ML20043A317
| ML20043A317 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 04/26/1990 |
| From: | GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| References | |
| NUDOCS 9005210188 | |
| Download: ML20043A317 (579) | |
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( . .. Nuclear OYSTER CREEK NUCLE AR GENER ATING STATION ANNUAL EXERCISE >
1990 l
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- SCENARID NO. 22 MMO REV. O s
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(- CENERAL PUBLIC UTILITIES-OYSTER CREEK NUCLEAR GENERATING STATION ,
EMERGENCY PREPAREDNESS EXERCISE SCENARIO (Revision 0)
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ANNUAL EXERCISE SCENARIO NO. 22 ,
r OCNGS REV. 0 4
( l GENERAL PUBLIC UTILITIES h
- f. OYSTER CREEK NUCLEAR GENERATING STATION TABLE OF CONTENTS
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SECTION PAQR i
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'1.0 TABLE-OF CONTENTS- 1-1 2.0
SUMMARY
's 2.1' . Introduction 2-1 ,
f .
t 2.1.1 Purpose
(' 2.1.2 Narrative Summary '
2.2 Schedule of Events 2.3 Participating Organizations 3.0 OBJECTIVES AND GUIDELINES 3-1
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3.1 Objectives i
3.2 Performance Guidelines 4.0 SCENARIO TIME LINE 4-1 <
5.0 CONTROLLER / OBSERVER ORGANIZATION 5.1 Assignments 5-1 Facility Telephone Numbers 5.2 5.3 Evaluation and Comment Forms
- l-l 6.0 SCENARIO CONTROL l 6.1 Pre-exercise Briefing 6-1 ,
s 6.2 Initial Conditions 6.2.1 Plan of the Day - Morning Briefing 6.2.2 STA Plant Status Sheet I
6.3 Radiological Assumptions SCENFRMS/2/ Disk 7
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-ANNUAL EXERCISE SCENARIO NO. 22 . ;
OCNGS REV. 0 'J l
a TABLE OF CONTENTS j K (Continued) .
SECTION IIILE Eh91 A SUPPORTING DATA A-1 operational Data A-1 ,
A .1.0 Critical Plant Parameters ,,
A-1.1 Critical Plant Parameters Summary -
)
A-1.2 KVAC System Status i A-1.3 ' Annunciator Status Sheets "A-1.4 Radiation Monitoring System Data A-1.5 RAGEMS Data ,
t A-2 Meteorological Data '
A-2.1 Meteorological Data A-2-1 ,
A-2.2 Meteorological Data Summary Table A-3 Source Term and Radiochemistry Data A-3 l
. A-3.1 A-3.2 A-3.3 Reactor Water Activity Torus Water Activity Drywell Gas Activity gl 3-A-3.4 Torus Gas Activity l A-3.5 Reactor Building Activity +
A-3.6' Turbine Building Activity )
L A-3.7 RAGEMS I Stack Activity 1
A-3.8 Refuel Floor Activity A-4 offsite Radiological Data A-4-1 A-4.1 Radiological Survey / Sampling Data '
A-4.2 Rueter-Stokes Data Summary Table A-4.3 Environmental Sampling Data A-4.4 Plume Search Data A-4.5 Dose Projections A-5
- Onsite Radiological Data A-5-1 l l
A-5.1 Floor Plan Radiation Dose Rates A-5.2' Emergency Facilities Radiation Data A-5.3 Onsite Survey Data A-6 Message Cards A-6-1 i
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ANNUAL EXERCISE SCENARIO NO. 22 OCNGS RTV. 0 TABLE OF CONTENTS .
(Continued) r
[ SECTION TITLE
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D MINI-SCENARIOS B-1 Fire Onsite B-1-1 g
B-2' Isolation Condenser Electrical Tault B-2-1 B-3' Site Evacuation to FRAA B-3-1 B-4 Public Information B-4-1 B-5 Additional Assistance B-5-1 C PLANT AND LOCAL INFORMATION C-1 Site and Systems Data C-1-1 C-1.1 Site Map C-1.2 Intentionally Left Blank C-1.3 BWR Schematic Diagrams C-1.4 System Label Guides C-1.5 Acronym List C-1.6 Access RWP Identifications C-1.7 Emergency Preparedness Contacts- .
C-2 Release Path . C-2-1 -
C-3 Directions to Oyster Creek Nuclear Generating Station C-3-1 -
C-4 Local Lodging List C-4-1 C-5 Local Rastaurant List C-5-1 9
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ANNUAL EXERCISE SCENK12] NO. 22 OCNCS REV. 0 I
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Section 2.0 2.1 Introduction
( 2.2 Schedule of Events 2.3 Participating organisations
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31
y ANNUAL EXERCISE SCENAR80 NO. 33 OCNGS NW. O I 2.1 Introduction 2.1.1 Purpose This scenario will be used as the 1990 Exercise at Oyster Creek Nuclear Generating Station on April 26, 1990.. The scenario is 1 designed to be as realistic as practical while meeting the exercise objectives.; Specific objectives are set forth in this document. In general, the intent is to' exercise a full spectrum of emergency response and demonstrate coordination between site and state organizations during the response to a radiological emergency at OCNGS.
The 1990 Exercise will demonstrate OCNGS ability to respond to a LOCA which requires consideration'of containment venting and a concurrent loss of ultimate heat sink.
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Plant data were generated on the Oyster Creek Basic Principles
-Trainer and are included as a section of this scenario. The BPT is a partial scope simulator. BPT data were. loaded into a simulated I SPDS system that is PC based. ' Simulated SPDS systems will provide plant data in the CR, TSC, EOF, OSC, and PTFC. SPDS system terminals are located in each of these ERF's. The OSC terminal is I presently being installed and should be operational in early 1990.
If it is not operational at the time of the exercise,: simulated SPDS information will not be provided in the OSC. Several electronic pages of data corresponding to real SPDS~ system screens.will be
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available to drill participants. Should this system. fail, controllers will revert to Plant Data Sheets presented in the scenario.
All radiological and chemistry data are generated by a plant specific computer program, developed by the Emergency Preparedness
]j Department, called RADDMAPP. QAD/C0 is a sub-module of the program for calculating in-plant doses due to shine and was obtained commercially.
Offsite radiological data are calculated by GPU. Nuclear's RAC dose f projection program.
It should be noted that the radiological release to offsite areas and the resultant dose to the population will tas due co an Isolation Condenser leak within the Reactor Building and subsequent elevated release. Section C provides a release path diagram. Dose rates'do not require protective actions:for the public.
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s ANNUAL EXERCISE SCENARIO NO. 38
~OCNCS REV. 0 ,
l 2.1 Introduction tcentinued)
All times indicated in this scenario are noted at "T" time. This is the time from the start of the scenario. .Although the proposed ,
start time is 2:30 p.m. this cannot be a certain start time due to >
the fact that Oyster Creek will be operating during the exercise. +
I The condition of the plant may require a short delay in exercise initiation. This being the case, clock times are not included in ,
exercise data. Exercice controllers and observers are well versed-
- in this practice at Oyster Creek.
Section 4.0 of this scenario contains the Scenario Time Line. This matrix is' intended to be a guide.for observers. Major eventn and g <
expected actions are catalogued here for easy. reference, section 8 g-contains the mini-scenarios for each key activity outside of the control Room. These are organised to provide Observer information on the specific activities they may be critiquing. Section C contains site especific information that may be useful to observers l-l W
unfamiliar with OCNGS and its environs.
The scanario has been independently reviewed by a shift Technical f Advisor (STA), GRCS qualified (Rad con Foreman), Maintenance, Fire-- ,
Protection, Environmental, Comrounications, and management personnel.
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OCNGS SCEMAR80 No. 83 REV. 0 2.1.2. Narrative Summary ,
The initial conditions for this exercise will have strong westerly winds impacting intake' canal and Barnegat Bay water levels.
L The level will be above the Unusual Event h declaration point and, therefore, will not require declaration of events due to-low level during the early stages of the exercise.
The low level does become important as-consideration is given to long-term cooling capability.
The B'. Isolation condenser will be out of service for repales to valve V-14-32. The initial conditions established the I.C.
failing the valve surveillance on the previous day.
Maintenance activities have stopped while awaiting parts to complete repairs. The Condenser is isolated and tagged out
[ of service. The. Tech Spec requirements have been met for A
this plant configuration.
In additir+ ^
the I.C.'s problem, the 'A' recire pumps will indicate . ' . '-ling seal. The recire pump will be off as part of the inui; 1 conditions due to the seal problem. Operating directives have been established to initiate a plant shutdown if the leak rate exceeds 4.5 gpm (currently at 4.0 gpm). .The seal leak will increase to greater than 5 gpm requiring the declaration of an Unusual Event.
This will be indicated by increased unidentified Rx Coolant leak rate, increasing Drywell humidity, and increasing-Drywell pressure. It is expected that these indications will be verified and Drywell venting in accordance with EOP's conducted to maintain pressure. Concurrently, a controlled shutdown will be initiated.
The seal leak will continue to worsen such that a reactor scram, due to high Drywell pressure, will occur causing an isolation of Drywell penetrations. Eventually this leak will.
result in the declaration of an Alert due to exceeding the 50 gpm limit caused by the complete failure of both cavities of the pump seal. During this period intake canal level will continue to decrease; it is expected that the circulating water pumps are turned off which will prevent the utilisation of the main condenser as the primary heat sink.
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. shortly.after the Rx scram, a fire onsite will take place. ,
The fire is intended to demonstrate the ability to deal with ;
multiple problems while ensuring the health and safety of '
site personnel. This sequence;of events is expected to tax l the Emergency Response Organisation since they will be dealing with divergent casualties (Rx coolant leak and a g.
g fire) and transferring responsibilities as additional support 'n becomes available. 1 1
Some' time;after the anticipated and of the' fire,' the' intake canal water level will decrease further. The level will drop below -3', requiring declaration of a site Area. Emergency- _ lj since the plant =is not in cold shutdown.. This condition will 5 ,
be so severe that suction will be lost to the pumps supplied )
by this source (service water, emergency' service water, g, screen wash and cire pumps). This offectively negates long g' term cooling functions including containment spray ard.
requires alternatives to be-identified to supplant the ultimate heat sink..
Subsequent to the loss of the heat' sink, Drywell temperatures i will increase significantly due to the-inability to remove the heat from the reactor vessel (radiant);and the heat gi 3 '
introduced due to the steam leak. This will'be further [
compounded by a steam leak on the operating Iso condenser. g.!
between the steam inlet valves. This leak will'not be g' immediately isolable discharging into the Reactor Building. ,
This I.C. leak will result in significantly increased building activity levels resulting in an elevated release.
The repair efforts will be hampered by the adverse building
.l*us '
environment, however, completion.is' expected. i The discharge into the Reactor Building will caust, an offsite !
I release through stand-by gas. There is no distinguishable offsite doses (8E-3 mRom/hr.). Concurrent with the isolation g of the Iso condenser, intake level will rise restoring suction to the service water and E.S.W pumps to allow a 5" 5 controlled cooldown to cold conditions.
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RNNUAL EXERCISE SCENARIO'NO. 23 OCNGS REV.-0 2.2 Schedule of Events
.2.2.1 . Observer Pre-briefing r1 Date and Times April 20, 1990 1:00 p.m. ,
b . Location Bid. 12 Auditorium 2.2.2 observer Briefing-( Date and Time:
Location:
April 25, 1990 20:00 a.m.
300 Complex Conference Room 2.2.3 NRC GET Date and Time April 26, 1990 9:30 a.m.
Location: Bid. 14 2.2.4 '
NRC Entrance and Briefing Date and Time: April 26, 1990 11:00-a.m.
Location: 2nd Floor Conference Room MOB
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2.2.5 NRC Familiarity Tour (if necessary)
Date and Time: April 26, 1990-12:00 p.m.
Location: Various i
( 2.2.6 NRC (only) Heating Date and Time April 26, 1990 11:00 a.m.
Location Residents Office
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2.2.7 Exercise Period Date and Time April 26, 1990 2:30 p.m. - 7:30 p.m.
f Location: Various 2.2.8 Observer Debrief j Date and Time: April 27, 1990 8:00 a.m. I Location: Bld. 14, Classroom 14 2.2.9 NRC Observer Debrief Date and Time: April 27, 1990 8:00 a.m.
Location: Bid. 12 - EP Conference Room 2.2.10 Exercise critique
( Date and Time: April 27, 1990 1:10 p.m.
Location: Energy Spectrum Tl I- 2.2.11 NRC Exercise Critique Date and Time April 27, 1990, 2:15 p.m.
Location: Energy Spectrum AESCEN90/12/ Disk 8 E
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4 ANNUAL EXERCISE OCNGS SCENARIS NO. 22 s REV. O .
2.3 Partieinatina Ornanizationa 2.3.1 GPUN organisatiotat>
[. Operating shift Personnel l
Radiological Controle Personnel security Personnel Initial Response Emergency organization f Emergency Support Organisation 2.3.2 offsite Agencies New Jersey office of Emergency Management (partial p4rticipation)
New Jersey Department of Environmental Protection (partial participation) f Forked River Fire Department
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,3 -AWNUAL EXE'RC2SE SCENARIO'NO. 32 l OCNGS REV. 0 '-
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1990 EXERCISE OBJECTIVES I
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, e ANNUAL EXERC2SE- SCENARIO NO. 22 OCNGS . REV. 0 -
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[ The=.1990-Oyster Creek Nuclear Generating Su6 tion Annual Exercise' Objectives are as follows:
If -A. Incident Asse g g A.A f Classifleation L - i- 1 1.- DegQnattate tne ability of th# 6e:Arcl Room Operators to promptly --
f c4 cognize that' Emergency _ Action Lssu'40 hRio been reached or exceeded,
(: properly declare the emergency, and implement the Emergency Plan.
2.- 'E Demonstrate the ability of'the control Room Operators to assess plant conditions, effectivelyfutilize engineering support,-and implement-procedures'in order to place the. plant in a safe condition.'
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, 3 .' Demonstrate the adequacy of.the plant staff to mitigate the- y consequences of the accident. sg 4 Demonstrate.the adequacy of the Emergency Plan-Implementing 1
.Proced ures.
f B. Notification and Communications
- 1. Demonstrate that. adequate and reliable communications' exist to.
accomplish appropriate and timely notification.of offsite-agencies.
2.. Demonstrate that adequate emergency communications systems are in place to facilitate transmittal of data among emergency response facilities.
- 3. Demonstrate the ability to effectively use the emergency communications systems.
- 4. Demonstrate the ability to. adequately alert station personnel of an emergency through the use of alarms and public address systems.
- 5. Demonstrate that adequate activation procedures exist to-provide for timely mobilization of emergency response personnel.
- 6. Demonstrate the ability-to effectively communicate with emergency teams at the plant and offsite.
- 7. Demonstrate proper recordkeeping and data display in emergency response facilities.
C. Radiolocical' Assessment
- 1. Satisfactorily perform onsite and offsite radiological monitoring activities in accordance with prescribed procedures. One onsite and two offsite teams will be activated.
- 2. Demonstrate the ability to perform offsite radiological dose projection estimates based on monitored radioactive releases.
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ANNUAL EXERCISE. SCENAR30 NO'. 32~
OCNGS REV. O'
-3. ' Demonstrate the use of post accident, sampling procedures to support .
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l the emergency assessment process. Actual. samples will not be taken
- from RAGEMS or. PASS. _ _
4.. ' Demonstrate that sufficient radiological protection. exists'for j
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emergency personnel <to properly carry out assigned roles and -l responsibilities in all facilities. . , a 1
- 5. Demonstrate.the ability to evaluate monitoring data, offsite. .
radiological ~ dose projections:and plant conditions'to. arrive at appropriate protective action recommendations. The source-term in 1
- this exercise.will not require protective-actions,for.the public.
- 6. Demonstrate effective coordination.of the radiological' and environmental. assessment peccess with the New' Jersey Office of- .-'
. Emergency Management and Bureau of Nuclear Engineering. ,
D.- . Emeroenev Facilities
-***l. Demonstrate the ability to activate-and adequately staff-the
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Emergency Control Center, Farsippany Tech Functions Center, Technical ~ -1 '
Support Center,' Forked River Remote Assembly Area, Operations 1 Support-center,-Emergency. Operations Facility, Emergency Assembly l Area, Annex-
-to.the EOF, and Joint Information> Center.
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- 2. Demonstrate that sufficient and adequate emergency. equipment exists- '
to effectively perform all necessary emergency actions.-
- 3. Demonstrate adequate' security including a viable means of access. '
control:that permits entry by authorized personnel only.'. . 13 1
- 4. Show that. sufficient space is dedicated in Emergracy Response Facilities ^to allow for proper emergency response -
E. Emercenev Resoonse ,
l 1. Demonstrate recognition by control Room Operators of events'and. ;'
l-symptoms, correct correlation of these with Emergency Operating -
Procedures 1and operator ability to follow EOPs throughout-the- t exercise. .
t 2. Demonstrate that emergency teams can be prepared and. dispatched in a l- timely manner to simulate repairs to plant equipment.
- 3. Demonstrate adequate protective equipment is available for emergency teams to. accomplish assigned tasks.
- ' Change'from iriginally submitted objectives to add demonstration of PTFC and Fire Brigade.
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1NNNUAL EXERCISt> -SCINARIO NO. 82 OCNGS' REV. 01
- 4. Demonstrate ability to perform onsite ' accountability in" a- timely .
manner.
L S .~ : Camonstrate the ability to locate personnel missing from; accountability in a; timely manner.
.6. Demonstrate'that. adequate provisions exist to evacuate site. personnel.
(a-simulated evacuation involving a.few~ individuals.will'take placep
- 7. DemonstrateLthe abilitycof the' Fire Brigade to' respond to a simulated ,
fire and: utilize offsitesfire department' support.-
F., Emeroency Direction and Control-
,1. Demonstrate that sufficient emergency personnel are available;toi
- properly mitigateLthe consequences of an emergency'and support the-
> emergency on a round-the-clock basis.
- 2. Demonstrate timely and proper response'of emergency; personnel;to
~ l activate emergency response facilities and carry out assigned rolas- !
and responsibilities.
- 3. Demonstrate that licensee management is-indcontrol:in accordance with
- the existing Emergency Plani that there'is one unambiguously defined j individual in charge.of overall direction and coordination of the:
emergency response at all. times. !;l i
- 4. Demonstrate appropriate coordination with: federal ~andistate -f government agencies. l 1
- 5. Demonstrate proper transfer- of responsibility between normal shif t .j and incoming emergency personnel. '
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G. Public Information j
- 1. Demonstrate the ability to develop and disseminate timelyLand 9 accurate news releases.
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- 2. Demonstrate proper and timely activation of the Joint Information center.
- 3. Demonstrate the ability to conduct news briefings and interface with' the news media, elected officials, and concerned citizens.
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Change from originally submitted objectives to add demonstration of i PTFC and Fire Brigade. ;
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l ANNUAI, EXERC2SE SCENAR2O'NO. 88-OCNGS REV.-O - l' ,
'1 H. criticue- .
1.. Demonstrate the capability.to' properly conduct;an exercise' critique = l with the participants in' order to identify major strengths and' weaknesses.
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Previous 1v Identified Insoection Follow Uo Items'.
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ANNUAL EXERCISE SCENARIO'NO. 22 s DCNCS. -.REV. O
'3.2 Performance Guidelines J I,
The following exercise guidelines have been developed to define the S " extent of play" by the exercise' participants in. meeting the exercise L< . objectives.-
'1. .Theil990 Annual Exercise will be conducted on April 26,~1990.- Drill participants-will posses prior know' ledge of the exercise'date but
'not-the start-time.' All: personnel should f ollow their . normal -
routines for that. day except those.prestaged(in accordance with j Item- 5 below. .
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2.1 Control Room activities;will be performed in!thel Control' Room. .
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. Controllers will provide the Operations staff with a; set of scenarioL j messages:and' alarm panel: indications:which'will: simulate plant: .
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conditions. 'The Controllerzwill also: provide information on the ' j status of plant / systems to the' extent that such status would !
normally.be indicated in the Control. Room. :l
- 3. Plant parameters will be displayed _.on a'. simulated SPDS' system in'the-Control Room, TSC,-PTFC, OSC, and EOF.. Critical Plant Parameters were developed using,the OCNGS Basic' Principles. Training-Simulator. I TheseLparameters were then loaded into the simulated SPDS system:
data files. .The simulated SPDS will be available-at all ERFs where. ;
[ SPDS-is available. The OSC SPDS is presently being installed. If .i l' it is not installed by the Annual' Exercise.SPDS will not'be j
-simulated in the OSC. U f 4.' Control Room instrument-indications that are important to the f scenario will be posted. These include such items as: Ventilation l
System, Area Radiation Monitoring' System, Meteorological-Monitoring l System, and Effluent Monitoring System, as indicated'in the scenario. Critical Plant Parameters will be posted'only?if.the' ,
simulated SPDS fails, d a
4 5. Exercise participants will be prestaged at the appropriate }!
facilities.as follows:
i An additional shift of operations personnel will be. stationed to watch the plant during the drill. -They are necessary to ensure nuclear safety and will be exempted from the exercise.
1 Security guards necessary to ensure site security will be stationed and will be exempted from the exercise.
Some maintenance workers may be exempted from the drill to support pl nt operations.
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, 3 ANNUAL EXERCISE ~ .SCENARZO No. 88 <
OCNGS. REV.: 0 - d
- observer will' play the part of' industry: support staff as-
-outlined in the AEOF' mini-scenario.
An observer will play ^the part-of citizens and media-individuals making telephone:. inquiries as outlined'in the
!Public Information mini-scenario. t
.l Personnel may be deslynated to perform as evacuees.as. outlined '
.j in the Site Evacuation to FRAA mini-scenario.- -i
- 6. The drill?will commence with a postulated plant. incident"which will initiate the declaration of an' Unusual Event and,will escalate to'an- 'l
' Alert. - and then to:a. site Area amaroency.
]
- 7. : Drill; players will perform,1as appropriate,: radiological monitoring-and dose assessment-activities to the. extent appropriate:to the M scenario.- This will' include actual sampling onsite and-offsite. '
- 8. At least two (2) offsite Radiological Field Monitoring, Teams and one.
(1) onsite Radiological Field Monitoring' Team:will.be dispatched for i the purpose of testing response time, communications; .and' monitoring; and sampling procedures.. The field teams will gather = sample:
material.and route those samples for analysis.
Each Radiological Monitoring Field Team will'be accompanied by an ,
observer.throughout'the drill. .Each; field team will rendezvous-with .
its observer at the: location at'which it obtains its emergen'cy: kits. .3
- 9. All emergency response facilities, as mentioned in.the " Objectives," .
will be manned and will perform their. prescribed functions as' a appropriate to the drill scenario. ..;
i
- 10. The Prompt Notification will not be activated. g.
g.
ll .c The Emergency. Broadcast System will not be activated..
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-ANNUAL EXERCZSE SCENARIO NO.-22 4 OCNGS REV.- 0; P
g 12. Where possible, actual-samples will be obtained and analyzed. . It must'be' realized this is dependent on plant status and management
-priorities.- As RAGEMS is now the-routine effluent monitoring' j
[i' . system, it cannot be aligned to its post accident, sampling k configuration for-the exercise.- A sample cartridge will be prestaged for pickup. The operations to. drop the cartridge will~be
' simulated but will be observed.1 Since there is no core-damage '
i
- h. postulated in this scenario, a. PASS sample.would not be approp'riate. I
- 13. The scenario will require the assembly land accounting for non-essential site personnel. . Personnel may be allowed:to return.to
{ duty after accountability is completed.
l l
14 . - _ Exemptions'from' accountability may be allowed if the work ~1s (9
critical to plant operations. A11'such exemptions will be approved in advance by plant management.
1
- 15. - Emergency management may decide to evacuate non-essential personnel f from the'aite. Preparations for the evacuation will be observed,- j
-but the evacuationLwill only include'a.few (4-6). individuals from i the Emergency Assembly Area. LThis is outlined.in the mini-scenario
'for evacuation to FRAA.
- 16. Participation by GPUNC onsite personnel directly involved in i
{; responding to an emergency shall be carried out to the< fullest
-{
extent practical, includingLthe deployment-ct,the radiological ~ ;
monitoring teams, emergency repair teams, and other emergency? i
' workers.
However, drill participation shall not be carried to-thel 1 extent of manipulating plant equipment.or deviation from Rad Con, Safety, Security, or other plant procedures. Thysrequirementmay l at times delay scenario play while actions are taken to ensure procedural compliance. This delay shall not be construed as ,
detracting from team response.
- 17. Initial conditions are given in thel Control Room. Initial conditions that would normally be.known by. plant staff regarding !
current plant conditions may be communicated by-drill Controllers in other locations at a convenient time before or during the drill. ;
Examples of this would be identification of on-going maintenance and ;
out-of-service systems; simulated " Plan of the Day" meeting minutes; simulated STA plant status reports; and " Drill". log entries.
- 18. If required by the drill' scenario, alternate means of accessing the )
plant shall be prepared but n21 actually implemented. l
- 19. Mini-scenarios identify additional specific player actions and any ,
simulations necessary.
AESCEN90/17/ Disk 8 a
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' ;. ANNUAL ~EXERC2SE SCENAR2O NO. 22' 1 i
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T-TIME MAJOR EVENT MESSAGE CONTENT MSG. NO DELIVERED BY -DELIVERED TO1 EXPECTED ACTIONS T=~00:15 Pre-drill' Initial conditions - PD-1 Plant Data -Control Room Brief =high winds'from- -
Controller ' Staff -
westerly direction m
T=00:05 Increasing Leak, rate recorder PD-2 Plant Data Control-Room. Verify readingi .
unidentified indicates 6gpm controller Staff through radwaste..
leak rate in- . pump run times side Drywell - Declare Unusual Event.- Controlled ~
- shutdown initiated.
Vent-Drywell to:
~
T=00:10 Drywell Drywell pressure .
pressure in- indicting 1.5 psig and control' pressure creasing increasing less than'3~psig
' Peak RAGEMS' read-
~
ings due'to-venting are BKGD
- .4
' Intake water level PD-3 ., Intake Control Room- Monitor intakei T=OO:20 - Decreasing' measured by staff. '. Observer Staff flevel. Update-intake water notifications.
~
level gauge -2.25 ft.-
~
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AETML!i90/1/ Disk 8 6
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- AtS!UAL EXERCISE SCENARIO NO.
OCMGS REV . ' O . :
4.0 EXERCISE GUIDE T-TIME MAJOR EVENT MESSAGE CONTENT MSG. NO DELIVERED BY DELIVERED TO. ' EXPECTED ACTIONS I Implement EOPs T=OO:30 Major leak Increasing Drywell ' respond to Drywell '
RC pump seal humidity leak. Declare failure Alert due to leak:
>50 com T=OO:32 Rx scram on Complete scram hi Drywell actions pressure T=01:00 Fouling of Intake water level PD-4 Intake Control Room Initiate actions to intake water measured by staff Observer Staff clean screens.
screens gauge -2.6 ft.. Grass Update'notifi-appears to be-fouling cations screens severely.
T=O1:30 " Fire on site" Report of fire onsite MB-1-1 Fire Brigade' . Control Room. Fire Brigade.
Initiation of in permanent plant Observer Staff respond to fire mini-scenario structure ' location B-1 T=01:40 Fire Brigade Description of MS-1-2 Fire Brigade . Fire Brigade Perform fire arrives at conditions Observer Leader fighting. Request' scene offsite assistance AETMLN90/2/ Disk 8
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REV. O
-OCNGS.
4.0 EXERCISE GUIDE T-TIME MAJOR EVENT MESSAGE CONTENT MSG. NO DELIVERED BY DELIVERED TO EXPECTED ACTIONS.-
. Evacuation of PEB MB-1-3X Fire Brigade Fire Brigade Evacuate PEB 3 T=O1:45 Fire threat to PEB requested Observer Leader Commence fire ~
T=OI:55 Offsite suppression assistance arrives News media Media personnel DC-1. Security _ SPO Gate 30 Direct news media T=O2:OO question signs of Observer or SPO Gate 29 personnel to Joint or later question Secur-onsite fire smoke Information Center ity Protection Officer Forked River FD radio transmission Extent of. damages MB-1-4 . Fire Brigade Fire-Brigade Report to Control.
T=O2:10 Fire is out Room' observer Leader or later MB-1-5 Fire-Brigade Fire Brigade Fire watch posted _.
T=O2:15 PEB declared Personnel may return to building observer '. Leader occupants return or later safe Decreasing Intake water level PD-5' Intake- Control Room .. Declare SAE due to .
T=O2:30 Staff intake level --
measured:by' staff Observer intake wate initiate alter-1 level . gauge'-3.2 ft. ESW native Decay Hoat.-
and SW pumps are not Removal (DHR) running efforts AETMLN90/3/ Disk 8
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OCNGS REV. O 4.0 EXERCISE CUIDE T-TIME MAJOR EVEN'I MESSAGE CONTENT MSG. NO DELIVERED BY DELIVERED TO. -EXPECTED ACTIONS.: ,
T=O2:45 Iso Condenser Status of Iso Con- MB-2-1 Plant Data Control Room Monitor indications A leak init- denser Valve V-14-30 Controller- Staff isolate Iso iated. Condenser.
Initiation of mini-scenario B-2 Petk RAGEMS read-..
T=O2:45 Elevated -ings are 160 cps release begins Dispatch Field-Monitoring Teams downwind T=O2:45 Activate GE- Request.GE support -DC-2 PTFC Observer 'Le'ader Tech.~ Comply'with~
or later support Support ' request T=O3:OO Public Info Simulated calls by. Direct' caller to request'- public to plant appropriate " Rumor Initiation of. telephones controla phone mini-scenario number.
B-4' T=O3:15 Identify cause' Fuse in breaker cubicle NB-2-2 Iso condenser. '
' Iso Condenser iReplace. fuse or later of loss of #V-14-30 is blown- Observer inspection team
. power to V-14-30 T=O3:30 Initiation of For exercise: demon- MB-3-IX' Lead Emergency Evacuate non-mini-scenario stration evacuate'frotu Controller Director essential personnel B-3 .EAA to FRAA to Forked River-
'. Remote Assembly .
Area 1
AETMLN90/4/ Disk 3
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SCENARIO NO.'
AtJtJUAL EXERCISE Oct2GS REV.-0 4.0 EXERCISE GUIDE
~ MESSAGE CONTENT MSG. NO DELXVEREU-BY. DELIVERED'TO- EXPECTED ACTIONS T-TIME MAJOR EVENT I
i i MB-5-1 EAC Observer' Group Leader Process persorinel-i T=O3:30 Additional Arriving G.E. '
- support personnel Admin. at-AEOF for plant;
] astistance access:
l arrives at plant.
Initiation of mini-scenario B-5 MB-3-2X security security at. Simulate opening T=O3:36 Evacuation of Do not actually open Observer EAAl doors Warehouse doors 130D and 139B .,
Direct news media
~
Media personnel DC-3 -Security. SPO Cate 30 or. ,
T=O3:40 News media question signs of Observer' SPO Gate 29 personnel.to Joint or later question Secur- Information_ Center-ity Protection site evacuation Officer ipersonnel leavinal Group Leader from G.E. M3-5-2 AEOF Observer ' Group Leader Initiate-T=O3:45 G.E. personnel. ' processing MB-5-3 - MCF' arrive at AEOF Response Team introduces self .
Valve V-14-30 can be MB-2-3 Iso Condenser -Iso Condenser Report status to-T=O4:OO Restoration of- OSC Observer inspection team
.or later power to closed V-14-30 AETMLt390/5/ Disk 8
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4.0 EXERCISE GUIDE T-TIME MAJOR EVENT MESSAGE CONTENT- MSG. NO DELIVERED BY- DELIVERED TO . EXPECTED ACTIONS s
T=O4:02 Intake canal Intake canal level PD-6 Intake Control. Room. Start ESW and S.W.;
rising --2. 8 f t . Observer Staff. pumps-T=O4:15 RAGEMS reading ESD informed going down T=O4:30 Emergency . Establish recovery.
management ~ organization >
implements termination T=05:OO Terminate Secure from Drill drilli 5
4 4
. AETMLN90/6/ Disk 8
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J ANNUAL EXERCISE SCENARIC NO. 22 OCNCS -REV. O s
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5.1 Assignments 5.2 ' Facility Telephone Numbers.
- 5.3 critique Forme 4
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ANNUAL EXERCISE SCENAR30 NO. 83-y- .OCNGS REV. 0-(5.1fAssionmenta
' ECC :- z p ' Plant Data Controller T. Blount l '. Operations Observer ~ J..Boyle-Rad / Chem Data Observer .W..Barnshaw
- 'TSC Lead Controller _ R.'Sullivan j Radiological. Assessment Controller J. Bontempo '
t R. Perry.
{.
TSC. Observers IW. Stewart: q LD. McMillan :
G .' Sevcik OSC 'l
.OSC Controller -I. Wazzan--
~OSC Observers- .T. Jenkins
'S. Lutz. j W. Southard' :)
-D..Knipple-'
W. Quinlan l
Chemistry Observer K. Brown }
Radiological 10bservers P.-Calandra: j J.vDerby _)
R. Heffner Fire Brigade Observer .T. Prosser Onsite Monitoring Observer B. Sands. -
Security Observe,re "
R. Finicle S. Michelson, ,
Media Controller B. DeMerchant.
-I EOF L EOF Controller L. Lammers j EACC/BNE Controller K. Burkholder Offsite Monitoring Observers L. Thompson R. Turner PTFC Observer R. Markowski
)
AEOF Observer R. Utzat i 1
AESCEN90/25/ Disk 8
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>(ANNUA $. EXERCISE SCENARIO NO.--83
- .OCN88- .
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-REV.'0 1
l- l Facility Talenhone Nn=%rs. .
'1
~ 5.2 0 comitroller Location ' Number Control Room '971-4959 E-Tech; Support Center. 971-1379 9 '< 1-415 8 - ,
9/1-0961' '
--t p; Operations Support conter' 971-4240
,5 4 > ,
,Ernergency Operations' Facility; (201);367-8771-(201).'.'362-8812- ; }l Shift 1 Commander Office, Maio Gate 1971-4954- l
-971-2159- .!
.3
-Emergency Preparedness. Office. 971-4011 '
- (Building'12.Page Announcement)
- Me'dia '. center . -(201) 240-1630:
-(201).240-1631- 1 (201)~-240-6466 i
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ANNUAL EXERCISE SCENARIO NO. 22 OCNGS- P2V. O s
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( Section 6.0 I
6.1 Pre-exercise Briefing j 6.2 Initial Conditions
( 6.2.1 Plan of the Day - Horning Briefing 6.2.2 STA Plant Status Sheet 6.3 Radiological Assumptions
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ANNUAL EXERCISE SCENARIO NO. 22 OCNGS REV.~ 0 L.
- 6.1 Pre-emercina Briefing A.- The Group Shif t Supervisor may terminate the exnecise at any time plant conditions warrant.
U 8. Take'no actions that affect unit or non-exercise related operations.
C. Take immediate action (s) to restore safe operation if an unsafe
(~ condition exists.
becomes a concern.
Ignore exercise situation if actual safety D. All simulations and verifications will be expressed in spoken words.
E. Exercise events will be initiated.by the drill controllers issuing message cards, plant status sheets, alarm window cards, and verbal instructions as appropriate.
F. Controllers will provide appropriate information at the location where that information would normally be available (e.g., reacter status at the control Room, dose rate readings with field teams, etc.).
G. Only selected parameters and readings will be provided. The selected information will be sufficient to make decisions in accordance with Oyster Creek plans and procedures.
H. The purpose of the exercise is to test Emergency Plan Implementing l Procedures and implementation of the major aspects of the Emergency. '
Plan. DO NOT BECOME OVERLY CONCERNED WITH THE MECMANICS OF THE REACTOR OR THE CAUSE OF THE ACCIDENT. THIS EXERCISE IS DESIGNED TO TEST OYSTER CREEK PLANS AND PROCEDURES AND IS NOT CONCERNED WITH ESTABLISHING THE PROBABILITY FEASIBILITY, OR DETAILED KECHANICS OF THE SIHULATED ACCIDENT. i I. There will be one or more Observer / Controller at each important location. Controllers will provide information and clarification on which actions are to be simulated or are outside the scope of this exercise in order to keep the exercise progressing in accordance with the scenario. Observer / Controllers will also observe all ,
f_ aspects of the exercise to prepare an in-house evaluation of plans, j procedures, and training. !
J. All exercise related public address announcements and offsite communications will begin and end with the statement "THIS IS A DRILL, THIS IS A DRILL"..~.
AESCEN9D/25/ Disk 8
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. l ANWUAL EKERCISE
- i SCENARIO NO. 82
'OCNGS REV. O .
6.1 Pre-awareiam ariefine teentinued) .
K. Initial Response Emergen:y Organisation and the Emergency Support organisation will respond to the exercise.
l
'L. The Drill Controller may authorise the Controllers to modify the scenario to fit utiusual conditions or events to maintain the scenario within the scope of the exercise objectives and in order to i maximise the practical training benefit presented by tho' exercise -
experience.- If.a modification is made, the controller should report- s to the Drill controller what changes were mado.- '
M. If samples inside or outside the site are deemed necesuary, they ;
will actually be collected, if possible, and their analysis -:
conducted or simulated as directed by a controller. Observer will .
accompany the survey teams both onsite and offsite.
N. This' exercise is conducted to evaluate plant plans and procedures. ;
The exercise is also a training vehicle for members of the oyster -
Creek Emergency Response Organisation to practice working together }
with outside organisations. Please make note of any improvements in ;
any area that you observe as a participant and submit them to the observer / Controllers at the conclusion of the' exercise. +
i NOTE: Answer questions from shift personnel regarding the exercise before i proceeding to T=00:00 Major Scenario Events..
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ANNUAL EXERCISE- SCENARIO NO, 22
' OCNCS REV. 0
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' ANNUAL EXRRC!st SCENARIO N). 22 i ocNos 'Arv. o 1
~6.2 initial conditions j'I Initial conditions operating at approximately 100%. j Load limited by 'A' Recirc Pump oos / 'C' Recirc Pump Cenerator AMPS Major equipment out of service / Tech spec items: j
-t
- #1 Dilution' Pump .
- 1-2 storam Packing Exhauster, j
- Service Water Radiation Monitor
- Drywell Recirc Fan 1-2. ~j
- 1-Sfsump Rad. Monitor
- off-gas riow Transmitter. . }
- Torus /DW Vacuum Breaker V-26-7 l
- * 'ARecire aump
- Iso condenser 'B' Major planned evolutions and testing ;
- Repair V-14-32' f
.i significant Events / comments ;
- Unidentified leakrata continues'to'be higher than normal; latest .
four hour average is 4.03 oPM. The unidentified leakrate is being -
-calculated on an hourly and four hour basis.
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i E-ANNtJAL EXERCISE SCENARIO No. 28
{ OCNCS REV. 0 l h *THIS 18 A DRILL * ,
f PLAN OF THE DAY - MORNING BRIEFING !
( ;
-- Persistent westerly. winds have been occurring for.the past two days. ;
-Canal level is .5', high tide is expected at 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br />. ,
i
-. Plant is operating at approximately 100% power. .Drywell leakrate appears- -r to be stable at approximately 4.0 ppm unidentified, operation will
[ centinue until leakrate reaches 4.5 gpm, then commence an orderly shutdown .;
for repair of,'A' Recirc Pump seal. 1 F
[-
-- Load limited by: 'A' Recirc Pump out of service and 'C' Recire Generatar. l
{L - Amps. j Major equipment out of service: 'f
- 1 Dilution Pump {
Service Water Rad. Monitor- ,
1-5 Sump Rad Monitor
'A' Recirc Pump 1-2 Steam Packing Exhauster
- Drywell Recire Fan 1-2
- off-gas Flow Transmitter Torus /DW Vacuum Breaker V-26-7
- Iso condenser 'B' out of service due to V-14-32 T.S. clock 7 days / 6 days left Major planned evolutions:
Repair 'A' Recire Pump Seals Repair V-14-32 when parts arrive from the vendor later today AESCEN90/33/ Disk 8
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._.........._...,_.........1,..,......i._.
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. . . . . _ . . . , . _ . - _ . _ . . , _ - - . . . . _ _ . . . . . . - . _ . . . . . . . - . . . . . - , . . . - - . _ _ . - . . ~ _
? DRIED SH2fT TECHNICAL ADVISOR PLANT STATUS SHEET STA P..C. DRZLL DATEt 4/26/90
( )
cYSTER CREEx NUCLEAR GENERATING STATION TIMES 06:10
- MODE sWZTcHs MS RAD LEVELS (Vh*ZTS) t RUN A-100 2-137 C-137 D-12 7 i
l AOGt IN SERVICE OTT-GAS ACTIVITZ'(UNITS) 106 flis REACTOR POVERS CONY. TACT. 92 / 90' DATE 3/14/90 v 1896 MWTH 640 MWE(GROSS) 619 MWE(NET) STACK GAS ACTZVITY(CPS) 11 / 12 98.2%TP(THERMAL) r 99.8%KDC NET (620)
MAIN STEAN TLOW 7.53 MLB/HR TEED PUMPSs ALL ON '
STCAM CNEST PRESS 960 PSIG TEED TLOWs 7.03 MLB/HR RX LEYEL 160* TAT (YARVAY) TECD TEMP,(TINAL) .107.6 7 (
RX PRESS 102C PSZG (NR ) COND. DEMZN bP '36 PSID THERMAL LIMITS (% of LL2 tit /Eocation).
(TZMEt04:32)
~
CONDENSER VACs 28.6 /28.7 /28.1 "HG
~MCPR 89.2 9 29 16 BAROMETERt 30.12* HG MLMGR 73.2 0 29.16 37 ZNTAKE TEMPT 42.3 i BRIDGE TEMPT 31.8 T MAPLHGR 80.5 0 29 18 37 DISCHARGE TEMP 63.1 F L PCZ (XW/TT) 0.20 0 31 16 37 ! '
RX CHEMZSTRY DATE 4/25/90 RECZRC PUNPS BoCoDoC ON TZME 10:45 POWER 1878 MWTH '
TLOW 14.33 X 10E4 GPM PHs 6.24 9 26 C CORE DP 16.51 PSZD CONDt 0.077 US/CMo CLt 0.40 UG/L' ;
Z-131 8.37E-4 UCZ/ML(DOSE EQUZY) '
HWC NA ECP NA MV RX CONTAINMENTt i
DV PRESS 1.19 PSIGo TEMP 125. 7 T(BULN) CHLORINATION STATUS TORUS PRESS 1.1 psige TEMP 62 T CIRC VATER OOS TORUS LEVEL 148.0 IN. SERVICE WATER 00T NRW / AOG 003 '
TRUNNZON ROOM TEMP 140 F '
RBCCW TEMP 69 T LEAXAGEt (GPM) Based on 24 HOUR AVG '
TDCCU TEMP 80 F UNIDENTITZED 3.72 ZDENTZTIED 4.75 i
CONTINUOUS DAYS ONLINEt 51 LOAD LZHZTED BYt 'A ' RECZRC PUMP 005 / 'C' RECIRC PUMP AMPS l
HA70R EQUIPMENT OUT OF SERVICE / TECH SPEC ITEMSt
- 1-5 SUMP RAD MONITOR
- SERYZCE WATER RAD MONITOR
'
- NO . 1 DILUTZON PUMP
- PUNP
- 1-2 STEM PACKING EXHAUSTER y
- 1-2 DW RECZRC TAN
- OPT GAS TLOW TRANSHITER
- TORUS /DW VACUUM BREAXER V-26-7
- 'A'
- RECIRC PUMP (SEAL LEAX) 'B ' IC (V-14-32 005) 7 DAY TS CLK MAJOR PLANNED EVOLUTIONS AND TESTINGt
- TROUBLE SHOOT AND ~ REPAIR V-14~32.
SIGNIFICANT EVENTS / COMMENTSt
- UNIDENTIFIED LEAKAGE CONTINUES TO BE HIGHER THAN NORMAL. LATEST 4 Hr AVERAGE IS 4.03 GPM. THE LEAX RATE IS BEING CALCULATED ON THE HOUR.
- V-14~32 WOULD NOT OPEN DURING AN ZC VALVZ OPERABILITY TEST MAINTENANCE IS INVESTIGATING THE PROBLEN.
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ANNUAL EKERCISE: SCENAR20 NO. 22 OCNGS REV. O s
6.3 Radiological Assumptions
~
- 1. Sourca Terms
[ Cladding failure le postulated as occurring during this drill.
The activity in the plant is tracked in the RADDKAPP ocenario generation code. .The code tracks activity transport throughout Loyster Creek and= includes isotopic radioactive decay and daughter product buildup, gaseous and liquid partition of chemical species, plateout of chemical species, and filter efficiencies for filter trains and liquid filtration-in the' torus water. The specific values used for each chemical are listed'in the table below:
Chemical species Cas-liquid HEPA Charcoal Deposition Partition. Efficiency Efficiency Velocity (mps)
Noble Cases .99 .01 .01 0.
{
Haltgens .001 .90 .95 .005
( Cesium, Rubidium .001 .90 .99 .001 strontium, Barium .001 '. 99 .99 .001 Tellurium .001 .99 .99 .001 Molybdenum, Ruthenium .001 .999 .999 .001 Y, la, & Ce .001 .999 .999 .001 l
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ANNUAL EXERCISE SCENARIO No. 22 ;
OCNGS .REv. O I
II. In-nlant kadiation Demaa onsite exposure rates are calculated by the RADDMAPP scenario g ,
generator. RA00NAPP utilises the QAD-CG gamma shielding code to gj calculate all onsite radiation exposure rates.-
RADDMAPP considers contributions from Core Power Operations, Core:
Fission Product Activity, Drywell Shine, Torus Shina, Reactor lL 3 (
l Building shine, Local Airborne Concentrations, Contaminated Piping, ll l and the Release Plume. j Reactor Building dose rates.and' airborne concentrations are. elevated ll due to an Isolation condenser line rupture at T=02:30 until the line' L is. isolated at approximately T=03:45. This will also be the source-for the elevated release through the stack.
l g
i III. offaite Data The radioactive releases from the plant are calculated using 1) the RAC code. f a) The main release from the plant stack is modeled by RAC as an elevated release using-a finite plume model.
II
- 2) The data for Emergency Air Sampling is derived from -
9473-IMP-1300.11.
- 3) The BNE air sample data calculated assumes'a 10 minute sample h collection at 3 cfm and a 5 minute sample counting as' -I described in the BNE's procedure. The sampler efficiency'io assumed to be 1.5%.
- 4) Iodine deposition is calculated'using the method described in i Reg. Guide 1. Direct frisker readings are calculated as recommended by NUREG/R-3365. Smear readings assume a-detector. l'g -
efficiency of lot. W:
IV. Onsite Radiation Deses Onsite exposure rates are the sum of overhead shine from the stack l release and direct shine from the stack activity in the Reacter Building and activity in the Turbine Building. I 1
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AESCEN90/32/ Disk 8 q
.- .- - - - . ~ .
y SCENARIO NO. 22 REY. .O J
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l Section A rupporting Data A Operational Data-A-2 Meteorological Data A-3 Source Term and Radiochemistry Data 1 A-4 offsite Radiological Data A-5 Onsite Radiological Data A-6' Hessage cards I
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. i ANNUAL ~ EXERCISE SCENARIO NO. 22 -
s OCNGS REV. O i
F Section A-1 A-1.0 Critical Plant Parameters-A-1.1 Critical Plant Parameters Summary A-1.2 .KVAC System Status '
. A-1.3 Annunciator Status sheets A-1.4 Radiation Monitoring System Data ,
A-1.5 RAGEMS Data M
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Oct1GS SCENARIO 22 AlitlUAL EXERCISE REV NO- O TABLE A-1.0a CRITICAL PLANT PARAMETERS
_---- -=__
To Be Used in Case of BPT Failure RPV Level (in TAF) 160.
. RPV Pressure-(psig) 1020.
RX Coolant Temp. (F) 526.
100.
D.W.Reactor Power {%)
Pressure-(psig) '1.0 D.W. Temperature (F) 131.
Torus Temp. (F) 74.
Torus Level (inches) 144.0 D.G. #1 Load (KW) O.
D.G. #2 Load (KW) O.
CST Level (ft) 30.0 RX Bldg Vac (in H2O) .25 T-Time (hr: min) 00:00 Clock Time (hr: min) l Torus Pressure equivalent to Drywell Pressure Y
, a v < r , -- u..N .ee- .---n n,~~ + , ,- ,-w g ,ec , - n,- ~.,
' O CliG S - SCENARIO 22 Ati!3UAL EXERCISE REV NO O .
TABLE A-1.0b CRITICAL PLANT PARAMETERS To Be Used in Case of BPT Failure i
RPV Pressure (psig) 1020. 1020.
RX Coolant Temp.' (F) 526. 526.
heactor Power (%)
100. 100.
D.W. Pressure (psig) 1.0 1.4 D.W. Temperature (F) 131. 135.
Torus Temp. (F) 74. 75.
- Torus Level (inches) 144.0 144.0 D.G. fl. Load (KW) O. G.
D.G. #2 Load (KW) O. O.
CST Level (ft) 30.0 30.0 RX Bldg Vac (in H2O) .25 .25 T-Time (br: min) 00:00 00:05 Clock Time (hr: min)
Torus Pressure equivalent to Drywell Pressure
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OCNGS SCENARIO 22 ANf3UAL EXERCISE REV NO' :6' --
TABLE A-1.0c ,
CRITIbAL PLANT PARAMETERS To Be Used in Case of BPT Failure RPV Level (in TAF) 160. 160. 160. ~.
RPV Pressure.'(psig) 1020. ~ 1020. . 1020.
RX Coolant Temp. (F) 526. 526. 526.
Reactor Power (%) 100. .100. 100.
D.W.. Pressure (psig) 1.0 -1.4 1.7 D.W. Temperature (F) 131. 135. 138.
Torus Temp. (F) '74. 75. 75.
Torus Level (inches) 144.0 144.0
~
144.0 D.G. #1 Load (KW) O. O. O.
D.G. #2 Load (KW) O. -0. O.
CST Level (ft) 30.0 30.0 30.0 RX Bldg Vac (in H2O) .25 .25 . . 25 T-Time (hr: min) 00:00 ' 00:05 - 00:10 Clock Time'(hr: min)
Torus Pressure = equivalent to Drywell-Pressure
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OCNGS s A!Jr1UAL EXERCISE SCENARIO 22-REV NO O TABLE A-1.0d CRITICAL' PLANT PARAMETERS
- To Be Used in Case of BPT Failure
.t h
RPV Level (in TAF) 160. 160. 160. 160.
RPV Pressure (psig) 1020. .1020. 1020. 1020.
RX. Coolant' Temp. (F) 526. 526. '526. 526.
Reactor Power (%)
D.W. Pressure (psie) 100. 100. 100. ~75. ,
1.0 l'. 4 1.7 2.3 ;
D.W.~ Temperature 1.9 131. 135. 138. 140.
Torus: Temp. (F, 74. 75. 75. 75.
TorusD.G.
Level.(inches) 144.0 144.0 144.0 144.0 ;
- 1 Load (KW) O. O. O. O. i D.G. #2 Load (KW) O. O. O. 0.
CST Level (ft) .30.0 30.0 . 30.0 '30.0 RX Bldg Vac (in H2O) .25 .25 .25- .25
.T-Time (hr: min) 00:00 . 00:05 00:10 00:15 Clock Time (br: min) i i
Torus Pressure equivalent to Drywell Pressure ~
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SCENARIO'22 AtitlUAL EXERCISE - REV NO O TABLE A-1.0e CRITICAL PLAllT PARAMETERS To Be Used in Case of BPT' Failure RPV Level (in TAF) 160. 160. 160. . 160. 160.
RPV Pressure (psig) 1020. 1020. 1020. 1020. 1020. '
RX-Coolant Temp. (F) 526. 526. 526. 526. 526.
Reactor Power (%) 100. 100. 100. 75. f70.
D.W.~ Pressure (psig) 1.0 '1.4 1.7 2.3 2.3 D.W. Temperature (F) _131. 135. 138. 140. 145.
Torus Temp. (F) 74. 75. 75. 75. 75.
Torus Level (inches) 144.0 ' 144.0 144.0 144.0 144.0 D.G. #1 Load (KW) O. O. O. O. 10 .
D.G. #2 Load (KW) O. 0. .
O. O. O.
CST Level (ft) .30.0 30.0 30.0 30.0 30.0 RX Bldg Vac (in'H2O) .' 2 5 .25 .25 .25 .25 T-Time (hr: min) 00:00 00:05 .00:10 00:15 00:30 Clock Time-(br: min) .
Torus Pressure equivalent to Drywell Pressure-W e
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, OCf1GS SCENARIO.22 '
- i. AN!!UAL EXERCISE REV NO .0
' TABLE A-1.0f CRITICAL PLANT PARAMETERS i
To-Be Used in Case of BPT Failure RPV Level ( in -- TAF) .-160. .160. 160. 160. 160. 149. t RPV Pressure (psig) 1020. 1020. 1020. 1020. ~ 1020. 800.
RX' Coolant Temp..(F) 526. 526. 526. 526. 526. '510.
Reactor-Power ^-(%) '100. 100. 100. 75. .' 7 0 . O. -
D.W. Pressure (psig) 1.0 1.4 1.7 2.3 2.3 11.3 D.W. Temperature (F) 131. 135. 138. 140. 145. 150.
Torus Temp. (F) 74. , 7 5. . 75. 75. '75. 78.
l Torus Level'(inches) 144.0 144.0 -144.0 144.0 '144.0 144.0 D.G..'#1 Load (KW) O. -O. O. O. .O. 0.
D.G. #2. Load (KW) 0. O. O. O. O. O.
l CST - Level - ( ft) :30.0 30.0 -30.0 30.0 -30.0 -30.0 RX Bldg Vac-(in H2O)
. 25 .25 .25 .25 .25 .25
, T-Time.(hr: min) 00:00 00:05 00:10 00:15 OJ:30 00:32 ,
Clock Time-(br: min) !
w
- Torus Pressure equivalent-to Drywell Pressure 4
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OCNGS SCENARIO 22 ANNUAL EXERCISE REV NO O TABLE A-1.0g ,
CRITICAL PLANT PARAMETERS To Be Used in Case'of BFT Failure RPV Level (in TAF) -160. 160. 160. 160. 160. 149.
800.
168.
724.
RPV Pressure (psig) 1020. 1020. 1020. 1020. 1020.
RX Coolant Temp. (F) 526. 526. 526. 526. 526. 510. 506.
Reactor Power (%) 100. 100. 100. 75. 70. O. O.
D.W. Pressure (psig) 1.0 1.4 1.7 2.3 2.3 11.3 '15.5 D.W. Temperature (F) 131. 135. 138. 140. 145. 150. 175.
Torus Temp. (F) 74. 75. 75. 75. 75. 78. '85.
Torus Level (inches) 144.0 144.0 144.0 144.0 '144.0 144.0 144.0 D.G. #1 Load-(KW) O. O. O. O. O. O. 'O.
D.G. #2 Load (KW) O. O. 0 .- O. O. O. 0. ,
CST Level (ft) 30.0 30.0 30.0 30.0 30.0 30.0 30.0 RX Bldg Vac'(in H2O) . 25 . 25 .25 .25 .25 .25 .25 T-Time-(hr: min) 00:00 00:05 .00:10 00:15 00:30 00:32 01t15 Clock Time (hr: min) i Torus Pressure equivalent to Drywell Pressure
-- " ' * - - ~ " *
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OCNGS SCENARIO'22:
AtillUAL EXERCISE REV NO O TABLE A-1.0h CRITICAL PLANT PARAMETERS To Be Used.in Case of BPT Failure RPV Level (in TAF) 160. 160. 160. 160. 160. 149. 168. 168.
RPV. Pressure (psig) 1020. 1020. 1020. 1020. 1020. 800. 724. 643.
RX Coolant Temp. (F) 526. 526. 526. 526. 526. 510. 506. 489.
Reactor Power.(%) 100. 100. 100. 75. :70. .O. O. O.
D.W. Pressure (psig) 1.0 1.4 1.7 2.3 2.3 11.3 15.5 . 15.7 D.W. Temperature (F) 131. 135. 138. 140. 145. 150. 175. '185.
Torus Temp.- (F) 74. 75. :75. 75. 75. :78.
. 85. 85.
Torus Level (inches) 144.0 144.0 144,0 144.0 144.0 144.0 144'.0 .145.0 D.G. #1 Load (KW) O. O. O. O. O. -O. O. O.
D.G. #2 Load (KW) O. O. O. O. .
O. O. 'O. O.
CST Levels (ft) 30.0 7 30.0 ..30.0 30.0 30.0 30.0 .30.0 30.0 RX B]dg Vac (in H2O) .25 .25 .25 .25 .25 .25 .25 .25 T-Time (hr: min) 00:00 .00:05 00:10 -00:15 00:30 00:32 01:15 -01:30 Clock Time (hr: min)
Torus Pressure equivalent to:Drywell Pressure.
-- .= = - = --- = - -
M M.. =
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OCNGS . .
- SCENARIO 22 ANNUAL EXERCISE REV NO. "O TABLE A-1.01 -
CRITICAL : PLANT PARAMETERS To Be-Used in Case of BPT Failure RPV Level (in TAF) 168.
RPV Pressure (psig) 563.
RX' Coolant Temp. (F) 472.
Reactor Power (%) D.
D.W. Pressure (psig) 15.3 ,
D.W. Temperature (F) 200.
Torus Temp. (F) 85.
Torus Level (inches) 145.0 D.G. #1 Load (KW) O.
D.G. #2 Load (KW) O.
CST Level (ft) 30.0 RX Bldg Vac (in H2O) .25 T-Time-(hr: min) 01:45 Clock Time (hr: min)
Torus Pressure' equivalent to Drywell' Pressure i .
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'OCNGS ANNUAL EXERCISE SCENARIO 22' REV NO :0-
-TABLE A-1.0j CRITICAL PLANT PARAMETERS
- ----------------=- .- _
To B'a Used in Case of BPT Failure-4 RPV Level (in TAF) 168. 168.
RPV Pressure (psig) 563. 482.
RX Coolant Temp. (F) 472. 456.
Reactor. Power (%)
D.W. Pressure (psig)
O. O.
- 15.3 15.0 D.W. Temperature. (F) 200. 205.
Torus Temp. - (F) 85. 84.
Torus D.G.
Level.(inches) 145.0 145.0 ,
- 1 Load'(KW) 'O. O.
D.G. #2 Loadf(KW) O. O. +
CST Level'(ft) 30.0 30.0 RX Bldg Vac-(in H2O) .25- . .25 T-Time (hr: min) 01:45 02:00 '
Clock Time.(hr: min)
Torus Pressure equivalent to Drywell Pressure i _
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OCNGS r
AlmUAL EXERCISE _
SCENARIO 22 TABLE A-1.Ok . REV.NO O CRITICAL PLANT PARAMETERS
'To.Be Used-in Case of BPT Failure RPV Level (in TAF) 168. It a . 168.
RPV Pressure *(psig) 563. 462. 402.
RX Coolant Temp. (F) 472. 456. 439.
D.W.Reactor Pressure Power-(%)
(psig)
O.
.15.3 O. O.
D.W. Temperature (F) 15.0 15.0 200. 205. '208.
Torus Temp. (F) 85. 84. 84.
Torus Level (inches) 145.0 145.0 145.0 D C.
D.L.
11 Load ~(KW) O. O. O.
1- Load (KW) O. O. O.
CST Level (ft)
RX Bldg Vac (in H2O) 30.0 30.0 30.0
.25 .25 .25
- T i me (hr: min) 01:45 02:00 '02:15 Clock T ' na (hr: min)
Torus Pressure equivalent to Drywell Pressure A
e
,~ . , , . , - . - - -
- ~
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AtillUAL EXERCISE ' '
SCENARIO 22.
~REV NO O -
TABLE A-1.Ol' CRITICAL PLANT PARAMETERS To Be Used in Case of.BPT' Failure
-1 t)
RPV Level (In TAF) 168. 168. 168. .168. l RPV-Pressure (psig) 563. ~482. 402. -321.
RX Coolant Temp. .(F) 472. 456. 439. .422.
Reactor Power (%) 0. O. O. 'O.
D.W. Pressure (psig) 15.3 15.0 15.0 15.5 9
D.W. Temperature (F) 200. 2055 208. 212.
Torus' Temp. (F) 85. 84. 84. 84.
Torus : Level - (inches) 145.0 145.0 145.0 146.0 D.G. #1 Load (KW) O. O. -0. O. -
D.G. #2 - Load (KW) .-O. 'O. O. -0.
CST-Level (ft) 30.0 30.0 30.0 ' 3 0.' O RX Bldg Vac...(in H2O) .25 .25 .25 .25 T-Time (br: min) -01:45 02:00 02:15 02:30 '
Clock Time (hr: min)
, Torus Pressure equivalent-to Drywell Pressure- -4 i
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l i, i ii in ii== '
OCNGS SCENARIO 22
- Ati!1UAL EXERCISE REV NO 'O TABLE A--1. 0m -
CRITICAL PLANT PARAMETERS:
To'Be Used in Case of BPT Failure .
168. 168. 168.
482. 402. 321. 321.
RPV Pressure (psig) 563.
RX Coolant Temp. (F) 472. 456. 439. -422. 422.
Reactor Power (%) O. O. O. O. 'O.
D.W. Pressure'(psig) 15.3 15.0 15.0 15.5 16.0 D.W. Temperature (F) ~ 200. 205. 208. 212. 215.
. Torus' Temp. (F) ~85. ~ 84. 84. 84. 84.
Torus Level (inches) 145.0 145.0 145.0 . 146.0 146.0 '
O. ~0. -- 0 . O.
D.G. #1 Load-(KW) O.
O. J0. O.
.D.G. #2 Load.(KW) - O. O.
CST Level (ft) :- 30.0 30.0 30.0 30.0 30.0 RX Bldg Vac (in H2O) . 25 .25 .25 .25 .. 2 5 T-Time,(hr: min) 01:45 02:00 ..02:15 .02:30 02:44 Clock Time-(hr: min)
Torus Pressure equivalent to Drywell' Pressure
.j^
9
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'+" _ m .w. m.a_,,m,em.. w,..wa_,g.,K',[ q,.ie , 4._ g
- -T9' "4
,s' j~R -
OCllGS SCENARIO 22 Af3NUAL EXERCISE 'REV NO- 0
' TABLE A-1.On CRITICAL PLANT PARAMETERS To'Be Used in Case of BPT Failure -
RPV Level (in TAF) -168. 168. -168. I 168. 16E 168.
RPV Pressure (psig) 563. 482. 402. 321. 321. '321.
RX Coolant Temp. (F) .472. 456. 439. 422. 422. :400.
Reactor Power (%) O. O. O. O .- O. O.
D.W. Pressure (psig) 15.3 .15.0 15.0 15.5 16.0 16.5 -
D.W. Temperature (F) 200. 205. 208. 212. 215. 220. '
Torus Temp. - (F) 85. 84. 84. 84. 84. 84.
Torus Level (inches) 145.0 145.0 145.0 1146.0 146.0 .146.0 D.G. #1 Load (KW) O. 'O. O. O. .O. O.
D.G. #2' Load.(KW) 0. O. O. O. O. O. ,
!- CST' Level (ft) 30.0 30.0 30.0 30.0 30.0 30.0 RX Bldg Vac (in.H2O) .25 .25 .25 .25 -.25 .00 T-Time (br: min) 01:45 02:00 02:15 02:30 02:44 02:45 .i Clock Time (br: min)
Torut Pressure equivalent ~to Drywell Pressure J
t i
e
, ,w...-+ a.m-....eum, ;_+--n...n.-..wy--
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OCNGS f
ANNLAL EXERCISE. ~ SCENARIO 22. '
.REV NO i
TABLE.A-1.0o O CRITICAL PLANT PARAMETERS I
~
To Be Used-in Case of BPT Failure l .
l RPV Level (in TAF)~ 168. 168. 168.
RPV Pressure (psig) 563. 482. 402.
168.
321.
168. 168. 168.
RX Coolant Temp. (F) .472. 456. 439. 422.
321. 321; 17.
422. 1300.
D.W.Reactor Power (%) O. O. 400.
O. - O. O. O.
Pressure (psig) 15.3 15.0 15.0 ~0.
D.W. Temperature (F) 15.5 210. 16.0 16.5 ;17.0 205. 208. 212. 215.
Torus - Temp. -(F) 85. 84. 84. 84.
220. 235.
'84.
Torus D.G.
Level (inches) 145.0 145.0 145.0 146.0 146.0 1<6.0
- 84. 90.
- 1. Load (KW) O. O. O. 146.0 D.G. O. O. O. O.
- 2 Load (KW) O. .O. O. O. O. O.
CST Level-(ft) 30.0 30.0 30.0 30.0 30.0 . 30.0
-0.
RX Bldg Vac-(in H2O) . 25 .25 .25 . 25 30.0
.25 .00 .40 T-Time _(hr: min) 01:45 02:00 02:15 - 02:30 02:44
~
Clock Time (br: min) 02:45 _ 02:50 Torus Pressure equivalent to Drywell Pressure.
3 g q - pr,. se -- -9 req g_ 9 .,5- awa.,. -y--- y,'4g- 3 y -e l.iWW W v- g y g- $=3**v,yde y -- % * .en g- e y ' y 4e-.4 8y sg g . p.m- 3
3 ,
2
- O Cl1 G S I ' SCENARIO 22. :S
-AN11UAL EXERCISE REV'NO. O'
-TABLE A-1.Op.- '
CRITICAL PLANT PARAMETERS
+
To Be Used in Case of BPT Failure 4
RPV Level (in TAF) 168. 168. 168. -168. 168. 168. 168. 168.
RPV Pressuref(psig) 563. 482. .402. J321. 321. 321. 17. 17.
RX Coolant. Temp. (F) 472. '456. 439. 422. 422'. 400. .300. 300.
Reactor Power (%) O. .0. O. O. .- 0 . O. :0. O.
D.W. Pressure (psig) 15.3 15.0 15.0 15.5 16.0 '16.5 17.0 16;0 D.W. Temperature (F) 200. 205. 208. ~212. 215. 220. 235. 230.
Torus Temp. (F) 85. '84. 84. 84. .84. 84. 90. . '93.
Torus Level (inches) 145.0 145.0 145.0 146.0 146.0 146.0 146.0 .146.0 D.G. #1' Load (KW) O. O. 0. O. -O. O. O. .0.
D.G. #2 Load (KW) O. O. O.. 0. :0. O. O. .0.
CST Level.(ft) -30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 RX Bldg Vac (in H2O) .25 .25 .25 .25 .25 .00 1
.40 .60 .
T-Time -- (hr: min) 01:45 02:00 02:15 02:30 02:44 02:45 02:50 -03:00 .d Clock Time (hr: min)
Torus Pressure equivalent to Drywell' Pressure i
1 4
e t
s
_ _ _ _ _ _ _ _ _ . _ - _ _ _ _ _ _ _ . - - - = . . . - . . - - .- - . , . . - - , .. - - -. . . . .=
OCtlGS ANilUAL EXERCISE SCENARIO-22 REV NO- 20 TABLE A-1.0g CRITICAL PLANT PARAMETERS To Be Used in Case of BPT Failure RPV Level- (in TAF) 168.
RPV Pressure (psig) 17.
RX Coolant Temp.'(F) 300.
Reactor Power (%) O.
D.W. Pressure.(psig) 15.0 D.W. Temperature-(F) 194.
Torus Temp. '(F) 94.
Torus . Level- (inches) 146.0 1 D.G. #1 Load (KW) O.
D.G. #2-Load-(KW) 'O.
CST Level (ft) 30.0 RX Bldg Vac.(in.H2O) .' 4 0
.T-Time (hr: min) 03:15 Clock Time (hr: min)
Torus Pressure equivalent to Drywell Pressure i
e 0
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OCNGS SCENARIO 22.
x ANNUAL EXERCISE REV~NO~ 0 TABLE A-1.Or .
CRITICAL PLANT PARAMETERS To Be Used in Case of'BPT. Failure' i I'
RPV PressureJ(psig) 17. 17. ,
RX Coolant' Temp. (F) .300. 300. 2 Reactor. Power ~(%) O. ~0.
j D.W. Pressure-(psig) -15.0 13.0 .
D.W. Temperature (F) 194. 195.
!' Torus Temp. (F) 94. -94. .
l.. Torus Levele(inches) 146.0 146.0 .sl' D.G. #1 Load (KW) O. 'O. .
L D.G. #2 Load l(KW) O. O.
! . CST Level ' ( f t) 30.'O 30.0
!- RX Bldg Vac (in H2O) .40 -.20 1 T-Time (hr: min) 03:15 03:30 l- Clock Time (hr: min) l
~
l Torus Pressure equivalent to Drywell~ Pressure -
i 2
o
..- .. .-- - - -- - - .- 2.- -- - . - . . ~ . .- . - . . . - . .. .
-~ ~
OCNGS ~
. SCENARIO 22' Afil1UAL' EXERCISE REV'NO O TABLE A-1.Os CRITICAL PLANT PARAMETERS To Be.Used in Case of BPT Failure RPV Level (in TAF) 168. 168. 168.
RPV Pressure (psig) 17. ,17. 17.
RX Coolant Temp. (F) .300. 300. 300.
Reactc) Power (%) O. O. O.
D.W. Preswre.(psig) 15.0 13.0 12.0 D.W. Temperature -(F) 194. 195. 196.
Torus Temp. (F) 94. 94. 94.
Torus Level (inches) .146.0 146.0 146.0 D.G. #1 Load (KW) O. 'O. O.
D.G. #2 Load-(KW) O. O. O.
CST Level:(ft) '30.0 30.0 30.0 RX Bldg Vac-(in H2O) .40 .20 .10 T-Time (br: min) 03:15 03:30 03:45 Clock Time (hr: min) .
Torus Pressure equivalent to-Drywell Pressure
'm,-.,..m-._o
. - =- *. -
" ^
v
- A OCNGS SCENARIO-22
~ Allt1UAL ' EXERCISE REV No :0, -
TABLE A-1.0t '
CRITICAL PLANT PARAMETERS .
To Be Used in Case of~BPT Failure i
RPV Level (in TAF) 168. 168. 168. 168.
RPV Pressure (psig) 17. 17. 17. 23.
RX Coolant Temp. .(F) 300. -300. 300. 297.
Reactor Power (%) O. O. O. O.
D.W.' Pressure.(psig) 15.0 13.0 12.0 10.0 D.W. Temperature. (F) L194. 195. 196. 196, Torus. Temp. . (F) 94. 94. 94. 94.
Torus' Level (inches) -146.0 146.0 146.0 146.0 D.G. #1. Load (KW) O. .O. O. O.
D.G. #2 Load (KW) O. 'O. O. O. -i CST Level (ft) 30.0 ~30.0 30.0 30.0 RX Bldg Vac (in H2O) ' .40 ..20 .10
.10 T-Time.(hrsmin) 03:15 03:30 03:45 -04:00 Clock Time (br: min)
Torus Pressure equivalent ~to Drywell Pressure
- w. . -
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-w w w OCEIGS SCENARIO 22 AfillUAL EXERCISE REV NO O TABLE'A-1.0u CRITICAL PLANT PARAMETERS To Be Used in Case of BPT Failure d RPV Level (in TAF) 168. 168. 168. 168. 168.
RPV Pressure (psig) 17. 17. 17. 23. 3 0.-
RX Coolant Temp. (F) 300. 300. 300. 297. 293.
Reactor Power (%) O. O. O. O. 'O.
D.W. Pressure (psig) .15.0 13.0 12.0 10.0 0.
D.W. Temperature (F) 194. 195. 196. 196. 180.
Torus-Temp. (F) 94. . 94. 94. 94. 94.
Torus' Level (inches) -146.0 146.0 146.0 146.0 146.0 -
D.G. #1 Load (KW) O. O. O. O. O.
D.G. #2 Load.(KW) O. O. O. O. .O.
CST Level (ft) 30.0 30.0 30.0 . 30.0 '30.0 RX Bldg Vac (in H2O) .40 .20 .10 .10 .10 T-Time-(hr: min) 03:15 03:30 03:45 -04:00 04:15 1
Clock Time (br: min)
Torus Pressure equivalent'to Drywell Pressure-I -
4 e .s-wMM-es e -Lf--'- ma- m'mW-m.a .,,=_tde r*m--4 *cm + - = =m4.>TA ***wm+ %. so- T-
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.e Af313UAL EXERCISE SCENARIO 22 REV NO - 0 i
TABLE A-1.0v CRITICAL PLANT PARAMETERS-s --
To Be Used in Case of BPT' Failure '
RPV Level 168. 168.
RPV Pressure (in TAF) .17 . 168. 168. 168. 168.
(psig) 17. 17 RX Coolant Temp. - (F) 23. 30. '36.
300. 300. 300. 297.
Reactor Power-(%) 293. 290.
D.W. Pressure'(psig) :O. O. O. 'O. O.
'15.0 13.0 O.
D.W. Temperature (F) 12.0 10.0 -O. O.
'194. 195. 196. 196.
Torus Temp.- (F) 94. . 94. 94. 94.
180. 175. ,
94.
Torus D.G.
Level (inches) -146.0 . 146.0 146.0 146.0 146.0 146.0 94.
- 1 Load (KW)
D.G. #2' Load (KW)
O. ~O. O. 0. O.
O. 'O.
- 0.
- 0. O. 0.- O.
CST-Level (ft)
, 5 30.0 30.0 '30.0 30.0 RX Bldg Vac-(in H2O) ..40 .20 .10 .10 30.0 -3 0.' O ,
.10 .10 T-Time (hr: min) 03:15 03:30 03:45 .04:00 04:15 04:30 Clock' Time-(hr: min)
Torus Pressure equivalent to Drywell Pressure-J 4 I
+
.g' g M .'E.
-- , a. - u: , . - . _ _-- __ . - ~ . _-- ~--__.__'
~
b OCIIGS SCENARIO 22 ~
AtillUAL EXERCISE REV NO O TABLE A-1.0w _
CRITICAL PLANT PARAMETERS To-Be Used in Case of BPT Failure
~
RPV Level (in TAF) 168. 168. 168. 168. -168. 168. 168.
RPV Pressure (psig) 17. 17. ' 1'7 . 23. 30. 36. 42.
RX Coolant Temp. (F) 300. 300. 300. 297. 293. 290. '287.
Reactor PoQer'(%) O. .
O. O. O. O. O. O.
I D.W. Pressure (psig) 15.0 13.0 12.0 10.0 0. 0. O.
D.W. Temperature (F) 194. 195. 196. 196. 180. -175. 150.
Torus Temp. (F) 94. 94. 94. 94. :94. .94. 94.
l Torus Level (inches) 146.0 146.0 - 146.0 146.0 - 146.0 . 146.0 146.0 D.G. #1 Load (KW) 'O. 0 .- O. O. 0. O. O.
D.G. #2 Load (KW) O. . O. 10. O. O. 0. 0.
CST Level (ft) H30.0 30.0 30.0 30.0 30.0 30.0 30.0 RX Bldg Vac (in H2O) .40 .20 -.10 -.10 .10 .10 -'10 03:45 04:00 04:15 04:30 04:45 T-Time (hr: min) 03:15 03:30 Clock Time (br: min)
Torus Pressure equivalent to Drywell Pressure .
e
-- A
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- OCNGS SCENARIO-22
~ ANNUAL EXERCISE REV NO O TABLE A-1.0x CRITICAL PLANT PARAMETERS . ,
To'Be Used in Case of BPT Failure 6
4
'RPV Level-(in TAF) 168. -168. 168. 168. -168. 168. 168. 168. ,
RPV Pressure (psig) 17. 17. 17. 23. 30. 36. '42. 49.
i RX Coolant Temp. (F) '300. 300. '300. 297. 293. 290. .287. 283.
Reactor' Power (%) .O. O. O. O. O. O. O. O.
D.W. Pressure.(psig) 15.0 l'3 . 0 12.0 10.0 0. 0. O. O.
D.W. Temperature (F) 194. 195. 196. 196. 180. 175. 150. ~125.
Torus Temp. (F) 94. 94. 7 94. . 94. 94. 94. 94. 94.
Torus Level 1(inches) . 146.0 146.0 146.0 146.0 146.0 146.0 146.0 146.0 D.G. #1. Load (KW) 0. O. O. -0. O. O. O. O.
- D.G. #2 Load (KW) O. O. -- 0 .
- 0. O. -0; O. O.
CST Level (ft) 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 RX Bldg Vac (in:H2O) .40 .20 ,
.10 .10 .10 .10 .10 '25 T-Time (hr: min) 03:15 03:30 ;03i45 04:00 04:15 04:30 04:45 05:00 Clock Time (hr: min)
Torus Pressure equivalent to Drywell Pressure i
i i
e d
P OCNGS d SCENARIO 22
- ANtiUAL. EXERCISE - REV NO O
.. TABLE A-1.0y CRITICAL PLANT PARAMETERS _
To Be Used in Case of BPT Failure t
RPV Pressure (psig) 55.
RX Coolant Temp. . (F) 280.
- Reactor Power (%) O.
D.W. Pressure (psig) O.
D.W. Temperature (F) 115.
Torus Temp. (F) 94.
Torus Level (inches) 146.0 D.G. #1 Load (KW) O.
D.G. #2 Load (KW) O.
CST Level (ft) 30.0 RX Bldg Vac (in H2O) .25 T-Time (hr: min) 05:15 Clock Time (hr: min)
Torus Pressure equivalent to Drywell Pressure 1
w b
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OCNGS SCENARIO 22-
-ANNUAL EXERCISE .REV NO O TABLE A-1.la CRITICAL PLANT PARAMETER -
SUMMARY
For Controller and' Observer Use Only-I .
RPV Level-(in TAF) 160. 160. 160. 160. 160. 149. 168. 168.
RPV Pressure (psig) 1020. 1020. 1020. 1020. :1020. 800. 724. 643.
RX Coolant Temp. (F) '526. 526. 526. 526.- 526. 510. 506. 489.
Reactor Power (%) 100. 100. 100. 75. 70. O. O. O.
D.W. Pressure (psig) 1.1 1.4 1.7 2.3 2.3 11.3 15.5 15.7 D.W. Temperature (F) 131. 135. 138. 140. 1145. 150. 175. 185.
Torus Temp. (F) '74. 75. 75. 75. 75. 78. 85. 85.
Torus Level (inches) 144.0 144.0 144.0 144.0 144.0 144.0 144'.0 145.0
~
D.G. #1 Load (KW) O. O. O. O. O. 0. O. O.
D.c. #2 Load (KW) O. O. O. O. O. O. O. .O.
CST Level (ft) 30.0 30.0 30.0 30.0 30.0 30.0 30.0 _ 30.0 RX Bldg Vac'(in H2O) .' 2 5 .25 .25 .25 .25 .25 .25 .25 T-Time (hr: min) 00:00 00:05 00:10 00:15 00:30 00:32 01:15 01:30 Clock Time (hr: min)
Torus Pressure equivalent to Drywell-Pressure D.W. Delta P (psig) .0 .0 .0 .0 .0 .0 .0 .0 D.W. Hydrogen (%) .0 .0 .0 .0 .0 . 0 ,0 .0 D.W. Oxygen (%) .0 .0 .0 .0 .0 .0 .0 .0 gm' ws-
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- muJ,msa e,-m ,- -me -
OCNGS ' SCENARIO 22 ANNUAL EXERCISE P.EV NO O TABLE A-1.lb ,
CRITICAL. PLgNT PARAMETER
SUMMARY
- . For Controller and Observer Use Only F
RPV Level (in TAF) 168. 168. 168. 168. 168. 168. 168. -168.
RPV Pressure (psig)~ 563. 482. 402. 321. 321. J321. 17. -17.
RX Coolant Temp. (F) 472. 456. 439. 422. 422. 400. 300. 300.
Reactor Power.(%) 'O. O. .
O. O. _0. O. O. O.
D.W. Pressure (psig) 15.3 15.0 15.0 15.5 16.0 16.5 17.0 16.0 D.W. Temperature 1(F) 200. 205. 208. 212. -215. 220. 235. 230.
Torus Temp. (F) 85. 84. 84. 84. 84. .84. 90. 93.
Torus Level- (inches) 145.0 145.0 145.0 146.0 '146.0 146.0 146.0 146.0 D.G. #1. Load (KW) O. O. O. O. O. O. 0. O.
D.G. #2' Load (KW) O. O. 1 0. O. O. O. 'O. O.
CST Level'(ft) 30.0 30.0 30.0 30.0 30.0 30.0 .30.0 ~
'30.0 RX Bldg Vac (in-H2O) .' 2 5 .25 .25 .25 .25 .00 .40 .60 T-Time (hr: min) 01:45 02:00 02:15 -02:30 02:44 02:45 :-02:50 03:00 C1'ock Time-(hr: min) 4 l : Torus Pressure equivalent to Drywell Pressure D.W. Delta-P'(psig) .0 .0 .0 .0 .0 .0 .0 .0 D.W. liydrogen (%) .0 .0 .0 .0 .0 '0
. .0 .0 D.W. Oxygen-(%) . 0 ;. .0 .0 .
.0 .0 .0 .0 .0 9
E e
S 1
- E O E E O U N N EE E.O O E' E, NE .E:M'
- w w w ,q l
- \
Oct3GS - SCENARIO 22 ANNUAL EXERCISE REV NO- 0 TABLE A-1.lc '
CRITICAL PLANT PARAMETER
SUMMARY
Por Controller and Observer Use Only RPV Level (in TAF) 168. 168. 168. 168. -168. 168. 168. 168.
RPV Pressure (psig) 17. 17. 17. 23. 30. 36. 42. 49.
RX Coolant Temp. (F) 300. 300. 300. 297. 293. 290. 287. 283.
Reactor Power (%) O. O. O. O. O. 4. O. O.
D.W. Pressure (psig) 15.0 13.0 12.0 10.0 0. O. O. ~0.
D.W. Temperature (F) 194. 195.' 196. 196. 180. 175. 150. 125. -
Torus Temp. (F) 94. 94. 94. . 94. 94. 94. 94. '94. _
Torus Level (inches) 146.0 146.0 146.0 - 146.0 146.0 146.0 146.0 .146.0 D.G. #1 Load (KW) O. O. O. O. O. 0. .0. O.
D.G. #2 Load (KW) O. O. .
O. O. 'O. 'O. O. O.
CST Level (ft) '30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 RX Bldg Vac (in H2O) .40 .20 .10 .10 .10 .10 .10 .25 T-Time (hr: min) 03: 15 03:30 03:45 04:00 04f15 04:30 04:45 05:00 Clock Time (hr: min)
Torus Pressure equivalent to Drywell' Pressure
.0 .0 .0 .0 .0 .0 .0 D.W. Delta-P.(psig) .0
.0 .0 .0 .0 .0 .0 .0 .0 D.W. Hydrogen-(%)
.0 .0 .0 .0 D.W. Oxygen (%) .0 .0 .0 .0 l
l
.Jli _,_ ._.- _i.i.___..'_..________._e _ _ .
__ ...i.~. . _ _ _ - - ~ _ - - , - - _ . . :. , . _.m_
C OCNGS SCENARIO 22 ANNUAL EXERCISE REV NO O TABLE A-1.1d CRITICAL PLANT PARAMETER
SUMMARY
For Controller and - Observer Use Only (
RPV Pressure l(psig) 55. .,
RX Coolant Temp. (F) 280.
Reactor Power (%) O.
D.W. Pressure (psig) O.
. D.W. Temperature-'.(F) 115.
Torus Temp. (F) 194.
i Torus Level (inches) 146.0 '
D.G. #1 Load-(KW) O.
D.G. #2 Load ~(KW) O.
-CSTJLevel.(ft) 30.0 '
RX Bldg Vac'(in:H2O) .25
- T-Time (hr
- min) 05:15 '
r.
Clock Time (hr: min) r Torus Pressure equivalent to Drywell Pressure
[~ D.W. Delta P (psig) .O D.W. Hydrogen (%) .0 D.W. Oxygen'(%) .O e .
I t
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. .OCNTS SCENARIO 22
[ ANNUAL EXERCISE REV NO 0- :
TABLE A-1.2a i VENTILA?; ION FAN STATUS: t, T-Timet '00:00 ,
f- PANEL 11R EF-1-5 ON- Reactor Building Exhaust EF-1-6 OFF Standby EF-1-7 ON Turbine Building Exhaust- i EF-1-6 OFF- Standby Gas Treattent A .
EF-1 9 OFF . Standby Gas Treatment B.
{
AOG PANEL i I
ON Augumented Offgas System l NOT IN CONTROL ROOM I
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N OCNGS . SCENARIO 22 I
ANNUAL EXERCISE REV NO O TABLE A-1.2b VENTILATION FAN STATUS T-Times 00:06 -i PANEL 11R EF-1-5 ON Reactor Building Exhaust EF-1-6. OFF Standby ['
EF-1-7 ON Turbine Building Fehaust EF-1-8 ON Standby Gas Treatreat A ;
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OCN28 SCENARIO 22- l ANNUAL EXERCISE REV NO O .
r TABLE A-1.4al .i
- d* B 2."!S B & S 8?"!*!_ *!* __!T "__22i??!___!_______1 NOTE: 'OSH' = Offscale High ;
i AREA PROCES$
l RADIATION MONITOR $ CSE sft/hr RA0lAfl0N n0NITOR$ CSE aft /hr Adeln tids Entry Turb Blde A 1 0.4 Conteltment Sprey H A Eff P 1 - 0.5 ,
Access to Centrol Room' A2 0.03 Centeltment sprey n B Eff P 2 0.7 Reactor Centrol Room A*3 0.2 containment torey M C Eff P 3 15.
Turbine Oper Floor Entry A4 3.0 Contalruent sprey M 0 Eff P 4 15.
( Lndry 4 Decen Aree(Chem la A 5 0.1 Vent mentfold Red non Ch 1 P 5 1.0
( Turb Lnho Olt E wip Aree A6 0.4 Vent IIentfold Red seen Ch 2 P 6 1.0 ,
Food Ptap Aree A*7 2.0 Cond Vent 1 Red non Ch 1 P7 1.0 ,
Condensete Pgasp Aree A8 3.0 Cond Vent 1 Red non Ch 2 P8 1.0 !
Cond Deeln Volve Aree A*9 4.0 Cond vent 2 Red non Ch 1 P9 1.0 Regenerstlen Area. A 10 10. Cond vent 2 Red non Ch 2 P 10 1.0' nakete Depin Aree $*1 0.2 service Water clochree non P 11 150.
Air Compressor Aree ' B2 0.5 RSCCW Discherse Isenitor P 12 430. '
Redueste Ptap Room 03 100.
Radieste Control Room 84 3.0 Redueste Conveyor Afste B5 5.0 Reessete Store and ship B6 0.3 TIP Velve Room BT 4.0 Peroemel Air Lock B8 3.0 Reactor Oper Floor Area 89 1.0 -
Reactor Equip Drain Ter* B 10 40.
l Cleerme System Puup Area C1 15.
76el Pool filters C2 35.
Emergency Condenser Area C3 6.0 i
Shutdown koet Exchanger C4 20.
j Spent Fuel Pool A w C5 4.0 Liquid Poison System Area C6 1.5 Control Rod Drive seedule C7 2.0 Air Ejoctore Area C8 440.
Fuel Pool (Low Range) C9 2.0 Fuel Pool (High Rense) C 10 30.
RAGEMS HIGH-RANGE MONITOR: 1.0E-13 Amps RAGEMS I4W RANGE MONITORS: 6. cps l
CHRRM NUMBER 1: 4. R/hr CHRRM NUMBER 2: 4. R/hr OFFGAS AIR EJECTOR MONITOR: 430. mR/hr MAIN STEAM LINE MONITOR: 99. mR/hr 1
. m._ . _ . - - - . - . - - - - - - - - -- _ _ .-. - . . .
^
OCNGS SCENARIO 22 ANNUAL EXERCISE REV NO O 1 TABLE A-1.4b Radiation Monitori."q System Data _ _ _ _ _ _ _ _ _ _(T_ _ _ _ 00:15) ________ ( _ _ _ _ _ _) _ _ _ _ _ _ _ _ _ _ = _l NOTE: 'OSH' = Offscale High !
R ATION MONITORS CODE aft /hr 40 ON MONITORS' CODE aft /hr Aemin Blds Entry Turb tido A 1 0.4 Contelrunent $ prey NX A Eff P*1 0.5 ,
Access to Control Room A2 0.03 Contelrunent $ prey MK $ Eff P 2 0.7 I Reactor Control Room A3 0.2 centaltenent sprey NX C Eff P 3 15. i Turbine Oper Floor Entry A4 3.0 contaltunent sprey NX 0 Eff P 4 15. j
. Lndry 8 Decon Aree(Chem le 4 5 0.1 vent Montfold Red seen Ch 1 P 5 1.0 ;
Turb Lube Oil Egulp Aree A6 0.4 vent Montfold Red seen Ch 2 P 6 1.0 Feed P g Area A7 2.0 . Cond vent 1 Red Mon Ch 1 P7 1.0 7 condensate Pwp Area A8 3.0 cond vent 1 Red Isen Ch 2 P8 1.0 J' Cond Domin valve Area A9 4.0 cond Vent 2 Red Mon Ch 1 P9 1.0 Regeneration Area A 10 10. Cond vent 2 Red Men Ch 2 P 10 1.0 4 Mekow Domin Aree 81 0.2 service Water Dischree aton P 11 150.
Air Compressor Aree B2 0.5 RSCcv Discherpe Monitor P 12 430.
Redueste Pep Room . B3 100. ,
Redueste Control Room 04 3.0 Rechseste Corweyor Af sle B5 5.0 -
Redweste Store and ship B6 0.3 j TIP Velve Room .BT - 4.0 Peroomel Air Lock 38 3.0 .
Reector Oper floor Aree B9 1.0 Reactor EcpJIP Drain Tank B*10 40. ,
,- Cloeng System Pwp Area C1 15.
(. Fuel Peot Filters C2 35.
[ toergency Condenser Area C3 6.0 l Shutdown Nest Exchanger C4 20. , ,
Spent fuel Pool Area C5 4.0 Liquid Poison System Area C6 1.5 Control Rod Drive loo &Le C7 2.0 i Air Ejectore Area C8 440.
Fuel Pool (Low Range) C9 2.0 Fuel Pool (High Range) C 10 30.
RAGEMS HIGH-RANGE MONITOR: 1.OE-13 Amps RAGEMS LOW RANGE MONITORS: 6. cps CHRRM NUMBER 1: 4. R/hr
- CHRRM NUMBER 2: 4. R/hr OFFGAS AIR EJECTOR MONITOR: 430. mR/hr MAIN STEAM LINE MONITOR: 99. mR/hr 1
. l; I:
E
- I .
=n'a ,,,em---,,en
1 OCNGS SCENARIO 22 ANNUAL EXERCISE REV NO O TABLE A-1.4c F Radiation Monitoring System Data (T = 00:30) ( .)
L -----------------------------------------------------------
NOTEt 'OSH' = Offscale High AREA PROCESS RADIAtl0N Moulicas CODE sdt/hr RADIAfl0N MONITORS CODE sa/hr E Admin tids Entry Turb Side A 1 0.4 Conteiraent sprey MX A Eff P 1 0.5 Access to Control Room A2 0.03 Conteltment sprey NX 8 Eff P 2 0.7 Reactor Control Room A3 0.2 Contalraent $ prey MX C Eff P 3 15.
Turbine Oper Floor Entry A4 3.0 Conteltment Spray MX D Eff P 4 15.
Lndry & Decon Aree(Chem la A 5 0.1 vent Montfold Red Mon Ch 1 P 5 1.0 Turb Lube Olt Equip Area A6 0.4 Vent Manifold Red Mon Ch 2 P 6 1.0 Feed Puup Area A7 2.0 Cond Vent i Red Mon Ch 1 P7 1.0
[. ..
Condensate Pump Area AB 3.0 Cond Vent i Red Mon Ch 2 P8 .1.0 Cond Domin Velve Area A9 4.0 Cond Vent 2 Red Mon th 1 P9 1.0 Regeneration Area A 10 13. Cond Vent 2 Red Mon Ch 2 P 10 1.0 Makeup Deeln Area tal 0.2 Service Water Dischrge Mon P 11 150.
[ Air Compressor Aree Redweste Puup Room B2 B3 0.5 100.
RSCCW Discherpe Monitor P 12 430.
Redweste control Room B4 3.0 Redweste Conveyor.Alste B5 5.0
[- Redweste Store and Ship t6 0.3 flP Velve Room B7 4.0 Personnet Air Lock S8 3.0 Reactor Oper Floor Area B9 1.0
[. Reactor Etwlp Drain Tank B 10 40.
Cleanup System Pump Area C1 15. ,
Fuel Pool Filters C2 35.
Emergency Condenser Area C3 6.0 Shutdown Neet Exchanger C4 20.
Spent Fuel Pool Area C5 4.0 .
Liquid Polson system Area C6 1.5 I Control Rod Drive Module C7 2.0 Air Ejectors Area C8 440.
Fuel Pool (Low Range) C9 2.0 .
Fuel Pool (High Range) C 10 30.
RAGEMS HIGH-RANGE MONITOR: 1.0E-13 Amps RAGEMS LOW RANGE MONITORS: 6. cps CHRRM NUMBER 1: 4.'R/hr CHRRM NUMBER 2: 4. R/hr OFFGAS AIR EJECTOR MONITOR: 430. mR/hr MAIN STEAM LINE MONITOR: 99. mR/hr f.
l L
OCNGS SCENARIO 22 .
ANNUAL EXERCISE REV NO O TABLE A-1.4d Radiation Monitoring System Data'___(T___=____ 00:45) _______
.( _____
) W!
NOTE:OSH' = Offscale High !
f I
AREA. . _
PROCE$$ l CODE eR/hr :
RADIAflou MONITORS- CODE sA/hr RADIAfl0N MONITOR $
i Adeln tids Entry Turb Bldg A 1 0.4 containment Sprey NK A Eff P 1- 0.5 Access to Control Room A2 0.03 Containment Sprey MX B Eff P 2 0.7 Reactor Control Room A3 0.2 , Cantoimeent sprey NX C Eff P*3 15.
Turbine opor Floor Entry A4 3.0 contelmeent sprey' NM D Ef f P 4 15.
Lndry & Decon Ares (Chem in A*5 0.1 Vent mentfold Red Mon Ch 1 P 5 1.0 Turb Lube Olt Egip Area A6 Feed Psap Area A7 0.4 2.0 Vent Montfold Red Mon Ch 2 P 6 Cond vent i Red mon Ch 1 P7 1.0 1.0 l'
g
- Condensate Ptap Area A8- 3.0 - Cond Vent 1 Red Mon Ch 2 P4 1.0 Cond Domin Valve Area A9 4.0 cond vent 2 Red Mon Ch 1 P9 1.0 '
Regeneration Area A 10 10.' Cond Vent 2 Red Mon Ch 2 P 10 1.0 150. f Makete Domin Area B1 0.2 Service Water Dischree non P 11 Air Cospressor Ares B2 0.5 .RSCCW Discharge Monitor P 12 430. ,
Redweste Pw p Room B3 100 + ,
Rocheeste Control Room 84 3.0 Redweste Conveyor Alste B5 5.0 W .
Redweste store and Ship B6 0.3 '
TIP Valve Room B7 4.0 Personnel Air Lock B8 3.0 ,
Reactor Oper Floor Area 89 1.0 Reactor Equip Drain Tank B 10 40.
Cleanup system Pung Area C1 15.
Fuel Pool Filters C2 35.
Emergency Condenser Area C3 6.0 y shutdown Nest Exchanger C4 20.
Spent Fuel Pool Area C5 4.0 Liquid Poison System Area C6 1.5 <
Control Rod Drive Module C7 2.0 ,
Air Ejectors Area C8 220. ,
Fuel Pool (Low Range) _ C9 2.0 Fuel Pool (High Range) C 10 30.
RAGEMS HIGH-RANGE MONITOR: 1.0E-13 Amps .
RAGEMS LOW RANGE-MONITORS: 6.- ~ cps CHRRM NUMBER 1: 4. R/hr CHRRM NUMBER 2: 4.-R/hr OFFGAS AIR EJECTOR MONITOR: 215. mR/hr MAIN STEAM-LINE MONITOR: 50. mR/hr I
. - < = , &n..[.-- -. ..- r...... , e a w . . - - + - . ~ . v-- , . , e
9.
( SCENARIO 22 OCNGS' ANNUAL EXERCISE REV NO O ;
(' TABLE A-1.4e ,
i
[ "*!**!!!2 " 211!!!2!. SE!!"_ *!"___!T :__22122L__!_______! _
NOTE: . 'OSH' = Offscale High -l
{ !
AREA PROCESS i RADIAT!DN MONITORS CODE aft /hr RADIATION MONITORS CODE.eR/hr Admin Blds Entry Turb Blde A 1 0. 6 , Contelrament Sprey HM A Eff P 1 0.5 Access to Control Room A2 0.03 contelrvoont Sprey NN 5 Eff P 2 0.7 :
Reactor control Room A3 0.2 . Contalismont sprey NX C Ef f P 3 15. .
Turbine Oper Floor Entry A6' 3.0 Contelrument sprey NX D Eff P 4 15.
f Lndry & Decon Aree(Chem La A 5 0.1 ' Vent Montfold Red Mon Ch 1 P 5 1.0 Turb Lthe bit E pip Area A6 0.4 Vent Montfold Red Mon Ch 2 P 6 1.0 Feed Ptap Area A7 2.0 Cond Vent i Red Mon Ch 1 P7 1.0 Condeneste Puip Area .A8 3.0 Cond vent 1 Red Mon Ch 2 P8 - 1. 0 -
f Cond Domin Velve Aree A9 4.0 cond Vent 2 Red Mon Ch.1 P9 1.0 Regeneration Area A 10 10. Cond Vent 2 Red Mon Ch 2 P 10 1.0 j Makeup Deeln Area B+1 0.2 Service Water Dischree Man P 11 150.
[
Air Compressor Area 32 0.5 RBCCW Discherpe Monitor P 12 430.
Redweste Ptap Room B3 100.
Redweste Control Room B4 3.0 '
Redweste Conveyor-Afste B5 5.0
[ Redweste Store and Ship B6 0.3 TIP Velve Room B7 4.0 Personnet Air Lock 48 3.0 Reactor oper Floor Area B9 1.0 Reactor Equip Drain Tank B 10 40.
Cleanup System Ptsp Area C1 1$.
Fuel Pool Filters C2 35. ;
l Emergency Condenser Area C3 6.0 ,
I Shutdown Heat Exchanger C4 20.
Spent Fuel Pool Area C5 4.0 Llwid Poison System Area C6 1.5 Control Rod Drive Module C7 2,0 AirEjectoreArea C8 15.
Fuel Poot (Low Range) C9 2.0 Fuel Pool (High Range) C 1C' 30.
. RAGEMS HIGH-RANGE MONITOR: 1.0E-13 Amps RAGEMS LOW RANGE MONITORS: 6. cps
- 1 l' CHRRM NUMBER 2: 4. R/hr CHRRM NUMBER 2: 4. R/hr OFFGAS AIR EJECTOR MONITOR: 10. mR/hr l
i MAIN STEAM LINE MONITOR: 5. mR/hr l'
/
w -,w-
_ - _~-. . - - - - - - .- . - _ . _ .
I1 OCNGS SCENARIO 22 i ANNUAL EXERCISE REV NO O l
r
' TABLE A-1.4f !
Radiation Monitoring System Data (T = 01:15) ( ) ,
. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ~ . . ,
NOTE: 'OSH' = Offocale High l i
i AREA. PROCESS RADIAi!ON MONt10R$ CODE W/hr RADIAfl0N MONITOR $ CODE W/hr .
Aatnin tids Entry Turb Stds A*1 0.4 Contelrunent $ prey NK A fff P*1 0.5 Access to control Room Reactor Control Room A.2 A3 0.03 0.2 Conts'rument sprey NM B Ef f P 2 Contelnment sprey NN C Eff P 3 0.7 15.
l!
g.,
, Turbine Oper floor Entry A4 3.0 contelnment sprey NK D Eff P 4 15. j t
Lndry & Decen Ares (Chem La A*5 0.1 Vent mentfold Red men Ch 1 P 5 1. 0 -
Turb Lube Oil Equip Area A6 0.4 Vent Manifold Red Mon Ch 2 P 6 1.0 '1, Food Pe p Aree A*7 2.0 Cond Vent i Red Mon Ch 1 P+7 2.3 Condensate Pa p Area A8 3.0 Cond Vent i Red Mon Ch 2 P8 ' 3.2 I Cond Deeln Velve Area A*9 4.0 Cond Vent 2 Red Mon Ch i P9 18.
Regeneration Area A*10 10. Cond Vent 2 Red Mon Ch 2 P 10 3.5 l ^f Make@ Deeln Area 31 0.2 Service Water Dischree Mon P*i1 150. W {i Air Compressor Area B2 0.5 RICCW Discharge Monitor P 12 430.
Redweste Pw p Room B3 100.
f Redweste Control Room B4 3.0 Redweste Conveyor Afste B5 -5.0 Redweste Store and Ship B6 0.3 TIP Velve Room 87 4.0 Personnel Air Lock B 8' 3.0 l Reactor Oper floor Area B9 1.0 ?
Reactor Equip Drain Tank B 10 40. ..
Cleen@ System Pwp Area C1 29.
')i Fuel Pool Filters C2 35.
Emergency condenser Area C3 7.1
$hutdown Heat Enchanger C*4 20. !
$ pent Fuel Pool Area Liquid Poison System Area C+6 C5 4.0 1.5 l[
g Control Rod Drive Module C+7 2.0 AirtjectorsArea C8 15.
Fuel Pool (Low Range) C9 2.0 Fuel Pool (High Range) C+10 30.
RAGEMS HIGH-RANGE MONITOR: 1.OE-13 Amps --
-j RAGEMS LOW RANGE MONITORS: 1. cps -
CHRRM NUMBER 1: 3. R/hr ,
CHRRM-NUMBER 2: 3. R/hr :
OFFGAS AIR EJECTOR MONITOR: 1. mR/hr i MAIN STEAM LINE MONITOR: 1.-mR/hr .
-t k
i w
y-. r _ - _ . .- - _ . , , +- wm --
4 y: .
.Ot F.22 . SCENARIO 22 ANNUAL EXERCISE- REV NO O TABLE A-1.4g Radiation Monitoring System Data (T.= 101:30) ( )
...---....--....--------............ -----------..n n.....--
NOTE: ' OSH' = Offscale High
.- u AREA PROCESS RA01Afl0N ICilTORS % ndt/hr . RADIATION MONITORS CODE !Wt/hr -
Admin 8tde Entry Turb Elde k. 0.4. Contalm:?t v .y NM A Eff P 1 0.5 Access to Control Room A2 0.03 Contait W nt hefty MX e Eff P 2 0.7
', Reactor Control Room A3 0.2 Conteirt ee ey p NM C E f f P 3 15.=
Turbine Oper Floor Entry A*4 3.0- Contalruen.i 'sprey HM 0 Ef f P 4 15.
Lndry & Decon Aree(Chem La A 5 0.1 vent Manifold Red leon Ch 1 P 5 - 1.0 m
Turb Lthe Ott Equip Area A6 0.4 Vent Montfold Red Mon Ch 2 P 6 1.0
. Feed Puup AMe A7 2.0 Corv '.%t 1 Red Mon Ch 1 P7 2.3 Condensate Puup Aree A8 3.0 cond Vent 1 Red lion Ch 2 P8 3.2 Cond Domin Velve Area A9 4.0 cond Vent 2 Red Mon Ch 1 P9 18.
_- Regeneration Aree. A 10 .- 10. Cond vont 2 Red Mon Ch 2 P 10 3.5 Makety Dea'n Area 81 0.2 . Service Water Olschrge Mon P*11 150
' Air Compressor Area B2 0.5 RBCCW Discharge Monitor P 12 430.
- Redweete Puup Room 63 100.
g Redweste control Room B4 3.0 todweste Conveyor Alste B5 5.0 Redseste Store and Ship .B6 0.3
-_ TIP valve Room - B7 4.0
% Personnel Air Lock B8 3.0 Reector oper Floor Area B9 1.0 Reactor Equip Drain Tank 9 10 40.
' Cleanne system Pwp Aree C1 29.
Fuel Pool Fitters C2 35.
Emergency Condenser Area C3 7.1 g_ Shutdown Heat Exchanger C4 20.
Spent Fuel Pool Area C5 4.0 Liquid Poison System Area C6 1.5
. Control Rod Drive Module C7 2.0 Air Electors Area C8 15.
Fuel Poot (Low Range) C9 2.0 Fuel Pool (High Range)- C 10 3C.
- 'RAGEMS HIGH-RANGE MONITOR: 1.0E-13' Amps RAGEMS LOW RANGE MONITORS: 1. cps CHRRM NUMBER 1: 3. R/hr CHRRM NUMBER 2:- 3. R/hr OFFGAS AIR EJECTOR MONITOR: 1. mR/hr w MAIN STEAM LINE MONITOR: 1. mR/hr k-
.o 3
m
. ----------imi-=im.. i i
_ i
... .. .. . ~ . ~. - - .
OCNGS' SCENARIO 22
~ ANNUAL = EXERCISE REV NO O i
TABLE A-1.4h
) Radiation Monitoring Syste'm Data (T = 01:45) (' ) I, i NOTE:-'OSH= Offscale High ,
l r
AREA PROCESS .I RADIATION MONITOR $ CODE aft /hr RADIATION MONITORS CODE adt/hr ((
Admin Blds Entry Turb Blde A 1 - 0.4 Contaltunent sprey NM A Eff P 1 0.5 Access to Control Room A 2. 0.03 - Centelrunent sprey NX 8 Eff P
- 0.7 ,r A3 :Contaltsment Spray HM C Eff P 3
- i. Reactor Control Room 0.2 15.
'3.0' l- - Turbine oper. Floor Entry - A-( contelrunent sprey NX 0 Eff F-4, 15.- ,
Lndry & Decon Ares (Chem to A 5 0.1 Vent mentfold Red Men Ch 1 195 1.0 Turb Lube Oil twfp Area A 6. 0.4 Vent Manifold Red Men Ch 2 9 6 1.0-Feed Pulp Area A 7- 2.0. Cond Vent 1 Red Men Ch 9 -P7' 2.3 Condensate Puup Area A8- 3.0 Cond Vent 1 Red Mon Ch 3 P8 3.2 Cond Domin Velve Aree A9 4.0 Cond Vent 2 Red Mon Ch 1 P9 18. [
Regeneration Area A 10 - 10. Cond Vent 2 Red Mon Ch 2 P 10
~
3.5 -
- Makeup Domin Aree 41 0.2 service Water Dischree Mon P 11 150.
Air Compressor Area 32 0.5 RSCCW Discharge Monitor- P*12 '430.
Redweeto Ptsp Ruem 83 100.:
Redweste Control Room B4 3.0 ,
Redweste Conveyor Alste B5 5.0 i Reesente store end Ship' .B6' O.3 -
.TIP Velve Room 87 4.0 Personnet Air Lock B8 3.f)
Reactor oper Floor Area I9 1.0 l
Reactor realp Drain Tank B 10 - 40.
Cleerme System Puup Area C1 29. .
Fuel Pool Filtere C2 35. ,
Emergency Cwideneer Area C3 7.1 W Shutdown Heat Exchanger C4 20.
Spent Fuel Pool Area C5 4.0 Ll wid Poleon System Area C6 1.5 1 Control Rod Drive Module C+7 2.0 ,
Air Ejectors Aree C8 15. .j Fuel Pool (Lou Range) C9 2.0 : .!
Fuel Pool (High Range) C 10 30. :
RAGEMS HIGH-RANGE MONITOR: 1.0E-13 Amps RAGEMS LOW RANGE MONITORS: 1. cps:
CHRRM. NUMBER 1: 2. R/hr CHRRM NUMBER 2: 2. R/hr 4 OFFGAS AIR EJECTOR MONITOR: 1. mR/hr MAIN. STEAM LINE~ MONITOR:' 1. mR/hr .-
L 1 L I I
i
.I.,!
, 4 4
.OCNGS -SCENARIO.22-g.
ANNUALUEXERCISE; .
-~REV,NO O 3 TABLE.A-1.41 '
hadiation Monitoring System Data--.... --
'(T =--------
02:00): .----------
(- -)
NOTE: 'OSH' = Offscale High AREA PROCESS RADIAfl0N MONITORS-- CCet aft /hr RADIAfl0N MONif0R$ CODE mR/hr..
Adeln tido Entry Turb Blde A 1 0.4 Containment spraylu A Eff Pa1 0.5
- Access to Control Room . A2 0.03 Containment $ prey WM B (ff P 2 - 0.7
. Reactor Control Room A3 0.2 contelnment spray MX C Eff P*3 15.^
Turbine Oper. Floor Entry A 4 - 3.0 Contalrunent Spray HX 0 Ef f P 4 15. -
- Lndry & Decon Ares (Chem La A 5 0.1 - Vent Montfold Red Mon Ch 1 P 5 1.0 Turb Lube 011 Equip Area A6 -0.4~ Vent Montfold Red Mon Ch 2 P.6 , 1. 0 Feed Puup Area - A7 2.0 ~ Cond Vent 1 Red Mon Ch 1' P7- t 2.3 -
Condensate Pulp Area A8 3.0 ~Cond Vent 1 Red Mon Ch 2~ P 8 3.2 -
Cone Domin Velve Area A*9. 4.0 Cond vent 2 Red Mon Ch 1 P9 -18. ,
Regeneration Area A 10 10. Cond Vent 2 Red Mon Ch 2 P 10 6 3.5 I Makeup Domin Area 81: 0.2 Service Weter Olschree Mnn P 11 150. '!
Air Compressor Area 32 0.5 RBCCW Discharge Monitor P 12 430. ,
Redweste Puup Room 83 100. :
Redweste Control Room B4 3.0 Redweste Conveyor Alsle B5 5.0 Redweste Store and Ship B6 0.3 !
TIP Velve Room B7 4.0 Personnel Air Lock B8 3.0 ;
Reactor Oper Floor Area B9 1.0 'I Reactor E @lp Drain Tank t 10 40.
Cleen@ System Pump Area C1 29.
Fuel Pool Filters C2 35.
- Emergency Condenser Area C3 7.1 Shutoown Heat Exchanger- C4 20.
Spent fuel Pool Area C5 4.0 -
Liquid Poison System Area C6 1.5 i Control Rod Drive Module C7 2.0 AirEjectorsArea C8 15.
Fuel Pool (Low Range) C9 c.0 Fuel Pool (High Range) C 10 30.
RAGEMS HIGH-RANGE MONITOR: 1.0E-13 Amps ,
RAGEMS LOW RANGE MONITORS: 10. cps CHRRM NUMBER 1: 2. R/hr .
CHRRM NUMBER 2: 2. R/hr 1 OFFGAS AIR EJECTOR MONITOR: 1. mR/hr MAIN STEAM LINE MONITOR: 1. mR/hr ,
i
..y.. . . _ _. . ._ ._. __ _ __ . ,- _ _ , . __
- l. ,
i- .,
OCNGS SCENARIO 22 l ANNUAL EXERCISE .
REV NO _0 TABLE A-1.4j. R Rad 3,ption-Monitoring System Data (T == 02:15)- ( )
. . 4 . . _________ _____ __ __ ____ ______ ____ __ ;
NOTE: 'OSH' ==Offscale High-I' .
AREA PROCESS g' RA01Afl0N MONITOR $ Cope en/hr . RADIA110N MONITORS- CODE. se/hr .
j Admin Olde Entry Turb Bldg A 11 0.4 Contairement sprey MM A Eff P 1 0.5 Access to Control Room A2 0.03 - Conteirinent $ prey HM B Eff P 2 0.7
- Reactor Control Room A3- 0.2- Contelrument $ prey NX C Eff P 3 15.. 'l Turbine Oper Floor Entry ~A4 3.0 Contelrument sprey NX D Eff P 4 15.,
I. Lndry & Decon Ares (Chem te A 5 0.1 Vent Montfold Red Mon Ch 1 P 5 , 1. 0 -- '
C Turb Lube of t Equip Area A-6 0.4 ; Vent Montfold Red Mon Ch 2 P 6 - 1.0
, Feed Puup Area A 7. .- 2.0'- Cond Vent 1 Red Mon Ch 1 P7 2.3 Condensate Puup Aree A8 3.0 Cond vent 1 Red Mon Ch 2 P8 3.2 - l Cond Deeln Velve Aree A9 4.0 cond vent 2 Red Mon Ch 1 P9 18. !
Regeneration Aree uA 10 10. Cond Vent 2 Aad Mon Ch 2 ' P 10 3.5 ~;
Makeup Domin Area B1 0.2- Service Water Dischree Mon P 11 150.
Air Compressor Area B2 .0.5 RSCCW Discherse Monitor. P 12 - 430. .
Rambeste Puup Room 83 -100.
Rechseate Control Room 84 3.0.
! Redweste Conveyor Afsle 85 5.0 l' .Redueste store end ship 0.3 l; f!P Velve Room 87- 4.0 - ,
I Personnet Air Lock B8 3.0
. Reactor Oper floor Area 59 1.0 j Reactor Equip Drain Tank 0 10 40.
Cleanup System Puup Area C1 29.
Fuel Poet' Filters C42 ' 35. l Emergency Condenser Area C3 7.1 '.
- Shutdown Meet Exchanger C4 20.
Spent fuel Pool Area C5 4.0 +
LicpJld Poison System Area C 6 '
1.5 3 l Control Rod Drive Module C7 2.0 ,
Air Ejectore Area C8 . 15. ,
Fuel Pool (Lou Range) C9 2.0 Fuel Pool (High Range) C 10 30. ;
RAGEMS HIGH-RANGE MONITOR: 1.0E-13 Amps RAGEMS LOW RANGE MONITORS: 1. cps l
CHRRM NUMBER 1: 2 .R/hr CHRRM NUMBER 2: 2. R/hr - ,
OFFGAS AIR EJECTOR MONITOR: 1. mR/hr -
MAIN STEAM LINE MONITOR: 1. .mR/hr -
ii I:
gg I .
4 OCNGS SCENARIO 22 ANNUAL EXERCISE REV NO O
. = TABLE A-1.4k
) Radiation Monitoring System Data- o .
(T.=. 02:30) (- -)
NOTE: 'OSH' = Offscale High AREA ' PROCESS
~
-RADIATION MONITORS. CODE ' ndt/hr - RA01Afl0N MONITOR $ C00E mR/hr Admin Blde Entry Turb Blde A+1 0.4 contelrvaant sprey NX A Eff P*1 0.5 Access to control Room A2 0.03 contelrunent sprey HM S Eff P 2 0.7 .
Reector Control Room A*3 0.2 contalrument sorey MX C Eff P.3- 15.
Turbine oper Floor Entry ' A4 3.0 ,contelnment sprey NX D Eff P 4 15. --.
Lndry & Deein Aree(Chem la A 5 0.1 Vent Montfold Red Men Ch 1 P 5- 1.0 .
- Turb Lube C's Equip Aree A6 0.4 Vent Manifold Red Men Ch 2 P 6 - 1. 0 )
Feed Puap Area. A7 2.0 Cond Vent 1 Red Mon Ch 1 - P7 2.3-Condensate Pump Area A8
)
3.0 cond Vent 1 Red Mon Ch 2 P8 3.2 Cond Domin Velve Aree A*9 '4.0- Cond vent 2 Red Men Ch 1 P9 18 !
Rogerwretion Area A+10 10. Cond Vent 2 Red Mon Ch 2 P 10 3.5 -
-Makeup Deain Area 31 0.2 service Water Dischrge Mon P 11 150.
Air Compressor Area 82 0.5 RSCCW Discharge Monitor P 12 430.
' Redweste Pump Room- B3 100. '
Redweste control Room e4 3.0 Redweste Conveyor Afste B5- 5.0 '
Redweste Store end Ship 36 0.3 TIP Velve Room- B7 4.0 Personnel Air Lock B 8- 3.0 Reactor Oper Floor Aree B9 1.0 Reactor Equip Drain Tank 8 10 40.
Cleerup System Pulp Area C1 29.
Fuel Pool Filters C2 35. i Emergency Condenser Aree C3 7.1 Shutdown Heat Exchanger C4 20.
Spent Fuel Pool Area C5 4.0
- Liquid Poison SyJtem Area C6 1.5 3
- Control Rod Drive Module C7 2.0 Alr Ejectors Aree 'C8 15. i Fuel Pool (Low Range) C9 2.0 Fuel Pool (High Range) l C 10 30.
RAGEMS HIGH-RANGE MONITOR: 1.OE-13 Amps RAGEMS I4W RANGE MONITORS: 1. cps CHRRM NUMBER 1: 2. R/hr CHRMM NUMBER 2: 2. R/hr .
OFFGAS-AIR EJECTOR MONITOR: 1.-mR/hr MAIN STEAM LINE MONITOR: 1. mR/hr i
\;
OCKGS SCENARIO 22'
' ANNUAL EXERCISE REV NO- O'
( ,
TABLE,A-1.41 t l : '
- E
') Radiation Monitoring System Data- .(T = 02:45) ( )- 3 NOTE: 'OSH' ='Offscale High .;
!~
, AREA PROCESS j I'
RA01Afl0N MONif0R$- CODE mR/hr RADIATION MONITOR $ - CODE sA/hr :
l Admin Ildt Entry Turb StdB A*1 0.4 :Contelnment Sprey NX A Eff P 1 0.5 <
' Access to control Room A2 0.03 .Contelnment sprey NX 8 Eff P 2. 0.7 i Reactor Control Room - A3 _ 0. 2 _ Contelteent spray NX C Eff P 3 ..
' 15.~ ,
Turbine oper Floor Entry ' A*4 '.
3.0 conteltment sprey NX 0 Eff P 4f '15.
Lndry & Decon Aree(Chem to A*5- 6.0 Vent Manifold Red Men Ch 1 P 5- 1.0 Turb Lube Oil Equip Area A6 0.4 Vent Manifold Red Mon Ch 2 P-6 -1.0- ,
feed PW p Aree A7 2.0' ' Cond Vent 1 Red Mon Ch 1: P7 1.0 ,
, Condensate Puup Area A8- ' 3.0 cond Vent 1 Red Men Ch 2 P8 1.0 i
-Cond Domin Volve Area. A 9- - 4.0 ' cond Vent 2 Red Mon Ch 1 P9 .1.0 Regeneration Area- A 10 - 10. Cond Vent 2 Red Mon Ch 2' P 10 1.0 g Makeup Domin Area Air Compressor Area 31" 82 0.2.
0.5
~ Service Water Dischree Mon P 11 ASCCW Discherse Monitor P 12 150.
430.
g*
- j. _Redweste Pw p Room .B3 100.
Rechseate Control Room 84 3.0 Redweete Conveyor Alste 85 5.0 Redweste Store and Ship = 86 0.3 ci 4 TIP Velve Room 87 27.
, .Persomet Alr Lock 828 3.0 i Reactor Oper Floor Area 89 0$N Reactor Equip Drain Tank 8 10
'r 40.
Clearagi System Puup Area C1- ' OSH ,
Fuel Pool Filters C2 35.
Emergency condenser Area C3' OSH Shutdown Heat Exchanger C4 OSM Spent Fuel Pool Area C5 OSM -
- Liquid Poison System Area C6 0$N 'i
- r. Control Rod Drive Modute C7 15.' ';
~AirEjectorsArea C8 15.
[ Fuel Pool (Low Range) C*9 CSH f' Fuel Pool (High Range) C 10 1.1E3 l' !)
-i RAGEMS HIGH-RANGE MONITOR: 1.OE-13_ Amps -!
RAGEMS LOW' RANGE MONITORS: 160. cps CHRRM' NUMBER 1: 2.'R/hr !
CHRRM NUMBER-2: 1. R/hr
- - OFFGAS AIR EJECTOR. MONITOR
- 1..mR/hr- l
- MAIN' STEAM LINE MONITOR
- 1. mR/hr 3
^
! l t-I i
I'
-t W.
OCNGS-.. SCENARIO 22 ANNUAL EXERCISE REV NO. 0
, TABLE A-1.4m Data Radiation Monitoring Sysw.c......___________________..... (T = 03:00): -
_____________(________).
l ___.__.
NOTE: 'OM' = Offaca'.e High-AREA ,
PROCESS RADIATION MONITORS CODE aA/hr RA0!Afl0N MONITOR $ CODE sft/hr Asesin Blde Entry Turb tldo A 1 0.4 ' Contsfroent spray NX A Ef f P 1 17.
Access to control Room A2 0.04 conteltment Spray HX 5 Eff P 2 17. >
q I Reector control Room Turbine oper Floor Entry A4.
A3 - 0.2 3.0 Contelrment sprey HX C Eff P 3 contelnment sprey MX 0 Eff P 4 17.
17.
Lrmey & Decon Aree(Chem La A 5- 6.0 Vent Manifold Red Mon Ch 1 P 5 1.0
'f Turb Lube Oil Equip Area A6 0.4' Feed Pusp Area A7 2.0 Vent Manifold Red Mon Ch 2 P 6 Cond Vent.1 Red Mon Ch 1' P 7' 1.0 2.0 hl Condonoste Pulp Area - A8 3.0- Cond vent 1 Red Mon Ch 2 P8 2.0 Cond Domin Vetve Aree - A9 4.0 Cond Vent 2 Red Mon Ch 1 P9 2.0 R'generetton e Aree . A 10 10. Cond vent 2 Red mon Ch 2 . P 10 2.0-I Make@ Domin Aree -- B1 ' O.2 Service Water Olsenroe Mon P 11 170.- i Air Compressor Area B2 0.5 RsCCW Discharge Monitor P 12 450.
Rechseste Pump Room s3 100.
Redweste control Room B4 3.0 I Redweste conveyor Alste B5 5.0 Redweste Store and Ship- B6 0.3 TIP Velve Room, 87- 310.
Personnel-Air Lock 58 ' 13.
Reactor Oper Floor Area B9 SSN.
z Reactor Equip Drain Tent B 10 60.
. Cleen@ System Pump Area C+1 OSH.
- l Fuel Pool Filters C2 35.
Emergency Condenser Area C3 OSH
[ Shutdown Heat EAchanger C*4 OSH
. Spent Fuel Pool Area C5 OSH.
Liquid Poison System Area C6 OSM ^
Control Rod Drive Module C7 13.
Air Ejectors Area C8 15.
I Fuel Pool (Low Range) C9 0$N. $
'I Fuel Pool (High Range) C 10 1.3E3 RAGEMS HIGH-RANGE MONITOR: 1.0E-13 Amps
) RAGEMS LOW RANGE MONITORS: 140. cps CHRRM NUMBER 1: 1. R/hr 3 CHERM NUMBER 2: 1. R/hr 3 i OFFGAS AIR EJECTOR MONITOR: ~ 1. mR/hr MAIN STEAM LINE MONITOR: 1. mR/hr 4
P OCNGS~ SCENARIO 22.
ANNUAL EXERCISE REV NO O' lL TAELE A-1.4n -
..s Radiation Monitoring System Data (T'= 03:15)- . (- ).
4
'OSH't= Offscale High
- NOTE: 'j AREA PROCESS RADIATION MONITORS CODE . W/hr RADIAfl0N MONITORS - CODE' m/hr-l Adeln Ilde Entry Turb Blde A 1- ,
0.4 Containment Spray XX A Eff,P*1 25. .i Acce6e to Control Room A 2" .- 0.04 Contalement Spray HX B Eff P 2 25.
Reactor Control Room : A3. 0.2 contalruent Sprey NX C Eff P 3 25. .]
. Turbira oper Floor Entry 'A4= 3.0 - Contelonent Spray HX D Eff P 4 - 25.
Lndry & Decon Aree(Chem La A $ :t
-6.0 Vent Manifold Red Mon Ch 1 P 5- 1.0
.Turb L@e Of t Equip Aree ' A*6 0.4 Vent Montfold Red Mon Ch 2 P 6- 1.0 Feed Puup Area A 7' ' 2.0 Cond Vent 1 Red Mon Ch 1 - P7 2.0 1 Condensate Puup Aree . A8 .3.0 cond Vent 1 Red Men Ch 2- P8 - 2.0 #
Cond Domin Velve Area A 9.. . 4.0 cond vent 2 Red Mon Ch 1' P9 2.0
' Regeneration Area A 10 =- 10. Cond Vent 2 Red Men Ch 2 P 10- - 2.0 i Makew Domin Area 5 1 --- 0.2 Service Water Dischrge Mon P 11 170. ..
- Air Compressor Aree "B2 0.5 RSCCW Discharge Monitor ~ ' P-12
.}
450.-
Redweste Puup Room ' B3- 100.
Redweste Control Room B 4- 3.0.
Redweste Conveyor Alele Redweste Store and Ship B5 B6
' 5.0 0.3
' l;t :
TIP Velve Room-
- e 7: 310. '
. Personrol Air Lock 88 25. '
Reactor Oper Floor Aree B9 OSH.
'l Reactor Equip Drain Tank 0 10 65.
Cloeng System Pump Aree, . C 1 OSH
- Fuel Pool Filters C 2. 35. -3 Emergency Condenser. Area C3- OSH '
Shutdown Heat Exenanger C4 OSH. '}
t Spetit Fuel Pool Area C5 OSH Liquid Poison System Area C6 OSH '
control Rod Drive Module C7 25. , ,
Air Ejectors Area - C8 15.
Fuel Pool-(Low RenGe) C9 OSH li Fuel Pool (High Range). C 10 1.3E3.
. I .1 RAGEMS HIGH-RANGE MONITOR: 1.OE-13' Amps RAGEMS LOW RANGE MONITORS.: .130. cps :
CHRRM NUMBER 1: 1.-R/hr !
CHRRM NUMBER 2: 1. R/hr -
OFFGAS AIR EJECTOR MONITOR: 1..mR/hr l.
MAIN STEAM LINE MONITOR: 1. mR/hr I
p Is a
)
- , - . . . - . .+.--.,--..-se. -e .ww,-+
-OCNGS . .
SCENARIO 22=
ANNUAL EXERCISE REV NO O
. TABLE A-1.4o*
l Redi
---' gtion M,ortitoring- System Data ~ (T~= 03:30) ( )
~
p L NOTE: 'OSH' = Offscale High ;
i AREA PROCESS ;
. RADIATION MONITORS ' CODE sdt/hr RADIATION MONITORS . CODE ast/hr
~
]
Admin Olde Entry Turb Bldg A 1 0.4= Conte 1nment Spray NX A Eff P 1- 55..
' Access to Control Room A2 0.04 contalrunent sprey NX B Eff P 2
- Reactor Centrol Room A3 ' 0.2 Contalronent Sprey NX C Eff P 3 55.
55.
J
-Turbine opor Floor Entry A4 }
3.0 . Containment Spray NX 0 Eff P 4: 55.
= Lndry & Decon Aree(Chem La A 5 i 5.0 Vent mentfold Red Mon Ch 1 P 5 Turb LLhe oit Ecpalp Area A6 0.6 ' Vent Montfold Red Mon Ch 2 P 6' 1.0 l 1.0 ,.
- )
Feed Puup Area.
Condensate Pump Area -
A7 A8
' 2.0 Cond Vent 1 Red Mon Ch:11 P*7 - 2.0- j 3.0 - Cond Vent 1 Red Mon Ch 21 P 8' . 2.0 i Cond Domin velve Area A9 4.0~ Cond Vent 2 Red Mon Ch 1 .P 9 2.0 ;
- Regeneration Aree ' A 10 10 Cond Vent 2 Red Mon Ch 2 P 10 2.0 Makeup Deeln Area B1 0.2 !
Service Water Olschree mon P 11 160.
l Air Compressor Area B2 0.5 RSCCW Discharge Monitor P 12 '450. j Rehete Puup Room - 5 31 -100,
- j
- Redneste Control Room- 84 3.0
Redweste Conveyor AlsLe' B5 Redweste Store and ship B 6-
- 5.0 -
0.3 j '
TIP Velve Room B7 0$N Personnel Air Lock B8 55.
Reactor Oper Floor Aree B9 CSM.
Reactor Equip Orsin Tank- B 10 275.
Cleanup System Pump Area C1 OSH Fuel Pool Filters. C2 35.
Emergency condenser Area C 3- OSM
' Shutdown Meet Exchanger C 4' -OSM.
Spent Fuel Pool Area C5 OSM Liquid Poison Systee Area C6 QSN -
Control Rod Drive Mochate C7 55.
Air Ejectore Area C8 15. .jl Fuel Pool (Lou Range) C9 OSH
Fuel Pool (Migh Range) C 10 1.1E3.
RAGEMS HIGH-RANGE MONITOR: 1.0E-13 Amps y RAGEMS-LOW RANGE MONITORS: 120 cps ;
CHRRM NUMBER 1: 1. R/hr CHRRM NUMBER 2: 1. R/hr OFFGAS AIR EJECTOR MONITOR: 1. mR/hr !
MAIN-STEAM LINE MONITOR: 1. mR/hr !
4 l'
-. . , . . . . . - _ . ~ , - - - _ . -
x OCNGSi . -SCENARIO 22' L W-
' ANNUAL' EXERCISE '- REV NO--. 0
.. TABLE:A-1.4p-Radiction._ Monitoring System __Data_____ __
__ _ _ _ _(T. _=_ _03:45) .( )
_ _ _ . _ _ _ _ _ _' _ _ _ _ _ _f .
NOTE:: 'OSH' = Offseale~'High a-t AREA- PROCESS RA01Afl0N MONITORS CODE sit /hr RADIATION' MONITORS' CODEi eR/hr i!
' Adeln Blds Entry Turb Bldg A 1 0.4 . ' Containment Spray NX A Eff P 1- $5. -
Access to control Room A2 0.04 Containment Sprey NX 8 Eff P 2f - 55. . ;
Reactor Control Room .A3 0.2' . Containannt Spray MX C Eff P 3. -55. -- '
Turbine Oper Floor Entry A 4' 3.0 1 Containment spray NX 0 Eff P 4 - 55.' .
Lndry & Decon Aree(Chem.te A 5 4.0i Vent Manifold Red pion Ch 1 P 5 1.0 . g[l_j Turb L4e Oil Egip Aree A6 0.4 Vent Montfold Red Mon Ch 2 P 6 1.01 ,
Feed Puup Area - A* 7 2.0 cond vent 1 Red Mon Ch:1 P7- 2.0: ;
Condeneste Pulp Area A8 ' 3.0 Cono Vent 1 Red Mon Ch 2.. P 8' 2.0 ' t
.. Cond Domin Velve Aree 'A9- 4.0 ~ .Cond vent 2 Red hon Ch11 P9 2.0 - m Regeneration Area- A 10 . 10. Cond vent 2 Red Mon Ch 2 ..Pa10 - 2.0 Makeup Domin Area 51 , 0.2 service Water Olschrge Mon P 11 160. -
Air Compressor Aree ~ B2 0.5 R8CCW Discharge Monitor 'P 12 450. , .
' Reduasto Pulp Room ^B3 100.
Redueste Control Room 84 3.0 Redueste Conveyor Alste B5 5.0 Li Redueste Store and Ship B6- 0.3 < .
TIP Velve Room .B7 0$N -
Personnel Air Lock. B8 '55.
Reactor Oper Floor Area B9 OSH Reactor Egip Drain Tank 8 10 270. !
. Cleeng System Puip Aret C1 OSN i Fuel Pool Filters ' C2~ 35 .
Emergency Condenser Area C3 - OSH
~
Shutdown Heat Exchanger- C4 0$N
- - )
Spent Fuel Pool, Area C5 OSH j Liquid Polson System Area C6 0$N Control Rod Drive Module - C 7 55. l~;
Air Ejectors Area C8 15. We '
Fuel Pool'(Low Range) C9 OSH Fuel Pool (High Range) C 10 1.0E3 RAGEMS HIGH-RANGE MONITOR: 1.OE-13 Amps i
RAGEMS LOW RANGE. MONITORS: 120. cps-CHRRM NUMBER 1: 1. R/hr !
l CHRRM NUMBER 2: 1. R/hr .. .
f
!: OFFGAS AIR' EJECTOR MONITOR: =1. mR/hr :
l' MAIN STEAM LINE MONITOR:' 1. mR/hr- g,,
W.,
1 E ,
. e E .i
OCNGS SCENARIO 22'-
ANNUAL EXERCISE REV NO _0 TABLE A-1.4q Madiation MonitoringLSystem Data- (T =- 04:00)_____-- ...._
(' )
NOTE: 'OSH=_offscale High-.
AREA PROCESS RADIATION MONITORS , CODE sR/hr - RADIATION le0NITORS -CODE oft /hr Admin Btds Entry Turb SLd8 A*1 0.4- - Contelnment Sprey NX A _Ef f P 1. 50.
Access to control Room A2 0.04- Contelnment Spray MX B Eff P 2 50.
- Reactor Control Room -A3 ' O.2 Containment Spray NX C Eff P 3 - 50.
Turbine Oper Floor Entry A4 ' 3.0 - Containeont sprey NX 0 Eff P 4 . 50.
Lndry & Decon Aree(Chem to A 5. 4.0. J Yent Menifold Red leon Ch 1 P 5 ^ 1.0
. Turb Lube Olt Equip Area A6- 0.4 . Vent Manifold Red Mon Ch 2 P 6- 1.0 Feed Puup Aree A*7 2.0 ' Cond Vent i Red Mon Ch 1-- PT -2.0-Condensate Pump Aree . A8 3.0 cond Vent 1 Red Mon Ch 2; P8 2.0 cond Domin Yelve Area A9 4.0 - Cord Vent 2 Red Mon Ch 1 P9 2.0 Rogeruration Area A 10 10. Cond Vent 2 Red Mon Ch 2 P 10 2.0 Makeup comin Area- B1 0.2 ' Service Water Dischree Mon P 11 160.
' Air Compressor Area- B2 0.5 RBCCW Discharge Monitor.- P 12 450.
Reduasto Pump Room : B3 -100.
Redueste control Room B4 ~ 3.0 Reesente Conveyor Afste B5 5.0 Redueste Store and Ship , B6 0.3 TIP Velve Room B7 980.
Personnel Air Lock B8 50.
Reactor Oper Floor Are6 89- 1000.
Reactor Equip Drain Tank 8 10 250.
CLeenup Systam Pump Area C1 1000.
Fuel Pool Filters 'C 2 35.
~ Emergency Corweenser Area C3 1000.
Shutdown Heat Exchanger C4 1000.
Spent Fuel Pool Area C5 1000.
Liquid Poleon System Ates C6 1000.
Control Rod Drive Module C7 50.
AirEjectoreArea C8 15.
Fuel Pool (Lou RenGe) C-9 1000 Fuel Poot (High Range) C 10 1.0E3. -
RAGEMS HIGH-RANGE: MONITOR: 1.0E-13 Amps RAGEMS LOW RANGE MONITORS: 110. cps CHRRM NUMBER 1: 1. R/hr CHRRM NUMBER 2: 1. R/hr OFFGAS AIR--EJECTOR MONITOR: 1. mR/hr MAIN STEAM LINE MONITOR: 1. mR/hr
tu +
OCNGS .
SCENARIO 22 ANNUAL: EXERCISE. . .REV NO. 0
.' TABLE A-1.4r Radiation Monitoring. System Data-_ _ _ _ _ _ _ _ _(T _ _=.
_ _04:15):
_ _ _ _ _ _ _ _(-_ _ _ _ _ _) _ _ _ _ _ _ _ _ _ ' _ _ _
NOTE: 'OSH= Offscale High AREA-PROCESS:
I.
RA01AT30N MONITORS ' CODE mR/hr RADIAfl0N MONITORS. CtBE sa/hr .j A<enin'Blde Ent T Turb side A 1 0.4 .- Containment sprey NX A Eff P 1 45.
-A2 Containment sprey MX 0 Ef f P 2 '45.-
Access to Control Room 0.04 ,
Reactor control Roce i A3 0.2 Contalmeent sprey,NX C Eff P 3 ' - 45.
TurbineoperFloorEntry;fA4- : 3.0 Containment Sprey NM 0 Eff P 4 45. ,
. Lndry & Decon Aree(Chem la A 5 4.0 Vent Manifold Red Mon Ch 1 P-5 : 1.0. i Turb Lube Olt Equip Aree A 6 ~ 0.4 Vent Manifold Red Mon Ch 2 P 6- 1.0 g
. Feed Ptap Aree Condeneste pump Aree .
-A7-A8 2.0 ' - Cond Vent 1 Red Mon Ch 1
. 3.0 P7-Cond Vent 1 Red Mon Ch 2 P 8-2.0-2.0 g,
1
. Cond Domin Velve Aree A9 ,4.01 Cond Vent 2 Red Mon Ch 1 P9 .2.0 Regeneration Area A 10 - 10. Cond Vent 2 Red Mon Ch 21 P 10 2.0 +
Makeup Domin Ares: 51 0.2 Service Water Diechree Mon P 11- 160.
Air Compressor Aree B2 0.5 RSCCW Discharge Monitor
{
.P 12 440.
Rechseste Ptap Room B3 '100.
84 3.0 Rechseate Control Room Redweete Conveyor Alste e5 5.0 f li g 't l: Redweste Store and Ship S6 0.3 TIP Velve Room B7. 930.
h-l Personnel Air Lock B8 45.
Reactor Oper Floor Area - B9 950. Ej Reactor Equip Drain Tank B 10 930.
. Cleanup System Ptap Area- C1 930.
Fuel Pool Filters C2 35. :
toergercy Condenser Aree C3 950. us. '
Shutdown Heat Exchanger C4 930.
Spent Fuel Pool Area C5 950.
Liquid Poison System Area C6 .950. --
Control Rod Drive Module C7 45.
AirElectorsArea C8 15.
Fuel Pool-(Low Range) C9 950 Fuel Pool (Nigh Range) C 10 ' 950. -
RAGEMS HIGH-RANGE MONITOR: 1.9E-13 Amps RAGEMS LOW RANGE MONITORS: 100. cps -
CHRRM NUMBER 1: 1. R/hr '
CHRRM NUMBER 2: 1. R/hr OFFGAS AIR EJECTOR MONITOR:- 1. mR/hr=
MAIN STEAM LINE MONITOR: 1. mR/hr 7 d
i, d
1, l.
1
1 3:
- OCNGS- SCENARIO 22 ANNUAL EXERCISE REVf.NO O.
l- '
- TABLE A-1.4s.
,>, -Rad,$ation Monitoring System Data -(T =- 04:30) (. ) ..
..z ...--s--- ------ . ---- -- -- ....-- ------ .------
NOTE:OSHL =-Offscale High-I ARfA. PROCESS-1 RAD 1ATION MONITORS: . CODE, sR/hr RADIATION MONITORS . CODE mR/hr -l A,sein 8tde Entry Turb Bldg A 1- 0.4 Contatriennt Sprey Nx A Eff P 1- 45.
Access to Control Room A2 0.04 contalruent sprey NX B Eff P 2 4$.
I Reactor Control Room Turbine oper Floor Entry A 4_
'A 3 0.2-3.0 Contelnment Spray NX C Eff P 3 Conteltment Spray MM 0 Eff P 4 45.
45.
3 l Lndry & Decon Aree(Chem to A 5. 3.0 ' Vent Montfold Red Mon Ch 1 P 5 1.0 '
j Turb Lube Oil E@lp Ares . A 6 0.4 Vent Montfold Red Mon Ch 2 P 6 1.0 Feed Pump Area-
'{
A 7L 2.0 Cond Vent 1 Red Mon Ch 1 P 7. . 2.0 ;
Condeneste Pump Area- A8~ 3.0 cond vent 1 Red Mon Ch 2. P8 2.0-Cond Domin Velve Aree A9 4.0 cond Vent 2 Red Mon Ch 1- P9 2.0 Regeneration Area A 10 10. Cond Vent 2 Red Mon Ch 2- P 10 . J2.0 ,
y Makeup Domin Aree' B1 0.2 Service Water Dischrge Mon P 11- 160. :
Air Compressor Aree B2 0.5 ReCCW Discharge Monitor P 12 440. .l Redweste Puup Room-- 53- 100. :i Redweste Control Room -B4 3.0 I Rechseste Conveyor Alste 'B5 5.0 Redweste Store and Ship B6 0.3 ,
T!P Velve Room B7 880.
.l Personnel Air Lock I Reactor Oper Floor Area 88 89 45.
900.
t 3
Reactor Equip Drein Tonk ' B 10 220. j
. Clean e System Pump Area C1 880. !
Fuel Pool Filters C2 35.
Emergency Conderwer Area C-3 900
{
Shutdown Waet Exchanger C4 880.
Spent Fwl Pool Ares . C5 900.
Ll w!d Poison System Area C6 900.
Centrol Rod Drive Mochte C7 45. j Air Ejectors Area C8 15. '
Fuel Pool (Low Range)- C9 900 1
Fuel Pool (High Range) C 10 ' 900.
RAGEMS HIGH-RANGE MONITORT. 1.OE-13 Amps RAGEMS I4W RANGE MONITORS: 100. cps
- 1. R/hr CHRRM NUMBER 1: ;
CHRRM NUMBER 2: 1. R/hr ;
I OFFGAS AIR EJECTOR MONITOR: 1. mR/hr '
MAIN STEAM LINE MONITOR:~ 1. mR/hr l
T imi
OCNGS-ANNUAL. EXERCISE .
SCENARIO,22=
-REV NO' O Ij
-1
.l i TABLE A-li4t-Radiation. Monitoring Syste$t Data :(T =. 04:45) ( ); {1 NOTE:' 'OSH' = Offscale High-I;
'1
- AREA PROCESS
- RAO'ATION le0NITORS CODE am/hr RADIATION MONif0Rs= CEBE am/br Admin tids Entry Turb Stdg A 1 0.4 contelrunent spray MX A Eff P+1 40. {
Access to Control Room A 2. 0.04 contelrunent sprey MX B Eff P 2 40. j Reactor Control-Room .A3 0.2 Contaltenent sprey NX C Eff P 3 40. - ' .,
Turbine oper floor Entry A 14 3.0 - Contalrunent sprey NX D Eff P 4/ 40.
Lndry & Decon Aree(Chem'La A 5 _ 2.0 Vent Montfold Red Men Ch 1 P 5 1.0 ;
~ Turb Lube oil Equip Area A6 0.4 -? Vent Manifold Red Mon Ch 2 P 6 - 1.0 '
Feed Pwp Aree .A7 2.0 cond vent 1 Red leon Ch 1- P7- 2.0 :
~ Condensate Pw p Aree ~ A8 3.0 - Cond vent 1 Red leon Ch 2 P8- 2.0 Cond Domin Velve Aree' A9- - 4.0 ' Cond Vent 2 Red leon Ch 1 P9 2.01 -J Regeneration Area A 10 10. Cond Vent 2 Red Men Ch 2 P 10 2.0 Makeup Domin Area - 'B1 0.2 - Service Water'Dischree Mon P 11 l160.
Air Coopressor Area 82 0.5 RSCCW Discharge Monitor - P 12 440.
Redueste Pw p Room S3 . 100. '
Redueste Control Room B4- 3.0 ,
i Redueste Conveyor Alele- B5 5.0 ,
Redueste Store and Ship 86 0.3. --
TIP Vetve Room 57 825. '
Persomel Air Lock 88 40.
. Reactor opor Floor Aree B9 '825.
Reactor Equip Drain Tank B 10 210.
Cleanup System PW p Area C1 825. -i Fuel Pool Filters C2 35. 4 Emergency condenser Aree' C3 825. - i Shutdown Heat Exchanger C 4' 825. i Spent Fuel Pool Area C5 825.
Liquid Poison System Area C6 825.
i -Control Rod Drive Mo & te C7 40. ;
L Air Ejectors Area. C8 15. i Fuel Pool (Lou Range)- C9 825 .
Fuel Pool (Migh Range) C 10 825.
RAGEMS HIGH-RANGE MONITOR: 1.0E-13 Amps RAGEMS LOW RANGE MONITORS: 94. cps :.
CHRRM NUMBER 1: 1.'R/hr.
CHRRM NUMBER 2: 1. R/hr ..
OFFGAS AIR EJECTOR MONITOR:~ 1. mR/hr 3 MAIN STEAM LINE MONITOR: 1. mR/hr 5' l
l I
- l'
. .. - ~. .
. _ . y . - .
,5 s .- ;
'~
OCNGS SCENARIO 22 ANNUAL EXERCISE- ,
REV NO- 0' .,
, TABLE A-1.4u ,
f(T =' 05:00)
' Radiation MonitoringISystem' Data................................................. (
).
NOTE ;'OSH'<-= Offscale.High, ,
'5
, AREA PROCESS ,
RADIATION IIONITORS CODE sdt/hr RADIAfl0N MONITOR 8 CODE :eR/hr- ,
l Adeln Bide Entry Turb Blde A 1' O.4 Contefruent Spray NX A Eff P 1 - 40.
I'
' Access to Control Room - A2 0.04~ Contelnment sprey NK B Eff P 2 , 40. :
Reactor Control Room. A*3 0.2 Contelrment Spray NX C Eff P 3 40.
Turbine Oper Ftoor Entry A4 3.0 . Containment sprey NM 0 Eff P 4 40. .
Lndry & Decon Ares (Chem la A 5- 2.0= vent seenifold Red Isen Ch 1 P 5 1.0, !
' Turb Ltdse Olt Egilp Aree . A6~ 0.4 - Vent tientfold Red alon Ch 2 P 6 - 1.0 s s feed Puup Aree . A7. 2.0 Cond vent 1 Red IIen Ch 1 P7 2.0 .
Condensate Puup Area - A8 3.0 Cond vent 1 Red Men Ch 2 : P8 2.0 - .;
, Cond Domin valve Area A9 6.0 Cond vent 2 Red Men Ch 1 P 9 2.0 Regeneration Area A 10- 10. Cond vent 2 Red Mon Ch 2 P 10 2.0 .
Makeup Domin Aree B1 0.2- Service Water Dischree Mon P 11.<160.
- ' ~ Air compressor Area 82 0.5 RtCcv Discharge leonitor P 12- 440.
l Redweste Pump Room '33- 100.
Redweste control Room B4 3.0 i Redweste Conveyor Alste B5 5.0 u' Redweste Store and ship B6 0.3 TIP valve Room 87 780.
Personnel Air Locki' 08 40.
Reactor Oper Floor Area B9 800. l
(; Reactor Equip Draf n Tank ' t 10 195. .{
- .. Cleente system Pump Aree C1 780. ,
, fuel Pool Filters C2 35.
l- Emergency Condenser Area C3 800, iJ Shutdown Heat Exchanger C4 780.
- j. Spent fuel Pool Area C5 800.
Liquid Poleon System Area C6 800. n
- control Rod Drive Module C7 40.
Air EJoctore Area C8 15. i Fuel Poct (Low Rence) C9 800.
Fuel Pool (High Rence) C 10 800.
RAGEMS HIGH-RANGE MONITOR: 1.0E-13 Amps RAGEMS LOW RANGE-MONITORS: 89' cps CHRRM-NUMBER 1: 1. R/hr ~l CHRRM-NUMBER 2: 1. R/hr .
OFFGAS AIR EJECTOR MONITOR: 1. mR/hr MAIN STEAM LINE MONITOR: 1. mR/hr l-
OCNGS- .
SCENARIO 22 ANNUAL EXERCISE -
REV NO O
. TABLE A-1.4v L D'*!*5!!S_" 2!!!d2?_8?"*". *!*1__!T "__ Si N___L______! > 1 NOTE: . 'OSH' = Offscale High if , i g LREA PROCESS RtDIATION MONITORS - CODE .st/hr' 'RADIAT10N MONITOR $. CODE ~ mR/hr ,
Admin Blde Entry Turb Blde A 1 . 0.4' contelrunent Spray NX A Ef f P 1 35.
- Access to Centrol Room .A2 0.04 Contelnnent Spray NW B Eff P 2 35.
JE ' Reactor Control Room. A3 0.2 . Contelnment sprey NX C Eff P 3- 35.
Turbine Oper Floor Entry A4 '3.0 contelrunent sprey MX 0 Eff P 4 35. ;
- Lndry & Decon Aree(Chem to A 5 - 2.0 vent Montfold Red Mon Ch 1 P 5 1.0, Turb Lube Olt Equip Area A*6 0.4 Vent Montfold Red Mon Ch 2 P 6' .1.0 Feed Pg Area A 7. 2.0 ' Cond vent 1 Red Men Ch 1 . P7 2.0 L.
- 'Condonoste Pw p Aree A8: 3.0 cond Vent 1 Red Mon Ch 2 P8 2.0 Cond Domin Velve Aree .A9- 4.0 . Cond Vent 2 Red Mon Ch 1 P*9 2.0 - '
Regeneration Area A 10 10. Cond vent 2 Red Mon Ch 2 P 10 2.0, Makew Deeln Aree .B1 0.2 . Service Water Dischrge Mon P 11 160.
l Air Compressor Area 82 0.5 RBCCW Discharge Monitor P 12 440.
i Redueste Pwp Room B3 100.
Redueste Control Room - 04 3.0 -
Redueste Conveyor Alele - B5 5.0 Redueste Store and Ship . B6 0.3
~TIP Velve Room B7 740.
+
Personnet Air Lock < 58 " 35.
Reactor Oper Floor Area 39 750.
Reactor Equip Drain Tank 3 10 190.
' Cleanup System Pw p Area C1- 740. .,
Fuel Pool ~Filtere C2 . 35.
[- .
Emergency Condenser Area C3- 750.
I Shutdown Neet EAchanger C4 740.
Spent Fuel Pool Aree C5 750.
l'- ' Liquid Poison system Area C6 MO, 1
. Control Rod Drive Modate C7 ' 35.
Air Ejectore Area C8 15. -
Fuel Pool (Lou Range) C9 750. -
Fuel Pool (High Range)- C 10 750. ,
RAGEMS HIGH-RANGE' MONITOR: 1.OE-13 Amps RAGEMS~ LOW RANGE MONITORS:- 84. cps l CHRRM NUMBER 1: 1. R/hr l CHRRM NUMBER 2: 1. R/hr-
- l. OFFGAS AIR' EJECTOR' MONITOR: 1. mR/hr ;
L[ MAIN STEAM LINE MONITOR: 1. mR/hr
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Cis!!33 TT1'. .,
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' ,_ RASENS REPORT: Apr . 26 1990
..........aagrxn I ......
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~ . .- 5 M IMT E V A L U E S ----------- R A GE M S I I ----------
Steck Gas Flow Rdle 2ococo SCFM i Sample 04s Pressure. Q.44 ATM fStockGasVelocitw 782. FPM i P.R.VntDct Flow Rate + J 14 3, SCFM stk E a 4Al.it. Ogit .P.rg,.s __.. _ . . .p . 91_ A T.H 1, P,. R . Vn t.De L V e l oc i t w 2071. FPM
'Stk Sample Gas Tear 73. Des F 1 P.R. Sample Flow Rwtw 1.323 SCFM Seriv-Gas Flow Rate 1.222 SCFM i P.R.Seeple Velocitw 2021. FPM fta ar l e_ G a s _Ve l.gs.ilw _ _._J 3.5. _f P.H .. ._ 2l.,P R . Isok. Vel. Rattu 1.02 *
- Isokinetie Vol.Rstio 0.94 I OpF1 VntDct FlowRate 34 7+8 SCFM HRH ChkSree Current 0.3099E-10 Ames i LbAr.VntDct FlowRate 9385. SCFM H R M.. B e_Is.sr.p d. ..C uf.r.ep.L.9 2040 E - 12. A m et, l_.0F/LA Stack Volueitw - 1857. FPM HRM I.C. Rad. Conc.* o.co6 Y6
- I 0F/LA Sep1 FlowRate 1.398 SCFM v----------------------------------- 1 0F/LA Samel Velocitw 1841.-FPMw 2 4 - Ho u r _ S t a c k.__09_s_ F l o w, _ 0 234E+09 SCF l 0F/LA Isok.Uwl.Rati.o 1 01-Stk Part Samele=0dsFlow 0.484E+04 SCF l HRH I.C. Rad. Cone.* C.B66+6 *a ;
Stk Iod. Sample GasFlow 0.482E+04 SCF l HRH OhkSrew Curtwnt 0.G744E-10 Ames
1 HRH Bksend Current 0 2060E-12 Amps SYS2 LRM Backarnd Count 24. CPM LAN Radiation Count -1 CPNi~
SYS2 LAN ChekSrce Count 142. CPM 24Hr PumpRe VntDct Flow 0.423Et08 SCT-
[ . OpF1/LA_PLI_ Sample Flow 0.449E+04 - SCF 24He LbAr VentDuet Flow 0.13CE408 SCF Puer Re P/I Semp1w Flow 0.739E+04 SCF 24He OpF1 VentDuct Flow 0.498E+08 SCF
(**=Eauivalent uCi/cc Xe 133) (*= Pressure Currected)
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. 1RAGEMS REPORT! Apr '. 26 1990 ovos .
.........-RAarMa I -------- ._1_.ti!MT E V A L U E S -------- --- R A GE MS I I ----------
Stock Gas Flow Rate . l37soo SCFM. I Sdeple Oss Pressure 0 64 ATM -
fStackGas:Velocitw . 782. FPH I P.R.VntDct Flow. Rate- 1J14K. SCFM .
1 S t. k S a ge.LJf. O s_it Pr et.s _..__ 9 91 ATH -l 1. P R V.g t,,qc t V e l n e i t v -
, 2071. FPM Stk Sample Oss Tema ~ 73. Des F l P.R. Semple Flow Rwte- 1.323 SCFM' Seplv Gas' Flow Rate 1.222 SCFM I P.R. Semple Velocitw 2021. FPM ,
S.aerle 0as.Velst11w... ._,13.5. JPH~ l P.R. Ibok. Vel.< Rattu 1.02
- Isokinelle Vol. Ratio 0.94. 1 OpF1 VntDet FlowRato 3t 7+ B. SCFM- .. '
HRM ChkSree Current 0.3099E-10-Ames l'LbAr.VntDct FlowRate 8365. SCFM. .:
HR.M BcAsf.pd. juf.rpp3.J) .j!040C 12_ Aery... 1._r)F/L A S t4ck Villueitw 1957. FPM t HRM I.C. Rod. Cone.*- o.oosys .** 1.0F/LA Sept FlowRate-- 1.398 SCFM- - '
r----------------------------------- 1 0F/LA Samel'Velocitw 1841. - FPM - l 2 4-Hou r S.t a c h_.O p_s_ F l o w .,;0.234Et09.SCF,l._OFA A Isok.Vol. Ratio . _
1 01- s Stk Part Sample 04sFlow-0.484E+04.SCF l HRM I.C. Rad. Cone.* '
- O. '6+( **
Stk Iod.: Sample GasFlow 0.482E+04 SCF l'HRM OhkSree Curtwnt 0.574 E-10 Amps. e
..................................... I HRM Sksend Current 0.2060E-12 Amps SYS2.LAN Backarnd Count .- 2 4 . CPM LRM Radiation Count . :-1. CPMi SYS2 LRM ChekSrce Count 142.' CPM- 24He PumpRe VntDct Flow'0.423E+08-SCF OpF1/LA_P/_I_. Sample Flow 0.449E+04 SCF 24He LbAt VentDuct Flow-0.135E+0S SCF Puse Re.P/I Semple-Flow 0.739E+04 SCF 24He OpF1 VentDuct Flow.0.498E+08"ICF ,
(***Eeuivalent uCi/cc Xe 133) " i
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a ANNUAL EXERCISE SCENARIO NO$ 22 OCNGS REV. O Section A-2 A-2.1- Meteorological Data A-2,2- Meteorological Data Summary Table SCENFRMS/27/ Disk 7 i
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-OCNGS SCENARIO 22 ANNUAL EXERCISE. REV=NO O TABLE A-2.la METEOROLOGIO DATA- (T =1.00:00) (- )-
c.
Wind S eed 380 ft.:. -24.8 mph Wind D rection 380 ft.1 279. degrees .
re Delta Temp 380-33': -3.40 F deg
[ Wind Speed-33 ft.: 114.4 mph.
. Wind Direction l33 ft.: 279 degrees.
Delta Temp 150-33': 1
-1.70.F deg
( . Ambient Temperature:- ' 47.2 deg F.
L- Precipitation (rain):' .00-inch Weather Forecast:
TODAY: Partly to-mostly sunny, high winds, high-in
- the mid-to-upper 40's. Winds westerly, 25 -30 miles
. per hour.
- h. TONIGHT: Winds'd'iminishing,-lows in the upper 30's-to around 40. Winds changing-to southerly.
' TOMORROW: Mostly sunny, continued cool,:high in the lowJ to mid 50's, cooler along the coast. Winds southerly, 8 to 12 miles per hour.
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OONGS- .
SCENARIO l22 ;
, i-ANNUAL EXERCISE. . _
REV.NO O- m-
' TABLE A-2.lb .
'g 1
-METEOROLOGIC DATA (T =- 00:15)- (L )
L'
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i Wind Speed'380-ft.:, 24.8' mph -
i Wind Direction 380'ft.: -279 degrees 1 Delta Temp 380-33':. -3.40:F deg ,j Wind Speed-33 ft.: .
14.4 mph I l Wind Direction 33 ft'.: 279 degrees-- E:
. Delta _ Temp 150-33'.:. ~-1.70.F deg- - 5 jl
-Ambient Temperature: 47.2 dag F
. Precipitation (rain):- . 00 ;-inch .: : :
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SCENARIO 22-ANNUAL' EXERCISE REV NO. 0 TABLE ~A-2,1c-METEOROLOGIC; DATA' (T =-100:30): (r )
Wind Speed.380=ft.:- 23.0cmph.
. Wind' Direction380 f t. :. 291= degrees =
Delta Temp 380-33 ' :: "-3.30?F deg
= Wind. Speed 33 ft.:--
~
12.'4 mph Wind Direction >33 ft.: '291 degrees:
~ Delta Temp 150-33't. -1.70 F deg:
Ambient: Temperature: -47.9 deg'-F Precipitation ~(rain): .00iinch 4
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ANNUAL EXERCISE- , REV.NO 0. E, TABLE A-2.1d -
E :)
METEOROLOGIC DATA (T.= .- 00:45)' -(-
)- ;
- _________ ________'._____ ......._________ . . 4 Wind Speed 380 ft.:- - 22.91 mph- I-~ ;
I .. LWind; Direction 380 ft.': L287 degrees Delta Temp 380-33': -3.20:F-deg-
- Wind Speed'33 ft.: :12.9 mph --
l; . Wind Direction 33'ft.:- - 290.~ degrees
{
l' = Delta Temp.150-33': -l.604 F deg ,
- . Ambient-Temperature: 48.1'deg Ff '
!' Precipitation-(rain): .00 inch .
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I i N UAL ; EXERCISE I -
METEOROLOGIC' DATA TABLE'A-2.le (T'= 01:00)_ ('
RE
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I Wind-Speed 380 ft.:
Wind 1 Direction:380fft.: 30.0 mph 284-degrees Delta Temp 380-33': - -3.00 F deg
-Wind-Speed'33 ft.: -
15.6 mph z
Wind Direction Delta Temp-150-33': 33-ft.:- . 282' degrees-Ambient Temperature: - -1.50 F deg Precipitation (rain): 47.6:deg-Fz 3 00Linch' Weather Forecast:
TODA'l:
-the mid-to-upper 40's. Partly to'mostly sunny,Ihigh winds, high in per hour. Winds westerly,'25 -30' miles ..
TONIGHT:
-to around 40.Mostly clear andJbreezy, lows in the: upper-30's at 10-25 mph. Winds diminshing,' changing to southerly TOMORROW:
to mid 50's,Mostlycoolersunny, alon continued cool,:high in the low; 8-to 12-miles per hour. g the~ coast. Winds southerly,'
, , , , , mi..--i--* ' ' ' ' ' " '
~
+
SCENARZOJ22
'OCNGS- . .
.REV NO 0 -~
iANNUAL EXERCISE:
. TABLE A-2.lf E' (T "* ;01:15)L .=( ). -B
' METEOR 0 LOGIC DATA l .
i .. .. .. ..... ....... .......... ... ...
Wind Speed 380 ft.: -25.8' mph 286. degrees Wind. Direction 380 ft.:.--2.90<F deg-Delta' Temp'380-33':
Wind Speed 33'ft.: 12.~51 mph ~
289_ degrees 3 Wind: Direction 33 ft.:. -1.40fF deg. g;
-Delta Temp 150-33':
Ambient Temperature:- 47.7 deg.FJ Precipitation (rain): .00 inch I;
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s OCNGS ' SCENARIO:22 ANNUAL EXERCISE ~ REV NO- 0
, : TABLE A-2.lg=
- METEOROLOGIC DATA (TH=. 01:30) ( _)
1:
L Wind Speed 380 ft.:--- 23.0= mph Wind Direction.'380-ft.: 294 degrees.
h Delta-Temp 1380-33': -2.'60 F'deg i 11.G= mph' l Wind Speed'33 ft.:-
WindLDirection 33 ft.:=
293' degrees r Delta 1 Temp 150-33':- -1.20LF deg_ ,
(L Ambient Temperature: .47.6 deg F.
Precipitation-(rain),: _.00 inch 1
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SCENARIO 22 [
ANNUAL EXERCISE . REV.NO . 0'- ~!
TABLE A-2.1h - ' l METEOR 0 LOGIC DATA _(T = -01:45) ( ) -- ';
. Wirkd Speed 380 f t. : 22.4' mph -
Wind Direction-380 ft.: 285 degrees'- ~!-
Delta. Tamp 380-33':. -2.60'F deg. +
Wind Speed 33Lft.: =11.0 mph- -
Wind Direction 33 ft.:' ' 293 deg: ees -
Delta Temp 150-33':- -1.10 F deg' -
'l Ambient Temperature:- 47.8 deg,F-Precipitation _(rain):- .00 inch- -
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- g. OCNGS SCENARIO.2f ANNUAL EXERCJSE REV NO O TABLE A-2.li 6 METEOROLOGIC DATA .(T = 02100) ( )
Ls r ____________________________________________
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Wind Speed 380 ft.t- 21.3 aph I Wind Direction 3EO ft.: 279 degrees Delta Temp 380-33't -2.40 F dug Wind Speed 33 ft. 11.1 mph Wind Direction 33 ft.: 282 degrees 1 .? elta Temp'150-33': -1.00 F deg Ambient Temperaturet 47.8 deg F Precipitation-(rain): .00: inch Weather Forecast:
TODAY: Partly to mostly sunny, high winds, high in the mid-to-upper 40's. Winds westerly, 25 -30 miles per hour TONIGHT:
to around 40.MostlyWinds clear and breezy,iminish expected to d and change tolows in the upperf30's I southerly at 10-25 mph.
TOMORROW - Mostl sunny, continued. cool high in the loe to mid 50's, coo er along the coast. W1nds southerly, '
I 8 to 12 miles per hour.
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"OCNGS. SCENAR20 22 j ANNUAL EXERCISE REV NO O TABLE A-2.13 METEOR 0 LOGIC DATA (T = 02:15) ( ) ,
)
............................................ 1
)
a Wind Speed 380 ft.: , 24.7 mph !
Wind Direction 380 ft.: 280 degrees J Delta Temp 380-33's ~2.40 F deg Wind Speed 33 ft.: ~12.4 mph
-Wind Direction 33 ft.: 278 degrees E- -
Delta Temp 150-33's -1.00 F deg E Ambiant'. Temperature 47.7 dag F Precipitation-(rain): .00 inch I.i .
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SCENARIO 22 OCNGS REV No 0 I ANNUAL EXERCISE METEOR 0 LOGIC DATA (T =
g 02 30) ( )
I Wind Speed 380 ft.t 21.1 mph I Delta Temp 380-33'1-288 Wind Direction'380 ft.t--2.20 10.1 degrees F deg mph Wind Speed 33 ft.t Wind Direction.33 ft.1 287 degrees I Delta Temp 150-33's Ambient Temperature
.90 47.5 F deg deg F precipitation (rain): .00 inch
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OCNGS ANNUAL EXERCISE SCENARIO 22' REV NO O I
METEOROLOO?,C DATA TABLE A-2.11 (T = 02t45) ( )
Wind Speed 380 ft. 17.6 mph Wind Direction Delta Temp 380-33't 380 ft.t 276 degrees a Wind g.,'i -2.00 F deg g Wir 33 ft.:
Dire, 'lon 33 ft.t 8.4 mph De.' ca Teu 278 degrees 150-33't .70 F deg 3 Amttent .emperature 47.6 deg F g .-
Prec. v=.ation (rain) .00 inch I
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i I OCNGS SC43ARIO 22 I ANNUAL EXERCISE METEOROLOGIC DATA TABLE.A-2.1k (T =- 02:30)- (
REV NO
)
O 1 j
1 i
I Wind Speed 380 ft.:
Wind Direction 380 ft.: 288 degrees Delta Temp 380-33's 21.1 aph
-2 20 F deg Wind Speed 33 ft.: 10.1 mph I
Wind Direction 33 ft.: 287 degrees Delta Temp 150-33's. .90 F deg
-Ambient Temperaturet 47.5 deg F :
Precipitation (rain): .00 inch
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OCNGS SCENARIO ?.2~
ANNUAL EXERCISE REV NO O TABLE A-2.ll METEOROLOGIC DATA (T u. 02:45) ( ) ;
Wind Speed 380 ft.: .
17.6 mph Wind Direction 380 ft.: 276 degrees 1 Delta Temp 380-33's -2.00 F deg l Wind Speed 33 ft. - 8.4 mph l Wind Direction 33 ft.:. 278 degrees E '
Delta Temp 150-33't- .70 F deg 5'!
Ambient Temperature: 47.6 deg F Precipitation (rain): .00 inch j J
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OCNGS SCENARIO 22 ANNUAL EXERCISE REV NO O
. TABLE A-2.1m.
(. METEOROLOGIC DATA (T = 03:00) ( )
Wind = Speed 380 ft.: 17.7 mph
- Wind Direction 380 ft.
- . 281 degrees
} Delta Temp 380-33's -1.80 F deg Wind Speed 33 ft.: . 8.5 mph Wind Direction 33 ft.: 281 degrees Delta Temp 150-33': .60 F deg' Ambient Temperature:- 47.5 deg F Precipitation (rain): .00 inch Weather Forecast:
TODAY:' Partly to mostly sunny, high winds, high in-the mid-to-upper 40's. Winds westerly, 25 -30 miles per hour.
TONIGHT:
to around 40. MostlyWinds clear and breezy,iminish, expected to d changing to-lows in the upper 30's southerly at 10-25 mph.
TOMORROW: Mostly sunny, continued cool high in the low to mid 50's,. cooler along the coast. W1nds southerly, 8 to 12 miles per hour.
l OCNGS- SCENARIO 22 I1 ANNUAL EXERCISE REV NO O Ei
, TABLE A-2.in g METEOR 0 LOGIC DATA (T = 03:15) ( ) :
g t
l Wind Speed 380 ft.t 17.9 mph. l Wind Direction 380 ft.I 284 degrees i Delta Temp 380-338 2 - 1.60 F deg Wind. Speed 33 ft.: 8.1 mph ;
Wind Direction 33 ft.: 283' degrees- - -
Delta Temp 150-33't .50 F dag i Ambient Temperaturet 47.4 deg F Precipitation (rain): .00 inch' t
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' OCNGS SCENARIO 22 ANNUAL' EXERCISE REV NO O' TABLE.A-2.lo METEOR 0 LOGIC DATA (T = 03:30) ( )
~
k Wind Speed 380 ft.: 13.4 mph, Wind Direction 380 ft.: 279 degrees i Delta Temp 380-33's -1.50 F deg
{ Wind Speed 33 ft.: 6.0 mph Wind Direction.33 ft.: 279 degrees Delta Temp 150-33't .50 F deg -
Ambient Temperature 47.3 deg F Precipitation (rain): .00 inch
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h OCNGS SCENARIO 22 [
ANNUAL EXERCISE REV NO O' ='
TABLE A-2.1p METEOROLOGIC DATA (T =. 03:45) ( )
a t -
Wind Speed 380 ft.: 12.7 mph i Wind Direction 380 ft.:- 278 degrees ~
i Delta Temp 380-33': -1.40 F deg
- Wind Speed;33 ft.: . 5.3' mph Wind Direction 33 ft.: 279 degrees E. ,
Delta. Temp 150-33': .40'F deg gi Amt ient Temperature 47.3 dag F -
Precipitation'(rain): .00 inch I
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4 OCNGS SCENARIO'22 ANNUAL EXERCISE REV NO 0- ;
TABLE A-2.lg j METEOROLOGIC DATA -(T = 04:00) ( ) ;
,1 Wind Speed 380 ft.: 13.0 mph Wind-Direction 380-ft.: 277 degrees-
{. Delta Temp.380-33': -1.20.F deg' I Wind Speed 33 ft.: 4.2 mph '
Wind Direction 33 ft.: 282 degrees Delta Temp.150-33': .40 F.deg.
Ambient Temperature: 47.2 deg F Precipitation-(rain): .00 inch' T
f Weather Forecast:
TODAY: Partly to mostly. sunny, high winds, high in the mid-to-upper 40's. Winds westerly, 25 -30 miles per hour.
TONIGHT:
MostlyWinds to around 40. clear and breezy,iminish, expected to d changing tolows in the upper-30's southerly at 10-25 mph.
TOMORROW: Mostly sunny, continued cool,'high in the low to mid 50's, cooler along the coast. Winds southerly, 8 to 12 miles per hour.
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OCNGS 'SCENAEIO 22 !
- ANNUAL EXERCISE .
REV NO O I TABLE A-2.1r '4 METEOROLOGIC DATA (T = 04:15) ( ) )
.i
-Wind Speed 380 ft.: 13.8 mph Wind Direction 380 ft.: .272 degrees )
Delta Temp 380-33': -1.00 F deg Wind Speed 33 ft.: 4.1 mph 'l Wind Direction 33'ft.': 275 degrees Delta Temp 150-33?: .30 F deg- -l Ambient Temperature: 47.2 de F- {
-Precipitation (rain): . .00'in h' ;
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SCENARIO 22 ANNUAL EXERCISE REV NO O TABLE A-2.ls y
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METEOR 0 LOGIC DATA (T = 04:30) -( )
Wind S eed 380 ft.: 15.0 mph f Wind D rection 380 ft.:. 276 degrees , ,
Delta Temp 380-33,': -1.00 F deg.
Wind Speed 33 ft. ' 4.9 mph Wind Direction 33 f t. :' 282 degrees Delta Temp 150-33's .30 F.deg Ambient Temperature: 47.4 deg F, Precipitation (rain): .00 inch L
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l OCNGS SCENARIO 22 l REV NO ANNUAL EXERCISE O TABLE A-2.lt METEOROLOGIC DATA (T = 04:45) ( ) i i
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Wind Speed 380 ft. 1s.6 mph i Wind-Direction 1380 ft.: 273 degrees .
l Delta Temp 380-33's -1.30'F deg '
Wind Speed 33 ft.: 3.6 mph Wind Direction 33 ft.: 263 degrees i
' Delta Temp 150-33's .40 F deg .j Ambient Temperature 47.5 de F Precipitation (rain): .00 in h l: 4 F
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' ANNUAL EXERCISE SCENARIO 22 REV No 0 TABLE A-2.lu
~ METEOROLOGIC DATA (T = 05:00) ( )
Wind Speed.380 ft.: 11.4 aph Wind Direction 380 ft.:
Delta Temp.380-33's 274' degrees
-1.30 F deg
{. Wind Speed 33 ft.: 4.2 mph Wind Direction 33-ft.:
Delta Temp 150-33's 269 degrees
.40 F deg Ambient Temperature:- 47.7 deg F
.[ Precipitation (rain): .00 inch L
Weather Forecast:
.r. TODAY:
( Partly to mostly sunny, highs in the mid-to-upper 40's. Winds dimii.sh laterwesterly, 25-30 mlles per hour and expected to in the day.
r TONIGHT:
( to around 40.
MostlyWinds clear expected and breezy,iminishlows to d in the upper 30's
, changing to southerly at 10-25 mph.
[ TOMORROW: Mostly sunny, continued cool I
to mid 50's, cooler alon high in.the' low 8 to 12 miles per hour. g the coast. W1nds southerly, ,
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OCNGS- SCENARIO 22 ANNUAL EXERCISE REV NO O TABLE A-2.1v-METEOROLOGIC DATA (T = 05:15) ( ) -
Wind Speed 380-ft.: 13.3 mph B Wind Direction 380 ft.: 275 degrees Delta Temp 380-33' -1.30 F dag l Wind Speed 33 ft.: 5.4 aph -
Wind Direction 33 ft.: '
Delta Temp 150-33':
277 degrees E
.40 F deg l Ambient Temperature: 47.7 deg F Precipitation (rain): .00 inch I
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K OCNGS SCENARIO 22 ANNUAL EXERCISE' REV No 0 h- TABLE A-2.2 METEOR 014GIC DATA SL30tARY TABLE
[
- 1*11Mt wt 380' WD 380' f 350 33 'Wt 33' WD 33' ' f 150 33. ftmP .talN.
00:00. 24.8 279 3.40 14.4 279
- 1.70 - 47.2 .00
.00:15 ' 23.0 291 3.30 12.4 291 1.70 47.9 .00 7 00:30' 22.9 247 +3.20 12.9 290 *i.60 48.1 .00 U 00:45 30.0 284 3,00 15.6 282 1.50 47.6 .00 01:00 25.8 286 2.90 12.5 289 +1.40 47.7 .00 01:15 23.0 294 -2.60 11.6 293 1.20 47.6 .00 01:30 22.4 285 a2.60 11.0 293 +1.10 47.8 .00
[. [= 01:45 21.3 279 2.40 11.1 282 *1.00 47.8 .00 9 02:00 24.7 280 2.40 12.4 -278 1.00 47.7 ' .00 02:15~ 21.1 268 2.20 10.1 287 .90 ~ 47.5 .00 02:30 17.6 ,2?6 2.00 8.4 278 0 . 70 47.6 .00 02:45 17.7 281 *1.80 8.5 281 -,.60 47.5 .00 03:00 " 17.9 284 1.60 8.1. 283 . 50 47.4 .00 03:15 13.4 279 1.50 6.0 279 . 50 47.3- .00 03:30 12.7 278 +1.40 5.3 279 .40 47.3 .00 03:45 13.0- 277 *1.20 4.2 282
- 40 47.2 '.00 :
04:00 13.8 272 1.00 4.1. 275 . 30 47.2 .00 04:15 1$.0 276 1.00 4.9 282= +.30 47.4 .00 h' 04:30 12.6 2T3 +1.30 3.6 263 . 40 47.5 . 00_ .
04:45 11.4 274 1.30- ' 4.2 269 *.40 47.7 . 00 05:00 13.3 275 +1.30 5.4 277 . 40 47.7 .00 05:15 11.2 2 75 al.30 3.8 274 . 40 47.7 .00 NOTE These are the Actual Meteorological Conditions At the Times Indicated Above.
The 15-minute Averages Provided to the Players Are 15 Minutes Behind the Above Values 1
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- ANNUAL EXERCISE SCENARIO NO. 22 L OCNCS REV. O i
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l Section A-3 A*3.1 Reactor Water Activity A-3.2 Torus Water Activity I. A-3.3 A-3.4 A-3.5 Drywell Cae Activity Torus cas Activity Reactor Building Activity A-3.6 Turbine Building Activity I A-3.7 A-3.8 RACEMS 1 Stack Activity.
Refuel Floor Activity 1
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. . . . . . . . . - - - . . _ . - - - - - - . - - - _ _ - . . . . . . - - . - . - - - - . _ - - ~ . - . . ~ . - . - . . - _ . - . . . ._--.- _.- .
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( OCNGS SCENARIO 22 ANNUAL EXERCISE REV NO O TABLE A-3.la REACTOR WATER ACTIVIY. - (T = 00: 00) (
)
There is an analysis delay of up to 30 minutes after sampling Nuclide Concentration 1-131 4.71E-04 uci/cc I-132 1.01E-03 uCi/cc I-132- 5.98E-03 uCi/cc
(- I-134 2.33E-02 uCi/cc I-135 1.40E-02 uCi/cc Cs-137 1.24E-04 uci/cc
~
TOTAL WATER SAMPLE 4.49E-02 uCi/cc DEI 131 -2.65E-03 uCi/cc Normal Sample (10 ml) Deze Rate at 1-ft.: < 2. mR/hr PASS Sample (1. ml n Dose Rate at 1.ft.: < 2. mR/hr PASS Sample (.1 ml Dose Rate at 1 ft.: < 2. mR/hr l
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OCNGS SCENARIO 33 ll' !
ANNUAL EXERCISE REV NO O i TABLE A-3.lb l REACTOR WATER ACTIVITY (T = 00:15) ( ) ,
1
]
Thore'is an analysis delay of up to 30 minutes after sampling ;
Nuclide Concentration ,
')
I-131 4.71E-04 uC1/cc I_q I-132 1.01E-03 uCi/cc I-133 5.98E-03 uCi/cc .!
I-134 2.33E-02 uci/cc I-135 1.40E-02.uci/cc Cs-137 1.24E-04 uCi/cc TOTAL WATER SAMPL2 4.49E-02 uCi/cc ,
DEI 131 2.65E-03 uCi/cc h
Normal Sample (10 ml) Dose Rate at l'ft. < 2. mR/hr It PASS Sample-(1. ml) Dosc Rate at.1 ft. < 2.'mR/hr '
PASS Sample (.1.ml) Dose Rate at 1 ft. < 2. mR/hr I
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'h OCNGS . . SCENARIO 22 ANNUAL EXERCISE REV NO O TABLE A-3.1c REACTOR WATER ACTIVITY (T = 00230) (
)
There is an analysis delay of up to 30 minutes after sampling-Nuclide Concentration
[ ___..._ __.............
I-131 4.71E-04'uci/cc I-132 1.01E-03 uCi/cc I-133 5.98E-03 uCi/cc-I-134 2.33E-02 uCi/cc I-135 1.40E-02 uCi/cc
['-
.Cs-137- 1.24E-04 uCi/cc.
TOTAL WATER SAMPLE 4.49E-02 uCi/cc
(- DEI 131 2.65E-03 uCi/cc
[
f-Normal Sample (10.ml) Dose Rate at 1 ft.: <.2. mR/hr PASS Sample (1. ml)
PASS Sample (.1 al)Dose Dose Rate < 3. mR/hr Rate at at 1 1 ft.:l ft.: < 2. mR/hr l
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OCNGS SCENARIO 22 lli ANNUAL EXERCISE REV NO O l TABLE A-3.id E; I: REACTOR WATER' ACTIVITY (T = 00:45) (
)
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.There is an analysis delay of up to'30 minutes after sampling Nuclide Concentration B:
'E l I-131' 4.71E-04 uCi/cc :
I-132 1.01E-0J uCi/cc I-133 5.98E-03 uCi cc i I-134 2.33E-02 uCi cc l I-135 1.40E-02 uci cc Cs-137 1.24E-04 uCi/cc TOTAL WATER SAMPLE -: 4.49E-02 uCi/cc -
l DEI 131 2.65E-03 uCi/cc l
I:
Normal Sample (10 ml) Dose Rate at 1 f t. :' < 2. .mR/hr -
PASS Sample-(1. ml) Dose Rate at 1 ft.: < 2 mR/hr !
PASS Sample ( .1 ml) Dose Rate at 1 ft.: < 2. .mR/hr .
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s s 0CNGS SCENARIO 22 ANNUAL EXERCISE. REV NO O
~
TABLE A-3.le' REACTOR WATER ACTIVITY (T = 01:00) (
)
- 'There is an: analysis delay of up to 30 minutes after sampling Nuclide Concentration L- ........ ...........___.
I-131 4.71E-04 uCi/cc
(. I-132 1.01E-03 uCi/cc I-133 5.98E-03 uCi/cc I-134 2.33E-02 uC1/cc I-135 1.40E-02 uCi/cc Cs-137 1.24E-04 uCi/cc TOTAL WATER SAMPLE 4.49E-02 uCi/cc DEI 131 2.65E-03 uci/cc Normal Sac,ple-(10 ml) Dose Rate at i ft. . < 2. mR/hr PASS-Sample (l'. ml) Dose Rate at i ft.: <'2. mR/hr PASS Sample (.1 ml) Dose Rate at 1 ft.: < 2. mR/hr
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OCNGS ANNUAL EXERCISE SCENARIO 22 I
REV NO O TABLE A-3.lf 4 REACTOR WATER ACTIVITY (T = 01:15)....................... ...__.......(.....
There is an analysis Nuclide delay of up to 30 minutes after sampling Concentration Xe-135 1.42E-04 uci cc I-131 4.58E-04 nCi/cc I-132 9.12E-04 uci cc I-133 5.76E-03'uCi cc
.I-134 1.86E-02 uCi cc
-I-135 1.32E-02 uCi/cc Cs-137 1.20E-04 uCi/cc TOTAL WATER SAMPLE 3.92E-02.'uci/cc DEI 131 2.54E-03 uCi/cc .
Normal Sample PASS Sample1. ((10 ml) DoseRate Rateat at11 ft.:
ft.: < 2. mR/hr I
ml) Dose PASS Sample (.1 ml) Dose Rate at 1 ft.: < 2..mR/hr
< 2. mR/hr. -
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SCENARIO 22 ANNUAL EXERCISE REV NO O TABLE A-3.lg E REACTOR WATER ACTIVITY (T.= 01:30) ( )
L- . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
ThereLis an analysis. delay of up to 30 minutes after sampling h $$$bbbI .bSES*.Eb5".bbSE.
Xe-135 2.80E-04 uCi/cc I-131 4.57E-04 uCi/cc I-132 8.46E-04 uCi/cc I-133- 5.71E-03 uC1/cc.
I-134 1.53E-02 uCi/cc I-135 .1.29E-02 uCi/cc Cs-137 1.20E-04 uCL/cc TOTAL WATER SAMPLE 3.56E-02 uCi/cc DEI 131 2.50E-03 uCi/ce'
[
Normal Sample (10 ml) Dose Rate at 1 ft.: < 2. mR/hr PASS Sample (1. ml) Dose Rate at 1 ft.: < 2. mR/hr
,. PASS Sample (.1 al) Dose-Rate at 1 ft.: < 2. mR/hr
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OCNGS SCENARIO 28 I -
ANNUAL EXERCISE REV NO O l TABLE A-3.1h REACTOR WATER ACTIVITY (T = 01:45) ( )
There is an analysis delay.of up to 30 minutes after sampling Nuclide Concentration i
Xe-135 '4.12E-04 uCi/cc I-131 4.57E-04 uCi/cc 7.84E-04 uCi/cc I-132 I-133 -5.67E-03 uCi/cc 3 I-134 I-135 1.25E-02 uCi/cc 1.26E-02 uCi/cc g; Cs-137' 1.20E-04 uCi/cc ,
i TOTAL WATER SAMPLE 3.26E-02 uCi/cc :i DEI 131 2.46E-03-uCi/cc !
i Normal Sample 10 ml Dose Rate at 1 ft.: < 2. mR/hr I1 PASS Sample 1. ml Dose Rate at 1=ft.: < 2. mR/hr ':(
PASS Sample .1 al Dose Rate at 1 ft.: < 2..mR/hr >
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- SCENARIO 22 d 1' ~ ANNUAL EXERCISE REV NO
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.. Of 3
- TABLEtA-3.11- ' ' '
. REACTOR-WATER ACTIVITY (T = 02:00);;(' ).
, q
- There'is'an.analysisLdelay of up-to 30 minutes;after sampling-
-s
-Nuclidei .:
.____.-- ' . Concentration.
.............. l
.- 4 Xe- 35' -5.38E-045uCi cc- , ,
4.56E-04 uCi cc-I-131 -
LI-132' 7.27E-04'uCi cc '
'?
-I-133 5.62E-03 uCi/cc- '
( ( '
.I-134 1~.03E-02-uCi/cc
'I-135
-1.22E-02 uC1/cc. 1
' " Cs,-137 1.20E-04:uci/cc 1
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-i 9 TOTAL WATER SAMPLE . 3' . 00E-02 .uci/cc r
. DEI 131: 2i43E-03 uCi/cc. -
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.- ' Normal ~Fample 10 ml -Dose Rate >at'1 ft.: -
.<.2.1mR/hr- -!
- ; ; PASS-Sample' 1.,ml
- Dose. Rate at:1 ft.:: < L 2.1- mR/hr. - ;
<'2..m3/hr.
PASS. Sample (.1 ml) Dose Rata =at 1 ft.:-
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SCENARIO 22-ANNUAL-EXERCISE' .
REV NO 0'
' TABLE A-3.1j-REACTOR WATER
__.........____.......... _______..__ACTIVITYc(T = 02:15)1('_... __)'- J .
P There-is an' analysis' delay of upito 30 minutesiafter sampling ~
Nuclide-Concentration iEfi g:-
....__.. ...___..........- r y
Xe-133 Xe-135 3.32E-05.uci/cc:
6.58E 04 uCi/cc lbl gr
'I-131 4.56E-04'uCi/cc ;
~
-I-132- :6.75E-041uCi cc 1-I-133- 5.57E-03 uci cc '
I-134 -8.46E-031uCi cc '-
.I-135 1.19E-02 uci cc- !
Cs-137' 1.20E-04 uCi/cc -
.j TOTAL' WATER. SAMPL2 2.79E-02 uCi/cc' DEI'131 '2.39E-03 uci/cc
~
.a Ii Normal' Sample' (10 ml) Dose Rate at.1 ft. : .=.'2.
< mR/hr. -
PASS Sample (1. ml) Dese . Rate atol ft. : .<-2. mR/hr ,
PASS Sample,( 1 ml) Dose Rate at'1,ft.:' -<12.-mR/hr .[
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OCNGS SCENARIO 22 ANNUAL EXERCISE REV NO O
) TABLE A-3.1k
) REACTOR WATER ACTIVITY (T = 02:30) ( )
\
There is an analysis delay of'up to 30 minutes after sampling
[ SSbb _bS$SbS"_bSS.
Xe-133 3.96E-05 uCi/cc Xe-135 7. */3E-04 uCi/cc I-131 4.56E-04 uCi/cc I-132 6.26E-04 uCi/cc I-133 5.53E-03 uCi/cc I-134 6.94E-03 uCi/cc I-135 1.16E-02 uCi/cc Cs-137 1.20E-04 uCi/cc TOTAL WATER SAMPLE 2.61E-02 uCi/cc I
DEI 131 2.36E-03 uCi/cc i
l Normal Sample (10 ml) Dose Rate at 1 ft.: < 2. mR/hr PASS Sample (1. ml) Dose Rate at 1 ft.: < 2. mR/hr PASS Sample (.1 ml) Dose Rate at i ft.: < 2. mR/hr
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OCNGS * -
SCENARIO 32
~ ~
ANNUAL EXERCISE . . - REV NO ' O~ j i .
. TABLE A-3.11 - - :
. - '$_ __ b ______
There:is an analysis
- delay.of up ito:.30 minutec-after; sampling Df Nuclide --Concentration ..
,Xe-133; .
-4.60E-05 uCi/cc- :
-Xe-135 8.82E-04 uCi/cc '
I-131 - 4.55E-04 u0i/cc-
- I-132. - 5.80E-04'uCi/cc: .
I-133 5. 4 SE-03 .: uCi/cc :
'I-134' 5.70E-03 uci/cc ?,
I-135 1.13E-02JuC1/cc '
.Cs-137 ' _______________
1.20E-04'uC1/cc
' TOTAL WATER-SAMPLE - 2.46E-02'uCi/cc -
. DEI 131 42.33E-03'uC1/cc: 1 5
.t Normal' Sample (10 ml). Dose Rate at.1 ft. :: --'< 2. ; mR/hr.:
~ PASS Sample-(1.-ml). Dose' Rate at1 ft.: .<t2. mR/hr-
.l
-PASS Sample (.1 ml)' Dose = Rate at?1 ft.: < 2 mR/hr-_ .
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SCENARIO 22-ANNUALfEXERCISE REV NO-
- 0
' TABLE A-3.1m - ..
REACTOR WATER ACTIVITY :(T-.=. 03 : 00) (;; . )-
___________________________________________m.
There is an' analysis delay of up to.30-minutes after sampling-
'Nuclide Concentration Xe-133: 5.24E-05'uC1/cc ,
[? EXe-135 -9.86E-04 uCi/cc LE 'I-131- 4'. 55E-04 ' uCi/ce '
-I-132 '5.38E-04 uCi/cc
(;
I-133 5.44E-03 uCi/cc-I-134 L4.68E=03 uCi/cc:
U I-135 J1.10E-02 uCi/cc.
Cs-137 1.20E-04L H
_________uci/cc'______
( -TOTAL WATER SAMPLE. 2.33E-02 uCi/cc-
" DEI 131- ' 2 ~. 3 0E-03 uci/cc --
(. '
5 Normal' Sample (10 ' ml)[: Dose ~ Rate 'at; l ' f t'. :. < 2.-mR/hr PASS Sample (1. ml) Dose' Rata at 1 ft.: :< 2. mR/hr-
-PASS Sample (.1 ml) . Dose Rate'_at-1 ft.: < 2.'mR/hr' i
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- SCENARIO 22. -
-ANNUAI[. EXERCISE ~ . .
REV NO 0- .- I TABLE A-3.1n= i
,-).
REACTOR WATER ACTIVITY . .__.
L(T. = .03 :15) ( .,3 There is an a'nalysis. delay-'of up to 30 minutes.after sampling .
j Concentration-Nuclide Xe-133 5'.86E-05 uCi cc . ;
~,. Xe-1351 1.08E-03~uCi cc- ,
- I-1311- 4.54E-04iuCi/cc 4 I-132- 4.99E-04 CCi/cc
-I-133 5.39E-03 uci/cc.
.I-134 3.85E-03'uCi/cc- q
-I-135 1.'08E-02CuCi/cc
t 1 .Cs-137 1.~20E-04 uCi/cc, .
c TOTAL'WATED SAMPLE _ 2.22E-02-uCi/cc R!
DEI 131 2.27E-03 uCi/cc' r
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Normal: Sample:(loiml) Dose. Rate'at-.1 ft.:- <-2. mR/hr -
. PASS Sample (1. ml) - Dose Rate 'at '11 f t. :: -<: 2.-.mR/hr PASS Sample-(.1 ml) Dose-Rate at;1.ft':1 < 2. mR/hr~
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OCNGS, , SCENARIO 22' ANNUAL EXERCISE- 1 REVcNo 0 TABLE A-3.lo REACTOR WATER: ACTIVITY-(T = 03:30) _(;__..__..
}
F There is an' analysis delay of up-to'30 minutes after sampling
-Nuc14de- Concentration-
- Xe-133 . ~6.49E-05 uCi cc1 Xe-135 1.18E-03 uCi cc I-131-. 4.54E-04 uCi cc '
-I-132 -4.63E-04 uCi/cc I-133 5.35E-03-uCi/cc
, I-134- 3.16E-03 ' uCi/cc-.
I-135 Cs-137,
'1.05E-02 uCi/cc
~1.20E-04=uCi/cc TOTAL WATERLSAMPLE 2.13E-02 uCi/cc1 DEI'131 2.25E-031uCi/ccL 14 -
o Normal SampleL(10 ml) Dose Rate at 1 ft.:; < f2. mR/hr-.
l PASS' Sample (1. ml) Dose Rate at 1' f t. : <- 2. mR/hr-PASS-Sample ( .1 ml); Dose - Rate at- 1. f t. : < L2. mR/hr- 'j 9
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OCNGS SCENARIO'22' ,
ANNUAL. EXERCISE REV NO 1:
~
O TABLE-A-3.1p -
/l REACTOR WATER ACTIVITY:(T.- 03:45) (
)
-There_is s an' analysis delay of up to 30 minutes-after sampling' ,
Nuclide . Concentration- ~
Xe-133- 7.10E-05 uCi/cc.
Xe-13 5 - ' 1.27E-03Luci/cc.
I-131 '4.53E-041uci cc '_
.I-132 4.30E-04 uci col EL
.I-133 5.30E-03)uci cc1 3 I-134 2.59E-03?uci/cc
-I-135: 1.02E-02 uCi/cc - -
Cs-137. :1.20E-04 uCi/cc
-l
' TOTAL WATER SAMPLE 2.05E-02 uCi/cci l
DEI 131 .2.22E-031uci/cc? is l
Normal Sample-(10 ml) Dose:-Rate at'1'ft.:. < 2. mR/hr
<-2'.-;mR/hr.-
PASS Sample ~(1. ml . Dose Rate'at 1 ft.:
PASS Sample-(.1 ml Dose. Rate at 1:ft.: ,<t2. mR/hr-
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- OCNGS . SCENARIO'22.
ANNUAL EXERCISE .
REV NO- . TABLE A-3.1q s
REACTOR WATER ACTIVITY-(T = 04:00) (
)-
_ There is art analysis -delay of up to 30 = minutes Jafter sampling-Nuclide Concentration L _...... ___...__.... __
Xe-133 7.71E-05 uCi/cc, h~~ Xe-135 1.35E-03~uci/cc I-131- 4.53E-04 uCi cc-I-132 3.98E-04 uCi cc j I-133 5.26E-03 uci cc .
[L I-134' 2.13E-03;uci cc >
d
__ I-135 9.96E-03 uCi cc !
Cs-137 le20E-04 uCi/cc' 1
( TOTAL WATER SAMPLE 1 98E-02 uCi/cc~
DEI 131 2.20E-03:uci/cc f
Normal SampleL(10fml) Dose' Rate at 1 ft.: < 2. mR/hr-PASS Sample-(1; ml) Dose Rate-at_1gft.-; ]ii
< 2._mR/hr-PASS ' Sample ( .1' ml) < Dose Rate: at f 1"ft. - <L2.EmR/hr'
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, t a i TOCNGS'. SCENARIO 22 ,
' ANNUAL EXERCISE RE'r NO, 4 0
. TABLE A'-3.'ir - .
REACTOR- WATER; ACTIVITY _(T' = : 04 :15); (-. -
_ . ): * .
'. \
l-.. -
L- There'is.'an analysis' delay _of up to 30.fminutes after<. sampling l
- Nuclide- Concentration J
.------- --------------- r Xe-133 8.32E-05auCi/cc Xe-135~ .1~.43E-03 uCi/cc '
I-1312 '4.53E-04 uCi/cc.
! I-132 3.70E-04 uCi/cc ;;
-I-133 :5.22E-03.uCi/cc. ti
-- I-13 4 t 1.75E-03 uC1/cc, :.i
'I-135' . 9.'71E-03 ; uCi/cc =
Cs-137" '1.20E-04;uCi/cc , E ii
.g
, --------Tuci/cc TOTAL WATER SAMPLE- 1.91E-02
.. DEI 131L(2.'17E 03 uCi/cc
- -t Normal Sample'(10 ml)= Dose 1 Rate'at'11fti
~
1< - 2 '. . mR/ h r : .?
PASS _ Sample _ (1. ;ml)-' Dose ' Rate: at _ l' f t. :- <' 2. : mR/hr.:
A PASS Sample _(.1 ml)j_ Dose. Rate'at 1:ft.: _ : < -. 2. mR/hr.- -
1:
4
~.
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' OCNGS-c ANNUAL" EXERCISE ~ SCENARIO 22 REV NO 0 TABLE A-3.ls' r'
I REACTOR WATER-ACTIVITY'.(T =-04:30)'(;-__. __._____.____....__________....___
I' .There[is'an analysis Nuclide delay'of up.toL30' minutes after sampling
. Concentration
.Xe-13 3 ' 8.91E-05 uCi/cc Xe-135 1.51E-03 uci/cc I-131 I-132 4.52E-04'uCi/cc
~
'I-133.
3.43E-04 uCi/cc.
~I-134 5.17E-03 uci/cc I-135 1.44E-03tuci/cc s -9.46E-03 uCi/cc;
- -Cs-137 1.20E-04'uCi/cc
. TOTAL WATER-SAMPLE. 1.86E-02:uci/cc, 1
(
1 DEI 131 2.15E-03;uCi/cc.
1 l
fl Normal. Sample-(10 ml)-Dose Rate at 1 ft.: .< 2; mR/hr<
- PASS = Sample. j
-PASS Sample:(1. mi i Cose. Rate at.1-ft.:s .<2. mR/hr -!
(.1 ml) Dose Rate.at 1 ft.: -< 2. mR/hr
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en
. . 1 OCNGS'.
ANNUAL EXERCISE..
SCENARIO 22.
REV NO- '0 -
}}l ~!
. . TABLE A-3.lt: -
REACTOR , WATER ACTIVITY '_(T = 04 : 4 5): '_( . }- '1
- ThereYis-an-analysis' delay of up to.30. minutes after sampling- :
Nuclidec ~ Concentration 1
]
Xe-133 l9.51E-05:uCi/cc. .'
'Xe-135-1.58E-03"uCi/ccj I-131. 4.52E-04luCi/cc ,
!I-132 : 3.18E-04 = uCi/cc ;: 1 1
'I-1331 5L13E-03!uCi/cc' - '
-I-134-- 1.~18E-03'. uCi/cc 1 ti
'I-135' 9.22E-032uCi/cc
' Cs-13 7 ::
1.20E-04 uCi/cc 3
- TOTALL WATER SAMPLE: 1.1. 81E-02. , uCi/cc DEI,131- 2.12E-03..uCi/cc, . .
Normal Sample (10 ml). Dose Rate:at 1 ft.: 7 < 2..mR/hr '
PASS Sample (1. ml) Dose Rate at 1'ft.:- < 2.;mR/hr
-PASS Sample (.1 ml).. Dose Rate at.1 ft.:- <:2._mR/hrf
- 3 d
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'OCNGS . , SCENARI0E22-LANNUAL EXERCISE:. . .
REV NO O TABLE A-3.lu?
REACTOR WATER ACTIVITY 1(T = 05:00) (. )~
There is an anal sis delay of up to 30 minutes after sampling
'Nuclide-- Concentration
, Xe-1331 l'. 01E-04:, uci/cc "
Xe-135 1.65E-03-uCi/cc I-131- 4~51E-04;uci/cc- -
I-132 2.95E-04,uci/cc I I-133 5.09E-03.:uci/cc I-134 9.68E-04 uci/cc I-135. .8.99E-03'uci/cc.
'.1.20E-04
............-- uCi/cc TOTAL WATER SAMPLE- 1.77E-02 uCi/cc <
~
- DEI 131, 2.10E-03---uci/cc s
. o
'{
q.
Normal ~ Sample-(102 ml) Dose = Rate.at::1 ft.:-.< 2. mR/hr~
PASS Sample (1. al) Dose Rate at 1:ft.:- < 2.1mR/hr:
PASS Sample (.1.ml)" Dose Rate at lift.:' < 2.LmR/?g
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OCNGS- -SCENARIO 22 ,
- ANNUAL EXERCISE REV NO- 0- ~ si TABLE A-3.1v- - '1 E REACTOR WATER ACTIVITY : (T =' 05:15) - (; ) i
- There'is an analysis delay,of up;to=30 minutes after sampl'ing
~
7
'Nuclide' Concentration.
,1 Xe-133E '1.07E-04 uCi/.cc Xab135 1.72E-03 uCi/cc I-131 .4.51E-04'uCi/cc. .
I-132, 2.74E-04 uCi/cc- l' I-133= 5.05E-03-uci/cc..
.I-134- -7.95E-04:uci/cc '!
- I-135 8.76E-031uCi/cc 6 Cs-137: .I n _'___..._______l.20E-04 uCi/cc-TOTAL WATER SAMPLE 1.73E-02 uCi/cc [
(
DEI 131 :2.08E-03/uci/cc -
5 l
1
-PASS Sample 10!ml) ((1.'ml)!DoseDose'Rate Rate at-1:'ft.:-
Normal Sample < '. 2. J:.mR/hr -
at'1 Eft.: < 2.lmR/hr -
t PASS Sample.(.1 ml). Dose Rate'at 1-ft.:< <~2.2mR/hrt 4 i
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, OCNGS SCENARIO 22- ;
,REV NO- 0 ANNUAL EXERCISE' TABLE-A-3.2a- , -;
. _TORUS
_ . . . _WATER
_ _ _ _ACTIVITY
_ _ _ _ (T. .=. 00:00)
. . . . .( . . _ _ _) _ _ _ _ _ _ _ _ _ _ _
- There is an analysis' delay of up:to-30 minutes after sampling.
Concentration Nuclide ,
~,
E Cs-134' 5.07E-08 uC1/cc
- Cs-137 1.87E-06 uCi/cc TOTAL' WATER SAMPLE 1.93E-06:uci/cc ,
DEI 131. As Found ,
~
' Normal Sample _(10 ml)" Dose Rate at'l'ft.:';<'2. mR/hr-
, PASS Sample (1.: ml) Dose ' Rate at"1: f t. : ' < 2. .mR/hr. -
PASS Sample (.1 ml) Dose Rate at-1 ft.:- < 2. mR/hr l i
k I
..m I
1 i
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OCNGS ANNUAL EXERCISE
, SCENARIO 22' I
- e. .
, REV:NO: 0-
. TABLE A-3.2b-y~ TORUSLWATER-ACTIVITY (T = 00:15)!(- ')
-. There Li:s an , analysis. delay; of-.up. to 30 minutes after sampling Nuclide: Concentration
, Cs-134' 5.07E-08 uCi/cc-Cs-137' 1.88E-06-uC1/cc TOTAL WATER SAMPLE 1.93E-06 uCi/cc q
DEI-1317 As Found.
_ g Normal Sample (10 ml)-' Dose Rate at 1 f t. :- _< 2'..mR/hr
~
2'. mR/hr-
- PASS.
PASS-Sample. (1. ml)!
Sample (.1_ml) Dose Rate at"1 ft.: << 2E Dose Rate at 1 aft.:
mR/hr. 1 z
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a OCNGS lSCENARIOL22-ANNUAL' EXERCISE' REV NO O'
~
TABLE A'-3.2c 1 TORUS WATER -)-
, ______________' ACTIVITY ~(T ='00:30) (
There is. an analysis delay of up , to' 30; minutes af ter sampling-c.
~
Nuclide Concentration: ;
_______ _______________. ~
Cs-134 - 5.' 07E-08_ uCi/cc
_' Cs-13 7 ' 1.88E-06 uCi/cc j -
TOTAL WATER SAMPLELfl.93E-06 uCi/cc DEIJ131: As1Found
. Normal 1 Sample (10"ml) Dose Rate at l'ft.: _. <2.EmR/hr )
- PASS: Sample (1.. ml)1 Dose Rate at t i 'ft. : < 2 1mR/hrJ i PASS-Sample--(.1 ml) Dose. Rate'at 1 ft.: J .< '2. mR/hri l
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-u OCNGS . . - SCENARIO-22 -
f . ANNUAL EXERCISE . ,
REV.NO- 0- .
TABLE A-3.2d. .
,[ '
).
y -__'___________
TORUS. WATER ACTIVITY.(T = 00:45) (
d- There - is an fanalysis delay of up- to 30 minutes af ter'samplitig ;-
y l .
' Nuclide
. Concentration.
~ Cs-134 - 5.07E-08 uCi/cc - 4 x Cs-13 7 .' 1.88E-06 uCi/cc; -
TOTAL WATER SAMPLE- 1.93E-06-uCi/cc. -;
DEI?1311- LAs'Found
_ I't Normal-Sample (10 ml) Dose Rate atL1 ft.: < 2.. mR/hr- :
PASS.' Sample
< =
- 2. mR/hr 'l
(.1(1.ml)-Dose ml) DoseRate Rateat at 1.ft.:
1 ft.: . < -- 2.f- mR/hr PASS Sample .
j h
1
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+ =
w- OCNGS: _ .
SCENARIO-22 ANNUAL EXERCISE 1REV NO .0
" TABLE A-3.2e .,
TORUS: WATER ACTIVITY (T =;01:00)= (
- c. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _). _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
Therells.'an analysis delay _of up to.~30 minutes afterl sampling-SSb"'_ __SESISbS"_bbSS.
< I-134 4.79E-09 uCi/cc-
'I-135' 2.87E-09 uCi/cc-4 Cs-134 5.08E-08 uCi/cc- <
Cs-137l _1.88E-06 uCi/cc TOTAL WATER SAMPLE .' 1.94E-06 uCi/cc=
DEI'131 5.45E-10-uci/ccl- ,
I Normal. Sample-(10 ml): Dose' Rate"at-1-ft.: <.2. mR/hr l PASS _ Sample (1.~ml)1 Dose Rate at 11ft.:
PASS Sample (.1 ml); Dose: Rate at l'ft;:
<-2. mR/ hrs
< ' 2 ". : mR/ hr _ ,
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'SCENARIOi22
-ANNUAL EXERCISE REV NO. .0 TABLE.A-3.2f. : -
TORUS: WATER ACTIVITY : (T =: 01:15) (
)
There is an analysisL delay of: up to 30 minutes af ter. sampling : 5L
- 4. ^. Nuclide Concentration = t >
I-132- ~ 3.93E-09'uCi/cc- .
I-133 .2.48E-08 uCi/cc l I-134-: 8.02E-08'uCi/cc :
I-135- 5.70E-08 uCi/cc:
7' -Cs-134' 5.67E-08 uci/cc' ,
o- -Cs-137 -2.~10E-06 uCi/cc TOTAL WATER SAMPLE' 2 3 E 06 uCi/cc DEI 131;- 1.09E-08[uci/cc- _
4 4
Normal-L Sample' (10 -ml). Dose = Rate t at;l f t. : - - < ' 2.: mR/hr PASS Sample (1. _ ml) Dose Rate at 1: f t. :. '< 2. mR/hr-PASS Sample ( .1 ' ml) . Dose Rate at 1 ft. :^ . < 2. mR/hr-I.
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'OCNGS- .
SCENARIO'22' ANNUAL EXERCISE. . REV NO -0:
. TABLE A-3.2g- .
L:. ___________________________________
TORUS WATER ACTIVITY_ (T = 01:30)'_( _______)-
There'is.an analysis' delay;of up to 30 minutes after sampling Nuclide- ,_______________.
Concentration-
-I-132 -3.61E-09:uci/cc I-133- 2.44E-08 uCi/cc I-134: 6.53E-08 uCi/cc I-135' 5.50E-08 uCi/cc Cs-134 6.14E-08 uCi/cc Cs-137~ <2.27E-06 uCi/cc.
TOTAL WATER SAMPLE 2.48E-06;uci/cci-
~
DEI 131 '1'.'07E-08 uCi/cc Normal Sample (10 ml) Dose Rate at 1-ft.: .< 2. mR/hr
<:2.. mR/hr
- PASS PASS Sample;(1.
Sample (.1 ml).ml)DoseDoseRateRate'at 11ft.: , < 2. mR/hr-at 1.ft.:
i
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-OCNGSi SCENARIO.32-
. ANNUAL EXERCISE . . . . . .. REV NO .0 TABLE A-3.2h -{
TORUS WATER ACTIVITYs(T.= 01:45);(. )* ,:q J
There.-is an. analysis delay'of up to 30 minutes ~after sampling 1 _J 4
Nuclide; Concentration. t
~
I-132' 3.35E-09 uCi cc^
'I-133 .2.42E-08 uCi cc E. - i' I-134- 15.36E-08'uCi/cc ;;
I-135 5.36E-08 uCi/cc-
'Cs-134 6.59E-08 uCi/cc:
'Cs-137 2.44E-06 uC1/cc. .
.i TOTAL' WATER SAMPLE 2. 64E-06 u'Ci/,cc. \
9
' DEI 131- 1.05E-08:uCi/cc- rl .
i t
NormalLSampleI(10.ml)' Dose'Ratetat-1:ft.:
L <-2. .mR/hr PASS - Sample . (1.: .ml) Dose : Rate: at 1 f t. :
<,2. mR/hr
-PASS Sample (.1 ml) Dose Rate;at'1'.ft.: _ <-2.;mR/hr ,.
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OCNGS SCENARIO 23 o -
ANNUAL EXERCISE REV.NO O TABLE A-3.21
, TORUS' WATER ACTIVITY-(T = 02:00)-l(
)'
There is an' analysis delay,of uptto 00 minutes after sampling Nuclide concentration L .-
I-132 ~ 3.11E-091uci/cc-I-133- 2'.40E-08 uCi/cc I-134 -4.~40E-08 uCi/cc I-135 5.23E-081uCi/cc
'Cs-134- 7.00E-08 uCi/cc Cs-137' 2.59E-06'uCi/cc:
. TOTAL WATER SAMPLEL: 2.78E-06 uCi/cc DEI 131' 1.03E-08 uci/cc 1 Normal Sample (10 ml) Dose Rate'at 1 ft'.: <b2..mR/hr PASS' Sample (1.Lml) Dose Rate-at:1 ft.: < 2 .1 mR/hr-PASSL Sample- ( .1 ml)1 Dose Rate: at 1 f t. : < 2.'mR/hr 3
l i
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... < OCNGS . SCENARIO 22-
.? --
' ANNUAL _ EXERCISE .
.REV NO O-
.. ' TABLE A-3.~21 ~E
'g.
TORUS: WATER ACTI /ITY c__ (T =______________
02 :15)J ( -)
'h There is'anianalysis delay of:up to 30; minutes'after sampling Nuclide . Concentration.
.I-133 2'.38E-08 'uCi/cc; :
I-134- 3.61E-08 uCi/cc-I-135 =5.09E-08'uCi/cc l Cs-134 7.35E-08!uCi/cc
' ..... _________ ; 3 .. . ;
TOTAL--WATER SAMPLE 2.91E-06 uCi/cc;
, = DEI 131'.1.'02E-08 uCi/cc~ :
Normal Sample- (10 ~ ml)' Dose ' Rate at ' 1: f t. :- < 2..mR/hr PASS Sample (l'. ml)' Dose Rate'.at l'ft.: . <i2.EmR/hr)
PASS Samplet( 1 ml) Dose Rate.:at 1 ft.: <.2.smR/hr; i
E f
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-OCNGS .
SCENARIO 22' ANNUAL EXERCISE-
. REV NO O
.TABL2.A-3.2k_
7 TORUS WATER ACTIVITY-(T'= 02:30)-( )
L There.1sLan analysis delay,of up to.30 minutes-after sampling Nuclide- Concentration.
[? _______ _______________
Xe-135 3.01E-09 uCi/cc I-133 '2.34E-08 uCi/cc
-I-134 2.94E-08^uci/cc -
I-135 4.92E-08 uCi/cc:
Cs-134 17.60E-08.uci/cc Cs-137u 2.81E-06'uci/cc TOTAL WATER SAMPLE 2.99E-06 uCi/cc
- i+ . DEI 131J 9.98E-09 uCi/cc Normal Sample-(10.ml)-Dose Rate at-1:ft.:' < 2. mR/hri PASS Sample (1.-ml) Dose Rate at i ft.:- < 2. mR/hr' j
' PASS: Sample (.1'ml)iDose. Rate at'1 ft.: <:2.-mR/hr' -
i
/ !
l 1
-SCENARIO 22-I i iANNUAL EXERCISE- .
REV No 01 ?
TABLE-A-3.21 -
TORUS. WATER ACTIVITY (T = 02:45)L(-
) =
r There islan analysis-delay of up to 30 minutes after sampling l '
Nuclide . .
Concentration -
Xe-135 3.4OE-09 uCi/ccl LI-133 2.32E-08"uci/cc-
'I-134- 2.41E-08.uCi cc:
I-135 4.79E-08 uCi cc Ti Cs-134 7.87E-08 uCi cc. I Cs-137 2.91E-06 uCi/cc
~- TOTAL' WATER SAMPLE-. l-3. 09E-06 uci/cc DEIfl31; 9.86E-09 uCi/cc I,
- )
Normal Sample'(10'ml)~ Dose Rate at'l-ft.:; _< 2. mR/hr. ~
PASS Sample-(1. ml)- Dose Rate at.1 - f t. :- < 2. mR/hr-PASS Sample (.1 ml)- Dose .Ratec at 1 ft. :
<~2. mR/hr ji I-ll Il
-1
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a
, OCNGS -
SCENARIO 22
' ANNUAL EXERCISE REV NO O'
-TABLE A-3.2m-LTORUS WATER ACTIVITY (T,= 03:00):(-
, ..........___...__________________..__.__-) .
Thereis an: analysis' delay of up to-30 minutes atter< sampling,
~
p Nuclide Concentration Xe-135 ~3'76E-09'uCi/cc I-133 2.30E-08 uCi/cc ,
--I-134l 1.98E-08 uCi/cc-l4.67E-08 uCi/ce' I-135 Cs-134 -8.11E-08 uci/cc Cs-137 3.00E-06 uCi/cc
- TOTAL WATERiSAMPLE
- 3'18E-06 uCi/cc=
DEI 131' 9.73E-09 uCi/cc q
q
[-- Normal Sample-(10 ml); Dose Rate at 1 ft.: .< -- 2 '. -.. mR/ hr .
t PASS Sample-(1..ml) Dose Rate at 1 ft.:
PASS Sample (.1-ml) Dose Rate at:1 ft.:.
< 2. mR/hr ;
< 2. mR/hr. ;
- f. -l 4
1 i
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. 3 OCNG S . '. SCENARIO:22 l' ANNUAL EXERCISE' REV NO 0. -
. TABLE A-3.2n -
TORUS WATER. ACTIVITY -- (T = 03 : 15) -- ( . -)' :
I s
There is:an analysis. delay of up to 30. minutes after sampling _-_ i Nuclide Concentration -
- ga;
.Xe-135:
I-133 4.09E-09 uCi/cc-
,2.28E-08 uCi/cc 3O '
--I-134 1.63E-08 uCi/cc' I-135' 4.55E-08.uci/cc ' B:
Cs-134'. '8.33E-08 uCi/cc- 3;,
3.08E-06 uCi/cc .
r TOTAL' WATER SAMPLE 3.25E-06 uCi/cc- _
- 1 DEI 131: 9.62E-09.uCi/cc < <f i ;;
t Normal Sample, (10. ml)' Dose ' Rate at 1 f t. :--
<~2.:mR/hr-
. PASS ' Sample -(1. ml) Dose' Rate at-1 ft.:--< 2. mR/hr PASS Sample: ( .1 ' ml) : Dose Rate > at~ l'. f t. : < 2. mR/hr, ,
m e
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l.
13 z, i
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OCNGS SCENARIO 22 ANNUAL EXERCISE REV NO O TABLE A-3.2o TORUS WATER ACTIVITY (T = 03 30) (
)
'there is an analysis delay of up to 30 minutes 'atter sampling p
Nuclide
-Concentration Xe-135 4.39E-09 uCi cc I-133 2.26E-08 uCi cc.
I-134' 1.34E-08 uCi cc-I-135 4.44E-08 uci cc 1 Cs-134
~
8.52E-08 uci cc Cs-137 3.15E-06 uCi/cc'.
~
TOTAL WATER SAMPLE 3 32E-06.uCi/cc.
DEI 131 9.50E-09 uCi/cc
- l l
- B Normal Sample (10 ml) . Dose Rate at 1 f t. I < 2.'mR/hr PASS Sample-(1. ml) Dose Rate at 1 ft.: < 2..mR/hr PASS Sample (.1 al) Dose Rate at 1 ft t. < 2. mR/hr l
- l. .
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OCNGS SCENARIO 22- l ANNUAL EXERCISE <REV NO O .i '
TABLZ A-3.2p TORUS WATER ACTIVITY (T = 03:45)-(
)-
There is an analysis delay of up to 30 minutes after sampling Nuclide Concentration _,!
Xe-135- 4.67E-09 uCi cc' : h I-133 2.24E-08 uCi cc !
I-134 1.10E-08 uCi cc- '
I-135 Cs-134
'4.32E-08 8.68E-08 uci uCi cc cc l[
3 Cs-137 _3.21E-06.uci cc j
TOTAL WATER SAMPLE 3.'38E-06 uC1/cc -l DEI 131 9.39E-09 uCi/cc {
Normal' Sample (10 ml Dose Rate at.1 ft.: < 2. mR/hr I. l PASS Sam-ia 11. ml . Dose Rate at 1 ft.: < 2. mR/hr ,
PASS Samp3 (.1 ml Dose' Rate at i ft.: < 2. mR/hr -
t i
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j OCNGS SCENARIO 22 ANNUAL EXERCISE REV NO- 0 i -
TABLE A-3.2q TORUS WATER ACTIVITY (T = 04:00) ( )
I There is an analysis delay of up to 30 minutes after sampling Nuclide Concentration Xe-135 4.93E-09 uCi cc I-133 2.22E-08 uci/cc I-134 9.02E-09 uci/cc I-135 4.21E-08 uCi/cc I Cs-134 8.8?E-08 uCi/cc Cs-137 3.26E-06 uci/cc TOTAL WATER SAMPLE 3 43E 06 uCi/cc DEI 131 9.29E-09 uCi/cc l
Normal. Sample (10.ml) Dose Rate at 1 ft.: < 2. mR/hr PASS Sample (1. ml) - Dose Rate at 1 f t. :
PASS Sample (.1 ml) Dose Rate at 1 ft.:
< 2. mR/hr
< 2. mR/hr I -
l 1
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OCNGS ,
SCENARIO 22 ;
ANNUAL EXERCISE REV No 0 TABLE A-3.2r ,
TORUS WATER ACTIVITY (T = 04:15) (
) ;
{
There is an analysis delay of up to 30 minutes'after sampling j c
""S2id* .se!'a!!!**!". !
Xe-135 5.16E-09 uCi/cc .
I-133 2.21E-08 uCi/cc '
I-134 7.40E-09 uCi/cc !
I-135
.Cs-134.
4.11E-08-uCi/cc 8.96E-08 uCi/cc 3'! -!
Cs-137- 3.31E-06 uci/cc g']
TOTAL WATER SAMPLE 3.48E-06 uci/cc ;
DEI 131 9.18E-09 uCi/cc .
1 Normal Sample 10 ml) Dose Rate at 1 ft.t- .< 2.:mR/hr PASS Sample 1. ml) Dose Rate at 1 ft. ; < 2. mR/hr .
j PASS Sample .1~ ml), Dose Rate at 1 ft.I ~< ?...mR/hr l q
)
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6 I
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s, OCNES SCENARIO 22 ANNUAL EXERCISE REV NO O TABLE A-3.2s TORUS WATER ACTIVITY-(T.= 04:30) ( )-
There is an analysis delay of upito'30 minutes after sampling-r Nuclide Concentration
(- . . . . . . . . ...............
Xe-135 5.37E-09 uCi/cc
(;- I-133 2.19E-08 uCi/cc L
I-134 6.08E-09 uci/cc I-135 4.00E-08 uCi/cc Cs-134 9.07E-08 uci/cc
- ~
f bibb2I.U $$
TOTAL WATER.SAMPLI 3.52E-06 uCi/cc
(-L DEI 131 9.08E-09 uCi/cc Normal Sample (10 ml) Dose: Rate at 1 ft.t < 2. mR/hr PASS Sample (1. ml) Dose Rate at 1 ft.t < 2. mR/hr PASS Sample ( 1 al) Dose Rate at 1 ft.: < 2. mR/hr 4
+
OCNGS SCENARIO 22 ANNUAL EXERCISE REV NO O TABLE A-3.2t TORUS WATER ACTIVITY-(T = 04145) (
)
There is an analysis delay of up to 30 minutes after sampling Nuclide concentratior.
Xe-135 5.57E-09 uCi cc '
I-133 2.17E-08 uCi cc I-134- 4.99E-09 uC1/cc
- I-135 3.90E-08 uCi cc Cs-134 9.17E-08-uCi cc.
Cs-137 3.39E-06 uCi/cc TOTAL WATER SAMPLE 3.56E-06 uC1/cc DEI 131 8.98E-09 uCi/cc Normal Sample (10 ml) Dosa Rate at 1 ft.* < 2. mR/hr PASS Sample (1. .ml) Dose Rate at 1 ft.:
PASS Sample (.1 ml) Dose Rate at 1 ft.:-
< 2. mR/hr
< 2. .
mR/hr _
-I I
I I
g
s OCNGS SCENARIO 22 ANNUAL EXERCISE REV NO O TABLE A-3.2u r
TORUS WATER ACTIVITY (T = 05:00) (
)
t There is an analysis delay of up to 30 minutes after sampling Nuclide Concentration Xe-135 5.74E-09'uCi/cc ,
(- I-133 2.15E-08 uCi/cc I-134 4.10E-09 uCi/cc I-135 3.80E-08 uCi/cc Cs-134 9.26E-08 uCi/cc Cs-137 .3.42E-06 uCi/cc TOTAL WATER SAMPLE 3.59E-06 uCi/cc DEI 131 8.89E-09 uCi/cc
(. .
Normal Sample (10 ml) Dose Rate at 1 ft.: < 2'. mR/hr PASS Sample (1. ml) Dose Rate at 1 ft.: < 2. mR/hr PASS Sample (.1 ml) Dose Rate at 1 ft.: < 2. mR/hr !
b
-6 e
OCNGS SCENARIO 22 ANNUAL EXERCISE 'REV NO O' TABLE A-3.2v TORUS WATER ACTIVITY (T = 05:15) (
)
There is an analysis delay of up to 30 minutes after' sampling Nuclide Concentration Xe-135 5.90E-09 uci cc ,
i I-133 2.13E-08 uCi cc-I-135- 3.70E-08 uCi cc l Cs-134 9.34E-08 uci cc ;
Cs-137 3.45E-06 uCi cc I TOTAL WATER SAMPLE 3.62E-06 uCi/cc :l DEI 131 8.79E-09 uCi/cc' ,
l I
Normal Sample 10 ml Dose Rate at 1 ft.: . < 2. mR/hr
, PASS Sample- 1. ml Dosa Rate at l'ft.: < 2. mR/hr !
PASS. Sample (.1 ml) Dose Rate at 1 ft.: ;< 2.7mR/hr -j 1
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{jy$[LEXERCISE SCENARIO 22 REV HO O
- TABLE A-3'3" L
DRYWELL GAS ACTIVITY (T = 00:00)
(~ )
L There is an analysis delay of up to 30 minutes after sampling Nuclida Concentration (1 Kr-85 2.11E-08 uci/cc TOTAL GAS SAMPLE 2.11E-08 uCi/cc
( TOTAL CHARCOAL SAMPLE As Found DEI 131 As.Found'
{ ..._.... ____..
TOTAL FILTER SAMPLE As Found Undiluted Gas Sample (15 ml) Dose Rate at 1 ft.: < 2. mR/hr Hydrogen Concentrations .0%
-[ oxygen Concentration: .0%
i
[
L i
4 i
4
OCNGS ANNUAL EXERCISE SCENARIO 22 I
L REV NO O -'
TABLE'A-3.3b .
.................................)..(........).
DRYWELL GAS ACTIVITY (T = 00:15 i.
I j
There is an analysis Nuclide delay of up to 30 minutes after sampling ,
Concentration xr- >
2las:ss.esite TOTAL GAS SAMPLE '2.11E-08 uCi/cc.
Ill ;
i
.............._ >j TOTAL CHARCOAL SAMPLE As Found-l i TOTAL. FILTER SAMPLE As Found !
Undiluted Gas Sample (15 ml) Dose Rate at 1 ft.:
II,
< 2. mR/hr. ,
Hydrogen Concentrations -.0%.
oxygen Concentration .0% l):'
)
l lli l l 4
l l
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l
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1 I
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k
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\
'OCNGS ANNUAL EXERCISE SCENARIO 22 REV NO O' TABLE A-3.3c DRYWELL GAS ACTIVITY = 00:30) (
......__.....__..__.....(T ....._____.. .......
)
There is an analysissdelay Nuclide of up to 30 minutes after sampling concentration Kr-85 4.22E-08 uCi/cc
{ TOTAL GAS SAMPLE 4.22E-08 (1Ci/cc I-131 8.01E-09.uci/cc , '
I-132 1.72E-08 ucl/cc
(. I-133 1.02E-07 uti/cc I-134 3.96E-07 uci/cc-I-135 1.07E-07 uCi/cc k TOTAL CHARCOAL SAMPLE 755EOhuCi/cc DEI 131
~
4.51E-08 uci/cc
. TOTAL FILTER SAMPLE 2.11E-09 uCi/cc Undiluted Gas Sample (15 ml) Dose Rate at i ft.: < 2. mR/hr Hydrogen Concentration: .0%
Oxygen Concentration: .0%
4 i
OCNGS SCENARIO 32 Il
' ANNUAL EXERCISE- REV NO O *
- TABLE A-3.3d 'i DRYWELL GAS ACTIVITY (T...,.....)
= 00:45 ..(........) i ll There is an analyais delay of up-to 30 minutes after sampling - '
Nuclide Concentration -
1 Kr-85' 6.33E-07 uCi/cc Xe-135 '1.10E-07 uC1/cc -! '
.............-- -. i iTOTAL GAS SAMPLE 7.40E-08 uCi/cc' l
' I-131 1.20E-07 uCi/cc
-I-132. 2.58E-07 uci/cc I-133: 1.53E-06 uCi/cc I-134 5.94E-06 uCi/cc ' 3' g!
I-135 2.81E-06 uCi/cc ;
TOTAL CHARCOAL SAMPLE l'06E-05 uCi/cc DEI 131 6.77E-07 uCi/cc -
TOTAL FILTER SAMPLE 3.18E-08 uC1/cc Undiluted Gas Sample (15 ml) Dose Rate at 1 ft.: <'2. mR/hr I Hydrogen Concentration: .0% j 0xygen Concentration:, .0% '
I, j-q y
-(
4 e 4
I-
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__.__._________m__
______..._____ -~u , , - . . . . , , , , , , . , _ _ , . . .,,g # j,,__..,, . . , . , _ . , , , . , , , , . . ,,y
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- OCNGS . SCENARIO 22 ANNUAL EXERCISE .
REV NO O ;
TABLE A-3.3e
[.
DRYWELL GAS ACTIVITY (T = 01:00) (
-)
There is an analysis-delay of up to 30 minutes after sampling
$$b .bSE$*.Eb5"bbSS. .
Kr-85 1.26E-06 uCi/cc Xe-135 2.21E uCi/cc
.....-07
-TOTAL GAS SAMPLZ 1.48E-06 uci/cc' I-131- 2'40E-07 uCi/cc I-132 5.16E-07 uCi/cc I-133- 3.06E-06 uCi/cc
( I-134 1.19E-05 uCi/cc l I-135 5.62E-06 uCi/cc TOTAL CHARCOAL SAMPLE 2.13E-05 uci/cc DEI 131 1.35E-06 uCi/cc I Cs-137 6.34E-08 uCi/cc TOTAL FILTER SAMPLE 7.22E-08 uCi/cc ;,
li Undiluted Gas Sample (15 ml) Dose Rate at 1 ft.: < 2. mR/hr Hydrogen Concentration: .0%
Oxygen Concentration: .0%
\
- d
b l L' OCNGS SCENARIO 22 I1 I ANNUAL EXERCISE REV NO O !
TABLE A-3.3f !
DRYWELL GAS ACTIVITY (T _ = 01:15) - ( ) l l
o There_is an analysis delay of up to 30 minutes after sampling l Nuclide Concentratien j Kr-85 2.52E-06 uCi/cc Xe-135 4.42E-07 uCi/cc !
TOTAL GAS SAMPLE 2.96E-06 uCi/cc .j I-131- 4.80E-07 uCi/cc -l I-132 5.33E-06 uCi/cc j l I-133 6.12E-06 uCi/cc :
I-134 2.38E-05 uCi/cc f 1.12E-05 uCi/cc I-135 TOTAL. CHARCOAL SAMPLE 4 6hh-OhuCi/cc ;
i DEI 131 2.70E-06 uCi/cc .
i.
Cs-137 .1.27E-07 uCi/cc TOTAL FILTER SAMPLE 1.87E-07 uCi/cc Undiluted Gas Sample (15~ml) Dose Rate at 1 ft.: < 2. mR/hr_ i Hydrogen concentration: 40% -
Oxygen Concentration .0%
i I
l l
I' h
I i
5
-i
' i l
1 P
L
- , - - , - ,.r. -.,.w *t
~
OCNGS . SCENARIO 22 ANNUAL EXERCISE REV NO O TABLE A-3.3g DRYWELL GAS ACTIVITY (T = 01:30) (
)
There is an analysis delay of up to 30 minutes after' sampling Nuclide Concentration Kr-85 2.78E-06 uCi/cc
- - 5 5:5: 7SS2/S!
(- .
TOTAL GAS SAMPLE' 4.43E-06 uCi/cc
( I-131 7.20E-07 uCi/cc I-132 5.85E-06 uCi/cc I-133 9.18E-06 uCi cc I-134 3.57E-05Luci cc
(. .I-135 1.68E-05'uci cc TOTAL CHARCOAL SAMPL2= 6.82E-05 uci/cc
( DEI 131 4.05E-06.uci/cc Cs-137 5.97E-07 uci/cc
( TOTAL FILTER SAMPLE 643E07uCf/cc Undiluted Gas Sample (15 ml) Dose Rate at 1L f t. : :< 2. mR/hr.
Hydrogen Concentration: .0%
0xygen Concentrations. .0%
{
(
l 7
{
I l
Il OCNGS SCENARIO 82 !
' ANNUAL EXERCISE REV No 0 -l TABLE A-3.3h . j DRYWELL GAS ACTIVITY (T = 01: 45) - ( ) 4 There is an analysis delay of up to 30. minutes after sampling Nuclide Concentration ,
i Kr-85 5.04E-06 uCi/cc ,
i Xe-135 8.84E-07 uCi/cc- ;
TOTAL' GAS SAMPLE 5.91E-06.uci/cc l'j I-131 9.60E-07.uci/cc 1 I-132 6.37E-06 uCi/cc j I-133' 1.20E-05 uCi cc
- I-134 4.76E-05 uCi cc I-135 - 2.24E-05 uci cc >
TOTAL CHARCOAL SAMPLE 8.93E-05 uCi/cc DEI 131 5.40E-06 uCi/cc l Cs-137 6.59E-07 uCi/cc !
L ...............
TOTAL FILTER SAMPL2- 7.23E-07 uCi/cc {
Undiluted Gas-Sample (15 ml) Dose Rate at 1 it.: < 2. mR/hr i Hydrogen-Concentration: B-Oxygen Concentrations 0%
0% l.; s 4
I:
l P
Ir
- u. -
k I
! .I L t F
u I!
! 1
- t t
u y up =.r
/
OCNGS SCENARIO 22 ANNUAL-EXERCISE REV NO O TABLE'A-3.31 r DRYWELL GAS ACTIVITY. (T = 02: 00) , ( )
p .
There is an analysis delay of up to,30 minutes after sampling i Nuclide Concentration s Kr-85 6.30E-06 uCi/cc r Xe-135 1.11E-06 uCi/cc
( ...............
TOTAL GAS SAMPLE 7.41E-06 uCi/cc
[ I-131 1.20E-06 uCi/cc
\ I-132 '6.89E-06 uCi/cc I-133 1.51E-05 uCi/cc I-134
~
5.95E-05 uCi/cc
. b. ~...$ .$$
TOTAL CHARCOAL SAMPLE 1.11E-04 uCi/cc
( DEI 131 6.75E-06 uCi/cc Cs-137 7.22E-07.uci/cc f TOTAL FILTER SAMPLE. 8 31E 07 uCi/cc Undiluted Gas Sample (15 ml) Dose Rate at 1 ft.: < 2. mR/hr Hydrogen Concentration .0%
oxygen Concentration .0%
4
. I OCNGS -
SCENARIO 22 ANNUAL EXERCISE .
REV NO O g, TABLE A-3.3j g'I '
DRYWELL GAS ACTIVITY (T = 02:15) (
)
There is an analysis delay-of up to 30' minutes after sampling-Nuclide Concentration E'
l XY-85 7.56E-06 uCi/cc- i Xe-135
.1.33E-06'uCi/cc f0TAL GAS SAMPLE 8.89E-06 uci/cc I-131 1.44E-06'uCi/cc -;
I-132 7.41E-06 uCi/cc 1 I-133 1.82E-05 uci/cc I-134 7.14E-05 uCi/cc [
I-135 3.36E-05 uCi/cc TOTAL CHARCOAL SAMPLE 13hE-04uCi/cc DEI.131 8.10E-06 uCi/cc Cs-137 '7.85E-07 uCi/cc.
f.
TOTAL FILTER SAMPLE 8.02E-07 uCi/cc-k Undiluted Gas Sample-(15 ml) Dose Rate at'l ft.: < 2. mR/hr ;
Hydrogen Concentration:
Oxygen Concentration:>.
.0%
.0% l ',
5
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I!
gi
- I f
I,!
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OCNGS .
SCENARIO 22 f~' . ANNUAL EXERCISE REV NO O
-TABLE A-3.3k :
t DRYWELL GAS ACTIVITY (T = 02:30) ( )
l-There is an analysis delay of up.to 30 minutes after sampling .
Nuclide concentration e
Kr-85 8.82E-06 uCi/cc Xe-135 1.55E-06 uCi/cc ;
TOTAL GAS SAMPLE .1.04E-05 uci/cc ;
I-131 1.68E-06 uCi/cc. -
f
' I-132-I-133 7.93E-06 uCi/cc ,
2.13E-05 uCi cc !
.I-134 8.33E-05 uCi cc' !
I-135 3.92E-05 uCi cc ;
3 TOTAL CHARCOAL SAMPLE 1.53E-04 uCi/cc ;
DEI 131 '9.45E-06 uCi/cc
[
Cs-137 -8.48E-07 uCi/cc-
- TOTAL FILTER SAMPLE 9.22E-07 uCi/cc Undiluted Gas Sample (15 ml) Dose Rate at i ft. : < 2. mR/hr i
i Hydrogen Concentration: .0%
Oxygen Concentrationt .0%
v
.i l
[
i i
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' OC14GS SCENARIO 88 I> ,
ANNUAL EXERCISE REV NO- 0' .i TABLE A-3.31 i
..N[ bb bb .Ibb$b .1$.I... ..b.f.......b !
There is an analysis delay of up-to 30 minutes after sampling f Nuclide Concentration Kr-85 1.01E-05'uCi/cc Xe-135 1.77E-06.uci/cc
.............. i TOTAL GAS SAMPLE 1.19E-05 uCi/cc I-131~ 1.92E-06:uCi/cc .
f I-132 8.45E-06 uCi/cc l I-133 2.44E-05 uCi cc !
I-134 9.52E-05 uCi cc !
I-135 4.98E-05 uCi cc ;
TOTAL CHARCOAL. SAMPLE 1.80E-04 uCi/cc l DEI 131~ 1.08E-05 uCi/cc !
Cs-137 9.11E-07 uCi/cc i TOTAL-FILTER SAMPLE 1.02E-06 uCi/cc ,
t Undiluted Gas Sample (15 ml) Dose Rate at 1 ft.t. < 2. mR/hr .
Hydrogen Concentration: .0% a oxygen Concentration: '
.0%
g ,1~
1 I
I!:
s I
Ii l
I l 8
OCHGS 4 ANNUAL EXERCISE' , SCENARIO 22 REV HO O TABLE A-3.3a
- DRYWELL GAS ACTIVITY )
. . . . . . . . . . . . . . . . . . . . . . . .( ....................
T=03:00)(
There.is an analysis Nuclide delay of up to 30 minutes after sampling 7 ....... Concentration I Kr-85 Xe-135 ' 1.14E-05 uCi/cc 1.99E-06 uCi/cc '
TOTAL GAS SAMPLE 1.24E-05 uCi/cc I-131.
I-132 2.16E-06 uCi/cc I-133 8.97E-06 uCi/cc 2.75E-05 uCi/cc I I-134 I-135 1.07E-04 uci/cc 5.04E-05 uCi/cc-TOTAL CHARCOAL SAMPLE 1.96E-04 uCi/cc DEI 131 1.22E-05 uCi/cc Cs-137 I 9.74E-07 uC1/cc TOTAL FILTER SAMPLE 1.12E-06 uCi/cc Undiluted Gas Sample _ (15 ml) Dose Rate at i ft. : < 2. mR/hr Hydrogen Concentration: .u.
Oxygen Concentration .0%
- i. .
I g _
'i l
u
_ - - - - ~ ~ ~-~' ~
OCNGS ANNUAL EXERCISE SCENARIO 32 i REV NO- 0 l TABLE A-3.3n DRYWELL GAS ACTIVITY.(T = 03:15 -
..................................)..(........) -
-l There is an analysis Nuclide delay of up to 30 minutes after sampling ;
Concentration ;
' t Kr-85 1.27E-05 uCi/cc i
-Xe-135 2.21E-06 uCi/cc
?
............... i TOTAL GAS SAMPLE 1.49E-05.uCi/cc
' I-131 2.40E-06 uci/cc -!
I-132 9.49E-06-uCi/cc I-133 I-134 3.06E-05 uCi/cc l;
.I-135 1.19E-04 uCi/cc 3?
- 5.60E-05 uC1/cc t TOTAL CHARCOAL. SAMPLE 2.17E-04 uCi/cc !
DEI 131 1.35E-05 uCi/cc .i Cs-237 1.04E-06 uCi/cc TOTAL FILTER SAMPLE 1.27E-06~uCi/cc.
I.r 3 l !
Undiluted Gas Sample (15 ml) Dose Rate at 1 ft.: < 2. mR/hr~
Hydrogen Concentration: .0% !
0xygen Concentration: .0%
o
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4 OCNGS SCENARIO 22 ANNUAL EXERCISE .
REV NO O TABLE-A-3.3o
[
DRYWELL GAS ACTIVITY (T = 03:30) (
)
, There is an analysis delay of up to 30 minutes after sampling b S$bbN* . .bS$$'.Sb#"bbS$...
Kr-85 1.40E-05 uCi/cc
(- Xe-135 2,43E-06 uCi/cc TOTAL GAS SAMPLE 1.68E-05 uCi/cc
( -I-131 2.64E-06 uci/cc I-132' 1.00E-05 uCi/cc I-133- 3.37E-05 uCi cc r I-134 1.31E-04 uCi cc
( I-135 6.16E-05 uCi cc TOTAL CHARCOAL SAMPLZ 2.39E-04 uCi/cc DEI 131 1.49E-05 uCi/cc Cs-137 1.10E-06 uCi/cc TOTAL FILTER SAMPLE 1.37E-06 uC1/cc
{ Undiluted Gas Sample (15 ml) Dose Rate at 1 ft.1 < 2. mR/hr' Hydrogen Concentration: .0%
Oxygen Concentration .0%
1 i
l 1
j
OCNGS SCENARIO 22 I-ANNUAL EXERCISE REV NO O TABLE A '.I.3 DRYWELL GAS ACTIVITY'(T =p03:45
.. .................. ............) ..(........)
There is an. analysis: delay of up to 30 minutes after sampling Nuclide Concentration i-Kr 1.53E-05 uCi/cc Xe-135- 2.65E-06 uCi/cc
- TOTAL GAS SAMPLE 1.80E-05 uCi/cc I-131 2.88E-06 uci/cc I- 132 1.05E-05 uCi/cc l Z-133 3.68E-05 uci/cc -
I-134 1.43E-04 uCi/cc I-135 6.72E-05 uC1/cc TOTAL CHARCOAL SAMPLE 2.60E-04 uCi/cc 1
DEI 131 1.62E-05 uC1/cc I Cs-137 1.16E-06 uCi/cc TOTAL FILTER SAMPLE 1.23E-06 uCi/cc .;
Undiluted Gas Sample (15 ml) Dose Rate at 1 ft.: < 2. mR/hr i
i
' Hydrogen Concentration: .0% '
Oxygen Concentration: .0%. -
- a l
Il l..
I ;
4 j
- i. $
OCN8S ANNUAL EXERCISE SCENARIO 22 REV NO O TABL2 A-3.3=q
-DRYWELL GAS ACTIVITY 04:00) (
................ .......(T.................... )
There is an analysis Nuclidedelay of.up to 30 minutes after sampling Concentration Kr-85 1.66E-05'uCi/cc Xe-135 2.87E-0C uCi/cc
( ,
TOTAL GAS SAMPLE 1.95E-05 uCi/cc r I-131-( I-132 3.12E-06 uCi/cc I-133 1.11E-05 uCi/cc I-134.
3.99E-05 uCi/cc f
'I-135 1.55E-04 uCi/cc
( 7.28E-05 uCi/cc TOTAL CHARCOAL SAMPLE 2.82E-04 uCi/cc DEI 131. 1.76E-05 uCi/cc Cs-137 1.23E-06 uCi/cc
( TOTAL FILTER SAMPLE 1.39E-06 uCi/cc Undiluted Gas Sample-(15 ml) Dose Rate at 1 ft.: < 2.'mR/hr Hydrogen Concentration: .0%
0xygen Concentration: .0%
i
~
1
)
a
OCNGS SCENARIO 22 ANNUAL EXERCISE REV NO O 1 TABLE:A-3.3r i DRYWELL GAS. ACTIVITY-(T = 04:15) (
). ;
i There is an analysis delay-of up.to 30 minutes:after sampling l
I Nuclide Concentration Kr-85 1.79E-05 uCi/cc l Xe-135 3.09E-06.uci/cc l -TOTAL GAS SAMPLE 2.10E-05 uCi/cc ;
I-131 3.36E-06 uCi/cc I-132 1.16E-05 uCi/cc. .
- i I-133 4.~30E-05 uCi cc .
I-134 1.67E-04 uCi cc l
- I-135 7.84E-05 uC1/cc ;
l TOTAL CHARC0AL SAMPLE 3.03E-04 uCi/cc ;
i DEI 131 1.89E-05 uCi/cc l Cs-137 1.29E-06 uCi/cc
.......-_...... I: ! t TOTAL FILTER SAMPLE 1.31E-06 uCi/cc 1
Undiluted Gas-Sample (15 ml) Dose Rate at:1 ft.: < 2. mR/hr )
Hydrogen Concentration .0%-
Oxygen Concentration .0%.
In 4
I! ,
I IR i
D
_ _ . . . - . . _ _ . - . - _ . . . _ - . __ . .. .a. ,__ ,__ _ ., __
OCNGS SCENARIO 22 ANNUAL EXERCISE . REV NO O' l TABLE A-3.3s DRYWELL GAS ACTIVITY (T = 04:30)
( . ...
)
There is an analysis delay of up to 30 minutes after sampling Concentration Nuclide Kr-85 1.92E-05 uCi co' Xe-135 3.31E-06'uCi cc ,
.....___.....__ t TOTAL GAS SAMPLE 2.25E-05 uCi/cc I-131 '3.60E-06 uCi cc I-132 1.20E-05 uCi cc I-133 4.61E-05 uCi/cc ;
I- I-134 1.79E-04 uCi/cc I-135 8.40E-05 uCi/cc TOTAL CHARCOAL SAMPLE 3 25E 04 uCi/cc DEI-131 2.03E-05 uCi/cc J
"~
- b
. b_. SS i' TOTAL PILTER SAMPLE 1.46E-06 uCi/cc Undiluted Gas Sample (15 ml) Dose Ratie at 1 f t. : < 2. mR/hr.
L Hydrogen concentration: 4
.0% '
Oxygen Concentration: .0% -
V t
w 1-5
- a L
- 7. .
L F t -
l L
L
.:-.~- a.
OCNGS- SCENARIO 22 I
ANNUAL EXERCISE .
REV NO O -
TABLE A-3.3t j DRYWELL GAS ACTIVITYJ (T = 04:45) (
.) .;
l There is an analysis delay of up to 30 minutes after sampling- .
Nuclide Concentration Kr-85 2.05E-05 uCi cc i Xe-135 3.53E-06 uCi/cc ;
TOTAL GAS SAMPLE 2.40E-05 uci/cc I-131 ;3.84E-06.uci/cc l' I-132 '1.26E-05 uci/cc I-133 4.92E-05 uCi/cc E I-134 1.90E-04 uCi/cc 3i I-135 8.96E-05 uCi/cc l
TOTAL CHARCOAL. SAMPLE 3.45E-04 uci/cc DEI 131 2.16E-05 uci/cc Cs-137. 1.42E-06 uCi/cc TOTAL FILTER SAMPLE- 1.51E-06 uCi/cc ,
Undiluted Gas Sample (15 ml) Dose, Rate at 1 ft.: < 2. mR/hr. I:'
Hydrogen Concentration:- .0%
Oxygen Concentration: .0% .
e -
It F
--I t
(
i mm l
l
. t gu I:f r
.. .__ _. . _ _ . . , _ _ - . _ ~ - _ - - . . - . . . . . - - . _ _ - , - _ _
t
. OCNGS .'
SCENARIO 22"
- ANNUAL EXERCISE- , ..
REV NO O u
TABLE A-3.3u
- . DRYWELL GAS ACTIVITY '(T = 05 t 00) ' (: ) L.
b ,
There is<an analysis delay of=up1t o-30'ainutesi fter sampling-
-l4 Nuclide- Concentration
.. Kr 8 : 2 18E-05 uCi cc-- .l 3.75E-06 uCi/cc
'Xe-135' 1
. TOTAL GAS. SAMPLE- 2.56E-05:uci/cc
-I-131~ 4.'08E-061uci cc-
>I-132' 1.31E-05 uCi cc.. H lI-133 5.23E-05 uCi/cc. 4 4
'I-134 2.02E-04 uCi/cc-
.I-135 9.52E-05 uCi/cc TOTAL CHARCOAL ~ SAMPLE =3.67E-04 uCi/cc
\
DEI 131 '2.30E-05 uCi/cc Li Bs i Cs-137 1.48E-06 uCi/cc:
h .
TOTAL FILTER SAMPLE _ 1'.57E-06,uCi/cc '-
Undiluted, Gas- Sample (15 ml) : Dose Rate.Jat'1Jfti:' y 2..mR/hr; .
5 Hydrogen Concentration:' .0%: y Oxygen Concentration: .0%- '
]
B.
4 I
o l b
1 i
i
,e :
+ l
't
- < .OCNGS SCENARIO 22- 'I ANNUAL 7 EXERCISE REV No O' .;
TABLE A-3.3v
- DRYWELL GAS: ACTIVITY (T'=>05:15) (
)- '.
There is anDanalysis; delay of up1to?30 minutes after' sampling- !
TI
- Nuclide Concentration
- Kr-85 2.31E-051uci/cc ;
'Xe-1351 3.97E-06,uCi/cc ,
'[
3 TOTAL GAS SAMPLE' 2.71E-05'uCi/cc-4.32E-06 uCi/cc I-131- ,
I-132 1.37E-05 uci/cc 5;54E-05.uci cc'
'I-133. '
I-134 '2.14E-04 uCi cc-
- I-135L 1=.01E-04 uCi cc TOTAL CHARCOAL-SAMPLE! 3.88E-04 uCi/cc- If
' DEI 131 2.43E-05cuci/cc 5 Cs-137- '
.1.54E-061uci/cc.
d TvTAL FILTER SAMPLE 1'. 71E-061 uci/cc' Undiluted Gas-Sample-(15-ml) DoseLRate at?1(ft.: ' <42. mR/hr.
i
' Hydrogen Concentration:: . 0%- i Oxygen Concentration:. ..' 0%-
L -
I 'i E "
1 m
f t
-~i r
i
'f
.l LI
)
,, m. . - , . J., , , - -- . . , - - , '& . . . ~ 3-- - . _ , . . .
s ,
. [i '
s R
OCNGS SCENARIO 22 ANNUAL-EXERCISE- .
. REV NO 0.
TABLE A-3.4a- ..
TORUS: GAS ACTIVITY (T = 00:00) (J
)-
h There 'ist an analysis delay of up to 30- minutes after sampling; "
Nuclide Concentration Kr-85 1.42E-08 uCi/cc
' TOTAL GAS SAMPLE '1.42E-081uci/cc
. TOTAL CHARCOAL SAMPLE 1 'As Found i DEI 131 As Found- j i
Cs-137' 1.83E-061uci/cci j
TOTAL FILTER SAMPLE- '1.88E-06 uCi/cc Undiluted _GasL Sample 1(15 ml)i D ose Rate at - 1 f t.':: < 2. mR/hr.
Hydrogen-Concentration: .0%
Oxygen Concentration: .0%
4 i
I i>
1 l
1 .i t1
't' i OCNGS' SCENARIO 22 i
' ANNUAL- EXERCISE .. .
REV NO- 0-
=
TABLE A-3.4b' l :. ,'
TORUS GAS! ACTIVITY-(T ='00:15)-( ) 3q L ,
There-is an analysis delay of-up to 30 minutes after sampling -
f Nuclide L concentration- 3i l .
r . .
-s .
Kr-85 '1.42E-08 uCi/cc l ' '
TOTAL GAS SAMPLE' l'.42E-08 uCi/cc
'i
. . . - 1 TOTAL CHARCOAL 1 SAMPLE - .As.Found !
, - 1
. DEI:131- As Found-Cs-137- 1.62E-06 uCi/cc l
TOTAL FILTER SAMPLE 1.66E-06 uCi/cc:- ~>
Undiluted Gas' Sample (15 ml) Dose. Rate a't-I ft.: .
< 2. mR/hr. :-
p Hydrogen Concentration:' = .' 0 % -
L Oxygen Concentration: . 0%
1 1 i l ;, .7 '
la .
.i ll .O
)
L i :
~)\
o 4 -
(
N
)
- a r
.i
./ , .
.;p
, 4 ! ,, , q
..__.-m-. s___ - -
.1 .
. - . - - . , . . . .i! . - - - - ,, '. . -
L.- . .
E . OCNGSi .
SCENARIO 22
)
-ANNUAL EXERCISE: .. REV NO O
} TABLE A-3.4c-TORUS.' GAS ACTIVITY (T; = 00:30): (: .
.).
4- There is an-analysis' delay of up toL30 minutestafter sampling i Nuclide Concentration.
'Kr-85' 1.42E-08 uCi/cc-
-TOTAL GAS SAMPLE 1.42E-081uci/ccL q i
TOTAL CHARCOAL SAMPLE As Found' DEI 131 AsLFound
, Cs-137 1.43E-06 uCi/cc n
TOTAL FILTER' SAMPLE 1.47E-06 uCi/cc - i Undiluted Gas Sample'(151ml) Dose Rate at i ft.: < 2. mR/hr Hydrogen concentration:- .0%
Oxygen Concentration:- .' 0% ll 1
I I
i t
i 1
i l
n.
..n
+ '
-OCNGS _ -
SCENARIO 22'
. ANNUAL EXERCISE: REV'MO- 0 :
TABLE-A-3.4d .
. TORUS: GAS ACTIVITY : (T1 = ,00: 4 5)- ( )
There is an. analysis delay'of up to 30-minutes after-sampling-Nuclide" Concentration.
~
b'._b~bb_Ub!S$ _ l TOTAL GAS' SAMPLE 1.41E-08~uCi/cc=
s.
~
TOTAL' CHARCOAL SAMPLE- As-Foundi DEI 131 As Found Cs-137- 1.,26E-06Euci/cc TOTAL FILTER SAMPLEL -1.29E-06 uci/cc ,
- 'j
~
i Undiluted. Gas Sample 1(15 ml): Dose-Rate at 1 ft.:. < 2L InR/hr.-
. Hydrogen Concentration: .0% -l Oxygen Concentrations. .0%'
il ;
l:: k l
.d -
gq E:
e -
4 OCNGS e ANNUAL EXERCISE- SCENARIO 22' lREV-NC 0 TABLE A-3.4e TORUS. GAS (
ACTIVITY-(T:=.01:00)..___-..__........._______).
-There is an analysis-delay Nuclide of up to 30 minutes after-sampling Concentration p -Kr-85 1.41E-08 uci/cc l
TOTAL GAS SAMPLE. 1.41E-08 uCi/cc I _-__.._.....___
TOTAL CHARCOAL SAMPLE As Found DEI 131 As.Found Cs-137 1.11E-06Tuci/cc-TOTAL' FILTER-SAMPLE 1.'14E-06>uci/cc Undiluted Gas Sample:(15'ml) Dose. Rate at 1 Eft.: ><'2. mR/hr
!\'
HydrogenEConcentration:'- .0%
Oxygen Concentration: .0% ,
I 4
l ,.
l .
a I .
l
- - . - - - - .- - . . . ~
, ll
^t OCNGS~ .
SCENARIO 22 .
, - ANNUAL EXERCISE , - REV NO :0 i TABLE A-3.4f .
TORUS GAS ACTIVITY . (T : = 01:15)-.. ( )
a Therefis an' analysis delay of;up to 30'; minutes after sampling.
Wuclide Concentration- .
- .__ __ ..___......____ r
-Kr (1.41E-08 u'Ci/cc:
l
. TOTAL GAS SAMPLE 1.41E-08 uci/cc
'I-131 2.60E-14 uC1/cc, .
4 I-132- 5.10E-14.uCi/cc- -"
I-133- 3.27E-13 uCi/cc '
'I-134 ;1.06E-12.uCi/cc- '
I-135 7.51E-13luci/cc.
TOTAL CHARCOAL SAMPLE'_2.'21E-12'uCi/cc
. DEI-131? 1.44E-13 uCi/cc-L ci- ,
ed e:e u e a t'#
TOTAL-FILTER SAMPLE > l'.01E-06;uCi/cc. ,
Undiluted Gas Sample-(15 ml) Dose)Ratetat 1"ft.: <[2. mR/hr- -
Hydrogen; Concentration: .~ 0 % ~ m Oxygen Concentration:' '. 0%
g ai 1
l .: 'L i
L -;
I e
t f
-A g
1 I . -o-. .+ - . . . . . . --.%.~.*bo. .- ,-= , .- +e.- ~ y-c~ ,--
s 5, OCNGS1 SCENARIO 22; ANNUAL EXERCISE . .
-REV NO O TABLE A-3.4g O TORUS GAS ACTIVITY ~(T.= 01:30)E( )
l.
'There is an analysis delay ofLup-to 30 minutes after sampling Nuclide. Concentration
.Kr 85- -
1.42E-08-uCi/cc TOTAL GAS SAMPLE: 1.42E-08Luci/cc I-1311 5.08E-14 uci/cc
-I-132 ~ '9.40E-14 uCi/cc I-133' 6234E-13 uCi/cc
'I-134' 1.70E-12 uCi/cc-
.I-135L 1.43E-12 uCi/cc j
TOTAL CHARCOAL SAMPLE. 3.91E-12.uci/cc -1 DEIJ131 -2.77E-13 uci/cc Cs-137 '8.71E-07,uCi/cc
_______________ y; TOTAL FILTER SAMPLE" 8.94E-07 uci/cc -1 Undiluted. Gas Sample (15 ml) Dose Rate..at.1 ft.: '< 2. mR/hr-Hydrogen Concentration: .0% ,
Oxygen Concentration: .0% -o 1l o
I
.I i
i li l
,Jz< .
i
' OCNGS- -- SCENARIO 22 I
- t. 0:
ANNUAL' EXERCISE . REV NO -
-l TABLE A-3.'4h" '
TORUS ' GAS ACTIVITY ' _(T =__01: 4 5). (_____..________'_).
i There:is an analysis delay of up to 30iminutes after sampling > I
- Nuclide- -Concentration.
j Kr 1.42E-08.uCi/cc;
. [I ;
TOTAL GAS? SAMPLE: .1. 4 2E-08 Luci/cc -- .,
I-131 .7 '. 2 5E-14 . uci/cc 7 ,
f I-132- .1.25E-13"uCi/cc -
I-133 '8.99E-13:uCi/cc'- !
I-134- 1.99E-12 uCi/cc
'I-13 5. : ,__1.99E-12 ____._uCi/cc:
.j
.- -TOTAL CHARCOAL. SAMPLE '5.09E-12'uCi/cce -
DEI 131! 3.90E-13.uci/cc.
Cs-137 -r -
1, 7.'_68E-07 e_____-
. _ ___ uCi/cc- -
TOTAL-FILTER SAMPLE-:7.89E-r" uCi/cc. .
4 Undiluted Gas Sample:(15 ml) Dose . Ra. .s -: at = 1:- f t. : - < 2. -E mR/hr - L 1
Hydrogen Concentration:- . 0 % '- i Oxygen Concentration:- . 0% .;
- l. o
[- <
v s
>- . U l
l l j l
- 5 1
. 7.
%2__
- t" ew y'+ ben- w-m Vpy.-- M =* +e-e " h- 96 'hi= '
.* T weW YW- --M '@ W -
w I.
v*
b
'l
. OCNGC-. .
SCENARIO 22
. . ANNUAL-EXERCISEE -REV NO 0-
' TABLE.A-3.41 TORUS GAS ACTIVITY (T'= 02:00) (
).
~
There~is an~ analysis delay of:up to 30 minutes after. sampling _
-Nuclide- Concentration g
Kr-85 , 1.42E-08LuCi/cc-TOTAL GAS SAMPLE!l1.42E-08 uCi/cc_- s I-131 9.16E-14LuCi/cc- 11 a I-132., - 1. 4 6E-13 : uci/cc
--I-133 .li 1.13E-12 uCi/cc I-134 '2.07E-12 uCi/cc I-135 '2.46E-12 uCi/cc TOTAL CHARCOAL SAMPLE 5 90E 12 uCi/cc:
-DEI 131' 4.'87E-13:uci/cc -
Cs-137 .6.78E-07 uCi/cc. I
-TOTAL FILTER SAMPLE 6. 9 6E-07 '- uCi/cc _. s Undiluted' Gas Sample (15 ml) Dase Rate at 1 ft.: <'2. mR/hr I Hydrogen-Concentration: . 0% j Oxygen Concentration:- .0% '
l
-1 14 m
(
1 i
,=y.
- - . . . . ~__- . . - - - .
. . , - - ~ - - . - - - - - .. - .
OCNGS '
ANNUAL EXERCISE SCENARIO >22 '1
'REV NO- O '.
1 TABLE A-3.4j: .
E' z
___ __. TORUS
_____. GAS E ..__.. ACTIVITY ___2 ____.. (T = 02:15)
.. J( _____ _ -
) g-l .
There is an analysis delay of up to 30aminutes.afterfsampling.
.) '
Nuclide~ -Concentration '
- )
, r < !
Kr-85D
.._'___ ..1141E-08 uC1/cc ; ELc g
-TOTAL GAS'SAMPLEi 1.42E-08LuCi/cc
.i 1
I-131 l'.08E-13 uci/cc -I I-132: 1.61E-13.uCi/cc. - -
I-133- 1.33E-12 uci/cc '
I-134- -2.02E-12 uCi/cc ::- !
I-135 2.84E-12 _.. uCi/cc j .
. TOTAL CHARCOAL SAMPLE;;6.'45E-12'uCi/cc: .
- l.
DEI-1311. 5.69E-13 uCi/cc-U
- e :>
. Cs-137 5.98E-07~uCi/cc -t N TOTALLFILTER-SAMPLE. 6.14E-07;uci/cci q;l g
Undiluted' Gas. Sample .(15 ml) Dose Rate ~ at 1 ft. : . .
< 2
~
mR/hr-. .E"i e
Hydrogen-' Concentration: .0% 3u =1 Oxypn: Concentration:' .0% ' ..
y
- E
e at l iE ',
i.
'I d .
1 e l i '
t
'- y,
'.y
- ' I
' 1 s
- .--wa- , - - < , . . . - , . -
1' m
,,q
-OCNGS---
,- ANNUAL EXERCISE SCENARIO 22.
REV NO- OJ TABLE:A-3.4k' TORUS GAS ACTIVITY (T = 02:30 e-
..----.........--.------)--(......--).
- There'is-an analysis
.Nuclide delay of;up to 30 minutes after sampling.
g ----- -
Concentration L
Kr 1.42E-08:uci/cc
{ ---....... --._
TOTAL ~ GAS-SAMPLE 1.43E-08 uci/cc- '
I-131 .i 1.24E-13LuCi/cca ~
{ I-132, I-133-I-134 1.70E-13Luci/cc 1.50E-12 uCi/cc 1.89E-12 uCi/cc I-135 3.16E-12 uCi/cc 3 . - - - - . . . . . - - - - - - . j TOTAL CHARCOAL SAMPLE- 6.86E-12 uCi/cc' 1
..s DEI 131 .6.42E-13 uCi/cc . 1 j
Cs-137 5.31E-07-.uci/cc -
\
TOTAL FILTER SAMPLE 5.45E-07 uCi/cc hi s
Undiluted Gas Sample (15 ml) Dose Rate at'l^ft.: -
<-2. mR/hr-i I
[
L.
Hydrogen Concentration: .0% '
oxygen Concentration:' ' 0% .
h !
4 1
q t
7 ,
n
-h
h- .
1
- OCNGSL .
SCENARIO 22' !
- ANNUAL EX?RCISEE . -
~ REV NO 0. -
' TABLE A-3.41 .
TORUS GAS ACTIVITY (T. = - 02 : 45) -(
.___' ________....__...___________.____'__.__._ ) -l
'l
~
There is an analysis delay of up to 30 minutes after sampling)
Nuclide Concentration- 5 Kr-85 '1.42E-08 uCi cc- ,
Xe-135- 1.85E-10 >
_..._ _ _ __uCi cc -______
' TOTAL GAS SAMPLE 1.44E-00 uCi/cc -1 I-131 .1.37E-13.uci/cc 1 I-132' 1.75E-13'uC1/cc Ji I-133--- 1.65E-12 uCi/cc El' A 'I i13 %
I- 13 k 1.72E-12 uCi/cc..
l3441E-12 uCi/cc, 3j >
TOTAL CHARCOAL . SAMPLE n
7.^10E-12"uci/cc ~lu
' DEI 131 7.02E-13 uCi/cc-4.68E-07:uci/cc:
Cs-137- ,
TOTAL FILTER SAMPLE 4.81E-07.uCi/cc.
[ l
-Undiluted: Gas Sample (15'ml) Dose Rate at l'ft.': ' <;2.'mR/hr: -
.}
. Hydrogen Concentration: .0%
Oxygen Concentration:' .0% .
3 ,
1 l
% v l 1
l A'
.l
'1
.l i
'l'
'l e
t
4 ,
4 T" OCNGS' . SCENARIO 22 x- -ANNUAL EXERCISE ~ _
REV-NO O TABLE A-3.4m
.. TORUS GAScACTIVITY'(T = 03:00). (.
)
There is an anal'ysis delay of up to:30 minutes after sampling-g.
-Nuclide" ' Concentration Kr-85 Xe-1351 11.42E-08:uci/cc 2.36E-10 uC1/cc TOTAL, GAS SAMPLE' 1.44E-08juCi/cc I-131 1.49E-13 uCi/cc I-132 -1.76E-13 uCi/cc
.I-1331 1.78E-12 uCi/cc
-I-134 ' 1.53E-121 uCi/cc I-135 '3.61E-12 uCi/cci TOTAL CHARCOAL SAMPLE 7.25E-12 uci/cc 7 !
}
DEI 131 17.52E-131uci/cc l Cs-137 14.13E-07 uCi/cc l
{ TOTAL-FILTER ~ SAMPLE 4.25E-071uci/cc 3
i i
Undiluted Gas Sample (15'ml) Dose Rate at'l ft.:' -
<'2.'mR/hr. 1 1 Hydrogen Concentration:' .0%L Oxygen' Concentration: .0%-
j 1
k I-4
): I
~
, n i
I l
G j OCNGS- -SCENARI0'22 _;
ANNUAL EXERCISE. .REV.NO O-TABLE-A-3.4n: ..
TORUS > GAS ACTIVITY -:- (T; = 4 03 :15) -(- . -)
There.is anianalysis' delay.of up to=30 minutes-after sampling. ; .
- l. Nuclide '
concentration
. 3, Kr-851 1.41E-08-uCi/cc.
l Xe-135- 2.90E-10 uci/cc 1
l' ' TOTAL GAS SAMPLE = 1.45E-08 uCi/cci - 'f
- ' .)
'1.59E-13 uCi/cc I-131
.1 l <
P I-132- 1.75E-13t uci/cc- -t l I-133 1.88E-12.uCi/cc' g7, I-134 1.35E-12 uCi/cc. g"L
.I-135 3.76E-12 uCi/cc-l TOTAL CHARCOAL SAMPLE . 7.33E-12 uCi/cc : -
l DEI 131 .7.95E-13 uCi/cc, ,,
t: ;
Cs-137 3.65E-07-uCi/cc: E
_____._____.___ _ g -- >
TOTALi FILTER SAMPLEi 3.75E-07 uCi/cc'
=
. Undiluted Gas . Sample f(15 L ml) . Dose. Rate at :1- f t. :
J< 2. mR/hr: -!
4 Hydrogen, Concentration: - .0%
l oxygen-Concentration: . .0%- ,.
i, 'I a i' I 4 3
f' t .;
i p ' !
s d
1 J?
(
- -+n- ,+ - . , - , - --s- n- ,~, ,- <a w ..A-,-.
A
.OCNGS -
SCENARIO 22 ANNUAL EXERCISE , REV NO O
-TABLE A-3.4o TORUS GAS ACTIVITY (Tl =, 03 : 30)- ( .)
- There is: an analysis = delay of: up to 30 minutes' atter ' sampling L Nuclide- Concentration; ,
L _______- _______________
Kr-85 1.41E-08 uCi/cc
(!! ,
. Xe-13 5_- 3.48E-10 uCi/cc TOTAL GAS SAMPLE 1.45E-08 uci/cc;
(' I-131 1I-132-1.68E-13-uCi/cci
'1.71E-13'uCi/cc-
'I-133 '1.98E-12'uCi/cc ,
. 1.17E-12 uCi/cc' I-134 E
I-135. 13.88E-12.uci/cc TOTAL CHARCOAL-SAMPLE- '7.36E-12.uci/cc DEI 131 8. 31E-13 uCi/cc Cs-137~ .3.22E-07 uCi/cc 1
-TOTAL FILTER SAMPLE 13'.31E-07 uCi/cc-
{ Undiluted Gas SampleL (15 ml): Dose Rate at-l' ft. :L < 2 '. mR/hr Hydrogen Concentration:' .0% '
Oxygen Concentration: .0% 1 a ;
i 4
1 2
/
s t
...c n, "!
. LOCNGS SCENARIO 22- '
ANNUAL EXERCISQ . REV NO 0 I TABLE-A-0.4p :l
-TORUS-GAS ACTIVITY (T =-03:45) ( )' l There11s an" analysis delay of up to 30l minutes after. sampling
'Nuclide ' Concentration #
i Kr-85l'. 1.41E-08tuci/cc.
Xe-135 4.10E-10 uCi/cc:
TOTAL GAS' SAMPLE-'1'.46E-08 uCi/cc. kq n;,
,; -I-131 1.76E 13 uCi/cc- :
I-132 1.66E-13 uCi/cc-
I-133'- 2.05E-12 uci/cc. .
I-134 1.01E-12 uCi/cc. -!
.I-135 3.962-12 uCi/cc
.. --_------ =l TOTAL CHARCOAL SAMPLE. 7~.36E-12 uCi/cc DEI 131 l8.60E-13 uCi/cc
.Cs-13'7. ~2.84E-07:uCi/cc.
TOTAL FILTER SAMPLE '2'.92E-07 uCi/cc .,
Undiluted Gas Sample-(15 ml)LDose Rate at-l'ft.: .< 2..mR/hr-' [
I Hydrogen Concentrationi '
.0% :
Oxygen Concentration: ' .0% -
t' i-I j
'1 l
. 'l -
.1 i
'l l
l l
, 1
=
, I g:
4 i
. . _ . . . . . _ _ ' - -. _ . ... . . . - . - - . .~ .. . s.;. a ..-..;,.
7--__
b ,
OCNGS- .
ANNUAL EXERCIS'S SCENARIO 22 -
REV No. 0 TABLE A-3.4q l TORUS GAS ACTIVITY (T = 04:00)- (
E )
There is an analysiscdelay Nuclide of,up to130 minutes after sampling-
- t. Concentration
[ __. .__ ____.......__..'
Kr-85 1.41E-08luci/cc
'Xe-135 4.74E-10 uci/cc-
' TOTAL GASfSAMPLE' l'.46E-08 uCi/cc- 1 I-1312 1.82E-13 uCi/cc
- I-132 1. 61E uci/cc ;-- -
I-133-I-134-2.12E-12'uCi/cc I-135
- 8. 59E-13: uci/cc 4.01E-12'uCi/cc-TOTAL. CHARCOAL 1 SAMPLE '7.33E-12.uci/cc DEI-1311 8.85E-13'uC1/cc' l Cs-137 !.2.51E-07 uCi/cc
...___.......... {
TOTAL. FILTER SAMPLE 2.58E-07.uCi/cc Undiluted Gas--Sample =(15 ml)LDose Rate atL1 ft.: < 2.=mR/hri !
Hydrogen--Concentration:: .0% '
Oxygen Concentration:) .0%= * ]
1 i..
q
.i h
i
-l 1't i
1
-i i
. .l
~ - -
, . . .g >. ,,
~...
i l<
,v OCNGS SCENARIO 22-ANNu7$L EXERCISE' REV NO O iJ
- TABLE-A-3.4r ,
,, TORUS. GAS ACTIVITY'(T = 04:15) ( ) , l
,There'is an: analysis delay of up to Concentration; 30 minutes after. sampling ' q Nuclide :
Kr-85 1.41E-084uCi/cc- It-j f
.Xe-135. 5.4OE-10 -
________'uCi/cc n
. TOTAL GAS SAMPLE-- 1.47E-08.uCi/cc I-131= ~ 1.89E-13'uCi/cc-I-132 1.54E-13 uCi/cc) ,
2.17E-12'uCi/cc ;5 I-133 >
- I-134. 7.30E-13Luci/cc- :
.I-135: s 4.05E-12.uci/cc:
~ TOTAL CHARCOAL SAMPLE'. L7.29E-12 uCi/cc !
DEI 131 9.05E-13 uCi/cc: ,
Cs-137' 2.22E-07
_ _ _ _ _ _uCi/cc 0
. TOT 7.L FILTER SAMPLE '.2.28E-07.uCi/cc
~ Undiluted' Gas: Sample.(15,ml) Dose. Rate at 1 ft.:
~
< 2. mR/hr Hydrogen Concentration:
Oxygen Concentration:
.0% lj
.0% W=
'f k
^;
4 6
P: ~OCNGS .
. SCENARIO 22' u ANNUAL EXERCISE .
'REV NO O TABLE A-3.4s'
. . . . . TORUS
. . . . . . .. GAS:ACTIVITYf(T
. . . . . _ _ _ . . _ _ . .=. .' 0 4 : 3 0 ) > ( .)
7 ................-
"c .
e There is- an analysis delay of up to' 30 minutes after sampling
- -Nuclide
. Concentration It Kr-85 Xe-135-1.41E-08 uC1/cc 6.09E-10
.....____uCi/cc .__...
I TOTAL ~ GAS SAMPLE-s1.47E-08 uCi/cc-I-131- 1.94E-13 uci/cc
.I-132: 1~.47E-13'uCi/cc >
E I-133' 2.22E-12'uCi/cc j g ~I-134. '6417E-13 uCi/cc. j
- I-135'
_4.06E-12
_........ . .. uci/ccL TOTAL CHARCOAL SAMPLE. -7.23E-12 uci/cc)
DEI =131 .
9.21E-13 uci/cc j t
I Cs 137 TOTAL FILTER SAMPLE 22.01E-07-uCi/cc 1.96E-07suci/cc' I
Undiluted Gas Sample (15 ml)' Dose: Rate' at ' l f t. :; < L2. mR/hr- -
.i Hydrogen Concentration: "
i Oxygen-Concentration:
.0%~
.0%
l 1 q 1
I 1 1
I I
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OCNGS" - SCENARIO-22 ANNUAL} EXERCISE . . REV NO- 0- 1 TABLE A-3.4t' - . .
1 TORUS GAS; ACTIVITY (T =:04:45)!.( )'
Therefis an analysis ~ delay of up'.to 30 minutes after_ sampling-Nuclide Concentration.
-Kr-85 1.41E-08 uCi/cc' !
4 Xe-135 6.79E-10.uci/cc
~ TOTAL GAS SAMPLE ;1.48E-081uci/cc- -
?
.I-1311 -1.99E-13 uCi/cc.
l- I-132 1.'40E-13 uCi/cc -v e I-133- 2.25E-12 uci/cc-< - '
'i
," I-134- 5.19E-13zuCi/cc- . 'j
, I-135 4.05E-12'uC1/cci TOTAL: CHARCOAL SAMPLE- 7.17E-121uci/cc. E- ,
g.
[ DEI 1311 .9.34E-13 uci/cc I Cs-137 1.73E-07'uCi/cc E
_______________ _l ';;'
2 . TOTAL FILTER SAMPLI 1.77E-07'uCi/ccL ;
I' ~
Undiluted Gas -Sample- (15 ml) . Dose Rate atil f t. : <^2. mR/hr - '
i L Hydrogen' Concentration:' _.0%
, ' Oxygen Concentration:. . 0%- 1 I
. t I
i I:
t; - '
- j. : i L 4 r-,.
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- 1
.1
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I' OCNGS SCENARIO /22 ANNUAL-ZXERC.ISE . . .
. _REV NO. O TABLE A-3.4u
___ b b_b b - _".b'1 bL ______L There is an analysis delay of'up to 30-minutes after sampling
[ .
Nuclide Concentration Kr-85 . 1.41E-08 uci/cc Xe4135 '7.51E-10 u01/cc
-TOTAL GAS SAMPLE. 1.49E-08 uCi/cc.
I-131 2.03E-13-uCi/cc I-132 1.32E-13 uci/cc-I-133' 2.28E-12 uCi/cc
=I-134 4. 3 5E uCi/cc !
I-135 '. 4. 04 E uCi/cc -; j TOTAL' CHARCOAL SAMPLE 7.09E-12 uCi/cc
- l DEI 131 9.43E-13 uCi/cc l
.1 Cs-137 1.52E-07'uCi/cc TOTAL FILTER. SAMPLE 1.57E-07 uCi/cc a
Undiluted Gas Sample.(15 ml)!Cose Rate at l ft.:. < 2.. . mR/hr -
Hydrogen Concentration: .0% .q Oxygen Concentration: -.0%
j l <
-i 1
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+
- ANNUAL EXERCISE. SCENARIO 22 REV NO- 0 TORUS: GAS' AC Y 05:15 -
~~~~~~~~~~~~-------------~________)*(~ )-
There is an analysis Nuclide delay lof'.up1to 30'mi'nutes after.. sampling; lIs, Concentration
~~ -- --
.Kr-85' '
-Xe-135 L1.40E-08 uCi/cc-8~.24E-10'uci/cc-
' ~
--- -- ~ -- -.
TOTAL GAS SAMPLE ,1.49E-08 uCi/cc .
I-131: 12.06E-13 uCi/cc; I-132L
~-I 133. 1.25E-13 uCi/cc ,
-I-134 22.31E-12LuCi/cc E" 3.64E-13!uC1/cci
.-I-135- , B:
'4.01E-12 uCi/cc-:
TOTAL CHARCOAL SAMPLE- "
- 7. 01E-12.1 uCi/_cc -
DEI l.131 9.51E-13 uCi/cc.
~
b *. ~~ - ' - SS-
- TOTAL; FILTER SAMPLE /l1.38E-07'uci/cc -
Undiluted Gas Sample! (15 ml) Dose Rate -at 1 ft. : .
<f2. mR/hr- - >
Hydrogen Concentration: .'0%
O x y g e n C o n c e n t r a t i o n ::.' = . 0%
= , , ,
g:
Bi I
3:
k . '
o ,
- i 4 ~OCNGS' SCENARIO'221 ANNUAL EXERCISE ~ 'REV-NO 0 TABLE A-3.5a
,_ _ . . .5_ bbb b ....___b m --There is an analysis? delay of up,to 30 minutes after sampling-I Nuclide- . Concentration I iTOTAL GAS SAMPLE-- As'Found 1 ' TOTS.L; CHARCOAL SAMPLE : As'Found q
. DEI 131- 'As'Found-
' TOTAL' FILTER SAMPLE As Found-Undiluted Gas' Sample.(15 ml)LDose Rate atL1 ft.: .< 2.fmR/hr.
1 1
Hydrogen Concentration: . 0 %'
Oxygen-Concentration:121.0%
Airborne Beta Dose. Rate: f<:2. mrad /hr ..
Net Air Sample Count-Rate:: < 2. cpm / min 1 I Air-Sample contact: Dose Rate:-< 0.2/ mrad /hr. .
]
Floor. Contamination:< 100,-cpm /100cm2 j Wall and .Equ pment Contamination:<: 100. cpm /100cm2 l l Personne Contamination Rate:<'100. cpm /100cm2.per minute- '
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OCNGS SCENARIO 22 Il'l ANNUAL EXERCISE .. .REV NO. 0 -
-l
. TABLE A-3.5b:
REACTOR BLDG ACTIVITY =(T:=-01:00) (.. .)
. There is'an analy$is' delay'of up to 30' minutes'after'. sampling- '
Nuclide concentration- _ -.
~
Au1Found:
TOTALLGAS SAMPLE' TOTAL CHARCOAL SAMPLE . As Found a .
l-DEI 131 LAs Found. g[ .
_ _ . . _ _ _ _ _ _ . - - gi TOTAL FILTER SAMPLE- As,Found- . g'.
Undiluted Gas Sample (15 ml) Dose Rate'at.1 ft.: < 2. .mR/hr, .]
. Hydrogen Concentration:a .041
. Oxygen Concentration: 21'.0%
Airborne Beta Dose' Rate:- '<-2. mrad /hr. *
. Net Air.-Sample Count Rate:: L< 2./ cpm / min i Air Sample Contact-Dose Rate:c<.0.2 mrad /hr' -
_1 Floor Contamination:<:.100. cpm /100cm2
~
. Wall--and Equipment' Contamination:< 100 cpm /100cm2.
Personnel Contamination. Rate:< 100.-cpm /100cm2-per. minute a , i.
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OCNGS' .
' SCENARIO 2'2 ANNUAL: EXERCISE- REV_NO 0 TABLE A-3.5c REACTOR
___ ... __________ BLDG ACTIVITY _______ (T =:02:00) (
......._'________. ) -
i There is ' an ' analysis / delay of' up to .30 : minut'es: after- sampling Concentration-Nuclide j '. TOTAL' GAS' SAMPLE As'Found.
1 TOTAL CHARCOAL SAMPLE As-Foundi i ,
DEI 131 As Found. ']
= TOTAL. FILTER SAMPLE As Found: '
Undiluted, Gas Sample (i5 ml) Dose Rate at 1 ft.: <L2. mR/hr
<1 Hydrogen Concentration: . 0 % .-
Oxygen Concentration: 21.0% '
i Airborne Beta Dose Rate: .< 2.'_ mrad /hr ~
Net Air-Sample Count Rate: '<2. cpm / min Air Sample-Contact Dose-Rate:-<LO.2 mrad /hr
. Floor contauination:<'100 _ cpm /100cm2.
Wall and< Equipment-Contamination:< 100.'. cpm /100cm2.
Personnel Contamination. Rate:< 100.. cpm /100cm2 per minute: 3 i
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ll1 OCNGS. SCENARIO 22- ,
. ANNUAL EXERCISE LREVENO-
~
O' ~!
TABLE A-3.5d. q REACTOR BLDG ACTIVITY .- (T = 02: 30) .( . ;)= ;
Therejislan analysis delay of up toL30lminutesLaft'er sampling J Nuclide Concentration o
'1
' TOTAL GAS SAMPLE- As Found -
,1
. TOTAL CHARCOAL SAMPLE- As;Found.
. DEIL131- 'As Found ^
P
, TOTAL FILTER SAMPLE ~As Found TUndilute'd Gas . Sample' .(15. ml) - Dose . Rate. at 41 f t. : . < 2. mR/hr
. Hydrogen Concentration:. .0%:
Oxygen Concentration: 21.0% ;
fAirborne Beta Dose Rate: l< .
2.' mrad /hr N Net- Air : Sample Count" Rate:; ~< - 2'.' cpm / min Air Sample Contact Dose' Rate:f< 0.212ad/hr- ,
FlooriContamination:'</100. cpm /100c52- H Wall.and Equipment Contamination:< 100.: cpm /100cm2-Personnel. Contamination Rate:< 100.scpm/100cm2:per minute.
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OCNGS SCENARIO 22 ANNUAL EXERCISE REV NO O j TABLE A-3.5e -
J )
REACTOR BLDG ACTIVITY (T = 02:45) (
There is an analysis delay of up to 30 minutes after sampling Nuclide Concentration
-Xe-133 9.74E-04 uCi/cc Xe-135 1.87E-02 uCi/cc TOTAL GAS SAMPLE 1.96E-02 uCi/cc I-131 2.75E-07 uC1/cc I-132 3.52E-07 uCi/cc B X-133' 3.32E-06 uCi cc j I-134 3.46E-06 uCi cc I-135 6.86E-06 uCi cc TOTAL CHARCOAL SAMPLE 1.43E-05 uCi/cc DEI 131 1.41E-06.uCi/cc j ....... .......
B TOTAL FILTER SAMPLE As..Found Undiluted' Gas Sample (15 m'.). Dose Rate at 1 ft.t <-2. mR/hr i Hydrogen concentration: . '0%
Oxygen Concentrationt 21.0%
~
Airborne Beta Dose Rate: 1000._ mrad /hr ',
Net Air Sample Couitt. Ratet 4.0E5 cpm / min '
Air Sample Contact Dose Ratet 30. mrad /hr Floor Contaminationt 4100.-cpm /100cm2
Wall and Equipment Contamination 500, cpm /100cm2 Personnel Contamination Rats: 1100. cpm /100cm2 per minute t
1
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i OCNGS~ SCENARIO 32 l ANNUAL-EXERCISE REV NO O ?
TABLE A-3.5f ,
.bb[bb... bib $b!b$b.b$.5b$bbb.f..__...
There is an analysis delay of up to 30 minutes after sampling- :
Nuclide Concentration i Xe-133 9.02E-04 uCi cc Xe-135 1.70E-02 uCi/cc i
TOTAL GAS SAMPLE 1.79E-02 uCi/cc -
I-131 2.25E-07 uCi cc '
I-132 2.66E-07 uci cc- r I-133 2.69E-06 uCi cc >
I-134 2.32E-06 uCi/cc I-135 5.46E-06 uCi/cc t
TitAL CHARCOAL SAMPLE 1.10E-05 uCi/cc DEI 131 1.14E-06 uCi/cc
.___.__........ i TOTAL FILTER SAMPLE As Found Undiluted Gas Sample-(15 ml) Dose-Rate at 1 ft.: < 2. mR/hr Hydrogen Concentration: .0% i Oxygen Concentration: 21.0% <
Airborne reta Dose Rate: 980. mrad /hr- i Net Air Sataple Count Rate: 3.255 cpm / min Air Sample Contact Dose Rate: 25. mrad /hr Floor Contamination: 3300. cpm /100cm2 Wall and Equipment Contamination: 420. cpm /100cm2 -
Personnel Contamination Rate 900. cpm /100cm2 per. minute O
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.OCNGS SCENARIO 22 ANNUAL EXERCISE REV NO O TABLE A-3.5g r
REACTOR BLDG ACTIVITY (T = 03:15) (
)
There is an' analysis delay of up to 30 minutes after sampling Nuclide Concentration Xe-133 8.67E-04 uCi/cc
'Xe-135 1.60E-02 uCi/cc TOTAL GAS SAMPLE 1.69E-02 uCi/cc I-131 2.10E-07 uCi cc
.I-132 2.31E-07 uCi cc.
I-133. 2.49E-06 uCi cc I-134 1.78E-06 uCi cc I- 5
{ 1:!!E:!'."c!/SS TOTAL CHARCOAL SAMPLE 9.69E-06 uCi/cc DEI 131 1.05E-06 uCi/cc TOTAL FILTER SAMPLE As Found Undiluted Gas Sample (15 ml) Dose Rate at 1 ft.: < 2. mR/hr Hydrogen. concentration: .00 Oxygen Concentration: 21.0%
t Airborne Beta Dose Rate: 850. mrad /hr
^
Net Air Sample Count Rate: 3.2E5 cpm / min Air Sample Contact Dose Rate: 25. mrad /hr Floor Contamination: 3300. cpm /100cm2 Wall and Equipment Contamination: 420. cpm /100cm2 Personnel Contamination Rate: 900. cpm /100cm2 per minute
l .!
4 OCNGS -
SCENARIO 22 ANNUAL EXERCISE REV.NO O TALLE ' A-3. L
- REACTOR BLDG ACTIVITY (T = 03:30) (~
)
There is antana3ysis delay of up to 30 minutesLatterfsampl'ing
- Nuclide Concentration Xe-133' 8.33E-04 uCi/cc
.Xe-135 1.52E-02 uci/cc '
TOTAL GAS SAMPLE. 1.60E-02 uC1/cc:
~I-131 1.98E-07 uci/cc I-132 2.03E-07 uCi/cc
I-133 ~
I-134 2.34E-06 uC1/cc-1.38E-06 uCi/cc 3
g I-135- 4,59E-06 uci/cc TOTAL CHARCOAL SAMPLE 8.70E-06 uCi/cc DEI ~131' 9.82E-07 uCi/cc
' TOTAL FILTER SAMPLE As Found Undiluted Gas Samploi(15 ml) Dose Rate at 1 ft. : < 2. mR/hr Hydrogen Concentration: .0%
o Oxygen Concentration: 21.0%- ,
Airborne Beta Dose Rate: 760.4 mrad /hr-Net Air Sample Count' Rates,3.1E5? cpm /mia Air Sample Contact Dose Rate: '22. mrad /hr
' Floor Contamination: 3200. cpm /100cm2 Wall and Equipment Contamination: 410.. cpm /100cm2 Personnel Contamination Rate: 900. cpm /100cm2 per' minute' l g1 I
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! 0CNGS' SCENARIO 22 ANNUAL' EXERCISE REV No O TABLE A-3.51
.bbIb$bbI.kIIbb!!!.((.b$.5.1.'b$......[ .
There is an analysis delay of up to 30 minutes after sampling
.Nuclide Concentration Xe-133 8.01E-06 uci/cc-
'Xe-135 1.43E-02 uCi/cc TOTAL GAS SAMPLE- 1.51E-021uci/cc
,I-131 1.85E-07'uCi/cc I-132- 1.76E-07 uCi/cc I-133 2.17E-06 uCi/cc~
I-134 liO6E-06 uCi/cc:
I-135 4.18E-06-uCi/cc TOTAL' CHARCOAL SAMPLE 7.76E-06 uCi/cc DEI 131 9.07E-07 uci/cc TOTAL FILTER SAMPLE As Found Undiluted Gas Sample (15 ml) Dose Rata at 1 ft.: < 2. mR/hr Hydrogen Concentration: .04-Oxygen Concentration: 21.0%
Airborne Beta Dose-Rate:' 750. mrad /hr Net Air Sample Count Rate: 2.9ES cpm / min-Air Sample Contact Dose Rate: 20. mrad /hr Floor contamination: 3000, cpm /100cm2 Wall and Equipment Contamination: 390. cpm /100cm2 Personnel Contamination Rate: 820. cpm /100cm2 per minute
. , . . . . , . . . . . . , - .1 . . , _ .
r
'OCNGS SCENARIO 22 ANNUAL EXERCISE . REV NO' 0 TABLE A-3.5j 'i REACTOR BLDG ACTIVITY.(T = 04:00)
(. ) !
e There is. an analysis delay of up to 30 minutes after sampling ;
Nuclide
....... .' concentration
'Xe-133 -7.70E-04 uCi cc Xe-135 1.35E-02 uCi cc ~j TOTAL GAS SAMPLE. 1.43E-02'uCi/cc I-131 8.92E-08 uCi/cc -;
?
.I-132 7.85E-08 uCi/cc I-133 1.04E-06 uci/cc I-134 4.20E-07 uCi/cc j I-135 1.96E-06 uCi/cc:
3.58E-06 uCi/cc TOTAL CHARCOAL SAMPLE DEI 131 4.32E-07' uCi/cc TOTAL FILTER SAMPLE As1Found ,
T Undiluted Gas Sample (lli- al) Dose Rate at 1 ft.: < 2. mR/hr Hydrogen concentration: .0%~
Oxygen! Concentration: 21.0%.
Airborne Beta Dose Rate 700. mrad /hr
- Net Air Sample Count Rate:'2.6E5 cpm / min Air Sample Contact Dose' Rate: 18. mrad /hr ,
Floor Contamination: 2700. . cpm /100cm2 7 Wall api Equ pment Contamination .360. cpm /100cm2 ..
Personne Contamination Ratet 750. cpm /100cm2 per minute L~ .
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a OCNGS- ' SCENARIO 22 l ANNUAL EXERCISE '
REV NO O ,
> TABLE A-3.5k i REACTOR-BLDG ACTIVITY (T = 04:15) (
) l There is an analysis delay of up to 30Lminutes after; sampling Nuclide: Concentration
- .t Xe-133 7.41E-04 uCi/cc
Xe-135 1.28E-02 uCi/cc
' TOTAL' GAS SAMPLZ- 13hE02uCi/cc I-131 1.06E-08'uci cc *
'E .I-132" 8.64E-09 uCi cc g I-133 1.22E-08 uCi cc i
I-134 4.09E-08 uC1/cc I-135- 2.27E-07 uCi/cc
- g ...............
g TOTAL CHARCOAL SAMPLE 4.09E-07 uCi/cc DEI'131 2.48E-08 uci/cc ;
............... t TOTAL FILTER SAMPL2 As Found-l Undiluted Gas Sample (15 ml) Dose Rate at l' ft. : < 2. mR/hr j.
Hydrogen concentration:- .0%
l I Oxygen Concentration: 21.0%
Airborne Beta Dose Rate: 640'. mrad /hr l
Net Air Sample C unt' Rate:-'2.2E5 cpm / min Air Samp?a Contact Dose Rate: 15. mrad /hr.
- Floor Contamination.2300. cpm /100cm2 Wall and Equipment Contamination:- 320, cpm /100cm2 l; Personnel Contamination Rate: 640, cpm /100cm2 per minute.
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SCENARIO 22 I! l I
ANNUAL EXERCISE . REV NO O TABLE A-3.51 i REACTOR BLDG ACTIVITY - (T = 04 : 30) 1( ) I i
1 There is'an analysis delay of up to 30 minutes after sampling.
Nuclide Concentration l
Xe-133 '7.12E-04.uci/cc j j Xe-135 1.21E-02-uCi/cc TOTAL GAS SAMPLE ' k27E02ubi/cb I-131 , 1.01E-08 uCi/cc ;
I-132 8.20E-09 uCi/cc I-133 1.16E-08 uCi cc
- I-134 ' 3.89E-08 uCi cc l I-135 2.16E-07 uci cc' .
l TOTAL CHARCOAL SAMPLE 3.89E-07 uCi/cc !
i 1
DEI 131 - 1.84E-08 uCi/cc TOTAL FILTER SAMPLE As Found Undiluted das Sample (15 ml)- Dose Rate at 1 ft. :- < 2. .mR/hr -
-Hydrogen Concentration: . 0% i Oxygen Concentration: 21.0% ;
Airborne Beta Dose Rate: 640. mrad /hr- l; Net Air Sample Count Rate: 2.0E5 cpm / min Air Sample Contact Dose Rate: ;14. mrad /hr- ;
Floor. Contamination:"2100, cpm /100cm2 Wall and Equipment Contamination: 300.. cpm /100cm2 Personnel Contamination Rate: 600, cpm /100cm2'per minute l >
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OCNGS SCENARIO 22 ANNUAL EXERCISE . REV NO O
- TABLE A-3.5m
............................04:45)
. REACTOR BLDG ACTIVITY (T =r
(
-)
(- There is an analysis' delay of up to 30 minutes after sampling L Nuclide Concentration Xe-133 6.85E-04 uCi/cc Xe-135 1.14E-02 uCi/cc TOTAL GAS SAMPLE 1.21E-02 uCi/cc-1-131 9.60E-09 uCi/cc
-I-122 7.79E-09 uCi/cc
'I-133 1.10E-08 uCi/cc I-134 3.70E-08 uC1/cc I-135 2.05E-07 uCi/cc TOTAL CHARCOAL SAMPLE '3.70E-07'uCi/cc DEI 131 1.31E-08 uCi/cc TOTAL FILTER SAMPLE As Found '
Undiluted Gas Sample (1.1 al) Dose Rate at 1 ft.: < 2. mR/hr Hydrogen Ccncentration: .0%
oxygen Concentration: 21.0S Airborne Beta Dose Rate: 600. mrad /hr Net Air Sample Count Rate: 1.8E5 cpm / min Air Sample Contact Dose Rate: 13. mRgd/hr Floor Contamination: 1900. cpm /100cm2 Wall and Equipment Contamination: 230. cpm /100cm2 Personnel Contamination Rate: 550. . cpm /100cm2 per minute ,
.i e -
R OCNGS SCENARIO 22 -'
ANNUAL EXERCISE- REV NO 0-TABLE A-3.5n
.""^ ??" ""."*IL!L:. 5' 21.1........!
There is an analysis delay of up to 30. minutes after sampling Nuclide Concentration !
Xe-133 (.58E-04-.uCi/cc ?
Xe-135 1.vdE-02 uCi/cc
............... - g l l
TOTAL CAS SAMPLE 1.14E-02 uOi/cc g-]
I-131 9.12E-09 uCi cc '
I-132 7.40E-09:uCi cc I-133 1.05E-08 uCi cc R I-134 3.52E-08 uCi cc j I-135 1.95E-07 uCi cc l i
TOTAL CHARCOAL SAMPLE 3.52E-07.uCi/cc g DEI 131 1.24E-08 uCi/cc j
-I TOTAL FILTER SAMPLE As Found Undiluted Gas Sample (15 ml) Dose : Rate at 1 ft. :
Hydrogen Concentration .0%
< 2. mR/hr Ilt .
B Oxygen Concentration: 21.0% g5 Airborne Beta Dose Rate: 560. mrad /hr-Net Air Sample Count Rate: 1.1E5 - cpm /mir Air Sample Contact Dose Rate: 7.8 mrad /ht 3{ ,
Floor Contamination: 1200. cpm /100cm2 Wall and Equ pment Contamination: 200. cpm /100cm2 i Personne Contamination Rate: 350. cpm /100cm2 per' minute I:
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OCNGS SCENARIO 22 E
ANNUAL EXERCISE .
REV No O TABLE A-3.5o REACTOR BLDG ACTIVITY (T = 05t15) ( )
(. ............................................
There is an analysis delay of up to 30 minutes after sampling Nuclide Concentration Xe-133 6.33E-04 uCi/cc t Xe-135 1.02E-02 uC1/cc l ................
TOTAL GAS SAMPLE- 1.08E-02 uCi/cc l I-131 8.66E-09 uCi/cc l I-132 7.03E-09 uci/cc I-133 9.98E-09 uCi/cc~
I-134 3.34E-08 uCi/cc I-135 1.85E-07 uCi/cc TOTAL CHARCOAT.. SAMPLE 3.34E-07 uci/cc DEI 131 1.17E-08 uC1/cc TOTAL FILTER SAMPLE As Found si Undiluted Gas Sample (15 ml) Dose Rate at 1 ft.: < 2. mR/hr Hydrogen Concentration: .0% i Oxygen Concentration: 21.0%
Airborne Beta Dose Rate: 530. mrad /hr Net Air Sample Count Rate: 1.0E5 cpa/ min Air Sample Contact Dose Rate: 7.0 mrad /hr Floor Contamination: 1100. cpm /100cm2 Wall and Equipment Contamination: 200. cpm /100cm2 Personnel Contamination Rate: 350. cpm /100cm2 per minute t i
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OCNES ANNUAL EXERCISE SCENARIO 22
+ .
REV NO O TABL2 A-3.6L y.
....................,..............)..(.......)-
. TURBINE BLDG ACTIVITY (T =.00:00
'There is an analysis Nuclide delay of up to'ho minutes after sampling
[
Concentration-TOTAL GAS' SAMPLE As Found TOTAL CHARCOAL SAMPLE As Found DEI 131 As Found I TOTAL FILTER SAMPLE As Found .
Undiluted Gas Sampl$ . (15 ml) Dose Rate at 1 ft.: < 2. mR/hr Hydrogen Concentration .0%
Oxygen Concentration: 21.0%
i Airborne Beta Dose Rate's- < 2. mrad /hr '
Not Air Sample Count Rate .
< 2. cpm / min run I Floor Contamination:< 100. cpm /100cm2 Wall and Equipment Contamination:< 100 cpm /100cu2 Personnel Contamination' Rate:< 100. Cpm /100cm2 per minute.
I' I
I I
I I
4,
\
)
l I, .
u.
.i
t .
\.
OCNGd ANNUAL EXERCISE SCENARIO 22 ;
i REV NO O s $
TABL2 A-3.6b' E' 1
-.............................................)
TURBINE BLDG ACTIVITY (T = 01:00) ( 5.,
'!}
.. There is'an analysis Nuclide-delay of up to 30 minutes after sampling Concentration .}
+
TOTAL GAS SAMPLE As Found -
...... . ...... I TOTAL CHARCOAL SAMPLE As Found '
DEI 131 As Found '
TOTAL FILTER SAMPLE As Found
{
Undiluted Gan Sample (15 ml)~' Dose Rate at 1 ft.: < 2. mR/hr i
- i Hydrogen Concentration:' .0%
Oxygen Concentration: 21.0% ,
i Airborne Beta Dose Rate: < 2. mrad /hr -
' Net Air Sample Count Rater. < 2. cpm / min *.un Fir;or Contamination:'< 100. cpm /100cm2 I' Wall and Equipment Contamination:< 100, cpm /100cm2 5 '
Personnel Contamination Rate < 100. cpm /100cm2 per minute .
IJ, W
I:
I1 I.
IL I. ,
\.-
e A'.. '. ,
h..
]Q ..s . - - . . - - - - - ~ ' - - ' - - - ' ~ ~ ~ ~ ~
' ~ ~ ~ ~ " ~ ~ ~ ' " ' ~ ~
OCNGS SCENARIO 22 ANNUAL EXERCISE REV No' 0 -
TABLE A-3.6c i
- TURBINE BLDG ACTIVITY.(T = 02
- 00) (
) .
There is an analysis delay of up:to 30 minutes after sampling Nuclide Concentration TOTAL GAS SAMPLZ -An Found ;
TOTAL CHARCOAL' SAMPLE As Found' ;
t DEI 131- As;Found-TOTAL TILTER SAMPLE As'Found Undiluted Gas Sample (15 ml) Dose Rate at 1 ft.: < 2. mR/hr Hydrogen Concentration: . 0% -
Oxygen Concentration: 21.0%
i Airborne Beta Dose Rate < 2. mrad /hr:
[ Net Air Sample Count Rate: <-2.' cpm / min run ,
l 'I Floor Contamination:<'100. cpm /100cm2 Wall and Equ pment Contamination:< 100.. cpm /100cm2 s j Personne Contamination Rate <'100. cpm /100cm2 per minute t 9
l V
W O
J
. , Si , . . - - _. . . . - . . _ ..;....._. . _ . . . . . . , , _ . --
. 1
- 0CNGS SCENARIO 22
\\ !
ANNUAL EXERCISE REV NO O !
-TABLE A-3.6d r
TURBINE BLDG ACTIVITY - (T = 03 : 00) (
.............................................)
1 There is an analysis delay of up to 30 mihutes after sampling Ej
.Nuclide Concentration W ;
TOTAL GAS SAMPLE As Found 1
. TOTAL CHARCOAL SAMPLE As Found .i
-DEI 131 As Found -)
- ............... .5 TOTAL FILTER SAMPL2- As Found .!
Undiluted Gas Sampic (15 ml) Dose Rate at i ft.: < 2. mR/hr Hydrogen Concentration .0% l*
0xygen Concentrationt'21.0%
Airborne Beta Dose Ratet < 2. mrad /hr -
Net Air Sample Count Ratet < 2. cpm / min run '*
Floor-Contaminationt< 100. cpm /100cm2 E.
l Wall and Equipment Contaminatient< 100. cpm /100cm2 15 '
Personnel Contamination Ratet< 100. cpm /100cm2 per' minute 4
i
.i I
l
,=
6 Il ,
4 I:
Il
~ OCNGS ANNUAL. EXERCISE SCENARIO 22
- REV NO O TABLE A-3.6e TUR8IMt T6
........................) ..(........)
G ~ ACTIVITY (T = 04:00 There is an analysis Nuclide delay of up to 30 minutes after sampling
. Concentration a
TOTAL GAS SAMPLE As Found
- TOTAL CHARCOAL SAMPLE As Found DEI 131 As Found TOTAL FILTER SAMPLE As Found Undiluted Gas Sample (15 ml) Dose Rate at i ft.
- < 2. mR/h'r Hydrogen concentration:. .0%
0xygen Concentration:'21.0%
1 Airborne Beta Dose Rate: < 2. mrad /hr Het Air 9 ample Count Rate: < 2. cpm / min run Floor contamination:< 100. cpm /100cm2 1- Wall and Equipment conta.tination:< 100. cpm /100cm2 Personnel Contamination Rate < 100. cpm /100cm2 per minute 1
~
1 l,
r t
_m
- [_,- r'
i 1
't OCNGS SCENARIO 22 ANNUAL EXERCISE REV No 0 '
TABLE A-3.6f ,
TURBINE BLDG ACTIVITY (T = 05:00) ( ) {
J There is an analysis delay of up to 30 minutes after sampling l
-Nuclide Concentration g.i
, ....... ............... 4
! l TOTAL GAS SAMPLF. As~Found TOTAL CHARCOAL SAMPLE As Found DEI 131 As Found l TOTAL FILTER SAMPLE - As Found
{
. Undiluted Gas Sample (15 ml) Dose P. ate at 1 ft.: < 2. mR/hr Hydrogen Concentration: .0%
, oxygen Concentration: 21.0% !
Airborne Beta Dose Rate: < 2. mrad /hr ,
Net Air Sample Count Rate < 2. cpm / min run 't i
Floor Centaminationt< 100. cpm /100cm2 E;
. Wall and Equipment Contamination:< 100. cpm /100cm2 E' i
Personnel Contamination Rate:< 100. cpm /100cm2 per minute t
l I) i.
11 I
I-
.gg IL u
l t'
>l ,
s OCN'S SCENARIO 22
- ANNUAL EXERCISE REV NO O TABLE A-3;7a v
RAGEMS STACK ACTIVITY (T = 00:00) (
)
I There is an analysis delay of up to 30 minutes after sampling L
Nuclide Concentration-Kr-85 1.99E-06 uCi/cc-TOTAL GAS SAMPLE 1.99E-06 uCi/cc
( TOTAL CHARCOAL SAMPLE ksFound DEI 131 As;Found
( ...............
TOTAL' FILTER SAMPLE As Found Undiluted Gas Sample (15 ml) Dose-Rate at 1 ft.: < 2. mR/hr Hydrogen Concentration: .0%
{. Oxygen Concentration: 21.0%
(
l
}
J' e
4
% ~- .
, .. .... - - _ . - . . _ - . . - - . . .- - - . - - . . . . . . - - - - - . - - . ~
1, OCN2S SCENARIO 22 ANNUAL EXERClISE REV No 0
' TABLE A-3.7b l RAGEMS STACK ACTIVITY (T.= 00:15) (
)
There is an analysis delay of up to 30 minutes after sampling i
.Nuclide- Concentration l
Kr-85 1.99E-06 uCi/cc
............... Ii ;
TOTAL GAS SAMPLE 1.99E-06.uci/cc i l
=j TOTAL CHARCOAL SAMPLE As Found 1
DEI 131 As Found 4
TOTAL FILTER SAMPLE As Found ,
l
' Undiluted Gas Sample (15 ml) Dose Rate at 1 ft.: < 2. mR/hr i a
' Hydrogen concentration:
Oxygen Concentration: 21.0%
.0%
I1) 1 I
i
.]
1 ~\
H l
-1 I
I L
1 1-. .
l 1
I; 1
OCNGS SCENARIO 22 ANNUAL EXERCISE REV NO O TABLE A-3.7c RAGEMS STACK ACTIVITY (T = 00:30) (
)
There is an analysis delay of up to 30 minutes after sampling
- Nuclide Concentration g .....__ ... ___________
Kr-85 1.99E-06 uCi/cc
-=
=
- TOTAL GAS SAMPLE 1.99E-06 uCi/cc TOTAL CHARCOAL SAMPLE As Found DEI 131 As Found TOTAL FILTER SAMPLE As Found J l Undiluted Gas Sample (15 ml) Dose Rate at 1 ft.
- < 2. mR/hr l Hydrogen Concentration Oxygen Concentration: 27. 0%
.0% __
l i
I I
l =
I -
~
I l s 1 ..
I
1 l
OCNGS SCENARIO 22 Ii i ANNUAL EXERCISE .
REV NO O I TABLE A-3.7d j RAGEMS: STACK ACTIVITY (T = 00:45) (.
) lj g1 -
There is an analysis delay of up to 30 minutes after sampling Nuclide Concentration l-u
....... ............... 1 i
- Kr-85 1.99E-06 uCi/cc
$-l p 1 TOTAL GAS SAMPLE 1.99E-06 uCi/cc {
TOTAL CHARCOAL SAMPLE As Found i DEI 131 As Found- :
TOTAL FILTER SAMPLE As Found Undiluted Gas Sample . (15 ml) . Dose Rate at 1 ft. : < 2. mR/hr I]4 Hydrogan' Concentration: . 0% E Oxygen Concentrations.21.0% 3
! i l ?
i t i
I ,(
)
i i l
i i -
t 4
't f
I
?
. . 'i
..,.- . . . --. . . , - , - ..--...-n. ..,,,-r
, , , ,, ,n. - , . . ,, ,,,,.n.,-a-,-, ,----,,,---,a ..n. ,, ~ , - . . . , ,
s .
OCN2S . SCENARIO 22 U ANNUAL EXERCISE REV NO. O TABLE'A-3.7e
- y. RAGEMS STACK ACTIVITY (T =-01:00) (
......................__.......__........s...
.- )
l t.
-There is an a.1alysis delay of up to 30 minutes after sampling Nuclide Concentration
(: ....... -_.....___......
Kr-85 -1.99E-06 uCi/cc
( TOTAL GAS SAMPLE k99E-06uCi/cc TOTAL ~ CHARCOAL SAMPLE .As Found DEI 131 lAs Found TOTAL FILTER SAMPLE As Found Undiluted Gas Sample (15 ml) Dose Rate at 1 ft.: < 2. mR/hr Hydrogen Concentration: .0%
Oxygen Concentration: 21.0%
~
)/
OCNGS SCENARIO 22 ANNUAL EXERCISE REV NO- 0
. TABLE A-3.7f.
RAGEMS STACK ACTIVITY (T = 01:15) (
)
There is in analysis delay of up.to 30 minutes after sampling Nuclide.
Concentration TOTAL GAS SAMPLE As Found TOTAL CHARCOAL SAMPLE As Found 1
DEI 131 As Found:
TOTAL FILTER SAMPLE As Found Undiluted Gas Sample (15 ml).. Dose-Rate at 1 ft.:
<~2. mR/hr .
Hydrogen Concentration: .0%
Oxygen Concentration: 21.0%
I I
I I
I I-1 l
i 11 I
OCNGS SCENARIO 22 ANNUAL EXERCISE REV NO O TABLE A-3.79 RAGEMS STACK ACTIVITY (T = 01:30) (
)
~
There is an analysis delay of up to 30 minutes after sampling Nuclide Concentration TOTAL GAS SAMPLE As Found TOTAL CHARCOAL SAMPLE AsFounb DEI 131 As Found I TOTAL FILTER SAMPLE As Found Undiluted Gas Sample (15 ml) Dose Rate at 1 ft.: < 2. mR/hr Hydrogen Concentration: .0%
Oxygen conenntration: 21.0%
i 1
I i
l I
I I
3
OCNGS SCENARIO 22 I
- ' ANNUAL EXERCISE REV NO O e-TABLE A-3.7h g' RAGEMS STACK ACTIVITY.(T =:01:45) (
)
-There.is an analysis: delay of-up to 30 minutes after sampling Nuclide Concentration TOTAL GAS SAMPLE As Found-TOTAL CHARCOAL SAMPLE As Found DEI 131 As Found TOTAL FILTER SAMPLE- As Found Undiluted Gas Sample (15 ml) Dose Rate at i ft.: '< 2..mR/hr Hydrogen Concentration: .0%
Oxygen Concentration:,21.0% .
I-I.
I I;
I I
I I
IR,
OCNGS SCENARIO 22 l ANNUAL EXERCISE REV NO O TABLE A-3.71 RAGEMS STACK ACTIVITY (T = 02:00) (
)
There is an analysis delay of up to 30 minutes after sampling Nuclide Concentration TOTAL GAS SAMPLE As Found TOTAL CHARCOAL SAMPLE As Found DEI 131 As Found TOTAL FILTER SAMPLE As Found Undiluted Gas Sample (15 ml) Dose Rate at 1 ft.: < 2. mR/hr Hydrogen Concentration: .0%
oxygen Concentration: 21.0%
_ , - - - . . _ _ , , , . _ _ _ _ _ _ - _ - _ - - - - - ~ - - . - - - - ~ - - - - . . -
~
OCNGS SCENARIO 22 I
ANNUAL EXERCISE .
'REV NO O TABLE A-3.7j RAGEMS STACK ACTIVITY (T = 02:15) (.
)
There is an analysis delay of up to 30 minutes after sampling Nuclide- Concentration
, TOTAL GAS SAMPL2 As Found TOTAL CHARCOAL' SAMPLE As Found DEI 131' As Found TOTAL FILTER SAMPLE As Found Undiluted Gas Sample-(15 ml) Dose-Rate at 1 ft.: < 2.'mR/hr Hydrogen. Concentration: .0%
Oxygen' Concentration: 21.0%
I-1 M
I I
A 3;
m
- Q ;[ ,
ty, OCNGS" . SCENARIO 22 ANNUAL EXERCISE .
. R E V - N O -- 0
. TABLE A-3.7k RAGEMS STACK ACTIVITY;(TC= 02:30): ( :)
There is an analysis delay of up.to 30 minutes,after sampling:
Nuclide Concentration ~
.__.t.___ .__._.......___
TOTAL GAC SAMPLE As-Found :I TOTAL CHARCOAL SAMPLE As Found DEI 11!' -As Found?
a TOTAL FILTER' SAMPLE- As'Found-Undiluted Gas Sample (15 ml)fDose Rate at 1.ft.:.- .<'2.
mR/hr.-
Hydrogen Concentration: . 0%
Oxygen Concentration: 21.0%'
f 4
-t
- h q
- i
.d !
.. j
'1 i
l i
l
'I i,l
^
+
if (
, t m
- ', w - -; i OCNGS.~ . . ' SCENARIO.22-
' ANNUAL EXERCISE" REV.-NO 0- -
TABLE A-3.71
^
RAGEMS STACK ACTIVITY 1(T =-02:45)___.( _____ )'
~ -
u ________..________ ........__ ... ;
t There.isjan.' analysis; delay of up(tO 30 minutes after sampling; '
- J Nuclide.. .i
' .' concentration-
. .. . .. .._. . . ...s g' 4
-Xe-133 1.'84E-O'5 uC1/cc e
, =Xe-135. 3 54E-04=uCi/cc f g
- i. ! TOTAL GAS SAMPLE ~ ' 3'.72E-04 uCi/cc : s
, , li II-131.. 5.20E-10 uCi/cc- j
.I-132~ :6.66E-10 luc 1/cc- ..' .:
I-133 6.28E-09'uCi cc. :r
- I-134 16.54E-09-uci ec ,
.j I-135 1 30E-08
. ._____.__..n.
2 uCi/cc ,
n
. TOTAL CHARCOAL SAMPLE < 2J70D 08'uCi/cc) o .
~ '
- . .. (
i . DEI 131'
- 2.67E-09 uC1/cc' g?.
TOTAL FILTER! SAMPLE As Found -W' Unailuted Gas Sample-(15 ml) ~ Dor;e Rate 'a.ti l- f t. : '- < 2'.imR/hr -
L Hydrogen Concentration: :.0%> '
9 l- Oxygen concentration: 21.0%- .
- t. .
- (
k I
,I f 'I i
5 t
r -'-
u -
I :
[
~ .
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_ OCNGS SCENARIO 22 ANNUAL EXERCISE REV NO O TABLE A-3.7m RAGEMS STACK ACTIVITY (T = 03:00) (
)
There is an analysis delay of up to 30 minutes after sampling
, Nuclide Concentration
= ....... --_-------_ ---
%e-130 1.71E-05 uCi/cc t Xo-135 3.21E-
.... _04 uCi/cc
- TOTAL GAS SAMPLE 3.38E-04 uCi/cc R
I-131 4.252-10 uCi/cc I-132 5.03E-10 uCi/cc I-133 5.09E-09 uCi/cc
- I-134 4.39E-09 uCi/cc
!! I-13S 1.03E-08 uCi/cc
? TOTAL O R .;OAL SAMPLE 2.07E-08 uCi/cc DEI 131 2.15E-09 uCi/cc Cs-137 1.02E-08 uCi/cc
_____.--__m 7 TOTAL FILTER SAMPLE 1.05E-08 uCi/cc N-kh Undiluted Gas Sample (15 ml) Dose Rate at 1 ft.: < 2. mR/hr Y
- " Hydrogon Concentration: .0%
Pe Oxygen Concentration: 21.0%
m E-
=
==
Me W
=_
E 1
~ '
)
& .q- ,
i;'
-- OCNGS: . SCENARIO 22 ANNUAL EXERCISE 2 ' REV'NO O TABLE'A-3.7n- E RAGEMS STACK ACTIVITYn(T = 03:15) ( _ _ )! ,5 There is-an analysis-delay of.up to.30 minutes after sampling 1 Eq Nuclide ' concentration- .B '
Xe-133 --1. 64E-05 uCi/cc -- -
Xe-135 -3.03E-04iuCi/cc1 4 TOTAL GAS SAMPLEL'3.19E-04 uCi/cc-
--i L
=3.97E-10.uci/cc-
-I-131-I-132. '4.37E-10/uci/cc; . . .
I-133: 4.71E-09 uCi/cc- 3.,
I-134 3.37E-09 uCi/cc - gi '
!I-135 9.42E-09 uCi/cc TOTAL CHARCOAL SAMPLE - 1.83E-08 uci/cc
. DEI 131 1.99E-09-uCi/cc.
Cs-137 'O.74E-09 uCi/cc. -
' TOTAL- FILTER 'S AMPLE: 1.00E-08 uCi/cc-0
-Undiluted Gas Sample (15 al)J Dose Rate at 1 ft. : '< 2.-lmR/hr; Hydrogen; Concentration:- -.0%
Oxygen-Concentration:121.0%- p 4
\'
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> d
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t ,
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,p" f.,
OCNGS- L
, ' SCENARIO 22 ANNUALLEXERCISE. ,, - REV NO 0:
B TABLE A-3.7o .
RAGEMS STACK ACTIVITY (T;=-03
. . _ _ _ _ _ _ . . _ _ . . . .. _ _ _ . _ . . . . . _ _ _1 3 0 ) - ( )
.There.is.an' analysis-delayiof upito 30 minutes >after sampling Nuclide Concentration
=Xe-133: 1.58E-05'uCi cc-Xe-13 5 --
7
".2.87E-04-uCi
________...... - cc-
. TOTAL GAS SAMPLE ?3.03E-04fuci/cc
'I-131' '3.74E-10 uCi/cc I-132 3.84E-10'uCi/cc--
I-133- 4.42E-091uci/cc I-134' 2-.61E-09 uci/cc I-135 8.683-09 uCi/cc TOTAL CHARCOAL SAMPLE' --1.65E-08 uCi/cc DEI 131'.1.86E-09 uCi/cc Cs-137 9.29E-09 uCi/cc '
TOTAL FILTER SAMPLE- 9.54E-09 uci/ccs .
Undiluted Gas Sample . (15 ml); Dose Rate atl lift. : < 2.'mR/hr-Hydrogen' Concentration: .0%~
Oxygen Concentration: 21.0%
.q i
i
- i
~
.i-1 m
, m -
i -- .,
L OCNGS.. SCENARIO 22: '!
I :- . ANNUAL. EXERCISE REV NO- O' a.
L* TABLE.A-3.7p
.g.'
..RAGEMS. STACK: ACTIVITY;(T =-03:45) ( ).
There2is an; analysis' delay'of-up;to 30 minutes after sampling-- -
~ '
Nuclide -Concentration t.~ '
L Xe-133 1.51E-05:uci/cc I Xe-135 2.70E-04
_________uCi/cc=
TOTAL GAS SAMPLE 2.86E-04 uCi/cc . i
,. I-131 ~3450E-10 uCi/cc.
- I-132 '3.33E-10 uCi/cc
- l;m. '
! 1 l- .I-133: '4.10E-09 uCi/cc H -I-134 2.00E-09:uci/cc '!
I-135' 7.90E-09 uCi/cc o;
, TOTAL CHARCOAL SAMPLE :1.47E-08 uCi/cc. -
l DEI 131' 1.72E-09 uCi/cc, i Cs-13*/ A 8.85E-09?uCi/cc TOTAL FILTER SAMPLE- 9.09E-09~uCi/cc-f . Undiluted ' Gas Samploi (15' ml) Dose Rate -at 1 - f t. : 1<: 2.<mR/hr~ '
t Hydrogen Concentration: .0% E; Oxygen: Concentration: 21.0%. _g;
'[
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o
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u OCNGS -
. SCENARIO 22 ANNUAL EXERCISE- - -
REV NO-
~
0 ABLE ' A-3 ~. 7 q -
RAGEMS STe - .rIVITY;(T-=.04:00) (
)
L There-is an~analysisLdelay of up-to.-30 minutes-after sampling -!
Nuclide Concentration __
r Xe-133- 1.46E-05 uci/cc:
f Xe-135- 2.55E-04 uCi/cc
[ -
. TOTAL GAS SAMPLE 2.70E-04 uCi/cc
[ :- . I-131' 1.69E-10 uCi/cc: 'j
(- ~ . I-13 2 : 1.48E-10.uCi/cc '
I-133- 1.97E-09 uCi/cc I-134' 7.94E-10 uCi/cc:
'I-135 3.71E-09 uCi/cc-
!(.1
... y)
' TOTAL CHARCOAL SAMPLE- 6.78E-09 uCi/ccL .1
- 1 DEI 131 8;21E-10 uCi/cc !
c >
Cs-137 8.49E-09 uCi/cc 1
TOTAL FILTER SAMPLEL 8.72E-09-uCi/cc Undiluted Gas Sample (15 ml): Dose' Rate lat'l ft.: -
<:2. mR/hr !
Hydrogen : Concentration:: -.0%'
Oxygen Concentration:121.0%.
4
.t
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f I
.4
}
t
, i c._1
'~ 4 4 ._ g
^'
- OCNGS: ' '
SCENARIO 22 ~. -
, A ANNUAL' EXERCISE REV NO 0-' -
TABLE.A-3.7r- .
RAGEMS STACK ACTIVITY-(T1= 04:15) (' -)'
There'is an analysis delay'of up-to 30 minutesuafter sampling: o l -
(. Nuclide l Concentration.
l l-Xe-133- - 1.' 4 0E-05-.' uCi/cc ,
l Xe-135 2.42E-04 =1
_____ ___uci/cc 1 _____
TOTAL GAS: SAMPLE - 2.56E-04;uCi/cc- .
~
~ '
'I-131. -2.02E-11 uCi/cc--
I-132 1.63E-111uCi/cc I-133 2.'31E-11 uCi cc' --
-I-134, . 7.73E-11 uCi cci '
4.29E-10LuCi/cc I-135' TOTAL' CHARCOAL' SAMPLE'- 5.66E-10..uCi/cc/
. - -3
~
' DEI-131; 4.71E-11;uci/cc- = -!
Cs-137 8.26E-09fuCi/cc TOTAL FILTER ~ SAMPLE 8. 4 8 E-09 , uCi/cc
- Undiluted Gas Sample (15:al) Dose-Rat'a'at 1 ft.: < 2. mR/hr -
, Hydrogen Concentration:' .0%' __,
L . - Oxygen Concentration: 221.0%- -
l I
4 I
5 > r i i 7
~.6 m .
1 .
. \
- i. 1 d i.
- .I
~
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,. g . /),t
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._l-_
- _ . - - . . . . . .. . . . . . . . - - - - . L.- r A . , -
>'A ~
OCNGS SCENARIO 22 ANNUAL EXERCISE- -
REV-No- 0:
T TABLE A-3.7s-RAGEMS STACK ACTIVITY (T -04:30): (
______. ...__________....___=_______.......__.. ) _
LThereiis an analysis delay lof up to 30 minutes.after sampling-r-
Nuclide Concentration L
Xe-133- -1.35E-05 uCi/cc-
{(;. =
Xe-135 2.29E-04-uci/cc TOTAL GAS-SAMPLE 2.46E-04:uci/cc-
{'
-I-131 1. 91E-11" uci/cc: '
I-132 1.55E-11 uCi/cc- *
.I-133 -2.19E-11 uCi/cc I-1341 7. 3 6E-11: uci/cc l I-135= 4.08E-10zuci/cc TOTAL CHARCOALA S'MPLE' '5.39E-10 uCi/cc
' DEI 131'. 4.46E-11 W,Ci/cc Cs-137
.8.12E-09 uCi/cc I TOTAL' FILTER SAMPLE -8.33E-09 uci/cc Undiluted Gas Sample (15;ml).-Dose Rate =at 1 ft.:. '<;-2 'mR/hr* j
\ Hydrogen? Conc.sntrations- . iO %
Oxygen ~ Concentration:121.0%
1
,2 ll 1
a i
1 i
- t. l 1
k i
t t x <
g l oCNGS. SCENARIO 22 )
. ANNUAL > EXERCISE REV NO O "
TABLE-A-3.7t :. ];
RAGEMS: STACK ACTIVITY (T- .-_.._---------...
- s. ,- -,
--..-_-- .....---.__..... = 04:45) ( )
)
- .There is an analysis delay of up;to3 30 minutas aftercsampling ,
Nuclide . Concentration !
4 ..
Xe-133- 'i.30E-05.uCi/cc j.
Xe-135 2.16E-04 uCi/cc TOTAL GAS-SAMPLE 2.29E-04 uCi/cc -
l I-131- - 1. 82E -1'1 uCi/cc i I-132 1.47E-11 uci/cc I-133 2.08L-11 uCi/cc, > .1 I-134 7.00E-11 uCi/cc- j!
I-135- : 3.881;-10 -uCi/cc 2 TOTAL CHARCOAL' SAMPLE e5'.11E-10 uCi/cc -
-7
. DEI.131 4.24E-11-uCi/cc. . .
j Cs-137 8.04E-09-uCi/c0
-._____ ._____ .E k*
xTOTAL FILTER SAMPLE .- 8. 2 6E-09 ' uCi/cc .
Undiluted- Gas Sample (15 ml), Dose .' Rate'/at 'l- f t. : - -< 2.2mR/hr.
i-
,HydrogeniConcentration:.
Oxygen Concentration:c21.0%~
.0% E1
.E i[ >
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OCNGS. LSCENARIO 22 ANNUAL EXERCISE .
REV No 01 TABLE A-3.7u r1 g l RAGEMS STACK . ACTIVITY ' (T = 05:00) '( )!
x.
There is an analysis delay of up'to 30-minutes after! sampling.
~
E ;Nuclide Concentration ,
{i-i . ......_______
l9 Xe-133' 1.24E-05'uC1/cci ,
Xe-135' 2.04E-04:uci/cc I TOTAL GAS S7MPLE. 2.17E-04.uci/cc:
- I-131'
- l'.72E-11' uC1/cci LI-132 1.40E-11/uci/cc "
1.
I-1331 1.99E-11'uCi/cc)
'I-134 6.66E-11 uCi/cc I-135 '3.69E-10 uCi/cct s
I -TOTAL CHARCOAL SAMPLE '4.86E-10 uCi/ccf j DEI 131' 4.n?E-11:uci/cc
~
-lb ~.'_U !SS
. TOTAL FILTER SAMPLE 8.23E-09 uCi/cc I ' Undiluted Gas 1 Sample ' (15 ml) - Dose Rate at -1 f t. : < 2.'mR/hr! q t
I 1 Hydrogen Concentration:L .0%
Oxygen Concentration:,21.0%
1 1 1
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-1 L OCNGS ~- - SCENARIO 22 ;
L : ANNUAL EXERCIt., , REV NO. 0 l TABLE A-3.7v .
W
')
RAGEMS ' STACK. ACTIVITY- (T = : 05:15) L ( -
\~ . .
! There [is l an. analysis' dalay 'of up : to. minutes af ter samplingL
-e Nuclide -Concentration L ,l
.___ ___ . _____________ ;\
I.
l.
lr .
l .Xe-133 1.20E-05:uci/cc ,
Q l
I
-Xe-135-, 1.93E-04 uci/cc c
l; <
. TOTAL GAL. SAMPLE. 2.05E-04.uCi/cc;
/g l
DI-131 1.64E-11 uCi/cc .
. t f 1.33E-11 uCi/cc.
)
- I-132 ,
I-133 -1.89E-11?uCi cc ,
I-I.3 4 ' . 6.32E-11 uci cc- % i<
p I-135~ -
3;50E-10Luci/cc.
l' TOTAL-CHARCOAL SAMPLE '*. 62E-10 uCi/cc. '
l DEI 131-' 3.83E-11 uCi/bc.
e
-Cs.137: 8.01E-09 uC1/cc
- < TOTAL-. FILTER SAMPLE -- 8 '. 2 3 E-09
- uCi/cc ?
Undiluted Gas:SampleJ(15 al) Dose Rate'at l'ft.: -
<2.4 mR/hr'
~-
q ~
! . Hydrogen. Concentration: . . 0% -
Oxygen-. concentration:'21.0%-
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SCENARIO-22=
'K < . _
ANNUAL EXERCISE:- i REV NO Ci
~N- TABLE A-3.8a
.N.
'. s
,e REFUEL FLOOR ACTIVITY (T> - 00:00): ( \'
-)?
a
.:.- s y s
There~is an7 analysis dehyl.of up to~30 minutes after. sampling.
Nuclide ' Concentration d 4, N
l' TOTAL GAS SAMPLE' As Found'qa ,
4 TOTAL CHARCOAL SAMPLE, As Found
> .i
- DEI 131; As Found . -
i -s x . .
TOTAL FILTER SAMPLE- As.Found' v
i '
Undiluted -Gas Sample > (15 al)x Dose Rate at 11- ft. : <-2.-mR/hr h -Hydrogen Co.hcentration:: .0%'
g oxygon Concentration: 21.Og '
i Airborne-Beta Dose' Rate:- !<-2.: mrad /hr' -
Net Air: Sample Count: Rate:
, < 2 . ,- cpm / min i j Air Sample Contact Dose Rate: -0.2 mrad /hr- s Floor Contamination:<:100. cpm /100cm2 -'
Wall and Equipment Contamination:< 100.c pm/100cm2 c *
' Personnel-Contamination Rate:< 100.' cpm /100cm2 per. minute'-
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OCNGS . . .
' % 0 1
'SCENAR.TO 22 -
l3 ANN %4 EXERCISE- REV NO- 0 '
TABLE A-3.8b- i lg.'E]!
LN
' REFUEL' FLOOR ACTIVITY _.L(T = 01: 00)- (;
-- ----- --------------.... ....- J --- -----
).
'There t is'anLanalysis delay;;of up.to 30' minutes:after, sampling V N!tclide Concentration i' Ed 1
x - Ej 1
-- -- . ---- ..------- o ;
s -s .
a- .
4 , . >
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NTOTAL. GAS SAMPLE;- As - Fcntnd - > 4 .;
1 6
- --.: . . --_ 1 -
[_ '
- t. ' TOTAL CHARCOAL SAMPLE - As~Found. i l
e
( -DEI 131'- As Found' &
s
' x:.
1 t
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' TOTAL' FILTER ~ SAMPLE As.Found' i .
$it h \ D .. .
a s
Undiluted Gas Sample (15-ml) Dose' Rate.at'l - -
s.. u.
ft.:-t< 2' . mh/hr 3
. Hydrogen Concentration: 5 0%' ;
Oxygen Concentration: 21.0%
6 3 ,
s
[( 3 .
Airborne Beta ~ Dose' Rate:' <y2.> mrad /hr 5(
y Net Air Sample C6unt Rate: L < 2. . cpm / min'. q Air Sample (Contact Lose Rate:-'<-012 mrad /hr 1 1
- 1. . . >
Floor Contaminationi< 100s. cpm /100cm2..
~
-s ;-
Wall and Equipment Contamination.:< 100.icpm/100cm2 .
Personnel Contamination'Ratos<'100.: cpm /100cm2.per minute.le
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OCNGS .ENARIO 22 ANNUAL EXERCISE I.EV NO O TABLE A-3.8c REFUEL FLOOR ACTIVITY (T = 02:00) (
)
There is an analysis delay of up to 30 minutes after sampling Nuclide concentration TOTAL GAS SAPPLE As Found TOTAL CHARCOAL SAMPLE As Found DEI 131 As Found TOTAL FILTER SAMPLE As Found Undfluted Gas Samplo (15 ml) Dose Rate at 1 ft.: < 2. :nR/hr Hydrogen Concentration: .0%
Oxygen Concentration: 21.0%
Airborne Beta Dose Rate: <. 2 . mrad /hr Het Air Sample Count Rate: < 2. cpm / min Air Sample Contact Dose Rate: < 0.2 RRad/hr Floor Contamination:< 100. cpm /100cm2 Wall and Equipment Contamination:< 100. cpm /100cm2 Pertsonnel Contamination Rate: < 100. cpm /100cm2 per minute I
i i
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OCNGS'. SCENARIO 28 ANNUAL EXERCISE REV NO ' 0'
. TABLE A-3.8d i^ REFUEL FIDOR-' ACTIVITY (T = 02:30) (. ); t There'.is an analysis delay of;up to 30 minutes after. sampling- -
Nuclide Concentratior >
TOTAL GAS SAntPLE. .As Found' ,
TOTAL CHARCOAL SAMPLE .As.Found ...
,I DEI.131 As Found
.i o
TOTAL FILTER' SAMPLE -As Found E!
L Undi'.uted' Gas . Sample (15 'al) 'Dese : Rate. at 1. f t. : <!2 1mR/hr?. l Hydrogan' Concentration: .0%
Oxygen Concentration: 21.0%
{
- Airborne B(ta: Dose Rate:. ' < 2.-~ mrad /hr Net Air Sample Count Rate:, < 2L cpm / min-Air Sample Contact Dose Rate:L<-0.3 mrad /hr
~ Floor Contamination:< 100. cpm /100cm2 1
Wall and Equ puent Contamination:< 100' cpm .- /100cm2-- .
Wt e Personne Contamination Rate:<-.100.-cpm /100cm2.per-minute'. :
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OCNGS SCENARIO 22 ANNUAL EXERCISE REV NO O TABLE A-3.8e
- r. a )
_____ .. . _. AC'*TVITY (T___
___________ = 02:45)
_ _____ (
There is an analysis delay of up to 30 minutes after sampling Nuclide Concentration Xe-133 9.74E-0* uCi/cc Xe-135 1.87E-00 uCi/cc TOTAL GAS SAMPLT; 1.96E-05 uCi/cc I-131 2.75E40 uCi/cc I-132 3.52E-10 uCi/cc I I-133 I 134 3.32E-09 uCi/cc 3.46E-09 uCi/cc I-135 6.86E-09 uCi/cc TOTAL CHARCOAL SAMPLE 1.43E-08 uCi/cc DEI 131 1.41E-09 uCi/cc TOTAL FILTER SAMPLE As Found Undiluted Gas Sample (15 ml) Dose Rate at 1 ft.: < 2. mR/hr Hydrogen Concentration: .0%
Oxygen Cor' centration: 21.0%
Air'ocene Beta Dose Rate: 3. mrad /hr Net Air Sample Count Rate: 1300. cpm / min Air Sample Contact Taose i. ate: ( 2. mrad /hr Floor Contramination: 310. cpm /iO0cm2 Wall and Equipment Contamination:< (00. cpm /100cm2 Persennel Contamination Rat.e: 150. cpm /100cm2 per minute l .
3 1
1 l
t h b EEEEEEERMERE17 n <nE.* v **6~1BaK
. . _ . _ _ . _ . __ . . _ _ . . _ _ _ _ __ .~ . - _ _ _ _ . _ _ _ _ _ _ _ _ - - _ - _ _ _ __
n.
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! n.: 1OCNGS'
-SCENARIO 22 ANNUAL' EXERCISE- REV NO' '
! , . TABLE : A-3. 8 f : .
REFUEL FICOR ACTIVITY (T = __.. ......__ (=
___......__.._______________-03:00) __
) '!
q
. 1 There is.an-analysis l delay of up.to 30 minutes'after sampling; ;
L#"'
- -Nuclide~
Concentration , ,
__...__ -__.____.__.___: 1
- S, c1
.Xe-13 31 2,26E-04LuCi/cc: gI gI f/
' Xe-135 4.25E-03 !
c __. _____'uci/cc ...___
J
- TOTAL GAS- SAMPLE -
- 4. 4 BE-03 : uCi/cc- ,
.I-131 - 5~. 63E dCi/cc
// I-132 6. 65E-08..'uC1/cc .
-6.73E-07,uCi/cc
-/ I-133 S I-134. ~S.80E-07 uCi/cc' ,
___.."05 uCi/cc
<~
7
-I-135 1.35E ,
TOTAL' CHARCOAL'SAMPL3 2.173E-07iuCi/cc q i DEI 331' 2.85E-07<uCi/cc TOTAL FILTER. SAMPLE. As Found ,( f l :i ~
' Undiluted Gas Sample-(15 ml). Dose N te at 11ft.:! -<-2. mR/hr Hydrogen - Concentrr.tionb .0%-
!" Oxygen Concantratiom 21.0%
's i' Airborne Esta'Dosa. Rate:;'300. mrad /hr- ,
' Net Air Sample' Count Rate: 11.1E5 cpm / min *
[ / Air Sample Contact. Dose Rate: 8.6 mrad /hr-- --
. Floor Contamination: 1100. cpm /100cm2 4 Wall.and Equipment Contamination: 1106 cpm /100cm2
, Personnel.Centamination Rate:. 220.tcpm/100cm2 per minute j.,
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yl,;Q OCNGS SCENARIO 22 ANNUAL EXERCISE REV NO O TABLE A-3. 8g REFUEL FLOOR ACTIVITY (T = 03:15) (
)
There is an analysis delay of up to 30 minutes after sampling Nuclide Concentration Xe-133 4.33E-04 uCi/cc Xe-135 8.00E-02 uCi/cc TOTAL GAS SAMPLE 8.43E-02 uCi/cc I-131 1.05E-07 uCi/cc I-132 1.15E-07 uCi/cc I-133 1.25E-06 uci/cc I-134 8.58E-07 uCi/cc I-135 2.49E-06 uCi/cc TOTAL CHARCOAL SAMPLE 4.84E-06 uCi/cc DEI 131 5.25E-07 uCi/cc TOTAL FILTER SAMPLE As Found Undiluted Gas Sample (15 ml) Dose Rate at 1 ft.: < 2. mR/hr Hydrogen Concentration: .0%
Oxygen Concentration: 21.0%
Airborne Beta Dose Rate: 450. mrad /hr Net Air Sample Count Rate: 1.6E5 cpe/ min Air Sample Contact Dose Rate: 12.5 mRac'hr Floor Contamination: 1900. cpm /100cm2 Wall and Equipment Contamination: 275. cpm /100cm2 Personnel Contamination Rate: 650. cpm /100cm2 per minute
OCNGS-. . SCENARIO 2. y ANNUAL EXERCISE REV NO O l TABLE A-3.8h H REFUEL . FLOOR ACTIVITY (T = 03:30) (
)
There is an analysis delay.of up.to 30 minutes after sampling Nuclide- Concentration '
.Xe-133- 8.33E-04 uCi/cc Xe-135 1.52E-02~uCi/cc-TOTAL. GAS SAMPLE .1.60E-02 uci/cc l
'I-131' 31.98E-07 uci cc t
-I-132 2.03E-071uCi cc I-133' 2.34E-06 uCi cc I-134 1.38E-06;uCi cc' -
1 LI-135 ,'4.59E-06 uCi/cc TOTAL CHARCOAL SAMPLE' 8.70E-O'6 uCi/cc.
DEIz l31 9.82E-07.uci/cc
____--____----. i 70T\L1 FILTER SAMPLE As Found "-
Undiluted Gas <Samplet(15 ml)' Dose Rate at 1Lft.: ~< 2 . mR/hr ,
. Hydrogen Concentration: .0%- ..
p Oxygen Concentration:'21.0%- '
t Airborne Beta Dose Rate: 760. mrad /hr !
Net Air Sample Count Rate: 3.1E5 cpm / min ;
Air Sample Contact Dose Rate: 22.fmRad/hr 1 4 <>
l Floor Contamination: 3200. cpm /100cm2 Wall and' Equipment Contamination: 410.: cpm /100cm2 ,
Personnel Contamination Rate: 900. cpm /100cm2 per minute .
4 4
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OCNGS'.' .
SCENARIO 22-ANNUAL EXERCISE! -
REV NO O TABLE:A-3.81
. . . . . . _ _(T_ =. .03:45)-
. . . . . . (. . _ _ _ . ).' _ . . _ _ _ _'
REFUEL
.___ .._' FLOOR_ _ . . .ACTIVITY There is anLanalysis~ delay of up to'30'ainutes after sampling Nuclide Concentration Xe-133 8.01E-04,uci/cc Xe-135 :1.43E-02
.........'uCi/cc= ......-
TOTAL GAS SAMPLE 1.51E-02:uci/cc I-131- 1.65E-07 uCi/cc-
~.
I-132- '1.76E-07 uCi/cc:
'I-133 2.17E-06 uci/cc .
I-134 1.06E-06;uci/cc-I-135 4.18E-06'uci/cc; TOTAL CHARC0AL SAMPLE- 7 76E 06 uCi/cc.
s s
' DEI 131 9.07E-07;uci/cc !
-TOTAL FILTER' SAMPLE As-Found: -i i
, Undiluted Gas ' Sample (15 ml)- Dose Rate' at 1D ft. : =<L2.'mR/hr, Hydrogen Concentration: .0%:
Oxygen Concentration: 21.0% }.
Airborne Beta' Dose Rate:' 750. mrad /hr-.
,1 Net Air Sample Count-Rate: 2.9E5: cpm / min 1 Air Sample Contact' Dose Rate: 20.' mrad /hr
,i
. Floor Contamination: 3000.: cpm /100cm2 1
- g. Wall and Equipment Contamination: -390.. cpm /100cm2 -: j
- g. Personnel Contamination Rate
- :820. cpm /100cm2:per minute [!
- Hj t
'l ll;
. ._ _ __ _ _ . . _ . , _ ._- ---___~--- - - = - _ -
,^ s i
9 -; - :t
~'
'OCNGS ' SCENARIO 22: l
<. . ANNUAL l EXERCISE , REV NO 'O = 'l TABLE A-3.8j, . . . -1 q ,
REFUEL FIh0R- ACTIVITY t(T.=c04:00)t (:- .)'
.\ ,
. 1, m There is:an' analysis delay of.up to!30 minutes after sampling- -
Nuclide Concentration- ,
\ .
I7.'70E-04 uCi/cc Xe-133- ,
Xe-135 1.35E-02-uCi/cc;
~ TOTAL GAS' SAMPLE 1.43E-02 uCi/cc .
I-131= 8.92E-08'uCi/cc!
- I-132 7.85E-08iuCi/cc LI-133 1.04E-06-uci/cc- .
s
-I-134 4 '. 2 0E uCi/cc .
'I-1351 '1.96E-06 uCi/cc' l
l TOTAL CHARCOAY,, SAMPLE'. 3.58E-06-uCi/cc '
- DEI 131. 4.32E-07"uCi/cc- g lt1,
- TOTAL-FILTER SAMPLE -As-Found l-
! Undiluted ~ Gas Sample (15 al) Dose Rate,atcl',ft.: . < 2. mR/hr. -. !
.]
Hydrogen: Concentration:- -.0%- j oxygen, Concentration: 21.0%- = gJ!
^
~
- {
p ~ Airborne' Beta Dose Rate:'- 700. mRed/hrt Net' Air-Sample Count Rate: 2.6E5 cpm / min
^
Air Sample; contact Dose Rate: .
~
- 18. mrad /hr .
(1 Floor' Contamination:,2700.: cpm /100cm2 ~-
l Wall and Equipment Contamination: 360. cpm /100cm2- -
[, Personnel Contamination, Rate: 750; cpm /100cm2'per minute '
t
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OCNGSL .
SCENARIO:22
- - ANNUAL EXERCISE -
.REV NO O I2 - -
TABLE A-3.8k .
REFUEL' FLOOR-ACTIVITY-(T. 04 :15) - (-. ) )
. . . . . . . . . . . . . . . . _ _ _ _ _ . . _ _ _ =_ _ _ . . . _ _ . . . . . . . . . .'
' There is an. analysis delay of up'. toe 30 minutes-after sampling-Nuclide Concentration
'Xe-133, 7.41E-04 uCi/cc Xe-135 1.28E-02 uCi/cc.
TOTAL GAS-SAMPLE _k3bbb2ubi/cc I-131- '
1.06E-08-uC1/cc ~
I-112. 8.64E-09 uCi/cc; I-133 .1.22E-08 uci/cc I-134' 4.09E-08 uCi/cc-I-135 .2.27E-07 uCi/cc.
TOTAL CHARCOAL SAMPLE 409b07ubi/cc
. DEI 131 2.48E-08'uCi/cc TOTAL FILTER SAMPLE As Found. '
Undiluted Gas : Sample 1(15 al): Dose- Rate ' at1' f t. :; < 2.:mR/h1
.]
-Hydroqen Concentration:. .0%' 1 Oxygen, Concentration:121.0%- '
~ Airborne Beta Dose Rate: 640.; mrad /hr I Net Air Sample Count Rate: . 2.2E5 cpm / min.
Air Sample Contact Dose Rate:- 15.. mrad /hr-Floor Contamination: 2300, 7pm/100cm2!
Wall and Equipment Contamination:i 320. :cp/100cm2 I Personnel Contamination Rate: 640. cpm /100cm2 per minute s
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4 OCNGS:. .. .. SCENARIO 22-
, - ANNUAL EXERCISE REV NO- 0 ,
TABLE A-3.81 REFUEL FLOOR ACTIVITY ___.m 1(T - =...04 : 30) ( .
) -
There is an analysis delay;of up to'30 minutes after sampling- .
Nucif.de Concentration:
Xe-133 7.12E-04'.uci/cc Xe-135 1.21E-02 uCi/cc-L TOTAL GAS SAMPLE 1.27E-02?uCi/cc i -
'I-131- '1.01E-08'uCi/cc I-132- 8.20E-09 uCi/cc I-133: -1.16E-08 uCi/cc- E
.I-134 -3.89E-08 uCi/cc- lg-I-135 2.16E-07 uCi/cc TOTAL CHARCOAL SAMPLE.~3.89E-07'uci/cc DEI 131' 1.84E-08.uCi/cc;
_______________ q TOTAL FILTER SAMPLE :As Found.
i
.. Undiluted Gas Sample -. (15 .Ial) Dose-Rate at.1 ft.: !< 2.fmR/hr ;
l 1
Hydrogan Concentration: . 0%. 11 Oxygen ConcentrationF21;0%' Im J Airborne Beta Dose Rate: '640. mrad /hr l Net. Air Sample Count Rate: 2.OE5. cpm / min.
- Air Sample Contact Dose Rate: 14. mrad /hr Floor Contamination: .2100. cpm /100cm2 -l Wall and Equipment Contamination:- 300. cpm /100cm2-Personnel Contamination Rate:
600.' cpm /100cm2.per minute l:j LIL g
nBy tl 4
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.f OCNGS'- SCENARIO 22 l
- ANNUAL' EXERCISE . REV NO. 0 .J i
TABLE A-3.8m .
. ::I REFUEL' FLOOR ACTIVITY (T = 04 : 45) ~ ( > ) .J;
> JThere is an analysis delay ofcup-tof30 minutes afterisampling- 0 '
L; Nuclide Concentration E' '
Xe-133. 6.85E-04 uCi/cc d 1.14E-02 uci/cc-
'Xe-135- 1 1
l .-3l ::,
+
TOTAL' GAS SAMPLE! :1.21E-02 uci/cc i' I-131' 9.60E-09 uCi/cc L ~
I-132. 7.79E-09?uci/cc- ;
!' I-133 ' 1.'10E-08 'uci/cc - t
-I-134 3.70E-08 uCi/cc l',"' I-135' 2.05E-07~uCi/cc.
. TOTAL ~ CHARCOAL SAMPLE -3.70E-07.uci/cc d l
DEIM131 11.31E-08:uci/cc- !
l
. TOTAL FILTER SAMPLE As'Found 4
[ Undiluted ' Gas Sample (15 ml):. Dose Rate at 1 - ft : < 2.'mR/hr h
Hydrogen Concentration: . . 0%
Oxygen Concentration:"21.0%: +
~
~ Airborne Beta-Dose! Rate:i.'600.~ mrad /hr ,
- -- Net Air Sample Count-Rate
- l'.8E5 cpr/ min- ': !
- Air. Sample' Contact-Dose Rate: 13. mrad /hr. !
a
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Floor Contamination: 1900. cpm /100cm2. 'I Wall and Equipment Contamination: 1 230, cpm /100cm2 i Personnel Contamination. Rate:. 550~ cpm /100cm2lper minute .
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OCNGS- . .
SCENARIO 23 ANNUAL EXERCISE REV-NO ,0.
TABLE A-3.8n- -
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, ; REFUEL FLOOR ACTIVITY -; (T =' 05:00)1 ( ): I
........_________...___..___. ..___..________- J
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R There is an analysis delay of upctos 30 minutes after. sampling g- Nuclide: Concentration =
.I g
.\
y Xe-133 6.58E-04 uCi/cc i
-Xe-135 1.08E-02 uci/cc , 5'
-l TOTAL-GAS: SAMPLE L1-.14E-02. uci/cc -
I-131-- 9.'12E-091uCi/cc I-132 7.40E-09?uci/cc-I-133 1.05E-08'uCi/cc
~I-134. '3.52E-08 uC1/cc I-135:
" _1. 95E-07 : uci/cc
~
-TOTAL CHARCOAL SAMPLEL 3.52E-07.uci/cc
?
DEIJ131. 1'.24E-08 uCi/cc !
_________.___-- l; TOTAL FILTER ~ SAMPLE- As_Found sq Undiluted Gas Sample _(15 ml) Dose Rate at 1-ft.: -< 21mR/_hr~
Hydrogen Concentration':: .0%'
Oxygen. Concentration:E21.0% i
. Airborne Beta: Dose Rate:1 : 560.E mrad /hr-Net. Air' Sample ~ Count Rate: 1.1E5. cpm / min- ,
Air Sample Contact Dose Rate: 7.8 mrad /hr. '
l Floor Contamination:"1200. cpm /100cm2 Wall and Equipment Contamination:- 200.; cpm /100cm2
. Personnel Contamination-Rate: - 350.Jcpm/100cm2Eper minute
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' /OCNGSL SCENARIO! 22' ANNUAL EXERCISE REV NO' '
O I TABLE A-3.8o .
j 7, EEFUEL FLOOR ACTIVITY.(T.= 05:15) ( )- j i
H
- .There is an analysis' delay of up to 30' minutes after. sampling. U
!. Nuclide Concentration 1 r
Xe-133 6.33E-04 uCi/cc ?
Xe-135- 1.02E-02 uCi/cc l' TOTAL GAS SAMPLE - 1. 08E-02.; uci/cc ' 4 i
, I-131- 8I66E-09 uCi/cc-
- I-132 '7.03E-09=uCi/cc
'I-133- 9' 98E-09 'uCi/cc I-134' 3.34E-08 uCi/cc
'I-135 1.85E-07 uCi/cc1 s
TOTAL' CHARCOAL SAMPL2' 3.34E-07 uCi/cc
, DEI 131- 1.17E-081uci/cc; ,
TOTAL FILTER SAMPLE- 'As Found-1:
l p Undiluted Gas - SampleE(1,5 ml)1 Dose- Rate at. l' ft. :- < 2.5mR/.hr-Hydrogen Concentration:' .0%-- ,
Oxygen Concentration: l21';0% ,
Airborne Beta' Dose Rate': 530.: mrad /hr Net Air Sample Count Rate 1.0E51 cpm / min 1 Air Sample Contact Dose Rate:- 17.0 mrad /hr ,
Floor' Contamination:-1100 7 cpm /100cm2- 3 g Wall and Equipment Contamination: 1200. cpm /100cm2. '
Personnel. contamination. Rate: 350 7 cpm /100cm2 per minute-l L .
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' ANNUAL EXERCISE- SCENARIO NO. 22 OCNGS1 REV. 0-x I
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[z t Section,A-4
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- A-4.1, Radiologi al Survey / Sampling Data-l' A-4 .' 2 - Reuter-Stokes-Data Summary' Table' A-4.3 Environmental Sampling Data.
- A-4.4 Plume Search Data f]