Stack.
A O.6 B
mR/hr.
A B
mR/hr.
Torus Pressure 14 7 osia Turbine Bldg.
Radweste Oldg. A O_3 B
O_S mR/hr.
Torus Level
_1 n,
inches Drywell Floor Leak Rate 1 o7 aps Area Radiation Monitors 1
mR/hr.
Drywell Equipment 2
mR/hr.
Leat rate 3 cc opa 3
mil /hr.
~--
4 mR/hr.
Busses Energized (/)
5 mR/hr.
6 mR/hr.
f 10300 V 10400 [
7 mR/hr.
8 mR/hr.
10500 [10600
- f 9
mR/hr.
10 mR/hr.
AOC [BDC /
11 mR/hr.
12 mR/hr.
Main Steam Line Radiatten 13 mR/hr.
Monitors 0.1 R/hr.
14 mR/hr.
15 mR/hr.
Coments:
16 mR/hr.
17 mR/hr.
RCIC INOP.
18 mR/hr.
19 mR/hr.
20 mR/hr.
21 mR/hr.
22 mR/hr.
h Rx Power 0%
ADS and SRV manual operation 25 mR/hr.
i amu ha 4 e nmi-s+-4v.
26 mR/hr.
27 mR/hr.
28 mR/hr.
29 mR/hr.
30 mR/hr.
fieteorology Windspeed Direction
.l Brooknaven Class J
-,.n..--
, -. - -,,, -,,, ~
Piga 9d Message No. 9, Supplement I issued to personnel investigating the open steam tunnel exhaust damper.
Gravity damper GD - is jammed in the OPEN position.
Attempts to move the damper appear futile.
i e
FITZPATRICK SCENARIO - August 11, 1982 MESSAGE ANTICIPATED RESULTS AND EMERGENCY TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COMMENTS CLASSIFICATION 0815 10 Radwaste Data given to Radwaste Operator 1.
Calculate leakage rate.
ALERT day ]
Control Rooin which will indicate continuing 2.
Report results to leakage from the Steam Tunnel Control Room.
into the southern Turbine Building Floor Sump.
(50 gpm leak rate)
NOTE:
Referee to make report to the Control Room if not made by Radwas :e Operator before 0820.
s a
9 9
I Pcga 10b MESSAGE NO. 10 n
i TIME:
0815 ON DAY 1 ISSUED TO THE RADWASTE CONTROL ROOM Turbine Building Floor Drain Sump Pump P-3A just completed a pump-out that took 20 minutes from the time the pump started until it stopped.
1 1
t i
i
PAGE _ lin i
)
FITZPATRICK SCENARIO - August 11, 1982 MESSAGE ANTICIPATED RESULTS AND EMERGENCY TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COMMENTS CLASSIFICATION 0830 11 Control Plant conditions stabelized 1.
TSC and OSC may be ALERT day 3 Room following,the scram.
A manned and operational.
70*F/hr. cool-down rate is 2.
Continued investiga-Plant established.
Steam tunnel tion of leakage source Status parameters given to assist should be underway.
Sheet in source identification.
3.
Post-scram coolant issued sampling may be to TSC.
initiated.
4 R
i i
Paga lib r
. MESSAGE NO. 11 TIME:
0830 ON DAY l ISSUED TO THE CONTROL ROOM i
Plant conditions are as listed on Plant Status Sheet. There has been established a stable 70'F/hr. cooldown rate using HPCI.
Steam line temperature detectors continue to show decreasing tunne; temperatures. Detectors TE-121A through D are at 157"F.
i t
( -
i l
l e
I i
l f
f I
I h
~-
I i
t
TIME 0830 PLANT STATUS SHEET SHEET NO.11c Day 1 EDG Starts V:ssel Level 225 inches A Running Loaded / Running Unloadeds Standby; 005 C Running Loaded / Running Unioadeds Standby; 005 Level Trend Stable B Running Loaded / Running Unioadeds Standbys 005 0 Running Loaded / Running Unioadeds Standbys 005 V:ssel Pressure 830 osig Pressure Trend decreasing 115KV Reserve Pggg-Available
- 3 LNH lyes 'No V:ssel Bottom
- 4 NMP Ves 'No 0
Orain Temp.
473 F
BJilding Vent Rad Monitors Cleanup Inlet Temp.508 "F
Rx. Building 150 CpH Refuel Floor itsu CPM Main Steam Pressure o psig Turbine Building 410 CPM Radwaste llo CPM Drywell Pressure 16_5 osia Control Room 100 CPM Off-Gas Rad Monitor D /S mR/hr.
0
~
Drywell Ave. Temp. 199 F
Stack Rad Monitor Cps Torus Ave. Water 0
Temperature 76 F
High Range Effluent Monitors Stack A
B Torus Pressure la 7 osia Turbine Bldg. A O.6 B
-mR/hr.
mR/hr.
Radweste Oldg. A o. 3 B
0.5 mR/hr.
Torus Level n oc:
inches Containment High Range 6 Monitor A b
R/hr.
Drywell Floor Leak Rate 3 on opm Area Radiation Monitors
-'~
1 mR/hr.
Drywell Equipment 2
mR/hr.
(
Leak rate
, en opm 3
mR/hr.
~'-'
4 mR/hr.
Eusses Enero12ed (/)
5 mPs/br.
6 "rJ/h.
13300 [10400 /.
7
-mR/hr, 4
/
8 mR/hr.
10500 5 10600 /
9
~~
efdhr.
j j
10 mR/hr.
A OC f B OC j 11
'"" ~
P/hr.
m 12 mR/hr.
~ R/hr.
Main Steam Line Radiation 13 m
~~
Monitors R/hr.
14 M/hr.
15 m4/hr.
Connents:
15 mR/br.
17 mP/h.
18 mR/hr.
m.
w inus.
19 mR/hr.
20 mR/hr.
21 mR/hr.
22 mR/hr.
may be inoperative."F"'"""
23 mR/hr.
24 mR/hr.
25 mR/hr.
26 mR/hr.
27 mR/hr.
28 mR/hr.
29 mR/hr.
30 mR/hr.
Meteorology Windspeed Direction I
Brooknaven Class l
.~.
PAGE m
_ " 2a
(
/
FITZPATRICK SCENARIO - August 11, 1982 MESSAGE ANTICIPATED RESULTS AND EMERGENCY TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS C0t#4ENTS CLASSIFICATION 0845 12 control Plant parameters updated.
1.
ALERT day ]
Room Cool-down continues of 70*F/hr.
2.
Continued investigatior of source of leakage.
Plant Status Sheet issued to TSC.
l l
l
.~
4
)
Paga 12b MESSAGE NO. 12
.l I
i TIME:
0845 ON DAY.1-j ISSUED TO THE CONTROL ROOM i
Plant cooldown continues at 70*F/hr. using HPCI Steam Tunnel Temperature Detectors TE-121A through D are at 145'F and decreasing.
f j-e i
i i
t i
(
5 i
i I
i
_/
m-.
}
TIME 0845 PLANT STATUS SHEET SHEET NO. 12c
,-m Day 1 EDG Starts V:ssel Level 225 inches A Running Loaded / Running Unioadeddtandby; 005 C Running Leaded / Running Unioadeds Stanabys005 Level Trend Stable B Running Loaded / Running Unloaded / Standby /OOS 0 Running Loaded / Running Unioaded/ Standby /005
-Vessel Pressure 710 osig Pressure Trend decreasing 115KV Reserve Pgag Available
- 3 LHH
'Yes 'No V4ssel Bottom
- 4 MP Ym 'No Crain Temp.
456
,F Building Vent Rad Monitors 0
C1tanup Inlet Temp. 490 F
Rx. Building 150 CPM Refual Floor 180 CPM Main Steam Pressure o osig Turbine Building 400 CPM Radweste
.10 CPM Drywell Pressure 16 6 osia Control Room
- .00 CPM Off-Gas Rad Monitor D/S mR/hr.
Drywell Ave. Temp. 199
'F Stack Rad Monitor Cps Torus Ave. Water O
Temperature 7n F
High Range Effluent Monitors Stack A
B mR/hr.
Torus Pressure 1a 9 osia Turbine Bldg. A 0. 6 B
mR/hr.
Radweste Oldg. A n 1 B
o_s mR/hr.
Torus Level
_n o c:
inches Containment High Range 6 Monitor A B
R/hr.
Drywell Floor Leak Rate 3 on opm Area Radiation Monitors 1
mR/hr.
(.
Drywell Equipment 2
mR/hr.
Leak rate
, en opn 3
mR/hr.
4 mR/hr.
Susses Energind (/)
5 mR/hr.
6 mR/hr.
s 10300 Y 10400 V 7
mR/hr.
8 mR/nr.
10500 V 10600 /
9 mR/hr.
p 10 mR/hr.
12 mR/hr.
Main Steam Line Radiation 13 nR/hr.
M;nitors R/hr.
14 mR/hr.
15 mR/hr.
Coments:
16 mR/hr.
17 mR/hr.
nrTr TMno.
18 mR/hr.
19 mR/hr.
20 mR/hr.
21 mR/hr.
22 mR/hr.
23 mR/hr.
ADS and SRV manual operation 24 mR/hr.
25 mR/hr.
4 -..
4,m 26 mR/hr.
---.., u 27 mR/hr.
28 mR/hr.
29 mR/hr.
30 mR/hr.
Meteorology Windspeed l
Direction Brooknaven Class l
PAGE
'3a FITZPATRICK SCENARIO - August 11, 1982 MESSAGE ANTICIPATED RESULTS AND EMERGENCY TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COMMENTS CLASSIFICATION 0845 13 Radwaste Data given to Radwaste Operator 1.
Calculate leak rate.
ALERT day 3 Control which will indicate continuing 2.
Report results to Room leakage from the Steam Tunnel Control Room.
into the suthern Turbine Building Floor Sump.
(50 gpm leak rate) e I
Paga 13b l
MESSAGE NO. 13 e
i TIME:
0845 ON DAY l
/
b f
i ISSUED TO RADWASTE CONTROL ROOM i
}
The south Turbine Building Floor Sump Pump started at 0835 and is still.
pumping.
k e
4 1
i
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i i
f k
1 1
I f
I i
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i i
J
?.
L'
,,, - ~_
. -,... - _ _ -.,, _, _., _ _,. - _, _ ~ -,
,..----,-m..-..
,.,---m._--
L'
li!
e NO YI a
CT 4
NA J)
EC GI RF EI MS T
E ES R
G A
E A
L L
P C
A D
NA S
TL US ST EN RE 49 Dt E0 TC AP I
C 2
I 8
T 9
N 1
A 1
1 s
t e
s u
u S
n g
T i
u N
.tn A
E T
d o N
ec O
t O
C a.
I dr R
E ph A
G u/
N A
F E
S s*
C S
r0 S
E e7 M
t K
et C
F ma I
O a
R rn T
Y aw A
R po P
A d
Z M
t -
T M
nl I
U ao F
S l o PC OT D
l E
o s
dC U
r t ut eS S
t m nt euT S
no aaes I
oo l th so CR PSSit E
GR 4
AE 1
]
E 0
M 0 y I
9 a T
0d j
j!
J
Paga 14b g
MESSAGE NO. 14 4
TIME:
0900 ON DAY 1 ISSUED TO THE CONTROL ROOM
' Plant cooldown continues at 70*F/hr. usiig HPCI Steam Tunnel Temperature Detectors TE-121A through D are at 138"F and decreasing.
1 l
1 4
k
)
I 4
I f
I r
.-._m._
..-,-_,..,,.-..---,m
. ~.. -. -.
_---_..-._...r,
TIME 0900 PLANT STATUS SHEET SHEET NO. 14c Day 1 EDG Starts V:ssel Level 225 inches A Running Loaded / Running Unloaded /S tandby/OOS C Running Loaded / Running Unloadeo/S tandby/005 L vel Trend Stable B Running Loaded / Running Unloaded / Stanoby/005 V:ssel Pressure 610
__psig Pressure Trend decreasing 115KV Reserve Pogge Available
~
Orain Temp.
440 F
Building Vent Rad Monitors 0
Cleanup Inlet Temp. 472 F
Rx. Building 150 CPM Refuel Floor 180 CPM Main Steam Pressure o ostg Turbine Building 390 CPM Radwaste
..10 CPM Drywell Pressure 16 ci asia Control Room
- .00 CPM Off-Gas Rad Monitor D/S mR/hr.
0 Drywell Ave. Temp. 191 F
Stack Red Monitor Cps Torus Ave. Water 0
Temperature 7A F
High Range Effluent Monitors Stack.
A B
mR/hr.
Torus Pressure ta7 osia Turbine Bldg. A O_6 B
mR/hr.
Radwaste Oldg. A n.1 B
0.5 mR/hr.
Torus Level
_n on inches Containment High Range 6 Monitor A B
R/hr.
Drywell Floor Leak Rate
, on opm Area Radiation Monitors 1
mR/hr.
0 ywell Equipment 2
mR/hr.
Leak rate
, en opm 3
mR/hr.
-'-~
4 mR/hr.
Busses Energited (/)
mR/hr.
6 mR/hr.
10200 s' 11400 e 7
-mR/hr.
mR/hr.
8 10500 i*10600 '
9 mR/hr.
10 mR/hr.
A OC ' B DC 4 11 mR/hr.
12 mR/hr.
Main Steam L!re Radiai;:rn 13 mR/hr.
Monitors R/hr.
14 mR/hr.
15 mR/hr.
Cane".ts :
16 mR/hr.
17 mR/hr.
RCTC INOP.
IB mR/hr.
19 mR/hr.
20 mR/hr.
21 mR/hr.
nns and ARv mannat nna va +-i nn 22 mR/hr.
may be inoperative.
23 mR/hr.
24 mR/hr.
25 mR/hr.
26 mR/hr.
27 mR/hr.
2B mR/hr.
29 mR/hr.
30 mR/hr.
Meteorology Windsceed Direction Brooknaven Class v
NO YI a
CT 5
NA 1
EC l
GI RF EI MS T
E ES R
G A
E A
L L
P C
A D
e N
t A
ao rt S
T ks L
at US el m ST l uo EN so RE eeR t r DM a
cot P
l pn I
aeo C
CRC 2
I 8
T 9
N 1
A 12 1
e 1
r t
og s
t n u
S ait g
T rua u
N en A
E pil T
Ot e s
N nn O
eon O
C t cu I
s t
R E
ae A
G wt m N
A d aa E
S ace C
S Rit S
E dS M
on K
ti m C
F o
I O
nl r R
elf T
Y vi A
R i we P
A g
gm Z
M h ap T
M ack g I
U ti a F
S ah e0 D wl5 OT e
D tl E
so U
ar S
wt m S
d no I
aoo RCR E
GR 5
AE 1
1 E
0 M
0 y I
9 a T
0d
F' Pcga-15b MESSAGE NO. 15
. - m.
' 7 P
TIME:
0900 ON DAY l i
ISSUED TO THE RADWASTE CONTROL ROOM t
t F
The south Turbine Building Floor Drain Sump Pump, P-3A, stopped pumping at 0855.
l t
i f
i I
L t
v.
L I
i
NO YI a
CT 6)
NA 1
EC GI RF EI MS T
E ES R
G A
E A
L L
P C
A D
NA S
P I
C 2
I 8
T 9
N 1
A I
1 1
t r
s h
u S
/
g T
F u
N m' A E
0 T
d7 N
e O
tt O
C aa I
d R
E ps A
G ue N
A u
E S
sn C
S ri S
E et M
t n K
eo C
F mc I
O a
R rn T
Y aw A
R P o P
A d
Z M
t -
T M
nl I
U ao F
S l o PC OT D
l E
o s
dC U
r t ut eS S
t m nt euT S
no aaes I
oo lth so CR PSSit E
GR 6
AE 1
(
]
E 5
M 1 y I
9 a T
0d
_.. =,
. _ _ = -
Pags 16b MESSAGE NO. 16 A
TIME:
0915 ON DAY 1 J
i ISSUED TO THE CONTROL ROOM Plant cooldown continues at 70'F/hr. using HPCI Steam Tunnel Detectors-l TE-121A through D are at 131*F and decreasing.
6 f
4 s
i i
3 I
i I
P G
I e
P i.,_ _-. -. - - -....,-,._ -,._,.-_.-. -. -...-........
TIME 0915 PLAfiT STATUS SHEET SHEET NO. 16c
(
Day 1 EDG Starts Vissel Level 225 inches A Running Loaded / Running Unloaded /StandbyLOOS 4
C Running Loaded /Rur.ning Unloaded / Standby, 005 Level Trend Stable B Running Loaded /Rt.nning Unloaded /S tancbys 005 0 Running Loaded / Running Unloaded / Standby, 005 Vassel Pressure 510 osig Pressure Trend decreasing 11SKV Reserve Pgg Available
- 3 LHH Yes, No Vessel Gottom
- 4 i#1P Yg No Orain Temp.
422 "F
Buf1 ding Vent Rad Monitors Cleanup Inlet Temp. 455 "F
Rx. Building 150 CPM Refuel Floor 180 CPM Main Steam Pressure O esig Turbine Building 380 CPM Radwests Drywell Pressure 16.5 osia Control Room
..10 CPM
- .00 CPM Off-Gas Rad Monitor D/S mR/hr.
O Drywell Ave. Temp. 17n F
Stack Rad Monitor Cps Torus Ave. Water Temperature 77 F
High Range Effluent Monitors Stack A
B mR/hr.
Torus Pressure la 7 osia Turbine Bldg. A O.6 B
mR/hr.
Radweste Oldg. A n 1 B o9 mR/hr.
Torus Level
_n on inches Containment High Range 6 Monitor A B
R/hr.
Drywell Floor Leak Rate
, u opm Area Radiation Monitors
-~ -
1 mR/hr.
Drywell Equipment 2
mR/hr.
Leak rate 1, 4_ e
_qps 3
mR/hr.
4 mR/hr.
Bu ges Ene-gized (/)
5 mR/hr.
6 rRihr.
10300 # 10400 W 7
mR/hr.
_/'
8 mR/hr.
10500 ( 10e00 v 9
mR/hr.
A OC (B OC t'~
10 mR/hr.
11 mR/hr.
12 mR/hr.
Main Stea'a Lirie Radiation 13 mR/hr.
Ms.11 tors R/hr.
14 mR/hr.
15 mR/hr.
Comments:
16 mR/hr.
17 mR/hr.
RCIC TMOP.
18 mR/hr.
19 m2/hr.
20 mR/hr.
21 mR/hr.
4DV ma ntia l nno rn t-i nn and ads 22 mR/hr.
may be inoperative.
23 mR/hr.
24 mR/hr.
I 25 mR/hr.
26 mR/hr.
27 mR/hr.
28 mR/hr.
29 mR/hr.
30 mR/hr.
lieteorology Windspeed Direction Brooxnaven Class V
PAGE 47a s
l J
FITZPATRICK SCENARIO - August 11, 1982 3
MESSAGE ANTICIPATED RESULTS AND EMERGENCY TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COMENTS CLASSIFICATION 0915 17 Radwaste Data given to Radwaste Operator 1.
Calculate leak rate.
ALERT day J Control which will indicate continuing 2.
Report results to Room leakage from Steam Tunnel at Control Room.
50 gpm.
S e
e
+
.___..m._.
l pig 3 17b
,i 4
MESSAGE NO. 17 i
4 m
TIME:
0915 ON DAY 1
}
ISSUED TO THE RADWASTE CONTROL ROOM i
i The south Turbine Building Floor Drain Sump Pump, P-3A, just started again.
J d
.i f
1 l
I I
4 i
i I
i a
I
[
f 1.-- -
PAGE
.laa
'l i_'
, )
FITZPATRICK.SCENAR10 - August-11, 1982 MESSAGE ANTICIPATED RESULTS AND EMERGENCY TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COMMENTS CLASSIFICATION
]
0930 18 Control The B Feedwater Line fails 1.
Shutdown condensate if SITE AREA day ]
Room catastrophically.
HPCI system operating to prevent EMERGENCY isolates during the transient.
flooding Turbine Plant The HPCI in-board isolation building.
Status valve breaker trips Thermal 2.
Reclassify the emer-Sheet overloads after reaching the gency condition to issued full closed position. If the SITE AREA EMERGENCY-to TSC.
condensate system remains in based upon the loss service, it begins pumping con-of all means of denser hotwell water through depressurizing vessel.
the break to the Turbine 3.
Restricted Area j
Building.
Evacuation may be.
i initiated.
4.
Activate EOF.
NOTE:
4 1.
J f operatorn or maintena: ice personnel are dispatched to investigate the breaker problem s ith the in~ board IIPCI s ;eam supply valve, they will report back in about 10 minutes with j
nessage No.
18, supplement 1.
2.
I f operatorn are dispatclied to measure the water level in the condenser bay, they will report lack in 5 m~nutes with message No. 18, supplement 2.
I I
F i
P;gn 18b O
MESSAGE NO. 18 TIME:
0930 ON DAY 1 ISSUED TO-THE CONTROL ROOM.
~
Another transient is in progress. The HPCI turbine just tripped and isolated due to high steam line flow signals.
The HPCI steam line isolation valves close. When the in-board isolation valves reaches the full closed position, the green indicator lamp near the control switch remains ON for a moment and then goes out also, the graph display indicator lamp shows the valve full closed.
(,'
Steam Tunnel Detectors TE-121A through D are at 125'F and increasing again.
HPCI area temperature detectors indicate normal.
i l
l C.;
i
'i
Paga 18e p, '
, m.
Message No. 18, Supplement issue to Control Room if condensate pumps are operating at 0930.on day.1.
Hotwell level is decreasing rapidly. The condensate demineralizer trouble annunciator just alarmed.
(
=
l
b TIME 0930 PLAfiT STATUS SHEET SHEET NO. 18d
,m Day 1 EDG Starts V:ssel Level 227 inches A Running Loaded / Running Unicaced/ Standby /005 C Running Loaded / Running Unicadec/Stanoby; 005 Level Trend increasing B Running Loaded / Running Unicaded/S tandby; 005 0 Running Loaded / Running Unicaded/Stanabys 005 V:ssel Pressure 430 osig Pressure Trend increasing 115KV Reserve Available
- 3 LHH I
No V;ssel Bottom f4 194P Tes No 0
Orain Temp.
405 F
Building Vent Rad Monitors 0
Cleanup Inlet Temp. 438 F
Rx. Building 150 CPM Refuel Floor 180 CPM Main Steam pressure O c ig Tureine Building 400 CPM Radwaste
.10 CPM Drywell Pressure 16.5 osia Control Room
- .00 CPM O
Drywell Ave. Temp. 1?n F
Stack Rad Monitor Cps Torus Ave. Water 0
Temperature 77 F
High Range Effluent Monitors Stack A
B mR/hr.
Torus Pressure 1a 7 osia Turbine Bldg. A 0_6 B
mR/hr.
Radweste Oldg. A n t B o _ si mR/hr.
Torus Level
_n 7e inches Containment High Range 6 Monitor A B
R/hr.
(" Orywell Floor Leak Rate 1_on opm Area Radiation Mcnitors 1
mR/hr.
[..
Drywell Equipment 2
mR/hr.
Leak rate 3 ---
opm 3
mR/hr.
en 4
mR/hr.
Busses Enercized :/)
5 mR/hr.
6 mR/hr.
10300 *710400 *,
7 mR/hr.
/
8 mR/hr.
10600 k 9
mR/hr.
10500 10 mR/hr.
A DC =/B OC /
11 mR/hr.
12 mR/hr.
Main Steam Line Radiation 13 mR/hr.
Monitors R/hr.
14 mR/hr.
15 mR/hr.
Connents:
16 mR/hr.
17 mR/hr.
RCIC INOP_
18 mR/hr.
19 mR/hr.
MPCT inninend.
20 mR/hr.
(
21 mR/hr.
Anq nnd MRV mantia l nneration 22 mR/hr.
may be inoperative. ~
23 mR/hr.
24 mR/hr.
25 mR/hr.
26 mR/hr.
27 mR/hr.
28 mR/hr.
29 mR/hr.
i I
30 mR/hr.
l fieteorology Windspeed iV Direction I
Brocknaven Class J
i l
PIga 18a Message No. 18, Supplement.I I
1 issued to personnel dispatched to MCC -- to investimate problem with the breaker for the HPCI inbound steam supply valve.
The thermal overloads for 13-MOV-15, the HPCI inboard steam supply valve, were tripped. One phase cannot be reset.
l 9
f i
v l
l u'
~
Pr.g a 18f f
Message No. 18, Supplement II issued to personnel investigating Turbine Building condenser bay water level in the case where condensate remained in operation at 0930.
Water level is about 4 inches deep through the condenser bay.
9 w
.q'
PAGE 19m.-
-s
(.
~T[
FITZPATRICK SCENARIO - August 11, 1982 MESSAGE ANTICIPATED RESULTS AND EMERGENCY TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COMMENTS CLASSIFICATION 0930 19 Radwaste All four Turbine Building floor
- Place all Turbine SITE AREA day J Control drain sumps just started pumping Building floor drain EMERGENCY Room down.
Room is available for pumps in pull to lock.
25,000 gallons of water in the
- Notify Control Room IF_
-Waste Surge Tank. The Floor of conditions.
CONDENSATE Drain Collector and Waste IS IN Collector Tanks are full and OPERATION being processed. All water has
~
about 1.5 units conductivity.
e 9
Paga 19b f
i s
MESSAGE NO. 19 TIME:
0930 ON DAY l ISSUED TO THE RADWASTE CONTROL ROOM All four Turbine Building Floor Drain Sumps are pumping down now.
The waste collector and floor drain collector tanks are within 1000 gallons each of being full. The waste surge tank has 30,000 gallons in it.
Water in the floor drain collector and waste collector tanks has a conductivity of 1.50 units.
~%
(
f i
6
' %d 4
1
PAGE
. 20c,
,_s
(
(
/
J FITZPATRICK SCENARIO - August 11, 1982 MESSAGE ANTICIPATED RESULTS AND EMERGENCY TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COMMENTS CLASSIFICATION 0945 20 Control vessel level continues to in-1.
Restricted Area Evacua-SITE AREA day J Room crease. Vessel pressure is tion may be in progress EMERGENCY increasing. Turbine Building 2.
Repair crews may be Plant exhaust radiation levels are dispatched to replace Status increasing.
Steam tunnel overloads in the HPCI Sheet temperatures have increased in-board steam iso-issued to the MSIV isolation set point lation valve breaker.
to TSC.
again.
3.
Radiological Survey Teams may be dispatched.
NOTE:
If repair crews are dispatched to repair the faulty overload in
- he in-board HPCI steam supply valve, they 4
will report bacl; in 45 minutes with message No. 20, supplement 1 6
l
a Pago 20b MESSAGE NO. 20 TIME:
0945 ON DAY 1 ISSUED TO THE CONTROL ROOM Plant parameters are as shown on the P'. ant Status Sheet.
Steam Tunnel Temperature Detectors TE-121A through p have increased to 195'F and MSIV isolation signals are again present.
e a
i
r 0945 PLATIT STATUS SHEET SHEET NO. 20c
, TIME I '
Day 1 EDG Starts V;ssel Level 229 inenes A Running Leaded / Running Unloaded /Stancbys 005 C Running Leaded / Running Unloaded /Stancby; 005 Level Trend increasing 8 Running Loaded / Running Unloaded /Stanchyj005 V:ssel Pressure 520 osig Pressure Trend increasing 11SKV Reserve P s./flo2 r Available f3 LHH fes V;ssel Bottom
- 4 TNP Yes 'ilo 0
~
Orsin Temp.
424 F
Building Vent Rad Monitors 0
cleanuo Inlet Temp. 457 F
Rx. Building 150 CPM Refuel Floor leu CPM Main Steam Pressure 0 osig Turbine Building 1400 CPM Radweste 110 CPM Orywell Pressure 16.5 osia Control Room 100 CPM Off-Gas Rad Monitor D/S mR/hr.
0 Drywell Ave. Temp. 191 F
Stack Rad Monitor Cps Torus Ave. Water 0
Temperature 77 F
Hign Range Effluent Monitors Stack A
B mR/hr.
Torus Pressure 14 7 osia Turbine B1dg. A B
mR/hr.
Radwaste Oldg. A 0. 3 S
0.5 mR/hr.
Torus Level
-n_75 inches Containment High Range 5 Monitor A B
R/hr.
Drywell Floor Leak Rate 1 An opm Area Radiation Monitors 1
mR/hr.
Drywell Equipment 2
mR/hr.
Leak rate t en opm 3
mR/hr.
4 mR/hr.
Busses Energized (/)
5 mR/hr.
6 mR/hr.
.j 10300 v 10400 7
mR/hr.
/
8 mR/hr.
10500 ! 600 V 10 9
mR/hr.
/
10 mR/hr.
A DC r B OC %y 11 mR/hr.
12 mR/hr.
Main Steam Line Radiation 13 mR/hr.
Monitors R/hr.
14 mR/hr.
15 mR/hr.
Ccanents:
16 mR/hr.
17 mR/hr.
RCIC INOP.
18 mR/hr.
19 m2/hr.
23-MOV-15 innnerative.
20 mR/hr.
21 mR/hr.
SRV's innnerative for ramnte 22 mR/hr.
activation.
23 mR/hr.
24 mR/hr.
25 mR/hr.
26 mR/hr.
27 mR/hr.
28 mR/hr.
29 mR/hr.
30 mR/hr.
tieteorology Windspeed Direction Brookhaven Class V
a
Pcga 20d Message No. 20, Supplement I i
issued upon return of the repair crew sent to' work on the HPCI inboard steam supply valve breaker.
t i
j Prior to attempting repair of the faulty overload the motor was checked l
l for continuity and grounds. The results are as follows:
i Continuity A-B Okay B-C Open 1
C-A Open
(
Resistance to ground A
10 B
10 Q C
0 0 i
l i
i a
t I
PAGE 21a
([.
/
FITZPATRICK SCENARIO - August 11, 1982 MESSAGE ANTICIPATED RESULTS AND EMERGENCY TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COMMENTS CLASSIFICATION 0945 21 Radwaste Issued if the condensate system 1.
Calculate leak rate.
SITE AREA day ]
Control-was not operating at 0930.
2.
Report results to EMERGENCY Room Data given to Radwaste Operator Control Room.
which will indicate continuing leakage from Steam Tunnel at 50 gpm.
4
Paga 21b MESSAGE NO. 21
(
TIME:
0945 'JN DAY l ISSUED TO THE RADWASTE CONTROL ROOM IF THE CONDENSATE SYSTEM WAS NOT IN OPERATION AT 0930.
The southern Turbine Building Floor Drain Pump stopped pumping at 0935.
(
l 1
\\
l l
NO YI a
CT NA 2) 2 EC AY GI EC RF RN EI AE MS G
E ES ER G
A TE A
L I M P
C SE sm D
a N
e A
T S
y T
e.
L vd US re ST uh EN S c RE t
gd P
o I
l e C
ob 2
I i
8 T
d y 9
N aa 1
A R m 1
I 1
tsu S
g T
u N
A E
T N
s O
r O
C e
I t
R E
e A
G m
N A
a E
S r
C S
a S
E p
M K
t C
F n
I O
a R
l T
Y p
A R
P A
e Z
M t
T M
a I
U d
F S
p U
OT D
l E
o s
dC U
r t ut eS S
t m nt euT S
no aaes I
oo l th so CR PSSit E
GR 2
AE 2
]
E 0
(
M 0 y I
0 a T
1d
Paga 22b MESSAGE NO. 22
?
TIME:
1000 ON DAY l ISSUED TO THE CONTROL ROOM Plant parameters are given on the Plant Status Sheet. Vessel pressure continues increasing. Vessel level is increasing.
Steam Tunnel Detectors TE-121A through D indicate about 215'F.
I
/
1 I
t e
.i t
i k
- l.. -..
22c TIME 1000 PLANT STATUS SHEET SHEET NO.
/-
Day 1 EOG Starts V:ssel Level 232 inches A Running Loaded / Running Unloadeds Standby '005 C Running Loaded / Running Unloadeds Standby '005 Level Trend increasin9 8 Running Loaded / Running Unloadeds StandbyJ005 V:ssel Pressure 625 csig Pressure Trend increasin9 115KV Reserve P Available
- 3 LNH No Vessel Bottom
- 4 NMP No Drain Temp.
443 0F Building Vent Rad Monitors 0
C1canup Inlet Temp. 476 F
Rx. Building 150 cpg Refuel Floor lov CPM Main Steam Pressure 0 osig Turbine Building CPM CPM Radweste liv Drywell Pressure 16.5 osia Control Room Avu CPM Off-Gas Rad Monitor mR/hr.
Drywell Ave. Temp. 122 0F Stack Rad Monitor
_ Cps fore?.be. Water Temperature 77 0F High Range Effluent Monitors
' Stack A
B mR/hr.
Torus Pressure 14.7 osia Turbine Bldg. A B
mR/hr.
Radweste Gidg. A U.J B
U.3 mR/hr.
Torus Level
-0.75 inches Containment High Range 5 Monitor A B
R/hr.
Drywell Floor Leak Rate 1_80 opm Area Radiation Monitors 1
mR/hr.
Drywell Equipment 2
mR/hr.
(
Leak rate 1.50 apm 3
mR/hr.
4 mR/hr.
Busses Energized (/)
5 mR/hr.
6 mR/hr.
s 10300 2'10400 V 7
mR/hr.
8 mR/hr.
10500 ','10600 v.,,
9 mR/hr.
10 mR/hr.
A OC v B DC 11 mR/hr.
12 mR/hr.
Main Steam Line Radiation 13 mR/hr.
'4oni tors R/hr.
14 mR/hr.
15 mR/hr.
{
Cannsts:
16 mR/hr.
l 17 mR/hr.
(
18 mR/hr.
hCAC INCP. 14-MVV-13 19 mR/hr.
j inoperative.
20 mR/hr.
21 mR/hr.
SRV's inoperative for remote 22 mR/hr.
activation.
23 mR/hr.
24 mR/hr.
25 mR/hr.
26 mR/hr.
27 mR/hr.
~ R/hr.
28 i
m 29 mR/hr.
30 mR/hr.
Meteorology Windspeed Direction Brooknaven Class V
PAGE, 23a s
(,
- )
FITZPATRICK SCENARIO - August 11, 1982 i
MESSAGE ANTICIPATED RESULTS AND EMERGENCY TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COMMENTS CLASSIFICATION 1000 23 Radwaste Issued if the condensate system 1.
Calculate leak rate.
SITE AREA day 1 Control was not operating at 0930.
2.
Report results to EMERGENCY Room Data given to Radwaste Operator Control Room.
which will indicate continuing leakage from Steam Tunnel at 50 gpm.
l 1
)
Paga 23b MESSAGE NO. 23 i
TIME:
1000 ON DAY l ISSUED TO THE RADWASTE CONTROL ROOM I_F THE CONDENSATE SYSTEM WAS NOT IN OPERATION AT 0930.
The southern Turbine Building Floor Sump Pump started pumping again at 0955.
4 l
f I
l l
5 G
NO YI 3
CT 4
NA 2 )
EC AY GI EC RF RN EI AE MS G
E ES ER G
A TE A
L I M P
C SE D
NA STL US ST s
C 2
I 8
T 9
N 1
A 1
1 tsu S
g T
u N
A E
)
T
~-
N s
O r
(
O C
e I
t R
E e
A G
m N
A a
E S
r C
S a
S E
p M
K t
C F
n I
O a
R l
9 T
Y p
A R
P A
e Z
M t
T M
a I
U d
F S
p U
O T
D l
E o
s dC U
r t ut eS S
t m nt euT S
no aaes I
oo l th so CR PSSit E
GR 4
AE 2
]
E 5
,(
M 1 y I
0 a T
1 d
4 Paga 24b r
s.
i i
MESSAGE NO. 24
,'N.
TIME:
1015 ON DAY l i
ISSUED TO THE CONTROL ROOM i
I Plant parameters are given on Plant Status Sheet. Vessel pressure continues increasing. Vessel level is increasing.
Steam Tunnel Detectors TE-121A through D indicate abut 225'F.
i e
v l
l
~
24c TIME 1015 PLANT STAWS SHEET SHEET NO.
a%
4 Day 1 EDG Starts V:ssel Level 235 inches A Running Loaded / Running Unioaded/StandbyJ005 C Running Loaded / Running Unloaded /StandbyLOOS Level Trend increasing 8 Running Loaded / Running Unloaded /StandbyJ005 V:ssel Pressure 735 osig Pressure Trend increasing 115KV Reserve P g Available
- 3 LNH lyes, No V:ssel Bottom
- 4 HMP Yes, No 0
Drain Temp.
462 F
Building Vent Rad Monitors 0
Cleanuo Inlet Temp. 495 F
Rx. Building 150 CPM Refuel Floor lev CPM Main Steam Pressure O osig Turbine Building CPM Radwaste llu CPM Orywell Pressure 16.5 osia Control Room luu CPM Orywell Ave. Temp. 199 F
Stack Rad Monitor Cps Torus Ave. Water 0
Temperature 77 F
High Range Effluent Monitors Stack A
B mR/hr.
Torus Pressure la_7 osia Turbine Bldg. A 8
mR/hr.
Radweste Oldg. A O. 3 S
0.5 mR/hr.
Torus Level n 7m inches Containment High Range 6 Monitor A B
R/hr.
Orywell Floor Leak Rate 1 nn opm Area R.:41ation Monitors 1
mR/hr.
Drywell Equipment 2
mR/hr.
(
Leak rate 1 en opa 3
mR/hr.
4 mR/hr.
Busses Energized (/)
5 mR/t.r.
6 mR/hr.
10300 v 10400 V 7
mR/hr.
r
/>
8 mR/hr.
10500 V 10600 6" 9
mR/hr.
f' 10 mR/hr.
A OC 1 B DC 7 11 mR/hr.
12 mR/hr.
Main Steam Line Radiation 13 mR/hr.
Monitors R/hr.
14 mR/hr.
15 mR/hr.
Comments:
16 mR/hr.
17 mR/hr.
RCIC INOP.
18 mR/hr.
19 mR/hr.
23-Mov-15 inneerative.
20 mR/hr.
21 mR/hr.
RRV'c i nnno vrat i ve fnr ramnte 22 mR/hr.
I activation.
23 mR/hr.
I 24 mR/hr.
25 mR/hr.
26 mR/hr.
27 mR/hr.
28 mR/hr.
29 mR/hr.
30 mR/hr.
Meteorology Windspeed Direction Brookhaven Class b
PAGE 25m
('
FITZPATRICK SCENARIO - August 11, 1982 MESSAGE ANTICIPATED RESULTS AND EMERGENCY TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COMMENTS CLASSIFICATION 1015 25 Radwaste Issued if the condensate system 1.
Calculate leak rate.
SITE AREA day 1 Control was not operating at 0930.
2.
Report results to EMERGENCY Room Data given to Radwaste Operator Control Room.
which will' indicate continuing leakage from Steam Tunnel at 50 gpm.
e h
Paga 25b
,t MESSAGE NO. 25
,3
(
a i
TIME:
1015 ON DAY 1 ISSUED TO THE RATWASTE CONTROL ROOM I_F THE CONDENSATE SYSTEM WAS NOT IN F
4 I
l OPERATION AT 0930.
The south Turbine Building Floor Sump Pump stopped at 1015.
i h
l i
1 L
d t
V s
,._,__ _ m
e e
NO YI a
CT 6
NA
'2 EC AY GI EC RF RN EI AE MS G
E ES ER G
A TE A
L I M P
C SE D
NA S
TL US ST EN RE N
P I
C 2
I 8
T 9
N 1
A 1
1 tsu S
g T
u N
A E
T N
s O
r O
C e
I t
R E
e A
G m
N A
a E
S r
C S
a S
E p
M K
t C
F n
I O
a R
l T
Y p
A R
P A
e Z
M t
T M
a I
U d
F S
p U
O T
D l
E o
s dC U
r t ut eS S
t m nt euT S
no aaes I
oo l th so CR PSSit E
GR 6
AE 2
-(
E 0
M 3 y I
0 a T
1 d
Ptga 26b MESSAGE NO. 26 TIME:
1030 ON DAY l ISSUED TO THE CONTROL ROOM Vessel level and pressure continues to increase.
Steam Tunnel Detectors TE-l'21A through D' indicate 227'F.
+
TIME 1030 PLANT STATUS SHEET SHEET NO. 26:
i Day 1 EDG Starts V:ssel Level 237 inches A Running Loaded /Runing Unloaded /Standbys 005 C Running Loaded /Rurcing Unicaded/Standbys 005 Level Trend increasing B Running Loaded /Runn11g Unloaded / Standbys 005 Vsssel Pressure 860 osig j
Pressure Trend increasing 115KV Reserve Pgr Available
- 3 LNH Yes, No V:ssel Bottom d4 2P Yes. No 0
Drain Temp.
480 F
Building Vent Rad Monitors 0
Cleanup Inlet Temp. 513 F
Rx. Building 150 CPM Refuel Floor luu CPM Main Steam Pressure O osig Turbine Building CPM Radweste 110 CPM Orywell Pressure 16.5 osia Control Room 100 CPM O
Drywell Ave. Temp. 19t F
Stack Rad Monitor Cps Torus Ave. Water 0
Temperature 77 F
High Range Effluent Monitors Stack A
B mR/hr.
Torus Pressure 14 7 osia Turbine Bldg. A B
mR/hr.
Radweste Oldg. A O.3 S
0.5 mR/hr.
Torus Level
_n n inches Containment Hign Range 6 Monitor A B
R/hr.
Drywell Floor Leak Rate i on opm Area Radiation Mcnitors 1
mR/hr.
g - Drywell Equipment 2
mR/hr.
Leak rate
, en cpm 3
mR/hr.
-'~
4 mR/hr.
Busses Energized (/)
5 mR/hr.
6 mR/hr.
10300 V 10400 W 7
mR/hr.
B mR/hr.
i 10500 410600 V 9
mR/hr.
10 mR/hr.
A OC w B OC k 11 mR/hr.
12 mR/hr.
Main Steam Line Radiation 13 mR/hr.
Monitors R/hr.
14 mR/hr.
15 mR/hr.
Coments:
16 mR/hr.
17 mR/hr.
RCIC INOP.
18 mR/hr.
19 mR/hr.
23-Mov-15 4nneerative.
20 mR/hr.
21 mR/hr.
RnV'c innnavative fnr romnte 22 mR/hr.
~
operation.
23 mR/hr.
24 mR/hr.
25 mR/hr.
26 mR/hr.
27 mR/hr.
28 mR/hr.
29 mR/hr.
30 mR/hr.
tieteorology Windsoeed Direction Brooknaven Clt,s G.
NO YI a
CT 7
NA 2)
EC AY GI EC RF RN EI AE MS G
E ES ER G
A TE A
L I M P
C SE D
NA S
P I
C 2
I 8
T 9
N 1
A 1
1 tsu S
g T
u N
A E
,': O C
e T
N s
O r
I t
R E
e A
G m
N A
a E
S r
C S
a S
E p
M K
t C
F n
I O
a R
l T
Y p
A R
P A
e Z
M t
T M
a I
U d
F S
p U
OT D
l E
o s
dC U
r t ut eS S
t m nt euT S
no aaes I
oo l th so CR PSSit E
GR 7
AE 2
]
(
E 5
M 4 y I
0 a T
1d
-.... _ -......... -. ~. -..
1 i
Paga 27b.
MESSAGE NO. 27 i
TIME:
1045 ON DAY 1 l
2 ISSUED TO THE CONTROL ROOM i
Vessel level and pressure continue to increase. Steam Tunnel Detectors i
TE-121A through D indicated 235'F.
I 9
4
)
e i
i
(
a
TIME 1045 PLAT 4T STATUS SHEET SHEET NO. 27c Day 1 EDG Starts Vistel Level 238 inches A Running Loaded / Running Unicaded/StanobyJ005 C Running Loaded / Running Unioadeo/Stancbys 005 Level Trend increasing 8 Running Loaded / Running Unicaded/Stanabys 005 Vessel Pressure 1000 osig i
Pressure Trend increasing 115KV Reserve Power Available
- 3 LHH Efio V3ssel Bottom
- 4 IMP YgNo Orain Temp.
497
,F Building Vent Rad Monitors 0
Cleanup Inlet Temp.530 F
Rx. Butiding 150 CPM Refuel Floor 100 CPM Main Steam Pressure O osig Turbine Butiding CPM Radwaste 110 CPM Orywell Pressure 16_5 osia Control Room 100 CPM Off-Gas Rad Monitor D/3 mR/hr.
0 Drywell Ave. Temp. 1 71 F
Stack Rad Monitor Cps Torus Ave. Water 0
Temperature 77 F
High Range Effluent Monitors Stack A
B mR/hr.
Torus Pressure 1a_7 osia Turbine Bldg. A B
mR/hr.
Radweste Didg. A O _3 8
0.5 mR/hr.
Torus Level nn inches Containment High Range 5 Monitor A B
R/hr.
Drywell Floor Leak Rate 3 on opa Area Radiation Monitors
-~~~
1 mR/hr.
Drywell Equipment 2
mR/hr.
i Leak rate i c:n opm 3
mR/hr.
'-~
4 mP/hr.
Busses Energized (/)
5 mR/hr.
6 mR/hr.
10300 '/ 400 Y 7
mR/hr.
10 8
mR/hr.
10500'[10600Y.-
9 mR/hr.
10 mR/hr.
A OC r B OC V 11 mR/hr.
12 mR/hr.
Main Steam Line Radiation 13 mR/hr.
Monitors R/hr.
14 mR/hr.
15 mR/hr.
Cormnents:
16 mR/hr.
17 mR/hr.
RCIC INOP.
18 mR/hr.
19 mR/hr.
23-Mov-15 innnarative.
20 mR/hr.
21 mR/hr.
c:nv ' e 4nnnare4va fnv ramnta 22 mR/hr.
i operation'.
23 mR/hr.
I 24 mR/hr.
25 mR/hr.
26 mR/hr.
27 mR/hr.
28 mR/hr.
29 mR/hr.
l 30 mR/hr.
t I
tieteorology Windsoeed Direction Brookhaven Class V
PAGE. 28a l
(~
)
FITZPATRICK SCENARIO - August 11, 1982 MESSAGE ANTICIPATED RESULTS AND EMERGENCY TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COMMENTS CLASSIFICATION 1045 28 Radwaste Issued if the condensate system 1.
Calculate leak rate.
SITE AREA day 1 Control was not operating at 0930.
2.
Report results to EMERGENCY Room Data given to Radwaste Operator Control Room.
which will indicate continuing leakage from Steam Tunnel at 50 gpm.
O 4
!l k
. ~ -. -.
Pega 28b MESSAGE NO. 28 i
TIME:
1045 ON DAY l ISSUED TO THE RADWASTE CONTROL ROOM E CONDENSATE WAS NOT IN OPERATION AT 0930.
The south Turbine Building Floor Sump Pump started at 1035.
4 l
j
+
1 i
l I
1 i
i V
(,
PAGE 290
)
FITZPATRICK SCENARIO - August 11, 1982 MESSAGE ANTICIPATED RESULTS AND EMERGENCY TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COMENTS CLASSIFICATION 1100 29 Control Vessel pressure increased to the 1.
Upgrade classification GENERAL day ]
Room SRV set points.
Pressure surges to the General Emer-EMERGENCY caused by the SRV cycling have gency level.
Plant resulted in failure of the in-2.
Evacuate repair teams Status board feedwater check valve.
from the restricted Sheet Vessel level is dropping rapidly area.
issued to TSC.
a 9
9
Paga 29b MESSAGE NO. 29 TIME:
1100 ON DAY 1 ISSUED TO THE CONTROL ROOM Vessel pressure increased to the SRV lift point.
Relief valves cycled several times accompanied with normal level transients.
However, following the last valve opening, vessel level began decreasing at a rate of 6 inches / minute.
Steam Tunnel Temperature Detectors TE-121A through D indicate 255'F.
s l
t i
I L
I I
l l
r i
I
[
l TIME 1100 PLAf4T STATUS SHEET SHEET NO. 29c I
Day 1 EDG Starts V:ssel Level 240 inches A Running Loaded / Running Unloaded / Standby /005 C Running Loaded / Running Unloadeo/S tandby/005 Lsvel Trend decreasing B Running Loaded / Running Unloaded / Standby /005 0 Running Loaded / Running Unloaded / Standby /005 V:ssel Pressure 1100 osig Pressure Trend decreasing 115KV Reserve P er Available
- 3 LHH es 'llo Vassel Bottom
- 4 tiMP
'gNo a
Orain Temp.
505 F
Building Vent Rad Monitors 0
Cleanuo Inlet Temp. 540 F
Rx. Building 150 CPM Refuel Floor leo CPM Main Steam Pressure O osig Turbine Building CPM Radwaste
- .10 CPM Drywell Pressure 16.5 osia Control Room
- .00 CPM 0
Drywell Ave. Temp. 171 F
Stack Rad Monitor Cps Torus Ave. Water 0
Temperature 7n F
High Range Effluent Monitors Stack A
B mR/hr.
Torus Pressure la 7 osia Turbine Bldg. A B
mR/hr.
Radweste Oldg. A o _1 B o5 mR/hr.
Torus Level n na inches Containment High Range 5 Monitor A B
R/hr.
Drywell Floor Leak Rate 3 on opm Area Radiation Monitors 1
mR/hr.
Drywell Equipment 2
mR/hr.
[
Leak rate 3 en opm 3
mR/hr.
-~~-
4 mR/hr.
Busses Energized (/)
5 mR/hr.
6 mR/hr.
/
j 10300 < 10400 C 7
mR/hr.
/
p' 8
mR/hr.
10500 Y 10600 'S 9
mR/hr.
/
10 mR/hr.
11 mR/hr.
12 mR/hr.
Main Steam Line Radiation 13 mR/hr.
Monitors R/hr.
14 mR/hr.
15 m2/hr.
Cormients:
16 mR/hr.
17 mR/hr.
RCIC IMOP.
18 mR/hr.
19 mR/hr.
23-MOV-15 innnaraeive.
20 mR/hr.
21 mR/hr.
c:nv e c innnarmeiva fnr ramnte 22 mR/hr.
operation'.
23 mR/hr.
24 mR/hr.
25 mR/hr.
26 mR/hr.
27 mR/hr.
28 mR/hr.
29 mR/hr.
30 mR/hr.
Meteorology Windspeed Ofrection Brookhaven Class V
PAGE, 302
(?..
FITZPATRICK SCENARIO - August 11, 1982 MESSAGE ANTICIPATED RESULTS AND EMERGENCY TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COMMENTS CLASSIFICATION 1100 30 Radwaste Issued if the condensate system 1.
Secure Turbine Building GENERAL day 1 Control was not operating at 0930.
floor drain pumps.
EMERGENCY Room All four Turbine Building floor 2.
Notify Control Room.
drain pumps just started.
Pcgn 30b
. MESSAGE NO. 30
,m TIME:
1100 ON DAY l ISSUED TO THE RADWASTE CONTROL ROOM The south Turbine Building Floor Drain Pump stopped at 1055. At 1100 all four Turbine Building Floor Sumps started in quick succession.
~
NO YI a
CT 1
NA 3)
EC Y
~.
GI C
RF LN EI AE MS RG E
ES ER G
A NE A
L EM P
C GE tn e
e D
r m
N orn A
coo jr S
f ai T
omv L
n US ed e ST mn EN iao RE t
t N
d oe P
ecl I
rne C
P ur 2
I 8
T 9
N 1
A 1
1 1
tsu S
g T
u N
s A
E r
T e
N t
O e
O C
m I
a R
E r
A G
a N
A p
E S
C S
t S
E n
M a
K l
C F
p I
O R
f T
Y o
A R
P A
e Z
M t
T M
a I
U d
F S
p U
OT D
l E
o s
dC U
r t ut eS S
t m nt euT S
no aaes I
oo l th so CR PSSit E
GR 1
AE 3
E 0
(
M 1 y I
1 a T
1d 9
l,
Paga 31b' 9
MESSAGE NO. 31
,m TIME:
1110 ON DAY 1 l
ISSUED TO THE CONTROL ROOM a
Plant parameters are as indicated on the Plant Status Sheet.
Steam Tunnel Temperatures on TE-121A through D are 275'F and increasing, i
4 L
i
/
1 1
i I
r i
1 b
t w
,. ~.. + _ _.
.r...t.
TIME 1110.
PLANT STATUS SHEET SHEET NO. 31c f
Day 1 EDG Starts Vessel Level 180 inches A Running Loaded / Running Unicaced/ Standby '005 C Running Loaded / Running Unicadeo/ Standby '005 Level Trend decreasing B Running Loaded / Running Unicaded/S tandby,'005 V:ssel Pressure 870 osig Pressure Trend decreasing 115KV Reserve Power Available
- 3 LHH RNo Vessel Bottom f4 HMP YesLNo 0
Drain Temp.
475 F
Building Vent Rad Monitors Cleanuo Inlet Temp. 510
'F Rx. Building 150 CPM Refuel Floor 180 CPM Main Steam pressure O csig Turbine Building CPM Radwaste
.10 CPM Drywell Pressure 16.5 osia Control Room
- .00 CPM Off-Gas Rad Monitor D/S mR/hr.
Drywell Ave. Temp. 191 F
Stack Rad Monitor Cps Torus Ave. Water Temperature no F
High Range Effluent Monitors Stack A
B mR/hr.
Torus Pressure la 7 osia Turbine B1dg. A B
mR/hr.
Radweste Oldg. A O. 3 8
0.5 mR/hr.
Torus Level
_n n inches Containment High Range 5 Monitor A B
R/hr.
Drywell Floor Leak Rate
, on opm Area Radiation Monitors I
mR/hr.
Drywell Equipment 2
mR/hr.
{' Leak rate opm 3
mR/hr.
1 en 4
mR/hr.
Busses Energized (/)
5 mR/hr.
6 mR/hr.
10300 0400*7 7
mR/hr.
,/
/_
8 mR/hr.
10500 ( 10600 6 9
mR/hr.
10 mR/hr.
A DC./
- B DC 11 mR/hr.
12 mR/hr.
Main Steam Line Radiation 13 mR/hr.
Monitors R/hr.
14 mR/hr.
15 mR/hr.
Comments:
16 mR/hr.
17 mR/hr.
RCTC INOP_
18 mR/hr.
19 mR/hr.
23-MOV-15 inneerative.
20 mR/hr.
21 mR/hr.
RRV'e innnaraH va for romote 22 mR/hr.
~
operation.
23 mR/hr.
24 mR/hr.
i 25 mR/hr.
26 mR/hr.
27 mR/hr.
28 mR/hr.
29 mR/hr.
30 mR/hr.
I Meteorology Windspeed Direction Brookhaven Class U
9 e
i e
NO YI a
CT 2
NA 3)
EC Y
GI C
RF LN EI AE MS RG E
ES ER G
A NE A
L EM P
C GE D
NA S
P I
C 2
I 8
T 9
N 1
A 1
1
.y t
l s
d u
S i
g T
p u
N a
.E
.r
,'A T
s N
rg O
en O
C ti I
es R
E ma A
G ae N
A rr E
S ac C
S pe S
E d
M t
K nl C
F ae I
O l v R
pe T
Y l
A R
d P
A el Z
M t e T
M as I
U d s F
S pe UV O
T D
l E
o s
dC U
r t ut eS S
t m nt euT S
no aaes I
oo l th so CR PSSit EGR 2
AE 3
E 0
O
(
M 2 y I
1 a T
1 d
Paga 32b MESSAGE NO. 32
..m TIME:
1120 ON DAY 1 ISSUED TO THE CONTROL ROOM Plant parameters are as indicated on the Plant Status Sheet.
Steam Tunnel Detectors TE-121A through D indicate 290*F.
- s 1
i I
3 1
i i.
l 4
_ _ _ _,., -, ~ _ _,, _ _ _
TIME 1120 PLANT STATUS SHEET SHEET NO. 32c m
i Day 1 EOG Starts V:ssel Level 120 inches A Running Loaded / Running Unloaded /Standby /OOS C Running Loaded / Running Unioaded/ Standby /OOS Lsvel Trend decreasing B Running Loaded / Running Unloaded /S tandby/005 V:ssel Pressure 680 ostg Pressure Trend decreasing 115KV Reserve Power Available
- 3 LHH GNo V:ssel Bottom
- 4 NMP YesfNo 0
Orain Temp.
455 F
Building Vent Rad Monitors 0
C1canup Inlet Temp. 480 F
Rx. Building 150 cpm Refuel Floor itsu CPM Main Steam Pressure O osig Turbine Building CPM Radwaste 110 CPM Drywell Pressure 16.5 osia Control Room 100 CPM Drywell Ave. Temp. 121 F
Stack Rad Monitor CDs Torus Ave. Water 0
Temperature 79 F
High Range Effluent Monitors Stack.
A B
mR/hr.
Torus Pressure 14_7 osia Turbine Bldg. A B
mR/hr.
Radweste Oldg. A O. 3 B
O.5 mR/hr.
Torus Level
-n 7a inches Containment High Range 5 Monitor A B
R/hr.
Drywell Floor Leak Rate 1 nn opm Area Radiation Monitors 1
mR/hr.
Drywell Equipment
(
Leak rate 2
mR/hr.
1 en opa 3
mR/hr.
4 mR/hr.
Busses Energized (/)
5 mR/hr.
./
6 mR/hr.
10300 V 10400 W 7
mR/hr.
/
8 mR/hr.
10500 [10600 V 9
mR/hr.
/
/
10 mR/hr.
R/hr.
A OC v B OC <
11 m
12
'mR/hr.
Main Steam Line Radiation 13 C/hr.
l Monitors R/hr.
14 mR/ w.
l 15 mR/hr.
Caments:
16 mR/hr.
i 17 mR/hr.
RCIC IMOP.
18 mR/hr.
19 mR/hr.
23-MOV-15 inor>erative.
20 mR/hr.
21 mR/hr.
SRV8 s inneerative for remote 22 mR/hr.
~
operation.
23 mR/hr.
1 24 mR/hr.
25 mR/hr.
26 mR/hr.
27 mR/hr.
28 mR/hr.
i l
29 mR/hr.
30 mR/hr.
Meteorology Windsoeed Direction Brooknaven Class v
~
NO YI a
CT NA 3)
EC Y
J.
GI C
RF LN EI AE MS RG E
ES ER G
A NE A
L EM P
C GE D
NA S
TL US ST EN RE M DM EO TC AP I
C 2
I 8
T 9
N 1
A 1
1 9
y t
l s
d u
S i
g T
p u
N a
~
,' A E
.r T
s N
rg O
en O
C ti I
es R
E ma A
G ae N
A rr E
S ac C
S pe S
E d
.M t
K nl C
F ae I
O l v R
pe T
Y l
A R
d P
A el Z
M t e T
M as I
U d s F
l E
o s
dC U
r t ut eS S
t m nt euT S
no aaes I
oo l th so CR PSSit E
GR 3
AE 3
.(
E 0
M 3 y I
1 a T
1 d
I Paga 33b.
MESSAGE NO. 33 t.
. TIME:
1130 ON DAY 1 ISSUED TO THE CONTROL ROOM Plant parameters are as indicated on the Plant Status Sheet.
Steam Tunnel Temperatures on Detectors TE-121A through D are 280*F.
- G
TIME 1130 PLAT 1T STATUS SHEET SHEET NO. 33c-Day 1 EDG Starts V;ssel Level 60 incnes A Running Loaded / Running Unloaded /StandbyJ005 C Running Loaded / Running Unloaded /StandbyJ005 Level Trend decreasing B Running Loaded / Running Unicoded/StandbyJ005 V2ssel Pressure 580 osig Pressure Trend decreasing 115KV Reserve Power Available
- 3 LHH Tflo Vsssel Bottom
- 4 IMP Yes 'flo 0
Orain Temp.
430 F
Building Vent Rad Monitors 0
Cleanup Inlet Temp. 455 F
Rx. Building 150 CPM Refuel Floor leu cpm Main Steam Pressure 0 osig Turbine Butiding CPM Radwaste 11u CPM Drywell Pressure 16.5 osia Control Room luu CPM
~
Drywell Ave. Temp. 123 F
Stack Rad Monitor Cps Torus Ave. Water 0
Temperature 79 F
High Range Effluent Monitors Stack A
B mR/hr.
Torus Pressure 14.7 osia Turbine Bldg. A B
mR/hr.
Radweste Oldg. A 0. 3 8
0.5 mR/hr.
1 Torus Level
-n_7a inctus Containment High Range 6 Monitor A B
R/hr.
Drywell Floor Leak Rate 1 An opm Area Radiation Monitors 1
mR/hr.
Drywell Equipment 2
mR/hr.
C~Leakrate 1 cn opm 3
mR/hr.
4 mR/hr.
Busses Energized (/)
5 mR/hr.
./
/
6 mR/hr.
10300 Y 10400 'I 7
mR/hr.
j 8
mR/hr.
10500 V10600 V 9
mR/hr.
/
/
10 mR/hr.
B OC V 11 mR/hr.
A OC 12 mR/hr.
Main Steam Line Radiation 13 mR/hr.
Monitors R/hr.
14 mR/hr.
15 mR/hr.
Cormnents:
16 mR/hr.
17 mR/hr.
RCIC INOP.
18 mR/hr.
19 m2/hr.
23-MOV-15 inoperative.
20 mR/hr.
21 mR/hr.
SRV's inoperative for remote 22 mR/hr.
operation.
23 mR/hr.*
24 mR/hr.
i 1
25 mR/hr.
25 mR/hr.
27 mR/hr.
28 mR/hr.
29 mR/hr.
30 mR/hr.
tieteorology Windspeed Direction I
Brookhaven Class 1
l r
9 NO YI s
CT 4
NA 3)
EC Y
GI C
RF LN EI AE MS RG E
ES ER G
A NE A
.L EM P
C GE D
NA S
TL US ST EN RE M DM EO TC AP I
C 2
I 8
T 9
N 1
A 1
1
.y t
l s
d u
S i
g T
p u
N a
A E
.r T
s N
rg O
en O
C ti I
es R
E ma A
G ae N
A rr E
S ac C
S pe S
E d
M t
K nl C
F ae I
O l v R
pe T
Y l
A R
d P
A el Z
M t e T
M as I
U d s F
l E
o s
dC U
r t ut eS S
t m nt euT S
no aaes I
oo l th so CR PSSit E
GR 4
AE 3
E 0
M 4 y I
1 a T
1d
'l
l Paga 34b l
fiESSAGE NO. 34-TIME:
1140 ON DAY l ISSUED TO THE CONTROL ROOM Plant parameters are as indicated on the Plant Status Sheet.
Steam Tunnel Temperatures on Detectors TE-121A through D are 280*F.
LOCA signals are sealed in EBG's and low pressure ECCS pumps are running.
C-i
(
l l
l l
l V
t
7 TIME 1140 PLANT STATUS SHEET SHEET NO. 34c
(
- Day 1 EDG Starts j
V:ssel Level 0
_ inches X Running Loaded / Running Unloaded / Standby /005 C Running Loaded / Running Unioeded/ Standby /005 Level Trend decreasin9 8 Running Loaded / Running Unloaded / Standby /0OS V*ssel Pressure 500 osig Pressure Trend decreasing 115KV Reserve Available
- 3 LHH No Vessel Bottom
- 4 NMP sqNo 0
Orain Temp.
410 F
Building Vent Rad Monitors 0
C1canup Inlet Temp. 435 F
Rx. Building 150 Cpg Refuel Floor luu
_ CPM L
Main Steam oressure 0 osig Turbine Building CPM Radweste 11U CPM Drywell Pressure 16.5 osia Control Room 100 CPM i
Off-Gas Red Monitor D/S mR/hr.
0 Orywell Ave. Temp. 123 F
i Stack Rad Monitor Cps Torus Ave. Water 0
Temperature 79 F
High Range Effluent Monitors Stack.
A B
mR/hr.
Torus Pressure 14.7 osia Turbine Bldg. A B
mR/hr.
Radwaste Oldg. A 0.3 8 ~ W mR/hr.
Torus Level
-n_7a inches Containment High Range 6 Monitor A 8
R/hr.
Orywell Floor Leak Rate 1 an opm Area Radiation Monitors 1
mR/hr.
Orywell Equipment 2
mR/hr.
(--Laakrate 1 cn opa 3
mR/hr.
4 mR/hr.
Busses Energized (/)
5 m1/hr.
6 mR/hr.
10300 '10400 Y 7
mR/hr.
8 mR/hr.
!10600 V..
9 mR/hr.
10500
/
/
10 mR/hr.
12 mR/hr.
1 Main Steam Line Radiation 13 mR/hr.
Monitors R/hr.
14 mR/hr.
15 mR/hr.
Comments:
16 mR/hr.
17 mR/hr.
RCIC INOP.
18 mR/hr.
i 19 mR/hr.
23-MOV-15 inocerative.
20 mR/hr.
21 mR/hr.
S RV ' st inneerative for remote 22 mR/hr.
operation.
23 mR/hr.
24 mR/hr.
25 mR/hr.
L 4
26 mR/hr.
p 27 mR/hr.
28 mR/hr.
29 mR/hr.
30 mR/hr.
Heteorology l
Windspeed Direction Brooknaven Class y;
L L
m-_----e
.m y-,--.-
,v.
n- - -
NO YI a
CT 5
NA
)
3 EC GI RF EI MS E
ES G
A A
L P
C D
NA S
C 2
I 8
T 9
N 1
A 1
1 tsu S
g' T
u N
A E
T NO O
C I
R E
A G
N A
E S
C S
S EM K
C F
I O
RT Y
A R
P A
Z M
T M
I U
F S
OT D
l E
o U
r S
t m S
no I
oo CR EGR 5
AE 3
E 0
M 5 y I
1 a T
1d
/
Jl l,
l' 1
1 i!
l
o Paga 35b MESSAGE NO. 35
,3 i
TIME:
1150 ON DAY 1 ISSUED TO THE CONTROL ROOM l
r l
l l
e 35c TIME 1150 PLANT STATUS SHEET SHEET NO.
(
Day'1 EOG Starts V:ssel Level
-60 inches A Running Loadeds Running Unloaded / Standby /OOS C Running Loadeds Running Unioaded/ Standby /005 Level Trend decreasing B Running Loadeds Running Unloaded /Stanoby/005 Vissel Pressure 420 osig Pressure Trend decreasin9 115KV Reserve Available
- 3 LHH es/No Vessal Bottom
- 4 NMP
'No Drain Temp.
390
'F Building Vent Rad Monitors cleanvo inlet Temp. 415
'F 2x. Building 150 CPM Refuel Floor Adv CPM Main Steam Pressure 0 osig Turbine Building CPM Radwaste 11u CPM Drywell Pressure 16.5 osia Control Room luu CPM Orywell Ave. Temp. 122
'F Stack Rad Monitor Cps Torus Ave. Water Temperature 79 F
High Range Effluent Monitors Stack.
A B
mR/hr.
Torus Pressure 14.7 osia Turbine Bldg. A B
mR/hr.
Radwaste Oldg. A 0.3 8
0.5 mR/hr.
Torus Level
-0.74 inches Containment High Range d Moniter A B
R/hr.
Drywell Floor Leak Rate 1 70 opm Area Radiation Monitors 1
mR/hr.
Drywell Equipment 2
mR/hr.
(
Leak rate 1 an opa 3
mft/hr.
4 mR/hr.
Busses Energized (/)
5 mR/hr.
/
6 mR/hr.
V 400 V 7
mR/hr.
10300 10
/
8 mR/hr.
10500 [10600 V 9
mR/hr.
/B DC ['
10 mR/hr.
A DC i 11 mR/hr.
12 mR/hr.
Main Steam Line Radiation 13 mR/hr.
Monitors R/hr.
14 mR/hr.
15 mR/hr.
Comments:
16 mR/hr.
17 mR/hr.
RCIC INOP.
18 nd/hr.
19 m2/hr.
23-MOV-15 inoperative.
20 mR/hr.
21 mR/hr.
SRV's inocerative for remote 22 mR/hr.
operation.
23 nd/hr.
24 mR/hr.
25 mR/hr.
26 mR/hr.
27 mR/hr.
28 mR/hr.
29 mR/hr.
30 mR/hr.
Meteorology Windspeed Ofrection Brooknaven Class O
.g PAGE
.._36a
(.
)
FITZPATRICK SCENARIO - August 11, 1982 MESSAGE ANTICIPATED RESULTS AND EMERGENCY TIME HUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COMMENTS CLASSIFICATION 1200 36 Control GENERAL day )
Room EMERGENCY Plant Status Sheet issued to TSC.
l 4
~-
9
P;ga 36b m
MESSAGE NO. 36 TI}E:
1200 ON DAY 1 ISSUED TO THE CONTROL ROOM
(
U
~
c TIME 1200 PLANT STATUS SHEET SHEET NO.
36c
,m
(
Day 1
?
EDG Starts V;ssel Level 0
inches A Running Loaded / Running Unloaded / Standby /OOS C Running Loaded / Running Unloadedj Stanoby/005 Level Trend increasing B Running Loaded / Running Unloaded /Stanoby/OOS V2ssel Pressure 140 osig Pressure Trend decreasing 115KV Reserve Power Available
- 3 LHH No Vessel Bottom
- 4 tetP No 0F Orain Temp.
Building Vent Rad Monitors 0F Rx. Building 140 CPM Cleanuo Inlet Temp.
Refuel Floor 160 CPM Main Steam Pressure 0 osig Turbine Building CPM Radwaste llu CPM Drywell Pressure 16.5 osia Control Room 100 CPM Off-Gas Rad ?tonitor D/S mR/hr.
0 Drywell Ave. Temp. 120 F
Stack Rad Monitor Cps Torus Ave. Water 0
Temperature 79 F
High Range Effluent Monitors Stack A
B mR/hr.
Torus Pressure 14_7 osia Turbine B1dg. A 8
mR/hr.
Radweste Oldg. A O. 3 B
0.5 mR/hr.
Torus Level
-n An inches Containment High Range 6 Monitor A B
R/hr.
Drywell Floor Leak Rate An opm Area Radiation Monitors 1
mR/hr.
Drywell Equipment 2
mR/hr.
f Leak rate an opm 3
mR/hr.
4 mR/hr.
Busses Energized (/)
5 mR/hr.
6 mR/hr.
10300 /10400 Y 7
mR/hr.
8 mR/hr.
10500 < 10600 Y 9
mR/hr.
10 mR/hr.
A OC F B DC /
11 mR/hr.
12 mR/hr.
Main Steam Line Radiation 13 mR/hr.
Monitors R/hr.
14 mR/hr.
15 mR/hr.
Cements:
16 mR/hr.
17 mR/hr.
18 mR/hr.
19 mR/hr.
20 mR/hr.
21 mR/hr.
22 mR/hr.
23 mR/hr.
24 mR/hr.
25 mR/hr.
26 mR/hr.
27 mR/hr.
28 mR/hr.
29 mR/hr.
30 mR/hr.
l l
Meteorology i
Windspeed I
Direction Brooknaven Class i
l l
8 8
0 Section IV EMERGENCY PLAN EXERCISE /JAFNPP RADIOLOGICAL DATA O
t
,3 The following meteorlogical parameters were used to calculate the radiological parameters for this drill:
2 m/s until 1330 Wind Speed
=
5 m/s from 1330 till end of drill E for duration of drill Pasquil Category
=
Wind Direction = out of 2000 until 8:50 hrs out of 3150 until 8:50 hrs to end of drill The fp11owing sets of maps show the isopleths of the release plume as they develop with time.
Table I shows the radiological parameters for these isopleths:
Offsite Isopleths Set #1 0930 - 1000
=
Set #2 1000 - 1030
=
Set #3 1030 1100
=
Set #4 1100 1130
=
Set #5 1130 - 1330
=
Set #6 1330 1345
=
1345 - 1400 Set #7
=
Set #8 1400 1415
=
(
Note 1:
Since the release is terminated at 1330, the plume is considered to be essentially dispersed after 1415.
Note 2:
The Noble Gas to Iodine Ratio is 1,000,000 to 1.
ss
t l
l7 Table 1 Noble Gas Nu Dose Rate l
Key T
mr/hr 1 (inner lE-4 20,000 isopleth) t 2
lE-S 2,000 3
lE-6 200 4
lE-7 20 5
lE-8 2
6 lE-9 0.2 7
lE-10 0.02 8 (outer isopleth) lE-11 0.002
^
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1 v% \\ Table II (Thyroid Dose) Thyroid Dose for Thyroid Dose for Total Dos 1st Half of Release 2nd Half of Release Infant 16.6 mrem /hr 23.5 mrem /hr 40.1 mren Child 18.1 mrem /hr 25.8 mrem /hr 43.9 mren Teenager 16.4 mrem /hr 23.2 mrem /hr 39.6 mren Adult 13.3 mrem /hr 18.9 mrem /hr 32.2 mren Q
f ~ Table III Ingested Dose (for 1st half of release) 3uci/m2 Deposition = 7.9833E 2uci/Kg 1.1405E Concentration in pasture = 3uCi/l 4.0647E Concentration in milk = Committed Dose 5 mrem Child = 1.0834E 5.3272E-6 mrem Teenager = 2.3874E-6 mrem Adult = (for 2nd half release) 2 1.1342E-2uCi/m Deposition = 1.6203E - 2uCi/Kg Concentration in pasture = 3uci/l Concentration in milk 5.7749E = Committed Dose Child = 1.5393E-5 mrem Teenager = 7.5635E-6 mrem 3.3896E-6 mrem Adult = l l M l l
-. - *'? Tcblo IV A . f. - 8/11/82 h i' s :. f. :,:. r. t. i i. I At L t!. A i !'Jf. : st 2 b of nWsG g !. F F L t.c N1 riu *.1 i U f-i; A :. r. C A: C6 1.*!UN Turbine Building hilEASE POINT ._ LOCAT10N COUNT RAIE (unit s) 1 : 9 5 6 7 E 19..._ _ O ! S I A N C E (en.' ZNVER$10N CONS T AN T _.lE luci/se.c/ cpm _. .. _ _.__ X/0 (1/mi _ 2l UC I/SEC ' 1 9.5_s LE9_ _ _ __ DOSE R A T E (mr /hr ' 1.9567E3 _. _ OICi/sec) af C t/stclu om c e, 4. 2.4 ? 4 hrs DURATION OF RELEASE shesi METEOROLOGICAL PARAMETERS: TUR8ULENCE CLASS 1 (PASOUILL A) OlRECTION FR0n coeg) _ _ _1 M __ _ _ 2 mis 4 5 mph 11 (PASQUILL 8.C) WINDSPEED (mpni _7 TYPE OF RELEASE g('(~PASQUILL01 Iy PASOUlLL E.F.GJ_E, lJROUND) / ELEV A T ED XE2 _ ilit ? m ' G((' k DD5ERATE 8 DCSERATE THYRDID 00SE ' 2t'R in?CID !LCC Ai!0N/ SECTOR ll i: , :,; g's ."[,,,,,,..,p. _ r xv/00/a ) (nr em/hr ) Imrem/hr) R ATE (rem /hr) CllSE tr em) .,. j a 1.72E 3
- Conter line 4.79E-4 4.3E5 mren 2.5E3xE2 2.3E-lxE, 4
t gg 0 f1 mile 2.5ES 2.3El 4.6 l T riY i u q canter i j5. 6 E 2i i line 1.79E-4 1.4E3xE2 7.8E2xE2l 6.9E-2xE2 av I 1' THY' 38 I 2 miles 1.4E5 7.8E4 6.9 1 l1.68Ef 3 2. 2 E-2 x E ]' j.
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5 miles l 4.87E-5 4.2E2xE2 2.5E2xE2 n I, 4.2E4 2.5E4 2.2 44 l l IHY. i I l l 1 5.2E1 N O mile s 1.62E-5 1.3E2xE2 7.7E1xE2 6'. 9 E-3 x E: W!3-1.3E4 7.7E3 6.9E-1 38 "'J % wn m
'ti-8/11)'82 Tablo IV B i .. i. t.'. ;c n A :. C AL LU A i ! O.*. : D,~ ~ . l;H lst 2 hrs of release t LF ri t:i N1 Mi, N 1 19-d A '_ r. C A: L G ; 4 ;. t.N Turbine Building kELEASE POINT _ LOCAT10N l 9567E10 [0sNT RAIE (uni t s}. . D I S T A N C E (,,.'
- ^,NVERSION C O N S T A N T _.._._lE-Luci/.s e c / c p m.
- X /0 (1/rn). 1.9567E9 .._ 00SE R A T E (mr /hr! O fuCt/SEC, Di C t/sici tiram si.e 4.2 4L O(Ci/sec) 1.9567E3 (f rom step 4.3.17) DURATION OF RELE ASE (hral .nETEOROLOGICAL PARAMETERS: TURBULENCE CLASS 1 (PASQUILL A) OlRECT10N F ROM to., ) 315 2 mis 4.5 mph II (PASOUILL 8.Cl-WINOSPEED (,non) )f IPASQUILL D) IYPE OF RELEASE GROUNO / EL[VATED IV IPASOUILL E.F.G)__.E i ait 4 mMif 9; DCFR A TE 8 DOSERATE THYR 010 00SE l 2t+ irt'RDID,,.,, g *(6: RATE t emenril 00SE (e.m> l,3,,, I.,J3.- lLDCA110%/ SECTOR xw /O l' /='l (,,r e m/ nr i (,v.m /w,1 1*68E 3 N.M.Pt. 4.5E-4 4.2E3xE2 2.5E3xE2 2.2E-lxE2 WB Rd. 4.2E5 2.5E5 2.2El 4.4 and Minor Rd. I THYi ~7* i Parkhursti 4.E-10 i.3g'3 l 3.4E-3xE 2E-3xE2 1.8E-7xE2 i Road and l Minor Rd. 3.4E-1 2E-1 3.6E-5 1.8E-5 t IHY i t 'l.8E-5xE2! l1,4g_k I North Rd. 4.5E-8 3.5E-lxE 2E-lxE2 and e I i " P' J Dennis Rd. 3.5El 2El 1.8E-3 3.6E-1 l I H Y. i 1.36E'-3 [ Dennis Rd 4.5E-10 I W B, t Wtrdic on R$ 3.4E-1 2E-l 1.8E-5
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1 .e.- - _ c. -s:: A. s -.- - - t.... Table IV C Dai[. 8/11/82 (m 7 I ns.r ._ _. _1 s t 2 lirs of release hEl.E l.5E R t.T E C AL CUL Al l 0f': EFFLUENT MONITOP BACK CALCULAT10N Turbine Building RELEASE POINT LOCATION _.. COUMT R A TE (unils) 1.9567E10 01 S T A N C E (m. ). __ ___.:-__ ___ _.___ CONUERS10N CONSTANT lE-luCi/sec/ cpm X/0 (I/ml Of uC i/SEC) 1.9567E9 00SER ATE (mr/hr! 1.9567E3 Q(Ci/Sec) O f C I/stc ) (f rom step 4.2.4, (from step 4.3.17) DURATION OF RELE ASE (hre) d hre METEOROLOGICAL PARAMETERS: TURBULENCE CLASS 1 (PASQUILL A1 O l R E C T I O N F R O M td g.) 11 ; (PASQUILL 8.C1 WINDSPEED (moh) 2 mis 4.5 mph .1 (PASQUILL 0) TYPE OF RELEASE IV (PAS 0 VILL E.F.G) E GROUNO / ELEVATED REtit'd m "iC!If y 00EERATE 8 00SERATE THTR010 DOSE 2HR infR010 gy m33l: g,;3__ a xo/ott/m ) 0 (mr.m/hr) (mrem /hr) R ATE' (rem /ht) 00SE(rem) ,LOCAf!0N/ SECTOR g,, _ _.n.. 1.68E 3 isopleth 4.5E-4 4.2E5 2.5ES 2.2El W8 4.4 THT 7 I i e i i i I 'l.92B2 I 4.5E-5 4.lE2xE2 2.8E4 2.5E-2 W6 d xE-1 SE-3 4.8E4 2.5E-3 thy l l I 15.6 { 4.5E-6 3.9ElxE2! 2.3E3 2.lE-3 W8 ~ ~ - ' ~ xE-1 l 4. 2E-4 3.9E3 2.lE-4 ygg I l 4.5E-7 3.7E2 2.2E2 1.9E-5 l'M l b* 3.8E-5 i TllY Ph: 3ARfD BY L
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~ O A ' '- 8/11/82 Table IV D 7iIe.m _._._ 1st 2' hrs of releas hELE!.5E RATE CALCULA110N: e LFFLUENT n0NITOP BACK CALCULAT10N RELEASE POINT Turbine Building.. _ -- LOCATION _ _ _ ~ 1.9567E10 COUNT-RATE (units) _ _ _ __. _ __ D I S T A N C E (m.) ___ _ CONVERSION CONSTANT 1E-i nci /aac / cpm X/0 (1/m) 0(uCr/SEC) 1.9567E9 00SER ATE [mr/hri 1.9567E3 Of C I/SEC1(from step 4.2.41 g[c[f3eg) (f rom step 4.3.17) 4 hrs DUR ATION OF RELE ASE shr:1 nETEOR0 LOGICAL PARAMETERS: TURBULENCE CLASS 1 (PASQUILL A1 D I RECT ION FR0t1 (d.g.) 2 mis 4.5 mph I' (PASQUILL 8.C1 WINOSPEED (men) \\ IPASQUILL 01 TYPE OF RELEASE OROUND / ELEVATED IV (PASQUILL E.F.G) __E _@ "U5 V 00ERATE 8 DCSERATE TNTR010 00SE 2HR THYR 010 '" O E r ILOCATION/ SECTOR zu/0(t/m 3 0 (m'em/hri (mram/hri RAT (rem /nri 00SE te em) . t r.r s )
- _em).
.14 isopleth 4.5E-8 3.5El 3.2El 2El 1.83E-3 WB xE-1 l 3.6E--4 1.83E-4 THY b i
- 1. 4 E 2 't-
"O 4.5E-9 3.5E-2 2.2 1.8E-7 l I 'I 3.5 1 I' l.36E -3 4.5E-10 3.4E-1 2.E-1 1.8E-5 j L._ % x1E-1 j 3.6E-6 1.8E-6 l Jgy t WS U l TliY l l Ph: =A;rn aY
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DAI-~ 0/11/82 hELEASE RATE CALCULAT10N: ,!M.____. Last._ half _of_re1 ease ^ i ( EFFLUENT MON! TOR BACK CALCULAT10N RELEASE POINT Tgrbine Building _ _ _ _ _ LOCATION _.. 1.9567ElO _ _.... __ 0 l S T A N C E (ma _._ __. COUNT RATE (uni t s) lE-luCi/sec/ cpm X/O (l/d CONVERSION CONSTANT 2. 8E9 00SER ATE (mr/hri O(uCI/SEC} OICi/sec) O f C 1/sEc (<,om ei., 4.2.4' (f rom step 4.3.17) 4
- DUR AT10N OF RELE ASE thr.)
METEOROLOGICAL PARAMETERS: TURBULENCE CLASS 1 (PASOUILL A) OlRECT10N FROM toeg.) 315 2 mis 4.5 mph (PASQUILL B.C) WINDSPEED <rnphi (" 1 (PASQUILL 01 TYPE OF RELEASE GROUND / ELEVATED E IV (PASOUILL E.F.G) RElitil 130.1 0 19 00SERATE 8 00SERATE THYROID 00SE 2hR THYROID ggggq3 gy xv/cil/m2) (nr em/hr t (mremAr) R ATE (rem /hr) DOSE tr em)
- .,43 lLOCAT!Dh/ SECTOR in,,3 1.921', 3 C.L.
4.79E-4 4.8E5 3.3E5 2.9E-2 WB l 1 mi. 5.8E-2 THY I 8E2 l i NO f 1.79E-4 2E5 1.2E5 lE-2 C.L. 2E-2 { 2 mi. THY l l 2.361:2 l C.L. 4.87E-5 5.9E4 3.5E4 3.lE-3 L _,, y B, l
- 6. 2 E-3 l
5 mi. THY l 80 1 C.L. 1.62E-5 2E4 1.2E4 lE-3 g 10 mi. 2E-: TilY PRt"AR?O BY
CALCU;ATOS PRCJECTED DOSE n0RK5HEET /11/82 Table IV F DATE Last half f release RELEASE RATE CALCULATION: TIME EFFLUENT MONITOR BACK CALCULATION ' 9 RELEASE POINT LOCATION COUNT RATE (units) 1.9567E10 DISTANCE <>wl CONVERSION CONSTANT 1r 1"N / ~ /=rk X/O (1/ml 2.7BE9 00SER ATE (mr/hr) 0( uC r/SEC) 2.78E3 Q(CI/sec) O f C t/SECl(f rom st.p 4.2.4i (f rom step 4.3.17) DURAT10N OF RELE ASE (hrs) A h" METEOROLOGICAL PARAMETERS: TURBULENCE CLASS 1 (PASQUILL A) DIRECTION FROM (d.,.) 2 m1s 4.5 mph II (PASQUILL B.C1 WINOSPEED (mph) (PASQUILL 01 TYPE OF RELEASE GROUND / ELEVATED IV (PASQUILL E.F.G) r 00 " v 00SERATE 8 00SERATE THTR010 00SE 2HR THTR0!D 0C$I Y,I0 LOCATION / SECTOR Xu/0(t/m81 0 cmr.m/n,3 cm,../w,3 a47E c,.m/hri 00SEtr.m) 3 g, m} N .Pt.Rd 4.5E-4 4.9E5 3.3E5 2.9E-2 WB 5.8E-2 Minor Rd. THY .002 Parkhurst 2.7E-8 gg Rd and 4.5E-10 SE-1 3E-1 Minor Rd 5.4E-8 THY .20 North Rd l and 4.5E-8 SE-1 3E-1 2.7E-6 WB l Dennis Rd 5.4E-6 THY l .002 nonnis Rd 4.5E-10 3E-1 SE-1 27E-8 W8 (,nd Woolson 5.4E-8 80 TitY l I PREPARFO BY
- ALCULAT0c PRCJECTED OCSE WORK 5hEET Table IV G
DATE 8/11/82 RELEASE RATE CALCULATION: Last lialf of release TIME EFFLUENT MONITOR BACK CALCULATION Turbine Building RELEASE POINT LOCATION COUNT RATE (units) 1 m nin OlST ANCE (mil CONVERSION CONSTANT lE-liCu/sec/ mph X/0 (1/m) Of UC t/SEC) 2.78E9 00SER ATE (mr/hr) 2. 8E3 O(Ci/sec) O f C I/SEC)(f rom step 4.2.4, OURAT10N OF RELE ASE thre) nETEOR0 LOGICAL PARAMETERS: TURBULENCE CLASS 1 (PASQUILL A) DIRECTION FROM (deg.) 315 2 mls 4.5 mph I.I (PASQUILL 8.C1 WINOSPEED (mph) ( (PASQUILL 01 TYPE OF RELEASE IV (PASQUILL E.F.G) E GROUNO / ELEVATED. 1 l RREE NUh y 00SERATE B 00SERATE THIR010 00SE 2HR INTRO 10 T[,I" e LOCATION / SECTOR Xu/Q(1/m ) 0 (mrem /hrt (mrom/ht) RATE (rem /hr) 00SEttem) g, 1.96 E3 2.9E-2 WB isopleth 4.5E-4 4.9ES 3.3E5 -2 i THY 2.4E-2 3.1E-3 WB 4.5E-5 6E4 3.5E4 E-3 THY 4.5E-6 5.6E3 3.2E3 2.9E-4 W'8 5. 8E - 4 THY 2'2 5.5E2 3.1E2 2.9E-5 WB (., 4.5E-7 5.8E c THY PREPARFC BY
r- ~ A ;.~..:. 4 ~. - _'.'_ECJi~ 7 5 0 COSE nO:.C -T E ~ Table IV H DAE _ 8/11/82 Last half of release hELEASE RATE CALCULA110N: (- tin-t EFFLUENT MONITOR BACK CALCULATION Turbine Building LOCATION _. RELEASE POINT COUNT RATE (unit s) 1.9567Elo O l ST ANCE (m.L CONVERSION CONSTANT lE-luc 1/sec/ cpm X/0 (I/m) O(uCI/sEc) 00SER ATE (mr/hr) Of C I/SECl(from step 4.2.41 2.79E3 OICi/sec) (f rom step 4.3.17) DURAT10N OF RELE ASE (hre) 4 h rc METEOROLOGICAL PARAMETERS: TUROULENCE CLASS 315 1 iPASQUILL A1 DIRECTION FROM toeg.) 2 mis 4.5 me i' (PASQUILL 8.C) WINOSPEE0 (mph) 1 (PASQUILL 01 TYPE OF RELEASE IV (PASQUILL E.F.G) E GROUND / ELEV ATE 0 B 00SERATE THTR010 00SE 2HR THYR 010 UhU [(005ERATE A LOCATION / SECTOR Xu/00/ar) mr em/hr t (mrom/hri R ATE trem/hr) 005Etrem) thes) (r em) .20 2.7E-6 WO 4.5E-8 SE1 3E1 isopleth
- 5. 4 E-7 THY T
. 0 3*g ! l 2.7E-7 4.5E-9 5 3
- 5. 4 E-7 THY
.002 4.3E-10 SE-l 3E-1 2.7E-8 W8 5.4E-8 _{H1 k> WB TilY PRFPARFG RY i
Table V (Offsite' Monitoring I.o c a t i o n s ) 0930 1000 1030 1100 1130 1200 1230 1300 1330 1400 1430 15 Environmental TLD's
- 45
.005 005 .005 .005 785 2.735 4.685 6.635 8.585 9.455 9.455 9.4
- 57
.070 .070 .070 .070 .070 .070 .070 070 070 071 .071 .0 Emergency T 1.D ' s _ E-13 .001 .001 .001 .001 .001 001 001 .001 .001 .001 .001 .( E-18 .001 12.5E-3 2.75E-3 3E-3 3.2SE-3 3.5E-3 3.75E-3 4E-3 4.25E.3 4.5E-3 4.5E-3 4.5 ~ - - - .}}