ML20117K490
| ML20117K490 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 03/29/1985 |
| From: | Gosdin T TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | |
| Shared Package | |
| ML20117K489 | List: |
| References | |
| PROC-850329-02, NUDOCS 8505150447 | |
| Download: ML20117K490 (739) | |
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o j COMANCHE PEAK STEAM ELECTRIC S~ATION l
CPSES EMEF.GENCY PLAN MANUAL f*T CONTROL j 1 T m\
PROCEDUP.E INDEX 073 i l a COPY U, 1
VOLUME II /
l REVISION 21 EN7 C 1
- PAGE 1 0F 2 1
- - Procedure No. Revision No. Procedure Title Review Date l- .
- EPP-204 3 Activation of the TSC and November, 1985 j TSC Personnel Duties i *EPP-205 2 Activation of the Operations Se.ptember, 1985
] Support Center and Operations y Support Center Personnel Duties
- EPP-206 2 Activation of the Emergency . November, 1985
- f Operations Facility (EOF) and a
.i -
EOF Personnel Duties
- EPP-207 2 Activation of the News Center October, 1985 1 and Personnel Duties I
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- EPP-208 4 Access Control During November, 1985 Emergency Conditions 1 *EPP-209 0 Personne.1 Assembly & July, 1984 Accountability
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} *EPP-210 4 Evacuation September, 1985
- EPP-211 1 Release of Toxic Material Proc. Retired j *EPP-212 1 Release of Information to the Proc. Retired _
1 Public
- EPP-300 2 Manual Calculation of Release January, 1986
] Rates y
- EPP-301 0 Computer Assecement of October, 1985 Radiological Conditions
- EPP-302 3 Manual Assersment of Radio- January, 1986 logical Conditions j
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COMANCHE PEAK STEAM ELECTRIC STATION EMERGENCY PLAN MANUAL PROCEDURE INDEX VOLUME II REVISION 21
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PAGE 2 0F 2
- ) Procedure No. Revision No. Procedure Title Review Date M
r EPP-303 0 Micro-Computer Based, November, 1985 Emergency Dose Assessment
>3 at 1 *EPP-304 5 Protection Action Guides November, 1985 A
Q *EPP-305 3 Exposure Guidelines and December, 1985
[I Personnel Dosimetry During f
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Energency Conditions
- EPP-306 5 Use of Thyroid Blocking Agents Febr:ary, 1986 Q *EPP-307 2 Radiological Monitoring of September, 1985 1 {V Site Evacuees.
- EPP-308 4 Transporting Contaminated January, 1986 a Injured Personnel d
- EPP-309 4 Offsite Radiological Au gus t , 1985 Monitoring i
- EPP-310 2 On-Site and In-Plant July, 1985 Radiological Surveys
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l' COMANCHE PEAK STEAM ELECTRIC STATION
' EMERGENCY PLAN MANUAL l
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i ij ACTIVATION OF THE i TECHNICAL SUPPORT CENTER (TSC) l AND y TSC PERSONNEL DUTIES i
b i PROCEDURE NO. EPP-204 i
S. REVISION NO. 3 CPSES courgog,
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[ EMERGENCY PLAN MANUAL NOV -61984 EPP-204 b ACTIVATION OF THE TECHNICAL SUPPORT Q CENTER (TSC) AND TSC PERSONNEL DUTIES REVISION No. 3 PACE 2 0F 24 t
1.0 Purpose This procedure provides instructions for the activation of the 7 Technical Support Center (TSC). This procedure also identifies the
[ required actions, responsibilities, authorities and interfaces of those personnel assigned to the TSC.
2.0 Applicability j This procedure shall be initiated following the declaration of an l Alert, a Site Area Emergency or General Emergency at CPSES. This j procedure is applicable to the TSC Manager and his staff. During an 3 emergency condition classified as a Notification of Unusual Event, the Emergency Coordinator at his discretion, may direct activation of the TSC.
This procedure becomes effective when issued.
3.0 Definitions I 3.1 Technical Support Center - The TSC is the onsite emergency
( response facility located in close proximity to the Control Room that shall provide plant management and technical support to
('b} Control Room personnel during an emergency condition at CPSES.
The TSC is equipped with technical data displays, plant records
- and other documents to assist TSC personnel in the detailed analysis and diagnosis of abnormal plant conditions and any releases of radioactivity to the environment. The TSC shall be
[ the primary communications center for the plant during an emergency. At CPSES, the TSC is located in the classroom and office areas above the Control Room, at elevation 840'-6" of the f
j
Electrical and Control Building. The TSC is provided with the j same habitability conditions as the Control Room. An example of the TSC layout is illustrated in Attachment 2 to this procedure.
4.0 Instructions
? _ ,
4.1 Minimum Staffing Requirements 1
4 The minimum staffing requirements for the TSC are as follows: i j a. Station t'anagement Representative
- b. Station Engineering Representative i c. Station Operations Representative I '
- d. Station Maintenance Representative g .7. _. - _ _ , - , . . . - . . , . . . , ,
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4 CPSES ISSUE DATE PROCEDURE NO.
EMERGENCY PLAN MANUAL EPP-204 j
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ACTIVATION OF THE TECHNICAL SUPPORT
(} CENTER (TSC) AND TSC PERSONNEL DUTIES REVISION NO. 3 PAGE 3 0F 24
- e. Station Radiation Protection Representative
- f. TSC Communicator
[ NOTE: The above indicates the position holder in the Emergency
[ Organization or a qualified alternate.
The above listed Station representatives must be able to assume control of the TSC and have suitable personnel available to i perform the functions delineated in 4.2.1.1 - 4.2.1.6, in order l to achieve the minimum staffing raquirement for activation of the 1 TSC.
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b 4.2 Facility Activation 4.2.1 In the event that emergency conditions (Alert or higher i
classification, or at the discretion of the Emergency Coordinator) warrant activation of the TSC; the TSC must be'able to perform the following functions in order to achieve minimum activation.
4.2.1.1 Facility Management
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k 4.2.1.2 Maintenance Functions 4.2.1.3 Communications 4.2.1.4 Technical Evaluations 4.2.1.5 Radiological Evaluations 4.2.1.6 Operations Evaluations
- f. NOTE: Activation of the TSC should be accomplished
[ within sixty (60) minutes after the " Alert" emergency classification has been declared.
4.3 Technical Support Center (TSC) Personnel Duties I 4.3.1 Technical Support Center Manager 4.3.1.1 The individuals designated to assume this position upon activation of the TSC (in
- descending order of succession)
l l 4.3.1.1.1 Manager, Plant Operations 4.'3.1.1.2 Engineering Superintendent 4.3.1.1.3 Operations Superintendent w ey + ee- p e 4mg -==-e4w tur w 9
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EMERGENCY PLAN MANUAL g g 1984 EPP-204 ACTIVATION OF THE TECHNICAL SUPPORT Q CENTER (TSC) AND TSC PERSONNEL DUTIES REVISION NO. 3 PAGE 4 0F 24 4.4.1.1.4 Maintenance Superintendent.
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[ 4.3.1.2 Responsibilities:
Upon arrival at the TSC, contact the on-duty Shift Supervisor (Emergency Coordinator) to obtain information regarding the plant status and the status of onsite and offsite emergency response activities.
i j 4.3.1.2.1 In addition to assuming the duties of
] the TSC Manager, assume duties of the
- Emergency Coordinator if the EOF has not been activated as specified in Procedure EPP-109, until such time as:
]
- a. The event is closed out.
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- b. The Recovery Organization is formed (EPP-121).
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- c. The EOF is accivated.
4.3.1.2.2 Formulate protective action recommendations (EPP-304), and disseminate to State and county authorities (only as Emergency
[ Coordinator).
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{ 4.3.1.2.3 Upon activation of the EOF, complete
{- the turnover of the Emergency j Coordinator function to the Emergency
- Coordinator in the EOF as per EPP-109.
I 4.3.1.4 Verify the proper activation of the TSC.
[.
4.3.1.5 Verify the activation of the Operations Support -
Center (OSC).
4.3.1.6 Check notifications of State and local authorities and other agencies in accordance b with EPP-203, " Emergency Notification".
j 4.3.1.7 Assume control of the direction and coordination of all onsite activities conducted from the TSC, including:
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,.3 4.3.1.7.1 The establishment of proper CJ communications with the Control Room, OSC, EOF, and other emergency response i
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CPSES ISSUE DATE PROCEDURE N0 0 EMERGENCY F'.AN MANUAL EPP-204 NOV -61984 ACTIVATION OF THE ?ECHNICAL SUPPORT
[) CENTER (TSC) AND T3C PERSONNEL DUTIES REVISION NO. 3 PAGE 5 0F 24 facilities and coordination of all emergency response activities j conducted within the Protected Area.
t 9 4.3.1.7.2 The determination of the severity of
, the emergency conditions and the
! current status of onsite emergency i
response activities.
4.3.1.7.3 Review of all plant manipulations.
1 4.3.1.8 Verify that all TSC emergency response functions i
are being performed.
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4.3.1.9 Relieve the Control Room personnel ~of eny administrative functions and decisions that are not directly related to the safe shutdown of the station.
I l 4.3.1.10 Interface with the Onsite Radiological l Assessment Coordinator to evaluate changes in
} plant status for potential offsite radiological consequences.
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8 4.3.1.11 Ensure coordination of activities conducted from the TSC with those activities conducted from the EOF.
4.3.1.12 Interpret plant technical information as required.
4.3.1.13 Initiate personnel rescue or emergency repair and damage control operations as appropriate.
4.3.1.14 Provide input te the NRC representative stationed at the TSC regarding plant operating license requirements. --
4.3.2 Maintenance Coordinator 4.3.2.1 The individuals designated to assume this position upon activation of the TSC are (in descending order of succession):
4.3.2.1.1 Maintenance Superintendent 4.3.2.1.2 Maintenance Engineer !
l 4.3.2.1.3 Electrical Maintenance Engineer.
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i CPSES ISSUE DATE PROCEDURE NO.
EMERGENCY PLAN MANUAL EPP-204 NOV -61984 l
t ACTIVATION OF THE TECHNICAL SUPPORT h CENTER (TSC) AND TSC PERSONNEL DUTIES REVISION NO. 3 PAGE 6 0F 24 4.3.2.2 Responsibilities:
4.3.2.3.2 Coordinate and direct emergency repair and damage control activities through j the OSC Supervisor.
9 4.3.2.3.3 Advise the OSC Supervisor of any changes in plant conditions which may
- affect emergency repair and damage g control activities.
P L 4.3.2.2.4 Advise the TSC Manager and other TSC
( personnel regarding the status of I; onsite emergency repair and damage e
U control activities.
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$ 4.3.3 Operations Coordinator y
4.3.3.1 The individuals designated to assume this
, position upon the activation of the TSC are (in
- descending order of succession)
t g 4.3.3.1.1 Operations Superintendent 4.3.3.1.2 Operations Engineer 4.3.3.1.3 Operations Supervisor.
t 4.3.3.2 Responsibilities:
4.3.3.3.1 Advise the TSC Manager and other TSC personnel regarding plant conditions
, and operational manipulations.
c 4.3.3.3.2 Evaluate the effects of proposed j operational manipulations.
4.3.3.3.3 Coordinate with the Operations
. Advisor.
4.3.3.3.4 Interface with the Maintenance Coordinator and the Engineering Team Coordinator.
4.3.3.3.5 Ensure that the Operational Status g Sheet. EPP-204-2 (Attachment 3), is
- completed in a timely manner, and
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establish and maintain a file of '
O completed forms. !
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CPSES ISSUE DATE PROCEDURE NO.
EMERGENCY PLAN MANUAL EPP-204 q ACTIVATION OF THE TECHNICAL SUPPORT l r,] CENTER (TSC) AND TSC PERSONNEL DUTIES REVISION NO. 3 PAGE 7 0F 24 h.
V 4.3.4 Engineering Team Coordinator 4.3.4.1 The individuals designated to assume this position upon the activation of the TSC are (in descending order of succession):
4.3.4.1.1 Engineering Superintendent 4.3.4.1.2 Results Engineering Supervisor i
4.3.4.1.3 Results Engineering Supervisor 4.3.4.2 Responsibilities:
4.3.4.2.1 Direct and coordinate the efforts of l the TSC Engineering Team.
4.3.4.2.2 Verify that emergency response engineering support personnel with TSC assignments are in position or have been notified and are proceeding to l the TSC.
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g' 4.3.4.2.3 Advise the TSC Manager on technical
- matters relating to the NSSS, fuel integrity, plant systems and equipment, plant electrical systems and electrical systems and equipment, and plant instrumentation.
4.3.4.2.4 Perform an independent assessment of critical plant parameters.
4
- 4.3.4.2.5 Coordinate any TUCCO requests for
! technical assistance and support from
! within the Texas Utilities System or from outside organizations. -
4.3.4.2.6 Directed requests for outside assistance to Engineering Support Coordinator at the EOF when the EOF is
! activated.
6 4.3.5 TSC Engineering Team 4.3.5.1 The TSC Engineering Team shall be composed of four (4) members with general knowledge in the following areas 9 9' d 90
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' CPSES ISSL'E DATE PROCEDURE NO.
EMERGENCY PLAN MANUAL EPP-204 i NOV -s taga I
ACTIVATION OF THE TECHNICAL SUPPORT CENTER (TSC) AND TSC PERSONNEL DUTIES REVISION NO. 3 PAGE 8 0F 24
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- . 4.3.5.1.1 Mechanical Engineering 4.3.5.1.2 Instrument and Controls Engineering f
F f 4.3.5.1.3 Electrical Engineering 4 4.3.5.1.4 Nuclear Engineering 4.3.5.1.5 Operations.
I 4.3.5.2 Responsibilities:
5 i NOTE: The responsibilities described may be l performed by individuals or by the entire team.
i 4.3.5.2.1 Trend and evaluate current nnd
, historical plant parameters.
4.3.5.2.2 Assess the severity of the emergency conditions.
g 4.3.5.2.3 Estimate time available to perform critical actions or before crucial parameters are exceeded or vital equipment is lost.
4.3.5.2.4 Prepare plant trend data and formulate actions based on the trend data.
4.3.5.2.5 Recommend corrective or preventative actions to the Engineering Team Coordinator.
t j 4.3.5.2.6 Provide time estimates for the
[ performances of repair activities to place vital equipment back in service. 1 4.3.5.2.7 Provide Engineering Support to Control, Room and TSC Emergency Organization
[ Groups.
t i 4.3.5.2.8 Prepare messages for the Nuclear Network System and transmit the
[
> messages to the Nuclear Network
[ operator at the EOF.
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EMERGENCY PLAN MANUAL EPP-204
] NOV -61o94 ACTIVATION OF THE TECHNICAL SUPPORT lhI CENTER (TSC) AND TSC PERSONNEL DUTIES REVISION NO. 3 PAGE 9 0F 24 4.3.5 Onsite Radiological Assessment Coordinator i
/ 4.3.5.1 The individual designated to assume this position upon activation of the TSC is a member
).
of the Nuclear Operations or Plant Staf f who is f trained and has experience in Health Physics.
4.3.5.2 Responsibilities:
4.3.5.2.1 Ensure the radiological safety of all emergency response personnel working within the Protected Area.
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4.3.5.2.2 Coordinate the activities of the TSC Radiation Monitoring System (RMS)
Computer Operators, Field Teams Communicator, Onsite Survey Teams Director and the Chemistry Supervisor a
at the OSC.
4.3.5.2.3 Direct and coordinate all radiological-related emergency response activities prior to the O' activation of the EOF.
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~4.3.5.2.4 Ensure that emergency sampling and radiological survey procedures are being properly implemented.
4.3.5.2.5 Collect, review, and evaluate data
- concerning plant conditions and
' distribute to the appropriate personnel as required.
4.3.5.2.6 Review and evaluate all onsite radiological data.
f _
4.3.5.2.7 Ensure that the in-plant use of protective clothing and respiratory protection, and access control measures are properly implemented.
4.3.5.2.8 Ensure that appropriate bioassay procedures have is an implemented for onsite personnel.
e 4.3.5.2.9 Ensure that personnel radiation j g3 exposures are maintained in
'O accordance with CPSES administrative limits unless otherwise authorized by the Emergency Coordinator.
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CPSES ISSUE DATE PROCEDURE N0.
EMERCENCY PLAN MANUAL EPP-204 NOV -61984 j ACTIVATION OF THE TECHNICAL SUPPORT y CENTER (TSC) AND TSC PERSONNEL DUTIES REVISION NO. 3 PAGE 10.0F 2t.
6 4 4.3.5.2.10 Ensure that personnel are properly decontaminated, if necessary, f 4.3.5.2.11 Assist in planning personnel search and rescue operations, if necessary.
9 4.3.5.2.12 Assist in the transfer of injured and g non-essential personnel if radiation f
or contamination hazards are involved.
4.3.5.2.13 Direct requests for additional support to the Radiation Protection
( Coordinator, at the EOF. including L any requests for:
L L a. Additional radiological monitoring equipment.
- b. Engineering evaluations of
, temporary shielding on special
[ tools and equipment.
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h" c. Additional health physics support j personnel.
- d. Additional instrumentation and equipment.
L 4.3.5.2.14 Advise and assist the Radiation Protection Coordinator on matters involving radiological safety.
4.3.5.2.15 Maintain records of all onsite
- radiological emergency response
- activities.
4.3.5.2.16 Ensure that the Radiological Status 6 - Sheet, EPP-204-3 (Attachment 4) is j completed in a timely manner, and I establish and maintain a file of
[ completed forms.
[; 4.3.5.2.17 Maintain personnel dosimetry records for the duration of the emergency situation.
, 4.3.6 TSC Radiation Monitoring System (RMS) Computer Operators c'.)
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4.3.6.1 The two TSC RMS Computer Operator positions 4
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] FMERGENCY PLAN MANUAL NOV -61984 EPP-204 ACTIVATION OF THE TECHNICAL SUPPORT
() CENTER (TSC) AND TSC PERSONNEL DUTIES REVISION NO. 3 PAGE 11 0F 24
'; shall be filled by individuals from the Radiation Protection Section.
4.3.6.2 Responsibilities:
4.3.6.2.1 Calculate the projected onsite and offsite doses.
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- 4.3.6.2.2 Provide the completed dose projections to the Onsite Radiological Assessment Coordinator.
4.3.6.2.3 Obtain information regarding current and forecasted meteorological conditions.
4.3.6.2.4 Provide input as required for the timely completion of the Radiological Status Sheet EPP-204-3 (Attachment 4).
4.3.7 Technical Support Center (TSC) Advisor 4.3.7.1 The primary individual designated to assume this position upon activation of the TSC is the Results Engineer. The designated alternates are Engineers from the Results Engineering Section.
4.3.7.2 Responsibilities:
4.3.7.2.1 Provide technical advice to the TSC Hanager and other members of the TSC' Staff as required.
4.3.7.2.2 Coordinate varehouse support se rvices.
4.3.7.2.3 Direct and coordinate the activities
. of the following personnels
- a. TSC Communicator
- b. TSC Clerk
- c. TSC Events Recorder
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i CPSES ISSUE DATE PROCEDURE NO.
j EMERGENCY PLAN MANUAI. EPP-204 NOV -61984
!i ACTIVATION OF THE TECHNICAL SUPPORT
] O..*'
CENTER (TSC) AND TSC PERSONNEL DUTIES REVISION NO. 3 PAGE 12,0F 24 f
] 4.3.7.2.4 Ensure that adequate logistical 1 support is provided both to the onsite and offsite emergency response
! and recovery efforts prior to the activation of the EOF. Such h logistical support may include, but j is not limited to, the following:
- (
j a. Additional clerical and j administrative support j personnel; if
]j b. Warehouse support, procurement and expediting services; O
q c. Life-support services (e.g.,
1 food, clothing, and sleeping fj quarters) for onsite emergency L) personnel; and f'
- d. Additional communications support P
f and equipment repair services.
L v' 4.3.7.2.5 Inform' the Logistical Support y Coordinator of any logistical activities, requests, etc. upon N activation of the EOF.
j 4.3.7.2.6 .If the EOF has not been activated, 1 verify the technical accuracy and j adequacy of all public information
. releases prior to their dissemination I
to the' news media.
1 J 4.3.7.2.7 Inform the Public Information j Coordinator of any news /information , ,
a releases made prior to activation of -
I the EOF.
1 '
] 4.3.7.2.8 Conduct and record plant trend date j analysis (i.e. indications of long j term degradation of plant or i 31 situation outlooks getting better).
2
] 4.3.8 TSC Communicator
] 4.3.8.1 The TSC Comunicator position shall be filled by q 3 plant operations engineers or technicians b trained in the responsibilities of the position.
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CPSES ISSUE DATE PROCEDURE NO.
EMERGENCY PLAN MANUAL EPP-204 NOV - A iona ACTIVATION OF THE TECHNICAL SUPPORT h CENTER (TSC) AND TSC PERSONNEL DUTIES REVISION NO. 3 PAGE 13 0F 24
~
k 4.3.8.2 Responsibilities:
F 4.3.8.2.1 Perform communications duties.
1 r 4.3.8.2.2 Log all incoming and outgoing communications in accordance with y
" EPP-202, " Emergency Communications",
and EPP-203 " Emergency Notification".
i 4.3.9 TSC Clerk
'l
) 4.3.9.1 The TSC Clerk position shall be filled by Plant Operations Engineers or Technicians trained in the responsibilities of the position.
4.3.9.2 Responsibilities:
] 4.3.9.2.1 Perform clerical and administrative duties (e.g., distributing or posting information and copying documents).
4.3.9.2.2 Assist and respond to any requests Q from the TSC Manager.
4.3.10 TSC Events Recorder
- 4.3.10.1 The TSC Events Recorder position shall be filled by Plant Operations Engineers or Technicians j trained in the responsibilities of the position.
i sj 4.3.10.2 Responsibilities:
~
4.3.10.2.1 Maintain a log of all pertinent emergency response activities occurring in the TSC.
4.3.10.2.2 Obtain information related to the -
emergency situation from TSC personnel.
4.3.10.2.3 Post information related to the emergency situation on the TSC t
Sequence of Events Board.
, NOTE: The TSC Sequence of Events
.{ Board should list, in
.{ chronological order, only i ,1 those event-type items reisted
's to the emergency situation.
Operational and radiological
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- i j CPSES ISSUE DATE PROCEDURE NO.
EMERGENCY PLAN MANUAL EPP-204
,g ggg4 ACTIVATION OF THE TECHNICAL SUPPORT REVISION No. 3 PAGE 16 0F 24 h CENTER (TSC) AND TSC PERSONNEL DUTIES ATTACHMENT 1 PAGE 1 0F 1 L TSC ACTIVATION CHECKLIST w
l ] Texas Utilities Generating Company 1 Comanche Peak Steam Electric Station TECl## CAL SUPPORT CENTWI OPetATMNes CHECKLIST >' Page 1 of 1 ftem Status Terified
- 1. TSC Layout A. As Per Attachment 2
- 3. Modified
- 2. Communicatione 2.1 Telephones Installed 2.2 tatablish Communicatione per EPP.202 and EPP-203 se 3 applicable.
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- 3. TSC Staff
- A. Minimum Activatico Staf f
} 1. Managemmet
- 2. fagineerias
- 3. Operettoes
- 4. Maintenance
- 5. Radiation j Protectics e 4. TSC Camemmicater
-l* 5. TSC Personnel Accountability Coadseted (Date/ Time) 4 TSC Activated , CC90GNTS t Tsc MAAAGER/DAf t av tomas4 EPP-204-1 l c... ._,-.._.,_.......,,._,..__., , , _ .. . ., .._ , . , , , . i a .. ..
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.t 9 CPSES ISSUE DATE PROCEDURE NO. 1 EMERGENCY PLAN MANUA1. EPP-204 NOV -61984
~ ; ACTIVATION OF THE TECHNICAL SUPPORT I t REVISION NO. 3
}h CENTER (TSC) AND TSC PERSONNEL DUTIES PAGE 17 0F 24 ATTACHMENT 2 PAGE 10F 2 SUGGESTED TSC LAYOUT i 3 TECHNICAL SUPPORT CENTER SEQUENCE 0, EvtNTS 90Am
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_ j. , . , :-. 3 __..-- i I CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL EPP-204 ACTIVATION OF THE TECHNICAL SUPPORT
) IS CENTER (TSC) AND TSC PERSONNEL DUTIES REVISION NO. 3 PAGE 18 0F 24
'y ATTACHMENT 2 PAGE 2 0F 2 SUGGESTED TSC LAYOUT ROOM 149 /149A 1 TSC MAN AGER l
2 OPERATIONS COORDINATOR
- 3 MAINTENANCE COORDINATOR 4 ENGINEERING TEAM COORDINATOR S ONSITE RADIOLOGICAL ASSESSMENT COORDINATOR
} S TSC ADVISOR 7 TSC ENGINEERING TEAM I
S TSC COMMUNICATOR 9 TSC CLERK l 10 TSC EVENTS RECORDER l ' 11 OPERATIONAL. STATUS RECORDER 5 12 RADIOLOGICAL STATUS RECORDER 13 flMS COMPUTER OPERATORS i 14 NRC OR DRILL CONTROLLER
! d" r
t Q PSX TELEPHONE
@ PSX/ TRUNK LINE TELEPHONE i
, @ DEDICATED TELEPHONE TO EOP _
@ DECICATED TELEPHONE TO OSC
@ DEDICATED TELEPHONE TO CONTROL ROOM i
STATE AND COUNTY RINGDOWN LINE - , C=3 RADIO BASE STATION SPOgl SAFETY PARAMETER DISPLAY SYSTEM m:=:::s COMPUTER TERMINAL SP SCREEN PRINTER RADIATION MONITORING SYST EM COMPUTER TERMINAL f I q-. -.-.#.._, - m ., .,. , ..,,y7.,,,.,.,
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.i ! (O s.y CENTER (TSC) AND TSC PERSONNEL DUTIES 1 i ].* ATTACHMENT 3 I - PAGE 1 0F 3 OPERATIONAL STATUS SHEET i
Texas Utilities Generating Company l
- Comanche Peak Steam Electric Station t
i OPERATIONAL STATUS SHEET
' Date: Page 1 of 3 Time:
- 1. Affacted Unit One Two
- 1. $
- a. Pressure: PSIC
- b. Tavg 'T
- c. PR:1 Levels :
- 4. Est. RCS Laaks CPM
- e. RCP: On Off k
- f. T/C (81/ Avg): / 'T
- g. Cg PPM Loop Status: 6
- h. 1 2 3 T F E
T 'T c I J. ECCS 11j No. Total i
- Pusos W l
- a. CC l
- b. RER
- c. SI .
- d. Cont. Spray ,
- e. SWST Levels 1
- f. Accueulators 1 2 3 k
Accus. Level g
- g. Accan. Pres. Ps!C k
I 4 Emettenew Response Cutiditees
- a. Precedures
- b. Step
- 4. Diagnosed Event O EPP.304 3 1
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3 i a CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL EPP-204 NOV -41984 b ACTIVATION OF THE TECHNICAL SUPPORT REVISION NO. 3 PAGE 20 0F 24 3* CENTER (TSC) AND TSC PERSONNEL DUTIES f] ATTACHMENT 3 3 PAGE 2 0F 3 l 1 OPERATIONAL STATUS SHEET fl I 1 1
't Texas Utilities Generating Company d
Comanche Peak Steam Electric Station OPERATIONAL STATUS SHEET Date: Page 2 of 3 Time: I
$. Critical Safety Tunctions I Time Red Orange Tellow Green f i Sub Crit. TRS-0.1 TRS-0.1 MS-0.2 Sat L
l : >g. FRC-0.2
"' Core Cooling TRC-0.1 TRC-0.3 TRC-0.4 Set RCS Integrity TRP-0.1 TRF-0.1 TRF-0.2 Sat
[' FRM-0.2 FRM-0.) Rest Stak ' FRH-0.1 FRH-0.3 FL'-0. 5 Sat l FR2-0.1 Sat Containment TR2-0.1 FR2-0.2 FR2-0.3 TRI-0.n 1 TR!-0.2 )* TRI-0.3 Sat InventorT d i . I
- 6. Plant Statas 6 e. Rm Trip t
i b. $* Actuation
, c. Containment Spear Actuation
- d. Power Level I
- e. Comments ,
I I s f t
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CPSES ISSUE DATE PROCEDURE NO. j EPP-204 EMERGENCY PLAN MANUAL g4g
)} ACTIVATION OF THE TECHNICAL SUPPORT REVISION NO. 3 PAGE 21 0F 24 ;
- j .Q "j CENTER (TSC) AND TSC PERSONNEL DUTIES
)
j i j ATTACHMENT 3 PAGE 3 0F 3 i l i OPERATIONAL STATUS SHEET l l i h ' j Texas Utilities Generating Company Comanche Peak Steam Electric Station 7 OPERATIONAL STATUS SHEET 1 Date: Time: Page 3 of 3 9 1 Co=t**-- t Conditises j a. Pressures PSIC
- b. Temperatures of
- c. Emidity: 1
- 4. Bad. Levels 1/at
- e. Phase A laelaties:
[ 2: f. Phase 3 Iselation 3 Test. Iselations
- h. Byerogen Concentration: 2 Tolume
8. Stem Generators . k s. Steam Generator: 6
, 1 2 3 l b. SC Invel: I
- s. SC Pressure: PSIG j d. MSIT Status:
- e. AFV Fleva CPM h f. APW Peps os Motor 1 Motor 2 Turtise 3 CST Levels 1 f 9. Suonert Svetems me, has G
) a. SSV P epe Operatingt j b. CCW Peps operatias
~
$ t. Emergency he taargised: Traia A Traia 3 j d. Offsite Power: Tee Es f e. Diesel Cee. Available No. 1 No. 2 '
li. Ms J l 1 1 i O EPP=30e=3b i l,
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) EPP-204 j EMERGENCY PLAN MANUAL NOV -61984 }
2 ACTIVATION OF THE TECHNICAL SUPPORT j CENTER (TSC) AND TSC PERSONNEL DUTIES REVISION NO. 3 PAGE 22 0F 24
, Y.]
' "Q d ATTACHMENT 4 PAGE 1 0F 3 e
4' t RADIOLOGICAL STATUS SHEET I Texas Utilities Generating Company J Comanche Peak Steam Electric Station U RADIOLOGICAL STATUS SNEET Date: Time: Page 1 of 3 [ i
- 1. R.,.... t.
d Anticipated
- a. Releaset Not occurring occurring I
Release initiated: b. F'
- c. Release Duration
- d. Location of Release: Plant Vent Steae Surface tiquid Discharge other Information e
i I e. Release Monitoredt Yes No f Monitors 5 Particulate tiquid Cas
- f. Physical Torn:
i 3 RCS Activity $ ample Availablet Yes ( uC1/ce) No L Particulates Quantity Ci Release Rate C1/sec -j h. 1sdine: Quantity Ci Release Rate C1/Sec 1. Ci Release Rate C1/sec
- j. Noele Casr Quantity .
- k. Unusual Radiation Levels in Plants I
mR/hr Where mR/hr Where
; mR/hr Where ] Coat Radiation Monitor: Highest R/hr. Average R/hr 1.
j I spp.304 8 ( *
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1 . CPSES ISSUE DATE PROCEDURE NO. - EMERGENCY PLAN MANUAL EPP-204 l NOV -6 B84 ACTIVATION OF THE TECHNICAL SUPPORT
' ;q REVISION No. 3 PAGE 23 0F 24 CENTER (TSC) AND TSC PERSONNEL DUTIES
': )
ATTACHMENT 4 PAGE 2 0F 3 RADIOLOGICAL STATUS SHEET l h f y Texas Utilities Generating Company [ u Comanche Peak Steam Electric Station RADIOLOGICAL STATUS SHEET l k ! Date: Time: Page 2 of 3 i i
- 2. Meteorolonical Data
- a. Primary Met. Tower Sackup Met. Tower
[
- b. Wind Velocity: s/sec sph
- d. Direction (fros): Direction (to):
- e. AT: 'T Stability Class:
' ' ~
- f. Other Information:
b
- 3. Pi m Data Centerline Plume Dose Rate lotograted Dose Affected Dose Projections Arrival f orw '%r 4 forwi Map For Locations: Time WB Thyroid WB Thyroid Sectors Exclusion Area me..a . m 2 Miles k
- n. ..
5 Miles 10 Miles
- 4. Reecnumended Protective Actions 4
l . 1 l a i Fi t O .. ...... t e Of T'N- -
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u CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MWAL EPP-204 NOV -61984 j ACTIVATION OF THE TECHNICAL SUPPORT j 9 CENTER (TSC) AND TSC PERSONNEL DUTIES REVISION NO. 3 PAGE 24 0F 24
'I i
ATTACHMENT 4
'I. 'l PAGE 3 0F 3 1 '
RADIOLOGICAL STATUS SHEET J' )
- 1 Texas Utilities Generating Company j Comanche Peak Steam Electric Statfor RADIOLOGICAL STATUS SHEET Date:
Time: Page 3 of 3
- 5. Reestks 7
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1 i COMANCHE PEAK STEAM ELECTRIC STATION l f m EMERGENCY PLAN MANUAL j 8;;/ i ] l N j .] 1 4 ACTIVATION OF THE OPERATIONS SUPPORT CENTER j AND OPERATIONS SUPPORT CENTER PERSONNEL DUTIES
- )
d 4 i O PROCEDURE NO. EPP-205
- j REVISION NO. 2 M ES
.] CONTROL 1 < 2 1 , g 073 @ l2 copy [ O p" i4 8AFET(-REI.ME - I ~ II t SUBMITTED BY: DATE: [M[ ] SUPERINTERDENT, SUPPORT SERVICES APPROVED BY: , DATE: Y-/[- fjV [ANAQM, CCE%R DPERATIONS b p,e --+w. .~ . - . . . . . , . , . . . . . . . . , . . . . . . ..,.g.,, ..,.%... . , . . , , .,. 7 _. ,
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_ j l l l 3 CPSES TSSUE DATE PROCEDURE NO. ' EMERGENCY PLAN MANUAL EPP-205 g[pg y gg4 ACTIVATION OF THE OPERATIONS SUPPORT CENTER 9 AND OPERATIONS SUPPORT CENTER PERSONNEL DUTIES REVISION NO. 2 PAGE 2 0F 12 ) 1
\ ,- 1.0 Purpose l*
This procedure provides instructions for the activation of the Operations Support Center (OSC). This procedure also identifies the required actions, responsibilities, authorities and interfaces of g those personnel assigned to the OSC. 4 )i 2.0 Applicability l This procedure shall be initiated following the declaration of an j Alert, Site Area Emergency or General Emergency at CPSES. This l; procedure is applicable to the OSC Supervisor and all other personnel reporting to the OSC. During an emergency condition classified as a i Notification of Unusual Event, the Emergency Coordinator, at his j discretion, may direct activation of the OSC. 1 This procedure becomes effective when issued. ] I 3.0 Definitions 1 1 3.1 Operations Support Center - The OSC is the onsite emergency response staging area, separate from the Control Room and the i Technical Support Center (TSC), where CPSES emergency response i hm) support personnel shall report in an emergency. Direct j communications are provided between the OSC and the TSC so that j personnel reporting to the OSC can be assigned to duties in j support of emergency response operations. The OSC is located in i the Maintenance Building Annex, which is southwest of the Unit 1 Turbine Building at elevation 810'-6". The OSC layout is illustrated in Attachment 2 to this procedure, j 4.0 Instructions ) 4.1 Facility Activation i 4.1.1 In the event that emergency conditions (Alert or higher i Emergency Classification or at the discretion of the _ i Emergency Coordinator) warrant activation of the OSC, the i following steps shall be performed: . 4.1.1.1 Complete the OSC Activation Checklist ] (Attachment 1, Form EPP-205-1). j 4.1.1.2 Verify that the OSC can perform the following j functions as a minimum: )j a. Maintenance Support Management 1 { b. Radiological Surveys
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$[P17 % EPP-205 ACTIVATION OF THE OPERATIONS SUPPORT CENTER 1 AND OPERATIONS SUPPORT CENTER PERSONNEL DUTIES REVISION NO. 2 PAGE 3 0F 12 s .
I c. Maintenance Functions
- d. Communications Functions NOTE: The OSC Supervisor shall ensure that steps 4.1.1.1 through 4.1.1.4 have been completed.
4.1.1.3 . Verify that the minimum staffing requirements have been met as per 4.2 below, i NOTE: Activation of the OSC should be j accomplished when sufficient personnel ll are available to assume the functions listed above in 4.1.1.2. 4.1.1.4 Personnel assigned specific functions as per Attachment 1, or their representatives, shall complete these functions as part of their personnel duties listed herein. 4.2 Minimum Staffing Requirements j h The minimum staffing requirements for activation of the OSC are as follows: 1
- a. Station Maintenance Representative I NOTE: The above indicates the position holder or a qualified
! alternate. -
i 3 The above listed station representatives must be able to assume, j control of the OSC and have suitable personnel available to perform the functions delineated in 4.1.1.2 above, in order to meet the minimum staffing requirements for activation of the OSC. g 4.3 Operations Support Center (OSC) Personnel Duties _ 4.3.1 Operations Support Center Supervisor J 4.3.1.1 The individuals designated to assume this position upon activation of the OSC are (in descending order of succession): j 4.3.1.1.1 Mechanical Maintenance Engineer i 1-j h
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3 CPSES ISSUE DATE PROCEDURE NO.
]
EMERGENCY PLAN MANUAL $$1T $ EPP-205 i ACTIVATICN OF THE OPERATIONS SUPPORT CENTER j f], AND OPERATIONS SUPPORT CENTER PERSONNEL DUTIES REVISION NO. 2 PAGE 4 0F 12 j 4.3.1.1.2 Electrical Maintenance Engineer 4 j 4.3.1.1.3 Mechanical Maintenance Supervisor. I J 4.3.1.2 Responsibilities: 4.3.1.2.1 Establish Communications with the b Control Room and Technical Support
! Center.
4.3.1.2.2 Complete the OSC Activation checklist from EPP-205-1. I 4.3.1.2.3 Notify the Control Room and TSC of the OSC Activation and log this j information. I 4.3.1.2.4 Interface with the Maintenance Coor-dinator to coordinate emergency repair and damage control activities. 4.3.1.2.5 Interface with the Onsite Survey Teams
) Director to coordinate the deployment
! J of the Onsite Survey Team (s), and if the EOF has not yet been activated, f the deployment of the Offsite Monitor-
! ing Teams, i
! 4.3.1.2.6 Interface with the Chemistry Super-
! visor to coordinate the deployment of
, Chemistry personnel.
l* 4.3.1.2.7 Interface with the Offsite Monitsring Teams Director to coordinate the deployment of the Offsite Monitoring f Teams. i l l ~ l l 4.3.1.2.8 Supervise and coordinate the activi-
,l ties of those personnel assigned to } the OSC. , ; l I , 4.3.1.2.9 Assipi to the emergency repair and j damage control teams.
( 4.3.1.2.10 Interface with the Maintenance ! Coordinator in the TSC as required to l organize and assign available person- )
~ nel. i
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CPSES ISSUE DATE PROCEDURE NO.
-l EMERGENCY PLAN MANUAL g[p17 jgg4 EPP-205 .]
1 ACTIVATION OF THE OPERATIONS SUPPORT CENTER AND OPERATIONS SUPPORT CENTER PERSONNEL DUTIES REVISION NO. 2 PAGE 5 0F 12 3 . 5 4.3.2 Onsite Survey Teams Director
,5 4.3.2.1 The primary individual designated to assume this 3l
- . position upon activation of the OSC is a 9 Radiation Protection Supervisor. The designated
?j alternate is a member of the Nuclear Operations or Plant Staff, trained and experienced in p]j health physics.
7 d 4.3.2.2 Responsibilities: L 4.3.2.2.1 Initiate operation of the Iodine Monitor and Area Radiation Monitor. g 4.3.2.2.2 Assist the OSC Supervisor in directing q the deployment of the Onsite Survey h Team (s) from the OSC. Provide tech-
;1, nical expertise in the OSC for all 1 radiation protection related matters.
3 1 4.3.2.2.3 Assist the OSC Supervisor in coordin- [.] ating the deployment of the Offsite 2 Monitoring Teams, if required. d, , . i 4.3.2.2.4 Inter face with the Onsite Radiological l Asses sment Coordinator to establish j those onsite and in-plant locations to
) be surveyed, the types of surveys to g be taken, the routes to be used by the
- 'Onsite Survey Team (s) to reach those locations, and any requirements for the ute of protective clothing and respiratory protection equipment.
~
4.3.2.2.5 Coordinate and direct the activities
; of the Onsite Survey Team (s).
~
.. Coordinate and direct the activities of t;he Offsite Monitoring Teams until the EOF is activated. j 4.3.2.2.6 Coordinate with the Offsite Monitoring j Teams Director. u 9 4.3.2.2.7 Advise the Onsite Radiological Assess-ment Coordinator regarding the radio-logical conditions encountered and the radiological-inonitoring data collected 3 ih.. by the onsite;and offsite radiological 4 monitoring te.ams. I 1 1 - 11 il
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j 4 CPSES ISSUE DATE PROCEDURE NO. J EMERGENCY PLAN MANUAL $(P17 % EPP-205 t 1 ACTIVATION OF THE OPERATIONS SUPPORT CENTER L AND OPERATIONS SUPPORT CENTER PERSONNEL DUTIES REVISION NO. 2 PAGE 6 0F 12 1 1 4.3.2.2.8 Interface with the Onsite Radiological Assessment Coordinator to assess the radiological considerations to be applied to planning emergency repair and damage control activities. h 4.3.3 Chemistry Supervisor 4.3.3.1 The individuals designated to assume this position upon activation of the OSC are (in
, descending order of succession): l 4.3.3.1.1 Chemistry Supervisor 1 4.3.3.1.2 Chemist.
J. 4.3.3.2 Responsibilities:
~
4.3.3.2.1 Assist the OSC Supervisor in organ-izing and dispatching personnel to perform chemical sampling. 4.3.3.2.2 Provide technical expertise in the OSC U for all chemistry related matters. l 4. [ 4.3.3.2.3 Ensure that emergency sampling proced-S ures are properly implemented. 4.3.3.2.4 Provide post-accident sampling anal-1 ~ysis results to the Onsite Radio-4 logical Assessment Coordinator. j 4.3.4 OSC Communicators j 4.3.4.1 The two (2) OSC Communicator positions shall be filled by Maintenance Technicians or Maintenance Engineers. _
. 4.3.4.2 Responsibilities:
1 4.3.4.2.1 Sign in on the OSC Staffing Status j Board and perform communications duties as directed by the OSC Sup- {, [ ervisor. 4.3.4.2.2 Log all incoming and outgoing com-j munications with the Control Room, h, TSC, EOF, and those personnel deployed h in-plant in accordance with the provisions of Procedure EPP-202, I " Emergency Communications" and i EPP-203, " Emergency Notification".
r_
. CPSES ISSUE DATE PROCEDURE NO.
EMERGENCY PLAN MANUAL gg17j%( EPP-205 4 1 ACTIVATION OF THE OPERATIONS SUPPORT CENTER
! A y
AND OPERATIONS SUPPORT CENTER PERSONNEL DUTIES REVISION NO. 2 PAGE 7 0F 12 4.3.5 OSC Clerks I 4.3.5.1 The three (3) OSC Clerk positions shall be [ filled by Maintenance Technicians or Maintenance i Engineers. I 4.3.5.2 Responsibilities: .! 4.3.5.2.1 Maintain the "ERDC Assignments and 3 Status Board", the "R. P. and Chem. j Assignments and Status Board", and the l " Sequence of Events Board" located in 3 the OSC.
+
h 4.3.5.2.2 Perform clerical and administrative j duties (e.g., distributing or posting y information, and copying documents) as ? directed by the OSC Supervisor. l 4.3.6 Emergancy Repair and Damage Control (ERDC) Group j 4.3.6.1 The ERDC Group shall be composed of: hh 1 4.3.6.1.1 Instrument and Control Technicians 4.3.6.1.2 Electricians 4.3.6.1.3 Mechanics. < j 4.3.6.2 Responsibilities: J ' 4.3.6.2.1 Sign in on the OSC Staf fing Status 4 Board and then await further I, instructions from the OSC Supervisor. a
- s i 4.3.6.2.2 The ERDC Group, under the direction of J the OSl: Supervisor, shall effect any ~
repairs er modifications necessary to
! minimize the damage in,accordance with j EPP-116, and to initiate recovery j actions in accordance with the provi-sions of Procedure EPP-121.
j 4.3.6.2.3 The ERDC Group shall also perform j search and rescue operations and j provide first aid treatment as neces-l' sary. 1 ,y ? i$ a [ ,_ .,
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ISSUE DATE PROCEDURE NO. ! EMERCENCY PLAN MANUAL g{p17 jgg4 EPP-205 1]1 l 'l ACTIVATION OF THE OPERATIONS SUPPORT CENTER I l p) AND OPERATIONS SUPPORT CENTER PERSONNEL DUTIES REVISION NO. 2 PAGE 8 0F 12 ! l
, 4.3.7 OSC Radiation Protection Technicians f
1 4.3.7.1 The OSC Radiation Protection Technician posi-i tions shall be filled by Radiation Protection Technicians. 4.3.7.2 Responsibilities 1 4.3.7.2.1 Sign-in on the "0SC Staffing Status l Board". I 4.3.7.2.2 Report directly to, and respond to
! requests from, the Onsite Survey Teams
; Director.
t 4.3.8 OSC Chemistry and Environmental Technicians i
~: 4.3.8.1 The OSC Chemistry and Environmental Technician j positions shall be filled by Chemistry and g
Environmental Technicians. - 4.3.8.2 . Responsibilities: h 4.3.8.2.1 Sign in on the "0SC Staffing Status Board". 4.3.8.3.2 At the OSC; the Chemistry and Envir-f onmental Technicians shall report [ directly to, and respond to requests tI from, the Chemistry Supervisor, J 4.4 Subsequent Actions 6 v 3 4.4.1 As required to support emergency response operations, the OSC Supervisor shall prepare and dispatch ERDC teams, '; Offsite Monitoring Teams, Onsite Survey Teams, and other personnel as appropriate. ; 4.4.2 In the event of extended operations, designated alternates shall relieve primary position holders as appropriate, i The time of turnover, and the name of the designated
- f. replacement, shall be logged.
t 4.4.3 The control of Offsite Monitoring Teams shall be trans-I ferred to the Offsite Monitoring Teams Director following activation of the Emergency Operations Facility.
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EMERGENCY PLAN MAN M . g[p}7jg4 EPP-205 i J ACTIVATION OF THE OPERATIONS SUPPORT CENTER f AND OPERATIONS SUPPORT CENTER PERSONNEL DUTIES REVISION NO. 2 PAGE 9 0F 12 4.4.4 Operation of the OSC shall continue until such time that the Emergency Coordinator or the Recovery Manager directs deactivation. 1 5.0 References 5.1 CPSES Emergency Plan
. 5.2 EPP-ll6, " Emergency Repair and Damage Control" j 5.3 EPP-202, " Emergency Communication" 6.0 Attachments } 6.1 Attachment 1. "0SC Activation Checklist" l f 6.2 Attachment 2, "0SC Layout" l
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11 CPSES ISSUE DATE PROCEDURE NQ. ) EMERGENCY PLAN MANUAL SEP 171984 EPP-205 l
.) ACTIVATION OF THE OPERATIONS SUPPORT CENTER 4
-3 AND OPERATIONS SUPPORT CENTER PERSONNEL DUTIES REVISION NO. 2 PAGE 10 0F 12 4
t y
} ATTACRMENT 1 ., PAGE 10F 1 i
{ OSC ACTIVATION CHECKLIST 4
?
l Texas Utilities Generating Company i Comanche Peak Steam Electric Station j OPERATIONS SUPPORT CENTER ACTIVATION CHECKLIST Page 1 of 1 Verified Activation item Responsibility or Complete 4 4 1.0 Administrative OSC Supervisor 1.1 Emplace O!C layout OSC Personnel 1 (Attachment 2) 1.2 Esplace OSC telephones OSC Personnel I (Attachment 2) 1.3 verify OSC layout OSC Supervisor 1.4 Conduct OSC personnel OSC Supervisor {'..s, accountability check and report results'to Security 1.6 Verify minimum staff OSC Supervisor l j requirement 1.7 Verify status of communications OSC Supervisor f- 1.8 Announce OSC activation OSC Supervisor j (Items 1- complete) 2.0 Communications OSC Supervisor I . j 2.1 Verify communications OSC Communicator i equipment functioning properly 2.2 Establish communications with OSC Conounicator Control Room f TSC (if activated) Station Security 3.0 Radiation Assessment / Protection OSC Onsite Survey Teams Director 3.1 Activate todice monitor OSC Radiation i Protection Personnel 3.2 Activate area radiation OSC Radiation schitor Protection Personnel [ 3.3 Establish control points (if recessary) CSC Onsite Survey Teams Director l 1 : g 4 (: OSC Supervisor Date i l EPP-205-1 4 . X, 4 - 's"~', , ;;TWQG
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! ACTIVATION OF THE OPERATIONS SUPPORT CENTER AND OPERATIONS SUPPORT CENTER PERSONNEL DUTIES REVISION NO. 2 PAGE 11 0F 12
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i- . 9 1 i ATTACHMENT 2 i PAGE 10F 2 t 3
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, OSC LAYOUT e
1 DESIGNATED PERSONNEL POSITIONS i
- 1. OSC SUPERVISOR S. ONSITE SURVEY TEAMS DIRECTOR l 4
- 3. CNEMISTRY SUPERVISOR
'i .
- j 4. OSC COMMUNICATORS (2) s S. OSC cLERMS (s) 0 .
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i j COMANCHE PEAK STEAM ELECTRIC STATION j b .) EMERGENCY PLAN MANUAL ,4 II I L i i I' h u 4 o ACTIVATION OF THE EMERGENCY OPERATIONS FACILITY (EOF) AND EOF PERSONNEL DUTIES PROCEDURE NO. EPP-206 REVISION NO. 2 CPSES p
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d 5 CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL EPP-206 NOV -61984 q ACTIVATION OF THE EMERGENCY OPERATIONS h ( L]'; ' FACILITY (EOF) AND EOF PERSONNEL DUTIES REVISION NO. 2 PAGE 2 0F 22 1.0 Purpose 1 This procedure provides instructions for the activation of the Emerg-ency Operations Facility (EOF). This procedure also identifies the required actions, responsibilities, authorities and interf aces of b those personnel assigned to the EOF. s i 2.0 Applicability This procedure shall be initiated following the declaration of a Site Area Emergency or General Emergency at CPSES. This procedure is applicable to all members of the Emergency Organization assigned to the EOF. During an emergency condition classified as a Notification g of Unusual Event or an Alert, the Emergency Coordinator, at his g discretion, may direct activation of the EOF. f This procedure becomes effective when issued. e ft 3.0 Definitions j 3.1 Emergency Operations Facility - The EOF is the emergency response facility from which the management of the overall CPSES emergency h response, including coordination with Federal State, and local officials, will occur. The EOF is equipped with technical data i displays and plant records to assist EOF personnel in the diag-nosis of plant conditions and to evaluate the potential for. l; actual release of, radioactive materials to the environment. e Coordination of offsite support and assistance will occur at the
; EOF. At CPSES, the EOF is attached to the Nuclear Operations i Support Facility (NOSF), which is located 1.2 miles west of the 7
station. The EOF layout is illustrated in Attachment 2 to this
, procedure.
d ' 4.0 Instructions
] 4.1 Facility Activation
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!i j 4.1.1 In the event that emergency conditions (Site Area
] Emergency, General Emergency or at the discretion of the *
;1 Emergency Coordinator) warrant activation of the EOF, the following steps shall be completed:
j 4.1.1.1 Complete the EOF Checklist (Attachment 1 Form EPP-206-1). 4.1.1.2 Verify that the EOF can perform the following functions as a minimum: f O a. Emergency Management W- p h **Tw eg mp'-e y y* a w >g e>* ghw * *** mi w e m . e e paw ++ M w ****.*****m@r-<*e e = * - * - + - em '
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2 CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL EPP-206
- NOV -s ma 1
ACTIVATION OF THE EMERGENCY OPERATIONS
] .) FACILITY (EOF) AND EOF PERSONNEL DUTIES REVISION NO. 2 PAGE 3 0F 22 1
1
- b. Administrative / Communications Functions
; c. Radiological Assessment 1 .i i d. Technical Evaluations NOTE: The Emergency Coordinator shall ensure P
that steps 4.1.1.1 through 4.1.1.4 have L been completed. j j 4.1.1.3 Verify that the minimum staffing requirements have been met as per 4.2 below. f NOTE: Activation of the EOF should be h-accomplished within sixty (60) minutes after the emergency classification was i declared. f 4.1.1.4 Personnel assigned specific functions as per Attachment 1, or their representatives, shall complete these functions as part of their p personnel duties listed herein. O 4.2 Minimum Staffing Requirements The minimum staffing requirements for activation of the EOF are as follows: 4 1
- a. Management Representative j b. Engineering Support Representative 41 .
j c. Radiation Protection Representative i j d. Security Representative i j e. Public Information Representative - 1
; f. Communicator -
NOTE: The above indicates the position holder or qualified alternate. i The above listed station representatives must be able to assume j control of the EOF and have suitable personnel available to perform the functions delineated in 4.1.1.2 above, in order to f meet the minimum staffing requirements for activation of the EOF. Q .d i
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CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL ,g g EPP-206
? - ACTIVATION OF THE EMERGENCY OPERATIONS h,,) FACILITY (EOF) AND EOF PERSONNEL DUTIES REVISION NO. 2 PAGE 4 0F 22
{ l 4.3 Emergency Operations Facility (EOF) Personnel Duties
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j 4.3.1 Emergency Coordinator 4.3.1.1 The individuals designated to assume this position upon activation of the EOF are (in descending order of succession): 4.3.1.1.1 Manager, Nuclear Operations jt 4.3.1.1.2 Operations Support Superintendent 4.3.1.1.3 Manager, Plant Operations j 4.3.1.1.4 Engineering Superintendent j 4.3.1.1.5 Vice President, Nuclear Operations
- j. 4.3.1.2 Responsib111 ties:
]i 4.3.1.2.1 Complete Facility Activation (Section ) , 4.1). .I k.) 4.3.1.2.2 Upon arrival at the EOF co'ntact the j
! TSC Manager and conduct a turnover of l
Emergency Coordinator position and functions in accordance with EPP-109 as soon as practical, i - 1 4.3.1.2.3 Assume duties of Emergency Coordinator as per EPP-109. 4 l 4.3.1.2.4 Verify minimum staffing. I
! 4.3.2 Engineering Support Coordinator 4
1 4.3.2.1 The individuals designated to assume this I l position upon activation of the EOF are (in i descending order of succession): l 1 4.3.2.1.1 Operations Support Superintendent k ] 4.3.2.1.2 Technical Support Engineer L 4.3.2.1.3 Engineer, Technical Support,
, 4.3.2.2 Verify that EOF HVAC flow is directed through j
(i ds the High-Efficiency Particulate Air (HEPA)
- filters.
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CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL EPP-206 1 NOV -61984
, ,.a ACTIVATION OF THE EMERGENCY OPERATIONS i f.) FACILITY (EOF) AND EOF PERSONNEL DUTIES REVISION NO. 2 PAGE 5 0F 22 l'I , 4.3.2.3 Verify that operation of the exhaust fans in the j decontamination area has been initiated.
] 4.3.2.4 Verify that emergency response engineering j support personnel with EOF assignments are in j position, or have been notified and are proceed-j ing to the EOF. 1 J 4.3.2.5 Verify the operability of the Safety Parameter
! Display System (SPDS).
i 4.3.2.4 Responsibilities: .] 4.3.2.4.1 Direct and coordinate efforts to
-{ technically assess plant status and l the severity of the emergency condi-
! tions.
1 l 4.3.2.4.2 Provide back-up engineering support to { the TSC Engineering Team. t j 4.3.2.4.3 Provide any information or technical I) , data requested by TSC or EOF person-nel, j 4.3.2.4.4 Advise the Emergency Coordinator on j technical matters relating to the
; NSSS, fuel integrity, plant systems and equipment, plant electrical systems and equipment, and plant j instrumentation.
I 4.3.2.4.5 Perform an independent assessment of critical plant parameters, l .j 4.3.2.4.6 Coordinate TUGC0 requests for tech- ,
' nical assistance and support from -
vithin the Texas Utilities System or
- from outside organizations, such as l Gibbs and Hill or Westinghouse.
i 4.3.2.4.7 Verify the technical accuracy of all public information releases prior to their dissemination to the news media, r 4.3.2.4.8 Ensure that the Operational Status i Sheet EPP-204-2, is completed in a j pd timely manner and maintain a file of completed forms. 4 8 . O p ,
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EMERGENCY PLAN MANUAL NOV -61984 EPP-206 I ACTIVATION OF THE EMERGENCY OPERATIONS
, FACILITY (EOF) AND EOF PERSONNEL DUTIES REVISION NO. 2 PAGE 6 OF 22 4.3.3 EOF Engineering Team h' 4.3.3.1 The EOF Engineering Team shall be composed of four (4) members from the Operations Support Department with general knowledge in the i following areas:
4.3.3.1.1 Mechanical Engineering 4.3.3.1.2 Electrical Engineering fi j 4.3.3.1.3 Instrument and Controls Engineering g. 4.3.3.1.4 Nuclear Engineering 4.3.3.1.5 Operations 4.3.3.2 In addition to those individuals specified k above, an individual shall be assigned to the EOF Engineering Team to formulate and coordinate h e Nuclear NETWORK transmissions during an 4 emergency situation at CPSES. j IG 4.3.3.3 Responsibilities: 1 i NOTE: The responsibilities described may be j performed by individuals on the entire team. 4.3.3.3.1 Trend and evaluate current and historical plant parameters. O _ 3 4.3.3.3.2 Assess the severity of the emergency conditions. 4.3.3.3.3 Estimate time available to perform . critical actions or before crucial parameters are exceeded or vital equipment is lost. 4.3.3.3.4 Recommend corrective or preventative f actions.
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4.3.3.3.5 Provide time estimates for the performance of repair activities to 4 place vital equipment in service. I 4 O- ' 3 3 3 6 eravid 6 ck=9 asia rias ==>>are ta
;' the TSC Engineering Team and engineering support to the radiological assessment and other emergency organization groups.
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CPSES ISSUE DATE PROCEDURE N00 EMERGENCY PLAN MANUAL g ,g jgg4 EPP-206 ] 4 j gn ACTIVATION OF THE EMERGENCY OPERATIONS l V FACILITY (EOF) AND EOF PERSONNEL DUTIES REVISION NO. 2 PAGE 7 0F 22 1 [ 4.3.3.3.7 Operate the Nuclear NETWORK terminal. e 4.3.3.3.8 Formulate outgoing Nuclear NETWORK j messages and coordinate the proper distribution of incoming messages from ] the Nuclear NETWORK system. NOTE: All outgoing Nuclear NETWORK transmissions from CPSES shall require the approval of the Emergency Coordinator. j 4.3.4 Radiation Protection Coordinator 4.3.4.1 The individuals designated to assume this !.l position upon activation of the EOF are (in i descending order of succession): i j 4.3.3.1.1 Radiation Protection Engineer 1
- 4.3.3.1.2 Chemistry and Environmental Engineer i
.l h 4.3.3.2 Responsibilities:
; 4.3.3.2.1 Initiate the operation of the Constant Air Monitor.
2 4.3.3.2.2 Iaitiate the operation of the Area ! -Radiation Monitor. I 4 4.3.3.2.3 Verify that the NOSF Decontamination i . Facility drains are directed to the I holdup tank and that drain valve 1 covers are locked in place (Attachment 3). . NOTE: The key to the decontamination - facility drain valve covers is located in the NOSF Emergency Equipment Storage Room. [ 4.3.3.2.4 Direct and coordinate the activities of the Onsite Radiological Assessment Coordinator and his staff at the TSC, l and the Offsite Radiological Assess-ment Coordinator, and the Offsite Monitoring Teams Director, and their O t tr == th tor-4.3.3.2.5 Correlate, assess and predict current and anticipated release rates and onsite/offsite radiation levels. t e
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{ __ 4 1 3 CPSES . ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL EPP-206 NOV -61984 ACTIVATION OF THE EMERGENCY OPERATIONS i h FACILITY (EOF) AND EOF PERSONNEL DUTIES REVISION NO. 2 PAGE 8 0F 22 4.3.3.2.6 Review and evaluate all radiological t data to assess the onsite and offsite consequences of any releases of h radioactive materials from the plant. I-t 4.3.3.2.7 Ensure that current and forecasted
? meteorological data is obtained and
( its effects upon any radiological F releases and dose projections are determined. F ' { 4.3.3.2.8 Ensure that emergency sampling, 2 in-plant and onsite radiological 7 monitoring, radiological safety.
. bioassay, access control and decon-5 i tamination procedures are properly k implemented by the Onsite Radiological i Assessment Coordinator.
4.3.3.2.9 Ensure that appropriate records of
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p radiological monitoring and dose assessment activities are maintained. O 4.3.3.2.10 Assist in planning onsite personnel search and rescue operations if necessary 4.3.3.2.11 Coordinate the transfer of injured and non-essential personnel if radiation j or contamination hazards are involved.
. 4.3.3.2.12 Coordinate the TUGC0 onsite and radiological assessment activities
,, with those of the State and Federal ] agencies. I]
- . 4.3.3.2.13 Provide the Emergency Coordinator with radiological data to be used in formulating protective action recom-h sendations to be submitted to the counties and State.
i 4.3.3.2.14 Advise the Emergency Coordinator on ' y matters involving radiological safety. I i' 4.3.3.2.15 Send requests for support personnel, material and equipment through the Logistical Support Coordinator. Q 9 WMuute + sa ** e >=,-mun~se=* +--*samm.='*o,
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w 4 CPSES - ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL EPP-206 g ,g gg4 T L' ACTIVATION OF THE EMERGENCY OPERATIONS f (h e FACILITY (EOF) AND EOF PERSONNEL DUTIES REVISION No. 2 PAGE 9 0F 22 f I 4.3.3.2.16 Direct requests for engineering i evaluations of temporary shielding on - special tools and equipment to the Engineering Support Coordinator. 4.3.3.2.17 Provide the Public Information 5l l Coordinator accurate radiological data d for release to the public and the news fj media.
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, 4.3.3.2.18 Ensure that the Radiological Status q Sheet, Form EPP-204-3, is completed in
.} a timely manner and establish a file d for completed forms. 1
} 4.3.4 Offsite Radiological Assessment Coordinator
.i k 4.3.4.1 The primary individual designated to assume this
]j position upon activation of the EOF is a member of the Nuclear Operations or Plant Staff trained and experienced in Health Physics practices.
"g 4.3.4.2 Responsibilities:
w 4.3.4.2.1 Coordinate and direct the activities i of the EOF RMS Computer Operator. f4 q 4.3.4.2.2 Assess current and anticipated release i rates and offsite radiation levels. 4 - l 4.3.4.2.3 Correlate current and anticipated
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release rates and offsite radiation levels. d 4.3.4.2.4 Formulate projections of offsite radiation levels. 4.3.4.2.5 Obtain current and forecasted meteor-ological data and determine its effects upon any radiological releases and offsite dose projections. 4.3.4.2.6 Review and evaluate all offsite radiological monitoring data and
] offsite dose projections.
D i 4.3.4.2.7 Brief the Radiation Protection Coor-
! -r dinator of activities accordingly.
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CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL EPP-206 NOV -61984
- ACTIVATION OF THE EMERGENCY OPERATIONS FACILITY (EOF) AND EOF PERSONNEL DUTIES REVISION NO. 2 PAGE 10 0F 22 i
j 4.3.4.2.8 Ensure that appropriate records of all 5 . offsite dose assessment activities are - I maintained. I e 4.3.4.2.9 Assist the Radiation Protection Coordinator in the formulation of p recommendations for protective action measures. t . 4.3.5 Offsite Monitoring Teams Director j 4.3.5.1 The primary individual designated to assume this position upon activation of the EOF is a Chemist. 1 The designated alternate is a member of the i Nuclear Operations or Plant Staff who has received training for this emergency plan position. l 4.3.5.2 Responsibilities:
; 4.3.5.2.1 Coordinate with the OSC Supervisor and j Offsite Radiological Assessment t Coordinator to coordinate the 5
f. h deployment of the Offsite Monitoring Teams, if required, i 4.3.5.2.2 Establish offsite locations to be U monitored, choose the routes to be f used by the Offsite Monitoring Teams to reach those locations, and any [t requirements for the use of protective clothing and respiratory protection L equipment. 4.3.5.2.3 Coordinate and direct the activities 4 of the Offsite Monitoring Teams. 4.3.5.2.4 Advise the Offsite Radiological Assessment Coordinator regarding the radiological conditions encountered and the radiological monitoring data collected by the onsite and offsite radiological monitoring teams. 4.3.5.2.5 Provide the EOF Radiological Status i Recorder with information regarding l the locations of the Offsite Monitor- )' ing Teams, and the results af any dose i O
\J rate surveys and air sample; taken.
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'q ACTIVATION OF THE EMERGENCY OPERATIONS 5 if FACILITY (EOF) AND EOF PERSONNEL DUTIES REVISION No. 2 PAGE 11.0F 22 I
I
.. 4.3.6 EOF RMS Computer Operator 1
j 4.3.6.1 The primary individual designated to assume this
] position upon activation of the EOF is an Engineer 1 from the Technical Support Section.
4.3.6.2 Responsibilities: I j 4.3.6.2.1 Verify the operability of the RMS 1 computer terminal and associated
.. equipment.
l 1 4.3.6.2.2 Utilize the appropriate Emergency Plan Dose Assessment Procedures to calcu-late the projected of fsite doses ~. 4.3.6.2.3 Provide the completed dose projections 3 to the Offsite Radiological Assessment j Coordinator. t
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4.3.6.2.4 Obtain information regarding current and forecasted meteorological condi-
] h tions from the Offsite Radiological Assessment Coordinator as required.
l) 4.3.6.2.5 Provide input as required for the j timely completion of the Radiological i- Status Sheet, Form EPP-204-3. 4.3.7 Offsite Monitoring Teams Communicator
. 4.3.7.1 The Offsite Monitoring Teams Communicator position b in the EOF shall be filled by Nuclear Training Department personnel.
4.3.7.2 Responsibilities: . 4.3.7.2.1 Establish and maintain radio and/or q telephone communications with the Offsite Monitoring Teams. {? I 4.3.7.2.2 Communicate to the Offsite Monitoring Teams any information regarding those locations to be monitored, the types
; of surveys and samples to be taken at } those locations, and the potential 1 radiological hazards that may be j
l Q encountered in route to, or at, the monitoring location. I h i
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4 4 - CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL NOV -61984 EPP-206 j 4 p ACTIVATION OF THE EMERGENCY OPERATIONS G FACILITY (EOF) AND EOF PERSONNEL DUTIES REVISION NO. 2 PAGE 12 0F 22 l l 4.3.7.2.3 Record any survey and sample data reported by the Offsite Monitoring Teams and provide the completed data
] sheets to the Offsite Monitoring Teams Director.
i 4.3.8 Communications Coordinator l
- ! 4.3.8.1 The primary individual designated to assume this
]
position upon activation of the EOF is the Direc-tor, Nuclear Training. The designated alternates are Training Supervisors from the Nuclear Training Department. 4.3.8.2 Responsibilities: 4.3.8.2.1 Verify that all telephones are proper-g ly placed at their designated loca-tions. 1
, 4.3.8.2.2 Ensure operability of all EOF Commun-e W
ications.
, 4.3.8.2.3 Conduct an EOF personnel accountabil-i ity check prior to activation. Report
[ finding to Security. I d 4.3.8.2.4 Coordinate and direct the activities p of the EOF Communicators.- I 4.3.8.2.5 Ensure that communications procedures are properly.. implemented, and that f : records of incoming and outgoing communications are being properly maintained.
! 4.3.8.2.6 Ensure that communications between the 4 CPSES Emergency Organization and l
Federal, State, and local emergency il response organizations are maintained. l l J E 4.3.8.2.7 Direct requests for additional com-k munications support and equipment
- f. repair services to the Logistical f Support Coordinator.
4.3.9 EOF Communicators
, 69' j 4.3.9.1 The two (2) Communicator positions shall be filled j by Nuclear Training Department personnel.
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,'1 l 4'.3.9.2 Responsibilities:
s, 4.3.9.3.1 Log all incoming and outgoing commun-ications. 4.3.9.3.2 Conduct communications operations to provide information to emergency response organizations, as required. fl
, -! 4.3.10 Logistical Support Coordinator t
4.3.10.1 The primary individual designated to assume the position of Logistical Support Coordinator is the
,j Administrative Supervisor. The designated alter-
+ nat'e is a qualified member from the Station Administration Department.
f
$ 4.3.10.2 Responsibilities:
P 4.3.10.2.1 Direct and coordinate the activities
~ of the following personnel stationed
-r in the EOF:
- a. EOF Clerk i
- b. EOF Events Recorder h
j c. EOF Operational Status Recorder 1j - j d. EOF Radiological Status Recorder, j i 4.3.10.2.2 Coordinate, direct, and respond to requests from the CPSES Emergency 9 Organization for administrative and logistical assistance. 4.3.10.2.3 Coordinate the recall and deployment j of administrative support personnel, b ' 4.3.10.2.4 Arrange transportation and temporary f housing for support personnel as 1 needed. L 4.3.10.2.5 Coordinate the retrieval of drawings
] and documents.
1 4 4.3.10.2.6 Ensure that onsite records management support is provided in a timely
] (*} manner.
! 4.3.10.2.7 Expedite the procurement of equipment i and supplies.
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e if j CPSES ISSUE DATE PROCEDURE NO. 1_ EMERGENCY PLAN MANUAL NOV -61984 EPP-206 j-4 n ACTIVATION OF THE EMERGENCY OPERATIONS J fh FACILITY (EOF) AND EOF PERSONNEL DUTIES REVISION NO. 2 PAGE 14 0F 22 l[ 4.3.10.2.8 Interface with other Texas Utilities { facilities. 4.3.11 EOF Clerk l c i 4.3.11.1 The EOF Clerk position shall be filled by a secretary or associate office assistant from the [ g Operations Support Department. 4.3.11.2 Responsibilities: [
- ~
4.3.11.2.1 Perform clerical and administrative duties (e.g., distributing or posting information, and copying documents). f ! 4.3.11.2.2 Respond to any requests from the ! Emergency Coordinator and other j emergency organization members, i e 4.3.12 EOF Events Recorder 2 . i 4.3.12.1 The EOF Events Recorder position shall be filled-t h by an engineer from the Operations Support Depart- [ t ment. 4.3.12.2 Responsibilities: )' 4.3.12.2.1 Maintain a log of all pertinent
- . emergency response activities occur-I ring in the EOF. Using the " Response and Recovery Activities Log Sheet",
Form EPP-109-1. h 4.3.12.2.2 Interface with the EOF Communicators t and the TSC Advisor to obtain informa-tion related to the emergency situa- . tion. 1 4 4.3.12.2.3 Post information related to the emergency situation on the " Sequence of Events Board." a NOTE: The " Sequence of Events Board" should list in chronological order, only those event-type
- items related to the emergency i situation. Operational and
(} radiological data shall be posted on separate status
' boards.
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f CPSES ISSUE DATE PROCEDUREdo.
; EMERGENCY PLAN MANUAL EPP-206-1 NOV -61984 ,
s ACTIVATION OF THE EMERGESCY OPERATIONS , 9 FACILITY (EOF) AND EOF PERSONNEL DUTIES REVISION NO. 2 PAGE 15,0F 22 . 4.3.13 EOF Radiological Status Recorder 0 . 4.3.13.1 The EOF Radiological Status Recorder position in E [ the EOF shall be filled by an engineer or a f' l- technician from the Operations Support Departrent. ,
,s
' The designated alternates are personnel from the }
U TUGC0 Site Quality Assurance Department. k 0 4.3.13.2 Responsibilities: 4.3.13.2.1 Plot the current locations of the ' y 3 Onsite Survey Team (s) and the Offsita i Monitoring Teams, and post the results 6 of any samples taken.
. 4.3.13.2.2 Ensure that the Field Teams Communi- l
. cator is provided with any information
"'s regarding offsite radiological !
monitoring activities which should be l posted on the similar maps in the TSC.
. . l 4.3.13.2.3 Respond to any requests from,the
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Radiation Protection Coordinator and his staff. Q 4.3.13.2.4 Maintain the Radiological Status
. Boards located in the EOF.
5 4.3.13.2.5 . Maintain a file the Radiological Status Sheets. 4.3.13.2.6 Complete the Radiological Stcstus Sheet
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t Form EPP-204-3 and ensu're thit the > Radiation Protection Coordinator and Offsite Radiological Assessment [ Coordinator have reviewed this form , [ for accuracy. - I & 4.3.14 EOF Operational Status Recorder - 4.3.14.1 The EOF Operational Status Recorder position at the EOF shall be filled by an engineer or a
. technician from the Operations Support Department.
1 The designated alternates are personnel from the TUGC0 Site Quality Assurance Department. [ 4.3.14.2 Responsibilities: O 4.3.14.2.1 Maintain the Operational Status Boards located in the EOF. 4' r 0,T*W J T Q _~ 2 T _ _} ' j '~ ~ )
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CPSES ISSUE DATE PROCEDURE NO. j EMERGENCY PLAN MANUAL NOV -61984 EPP-206 ACTIVATION OF THE EMERGENCY OPERATIONS
.hm FACILITY (EOF) AND EOF PERSONNEL DUTIES REVISION NO. 2 PAGE 16 0F 22 1
l l 4.3.14.2.2 Complete the Operational Status Sheet, j Form EPP-204-2, and ensure that the j
. Engineering Support Coordinator has l.] reviewed this form for accuracy.
? 4.3.14.2.3 Maintain a file on the Operational fi Status Sheets. 1 ij 4.3.15 Security Supervisor 1 j 4.3.15.1 The primary individual designated to assume the j Security Supervisor position when the EOF is y activated is the Security Supervisor. The desig-4 nated alternates are Security Coordinators. 3 4.3.15.2 Prior to the activation of the EOF, the Security j Supervisor shall establish and maintain communi-y cations with the Security Shif t Supervisor and fi verify that a security officer has been dispatched p to the EOF and has established operations at tlie f t EOF. h 4.3.15.3 Responsibilities: , 4.3.15.3.1 Coordinate activities to ensure the i security of the entire plant site j within the Owner Controlled Area.
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I 4.3.15.3.2 Implement the applicable provisions of the CPSES Security Plan, y 4.3.15.3.3 Ensure measures to establish security at those activated emergency response facilities have been initiated. l 4.3.15.3.4 Assist with the assembly and account-
. ability of personnel at the designated -
plant assembly point (s). I 4.3.15.3.5 Ensure that all non-essential site personnel are evacuated and that
] unauthorized personnel cannot enter ; the site.
i j 4.3.15.3.6 Coordinate the movement and badging of all personnel entering the site. 4.3.15.3.7 Initiate personnel accountability procedures and maintain accountability i 4 4
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j CPSES ISSUE DATE PROCEDURE NO. EPP-206 }t EMERGENCY PLAN MANUAL NOV -61984 1 i p's ACTIVATION OF THE EMERGENCY OPERATIONS FACILITY (EOF) AND EOF PERSONNEL DUTIES REVISION NO. 2 PAGE 17,0F 22 1 lt for those personnel working within the Protected Area. 3 4.3.15.3.8 Coordinate search and rescue opera-tions with the OSC Supervisor.
.f I 4.3.16 Public Information Coordinator 4
1
< 4.3.16.1 The primary individual designated to assume the position of Public Information Coordinator upon activation of the EOF is the Support Services ) Superintendent. The designated alternate is the Public Information Specialist.
4 4.3.16.2 Responsibilities: f 4.3.16.2.1 Initiate and verify activation of the News Center. l4 4.3.16.2.2 Formulate and issue public information releases. () 4.4 Subsequent Actions 4.4.1 In the event of extended operations, the E0F staff may be altered as necessary by the Emergency Coordinator to maintain 24 hour operations capability. ( 1 4.4.2 Operation of the EOF shall continue until such time as the Emergency Coordinator or the Recovery Manager directs it deactivation. 5.0 References j 5.1 CPSES Emergency Plan a 5.2 EPP-109, " Duties of the Emergency Coordinator" " 1 4 5.3 EPP-115. " Release of Emergency-Related Information to the Public" c
; 5.4 EPP-116, " Emergency Repair and Damage Control" 4 5.5 EPP-121, " Recovery and Reentry" 5.6 EPP-202, " Emergency Communications" 5.7 EPP-203, " Emergency Notification" I
h'") 5.8 EPP-207, " Activation of the News Center and Personnel Duties" l I i
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! EMERGENCY PLAN MANUAL EPP-206 NOV -61984 .l ACTIVATION OF THE EMERGENCY OPERATIONS 'l ;. ,- FACILITY (EOF) AND EOF PERSONNEL DUTIES REVISION NO. 2 PAGE 18.0F 22 i 5.9 EPP-208, " Control of Site Access" d 5.10 EPP-209, " Personnel Assembly and Accountability" l
j 5.11 EPP-210. " Evacuation" 5.12 EPP-309, "Offsite Radiological Monitoring" 5.13 EPP-310. "Onsite and In-Plant Radiological Surveys" 6.0 Attachments y 6.1 Attachment 1, " EOF Checklist" 6.2 Attachment 2. " EOF Layout"
] 6.3 Attachment 3 "NOSF Decontamination Facility Drain Valve Lineup" i
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CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL g4g EPP-206
^
ACTIVATION OF THE EMERGENCY OPERATIONS r FACILITY (EOF) AND EOF PERSONNEL DUTIES REVISION NO. 2 PAGE 19 0F 22 u. ATTACHMENT 1
' PAGE 1 0F 1 EOF CHECKLIST 1
t Texas Utilities Generating Company Comanche Peak Steam Electric Station EMERGENCY OPERATIONS FACILITY OPERATIONS CHECKLIST i Page 1 of 1 verified Ites Responsibility or Complete
- 1. Check EOF layout (Attachment 2) EOF Fersonnel b 2. EOF telephones installed ECF Fereonnel (Attachment 2)
- 3. Conduct EOF persoesel Communication accountability check and report Coordinator results to Security 6
*' Verify minimum etaff requirement Esergency Coordinator
-) 4
('1)
- 1. Management
- 2. Engineering
- 3. Radiation Protection
- 4. Security
- 5. Comunications .
' 6. Public Informatien
$. Establish communicatione per EFF.203: 30F Communicator
- 6. Plant Status Report received ,
tagineettag Support Coordinator
- 7. Activate air monitor and area. Radiation Protection
' radiation monitor Coordinator
- 3. Line-up 20F IVAC to flow thru REFA tagineering Support Coordinator
- 9. Line-up Decon Facility Valves Radiation Fratection ~
and lock valve cover (Attachment 3) Coordinator
- 10. totablish control pointe 20F Radiatise (if necessary) Protection Feroonnel
- 11. Radiological Data Report received . *retection
! 12. Offette monitoring teams contacted
- ! Te t
- 13. Verify Security poste established Securit) _
- 16. 20F activated / Time toergency Coo. s C om-im ;
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f CPSES TSSUE DATE PROCEDtiRE NO. V; EMERGENCY PLAN MANUAL EPP-206 i '. .s ACTIVATION OF THE EMERGENCY OPERATIONS
/ -] FACILITY (EOF) AND EOF PERSONNEL DUTIES REVISION NO. 2 PAGE 20 0F 22 ATTACHMENT 2 g
PAGE 1 0F 2 EOF LAYOUT ilt d (Example) 4
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y ;- y z- -, _-- a CPSES TSSUE!DATE [ROCEDURENO. EMERGENCY PLAN MANUAL g g 4 g'g . EPP-206 3 ACTIVATION OF THE EMERGENCY OPERATIONS 1.1 FACILITY (EOF) AND EOF PERSONNEL DUTIES REVISION NO. 2 PAGE 21.0F 22 j ATTACHMENT 2 1 PAGE 2 0F 2 i l EOF LAYOUT a 1 4 )l DESIGNATED PERSONNEL POSITIONS 1
- 1. EMERGENCY COORDIN ATOR 14. NOTEPAD COORDINATOR
- 2. R ADI ATION PROTECTION COORDINATOR 18. EOF R ADIOLOGICAL i 3. SECURITY SUPERVISOR RECORDER STATUS j 4. LOGISTICAL SUPPORT COORDINATOR 18. EOF EVENTS RECORDER l S. COMMUNICATIONS COORDINATOR 17. EOF OPER ATION AL
- 6. ENGINEERING SUPPORT COORDINATOR * , STATUS RECORDER
] ~ T. PUBLIC INFORMATION COORDINATOR 18. EOF CLERK
- 8. OFFSITE MONITORING TE AMS DIRECTOR 18. OFFSITE MONITORING TEAMS I
S. OFFSITE RADIOLOGICAL ASSESSMENT COMMUNICATOR f COOR3tNATOR 20. SECURITY OFFICER l 10. EOF ENGINEERING TEAM ,
- 21. STATE DEPT. OF NEAkTH LIAISON
>l
.. 11. EOF COMMUNICATORS 22. EOF flMS COMPUTER OPERATOR I ();,/ 12. NRC PERSONNEL 28. NEWS RELEASE WRITER 3 13. FEMA PERSONNEL 34. TypgST 1,
d d,
- l. O PSx TELEPHONE O pbx / TRUNK LINE TELEPHONE
- 1 -
j C2 RADIO S ASE STATION t ] @ DEDICATED TELEPHONE TO TSC f $ DEDICATED TELEPHONE TO CONTROL ROOM . l O STATE AND COUNTY RINGOOWN TELEPHONE I O EMERGENCY NOTIFICATION SYSTEM TELEPHONE - I
; O HE ALTH PHYSICS NETWORM TELEPHONE SPOS
' b
) S AFETY PARAMETER DISPLAY SYSTEM COMPUTER TERMINAL O , SP SCREEN PRINTER i R ADIATION MONITORING SYSTEM COMPUTER TERMIN AL (.. O PRIVATE LsNE
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e - - - l} I CPSES ISSUE DATE PROCEDURE Nd.
} EMERGENCY PLAN MANUAL gy g jgg4 EPP-206 I. ACTIVATION OF THE EMERGENCY OPERATIONS l p) sf FACILITY (EOF) AND EOF PERSONNEL DUTIES REVISION NO. 2 PAGE 22 0F 22 1
1 J ATTACHMENT 3 PAGE 1 0F 1 NOSF DECONTAMINATION FACILITY DRAIN VALVE LINEUP NOSF e i . .L l l l l see Inset ['] Entrance HOLD UP] IO TANK j Decon I Facility I s g i
<s From NOSF Decon Area i
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Tank - NORMAL VALVE LINEUP From NOSF Decon Area
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j COMANCHE PEAK STEAM ELECTRIC STATION $ EMERGENCY PLAN MANUAL , O t i e i I ACTIVATION OF THE NEWS CENTER AND PERSONNEL DUTIES J PROCEDURE NO. EPP-207 l REVISION NO. 2 i me
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CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL EPP-207 OCT 261984 , ACTIVATION OF THE NEWS CENTER (9 a:s AND PERSONNEL DUTIES REVISION NO. 2 PAGE 2 0F 16 ( 1.0 Purpose This procedure provides instructions for the activation of the News Center in the event that the Emergency Coordinator directs its activation in response to an emergency condition at CPSES. 2.0 Appifcability This procedure shall be initiated following the declaration of a Site Area Emergency or General Emergency at CPSES. This procedure is applicable to the Public Information Coordinator, and the News Center Manager and his staff. During an emergency condition classified as a > Notification of Unusual Event or an Alert, the Public Information / Coordinator, with the concurrence of the Emergency Coordinator may direct activation of the News Center. T31s procedure becomes effective when issued. 3.0 taf1.itions 3.1 Emergency Classification - A classification system of emergency severity based on operational, radiological, and meterological Q conditions at or near the plant site. 3.2 Emergency Action Level (EAL) - Initiating conditions which provide a basis for determining the appropriate Emergency classification. 3.3 Emergency coordinator - The. designated onsite individual having the responsibility and authority for implementing the Emergency Response Plan and who will direct all site ef forts to limit the i consequences of the emergency and bring it under control. 3.4 Public Information Coordinator - The member of the CPSES Emergency Organization who is responsible for formulating all information to be released by Texas Utilities Generating Company (TUCCO) during an emergency situation at CPSES and ensuring that - information approved for release is promptly transmitted to
. Corporate offices following its release at the News Center. In the event that the Emergency Operations Facility (EOF) is activated, he will report to that facility.
3.5 News Center Manaaer - The member of the CPSES Emergency Organization responsible for activation and operation of the News Center. 3.6 Spokesman - A representative of TUCCO who shall release approved o information at the Neve Center. U (. .. - , . - . . . , -
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4 i CPSES ISSUE DATE PROCEDURE NO. I EMERCENCY PLAN MANUAL EPP-207 j 007 o n maa
~
{ n ACTIVATION OF THE NEWS CENTER Qt AND PERSONNEL DUTIES REVISION NO. 2 PAGE 3 0F 16 3.7 News Center - The News Center is the single point onsite from which information regarding an emergency condition at CPSES will , be disseminated to the public and the news media. This facility will contain equipment and supplies to support public information and rumor control activities, and will be utilized for news , conferences and special announcements. The News Center , encompasses the auditorium, display area and the public viewing room within the Nuclear Operations Support Facility (NOSF). The [ News Center auditorium is capable of recommodating 75 news media personnel. I 3.8 Alternate News Center - A facility located in the Cleburne Senior Citizens Center (301 W. Henderson Street, Cleburne, Texas). It F includes work space for 'he media as well as space for news , conferences. The Alternate News Center shall be activated if i emergency condition prevent activation or warrant evacuation of the News Center. 3.9 Alternate News Center Annex - A facility located in the Cleburne City Hall (302 W. Henderson Street, Cleburne, Texas) which provides space for the Spokesman and his staff as well as Rumor Control when the Alternate News Center is activated. The Q facility shall be equipped with telephone and telecopier links to the EOF. 3.10 Rumor Control - Two telephone lines in the NOSF are dedica,ted
- strictly for use in answering questions and dispelling rumors
, from residents in the CPSES area during an emergency situation. Rumor Control shall be activated in conjunction with the News Center. 4.0 Instructions f 4.1 News Center Personnel F l . 4.1.1 News Center Manager ( 4.1.1.1 The individuals designated to assume this g position upon activation of the News Center are (in descending order of succession): 1
; 4.1.1.1.1 Public Information Specialist 1 (TUCCo-CPSES) i 1 4.1.1.1.2 Employee Publications Editor
- (TUSI-Dallas) 4.1.1.1.3 Supervisor, Creating Services D,
(TUSI-Dallas) l L h l
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y _ . . _.- CPSES . ISSUE DATE PROCEDtiRE NO. I EMERGENCY PLAN MANUAL EPP-207 i r ACTIVATION OF THE NEWS CENTER 6 A AND PERSONNEL DUTIES
\C/ REVISION NO. 2 PAGE 4 0F 16 h 4.1.1.2 Responsibilities:
I 7 4.1.1.2.1 Contact the Security Supervisor or f Security Shif t Supervisor and verify [ that a Security officer has been dispatched to the NOSF. , 4.1.1.2.2 Direct and coordinate the activation
- of the News Center. Complete the News r
Center Activation checklist Form EPP-207-1 (Attachment 1). 4.1.1.2.3 Ensure that the News Center is prop-erly arranged as per Attachment 2, !
" News Center Layout".
4.1.1.2.4 Ensure that telephones and conupunica-tions equipment are properly placed as per Attachment 2. " News Center Layout". l 4.1.1.2.5 Notify the Public Information ! gg Coordinator of News Center activation. 4.1.1.2.6 Coordinate the issuance of public ! information releases with the l Spokesman. i 4.1.1.2.7 Arrange for and coordinate news , conferences. 4.1.1.2.8 Supervise and direct those personnel assigned to the News Center. 1 4.1.1.2.9 Ensure that news media representatives receive a copy of " Instructions to the l News Nedia" (Attachment 5), a press - kit, sign in and receive a press pass. ' 4 4.1.1.2.10 Assign News Center Aides to work i station at the NOSF front I desk. i 4.1.1.2.11 Assign two Rumor Control Aides to the Rumor Control Center. ( 4.1.1.2.12 Provide Rumor Control with copies of . the latest news releases as well as ;
; h)- approved information from local and t state officials. j 4
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p--- . CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL EPP-207 OCT 261984
,, ACTIVATION OF THE NEWS CENTER l AND PERSONNEL DUTIES REVISION NO. 2 PAGE 5 0F 16 4.1.1.2.13 Direct the activation of the Alternate
- News Center, 1f required.
, 4.1.1.2.14 Direct the deactivation of the News , l Center (s). k 4.1.1.2.15 Obtain through the Logistical Support Coordinator or other source, any additional equipment needed for,the News Center.
- 4.1.2 Spokesman 4.1.2.1 At the Unusual Event or Alert action levels, the
, Manager, Nuclear Operations is the Primary
. Spokesman. Upon activation of the EOF and the News Center, the primary individual designated <
to assume the position of Spokesman is the i Vice-President, Nuclear Operations. . His
- designated alternate is the Administrative Superintendent.
E 7 g? 4.1.2.2 The Spokesman is the official source of information at the News Center for the news media during an emergency condition for TUGCo. [ 4.1.2.3 Other duties for the spokesman are specified in Procedure EPP-115. " Release of Emergency-Related Information to the Public". 4.2 News Center Support Personnel i 4.2.1 Positions, listed below, support the activities of the
- Spokesman, Public Information Coordinator and News Center
- Manager.
i j 4.2.2 News Release Writer - The News Release Writer proposes -- i news releases using information supplied by the Public Information Coordinator. The News Release Writer will i also assist the Public Information Coordinator in other r tasks as requested. l 4.2.3 News Center Assistant - The News Center Assistant is a
- liaison between the media and the News Center Manager.
l The News Center Assistant will also assist the News Center Manager in other tasks as requested. ! ,.S 4.2.4 Plant Systess Technical Assistant - The Plant Systems i O.) Technical Assistant assists the Spokesman in understanding i details of the emergency as well as assisting the I f
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CPSES ISSUE DATE PROCEDURE NO. EMERCENCY PLAN MANUAL EPP-207 T 26 t384
..s ACTIVATION OF THE NEWS CENTER
( AND PERSONNEL DUTIES REVISION NO. 2 PAGE 6 0F 16 Spokesman during news conferences. The Plant Systems Technical Assistant may also be available after news conferences to assist the media in understanding plant systems. 4.2.5 Radiation Protection Technical Assistant - The Radiation
, Protection Technical Assistant assists the Spokesman in understanding details of the emergency as well as assist-
}
- ing the Spokesman during news conferences. The Radiation
- Protection Technical Assistant may also be available after
, news conferences to assist the media in understanding j radiation protection. i 4.2.6 News Center Aide No. 1 - News Center Aide No. 1 issues and retrieves press passes, takes and posts messages for the media and assists with the activation of the News Center. e 4.2.7 News Center Aide No. 2 - News Center Aide No. 2 takes care of media needs for such things as extra news release copies, writing materials and refreshments. News Center Aide No. 2 will also assist News Center Aide No. I as , needed and will assist with the activation of the News i (j Center. 4.2.8 Audio-Visuni Aide - The Audio Visual Aide records, normally via tape recorder, news conferences and assists with the activation of the News Center. . 4.2.9 Word Processing Aide - The Word Processing Aide handles typing and copying needs as directed by the Public Information Coordinator and News Release Writer. The Word Processing Aide will also telecopy information as directed by the Public Information Coordinator. 4.2.10 Rumor Control Aides - Using approved information, the Rumor Control Aides answer questions from the public over the rumor control lines. -- 4.3 Subsequent Actions , 4.3.1 Following activation of the News Center, the News Center Manager shall coordinate the operation of the News Center and the release of information to the news media with the Public Information Coordinator in accordance with Procedure EPP-115. " Release of Emergency-Related Information to the Public". 4.3.2 Operation of the News Center shall continue until such time that the Emergency Coordinator has deternined that news media interest in the event has diminished and
-- ~
CPSES IS3rE DATE PROCEDURE NO. EMERCENCY PLAN MANUAL EPP-207 OCT 261984 ACTIVATION OF THE NEWS CENTER i ), AND PERSONNEL DUTIES REVISION NO. 2 PACE 7 0F 16 f 8 operation of the f acility is no longer required.
, Deactivation of the News Center requires the approval of the Energency Coordinator.
e 4.3.3 Following deactivation, the News Center Manager shall ensure that the News Center is restored to its ! pre-emergency status. 4.4 Activation of the Alternate News Center and Alternate News Center Annex 4.4.1 When ordered by the Emergency Coordinator to evacuate the News Center and activate the Alternate News Center and Alternate News Center Annex. the News Center Manager and Spokesman shall call a news conference to notify the media of the evacuation order and provide them of the safest route from the News Center to the Alternate News Center. 4.4.2 The News Center Aide stationed at the NOSF front desk shall log out media members and retrieve their news media identification badges. 4.4.3 Telephones, the telecopier, " Instructions to the News () Media," News Media Registration Logs, and any other equipment and supplies needed for operation of the Alternate News Center and Alternate News Center Annex shall be transported from the News Center to those facilities. 4.4.4 The Public Information Coordinator shall notify the Cleburne City Manager or his designee and inform him of the need for those facilities. 4.4.5 The News Center Manager and his staff shall establish operations at the Alternate News Center following its activation. 4.4.6 The Spokesman and his staf f, and Rumor Control personnel shall establish operations at the Alternate News Center Annex following its activation. 5.0 References 5.1 CPSES Emergency Plan 5.2 EPP-115. " Release of Emergency-Related Information to the Public"
. 5.3 EPP-203, " Emergency Notification" kl !
~
f P' CPSES ISSCE DATE PROCEDURE N00 o EMERGENCY PLAN MANUAL OCT 26 884 EPP-207- ' 3 ACTIVATION OF THE NEWS CENTER k;) AND PERSONNEL DUTIES REVISION NO. 2 PAGE 8 0F 16 4 i ( 6.0 Attachments F 6.1 Attachment 1. " News Center Activation Checklist" Y
- 6.2 Attachment 2. " News Center Layout" r
il e 6.3 Attachment 3. " News Media Registration Log" 6.4 Attachment 4. " News Media Identification Badge" ' i e 6.5 Attachment 5 " Instructions to the News Media" l I , 1 i h l 9
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ATTACHMENT 1 PAGE 3 0F 4 NEWS CENTER ACTIVATION CHECKLIST b Texas Utilities Generating Company Comanche Peak Steam Electric Station
. NEWS CENTER ACTIVATION CHECKLIST PAGE 3 of 4 NEk'$ CENTER ACTIVATION CHECKI.IST h
Tese 1 einer Tascas 133 cassette recorder legen CAM _ Besen C10 h 6 ( _ legen CHS3$3 j _ Lower projection screen. I _ Move overhead projector free projection booth to floor area in front of stage center. Plus media feed bou in outlet below projection booth windov*. Flus backup cassette recorder into media feed box. Check operation of Microphones i Backup cassette recorder Overhead projector Frejection booth recording equipoent 4.0 Document Control Center . 1 4.1 The technical aestetante are responsible for activating thie
- area.
I 4.2 Aettvetion Remove two phonse marked "Spekseman" f ree shelf in rumor centrol eres. Flus phones into outlets 6711 and 4712 toested to right of east emit free document control center. Se sure phones are plugged in att the way and have a dial tone. spp-screte g, . . . ,
. ,_ .;.-. wa 4
I CPSE3 ISSUE DATE PROCEDURE NO. O EMERGENCY PLAN MANUAL EPP-207 ACTIVATION OF THE NEWS CENTER (,j AND PERSONNEL DUTIES REVISION NO. 2 PAGE 12 OF 16 ll [ ATTACHMENT 1 PAGE 4 0F 4 Y NEWS CENTER ACTIVATION CHECKLIST 2 h 3 j Texas Utilities Generating Company y Comanche Peak Steam Electric Station 1 NEWS CENTER ACTIVATION CHECKLIST PAof 4 of 4 4 9 NEWS CENTER ACTIVAT10N CEECKLIST 4
- 5.0 Rumor Control Area 4
1 S.1 The rumor control aides are responsible for activating this area. h 3.2 Activation Remove two phones marked " rumor control" free shelf and plug _
- into outlete 4701 and 4702. Se sure phones are plugged in all the way and have a dial tone.
3 _ Dial di and hans up to remove call forwarding. temove radio free shelf, plus in sad tune to WBAF. 820 AM. Notebooks for recording -calle are also on shelf. 5 h i News Center Manager Date t a+m
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CPSES ISSUE DATE PROCEDURE NO.
? EMERGENCY PLAN MANUAL EPP-207
. OCT 261984
[ , ACTIVATION OF THE NEWS CENTER (,] AND PERSONNEL DUTIES REVISION NO. ? PAGE 13 0F 16 ATTACHMENT 2 PAGE 1 0F 1 . NEWS CENTER LAYOUT Parking "I 4 y- ry-
; ry1 ry1 lx xl lx xl n ..u.. i. o...
e I I i Lobby = ( T Display Area S k,,,,,,,,,,,,,,,, a f
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L CPSES ISSUE DATE PROCEDURE NO. i EMERGENCY PLAN MANUAL EPP-207 OCT 261984 ACTIVATION OF THE NEWS CENTER I
> b~ AND PERSONNEL DUTIES REVISION NO. 2 PAGE 14 0F 16 l '
l 7 ATTACHMENT 3 ; i PAGE 1 0F 1 NEWS MEDIA REGISTRATION LOG Texas Utilities Generating Company l Comanche Peak Steam Electric Station I NEWS MEDIA MEQl8TMATICN LCG ! i Cate: Page: l 6 Crganisation Identification i t Name or tematicadon Iac;e Returned l Atmladen I"8" " (Yes/No) I i l i I I i i b.3 I I a
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t I i I i ! I i i l I l 1 l I i ll l l l I I e i I l 1 I i ! l I I t i l I i i n i l i i ! I I J 6 l l ' I t I ! { l l I I l l 6 i 6 6 i ) i t t IPe=207 8 . b 7 "N f 3 i 4 ,I '
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t CPSES 19 PROCEDURE No, EMERGENCY PLAN MAN 1'AI. OciUE DAU2 6 1984 EPP-207
, ACTIVATION OF THE NEWS CENTER
) AND PERSONNEL DUTIES REVISION NO. 2 PAGE 15 0F 16 4
1 ATTACHMENT 4
) PAGE 1 0F 1 f
NEWS MEDIA IDENTIFICATION BADCE (FACSIMILE) k r , ( T;{. . , f h[ .
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e p.ld.. . tCOMANCNE PEAK L 9.? STEAM ELECTRIC STATION i n ,. . , - ! g? u y,;' i o _ EPRESS h,.* t ( kPA.SS
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- i Pass No.
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r , i CPSES ISSUE DATE PROCEDURE NO. l EMERCDICY PLAN MANM. EPP-207 OCT 261984 ACTIVATION OF THE NEWS CENTER (,S j AND PERSONNEL DUTIES REVISION NO. 2 PAGE 16 0F 16 ATTACHMENT 5 PAGE 1 0F 1 . INSTRUCTIONS TO THE NEWS MEDIA t r ftIAS UTILIT!!$ SENERATING CONpANY COMANCHE PEAR STEAM (LECTRIC STATION INSTNUCTIONS TO TMt NEWS EDIA
- 1. Any unautherf aed or unescorted individual from the news media found to be outside the News Center area will be espelled from the site and denied site access for the duration of the event. .
- 2. The Company spokespersen in the leews Center is the sole source of offletal informatten en the Comenche Peak site, i
- 3. The telephones located around the periphery of the lobby display area l and public viewing roes are for everyone's use. Ploese do not utilite e telephone any longer then is necessary.
l , 4 Please dispisy your feentificatten badge at all times. Return this badge [ to the Security Guard if yev leave the News Center area. ! l. Your professional conduct and cooperetton with Comenche Peak officials l wm se espected and .pprocteted. Partime J
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s COMANCHE PEAK STEAM ELECTRIC STATION
's EMERGENCY PLAN MANUAL L) l i
i I i ACCESS CONTROL DURING EMERGENCY CONDITIONS
.) PROCEDURE NO. EPP-208 REVISION NO. 4 D ,
07 SAFETY-RELATED%;~ SUBMITTED BYI \ [#2 SUPER 1tCENDENT, SUPPORT SERVICES DATE [*/[" i
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CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL EPP-208 3 3 NOV -51984 j ACCESS CONTROL DURING h EMERGENCY CONDITIONS REVISION NO. 4 PAGE 2 0F 13 1.0 Purpose { The purpose of this procedure is to establish the criteria and responsibilities for controlling access to the CPSES site and ) onsite emergency response facilities upon activation of the CPSES l Emergency Organization.
; 2.0 Applicability l This procedure is applicable to the CPSES Security Organization
- and selected emergency response and plant management personnel during emergency conditions at CPSES.
I This procedure becomes effective when issued. i 3.0 Definitions 3.1 Emergency Classification - A classification system of emergency severity based on operational, radiological and meteorological conditions at or near the plant site. The Emergency Classifications in order of increasing severity are: O 3.1.1 Notification of Unusual Event - Unusual events are in progress or have occurred which indicate a potential degradation of the level of safety of the plant. No releases of radioactive material requiring offsite response or radiological monitoring are expected for this classification unless further degradation of , plant safety systems occur. 3.1.2 Alert - Events are in progress or have occurred which
- involve an actual or potential substantial degradation of the level of safety of the plant. It g is the lowest level of classification where near-site or offsite emergency response may be anticipated.
For most Alert events, the plant would be brought to - a safe, stable condition, and radioactive releases, if any, would be minimal. - 3.1.3 Site Area Emergency - Events are in progress or have i occurred which involve actual or likely major h failures of plant functions needed for protection of l the public. The Site Area Emergency classification j reflects conditions where some significant releases , of radioactive material are likely, or they are occurring, but where a core meltdown situation is not indicated based upon current information. Any (]. releases are not expected to exceed EPA Protective
- Action Guideline exposure levels except near the site l boundary.
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I CPSES ISSUE DATE PROCEDURE NO. l EMERGENCY PLAN MANUAL NOV -51984 EPP-208 l
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ACCESS CONTROL DURING I EMERGENCY CONDITIONS 1 k.3 REVISION NO. 4 PACE 3.OF 13 i j 3.1.4 Ceneral Emergency - Accident situations involving l I 1 actual or imminent substantial core degradation or melting'with the potential for loss of containment integrity. Releases can be reasonably expected to j exceed EPA Protective Action Guideline exposure l levels for tiore than the immediate site area. 3.2 Emergency Response Facility - Those facilities, including the Control Room, the Technical Support Center (TSC), the
! Operations Support Center (OSC), the Emergricy Operations Facility (EOF), and the News Centei, fron which emerger.cy f response activities are directed.
j .. ; . a I 3.3 Frisker - A portable cot-qt rate instrument sensitive, to low. levels of radioach.ive, con,taniertion.
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3.4 Non-Essential Personnel - Personnel falling into one of the , i following categories: 1 ' J 3.4.1 Seployees not havird mergericy organization ' assit eents. ,
.. s Q 3.4.2 Visitors, s.
j *3.4.3 Contrace' 'o r (excl2. ting security organization) and construction psOmnele a
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s 3.4.4 'IndiyJduals who are in'rolved in non-operational' , activities permit'ted yitMn'the Exclusion Area. ' ' .
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1 3.4.5' 1:quaw Creek Park patrons. . . j . N , i 3.4.6 Other persons Who may be in publit, Access arese or l passing Phrough the site or withiu .t.he owner l controlled araa. , 3.5 Onsite - The land area forming the peninsula'on which CPSES % is sited. Tha vestern boundary of this area is the westurn-most eviporation pond. - i 3.6 Protected Area - That area around the plant which is lI encompassed by physical barriers and to which access is controlled. j 3.7 Radiation Controlled Area,- Any area to M.'ich ascess is l l controlled for the purposes of radiation protection. v:
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f~ #- CPSES ISSUE DATE PROCEDURE NC. EMERGENCY PLAN MANUAL NOV -51984 EPP-208 ACCESS CONTROL DURING i Q EMERGENCY CONDITIONS REVISION NO. 4 PAGE 4 0F 13 i f 4.0 Instructions 4.1 Precautions 4.1.1 Only the Emergency Coordinator or the Security Supervisor, may authorize access to the CPSES site during an emergency condition. 4.1.2 CPSES Security shall have the authority to direct the activities of Brown and Root Security during emergency conditions in accordance with Procedure SEC-610. 4.1.3 Entry to onsite Radiation Controlled Areas shall be controlled in accordance with Radiation Protection Procedure HPA-112. " Radiation Work Control". i 4.1.4 At a Site Area Emergency or General Emergency, State and NRC emergency response teams should be expected I and provided with expedited access. l 4.1.5 Following the declaration of an Emergency h'
- Classification, the Emergency Coordinator shall notify Security of the pending arrival of any l emergency response vehicle and the location where it i should be directed.
4.2 Initial Actions / Responsibilities l 4.2.1 Control of Access during a Notification of Unusual Event or Alert 4.2.1.1 Emergency Coordinator l. 4.2.1.1.1 Ensure that the Security Shift Supervisor is notified in -
~
accordance with EPP-203, t
} " Emergency Notification".
4.2.1.1.2 Ensure that access control to the E CPSES site has been implemented. 4.2.1.1.3 Grant special access to personnel . _ . . as the emergency situation y, - dictates. i d
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j < ~ CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL EPP-208 NOV -51984 I ACCESS CONTROL DURING hi- EMERGENCY CONDITIONS REVISION NO. 4 PAGE 5 0F 13 Y A D 4.2.1.2 Security Shift Supervisor 4 l j! ' '( ' 4.2.1.2.1 Initiate response in accordance with Procedure SEC-610. " Security [ , Response During Operating Emergencies". e I a
- s 4.2.1.2.2 Initiate SEC-304, " Vehicle li Control". )
n P 4.2.1.2.3 Initiate EPP-209, " Personnel [ Assembly and Accountability", as ) i directed by the Emergency d Coordinator. H Il 4.2.1.3 Security Personnel 4.2.1.3.1 Control personnel access to CPSES g t' h site in accordance with SEC-610. l }. 4.2.1.3.2 Control vehicle access to the h li Protected Area (SEC-304). f , {* 4.2.1.3.3 Control vehicle activity in the d Protected Area (SEC-304).
- i s,' 4.2.1.3.4 Maintain accountability of all lj personnel in the Protected Area
~
(EPP-209) throughout the duration i of the emergency as directed by lj the Security Shift Supervisor. h p 4.2.2 Control of Access during a Site Area Emergency or j ' General Emergency y j 4.2.2.1 Emergency Coordinator 4.2.2.1.1 Ensure that the Security Shif t
. Supervisor is notified in j , accordance with EPP-203.
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4.2.2.1.2 Ensure that access control to the CPSES site has been implemented. ]; 4.2.2.1.3 Grant special access to personnel as the emergency situation dictates. 4.2.2.2 Security Shift Supervisor 4.2.2.2.1 Initiate SEC-610.
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Fr 1 CPSES ISSUE DATE PROCEDURE NO. f EMERGENCY PLAN MANUAL NOV -51984 EPP-208 i l ACCESS CONTROL DURING EMERGENCY CONDITIONS REVISION NO. 4 (}c) PAGE 6 0F 13 e l 4.2.2.2.2 Establish and maintain security posts at: .
, a. Squaw Creek Park
- b. Any locations deemed j necessary by the Emergency j Coordinator or Security j Supervisor.
4.2.2.3 Security Personnel
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l 4.2.2.3.1 Man security posts and access
! points.
I J 4.2.2.3.2 Grant site access in accordance 1
+
with SEC-610. 1 s 4.2.2.3.3 Prohibit all access to Squaw
?-
Creek Park except for authorized radiological monitoring teams with appropriate identification. t C:
; Me NOTE: TUCCo radiological j monitoring team vehicles will be identified by a placard stating "TUGCo CPSES Field Monitoring Team".
l 4.2.2.3.4 Prohibit access to CPSES of all
;' non-essential personnel.
NOTE: Emergency Response Personnel presenting l proper identification and j' news media presenting a -- l
, " Press Pass" shall be j' granted access. News media shall not be allowed past the NOSF ,
except as permitted by i EPP-207, " Activation of the News Center and ] i Personnel Duties". I. (C.N.
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; 4.2.2.3.5 Permit access only to emergency ; response personnel.
t
! NOTE: Personnel requiring an escort must have the , escort present in order l l to be allowed access. '
4.2.2.3.6 Control vehicle access to the j Protected Area (SEC-304). F 4.2.2.3.7 Control vehicle activity in the. Protected Area (SEC-304). 4.2.2.3.8 Maintain accountability of all
, personnel in the Protected Area j (EPP-209) throughout the duration
{ of the emergency. I l 4.2.3 Emergency Response Facility Access Control l 4.2.3.1 Responsibilities: (' ) - Responsibility for authorizing access to an emergency response facility is assigned as l follows: 4.2.3.1.1 Control Room - Shift Supervisor 4.2.3.1.2 iechnical Support Center (TSC) - TSC Manager 4.2.3.1.3 Operations Support Center (OSC) - OSC Supervisor 4.2.3.1.4 Emergency Operations Facility i (EOF) - Emergency Coordinator -- I L 4.2.3.1.5 News Center - News Center Manager. 4.2.2.3 Security Shift Supervisor 4.2.3.2.1 Upon notification of a Site Area Emergency or General Emergency, initiate actions to establish and (.?
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L. J t CPSES ISSUE DATE PROCEDURE NO. { EMERGENCY PLAN MANUAL EPP-208 NOV -51984 L ACCESS CONTROL DURING l j EMERGENCY CONDITIONS REVISION NO. 4 PAGE 8 0F 13 maintain Security posts in I accordance with Security pro- '
) cedures at the following j locations:
1 1 i 4.2.3.2.1.1 Nuclear Operations Support Facility k (NOSF)/ News Center 4.2.3.2.1.2 Emergency Operations Facility 4.2.3.2.1.3 Other facilities as deemed necessary by 1 the Emergency Coordinator or the 4.2.3.3 Security Personnel l 4.2.3.3.1 Maintain security of NOSF/ News Center.
! 4.2.3.3.2 Deny or permit personnel access d
to the E0F. h NOTE: A list of personnel authorized to enter the EOF is presented in Attachment 1, " Personnel Authorized for EOF
- . ~
Entry". [ 4.2.3.3.3 Maintain a current account-
] ability log of those personnel l present within the EOF 2
(Attachment 2, EPP-208-1). ~ 4.3 Subsequent Actions - 4.3.1 The access control measures contained in this procedure shall remain in effect until instructed otherwise by the Emergency Coordinator or the Recovery Manager. 5.0 References 5.1 CPSES Emergency Plan, Section 8.0 5.2 CPSES FSAR, Section 2.1.2, " Exclusion Area Authority and Control" i
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i CPSES ISSL'E DATE PROCEDURE NO. EMERGFECY PLAN MANUAL EPP-208 NOV -5 m
.l;, - . ACCESS CONTROL DURING (h EMERGENCY CONDITIONS REVISION NO. 4 PAGE 9 0F 13 5.3 EPP-203, " Emergency Notification" j 5.4 HPA-112, " Radiation Work Control" h
I 5.5 SEC-304, " Vehicle Control" 5.6 SEC-610. " Security Response During Operating Emergencies" 6.0 Attachments 6.1 Attachment 1, " Personnel Authorized for EOF Entry" 6.2 Attachment 2, " Emergency Response Facility Accountability Log" I. c3 i k I 1 a
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_ . . . . _ m. - 1 j CPSES ISSUE DATE PROCEDURE NO. j EMERGENCY PLAN MANUAL NOV -51984 EPP-208 i ACCESS CONTROL DURING fh EMERGENCY CONDITIONS REVISION NO. 4 PAGE 10 0F 13 i - ATTACHMENT 1 PAGE 1 0F 3 [ PERSONNEL AUTHORIZED FOR EOF ENTRY t, A . F L S ALDRICH, D.G. lFARRING'f0N,J.S. l LAMBERT'L.M. ALLDREDGE, J.J. FISHENCORD, R.E. [ _LANCASTER, B.T.
] [ SCHMITTI E. ]
[ SCOGIN, A.J. ] ( [ ALLISON, J.R. , [ FLETCHER,G.J. ] [LAUGHLIN, G.J. [ SHANTS, F.B. j [ ANZ, E.J. - [FLOYD,E. ] [ LEE, K.D. ]~ [ SILVERMAN, G.W. ' j [ ARDIZZONI, J.H. 3 [ FOX, M.H. , (LICHTY,T.E. ' [ SMITH, P.G. ] ) [ FRATUS , C. , ,LOWRIE, D.A. [ SMITH, R. A. j "] B_ [ FREEMAN,P.C. . . LUNA, J.A. ] [ SMITH, S.L. j [ BAURA, M.V. . [ LYONS , E.
] [ SPENCER, M.D.
[ BELECKIS, R.A. 2- - G [ STACHA, W.R. [ BELL, G.L. 3 [ GALLMAN , J. R. , M [ STEARNS , D. ( BISE, K.L. 3 [ GARBARINO, L.N. [ MACHO, M. I. [ STENDEBACH, W.L. B0HANNON, J.N. 3 [ GAVIN, C.W. [ MANROE, M. A.
]
i
] [ STENGAR, W. l l
BOST, R.W. 3 GARY, R.J. ' 3 (MARLOW, MAYFORTH,J.W.
! BOWLES, J.E. ) 'GOODWIN, D.A. '
R.P. " T 5 [ BRASWELL, D.W. 'GOSDIN, T.L. 3 I [ TACKETT7 P.H. [ GREEN,M.0. '
' TITUS, K.V.
- f. @ ((BRITTON, BuUDT, T.E.
P.G. 3 [ GUARINO, A. 3 3
.lMcCAMEY, McINVALE, J.B.
MEINERSHAGEN,A.V.) R.B. [TUGWELL,S.C. l ( BROCK, S.S. 3 (MILLER,K.M. l [ TURNER, C L ] BRYSON, W.D. 3 H ,MITCHELL, G.A. [ ,
. BurEu, G.T. 3 ,HAGAR, R.C.
MONTGOMERY, J.L. W
, MRDESTY, J.A.
l, MOORE, D.L. [ WEBB, B.D. 3 1l C . HARDING, K.R. ' [ MURPHY, M. A. ] [WESTBROOK,W.H.' [ [ MRRIS , N. CHEATHFIM, H.J. (WHITWELL,D.F.'
]
[ CISNEROS, R. l [ HAWKINS , R.W. " N WILKIE, G.A. jl l CLA U , R.W. ] lHEMPHILL,C.C. [ NIEMEYER, M. A. ] [WISTRAND,R.R.l j . CLEMENTS, B.R. ,HISE, W.N. [ WOOD, J.M. . l [ COFFEE. J.W. .
.HOLLINGSWORTH, W.A. P i [ COLLINGS, C.R. ] [ HOOTON, A.J. ) PALMER, M.D. , Y
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j- [ CURRY, C.D. ] [ HUNTER, J.S. ] [.' PICKETT, J.C. . [ YEAGER, L.G. ] : 3 [ CURTIS, R. ] POINTON, J.W. ] - i J l D [ JEANES , 5.L. , R i- [ DANIELS7L.E. ] [ JENKINS , R.T. ] [ REDLOW, A.H. , [ REIFF, A.T.
! DELANO, R.D. ] [ JOHNSON, C.R. l .
l; [ DIONNE, D.B. [ JONES, G.D. ] l RICE, C.M. ] [ DYAS, E.L. [ JONES , R. A. ]
- j. ](.RIGGS,M.J.
ROGERS, A.T. 3 g E K ROSE, T. ,
; EDWARDS 7 J.D. ] [KARNES,P.K. ] [ RUMSEY, J. .
i l EDWARDS, P.L. ] [ KELLOGG, B. ]
; r. (KITTELSON,D.B. ]
; % , KNOWLES W.O. ,
. KUYKENDALL, J.C.
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4 d l CPSES ISSL'E DATE PROCEDURE NO. l EMERGENCY PLAN MANUAL EPP-208 NOV -51984 ACCESS CONTROL DURING l (.) EMERGENCY CONDITIONS REVISION NO. 4 PAGE 11 0F 13 l l i ATTACHMENT 1 PAGE 2 0F 3 - I i, OTHER PERSONNEL:
! (1) NRC PERSONNEL, STATE PERSONNEL, and/or FEMA PERSONNEL presenting ; proper identification (examples shown below) shall be granted access.
(2) Persons not possessing proper identification may be allowed access if escorted by the constituents or if authorized by the Emergency Coordinator or the Security Supervisor. i [ ugsIER SERIES FOR IEllOR j I A. 258
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- ISSUE DATE PROCEDURE NO.
EMERGENCY PLAN MAWAL EPP-208 NOV -51984 1 ACCESS CONTROL DURING 4 /7T ( t .: '! EMERGENCY CONDITIONS REVISION NO. 4 PAGE 12 0F 13 ATTACHMENT 1 PAGE 3 0F 3 . t i
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RESPONSE
OBSERVER / I EVALUATOR i a OJ NO=
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l CPSES ISSUE DATE PROCEDURE 30. EMERGENCY PLAN MANUAL EPP-208 NOV -51984 ACCESS CONTROL DURING
.1
. EMERGENCY CONDITIONS REVISION NO. 4 PAGE 13 0F 13 3
I ATTACHMENT 2 l PAGE 1 0F 1 j EMERGENCY RESPONSE FACILITY ACCOUNTABILITY LOG J , J l Texas Utilities Generating Company 1 Comanche Peak Steam Electric Station i EMERGENCY RESPONSE FACILITY ACCOUNTABILITY LOG [ Control Room OSC Date: TSC EOF Page: of Name Key Card Name Key Card l Last, First, Mid. Initial Number Last, First, Mid. Initial Number j
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- D, v EMERGENCY PLAN MANUAL j .
l j a 1, J i l 1 i j PERSONNEL ASSEMBLY AND ACCOUNTABILITY PROCEDURE NO. EPP-209 ), REVISION NO 0 CPSES CONTROL
- SAFETY-RELATEDg m *
} c COPY y D CO SUBMITTED BY: ' [/t/t DATE: c7 83 RADIATION PROTECTION ENGINEER
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d APPROVED BY: ((% M MW MANAGER, PLANT OM!' RATIONS DATE: / A 7 88 4 I e 1
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7 CPSES ISSUE DATE PROCEDURE NO. l EMERGENCY' PLAN MANUAL JUL 291983 EPP-209 O '
- Q/ j PERSONNEL ASSEMBLY AND ACCOUNTABILITY REVISION NO. O PAGE 2 0F 5 1.0 Purpose This procedure provides guidelines for personnel assembly and I accountability at CPSES.
l 2.0 Applicability This procedure is applicable to CPSES personnel and visitors Squaw Creek Park personnel and patrons, Construction personnel and Security h personnel during an emergency. condition at CPSES. 3.0 Definitions 3.1 Squaw Creek Park - 470 acres of land owned by Texas Utilities, I Inc. controlled by a private organization Squaw Creek Park, Inc., < and provides the only public access to Squaw Creek Reservoir and I h the CPSES Exclusion Area. A. ~ f 3.2 Onsite - The owner controlled area, or that area surrounding the Protected Area owned by the licensee which may be controlled by the owner. 3.3 Protected Area - That area around the plant, which is encompassed
@ by physical barriers and to which access is controlled, f
c $ 3.4 Non-Essential Personnel - Personnel falling into one of the { following categories: S [ 3.4.1 Employees not having. emergency assignments. V [ 3.4.2 Visitors. t Contractor and construction personnel. y 3.4.3 l 3.4.4 Individuals who are involved in non-operational activities
}
permitted by the FSAR within the Exclusion Area. j 3.4.5 Squaw Creek Park patrons. 1 3.4.6 Other persons who may be in pub'lic access areas or passing il 1 through the site or within the owner controlled area. J ,1 4.0 Instructions M l 4.1 Precautions ' l 4 4.1.1 Individuals requiring an escort shall remain with an ] ff3' Personnel. 1 I k ? h u w; M ; 2 's; m !" 7 ~ m ~ v ~ 7 ;~ 7 T T 3 . . _
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._ 3-O l CPSES ISSUE DATE PROCEDURE NO.
] EMERGENCY PLAN MANUAL .till 2 91983 EPP-209 i
) tD d D PERSONNEL ASSEMBLY AND ACCOUNTABILITY REVISION NO. O PAGE 3 0F 5 N
s 3 4.1.2 CPSES Security shall have the authority to direct the l activities of Brown and Root Security during emergency . j . conditions in accordance with Procedure SEC-610. 4.2 Personnel Accountability 4.2.1 Personnel within the Protected Area. 4.2.1.1 When a site evacuation is ordered per Procedure EPP-210. " Evacuation", all non-essential personnel shall leave the protected area in accordance with routine egress procedures. f 4.2.1.2 Each manager of an emergency response facility, 7 located within the Protected Area, or his representative, shall provide a roster of the
- personnel in his facility to the Security Shift
- Supervisor within 30 minutes after 'the i activation of that facility.
t 4.2.1.3 Within 30 minutes, after the evacuation was !* ordered, the Security Supervisor shall provide g the Emergency Coordinator with a list of names
- s. W . of personnel unaccounted for in the Protected Area.
4.2.1.3.1 The list of names may be generated by i .using the Security Access computer or
,by the vacant positions on the ', security badge storage rack.
b 4.2.1.3.2 The list generated for the Emergency k Coordinator shall be updated until all 4 personnel have been located. l 4.2.1.4 To locate missing individuals, the Security d) Supervisor shall initiate steps such as a 3 interviewing co-workers or checking access I records to determine the last known location of 1 the individual. As required, these activities
, shall be coordinated with the OSC Supervisor.
4.2.1.5 Af ter the initial 30 minute accountability i- period, CPSES Security shall maintain continuous 1 accountability of all individuals within the 3 Protected Area throughout the duration of the emergency condition.
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. . CPSES ISSUE DATE PROCEDURE NO.
- t. EMERGENCY PLAN MANUAL JUL 291983 EPP-209 3
l O PERSONNEL ASSEM3LY AND ACCOUNTABILITY REVISION NO. O PAGE 4 Op 5 t-i 4.2.2 Personnel Accountability Outside the Protected Area 4.2.2.1 When an evacuation is ordered, personnel in the j affected area (s), unless assigned an emergency i function, shall proceed to the appropriate
. assembly area in accordance with Procedure EPP-210.
4.2.2.2 Security personnel shall check the buildings
; outside the protected area, as required, to 4
ensure that all personnel have been informed and j that personnel have evacuated.
- 4.2.2.3 Everyone is responsible for the safety of his j co-worker; therefore, an absenteeism should be j reported to Security as soon as possible.
i
- 4.2.2.4 If required, Security personnel shall initiate
- the necessary actions to locate any missing l persons. 'Any unescorted vicitors shall be i escorted to the designated assembly area. ~
i I NOTE: This shall include any individuals who (Gg f are involved in non-operational } activities permitted by the FSAR { within the Exclusion Area other than Squaw Creek Park patrons. l 4.2.2.5 Squaw Creek. Park, Inc. personnel are responsible for warning and evacuating all- patrons of Squaw ( Creek Park. TUGCo Security personnel or the ! County Sheriff chall assist SCPI personnel, as { requested. - ! 4.3 Personnel Assembly i 4.3.1 If a building evacuation is ordered, the affected area or - structure shall be evacuated. 4.3.1.1 TUCCO personnel and their visitors shall leave the affected area quickly and safely and assemble in the appropriate assembly area in accordance with Procedure EPP-210. i a. Those who may have been exposed to i radioactive or toxic materials shall inform a Radiation Protection technician immediately. l C,w i i l i - f w.-y ...,,7.~.. .n-c .~. ..: . .y . -n.n.~.- .. :~.. ,~.-~,..---,..- ,..,_ ,---,-.. n p, , , - - . . . - - s,,pwn.
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CPSES ISSUE DATE PROCEDURE NO. 4- EMERGENCY PLAN MANUAL jll! ?9'Edj EPP-209 m PERSONNEL ASSEMBLY AND ACCOUNTABILITY REVISION NO. O PAGE 5 0F 5
- b. Personnel shall remain in the assembly area until released by a Radiation Protection .
technician or the Emergency Coordinator. I i 4.3.1.2 Brown and Root and other construction and 3 contractor personnel shall evacuate affected areas or structures and assemble in the appropriate assembly area in accordance with the
,j Brown and Root Evacuation Procedure (refer to j Procedure EPP-210 Attachment 5). Personnel } shall remain in the assembly area until i released. )
J 4.3.2 If a site evacuation is ordered, all non-essential i personnel shall evacuate the site in accordance with 4 sections 4.3.1.1 and 4.3.1.2 of this procedure, as appropriate. { 4.3.3 If a release has occurred or the possibility of personnel
, ' contamination exists, Radiation Protection technicians i shall report to the designated assembly areas and j implement Procedure EPP-307, " Radiological Monitoring of
(]. j Site Evacuees", as soon as possible. j 5.0 Referencet l 1 5 5.1 CPSES FSAR Section 2.1.2.2 2 5.2 CPSES Emergency Plan Section 8.0 5.3 Procedure EPP-210. " Evacuation" i 5.4 Procedure EPP-307, "Radiologi' cal Monitoring of Site Evacuees" 6.0 Attachments j None -- s i e ( I t i w,.. ,a.-.= y-...,=*-== n,.-- ,.
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I COMANCHE PEAK STEAM ELECTRIC STATION EMERGENCY PLAN MANUAL
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1 .1 .t d EVACUATION t PROCEDURE NO. EPP-210 D
' REVISION NO. 4
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z- :" l^ CPSES I SUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL $ 1$ $ EPP-210 ,
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h EVACUATION REVISION NO. 4 PAGE 2 0F 21 s g. 1.0 Purpose This procedure provides instructions for the evacuation of personnel and visitors, from Station buildings or the CPSES site. } 2.0 Applicability This procedure affects all personnel working or visiting within the CPSES Exclusion Area Boundary. This procedure becomes effective when issued. I 3.0 Definitions u 3.1 Building Evacuation - The evacuation of specific in-plant or onsite areas or buildings due to an incident affecting those - f areas. This evacuation may not affect all personnel or areas and may be prompted by at least one of the following conditions:
< 3.1.1 Unevaluated radioactive airborne concentration in excess of 1.0 E-9 uCi/cc. ! h~) 3.1.2 Unevaluated release of toxic materials or the failure of a ; toxic material storage tank.
3.1.3 Unevaluated or unexplained dose rate in excess of 2 j mrem /hr in an uncontrolled area or 100 mrem /hr in a controlled area. 2 j 3.1.4 Surface contamination in excess of 1000 dpm/100cm in an
) uncontrolled area. ; 3.1.5 A fire requiring the attention of the fire brigade. )
l 3.1.6 Fuel handling incident or the criticality alarm sounding in either Containment or Fuel Handling Building. _ 3.1.7 Sounding of an area radiation monitor alarm. 3.1.8 Any incident that, in the opinion of the Emergency Coordinator, requires evacuation as a protective action a
- measure.
Y 3.2 Site Evacuation- The evacuation of all non-essential personnel and Squaw Creek Park visitors from the CPSES site. A site i evacuation shall be required if a Site Area Emergency or a General Emergency is declared. 3.3 Plant Evacuation Routes - Predetermined evacuation routes designated by signs or posters located throughout the plant. I i i
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] EMERGENCY PLAN MANUAL $[p { g jgg4 EPP-210
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([) EVACUATION REVISION NO. 4 PAGE 3 0F 21 l These routes should be followed if no other directions are given so that radiation exposure will be minimized. An example of an . Emergency Evacuation Route poster is given on Attachment 8. i 3.4 Visitors - Any personnel requiring an escort and whose safety and - l conduct are the responsibility of that escort. 4 l 3.5 Assembly Areas - Locations in and around the Station where
! personnel shall congregate in the event of an emergency. The l folleuing locations have been designated as assembly areas:
3.5.1 Hallway outside the Containment Personnel Hatch a 3.5.2 Radiation Controlled Area Access Point i 3.5.3 Administration Building parking lot 3.5.4 Nuclear Operations Support Facility (NOSF) parking lot 3.5.5 Plant Access Road adjacent to Brown and Root parking area 3.6 Radiation Controlled Area - Any area which is controlled for the f Q" purposes of radiation protection. Any area where an individual
. could receive a dose in excess of 2 millirem during any one-hour period.
3.7 Protected Area - That area around the plant which is encompassed by physical barriers and to which access is controlled. 3.8 Onsite - The owner controll'ed area, or that area surrounding the Protected Area owned by the licensee which may be controlled by the owner. j 3.9 Non-Essential Personnel - Personnel falling into one of the following categories: 3.9.1 Employees not having emergency organization assignments. - 3.9.2 Visitors. .
, 3.9.3 Contractor (excluding security organization) and l construction personnel.
i 3.9.4 Individuals who are involved in non-operational activities permitted by the FSAR within the Exclusion Area. 3.9.5 Squaw Creek Park patrons. l 3.9.6 Other persons who may be in public access areas or passing through the site or within the owner controlled area. _v. gy;3 .-~r ,
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P i: CPSES ISSUE DATE PROCEDURE NO. [ EMERGENCY PLAN MANUAL g}$ @ EPP-210 L EVACUATION REVISION NO. 4 PAGE 4 0F 21 4.0 Instructions f 4.1 Precautions 4.1.1 Prompt and accurate evaluation of the emergency is [ necessary to determine the need for and the type of evacuation. 4 4.1.2 Personnel in an affected area shall be alerted promptly to expedite evacuation of that area and to prevent any y unnecessary exposure to radiation, airborne contamination f or other hazards. 5 @ 4.1.3 Personnel working in the Radiation Controlled Area shall f ' exit the area observing normal exit procedures unless > directed otherwise by Radiation Protection section personnel or the Emergency Coordinator, te.l.4- Upon hearing the site evacuation announcement or alarm signal, emergency response personnel shall report to their assigned emergency response facility, unless directed [ , otherwise by the Emergency Coordinator. 4.1.5 The personnel dosimetry maintained at the Primary Access Point (Security Building) shall be relocated to an alternate access point by Security personnel if it becomes necessary to evacuate the Security Building. A suitable alternate access point will be determined according to radiological conditions, f
- 4.1.6 Personnel shall not re-enter an af facted area unless ,
i specific authorization has been given by the Emergency Coordinator or the area has been released by Radiation r Protection. [ 4.1.7 Monitoring of personnel and materials, and any required _
, decontamination, shall be conducted in accordance with j Procedure EPP-307, " Radiological Monitoring of Site Evacuees".
t 4.1.8 Prior to evacuating an area, personnel shall place their equipment in a safe condition and proceed to the nearest ] i designated assembly area (for Building Evacuation) or l leave the site (for Site Evacuation). l l 4.1.8.1 Other evacuating personnel should avoid the affected area. i l p . .. y .... ...,..- ,. eq.3 , _ g.~.-. _ . ++ *ree -e; **1
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i l 24 j CPSES ISSUE DATE PROCEDURE NO. , EMERGENCY PLAN MANUAL g gg EPP-210 l EVACUATION REVISION NO. 4 PAGE 5 0F 21 4.1.8.2 Personnel within or who have passed through the affected area shall be segregated from other - , personnel until monitored by Radiation Protection Section Personnel. ) 4.1.9 CPSES Security shall have the authority to direct the activities of Brown and Root Security during emergency conditions in accordance with Procedure SEC-610. " Security Response During Operating Emergencies." l 4.2 Initial Actions ] 1 4.2.1 The Emergency Coordinator shall: o lI 4.2.1.1 If not already initiated, initiate a Building i Evacuation should any of the conditions described in Section 3.1 exist. A Building
; Evacuation shall be initiated by means of an announcement over the plant page-party system.
NOTE: A Building Evacuation may be initiated in response to the observation of an [ ( h emergency condition by personnel in the affected area, or in response to an automatic alarm, such as an area e radiation monitor alarm or the . j criticality alarms in either containment or the Fuel Handling Building. 4.2.1.2 Initiate a Site Evacuation in the event that a , Site Area Emergency or General Emergency is ] declared. A Site Evacuation should be initiated j at the Alert emergency classification unless, in j the opinion of the Emergency Coordinator, j absolutely no potential for contamination or J exposure of personnel exists. bi 4.2.1.2.1 Perform the follouing functions prior
. to sounding the site evacuation alarm or making a site evacuation announcement:
a
- a. Determine the need for monitoring of personnel for radiological contamination.
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EMERGENCY PLAN MANUAI. EPP-210 SEP191984 9. h EVACUATION REVISION NO. 4 PAGE 6 0F 21 A 41
- b. Notify TUGC0 Security at the Central Alarm Station (CAS) by
- j means other than the plant y page-party system of the intent to
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d evacuate the site and whether T radiological monitoring of evacuees is or is not required.
$ Instruct them to implement their
[ procedures for site evacuation. a F,
- c. If personnel contamination monitoring is required, dispatch Emergency Response Monitoring
' Teams to establish a Radiological Monitoring Station at a location ; on the plant acces's road by the NOSF parking lot (reference Procedure EPP-307, " Radiological Monitoring of Site Evacuees"). )! NOTE: If radiological conditions do not permit monitoring of
(*1]:- evacuees at the selected point on the plant access 4 road, an alternate
. monitoring location should h be determined as allowed by C7 the current conditions.
f 4.2.1.2.2 If conditions permit, allow time for Security and monitoring teams to respond and establish operations bafore sounding the site evacuation (,; alarm or making a site evacuation announcement. i j 4.2.1.2.3 Make a plant-wide announcement ~
} addressing the nature of the emergency ,1 and the evacuation procedures to be I
1 followed. j a. The announcement should include
, information concerning the area to be evacuated, hazards that should be avoided, the evacuation routes to be followed, and any special instructions to be followed.
(Example announcements are given in j , U7 Attachment 7.) 1 s
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lj - CPSES ISSUE DA PROCEDURE NO. EMERGENCY PLAN MANUAL $$1I EPP-210 EVACUATION REVISION NO. 4 PAGE 7 OF 21 NOTE: Personnel should follow j established plant evacuation routes as designated by b signs and/or the Emergency Evacuation Route Posters y throughout the plant unless y; other routes are announced over the Page Party System. j
- b. Sound the appropriate evacuation j alarm tone from the control room q for one minute then repeat the 1 announcement. The three alarm
,1 4 tones used in the CPSES Page Party Alarm System are:
- 1. " Steady" tone - used in a fire 3 emergency.
o L' 2. " Pulse" tone - used for plant 1 evacuation in situations other 9 than fire or radiological q h emergencies. R 3. " Siren" cone - used in ti radiological emergencies.
- c. The evacuation announcement and the sounding of the evacuation alara j' shall be repeated 3 additional times at 5 minute intervals.
4.2.1.2.4 Advise local law enforcement agencies P of the site evacuation order and request their assistance in providing of fsite traffic control, as ._ i appropriate. 4.2.1.2.5 Coordinate with Security to ensure - notification of Squaw Creek Park. Inc. i (SCPI) personnel of the emergency f condition in accordance with Procedure EPP-203, " Emergency Notification". a l 4.2.2 Personnel responding to a Building Evacuation announcement g or alarm shall l 1 (} 4.2.2.1 Evacuate to the following areas unless otherwise directed by the Emergency Coordinator: l 3 1 D o
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4 CPSES EMERGENCY PLAN MANUAL QUff MrA3 PROCEDURE NO. EPP-210 . 4 1 ,, W EVACUATION REVISION NO. 4 PAGE 8 0F 21
- a. If the emergency condition affects only the Unit 1 Containment, assemble in the hallway
? / outside the personnel hatch (refer to 3 Attachment 1). 1 ) b. If the emergency condition affects the j Radiation Controlled Area (RCA), including the Unit 1 Containment, assemble at the RCA
. access point outside the Radiation Protection Office (refer to Attachment 2).
a c. If the emergency condition affects locations within the Protected Area, but not within . the RCA; the Administration Buildings; F and/or the Warehouses, assemble at the ! Administration Building parking lot (refer ! l to Attachment 3). I M d. If the emergency condition affects the NOSF, [ assemble at the east NOSF parking lot (refer g to Attachment 4). (Ih 4.2.2.2 Construction and contractor personnel shall assemble on the plant access road adjacent to , the Brown and Root Parking lot (refer to Attachment 3). All actions of construction and contractor personnel responding to a Building Evacuation shall be in accordance with the Brown 3 and Root Evacuation Procedure (refer to Attachment 5), unless otherwise directed by the Emergency Coordinator.
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4.2.2.3 Exit the affected area using the predesignated evacuation routes unless otherwise directed. 6 NOTE: Only the affected areas should be ~, evacuated. Unaffected personnel should > be made aware of the emergency, but should continue with their routine l duties unless assigned to emergency response duties. 4.2.2.4 Remain at your designated assembly area until released by Radiation Protection personnel or the Emergency Coordinator. 4.2.3 In the event that a Site Evacuation is ordered, TUCCO Q Security shall i i - l
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CPSES ISSUE DATE PROCEDURE NO. l EMERGENCY PLAN MANUAL SEP 191984 EPP-210
.) EVACUATION REVISION NO. 4 PAGE 9 0F 21 4.2.3.1 Notify Brown and Root Security of the intent to evacuate the site and whether personnel monitoring is or is not required.
4.2.3.2 Initiate the following actions to respond to a site evacuation in accordance with Procedure SEC-610. " Security Response During Operating Emergencies":
- a. Assist in traffic control and access control in accordance with Procedure EPP-208,
" Access Control During Emergency Conditions".
- b. Account for all personnel within the Protected Area in accordance with Procedure EPP-209, " Personnel Assembly and Accountability". l
- c. Survey IUGC0 buildings located to the south of the Protected Area to ensure evacuation of personnel (i.e. TUGC0 Administration (h) Building Administration Building, Annex, etc.).
- d. Assist in the evacuation of Squaw Creek Park, if required.
- e. Survey areas adjacent to the Protected Area and Owner Controlled Area to ensure that personnel have heard the evacuation alarm.
4.2.3.3 As directed by the Emergency Coordinator, inspect the Owner Controlled Area for any non-essential personnel remaining onsite.
~~
4.2.3.3.1 Any non-essential personnel found to be on the Company Property shall be directed to the designated assembly area for the purpose of personnel monitoring prior to being released from the site. 4.2.4 In the event that a Site Evacuation is ordered, Brown and Root Security shall: 4.2.4.1 Initiate actions in accordance with the Brown and Root Security Emergency Response Program (}} Directive (refer to Attachment 6). Actions include assisting in providing traffic control, establishing access control points, and A = b ' ' .
{^-'-~,- ,_ u_ . , f-CPSES ISSUE DATE PROCEDURE NO.
]
EMERGENCY PLAN MANUAL $[p1$1984 EPP-210 1 EVACUATION REVISION NO. 4 PAGE 10 OF 21 1 II-f surveying buildings adjacent to the Protected * { Area to ensure that personnel have evacuated. ! Specific attention should be given to the 0 evacuation of the Construction Administration Building, the Pipe Fabrication Building, e Warehouses, and other areas where personnel may have difficulty hearing the evacuation alarm. J 4.2.4.2 Notify Brown and Root Safety and instruct them to sound the Brown and Root evacuation alarm when the TUGC0 evacuation alarm or announcement is heard. 3. f 4.2.4.3 Perform other actions as requested by the TUGC0 4 Security Supervisor. h 4.2.5 In the event that a Site Evacuation is ordered Brown and Root Safety shall sound the Brown and Root evacuation , alarm after the TUCCO evacuation alarm or announcement is
- heard. When the TUGC0 alarm or announcement is heard the alarm shall be sounded immediately. The alarm consists of g 5 short blasts of the construction siren. This signal 4
) h , shall be repeated three additional times at 5 minute intervals. [ 4.2.6 In the event that a Site Evacuation is ordered and
+
radiological monitoring of evacuees is required, Emergency Response Monitoring Teams shall implement the appropriate following actions as- deemed necessary by the Emergency l Coordinator and/or the Onsite Radiological Assessment Coordinator: ). .- f 4.2.6.1 If monitoring of evacuees is not necessary, no g actions are required. 4.2.6.2 Proceed to the location on the plant access road ~
- j. by the NOSF parking lot (refer to Attachment 4) and establish a Radiological Monitoring Station f - for evacuees unless directed to an alternate
; location by the Emergency Coordinator.
-j j 4.2.6.3 Establish barriers and conduct monitoring activities as specified in Procedure EPP-307,
" Radiological Monitoring of Site Evacuees".
4.2.6.4 Evacuees who are contaminated shall be taken to the NOSF decontamination facilities and decontaminated in accordance with Procedure EPP-307. (
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CPSES ISSUE DATE PROCEDURE NO.
, EMERGENCY PLAN MANUAL $[p1$ 1984 EPP-210 I
h EVACUATION REVISION NO. 4 PAGE 110F 21 Y i 4.2.6.5 Vehicles found to be contaminated shall not be ] allowed to leave the site. Such vehicles will
- be impounded and retained for decontamination.
4 4.2.7 Personnel responding to a Site Evacuation announcement or ! } alarm shall: 1 I 4.2.7.1 Exit the Radiation Controlled Area via established evacuation routes and follow normal RCA exiting procedures, unless directed otherwise. 4.2.7.2 Exit the station via their normal access point. 4.2.7.3 Construction personnel exiting the Station shall , follow the Brown and Root Evacuation Procedure (refer to Attachment 5), unless otherwise directed by the Emergency Coordinator. . 4.2.7.4' Using personal vehicles, leave the site using I the normal two right hand lanes of the plant 0 access road as outbound lanes. l
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NOTE: DO NOT USE THE LEFT HAND LANES AS THESE LANES MUST REMAIN CLEAR FOR ANY INCOMING EMERGENCY RESPONSE VEHICLES AND j PERSONNEL. f 4.2.7.5 If contamination monitoring is required, a q Radiological Monitoring Station will be 4 established on the plant access road by the NOSF e parking lot. Evacuees will not be allowed to j proceed past this point unless cleared by j emergency response personnel. s 4.2.7.6 Follow any special instructions given by the ~ l Emergency Coordinator, Security person.el, I and/or Emergency Response Monitoring personnel. 4.2.8 Work supervisors (including TUGCO TUSI, Brown and Root, l 4 and contractors), upon hearing the evacuation alarm, should ensure that personnel in their areas have heard the alarm and are evacuating, and then immediately evacuate themselves. 1 d NOTE: This does not mean that supervisors must physically account for all personnel reporting to them. sO k ? l
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CPSES ISSUE DATE PROCEDURE NO. EMERCENCY PLAN MANUA1. EPP-210 SEP19 M
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3 ' ;.,% ) EVACUATION REVISION NO. 4 PAGE 12 OF 21 4.3 Subsequent Actions
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1 4.3.1 Personnel shall remain at their assembly areas pending
. further instructions from the Emergency Coordinator.
j - 4.3.2 Should the safety of a designated assembly area be compromised, personnel assembling at that area may be
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il directed to another assembly area. A j 5.0 References 5.1 CPSES Emergency Plan, Section 8.0 3 J 5.2 EPP-203 " Emergency Notification" A
- j. 5.3 EPP-208, " Control of Site Access" j -
5.4 EPP-209, " Personnel Assembly and Accountability" 5.5 EPP-307, " Radiological Monitoring of Evacuees"
.: , 5.6 Brown and Root Evacuation Procedure
(
} 5.7 SEC-610. " Security Response During Operating Energencies" i
j 6.0 Attachments j? 6.1 Attachment 1 Assembly Area for Personnel Working Within
! Containment
] 6.2 Attachment 2, Assembly Area for Personnel Within the Radiation l e Controlled Area., 6.3 Attachment 3. Station Assembly Areas 6.4 Attachment 4, Site Evacuation Routes and Assembly Areas __ 3 6.5 Attachment 5. Brown and Root Evacuation Procedure 6.6 Attachment 6. Brown and Root Security Emergency Response Program i Directive 6.7 Attachment 7, Evacuation Announcements 6.8 Attachment 8, Emergency Evacuation Route Poster [ E
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CPSES ISSUE DATE PROCELURE NO. EMERGENCY PLAN MANUAL SEP 191984 EPP-210
, EVACUATION REVISION NO. 4 PAGE 13 0F 21 ATTACHMENT 1
.1. PAGE 1 0F 1 - ASSEMBLY AREA FOR PERSONNEL WORKING WITHIN CONTAINMENT _ i STATION BUILDING EVACUATION e ASSEaASLY AREA POR 4 CONTANetIENT PERSO9IhEL - [ . 1. NORTH T ' HALLWAY OUTSIDE
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4 i ATTACHMENT 2 V PAGE 10F 1 4 ASSEMBLY AREA FOR PERSONNEL
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h, - _ L CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN W UAL SEP 191984 EPP-210 L1 rs EVACUATION REVISION NO. 4 PAGE 15 0F 21 cre.a. o ATTACHMENT 3 d PAGE 1 0F 1 L J a.
" STATION ASSEMBLY AREAS" U
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CPSES ISSUE DATE PROCEDURE NO. I EMERGENCY PLAN MANUAL SEP 191984 EPP-210 1 gg EVACUATION REVISION NO. 4 PAGE 16 0F 21 ., v ATTACHMENT 4 PAGE 1 0F i 1 ,t
; SITE EVACUATION ROUTES
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, EMERcENCY PLAN MANUAL $EP 191984 EPP-210 L !j g}
u EVACUATION REVISION NO. 4 PAGE 17 0F 21 ATTACHMENT 5 PAGE 1 OF 2 . V ! 6 CONSTRUCTION EVACUATION PROCEDURE I
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1.0 INTRODUCTION
g .0 EVA AT,e >c - ENGINEERING USE ONLY 3.0 EVACUATION ) p
} A.0 TYPES OF EVACUATION ,
j A.1 PLANT STRUCTURE EVACUATION ( A.2 $1TE EVACUATION 5.0 PERSONNEL NOTIFICATION . !
- I j
1.0 INTRODUCTION
'f l i The purpose of this procedure is to provida direction for the lj evacuation of the plata structures or the site as conditions !
- j. , warrant. This procedure is applicable to a1Q construction.
engineering, administrative, and subcontracted personnel ! regardless of compen, af filiation. . 2.0 EVACUATION $1CNAL $ The evacuation signal vill be a series of five (5) short blasts of the plant siren. ] 3.0 EVACUAtt0N When the evacuation signal is given, all persor.nel shall evacuate sthe plant ette, in a safe manner as follove All esplayees shall stop work. Any employees using flammable ] , I e gas or argon shall sut off the ses at the closest source. l ; Employees will not attempt to locate personal belongings or i j turn in tools, but shall evacuate at once. ; g O I-
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, PRCCEDi;RE EFFECTIVE BROWN & ROOT. INC. NUMSER REVISION CPSES DATE PAGE JCB 35-1195 CP-CPM 1.1 1
9/26/83 2 of 2 I l i Personnel site who entered the site in a vehicle shall exit the in a vehicle. l l All others shall exit on foot. ! Personnel, including visitors, shall exit . gate through which they entered the projec& through
- t. and shall the brass-out or sign-out as normally required when leaving the project. i 4.0 TTP05 0F EVACUATION '
i Evacuation vill be of two types, depending on conditionst I. 1. l Plant structures, including feb shape and administrative buildings, f
- 2. Site, including all parking lots.
j k In either case, the same evacuation signal vill be sounded. Personnel stil be provided additional direction at their point { of exit. Fay attention to security personnel and/or barricades 4 and signs. i i
- 4.1 PLANT STRUCTURE EVACUATION i Evacuate as discussed in paragraph 3.0.
Personnel will be directed to assemble on the access road near Security Post fl or en alternate . area as directed by secondary personnel. this area until the all clear signal is given. Personnel vill remain in The all clear signal ; will be a blast of the plant siren. .After the all clear signal, personnel may return to their work statione. i 6.2 SITE EVACUATION ( Evacuate as discussed in Paragraph 3.0. Personnel vill be directed to the parking lot and shall leave the site immediately. e Barricades any be set up along the access road for peracterfbi-monitoring. l Pay attention to the barricades and watch out for your co-workers. \ t 3.0 PgRSONMEt, WTtFICATION Upon hearing the evacuation alars, supervisory personnel shall ensure ! that personnel have heard the alarm and are evacua ,' performed by physical surveillance of the areas or;1pg. This may by phone. be Personnel a accountability is not the supervisors' responatbility. 1 1 !
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CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN N W. $[P 191984 EPP-210 l r' ' EVACUATION REVISION NO. 4 PAGE 19 0F 21 0 ATTACHMENT 6 PAGE 1 OF 1
- CGulICE FEAK STRAM ELECTRIC STATTUN
' BROWN AND ROOT SECURITT EMERGUCT RESPONSE FFMRAM DIRECTIVE DECDtBER 1,1943 This procedure outlinea general responsibilities, duties, and authorities c - of the Brown and Root Security Organisation during emergencies at the CPSES 3 site.
- 1. The responsibility and authority for maintaining security of the CPSES site during seersency conditions rest with the TUCCo Security Super-
- visor. The TUGCo Security Supervisor has the authority to direct the activies of the Brown and Root Security Organisation during emergency condi 4
- 2. Emergency conditions affecting Unit 2 construction or construction perseenel (i.e., construction accidents, chemical spills, security threats) that are detected by or reported to Brown and Root Security
. . personnel shall be immediately reported to the TUGCo ca-duty Operations Shif t Supervisor.
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- 3. The TUCCo Security Supervisor, or his representative, will notify the Brova and Root Security Manager and inform him that an emergency has '
been declared by the TUCCo Emergency Coordinator.
- 4. The Brown and Root Security Manager, or his senior repreeestative, shall establish and maintain coMcations with TUCCo Security at the Secondary Alara Station (SAS).
- 5. Brows and Root Security personnel assignments shall be as directed by the TUCCo Security Supervisor.
AFFROVID BT: . ##w- <#rf/ D. C. Frankum Brown and Root Project Manager l t CONCURRED ST J Rumsey b f/ Security Supervisor s
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CPSES . ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL SEP191984 EPP-210 EVACUATION REVISION NO. 4 PAGE 20.0F 21 ATTACHMENT 7 PAGE 1 0F 1 - EVACUATION ANNOUNCEMENTS I. BUILDING EVACUATION ANNOUNCEMENT: ATTENTION ALL PERSONNEL IN EVACUATE THE AREA BY WAY OF ASSEMBLE AT 1- Describe the building or area to be evacuated. i ! 2- State directions for evacuation. If applicable, describe areas
- that should be avoided due to hazards such as fire, smoke, steam, I wreckage, radiation, etc.
i l 3- State assembly location (s). Provide instructions concerning evacuation procedure. If normal egress procedures are to be followed, so state. 9 II. SITE EVACUATION ANNOUNCEMENT: ATTENTION ALL STATION PERSONNEL. A SITE EVACUATION HAS BEEN ORDERED. EVACUATE THE SITE FOLLOWING f -
, ALL EMERGENCY RESPONSE PERSONNEL SHALL REPORT TO THEIR ASSIGNED EMERGENCY RESPONSE FACILITY, 1- Describe the evacuation procedure to be followed. If applicable, describe evacuation routes and areas that should be avoided. If
, normal egress procedures are to be followed, so state.
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EMERGENCY PLAN MANUAL M OS W EPP-300 Q~ MANUAL CALCULATION OF RELEASE RATES REVISION NO. 2 PAGE 2 0F 75 i [r 1.0 Purpose f The purpose of this procedure is to provide the guidance and j instructions for manually estimating airborne radioactivity release
& rate and total curie release values under emergency conditions at the
{ Comanche Peak Steam Electric Station.- 2.0 Applicability ! 2.1 This procedure shall be utilized when the General Atomic RM-21 computer is inoperable during the following emergency action [( levels: Alert, Site Area Emergency, and General Emergency. 2.2 The estimated release rate and total release values calculated in f accordance with this procedure shall be used in conjunction with l l Procedures EPP-302, " Manual Assessment of Radiological
- I Conditions" and EPP-304, " Protective Action Guides," as a basis i for determining what offsite protective actions should be recommended to state and local officials.
^
P l 2.3 This procedure will be implemented by CPSES emergency response 1 ! personnel in the following manner: O 2.3.1 Prior to manning the Technical Support Center (TSC), the Shift Technical Advisor, who is trained in this procedure. l
. shall perform these calculations.
{ I 2.3.2 After the TSC is manned, but prior to the activation of the Emergency Operations Facility (EOF), the Onsite Radiological Assessment Coordinator shall implement this [l. procedure. b - H 2.3.3 Upon activation of the EOF, the Offsite Radiological Assessment Coordinator or the Radiation Protection j Coordinator shall implement this procedure. 2.4 This procedure becomes effective when issued. - i
) 3.0 Definitions -
j 3.1 Absorption Factor
) That fraction of a radionuclide that is estimated to escape from
,i a particular removal system. a t O i i m memn,=y= r -
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CPSES ISSUE DATE PROCEDURE NO. j l EMERGENCY PLAN MANUAL M 09 M EPP-300 I= h MANUAL CALCULATION OF RELEASE RATES REVISION NO. 2 PAGE 3 0.F 75 i 3 3.2 Building Removal Rate j ., [ The rate at which air is removed from a particular building by [ ventjlationprocesses. Usually expressed in terms of see or . hrs . Attachment 19 contains several tables which list the l building removal rates under different operating conditions. 3.3 Containment Spray Removal Rate The rate at which iodine is removed from the containment atmosphere as a result of reacting with NaOH in thag ontainment spray. A containment spray removal rate of 9.6 hrs shall be used for projecting radioactive release rates. I- 3.4 Cooling Time. f . )' The amount of time (in days) elapsed between the time of last power operation and the time that the release occurred._ Cooling ,. time is utilized to correct the fission product inventory in the i damaged core for decay. The cooling time may also be the amount of time which has elapsed from the time the latest sample , analysis results were completed and the time that the release Q occurred. [ 3.5 Decay Factor That factor by which a quantity of radioactive material is j reduced as a result of radioactive decay. Th9 radioactive decay factor is usually expresse& in units of hours I 3.6 Effective Age , i j The amount of i:'ine elapsed from the instant reactor core power i generation is terminated until the dose is received from the l released mixture. For the purpose of .this procedure consider the f effective age to consist of two time components: (1) effective age at the time of the release onset and (2) the transit eine -
! from the point of release to the arrival at the key receptor i location (s). The ef fective age is usually expressed in units of l hours.
I j- 3.7 Effective Cleanup Factor r That factor by which a quantity of radioactive material is I reduced as a result of having experienced several effective cleanup half-lives. This factor is determined using the number of elapsed effective half-lives and Attachment 16. Ih i i i p. t i
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CPSES ISSUE DATE PROCEDURE E0. EMERGENCY PLAN MANUAL JAN 091985 EPP-300
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U MANUAL CALCULATION OF RELEASE RATES REVISION NO. 2 PAGE 4 0F 75 i 3.8 Effective Cleanup Half-Life The time it takes to reduce a quantity of radioactive material by one-half as a result of the combined influence of several j factors. These factors may include radioactive decay, building
- exhaust flow rates, containment spray removal and others. The
[ effective cleanup half-life is usually expressed in units of i hours. i 3.9 Emergency Conditions l Situations occurring which cause or may threaten to cause j radiological hazards affecting the health and safety of onsite I personnel or the general public, or which may result in damage to property. 3.10 Filter Cleanup Factor The factor by which a quantity of radioactive material is reduced , as a result of passage through a filter bank. This value is l conservatively estimated to be 1.0 and 0.05 for noble gases and iodines respectively. [ O 3.11 Cap Activity The amount of activity of a radionuclide present in the volume between the fuel pellets and the fuel cladding. 3.12 Cap Release Fraction - That fraction of radioactive material which is estimated to be l released from the gap as a result of a breach in the fuel
- cladding. This value is conservatively estimated to be 1.0 and l 0.25 for noble gases and iodines respectively.
3.13 Half-Life That amount of time it takes for a quantity of radioactive material to be reduced by one-half'. The half-life is usually expressed in units of hours. l 3.14 Liquid Release Fraction I ! That fraction of radioactive material which is estimated to escape from the liquid after its introduction into the liquid. This value is conservatively estimated to te 1.0 for noble gases. For iodines this value is dependent upon the emergency conditions l D present. __.v._ . ._ _ _ . . . _ _ . , _ . . _ _ . . _ . . . . _ .. .. _ _ _ . ,- .
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4 CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL M 09 W EPP-300 () MANUAL CALCULATION OF RELEASE RATES REVISION NO. 2 PAGE 5 0F 75 3.15 Melt Release Fraction That fraction of radioactive material which is estimated to be released from the fuel as a result of fuel damage (melting).
- 1 This value is conservatively estimated to be 1.0 and 0.25 for jl noble gases and iodines respectively.
-1 3.16 Partition Factor 'i i i The ratio of the quantity of a nuclide in the gas phase to the total quantity in both the liquid and gas phases when the liquid j and gas are at equilibrium. 3.17 Projected Dose 4 That dose of ionizing radiation that is likely to be received by
- a population group if no protective actions are implemented.
3.18 Release Rate The average quantity of radioactive material released to the
. environment from a nuclear power reactor during normal operations i and anticipated operational occurrences. The release rate is 4 ~' usually expressed in units of Ci/sec.
- i 3.19 Source Term
, The calculated average quantity of radioactive material released to the environment from a nuclear power reactor during normal operation including anticipated operational occurences. The source term is the isotopic distribution of radioactive materials used in evaluating the impact of radioactive releases on the i environment. The source term is usually expressed in units of curies (Ci).
- 3.20 Water Scrubbing Factor
. The factor by which a quantity of radioactive material is reduced
- . as a result of it passing through a quantity of water. This value is conservatively estimated to be 1.0 for noble gases and for iodines the value must be determined based upon the existing emergency conditions.
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- CPSES ZSSUE DATE PROCEDURE N0 0 EMERGENCY PLAN MANUAL JAN 091985 EPP-300 1
(h MANUAL CALCULATION OF RELEASE RATES REVISION NO. 2 PAGE 6 0F 75 1 4.0 Instructions 4.1 Precautions
! 4.1.1 The primary method of determining release rate and j integrated release values for use in projecting offsite j doses shall utilize the General Atomic RM-21 computer as per EPP-301, " Computer Assessment of Radiological j Conditions". This procedure serves only as a backup j method in the event the RM-21 computer is inoperable for I any reason.
1 i 4.2 Initial Actions ! 4.2.1 Obtain the dose assessment kit from the Control Room, l Technical Support Center, or the Emergency Operations Facility. This kit contains the following materials: { 4.2.1.1 A base map covering a ten mile radius (plume
- exposure pathway EPZ) from the reactor building.
- j. (Not in the Control Room) 1 -
j
^ (7) 4.2.1.2 A set of seven overlays; one for each of the seven Pasquill atmospheric stability classes.
i These overlays are used for estimating the ! affected areas downwind from the release point. (Not in the Control Room) i 4.2.1.3 An overlay.of concentric circles around the
- reactor building for prediction of the plume movement outward from the building. (Not in the
- , Control Room) i l 4.2.1.4 A set of manual of fsite dose calculation j worksheets.
5 t 4.2.1.5 A set of manual release rate and integrated - release worksheets. i 4.2.1.6 A TI-59 programmable calculator / printer with a j magnetic card library containing the programs L used to project the release rates and source terms. ,f 4.2.2 Obtain the necessary physical plant data and complete the appropriate attachments found at the end of this , procedure. The emergency situation will determine which {} attachments need to be completed. If there are any questions about which calculations should be performed the Onsite or Offsite Radiological Assessment Coordinator should be consulted. 1 P
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4 EMERGENCY PLAN MANUAL _ggg gg gent EPP-300 .4 q)' MANUAL CALCULATION OF RELEASE RATES REVISION NO. 2 PAGE 7 0F 75 I oj 4.2.3 Upon completion of the release rate and integrated release J calculations, the resulting values shall be utilized to . project offsite doses in accordance with the requirements q* of EPP-302, " Manual Assessment of Radiological Conditions". These dose projections will then be compared - to the Protective Action Guides contained in EPP-304, p " Protective Action Guides" for the formulation of l protective action recommendations. 4.2.4 The following instructions provide the general guidelines which should be followed in order to compute the release rate and total release data to be used in determining j which level of protective actions to implement. 1 , 4.2.4.1 Attachments 1 through 20 found at the end of \ l this procedure are used to estimate, record and report the source term, release rate and total li release data in the event of an emergency situation at CPSES. l I 4.2.4.1.1 Attachment 1, " Operating Instructions i for the TI-59 Calculator / Printer" l j I () ~ contains the general operating instructions which need to be followed
} in order to perform these ' calculations. Instructions on how to l perform specific release rate I '
calculations are found in Attachments 3, 5, 7, 9, 11, 13 and 15. 4.2.4.1.2 Attachment 2. Form EPP-300-1, " Plant i Stack Release Rate Calculations" is 1 used to determine stack Felease rates under any condition. Because of the common ventilation plenum releases of radioactive material which occur in the safeguards buildings, auxiliary - building, fuel handling building or j - containment should be detected by the
; stack monitors. These calculations i should be used to perform release rate i
calculations for all types of
; emergency situations except for steam generator tube rupture accidents.
4.2.4.1.3 Attachment 3. " Instructions for i Performing Plant Stack Release Rate Calculations" provides the necessary
' U'S instructions for performing plant stack release rate calculations and completing Form EPP-300-1. , I
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l I h'S CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL #N es M EPP-300 h MANUAL CALCULATION OF RELEASE RATES REVISION NO. 2 PAGE 8 0F 75 f 4.2.4.1.4 Attachment 4, Form EPP-300-2,
" Containment Release Rate - ! Calculations" is used to estimate k radioactive releases from the containment buildings. Normally any
, . activity released from the containment [ will be detected by the stack gas f monitors. This form will be used in situations where the accident is in the containment and we wish to know y the release rate from containment.
- This attachment is used only when the
, containment ventilation or purge is in operation during or after the accident situation. ) 4.2.4.1.5 Attachment 5. " Instructions for . Performing Containment Release Rate l Calculations" provides the necessary instructions for performing t containment release rate calculations j and completing Form EPP-300-2. 4.2.4.1.6 Attachment 6. Form EPP-300-3, " Fuel t f Assembly / Core Source Tera l Calculations" is used in the event of
- a fuel handling accident, loss of coolant accident, or other accident where the major portion of activity comes from fuel damage. The available activity estimated by these calculations is used in Attscheent 12 to determine the release rate from the I plant.
I 4.2.4.1.7 Attachment 7. " Instructions for
! Performing Fuel Assembly / Core Source i Terms Calculations" provides the , necessary instructions for performing fuel assembly / core source term 7
t calculations and completing Fora l EPP-300-3. I f i t t . j 1'
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i f- CPSES ISSUE DATE PROCEDURE NO. t EMERGENCY PLAN MANUAI. JM 09125 EeP-300 h MANUAL CALCULATION OF RELEASE RATES REVISION NO. 2 PAGE 9 0F 75 1 4.2.4.1.8 Attachment 8. Form EPP-300-4, " Gaseous A-Tank Source Term Calculations" is used - f in the event of a tank rupture, such as a volume control tank (VCT) rupture. The release mechanism results from situations where noncondensible gases constitute the principle material released. If a liquid is present in the container which fails, conditions are assumed to be such that the liquid does not ;
; vaporize significantly, although it .
may give up dissolved gases due to depressurization. The available
; activity estimated by these i ! calculations is used in Attachment 12 to determine the release rate from the k' - plant.
t j 4.2.4.1.9 Attachment 9. " Instructions for ; 4 Performing Gaseous Tank Source Tera k ' Calculations" provides the necessary . Q instructions for performing gaseous tank source term calculations and completing Fora EPP-300-4 . ([ 4.2.4.1.10 Attachment 10. Form EPP-300-5, "Stesa ( ! ( Accident Source Term Calculations" is ( used in the event of a steam release r or a hot liquid which flashes to vapor : l as it is released. Examples of this a type of release are: steam line break, . j sus 11 loss of coolant without fuel l damage (if fuel is damaged. Attachment
- i 6 should be used), blowdown through a relief valve, feedwater line break, letdown line failure, etc. The available activity estimated by these j -
calculations is used in Attachment 12 to determine the release rate from the i plant. 4.2.4.1.11 Attachment 11. " Instructions for . Performing Steam Accident Source Term Calculations" provides the necessary l instructions for performing staan accident source term calculations and (} completing Form EPP-300-5. i i I
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i CPSES ISSUE DATE PROCEDURE NO. 1[ EMERGENCY PLAN MANUAL gg gg gg EPP-300 3 i hJ MANUAL CALCULATION OF RELEASE RATES REVISION NO. 2 PACE 10.0F 75 9 t f 4.2.4.1.12 Attachment 12, Form EPP-300-6, " Plant h Release Rate Calculations" is used to - I estimate initial and subsequent plant , release rates and total activity released during a particular time k f rame based on the source terms { estimated in Attachments 6, 8 and 10. y The results of these calculations are f used to estimate exposures to members j of the general public for j' implementation of the appropriate j protective actions. 3 4.2.4.1.13 Attachment 13. " Instructions for
. Performing Plant Release Rate Calculations" provides the necessary J instructions for performing plant release rate calculations and completing Form EPP-300-6.
( 4.2.4.1.14 Attachment 14, Form EPP-300-7, " Steam Generator Tube Rupture Release Rate C). Calculations" is used to estimate release rates which may occur as a g result of a primary to secondary leak j and/or tube rupture. The results of i these calculations are used to project { thyroid and whole body exposures to 3 the general population to be used in , the formulation of protective action 1 recommendations. I i .. ) 4.2.4.1.15 Attachment 15. " Instructions for ! Performing Steam Generator Tube l Rupture Release Rate Calculations"
; provides the necessary instructions for perforains steam generator tube i rupture release rate calculations and j completing Form EPP-300-7.
) l 4.2.4.1.16 Attachment 16. " Radioactivity Decay i Factor vs Number of Elapsed Half-Lives" is used to correct the amount of radioactivity available for
- release for radioactive decay and f cleanup from the time the activity is I measured or available for release and the time it is released.
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CPSES ISSt'E DATE PROCEDURE NO. h EMERGENCY Pl.AN MANUAL JAN Og tong EPP-300 e [h MANUAL CALCULATION OT RELEASE RATES REVISION NO. 2 PAGE 11 0F 75 4.2.4.1.17 Attachment 17. " Ratio of Total Noble [ Cas to Kr-85 and Xe-133 vs Effective - Age" is used to estimate the amount of u noble gas activity from the amount of i 1 Kr-85 and Xe-133 activity present. f 4.2.4.1.18 Attachment 18. " Building and Tank j Volumes" contains a listing of building and tank volumes which may be } needed under emergency conditions. 4.2.4.1.19 Attachment 19. " Building Exhaust Removal Rates" contains the equations and values to be used when estimating
, the plant release rates as a result of t an accident at CPSES. The building ! exhaust removal rates generated from
- this attachment estimate the release rate of radioactivity from the
; different buildings under various conditions.
fh { 4.2.4.1.20 Attachment 20. " Design Basis Accident Data" contains the default release rate values to be used to project offsite doses when information cannot he obtained from the Digital Radiation Monitoring System or from chemistry sample analysis. 4.2.4.2 Source Term Data There are three sources of radiological i information which can be used to perfore these calculations. These sources are the Digital
. Radiation Monitoring System (DRMS). Design Basis Accident (DBA) data and in-plant sample -
4 analysis. I 4.2.4.2.1 The Digital Radiation Monitoring System provides the most l up-to-the-minute data available for source term calculations. This systen monitors activities in the process and effluent streams and provides this j information as requested to control
. room personnel. The information
] obtained from this system should be
- l Q' used when performing release rate calculations whenever possible. For I
i 4
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_. y.-v c.- CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL .AAM 881g EPP-300 1 J) MANUAL CALCULATION OF RELEASE RATES REVISION NO. 2 PAGE 12.0F 75 i; .
! example, when computing stack release j rates the data from PvG-084 and -085 -
i would yield the best estimate of activity released per unit time. ' i 4.2.4.2.2 Attachment 20, " Design Basis Accident i Data" contains information developed by the assumptions and parameters
; found in Chapter 15 of the CPSES Final J Safety Analysis Report when performing j design basis accident calculations.
This information should be utilised to project offsite doses only as a last
, resort because of its conservative
[ nature. This data should be used when the DRMS and in plant sample analyses can not provide the data necessary or can not provide the necessary data in the time required. This information was obtained from the computer 4 analyses performed by Gibbs and Hill i for six different accident scenarios. Q Care must be taken when using this data to ensure that the data taken from this attachment is taken from an accident scenario which is similar to
- the accident in progress.
l . 4.2.4.2.3.In-plant sample analysis data would 6 yield more accurate estimates than DBA I data but the length of time needed to acquire the, sample results may not allow this data to be used. Generally speaking this information should be , used to aske comparison calculations l to compare with DBA data calculatione. , This information would be obtained -- from the Chemistry and Environmental Section at CPSES.
- 4.3 Subseeuent Actions h 4.3.1 These calculations should be performed at the same frequency as offsite dose projections unless it is determined that the plant releases have been terminated, f 4.3.2 These calculations should be updated if any of the following conditions occurt i
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) CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL EPP-300 JAN 091M5 t i [) MANUAL CALCULATION OF RE1. EASE RATES REVISION NO. 2 PAGE 13 .0F 75 4.3.2.1 There is reason to believe that release rates { have increased by more than 25 percent; - j 4.3.2.2 Prior to any planned releases; and 4.3.2.3 There is any reason to believe that a new source of activity has developed since the onset of the emergency condition or previous release calculations. [ 4.3.3 All persons performing release rate and integrated release
- calculations should keep the Offsite Radiological
! Assessment Coordinator and the Radiation Protection 4 Coordinator informed as to the status of all release rate [ and integrated release results. (
- 5.0 References
! 5.1 Procedure No. EPP-302 " Manual Assessment of Radiological Conditions" 5.2 Procedure No. EPP-304, " Protective Action Guides" O 5.3 CPSES Final Safety Analysis Report 5.4 Radiological Health Handbook . 6.0 Attachments . 6.1 Attachment 1. " Operating Instructions for the TI-59 l l Calculator / Printer" 6.2 Attachment 2. Fora EPP-300-1, " Plant Stack Release Rate l Calculations" 6.3* Attachment 3 " Instructions for Performing Plant Stack Release , Rate Calculations" - 6.4 Attachment 4. Fora EPP-300-2, " Containment Release Rate - Calculations" 6.5 Attachment 5, " Instructions for Performing Containment Release Rate Calculations" 6.6 Attachment 6. Form EPP-300-3, " Fuel Assembly / Core Source Term Calculations"
,i.g, 6.7 Attachment 7. " Instructions for Performing Fuel Assembly / Core Source Term Calculations" 4
g 6.8 Attachment 8. Form EPP-300-4, " Caseous Tank Source Ters ! ) Calculations" 1 < l s a y * * *
~-
t i CPSES ISSUE DATE PROCEDURE No. l EMERGENCY PLAN MANUAL g, _ EPP-300 j . . . . . . . - - - . B f 1 () MANUAL CALCULATION OF RELEASE RATES REVISION NO. 2 PAGE 14,OF 75 h { 6.9 Attachment 9. " Instructions for Performing Gaseous Tank Source r Term Calculations" - 6.10 Attachment 10 Form EPP-300-5, " Steam Accident Source Term Calculations" t 6.11 Attachment 11. " Instructions for Performing Steam Accident Source j Term Calculations" 6.12 Attachment 12. Form EPP-300-6, " Plant Release Rate Calculations" b i
- 6.13 Attachment 13. " Instructions for Performing Plant Release Rate Calculations" l
C 6.14 Attachment 14. Form EPP-300-7 " Steam Generator Tube Rupture d Release Rate Calculations" *
- 6.15 Attachment 15. " Instructions for Performing Steam Generator Tube Rupture Release Rate Calculations" 6.16 Attachment 16, " Radioactivity Decay Factor vs Number of Elapsed Half-lives" O 6.17 Attachment 17. " Ratio of Total Noble Gas to Kr-85 and Xe-133 vs
- Effective Age" 6.18 Attachment 18. " Building and Tank Volumes" k
6.19 Attachment 19. " Building Exhaust Flow Rates" l 6.20 Attachment 20, " Design Basis Accident Release Rate Data" 0 i i . t 5 i l0 ) ?
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CpSES ISSUE DATE PROCEDURE No. j EMERGENCY PLAN MANUAL M 09 W EPP-300 l fh t MANUAL CALCULATION OF RELEASE RATES REVISION NO. 2 PACE 15 0F 75 ATTACHMENT 1 PACE 1 0F 1 - OPERATING INSTRUCTIONS FOR THE TI-59 CALCULATOR / PRINTER
- A. After obtaining the calculator / printer from its storage location, plug it into a 120 volt AC power supply. The calculator / printer can not be
{ operated using the calculator battery pack. E B Turn on both the calculator and the printer. The printer on-off switch is located on the right hand side of the printer. A sero f should be displayed on the calculator and the red light on the printer will be lit when the power is turned on. C. Select the appropriate magnetic card from the black vinyl card file. D. Enter the program into the calculator by inserting Side 1 of the card into the reader slot found on the top right hand side of the esiculator. A good feed is indicated by the number 1 being displayed on the calculator. Press the CLR button and repeat for Side 2. The number 2 will be dispisyed after a good feed. A flashing 1 or 2 , indicates a poor feed and that side must be re-entered. To do so just h press CLR and insert that side into the reader slot. CAUTION: THE CALCULATOR DISPLAY MUST HAVE A ZERO IN IT IN ORDER FOR THE MAGNETIC CARDS TO BE READ. E. To initiate the program, press the RST and R/S keys. The first prompt will appear on the strip chart recorder. F. Information can now be inputted by entering the appropriate values as
- prompted by the program. . Enter the value and press R/S for inputting l data. The value will be printed and the next prompt will appear on the strip chart. Be sure to check all values entered prior to pressing R/S. If a wrong value is printed out, press RST and then R/S
- to reset the program and then start entering data from the beginning j as prompted by the strip chart. -
( L C. When performing calculations using the TI-59 programs be sure that the calculator / printer remains on at all times. If the power should be cut off, the programs must be reinitiated and the data re-entered. 4 i t k, I l
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CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL. EPP-300 JM 091985 MANUAL CALCULATION OF RELEASE RATES REVISION NO. 2 PAGE 16 0F 75
,l
] ../ ATTACHMENT 2 PAGE 1 0F 1 I Texas utstles Generating Company l Comanche Peak Steam Electric Station ji PLANT STACK RELEASE RATE CALCULATICNS 4
>=en 1 as t
- 4. Generet teforsettee
]
- Calculaeice me.: Deae Time:
Aff*sted Unit (1 er 21 seester m edeva Dates Times Radielesteal Seerse Terms Digital Radiaties Mealtarias 3retse j Seeple Analysee Analyst Sisestures Dates Times .] S. Deter =8-=ttee of f rack Flow tatee Stash as Dare Monitor FTC-osAs et/see i TJ er Destga Tlev late (Attaat. 19)e ee/see i 1 aak se DEMI Mositer r?C-Oels ee/see er
/ Deelen Fisw sate (Attack. 19)e ee/see C. Release f e rv ,
j Radise=t W Creep Salesee Total Aetivity I late teleased (C1/tet) (Cil 1 - Setle Casee j !
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j CPSES IS UE D PROCEDURE NO. ) EMERCENCY PLAN MANUAL $$ , , EPP-300 i h MANUAL CALCULATION OF RELEASE RATES REVISION N0. 2 PACE 17 0F 75 I f ATTACHMENT 3 j PACE 1 0F 5 - 3 . INSTRUCTIONS FOR PERFORMING PLANT STACK RELEASE RATE CALCULATIONS i ! I. Instructions for Coasletina Fora EPP-300-1. " Plant Stack Release Rate j Calculations l' ! A. General Inforestion l Calculation No.: A.1 Date A.1 Times A.1 L t Affected Unit (1 or 2): A.2 Reactor Shutdown Date A.3 Time : A.3 l l Radiological Source Term: A.4.1 Digital Radiation Monitoring System i j A.4.2 Sample Analyses 4 l Analyst Signature: A.5 Date A5 Time: A.5 0' A.0 This section of Fora EPP-300-1 addresses the general inforestion' requirements for these calculations. 4 ( A.1 The calculation number is required to identify each separate l calculation so as to avoid confusion when referring to the results. l The numbering format should. start with 001 and be proceeded by ,4 either TSC or E0F to signify where the calculation was performed
- (e.g. 50F-001 or TSC-001). The date and time when these calculations were performed should also be entered into the
( appropriate spaces. ! A.2 Enter the appropriate reactor unit involved (e.g. 1 or 2). ) A.3 Enter the date and time that the reactor was shutdown if it has 1-been shutdown. A.4 Identify the radiological source term used to determine the release ! rates or total releases. I i A.4.1 If the source term was obtained from the Digital Radiation-Monitoring System monitor, check this space. 1 i A.4.2 If the source ters was obtained from in-plant sample l analysis, check this space. i i . t
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l l-CPSES ISSUE DATE PROCEDt,a NO. EMEACENCY PLAN MANUAL _sans gg gggg EPP-300 ) l )' O, t. MANUAL CALCULATION OF RELEASE RATES REVISION NO. 2 PAGE 18,0F 75 ATTACHMENT 3 F PACE 2 0F 5
- h .
A.5 The analyst who performs the calculations should sign the form and a enter the date and time in the appropriate spaces. During an Alert [ Condition, the form will normally be reviewed by the Onsite i Radiological Assessment Coordinator. During Site Area or General J emergencies this form will normally be reviewed by the Offsite Radiological Assessment Coordinator or the Radiation Protection j Coordinator. l i B. Determination of Stack Flow Rates H ' Stack As DRMS Monitor FVG-084: 5.1 cc/see or Design Flow Rate (Attach. 19): 5.2 cc/see i ) l Q> Stack 3: i DRMS Monitor PVC-085: 5.1 cc/sec or Design Flow Rate (Attach. 19): 3.2 cc/see i 5.0 This section of Fora EPP-300-1 addresses the determination of the stack exhaust flow rate. The flow rate can be determined by using 4 information obtained from the Digital Radiation Monitoring Systen gr, estimated by determining the number of ventilation fans operating at any particular time. The DRMS information should be - used if at all possible because it will yield more accurate results. The second method should be used as a backup method. B.1 Enter the plant vent stack flow rate as indicated by the wide range gas monitors in these spaces. This information is obtained from the RM-11 consoles located in the control room. The operation of f the RM-11 will normally be the responsibility of operations 1 personnel in accordance with the requirements of plant procedure [ 507-706, "DRMS Operations". I h f N
g - z CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL .lAN gg 1Wtg EPP-300 (fj) MANUAL CALCULATION OF RELEASE RATES REVISION NO. 2 PAGE 19 0F 75 1
} ATTACHMENT 3 j PAGE 3 0F 5 .
B.2 Enter the plant vent stack flow as indicated in Section 3 of j Attachment 19 in these spaces. The stack flow rate is based upon
?.
the design capacity flow rate of each primary plant ventilation fan and the number of fans operating at a particular time. C. Release Summary
?
1 Radionuclide Release Total Activity i Group Rate Released l (Ci/sec) (Ci) 1 0 roble Gases C.1 C.2 4 l I-131 C.1 C.2
; C.0 This section of Form EPP-300-1 addresses the suusarization of the stack release rate calculations,
{ j j (7) A C.1 Enter the noble gas and I-131 stack release rates as measured in
- C1/sec in these spaces.
C.2 Enter the total noble gas and 1-131 activity released as measured in Ci in these spaces. II. Instructions for Using the TI-59 Stack Release Rate Calculation Prograa
, A. Obtain the magnetic card marked " STACK RELEASE" from the black vinyl TI-59 card file and enter the program into the calculator in accordance 3
with the instructions found in Attachment 1 of this procedure. 4 l B. In order to perform the analysis provided by this program several inputs j must-be made when prompted by the calculator / printer. These prompts, i i inputs and Jtatements are described in the following paragraphs, i [ B.1 STK A FL RATE 7 This prompt asks for the stack A flow rate in cc/sec. This value can be obtained from Section B of Form a EPP-300-1. I l B.2 STK B FL RATE? This prompt asks for the stack B flow rate in f ec/sec. This value can be obtained from Section B of Form ( EPP-300-1.
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'CPSES ISSUE DATE PROCEDURE NO.
)' EMERGENCY PLAN MANUAL JAN 09 W EPP-300 j 1
' 3 s.;y MANUAL CALCULATION OF RELEASE RATES REVISION NO. 2 PAGE 20.0F ,75 4
ATTACHMENT 3 l PAGE 4 0F 5
- 1 j B.3 STK A NG CONC? This prompt asks for the stack A noble gas j concentration in uCi/cc. This value may be obtained from the DRMS l . Operator if the system is operating or it may be obtained from the i Chemistry Supervisor if sample analyses were performed to determine the concentration.
, B.4 STK A I CONC 7 This prompt asks for the stack A iodine L concentration in uCi/cc. This value may be obtained from the DRMS Operator if the system is operating or it may be obtained from the j Chemistry Supervisor if sample analyses were performed to determine q the concentration.
l B.5 STK B NG CONC? This prompt asks for the stack B noble gas concentration in uCi/ce. This value may be obtained from the DRMS Operator if the system is operating or it may be obtained from the fi Chemistry Supervisor if sample analyses were performed to determine the concentration. W i j B.6 STK B I CONC 7 This prompt asks for the stack B iodine t 'D, concentration in uCi/cc. This value may be obtained from the DRHS Operator if the stack monitor is operating or it may be obtained jl from the Chemistry Supervisor if sample analyses were performed to determine the concentration. I B.7 ELAP. TIME 7 This prompt asks for the estimated release duration in ) hours. The elapsed time may be estimated using the length of time
) the stack monitor (s) recorded above normal stack concentrations or j the. length of time it will take to terminate the release.
f . j B.8 NBL G RELS RATE = This statement provides the noble gas release 1 rate in Ci/sec from CPSES. This value should be entered into j Section C of Form EPP-300-1.
.i l B.9 I-131 RELS RATE = This statement provides the iodine-131 release "
rate in Ci/sec from CPSES. This value should be entered into Section C of Form EPP-300-1. -
! B.10 TOT NBL G RELSL = This statement provides the total noble gas I released from CPSES in C1 as a result of the emergency situatien.
This value should be entered into Section C of Form EPP-300-1. B.11 TOT I-131 RELSE = This statement provides the total iodine-131 released from CPSES in Ci as a result of the emergency situation. This value should be entered into Section C of Form EPP-300-1.
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w 1 A CPSES ISSUE DATE Pit 0CEDURE NO. 1 EMERGENCY PLAN MANUAL EPP-300 's JAN 091985 9 fn I dN MANUAL CALCULATION OF RELEASE RATES REVISION NO. 2 PAGE 21 0F 75
- l t
.l ,
r , - ATTACHMENT 3 PAGE 5 0F 5 3'i de '- C. The TI-59 strip chart printout should be attached to Form EPP-300-1 in
;l the space provided when the calculations have been completed. The Q , figure below shows what the printout should look like.
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L CPSES ISSUE DATE PROCEDURE NO. l EMERGENCY PLAN MANUAL JM 09 25 EPP-300 q MANUAL CALCULATION OF RELEASE RATES REVISION NO. 2 PAGE 22 0F 75 ATTACHMENT 4 PAGE 1 0F 1 . k Texas Utmties Generating Company Comanche Peak Steam Bectric Station
- g CONTAINMENT RELEASE RATE CALCULATIONS I 1
pues 1 er 1
! A. General Taformation
~ , Calculation Be.: Date: Time Affected Unit (1 er 2): Reactor Shatdows Date Times Radiological Source Ters: Digital Radiation Monitoring Sreten Sample Analysee Analyst's Signatures Dece: Time 'e
- 3. talease Summary Radienmelide salasse Total Activity
(- Group Rate , (ct/sec) taleased (ci) [ 5e61e cases Iodiae = 131 t t i mm ) i ) i
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,1 CPSES ISSUE DATE PROCEDURE NO.
EMERGENCY PLAN MANUAL JM 091985 EPP-300 h MANUAL CALCULATION OF RELEASE RATES REVISION NO. 2 PAGE 23 0F 75 l ATTACHMENT 5 PAGE 1 0F 4 . INSTRUCTIONS FOR PERFORMING CONTAINMENT l RELEASE RATE CALCULATIONS -4 j I. Instructions for Completing Form EPP-300-2, " Containment Release Rate j Calculations N A. General Information j Calculation No.: A.1 Date: A.1 Time: A.1 Affected Unit (1 or 2): A.2 Reactor Shutdown Date: A.3 Time: A.3 i , Radiological Source Tenn: A.4.1 Digital Radiation Monitoring System A.4.2 Sample Analyses Analyst Signature: A.5 Date: A.5 Time: A.5 A.0 This section of Fonn EPP-300-2 addresses the general information requirements for these calculations. j A.1 The calculation number is required to identify each separate 4 calculation so as to avoid confusion when referring to the results. The numbering format should. start with 001 and be preceeded by either TSC or EOF to signify where the calculation was performed f: (e.g. EOF-001 or TSC-001). The date and time when these j calculations were performed should also be entered into the p appropriate spaces. H A.2 Enter the appropriate reactor unit involved (e.g.1 or 2). ? 3 A.3 Enter the date and time that the reactor was shutdown if it has - f been shutdown. j . p A.4 Identify the radiological source term used to determine the release { rates or total releases. ' h F A.4.1 If the source term was obtained from the Digital Radiation Monitoring System monitor, check this space. I A.4.2 If the source term was obtained from in-plant sample ' analysis, check this space.
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'b CPSES ISSUE DATE PROCEDURE NO.
EMERGENCY PLAN MANUAL EPP-300 s 9 JAN 09125 (-) MANUAL CALCULATION OF RELEASE RATES REVISION NO. 2 PAGE 24 OF 75 ATTACHMENT 5 PAGE 2 0F 4 . j A.5 The analyst who performs the calculations should sign the form and j enter the date and time in the appropriate spaces. During an Alert
} Condition, the form will normally be reviewed by the Onsite J Radiological Assessment Coordinator. During Site Area or General ! Emergencies this form will normally be reviewed by the Offsite ] Radiological Assessment Coordinator or the Radiation Protection Coordinator. , B. Release Summary 4 Radionuclide Release Total Activity J Group Rate Released j (Ci/sec) (Ci) l Noble Gases B.1 B.2 l
Iodine - 131 B.1 B.2 i B.O This section of Form EPP-300-2 addresses the summarization of the j containment release rate calculations. 1
) B.1 The noble gas and iodine - 131 containment release rates in Ci/see should be entered in these spaces.
3 B.2 The total noble gas and iodine - 131 activity released from 1 containment in Ci should be entered into these spaces. 3 II. Instructions for Using the TI-59 fontainment Release Rate Calculation Program 3 A. Obtain the magnetic card marked " CONTAINMENT RELEASE" from the black vinyl TI-59 card file and enter the program into the calculator in
- 1 accordance with the instructions found in Attachment 1 of this -
d procedure. 3 B. In order to perform the analysis provided by this program several inputs jj must be made when prompted by the calculator / printer. These prompts, inputs and statements are described in the following paragraphs. B.1 NO. FANS, VENT? A This prompt asks for the number of containment veniltation fans which are operating to be entered into memory ]; storage location A. This information should be obtainable from ] Operations personnel. ]O$ l a j 1 T y '"7r W W T ..- -q C _ qs y .p.{]yy 'gE.*;5;7:K;K"'
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E4 t d Ll CPSES ISSUE DATE PROCEDURE NO. 1 EMERGENCY PLAN MANUAL M 09 E EPP-300 h MANUAL CALCULATION OF RELEASE RATES REVISION NO. 2 PAGE 25 0F 75 1 l ATTACHMENT 3 lj PAGE 3 0F 4 - q B.2 NO. FANS, H PUR7 B This prompt asks for the number of containment
; hydrogen purge fans which are operating to be entered into memory 1 storage location B. This information should be obtainable from j Operations personnel.
1 B.3 NG ACT? C This prompt asks for the containment air noble gas
- concentration in uCi/cc to be entered into memory storage location
] C. This value can be obtained from the DRMS Operator if the ] containment air monitor and RM-11s are operating or the Chemistry ] Supervisor if the concentration is determined using chemistry j sample analysis, l' B.4 I ACT? D This prompt asks for the containment air iodine q
- j. concentration in uCi/cc to be entered into memory storage location 1- D. This value can be obtained from the DRMS Operator if the l containment air monitor and RM-lls are operating or the Chemistry j Supervisor if the concentration is determined using chemistry j sample analysis.
" { B.5 REL DUR? E - This prompt asks for the release duration in hours to be entered into memory storage location E. The release duration
; may be an actual measured length of time or it may be an estimate 1 of the time the release is expected to last. ,
d B.6 NG REL RT = This statement provides the noble gas release rate from I? containment in Ci/sec. This value should be entered into Section B of Form EPP-300-2. B.7 I REL RT = This statement provides the iodine release rate from containment in Ci/sec. This value should be entered into Section B of Form EPP-300-2. B.8. NG ACT REL = This statement provides the total quantity of noble gas released from containment in Ci over the release period. This - p value should be entered into Section B of Form EPP-300-2. L' B.9 I ACT REL = This statement provides the total quantity of iodine released from containment in Ci over the release period. This
) value should be entered into Section B of Form EPP-300-2.
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r,. j CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL JAN 091985 EPP-300
., O. . , MANUAL CALCULATION OF RELEASE RATES REVISION NO. 2 PAGE 26 OF 75 3
l 1 l ATTACHMENT 5 i 4 PAGE 4 0F 4 . i
; C. The TI-59 strip chart printout should be attached to Form EPP-300-2 in d the space provided when the calculations have been completed. The
- 9. figure below shows what the printout should look like.
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]o . EMERGENCY PLAN MANUAL g y yggg EPP-300 MANUAL CALCULATION OF RELEASE RATES REVISION NO. 2 PAGE 27 0F 75 ". Q l .:.)
ATTACHMENT 6 j PAGE 1 0F 1
)
3 Texas UtlBties Generating Company L Comanche Peak Steam Eactric Station l J FUEL ASSEMBLY / CORE SOURCE 1 TERM CALCULAT10NS - ij pues l es 1 A. General taformation j ' Calculeties Be.s Dete: Timea
] '
Affected Unit (1 er 2) Baector Shutdows Date: Times Analyst's Signature Date: Time: ( J j *
- 3. Sourte Teru Sa m ry .
t
- 1. Type of fuel Demenes e
! Tsetope Ave 11able Activit? (C1)
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- CPSES ISSUE DATE PROCEDURE NO.
EMERGENCY PLAN MANUAL JM 09 M5 EPP-300 MANUAL CALCULATION OF RELEASE RATES REVISION NO. 2 PAGE 28 0F 75 h ATTACHMENT 7 L PAGE 1 0F 5 - k n INSTRUCTIONS FOR PERFORMING FUEL ASSEMBLY / CORE SOURCE TERM CALCULATIONS I. Instructions for Completing Form EPP-300-3, " Fuel Assembiv/ Core Source Term Calculations U A. General Information Calculation No.: A.1 Date: A.1 Time: A.1 [ Affected Unit (1 or 2): A.2 Reactor Shutdown Date: A.3 Time: A.3 ?
- r Analyst Signature
- A.4 Date: A.4 Time: A.4 5
, A.0 This section of Form EPP-300-3 addresses the general information
[ requirements. I 's
^
A.1 The calculation number is required to identify each separate I calculation so as to avoid confusion when referring to the results. I The numbering format should start with 001 and be preceeded by { either TSC or EOF to signify where the calculation was performed g (e.g. EOF-001 or TSC-001). The date and time the calculations were performed should also be entered into the appropriate spaces. e A.2 Enter the appropriate reacto'r unit involved (e.g.1 or 2). ; t A.3 Enter the date and time the reactor was shut down. i A.4 The analyst who performs these calculations should sign the form [ and enter the date and time in the appropriate spaces. During an ! Alert condition, the form will normally be reviewed by the Onsite Radiological Assessment Coordinator. During Site Area or General - emergencies this form will normally be reviewed by the Offsite Radiological Assessment Coordinator or the Radiation Protection < Coordinator. ! l l.} 6 j ! l l
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._ -_e CPSES ISSUE DATE PROCEDURE NO.
jl EMERGENCY PLAN MANUAL JAN 09 25 EPP-300 1 1 h MANUAL CALCULATION OF RELEASE RATES REVISION NO. 2 PAGE 29 0F 75 0 ATTACHMENT 7 PAGE 2 0F 5 . i j B. Source Term Summary 1 4 1. Type of Fuel Damage: B.1 ) Isotope Available Activity (Ci) l , Xe-133 B.2 Kr-85 B.2 I-131 B.2 B.O This section of Form EPP-300-3 addresses the summarization of the fuel assembly / core source term calculations. ? [ B.1 The type of fuel damage which is suspected to have occured should (:
@ be entered into this space. There are basically two types of damage which may occur. The first is fuel cladding damage which*
} results in the release of gap activity from the fuel rod. The ^ second is fuel pellet melting which results in the release of activity from the core fuel itself. Based upon existing plant conditions the Engineering teama should be able to determine if any fuel assembly / core damage has occurred or is imminent. - f B.2 The projected activities of Xe-133, Kr-85 and I-131 in Ci should be
} entered into the appropriate spaces. These values will be used in the calculations performed in Attachment 12 to determine the plant
[
; release rates.
i l II. Instructions for Using the TI-59 Fuel Assembly / Core Source Term Calculation
; Program -
I' A. Obtain the magnetic cards marked " FUEL ASSEMBLY" from the black vinyl TI-59 card file and enter the program into the calculator in accordance with the instructions found in Attachment 1 of this procedure. l NOTE: This program utilizes two magnetic cards to perform these calculations. Be sure that both cards are used in the proper I order when performing these calculations. B. In order to perform the analysis provided by this program several inputs
;3 must be made when prompted by the calculator / printer. These prompts, inputs and statements are described in the following paragraphs.
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_ .- I CPSES ISSUE DATE PROCEDURE NO. I
]3 EMERGENCY PLAN MANUAL ,gy g g g EPP-300 8
x 1 MANUAL CALCULATION OF RELEASE RATES REVISION NO. 2 PAGE 30 0F 75 1
,! ATTACHMENT 7 j PAGE 3 0F 5 .
j B.1 COOL TIME? A This prompt asks for the cooling time in days to be 3 entered into memory storage location A. The cooling time is the l1 interval (days) between the time of last power operation and the time that the damage occurred. Cooling time is utilized to correct the fission product inventory in the damaged core for decay. For a
; bundle which has been out of the core three months, TC = 90 days.
j For a LOCA during operation, TC = 0 days. l B.2 NO. T 1/2 - This statement provides the number of elapsed half-lives between the time the reactor was shutdown and the fuel damage occurred. These values are used to determine the decay factors found in Attachment 16 and entered in step B.3 below. B.2.1 XE133 = This statement provides the number of elapsed i,_ half-lives that the Xe-133 has undergone. 3 l B.2.2 KR85 = This statement provides the number of elapsed half-lives that the Kr-85 has undergone. 4 () - B.2.3 1131 = This statement provides the number of elapsed half-lives that the I-131 has undergone. L B.3 DECAY FAC ATT 16 - This statement introduces the next section j within the program calculations. The three prompts which follow i this heading ask for the decay correction factors from Attachment
} 16. The decay factors are determined in the following manner. The
( number of half-lives is located on the X-axis and then a vertical line is drawn which intersects the curve. From this point of
,. intersection a horizontal line is drawn to the Y-axis. The decay ; factor is this point of intersection. Enter this value in the j appropriate memory location.
i B.3.1 XE133 FAC7 B This prompt asks for the Xe-133 decay factor '.
, to be entered into memory storage location B. - )
B.3.2 KR85 FAC7 C This prompt asks for the Kr-85 decay factor to be entered into memory storage location C. B.3.3 1131 FAC7 D This prompt asks for the I-131 decay factor to 1 be entered into memory storage location D. 1 l O, i g
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CPSES ISSUE DATE PROCEDURE E0. EMERGENCY PLAN MANUAL M 09 E EPP-300 MANUAL CALCULATION OF RELEASE RATES REVISION No. 2 PAGE 31,OF 75 'I ATTACHMENT 7 PAGE 4 0F 5 - , B.4 % POW 30D? E This prompt asks for the average reactor power over d the last 30 days of reactor operation to be placed in memory 1 storage location E. Enter the average reactor. (not bundle) power j i over the last 30 days of reactor operation. For example, if a bundle is damaged and, during its last 30 days of operation, the 3 reactor operated at 100% power 75% of the time and 50% power 25% of 1 the time, the average power (expressed as a fraction of rated j power) is: 1 (1.00) (0.75) + (0.50 (0.25) = 0.875 4 B.5 READ CARD 2 This command' directs the radiological assessment team j to program the calculator with the second magnetic card to continue j with the calculations. $ B.6 NO. DAM RODS? A' This prompt asks for an estimate of the number of l damaged fuel rods to be entered into memory storage location A'. 4 The number of damaged fuel rods (suffering either clad rupture or j '
. , pellet melting) must be estimated. For reference purposes, each assembly consists of 264 fuel rods, and the core as a whole contains 50,952 fuel rods (193 assemblies).
~ '
j t l B.7 GAP 0, MELT 1 B' This prompt asks what kind of activity is being I released. If the fuel damage consists of a loss of fuel cladding integrity only then zero (0) should be entered into memory storage
- location B' because the activity which would be released would be
! activity from the gap found between the fuel pellets and the fuel cladding. If the fuel damage consists of . fuel pellet melting then one (1) should be entered .into memory storage location B' because the activity which would be release would come from the fuel
- itself.
B.8 MELT REL or GAP REL This statement indicates what type of release ', is projected to take place and what type of calculations are being - 1 performed. The statements which follow this statement provide the available activity as a result of the accident situation. These values are used in Attachment 12 to estimate the plant release
; rate.
1 s B.8.1 XE133 ACT = This statement provides the Xe-133 activity in
- Ci which is available for release from the plant. This value should be entered into Section B of Form EPP-300-3.
i B.8.2 KR85 ACT = This statement provides the Kr-85 activity in Ci i which is available for release from the plant. The value
~' should be entered into Section 3 of Form EPP-300-3.
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CPSES ISSUE DATE PROCED','RE NO. EMERGENCY PLAN MANUAL g EPP-300
.o kl' MANUAL CALCULATION OF RELEASE RATES REVISION NO. 2 PAGE 32 0F 75
{ 1 ATTACHMENT 3
. PAGE 5 0F 5 -
B.8.3 1131 ACT = This statement provides I-131 activity in Ci
. which is available for release from the plant. This value should be entered into Section B of Form EPP-300-3.
.; C. The TI-59 strip chart printout should be attached to Form EPP-300-3 in the space provided when the calculations have been completed. The figure below shows what the printout should look like. 1 2 I P.JCCDDQTIME? LR.E._. -l,;~J
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, CPSES ISSUE DATE PROCEDURE NO.
! EMERGENCY PLAN MANUAL EPP-300 1
RN 09 MS b
,4 i
i MANUAL CALCULATION OF RELEASE RATES REVISION NO. 2 PAGE 33 0F 75
- ) (b
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j ATTACHMENT 8
] PAGE 1 0F 1 i
j1 Texas Utsties Generating Company
- j Comanche Peak Steam Electric Station
-3 GASEOUS TANK SOURCE TERM CALCULATIONS I - poemt se 1
- \
4 A. General taformation a - Calculation Een Tates Time Tank Idescificatisas
- j Sample Analysia Ligeid Date: Time
$ Ces Date Tins I
j Balasse Dates Times Analyst's $1sastures Date Times 1
- i
$ 3. Seurte Tere 5 maarv Isotese Avetlable Activity (C1)
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t '[ CPSES IpSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL JAN 09 25 EPP-300 (.) MANUAL CALCULATION OF RELEASE RATES REVISION NO. 2 PAGE 34 0F 75 l I ATTACHMENT 9
, PAGE 1 0F 5 -
t INSTRUCTIONS FOR PERFORMING GASEOUS
- j. TANK SOURCE TERM CALCULATIONS
^
1 I. Instructions for Completing Form EPP-300-4, " Gaseous Tank Source Term i Calculations" } j I A. General Information i 1 Calcula' tion No.: A.1 Date: A.1 Time: A.1 1 Tank Identification: A.2 1 j Sample Analysis: Liquid Date: A.3 Time: A.3 1 Gas Date: A.3 Time: A.3 i Release Date: A.4 Time: A.4 i j i {} Analyst Signature: A.5 Date: A.5 Time: A.5 i A.0 This section of Form EPP-300-4 addresses the general information j requirements for these calculations. A.1 The calculation number is required to identify each separate calculation so as to avoid confusion when referring to the results. . The numbering format should start with 001 and be preceeded by ) , either TSC or EOF to signify where the calculation was performed I (e.g. EOF-001 or TSC-001) . The date and time the calculations were
! performed should also be entered into the appropriate spaces.
A.2 Enter the identification of the tank involved in the event. A.3 Enter the date and time of the last known liquid and gas analyses which were performed on the contents of this tank. This - information is needed to correct the tank activity for radioactive decay. A.4 Enter the date and time at which the release of interest occurred.
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d CPSES ISSUE DATE PROCEDURE NO. j EMERGENCY PLAN MANUAL JAN en 14Aq EPP-300 I MANUAL CALCULATION OF RELEASE RATES REVISION NO. 2 PAGE 35.0F 75 ij - ATTACHMENT 9 lj PAGE 2 0F 5 - 1 J A.5 The analyst who performs these calculations should sign the form 1 and enter the date and time in the appropriate spaces. During an Alert condition the form will normally be reviewed by the Onsite l Radiological Assessment Coordinator. During Site Area or General emergencies this form will normally be reviewed by the Offsite Radiological Assessment Coordinator or the Radiation Protection Coordinator. [ j B. Source Term Summary V Isotope Available Activity (Ci) [ Xe-133 B.1 l Kr-85 B.1
; I-131 B.1 l B.O This section of Form EPP-300-4 addresses the summarization of the gaseous tank source term calculations.
l t B.1 The projected activities of Xe-133, Kr-85 and I-131 in Ci should be 0 entered into the appropriate spaces. These values will be used in the calculations performed.in Attachment 12 to determine the plant release rates. I II. Instructions for Using the TI-59 Gaseous Tank Source Term Calculation Program j A. Obtain the magnetic cards marked " GASEOUS TANK" from the black vinyl
/ TI-59 card file and enter the program on the first card into the l j calculator in accordance with the instructions found in Attachment 1 of
~
l this procedure. i NOTE: This program utilizes two magnetic cards to perform these l calculations. Be sure that all cards are used in the proper
} sequence when performing these calculations.
) B. In order to perform the analysis provided by this program several inputs l' must be made when prompted by the calculator / printer. These prompts, i' inputs and statements are described in the following paragraphs. B.1 COOL TIME? A This prompt asks for the cooling time in days to be entered into memory storage location A. 3 ' Q The cooling time is the time elapsed in days from the time the tank contents were sampled and analyzed and the time the release occurred. h
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_- _ ^ } s CPSES ISSUE DATE PROCEDURE NO. i EMERGENCY PLAN MANUAL M 09 MS EPP-300 O Q,/ MANUAL CALCULATION OF RELEASE RATES REVISION NO. 2 PAGE 36 0F 75 ; l t ATTACHMENT 9 m PAGE 3 0F 5 - 1 B.2 NO. T 1/2 - This statement provides the number of elapsed 1 half-lives between the time the sample was analyzed and the H occurrence of the release. These values are used to determine the y, decay factors found in Attachment 16 and entered in step B.3 below.
) B.2.1 XE133 = This statement provides the number of elapsed half-lives that the Xe-133 has undergone.
j B.2.2 KR85 = This statement provides the number of elapsed g half-lives that the Kr-85 has undergone. l B.2.3 I131 = This statement provides the number of elapsed half-lives that the I-131 has undergone. B.3 DECAY FAC ATT 16 This statement introduces the next section within the program calculations. The three prompts which follow this heading ask for the decay correction factors from Attachment 16. The decay factors are determined.in the following manner. The number of half-lives is located on the X-axis and then a vertical j L h line is drawn which intersects the curve. From this point of intersection a horizontal line is drawn to the Y-axis. The decay 1 factor is this point of intersection. Enter this value in the appropriate memory location. ,k
} B.3.1 XE133 FAC? B This prompt asks for the Xe-133 decay factor j to be entered into memory storage location B.
I B.3.2 KR85 FAC? C This prompt asks for the Kr-85 decay factor to j be entered into memory storage location C. i B.3.3 1131 FAC7 D This prompt asks for the I-131 decay factor to 3 be entered into memory storage location D. 1 d B.4 SAMP ACT - This statement introduces the section of inputs needed - I to perform these calculations. The prompts which follow this j heading ask for the gaseous and liquid phase isotopic activities. j Enter the concentration as prompted by the calculator / printer. B.4.1 XE133 GAS? A' This prompt asks for the gaseous Xe-133 activity of the tank in uCi/cc to be entered into memory ; storage location A'. f ( B.4.2 READ CARD 2 This command directs the radiological ! assessment personnel to enter the second magnetic card { program into the calculator / printer. This card is entered '
-) in the same manner as that described in Attachment 1 of this procedure.
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c _ . . i l j CPSES ISSUE DATE PROCEDURE NO. l EMERGENCY PLAN MANUAL M 99 M EPP-300 I s m
! M MANUAL CALCULATION OF RELEASE RATES REVISION NO. 2 PAGE 37.0F 75 ;i *
- s '
}
J = ATTACHMENT 9 Y PAGE 4 0F 5 - B.4.3 XE133 LIQ? A This prompt asks for the liquid Xe-133 , activity of the tank in uCi/cc to be entered into memory ( storage location A. B.4.4 KR85 GAS? B This prompt asks for the gaseous Kr-85 activity 1 of the tank in uCi/cc to be entered into memory storage j location B. B.4.5 KR85 LIQ? B' This prompt asks for the liquid Kr-85 activity j of the tank in uCi/cc to be entered into memory storage j location B'. 1
]
B.4.6 1131 GAS? C This prompt asks for the gaseous I-131 activity of the tank in uCi/cc to be entered into memory storage location C. 3 - B.4.7 1131 LIQ? C' This prompt asks for the liquid I-131 activity of the tank in uCi/cc to be entered into memory storage location C'. B.5 GAS PHASE VOL? D This prompt asks for the gaseous phase volume in ec's to be entered into memory storage location D'. r B.6 LIQ PHASE VOL7 D' This prompt asks for the liquid phase volume in ( cc's to be entered into memory storage location D'.
$ NOTE: Attachment 18, " Building and Tank Volumes" contains a list h of some building and tank volumes which may be of particular j interest and use.
O l- B.7 PRESS ABS? E This prompt asks for the absolute pressure of the i tank in psia to be entered into memory storage location E. Since it is standard practice to express gas sample results in uCi/cc at ~ 1 atmospheric pressure, the sample concentration must be converted to
] prevailing tank pressure. This is accomplished by multiplying by 1 the ratio, P /14.7 is the absolute container pressure j in psia. No*pEessure, where Pcorrect$bEs are required for the liquid d sample concentrations.
3 f B.8 READ CARD 3 This command directs the radiological assessment 3 personnel to enter side 1 of the last magnetic card in order to j complete these calculations. This card should be entered in the same manner as that described in Attachment 1 of this procedure. ] a N o A [ g - - - g 4 '$ 'f
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4 CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL JM 09 M5 EPP-300 l ( MANUAL CALCULATION OF RELEASE RATES REVISION NO. 2 PAGE 38 0F 75 s j ATTACHMENT 9
~
l PAGE 5 0F 5 l B.9 XE133 ACT = This statement provides the Xe-133 activity in Ci available for release from the plant. This value is used in Attachment 12 to determine the plant release rate and should be
- entered into Section B of Form EPP-300-4.
1 B.10 KR85 ACT = This statement provides the Kr-85 activity in ci available for release from the plant. The value is used in Attachment 12 to determine the plant release rate and should be entered into Section B of Form EPP-300-4. l B.11 I131 ACT = This statement provi. des 1-131 activity in ci available for release from the plant. This value is used in Attach =ent 12 to determine the plant release rate and should be entered into Section B of Form EPP-300-4.
, C. The TI-59 strip. chart printout should be attached to Form EPP-300-4 in the space provided when the' calculations have been completed. The figure below shows what the printout should look like.
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4 CPSES ISSUE DATE PROCEDURE NO. EMERCENCY PLAN MANUAL EPP-300 JAN 091985 MANUAL CALCULATION OF RELEASE RATES REVISION NO. 2 PAGE 39 0F 75 i); ATTACHMENT 10
,1 PAGE 1 0F 1
- 1 Texas UtSties Generating Company Comanche Peak Steam Eectric Station STEAM ACCIDENT SOURCE TERM CALCULATIONS 1
e.e.1.e l j A. Ceeer.1 tafemaeton
'Calculaties to.: Date Tibst Systen/Costainer Identificaties:
Analyet's Signature: Date: Time: 't f, S. Salease Information - >f semple Analyste Liquid Date: Times Cae Date: Times ^! .
- Steael Bleudeus late the/hr
[ . 31eudows Duraties: hre , stamm Released: the ! Yeperised Liquid 1h's
)
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CPSES ISSUE DATE PROCEDURE NO. P) EMERGENCY PLAN MANUAL _latl ne 100t EPP-300 MANUAL CALCULATION OF RELEASE RATES REVISION NO. 2 PAGE 40 0F 75
?, - 'j ATTACHMENT 11 j PAGE 1 0F 5 l
j'i INSTRUCTIONS FOR PERFORMING STEAM ACCIDENT SOURCE TERM CALCULATIONS 1 l I. Instructions for Completing Form EPP-300-5, " Steam Accident Source Term Calculations" i
- A. General Information i
j Calculation No.: A.1 Date: A.1 Time: A.1 4 i System / Container Identification: A.2 1 Analyst Signature: A.3 Date: A.3 Time: A.3 3 A.0 This section of Form EPP-300-5 addresses the general information requirements. f h A.1 The calculation number is required to identify each separate calculation so as to avoid confusion when referring to the results. g The numbering format should start with 001 and be preceeded by i either TSC or EOF to signify where the calculation was performed k (e.g. EOF-001 or TSC-001). The date and time when the calculations were performed should also be entered into the appropriate spaces. i A.2 Enter the identification of the tank or container which has been i involved in the event. h 3 A.3 The analyst who performs the calculations should sign the form and enter the time and date in the appropriate spaces. During an Alert condition the form will normally be reviewed by the Onsite Radiological Assessment Coordinator. During Site Area or General _ ? emergencies this form will normally be reviewed by the Offsite Radiological Assessment Coordinator or the Radiation Protection f Coordinator. - o b I i
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I 1 I 1 CPSES ISSUE DATE PROCEDURE NO. [ i EMERGENCY PLAN MANUAL JM09 M EPP-300
- m. !)
MANUAL CALCULATION OF RELEASE RATES REVISION NO. 2 PAGE 41 0F 75 1 i ATTACHMENT 11 i PAGE 2 0F 5 - d g B. Release Information d 1 Sample Analysis Liquid Date: B.1 Time: B.1 l J Gas Date: 3.1 Time: B.1 Steam Blowdown Rate: B.2 lbs/hr j . Blowdown Duration: B.3 hrs Steam Released: B.4 lbs H j Vaporized Liquid: B.S lbs 4 Pressure: B.6 psig Initial Mass: B.7 lbs w B.O This section of Form EPP-300-5 addresses the information required
, h to complete the steam accident source term calculations. , ] B.1 Enter the date and time of the last known liquid and gas sample l analyses.
3 B.2 The principal information which must be estimated is the mass of 4 steam which is released. Because the entire contents of a j container may not be released, the circumstances of the actual j accident must be considered. One way to estimate the mass released
? ._ is to utilize the blow down rate and duration, if known. The blow l down down rate is entered in space B.2 and the duration is entered in space B.3. The total mass released is calculated by multiplying )) these two values together. The result is entered into space B.4.
A second method of determining the release is to compare the j "before release" and "af ter release" contents of the tank or ~ j container. If the container initially contains both liquid and
,; steam, and the release is from a point above the water level, -
r, assume that the initial inventory of steam is exhausted before any 1 liquid vaporizes. The difference between the total mass released
] and the initial inventory of steam represents the mass of liquid rj which is vaporized. If the release comes from a point below the a water level, assume all of the released mass is from vaporized y liquid. If the container is completely filled with water, then all ; of the mass released is considered to be vaporized water. The I- reason for making these distinctions is that the retention of ) [] '
iodine is influenced by the way in which the release takes place.
). Enter the volume of liquid vaporized in space B.S.
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1 s - s CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL M 09 M EPP-300 m J) MAh'UAL CALCULATION OF RELEASE RATES REVISION NO. 2 PAGE 42 0F 75 0 1 ATTACHMENT 11
! PAGE 3 0F 5 ^
B.6 Enter the pressure of the tank or container prior to the occurrence of the event, if known. B7 Enter the total mass of the tank or container prior to the l occurrence of the event. L C. Source Term Summary l j Isotope Available Activity (Ci) J Xe-133 C.1 Kr-85 C.1 I-131 C.1 C.0 This section of Form EPP-300-5 addresses the summarization of the h , steam accident source term calculations. C.1 Enter the available activities of Xe-133. Kr-85 and I-131 in Ci in these spaces. These values are used in Attachment 12 to estimate the plant release rates. I II. Instructions for Using the TI-59 Steam Accident Source Term Calculation Program J A. Obtain the magnetic cards marked " STEAM ACCIDENT" from the black vinyl ] TI-59 card file and enter the program on the first card into the ] calculator in accordance with the instructions found in Attachment 1 of j . this procedure. NOTE: This program utilizes two magnetic cards to perform these - I calculations. Be sure that all cards are used in the proper i sequence when performing these calculations. i B. In order to perform the analysis provided by this program several inputs j must be made when prompted by the calculator / printer. These prompts, inputs and statements are described in the following paragraphs. 1 i B.1 MASS ST REL? A This prompt asks for the mass of steam in lbs j released as a result of the accident to be entered into memory l storage location A. This value is obtained from Section B of Form Q EPP-300-5. e
CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL EPP-300 Y M 09 M j h MANUAL CALCULATION OF RELEASE RATES REVISION NO. 2 PAGE 43 0F 75 ATTACHMENT 11 PAGE 4 0F 5 - B.2 MASS LIQ REL? B This prompt asks for the mass of liquid in lbs to be entered into memory storage location A. This value is obtained from Section B of Form EPP-300-5. B.3 XE133 ST ACT? C This prompt asks for the Xe-133 steam l concentration in uCi/cc to be entered into memory storage location
} C.
B.4 XE133 LIQ ACT? D This prompt asks for the Xe-133 liquid i concentration in uCi/cc to be entered into memory storage location j D. B.5 KR85 ST ACT? E This prompt asks for the Kr-85 steam concentration , in uCi/cc to be entered into memory storage location E. i B.6 READ CARD 2 This command directs the radiological assessment personnel to enter the second magnetic card program into the calculator / printer in order to complete the calculations. L f (} B.7 KR85 LIQ ACT? A' This prompt asks for the Kr-85 liquid concentration in uCi/cc to be entered into memory storage location A'. I B.8 1131 ST ACT? B' This prompt asks for the I-131 steam concentration in uCi/cc to be entered into memory storage location B'. x B.9 1131 LIQ ACT? C' This prompt asks for the I-131 liquid
- i. concentration in uCi/cc to be entered into memory storage location j C'.
f B.10 The next two prompts ask for the iodine release fractions in steam and liquid. j B.10.1 I131 ST REL FRAC 7 D' This prompt asks for the I-131 steam - release fraction to be entered into memory storage location D'. This value is assumed to be one (1) in all cases. $ B.10.2 I LIQ REL FRAC? E' This prompt asks for the I-131 liquid release fraction to be entered into memory storage location E'. When the leak is from a point above the water level, j the2 appropriate release fraction for iodine from water g 10 . When the leak is from a point below the water level ! and the water itself tries to escape, it carries no iodine , with it and the appropriate release fraction is 10 0 9 ]T "~ ; ~ *' Y * (***-* *8f*-"M7P *****"'-***% -
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CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL EPP-300 M 09 E m O MANUAL CALCULATION OF RELEASE RATES REVISION NO. 2 PAGE 44.0F 75 l ATTACHMENT 11 L PAGE 5 0F 5 - B.11 XE133 ACT = This statement provides the total Xe-133 activity in ci available for release from the plant. This value is used in Attachment 12 to determine the plant release rate. This value should be entered into Section C of Fom EPP-300-5. ( B.12 KR85 ACT = This statement provides the Kr-85 activity in Ci available for release from the plant. This value is used in .l j ' Attachment 12 to determine the plant release rates. This value j should be entered into Section C of Form EPP-300-5. a j B.13 I131 ACT = This statement provides the total I-131 activity in Ci j available for release from the plant. This value is used in ] Attachment 12 to determine the plant release rates. This value should be entered inte Section C of Form EPP-300-5. ! C. The TI-59 strip chart printout should be attached to Form EPP-300-5 in j the space provided when the calculations have been completed. The figure below shows what the printout should look like. f:m ~; 1 N.:
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j -. CPSES ISSUE DATE PROCEDURE NO.
.i EMERGEECY PLAN MANUAL M 09 585 EPP-300 i
q MANUAL CALCULATION OF RELEASE RATES REVISION NO. 2 PAGE 45 0F 75 ATTACHMENT 12
! PAGE 1 0F 1 l
'I Texas UtRities Generating Company Comanche Peak, Steam Eectric Station PLANT RELEASE RATE CALCULATIONS il . Doen1 ef 1 A. Ceneral taformattoe
- Calculaties Es.: Date: Times
.* 1acident Situations i Smilding
! Analyst's $1 gestures Date Times 3* Avetlable Tsecome Activttv (Att. 3, & of 3) testese Activiev (C1)
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CPSES ISSUE DATE PROCEDURE NO. I EMERGENCY PLAN MANUAL EPP-300 M 09 M l ni> MANUAL CALCULATION OF RELEASE RATES REVISION NO. 2 PACE 46 0F 75 ATTACEMENT 13 . PAGE 1 0F 6 - INSTRUCTIONS FOR PERFORMING PLANT
- . RELEASE RATE CALCULATIONS s
P Q I. Instructions for Completing Form EPP-300-6, " Plant Release Rate Calculations" G
- f
} A. General Information ll Calculation No.: A.1 Date: A.1 Time: A.1 9 d ~ Incident Situation: A.2 'i l Building: A.3 [ 0 Analyst Signature: A.4 Date: A.4 Time: A.4 4. A.0 This section of Form EPP-300-6 addresses the general information il . ~~ requirements of these calculations. 1' (;:/ . A.1 The calculation number is required to identify each separate calculation so as to avoid confusion when referring to the results. The numbering format should start with 001 and be preceeded by N either TSC or EOF to signify where the calculation was performed (e.g. EOF-001 or TSC-001) . The date and time when the calculations were performed should also be entered into the appropriate spaces.
. A.2 A brief description of the type of event which has occurred. For example, if a.. gas decay tank has ruptured and is releasing activity to its surroundings, a suitable entry would be: " Gas decay tank p
rupture". A.3 Enter the identity of the building from which the release is coming or is expected to emanate from.
, A.4 The analyst who performs the calculations should sign the form and enter the time and date in the appropriate spaces. During an Alert condition the form will normally be reviewed by the Onsite Radiological Assessment Coordinator. During Site Area or General S emergencies this form will normally be reviewed by the Offsite 4 Radiological Assessment Coordinator or the Radiation Protection Coordinator.
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i i CPSES ISSUE DATE PROCEDURE NO. j I EMERGENCY PLAN MANUAL M 09 M EPP-300 j M9 MANUAL CALCULATION OF RELEASE RATES. REVISION NO. 2 PAGE 47 0F 75 i ATTACHMENT 13 PAGE 2 0F 6 E B. Available Isotope Activity (Att. 3, 4 or 5) J Isotope Activity (C1)
; Xe-133 B.1 1
r, Kr-85 B.1 i it 1 i I-131 B.1 j B.O This section of Form EPP-300-6 addresses the available activity i estimated on Forms EPP-300-3, -4 and -5. 1 1
, B.1 The available activities of Xe-133. Kr-85 and I-131 in ci projected ; by calculations for Forms EPP-300-3, EPP-300-4 and EPP-300-5 should , be entered in the appropriate spaces. From these values the noble
- gas and I-131 release rates are estimated.
j C. Release Summary
; Radionuclide Release Rate j Group (Ci/sec) -
3 l Noble Gases C.1 i
.. 1-131 C.1 C.0 This section of Form EPP-300-6 addresses the summarization of the ?
plant release rates. ; a C.1 The noble gas and I-131 release rates in Ci/see should be entered l into the appropriate spaces when the plant release rate '
} calculations are completed.
.) II. Instructions for Using the TI-59 Plant Release Rate Calculation Program l- A. Obtain the magnetic cards marked " PLANT RELEASES" from the black vinyl
~
TI-59 card file and enter the program on the first card into the ! calculator in accordance with the instructions found in Attachment 1 of l this procedure.
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6 't , 4 j CPSES ISSUE DATE PROCEDURE NO.
- EMERGENCY PLAN MANUAL EPP-300 J JAN 091985
! MANUAL CALCULATION OF RELEASE RATES REVISION NO. 2 PAGE 48.0F 75 3
3 i ] ATTACHMENT 13 PAGE 3 0F 6 -
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3 NOTE: This program utilizes two magnetic cards to perform these , , j calculations. Be sure that all cards are used in the proper '
; sequence when performing these calculations. '
a j l B. In order to perform the analysis provided by this program several inputs j must be made when prompted by the calculator / printer. These, prompts, inputs and statements are described in the following paragraphs. 1 B.1 ELAP TIME? A This prompt asks for the elapsed time, in hours, to
] be entered into memory storage location A. The elapsed time can be j the length of time passed since the beginning of the event to its ! conclusion or any time frame in between. The elapsed time must be d measured in units of hours and fractions of hours should be rounded downward to the nearest tenth of an hour.
j B.2 BD EXH REM R] B This prompt asks for the building exhaust removal a rate, in sec , to be entered into memory storage location B. The
} building exhaust removal rates are estimated using the tables'and 1 instructions found in Attachment 19.-
j h B.3 C S F REM RT? C This prompt asks for the containment spray removall
,4 rate for iodine to be entered into memory storage location C. This value is always zero when the containment spray is inoperable or if the containment is not the building of interest. If the j containment spray is operable and the containment represents the j point of release the removal rate must be entered. Thecogainment
- spray removal coefficient has been estimated to be 9.6 hrs based i on desg base removal1 efficiencies f r elemental iodine of-- '
[ 10 hrs and 1.07 hrs for particulate iodine and .their respective i contributions, 91% and %5. ( l B.4 NO. T 1/2 - This statement provides the number of ef fective cleanup half-lives which the isotopes are projected to have undergone prior ~ to the material being available to deliver a dose to a member of
- the general population. These values are used to determine the I decay factors found in Attachment 16 and entered in step B.5 below.
l B.4.1 XE133 = This statement provides the number of elapsed
; effective cleanup half-lives that the Xe-133 is estimated to have undergone.
B.4.2 KR85 = This statement provides the number of elapsed effective cleanup half-lives that the Kr-85 is estimated to have undergone. (~h u.. /
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a-t. CPSES ISSUE DATE PROCEDURE NO. EMERCENCY PLAN MANUAL ggg EPP-300 h.
. MANUAL CALCULATION OF RELEASE RATES REVISION NO. 2 PACE 49 0F 75 ATTACHMENT 13 ,
PAGE 4 0F 6 *) 4 B.4.3 1131 = This statement provides the number of elapsed j N ^ i effective cleanup half-lives that the I-131 is estimated to
; have undergone.
j B.5 FACTOR ATT 16 This statement introduces the next section within a the program calculations. The three prompts which follow the fj heading ask for the decay factors from Attachment 16. The decay I factors are determined in the following manner. The number of elapsed effective cleanup half-lives is located on the x-axis and then a vertical line is drawn which intersects the curve. From this point of intersection a horizontal line is drawn to the y-axis. _The effective cleanup factor is this point of
'. intersection. Enter this value in the appropriate memory location.
} f , B.5.1 XE133? A' This prompt asks for the Xe-133 decay factor to
?
be entered into memory storage location A'. a i B.5.2 KR857 B' This prompt asks for the Kr-85 decay factor to be j entered into memory storage location B'. 5
! B.S.3 READ NEXT CARD This command directs the radiological 7_ assessment personnel to enter the second magnetic card ! program into the calculator / printer in order to complete the' J
calculations, j- - B.S.4 1131? C' This prompt asks for the I-131 decay factor to be j entered into memory storage location C'. 1 j B.6 I WA SCR FAC? D' This prompt asks for the iodine water scrubbing h factor to be entered into memory storage location D'. If an iodine J release occurs in water, such as from fuel damage to a fuel ? assembly while submerged in the spent fuel pool, a large part of i
- the iodine will be scrubbed out of the bubbles as they rise to the '
... - surface. If the release is above the water level, use 0.1. If the
~
release is below the water level use 0.01. o - 0 B.7 I FIL CL FAC? E' This prompt asks for the iodine filter cleanup i
. factor to be entered into memory storage location E'.
Theoretically, a charcoal filter has a removal efficiency of
; 99.97%, corresponding to a cleanup factor of 0.0003. However, some of the iodine is organic, which is not removed as efficiently, so 1 -
99.9% (filter factor of 0.001) is assumed. The design base analyses in the FSAR assume only 95% removal efficiency (clean-up i factor of 0.05). A value of 0.05 will be used to estimate the Q iodine release rate. 1
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.4 CPSES ISSUE DA'TE PROCEDURE NO.
EMERGENCY PLAN MANUAL ggg EPP-300 MANUAL CALCULATION OF RELEASE RATES REVISION NO. 2 PAGE 50 0F 75
.3 a
ATTACHMENT 13 (h ; 1 PAGE 5 0F 6
/ NOTE: Be certain that an exhaust filter cleanup factor is only taken credit for if the plant ventilation is operating in j
9 the affected area during the release.
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B.8 NG COR FAC? E This prompt asks for the noble gas correction factor j to be entered into memory storage location E. The noble gas J correction factor is determined from the figure found in Attachment
; 17.
B.9 BD REL RT - This statement identifies the results of the plant k release rate calculations. These values should ,be entered into the appropriate spaces in Section C of Form EPP-300-6. , { l [ B.9.1 XE133 = This statement provides the Xe-133 release rate in ' b Ci/sec. f B.9.2 KR85 = This statement provides the Kr-85 release rate in ( Ci/sec.
- h B.9.3 I131 = This statement provides the I-131 release rate in C1/sec. This value is used to project exposures to personnel in accordance with the instructions found in EPP-300, " Manual Assessment of Radiological Conditions".
g B.9.4 TOT NG REL RT = This statement provides the noble gas release rate in Ci/sec. This value is used to project ( exposures to personnel in accordance with the instructions found in EPP-300, " Manual Assessment of Radiological Conditions". . y l? !I I! d ~ r J ' p' (3 z 1 y , LO a
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i 1 l CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL EPP-300 JAN 091985
't MANUAL CALCULATION OF RELEASE RATES REVISION NO. 2 PAGE 51 0F 75 k
ATTACHMENT 13 PAGE 6 0F 6 ~ J o /' C. The TI-59 strip chart printout should be attached to Form EPP-300-6 in the space provided when the calculations are completed. The figure below illustrates the appearance of the strip chart printout, b Li .y 1 ELAP. TIME? F1 cm j ' A v.*, = v' g, 'j H.el4 ulk.ig I
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l CPSES ISSUE g PROCEDURE NO. j EMERGENCY PLAN MANUAL JAN 09 d EPP-300 l ] (h MANUAL CALCULATION OF RELEASE RATES REVISION NO. 2 PAGE 52 0F 75 l i- ATTACHMENT 14
] PAGE 1 0F 1 Li 1
1 ; q~ Texas utstles Generating Company ] Comanche Peak Steam Eectric Station l I STEAM GENERATOR TUBE RUPTURE RELEASE RATE CALCULATIONS
. I poos t of1 A. General taformaties ,
Calculation so.'s Dates Time: 'f 1 j Affected Unit (1 er 2): Affected Steam Ceeerator l Analyst $1snature: Date: Times ) '. n - j 3. Flow Este Determination (Use only one)
.b i
- 1. Steam F1sw Rate Moeitar Ident.: )
Flow late: n/hr 1
- I 2. Falve Ihaber of Belief
- Flav Jj open valvee Capacity Rate (h /br) (1b/hr)
(
- i Ac = *Fh aria Safety
'l i Total Flow Rate (1h/hr) 1 .j 3. Primary /w -y t ek .
4 couversion Factor Flow Rate Leak (ass) Rate
- fase unter to cr/sec-eteen) (cc/tec) *
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J 1.34 1 103 2 . . . 1 3 - C. Partition factors , j
- ! tadisemelide Croup 3/C unter Invol .
1 Emotv sereal Flooded ;
, n. 'I !sette cases 1.0 1.0 1.0 $'
j Iodiam-131 0.1 0.01 1.0 0.01 0.01 1.0 " 1 Ferticulate #
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4 c. n.1a . s - arv : l 1 Radioenclide talease Total Activity
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_ .; . w. . __..; -- CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL FPP-300 JAN 091985 MANUAL CALCULATION OF RELEASE RATES REVISION NO. 2 PAGE 53 OF 75 ATTACHMENT 15
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PAGE 1 0F 7 INSTRUCTIONS FOR PERFORMING STEAM GENERATOR TUBE RUPTURE RELEASE RATE CALCULATIONS
- :. . Instructions for Completing Form EPP-300-7, " Steam Generator Tube Rupture Release Rate Calculations" l '
A. General Information Calculation No.: A.1 Date: A.1 Time: A.1
. Affected Unit (1 or 2): A.2 Affected Steam Generator: A.3
[ Analyst Signature: A.4 Date: A.4 Time: A.4 t j A.0 This section of Form EPP-300-7 addresses the general information j requirements. cm (y A.1 The calculation number is required to identify each separate , calculation so as to avoid confusion when referring to the results. y The numbering format should start with 001 and be preceeded by i either TSC or EOF to signify where the calculation was performed j (e.g. EOF-001 or TSC-001). The date and time the calculations were j performed should also be entered into the appropriate spaces. A.2 Enter the number of the affected unit in this space (e.g. Unit 1 or b 2), k' k.3 Enter the number of the defective steam generator in this space. j l ) A.4 The analyst who performs the calculations should sign the form and j enter the time and date in the appropriate spaces. During an Alert __ j condition the form will normally be reviewed by the Onsite j Radiological Assessment Coordinator. During Site Area or General i emergencies this form will normally be reviewed by the Offsite - i Radiological Assessment Coordinator or the Radiation Protection Coordinator. I h i ) er% k kh) 1
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CPSES ISSUE DATE PROCEDURE NO. EPP-300-EMERGENCY PLAN MANUAL
.j 0 gy MANUAL CALCULATION OF RELEASE RATES REVISION NO. 2 PAGE 54.0F 75 i
ATTACHMENT 15 1 PAGE 2 0F 7 ' B. Flow Rate Determination (Use only one)
- 1. Steam Flow Rate Monitor Ident.: B.1 Flow Rate: B.1 lb/hr
- 2. Valve Number of X Relief = Flow 1 Type Open Valves Capacity Rate !
9 a (1b/hr) (lb/hr) Atmospheric B.2.1 B.2.2 B.2.3 ) 1 3lj ' Safety B.2.1 B.2.2 B.2.3 1 ] Total Flow Rate (lb/hr) B.2.4 i
; 3. Primary / Secondary Leak l h' Leak Rate Conversion Factor "
Flow Rate (apa) (spm water to ec/sec-steam) (cc/sec) j B.3.1 1.58 x 10s B.3.2 B.O This section of Form EPP-300-7 addresses the determination of the steam flow rate or primary to secondary leak rate. There are three methods which can be utilized to estimate the release rate as a result of a steam generator tube rupture. These three methods are listed here in order of preference. When performing these il . calculations it is necessary to remember that only one method needs j ' to be utilized. It is very important to remember which method is used when performing isotopic release rate calculations. y B.1 Steam Flow Rate Monitors [ ' F This method of steam flow rate determination is the method of choice. Each steam line leading to the relief valves has two flow l j rate monitors. The highest flow rate indicated on the affected line should be used in these calculations, ] s 4 1 1
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j, - i 1 i h CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL ggg EPP-300 n 1-
-h- MANUAL CALCULATION OF RELEASE RATES REVISION NO. 2 PAGE 55.0F 75 y
b j ATTACHMENT 15 j PAGE 3 0F 7 i' B.l.1 Enter the number of the highest reading monitor (s) in these spaces. Each monitor identifier begins with 1-FI-and is followed by a three number and one letter code. The
]j identifiers are listed below:
a f Steam Generator No. I l-FI-512A
!1 1-FI-513A i
j Steam Generator No. 2 1-FI-522A j 1-FI-523A
'l J. Steam Generator No. 3 1-FI-532A ) 1-FI-533A 1
j Steam Generator No. 4 1-FI-542A
.j . 1-FI-543A B.1.2 Enter the indicated steam flow rate in these spaces. These values can be obtained from control room personnel.
O B.1.3 If more than one steam generator is involved in the incident situation add the flow rates together and enter the result in this space. This result is used to determine the isotopic release rate. B.2 Operation of Relief and/or Safety Valves This is the method of second choice for determining the steam flow [ rate. There are two types of valves of interest an atmospheric dump valve and the safety relief valves. These valves lift under overpressure situations to prevent excess overpressurization. B.2.1 Enter the number of each type of valve which has opened in these spaces. ~ ![ B.2.2 Enter the relief capacity of each type of valve in lbs/hr in these spaces. 1 B.2.3 Determine the flow rate through each type of valve by multiplying the number of valves open times the relief capacity of each type of valve. Enter the results in these
; spaces. !i j B.2.4 Sum the flow rates from each type of valve and enter the 1 result in this space. This value will be used to determine G-} the isotopic release rates.
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f ATTACHMENT ~15 1 PAGE 4 0F 7 - f B.3 Primary to Secondary Leak Rate . 3 - The atmospheric release of steam can be estimated if the primary to secondary leak rate is known. If direct determination of this j value is not possible the default value for a steam generator tube L rupture is 1 gpm. 4
'B.3.1 Enter the primary to secondary leak rate in this space if
{- known or the 1 gym default value for worst case basis j calculations.
< B.3.2 Calculate the atmospheric flow rate by multiplying the l primary to secondary leak rate times a conversion factor.
The conversion factor converts the water leak rate in gallons per minute to a steam flow rate in cc per second. I n f C. Partition Factors i h Radionuclide Group Empty S/G Water Level Normal Flooded
,L Noble Gases 1.0 1.0 1.0 Iodine-131 0.1 0.01 1.0 Particulate 0.01 0.01 1.0 L
C. This section of Form EPP-300-7 addresses the determination of the , appropriate partition factors. The group partition factors are l dependent upon the water level of the steam generator. The appropriate j values are simply read from the table, t I-D. Release Summary [ Radionuclide Release Total Activity I Group Rate Released g (Ci/sec) (Ci) y i Noble Cases D.1 D.2 ; i I-131 D.I D.2 - l
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] ATTACHMENT 15 PAGE 5 0F 7 j D. This section of Form EPP-300-7 addresses the summarization of the . j release rates.
?
f D.1 Enter the noble gas and I-131 release rates in C1/sec in the
] appropriate spaces.
D.2 Enter the noble gas and I-131 total activity released in ci in the
! appropriate spaces.
l j II. Instructions for Using the TI-59 Steam Generator Tube Rupture Release Rate j Calculation Program i i A. Obtain the magnetic card marked "SG RELEASE" from the black vinyl TI-59 card file and enter the program into the calculator in accordance with j the instructions found in Attachment 1 of this procedure. i , B. In order to perform the analysis provided by this program several inputs
- must be made when prompted by the calculator / printer. These prompts, inputs and statements are described in the following paragraphs.
) . B.1 RC ACT7 This prompt asks for the total reactor coolant activity in j uCi/cc to be entered into the program memory.
, B.2 NG ACT? This prompt asks for the reactor coolant noble gas activity in-uCi/cc to be entered into the program memory.
{ B.3 1 ACT? This prompt asks for the reactor coolant iodine activity in j uCi/cc to be entered into the program memory. I - B.4 PRT ACT7 This prompt asks for the reactor coolant particulate j activity in uCi/cc to be entered into the program memory. B.5 PF-I? This prompt asks for the iodine partition factor to be _
- entered into the program memory. This value is obtained from
! section C of Form EPP-300-7. B.6 PF-P7 This prompt asks for the particulate partition factor to be
- j. entered into the program memory. This value is obtained from
, section C of Form EPP-300-7. l e B.7 MS LN ACT7 This prompt asks for the main steam line activity monitor reading in uC1/cc to be entered into the program memory. Th'e value should be obtainable from the DRMS Operator.
. ~. .- . _ _ . . . . . _ . _ . _ _ _ . _ _ . . . . ,
y ~ P 4 CPSES ISSUE DATE PROCEDURE NO. {f EMERGENCY PLAN MANUAL JIANOstSBS EPP-300 a 1 j- d-- MANUAL CALCULATION OF RELEASE RATES REVISION NO. 2 PAGE 58.0F 75 1 l ATTACHMENT 15 PAGE 6 0F 7 ~ l ij B.8 FLOW 7 This prompt asks for the steam release rate in lbs/hr to be j entered into the program memory. This value is obtained from j section B of Form EPP-300-7.
~
NOTE: At the present time the program does not utilize the primary i to secondary leak rate to determine the release rate. This method will be placed into the program shortly.
.}
a B.9 E TM? This prompt asks for the release duration, in hours, of the
; steam release. The elapsed time may be a measured time or an ] estimated time period. .: B.10 NG REL RT = This statement provides the noble gas release rate in Ci/sec. This value is used to project emergency population )}
L exposures in accordance with EPP-302, " Manual Assessment of j Radiological Conditions" and should be entered into the appropriate i space in section D of Form EPP-300-7. i B.ll I REL RT = This statement provides the iodine-131 release rate in i ([') Ci/sec. This value is used to project emergency thyroid exposures j to the general population in accordance with EPP-302, " Manual J Assessment of Radiological Conditions" and should be entered into the appropriate space in section D of Form EPP-300-7. i j B.12 NG RELS = This statement provides the total noble gas activity, in j Ci, released from the plant. This value should be entered into 1 section D of Form EPP-300-7. 3
! B.13 I RELS = This statement provides the total iodine-131 activity, in b Ci, released from the plant. This value should be entered into ! section D of Form EPP-300-7.
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3 ATTACHMENT 15 4 PAGE 7 0F 7 s i
; C. The TI-59 strip chart printout should be attached to Form EPP-300-6 in j the space provided when the calculations are completed. The figure
( below illustrates the appearance of the strip chart printout.
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! A MANUAL CALCULATION OF RELEASE RATES REVISION NO. 2 PAGE 62 0F 75 ,1, i
ATTACHMENT 17
.l* PAGE 1 0F 1 l
1:. 1 RATIO OF TOTAL NOBLE GAS TO XR-85 ANO XE-133 VS. " EFFECTIVE AGE"
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ATTACHMENT 18
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PAGE 1 0F 2 BUILDING AND TANK VOLUMES
. A. Building Volumes (cc) i .! Containment Free Volume 8.45 x 10 10 i
j I Fuel Handling 3.63 x 10 10 f Safeguards 1 2.78 x 10 10
., Safeguards 2 2.78 x 10 10 1 ): Auxiliary 5.30 x 10 10 Diesel Generator 1 4.96 x 10 9 i
y Diesel Generator 2 4.96 x 10 9 C:) 3.43 x 10 10 Electrical Control
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j B. Tank Volumes (cc) a Volume Control Tank 1.14 x 10 7 Pressurizer Relief Tank 5.10 x 10 7 y Spent Resin Storage Tank 1.55 x.10 7 f Waste Holdup Tank 3.79 x 10 7 Waste Evaporator Condensate Tank 1.89 x 10 _ 0 Chemical Drain Tank 2.27 x 10
- Floor Drain Tanks )
7 !l, I 3.79 x 10 j II 3.79 x 10 7 I l III 1.14 x 10 8 i , i
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) ATTACHMENT 18 4 PAGE 2 0F 2 A
BUILDING AND TANK VOLUMES Waste Monitor Tank 1.89 x 10 a 6 Reactor Coolant Drain Tank 1.32 x 10 Laundry and Hot Shower Tank 3.79 x 10 Laundry Holdup and Monitor Tank 1.89 x 10 Laundry Head Water Tank 1.89 x 10 6 J Reverse Osmosis Concentrate Tank 3.79 x 10 Gas Decay Tank 1.70 x 10 p f:3.- . 8 \. t v w l t, 4 p. t b b
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) MANUAL CALCULATION OF RELEASE RATES REVISION NO. 2 PAGE 65.OF 75 t
l ATTACHMENT 19 j PAGE 1 0F 7 BUILDING EXHAUST REMOVAL RATES i 1.0 Ventilation Information This attachment contains the building exhaust removal rates for the fuel 1 handling building, auxiliary building, Unit I and Unit 2 safeguards
! buildings, and containment. The building exhaust removal rates have been j identified for a variety of operating conditions and for situations where ! from 1 to 14 ventilation fans are operating. The three basic operating conditions are the nomal ventilation system operation, building isolation and partial damper flow restrictions. The building exhaust removal rates can i be determined using either the actual plant stack flow rate or the design flow rate of the ventilation fans. The building exhaust removal rates are conservative in nature, especially so for the values calculated using the design flow rate of the ventilation fans. The tables below contain the building exhaust removal rates or the different cases. All removal rates are expressed in units of sec 2.0 Building Exhaust Removal Rates 2.1 Calculations Using Plant Stack Flow Rates
, The primary method for estimating builtiing exhaust removal rates should I be calculations using the plant stack flow rate as measured by stack [ monitors PVG-084 and PVG-085 for stacks A and B respectively. These [ monitors provide the stack flow rate in ec/sec. 2.1.1 Normal Ventilation Operation lb . ] Under normal plant operating conditions the ventilation system j exhausts air from the fuel handling building, auxiliary building j and safeguards buildings simultaneously. The relative
, contributions to the total exhaust through the stack from each of ~ ? these buildings are 1/6,1/2 and 1/6 respectively. The following formula is used to estimate the building axhaust removal rate:
4
; Building Exhaust = Plant Stack Flow Rate x Exhaust Fraction j Removal Rate Building Volume P
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- CPSES ISSUE DATE PROCEDURE NO.-
j EMERGENCY PLAN MANUAL JAN 09 25 EPP-300 4
, m ! Dj MANUAL CALCULATION OF RELEASE RATES REVISION NO. 2 PAGE 66 .0F 75 l
k' ATTACHMENT 19
, PAGE 2 0F 7 -
i BUILDING EXHAUST REMOVAL RATES 0 t h The units and/or values of the variable are: s f' building exhaust removal rate - sec ; [ plant stack flow rate (PVG-084 or -085) - cc/sec; exhaust fractions - fuel handling building - 1/6, g- ' , auxiliary building - 1/2, and i safeguards buildings - 1/6 each; and ( building volumes - cc; Attachment 18 contains a list of building volumes. J. The buildings of particular interest are listed below: 10 fuel handling - 3.63 x 10 cc 10-auxiliary - 5.30 x 10 cc 10 e safeguards - 2.78 x 10 cc 10 }'- containment - 8.45 x 10 cc y F 2.1.2 Complete Building Isolation 1. If the ventilation system has been arranged such that the dampers have isolated a particular building and all the exhaust is attributed to air removed from just that building the building + exhaust removal rate is estimated using the following equation:
~
f- Building Exhaust = Plant Stack Flow Rate 2 Removal Rate Building Volume k I Because the entire exhaust is from one building the exhaust fraction is no longer a factor which must be taken into - consideration. 3 , O i ym.57,- - - - - - - - -
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1 CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL JAN 091985 EPP-300 MANUAL CALCULATION OF RELEASE RATES REVISION NO. 2 PAGE 67 0F 75 ]z. ATTACHMENT 19 PAGE 3 0F 7
?] .) BUILDING EXHAUST REMOVAL RATES l
j 2.1.3 Partial Damper Flow Restrictions i The contribution to the total exhaust from the different buildings can change dramatically depending on the position of the dampers within the ventilation system. To determine the building exhaust removal rate to be used in Attachment 13 the r i following equation is used; d 1 Plant Stack Number of Building E} Building Exhaust = Flow Rate X Fahaust Ducts Open j ' Removal Rate Building Volume X Total Number of Ventilation Exhaust Ducts Open r
$ For conservativeness in these calculations it is assumed that the i ventilation system exhaust removes air equally from any open
- ducts and that any ducts which are even partially open are
,: considered to be fully opened for release rate estimation j purposes.
j1 2.2 Calculation Using Fan Design Flow Rate Capacity 1 if the stack flow rate is unavailable the building exhaust removal rate can be estimated using the design flow tate capacity of the ventilation i fans. The same three operating conditions considered in Section 2.1 are considered in this section also. Normal plant operations require twelve fans to operate and under emergency conditions as f ew as only two fans
. may be operating. The building exhaust removal rates below are 4; identified for situations where from 1 to 14 primary plant ventilation
, fans are operating. The design flow rate of each fan is 15000 cfm and
? this value is used in these calculations. _
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_ . . j. ,_ CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL JAN 091985 Ere-300 (:% e MANUAL CALCULATION OF RELEASE RATES REVISION NO. 2 PAGE 68.0F 75 ATTACHMENT 19 i PAGE 4 0F 7 - 4 BUILDING EXHAUST REMOVAL RATES i l ) 2.2.1 Normal Ventilation Operation ] The building exhaust removal rates listed in the table below are
; based on the building volumes found in Attachment 18, fan design capacity flow rate and normal alignmentg of the ventilation j dampers. All values have units of see Number of Operating Fans i Building 1 2 3 4 5 Fuel Handling 3.25x10-5 6.50x10
-5 9.75x10
-5 1.30x10
-4 1.63x10
-4 4.24x10 -5 8.49x10-5 -4 -4 Unit 1 Safeguards 1.27x10 ' 1.70x10 2.12x10 Unit 2 Safeguards 4.24x10-5 8.49x10
-5 1.27x10 '
1.70x10
-4 -0 2.12x10
-4 -4 -4 -
Auxiliary 6.68x10-5 1.34x10 2.00x10 2.67x10 3.34x10 ' 1 2
; Number of Operating Fans Building 6 7 8 9 10 l
-4 -4 - - -
Fuel Handling 1.95x10 2.28x10 2.60x10 ' 2.93x10 ' 3.25x10 '
-0 -4 -4 -0 -
Unit 1 Safeguards 2.55x10 2.97x10 3.40x10 3.82x10 4.24x10 '
-0 -4 - -0 -
Unit 2 Safeguards 2.55x10 2.97x10 3.40x10 ' 3.82x10 4.24x10 ' 4.01x10" 4.68x10
-0 -4 -4 -5 !
Auxiliary 5.34x10 6.01x10 6.68x10 i ' 1 Number of Operating Fans l Building 11 12 13 14 o
-4 Fuel Handling 3.58x10 3.90x10 ' 4.23x10 ' 4.55x10
-4 -4 -
-4 Unit 1 Safeguards 4.67x10 5.09x10 5.52x10 ' 5.94x10
-4 - -0 Unit 2 Safeguards 4.67x10 ' 5.09x10 5.52x10 ' 5.94x10
-4 -
-0 -4 Auxiliarv 7.35x10 8.02x10 ' 8.68x10 9.35x10 l
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CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL Jul og 1985 Ere-300 l U MANUAL CALCULATION OF RELEASE RATES REVISION NO. 2 PAGE 69 0F 75
- ATTACIDfENT 19 PAGE 5 0F 7 BUILDING EXHAUST REMOVAL RATES n
2.2.2 Complete Building Isolation q If the ventilation system has been arranged such that the dampers
} have isolated a particular building then all the air which is exhausted through the primary plant ventilation system may be C: assumed to come from just that one building. The building jj exhaust removal rates for this situation are contained in the *, table below:
n Number of Operating Fans Building i 2 3 4 5
-4 -0 ~4 ~4 1, Fuel Handling 1.95x10 3.90x10 5.85x10 7.80x10 9.75x10 Unit 1 Safeguards 2.55x10
-4 5.09x10
~4 7.64x10
~4 1.02x10
-3 1.27x10-3 Unit 2 Safeguards 2.55x10
~
5.09x10
~0 7.64x10
~4 1.02x10
~3 1.27x10
-3
~4 ~ ~
~4 -4 Auxiliary 1.34x10 2.67x10 4.01x10 ' 5.34x10 6.68x10 f
Number ~of Operating Fans Building 6 7 8 9 10 Fuel Handling 1.17x10-3 1.37x10
-3 1.56x10
~3 1.76x10
-3 1.95x10~3 c
Unit 1 Safeguards 1.53x10
-3 1.78x10
~3 2.04x10
-3 2.29x10
-3 2.55x10 -3 n
Unit 2 Safeguards 1.53x10
-3 1.78x10
-3 2.04x10
~3 2.29x10
~3 2.55x10
-3 Auxiliary 8.02x10
~0 9.35x10
-4 1.07x10
-3 1.20x10-3 1.34x10 ~3 L
s. ~ Number of Operating Fans , Building 11 12 13 14 U Fuel Handling 2.15x10
~3 2.34x10
-3 2.54x10
~3 2.73x10
-3 Unit 1 Safeguards 2.80x10" 3.06x10
-3 3.31x10
-3 3.57x10
-3
( _.a' -3 -3
~3 ~
Unit 2 Safeguards 2.80x10 3.06x10 3.31x10 3.57x10 ' ~
-3 -3 1.87x10
-3 Auxiliary 1.47x10 1.60x10 1.74x10 l
^ EE , T Z T. ~ 7 7 7 .J.TE.~~ T Z Z T ~ Z i . E".2 F U '~'!.7 "! ~ T.1..
w _ _ y - -- =_ . j. CPSES ISSUE DATE PROCEDURE NO. j EMERGENCY PLAN MANUAL JM 09 M EPP-300 y . 'Ih3 d 1 MANUAL CALCULATION OF RELEASE RATES REVISION NO. 2 PAGE 70 0F 75 1 ATTACHMENT 19 PAGE 6 0F 7 BUILDING EXHAUST REMOVAL RATES ' 4 I l 2.2.3 Partial Damper Flow Restrictions 1
] The contribution to the total exhaust from the different ! buildings can change dramatically depending on the position of } the dampers within the ventilation system. To determine the J
building exhaust removal rate to be used in Attachment 13 under partial damper restrictions the following equation should be i used: 3 l Number of Building j Building Exhaust = Building Exhaust X Exhaust Ducts Open Removal Rate Removal Rate Total Number of
, (2.2.2) Ventilation Exhaust j Ducts Open 1
For conservativeness in these calculations it is assumed that the }l ' (h t ventilation system exhaust removes that the ventilation system exhaust removes air equally from any open ducts and that any l ducts which are even only partially open are considered to be fully opened for release rate estimation purposes. 3.0 Plant Stack Flow Rate {; The plan stack exhaust flow rates are dependent upon the number of primary a plant ventilation fans which are opeating at a particular point in time. The j stack flow rates-listed in the following table represent the flow rates coming out of each individual plant stack. These values were derived using
- the following assumptions; 1) the flow rate is evenly divided between the two plant stacks 6 2) the design flow rate of each primary plant ventilation fan is 7.08 X 10 cc/see and 3) there is no flow reduction due to damper restrictions or other factors. The flow rate values are expressed in units of cc/sec.
] i l f
,g -.= ,
") *M "'gT".*'l -
"* P " ? ^ .e'# P ' . "
- T Y" C
l CPSES ISSl'E DATE PROCEDURE NO. j- EMERGENCY PLAN MANUAL M 09 M EPP-300
- - MANUAL CALCULATION OF RELEASE RATES REVISION No. 2 PAGE 71 0F 75 j~
A I ATTACHMENT 19
^
) PAGE 7 0F 7 d
si BUILDING EXHAUST REMOVAL RATES I
] ! Stack Number of Operating Fans 2 3 4 5 6 7 f 1 0 0 A 3.54x10 7.08x10 1.06x10 1.42x10 1.77x10 2.12x10 2.48x10 6 6 7 7 B 3.54x10 7.08x10 1.06x10 1.42x10 1.77x10 2.12x10 2.48x10 i
- 1 9
l Stack Number of Operating Fans 8 9 10 11 12 13 14 7 7 7 7' A 2.83x10 3.19x10 3.54x10 3.89x10 4.24x10 4.60x10 4.96x10 I 7 7 B 2.83x10 3.19x10 3.54x10 3.89x10 4.24x10 4.60x10 4.96x10 (). i! j -
!i a
1 _et. 4
;i -
e
--,e , +a= +=e v ee =+ *. m o p. = -p.e, y- mgm-ae - ,S-e e = > ne e- *7-*=y* %* 7 +*
- 1ry *t- 9 * '-~"-'**+te a,** y,*r
, . - . - . a _ -- _ . - - - . _ . .
b - i CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL g gg g EPP-300 l I
) k MANUAL CALCULATION OF RELEASE RATES REVISION NO. 2 PAGE 72 0F 75 ATTACHMENT 20 }' ; PAGE 1 0F 4 y
i DESIGN BASIS ACCIDENT DATA A. General Information g A.1 The Design Basis Accident information contained in this attachment is a utilized for dose projection purposes in the event the Digital Radiation Monitoring System is inoperable and the time required to obtain in-plant sample analyses results is too great. Because of the extreme h- conservativeness of this data, it should only be used as a last resort. j - The release rates found in the following paragraphs were generated by dividing the activity released to the environment during the first two hours by 7200 seconds. These values are just the average release rates r during this particular time period. 7 i A.2 When the use of this information is required caution must be used to f ensure that the design basis accident information chosen is from an accident scenario that is very similar to the incident situation in h progress.
- @ A.3 The information used is entered directly on Form EPP-302-1 and used in p
a projecting offsite doses in accordance with the requirements of EPP-302,
" Manual Assessment of Radiological Conditions".
, A.4 Two sets of data can be found for each situation. The conservative data f represents a worst case basis situation while the realistic data represents what is actually expected as a result of safety equipment 2 operation (i.e. charcoal filtration). If it is suspected that one or b . more similar systems are inoperable the conservative data should be used. If everything appears to be operating normally then the realistic data should be used. I Release Rate Data
- B.
't i B.1 Loss of Coolant Accident
] This data should be used to estimate the offsite doses as a result of a j loss of coolant accident. These values were arrived at using the parameters and assumptions found in Table 15.6-9 of the CPSES Final Safety Analysis Report (FSAR).
f 5 F G
%y3 3m;3 , mm m :
-33 y . 3 , y g .; m . m p y n .-
~ - '
_ .; 7 .. . , . _ I l CPSES ISSUE DATE PROCEDURE NO.
]
EMERGENCY PLAN MANUAL JAN 09 25 EPP-300 m
. 4[j MANUAL CALCULATION OF RELEASE RATES REVISION NO. 2 PAGE 73.OF 75 4
ATTACHMENT 20
^
J PAGE 2 0F 4 l Release Rates (C1/sec) Isotopes Conservative Realistic r Total Noble Gas 2.33 x 10 -2 1.57 x 10-5 Xe-133 1.82 x 10-2 1.39 x 10-5 Kr-85 2.13 x 10 -3 2.08 x 10 -8 ?t Total Iodine 5.28 x 10-3~ 1.31 x 10
-6 a
3 I-131 2.5 x 10 -3 4.03 x 10 -7 i I B.2 Main Steam Line Break i J This data should be used to estimate the offsite doses as a result of a main steam line break accident. These values were arrived at using the parameters and assumptions found in Table 15.1-3 of the CPSES FSAR. l
.Q Isotopes Release Rates Conservative (Ci/sec)
Realistic
-2 ; Total Noble Gas 9.12 x 10 1.10 x 10-5 ! Xe-133 6.46 x 10 -2 9.44 x 10 -6 Kr-85 7.49 x 10 -3 1.31 x 10 -8 Total Iodine 8.37 x 10 ~3 1.32 x 10 -6 .! - I-131 3.34 x 10 -3 4.63 x 10 -7 J
i i 7 B.3 Steam Generator Tube Rupture
! This data should be used to estimate the offsite doses as a result of a i steam generator tube rupture. These values were arrived at using the j parameters and assumptions found in Table 15.6-2 of the CPSES FSAR.
i 1 i= 1 b o
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4
,_ , , - _ , , . - . 7,. - - c,,,._ _ , - , - - _ . . c....
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., CPSES ISSUE DATE PROCEDURE NO.
j EMERGENCY PLAN MANUAL JM OS 1985 EPP-300 1 j MANUAL CALCULATION OF RELEASE RATES REVISION NO. 2 PAGE -74 0F 75 1 j ATTACHMENT 20 PAGE 3 0F 4 Release Rates (C1/sec)
) Isotopes Conservative Realistic
~
l Total Noble Gas 2.47 4.71 x 10
-2 Xe-133 2.26 4.06 x 10 j Kr-85 7.1 x 10 -2 5.61 x 10-5 4.1 x 10 -6
-4
) Total Iodine 8.58 x 10 1.11 x 10 -6
' ~
I-131 2.14 x 10 * 'l
; B.4 Rod Ejection i
i This data should be used to estimate the offsite doses as a result of a
$ rod ejection accident. These values were arrived at using the parameters and assumptions found in Table 15.4-4 of the CPSES FSAR.
h Isotopes Release Rates Conservative (Ci/sec) Realistic i
-I ~
j Total Noble Gas 3.75 x 10 3.23 x 10 ' 1.02 x 10 ~I
~
Xe-133 2.18 x 10 ' Kr-85 3.20 x 10 ~3 2.53 x 10-5 Total Iodine 1.92 x 10 -3 2.89 x 10 -6 1.17 x 10 -6 " -4 I-131 3.01 x 10 i B.5 Fuel Handling Accident _ This data should be used to estimate the offsite doses as a result of a i fuel handling accident. These values were arrived at using the parameters and assumptions found in Table 15.7-7 of the CPSES FSAR. 1 l
! E)
I 1 i f
.m.7,p .- .,. ,- .c y .eem;.--ur -.>.~L7..---..,,~. ,;- e-
, - .7 s 7 ++- 7 yy pg
m _ . _ .g._.. _ z , CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL EPP-300 JAN 09125 MANUAL CALCULATION OF RELEASE RATES REVISION NO. 2 PAGE 75.0F 75 l . i ATTACHMENT 20 PAGE 4 0F 4 ^ l f Release Rates (Ci/sec) Isotopes Conservative Realistic Total Noble Gas 14.48 9.37 x 10 -1
; Xe-133 13.89 8.99 x 10 -1 Kr-85 3.56 x 10-1 2.29 x 10 -2 Total Iodine 4.08 x 10 -3 5.27 x 10-5 I-131 3.65 x 10 -3 4.72 x 10-5 B.6 Radioactive Liquid Waste System Leak or Failure l
! This data should be used to estimate the offsite doses as a result of a leak or failure in the radioactive liquid waste system. These values
- vere arrived at using the parameters and assumptions found in Table i 15.7-4 of the CPSES FSAR.
)
; Release Rates (Ci/sec)
- Isotopes Conservative Realistic j.
. Total Noble Gas - - i l Xe-133 - - i j Kr-85 - - 1.54 x 10 -3
-2 Total Iodine 1.29 x 10
! I-131 3.15 x 10 ~3 3.78 x 10
-4 4
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j i$ h j COMANCHE PEAK STEAM ELECTRIC STATION 1 1 - EMERGENCY PLAN MANUAL
'! kg./
i . 'l l i .I 1 COMPUTER ASSESSMENT OF RADIOLOGICAL CONDITIONS !} 6 , .. I h) PROCEDURE NO, EPP-301 REVISION NO. O cos f' ggBMRMED, t a; , C COPY h CO 1 <
/f llf SUBMITTED BY: x d DATE: /- ! SUPRINTENDENT, SOPPORT SERVICES
- i / /
APPROVED BY: [ //t/ ? DATE:/4 S# [V
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/ MANAG,5K, NUCLEAR OPERATIONS l
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i ^ CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL OCT 261984 EPP-301 1 4 9 COMPUTER ASSESSMENT OF i UI . ,
, RADIOLOGICAL CONDITIONS REVISION NO. O PAGE 2 0F 65 0
li j M1'.0 Puhpose
- ) .,
j Th4 purpose of this procedure is to provide guidance to dose assess-
] . _ , . ment personnel in estimating offsite dose rates and integrated doses -
] using the RM-21 system.
\ *
- b. .
j 2.0 Applicability.
.) . 2 0 This procedure is applicable to the Shift Technical Advisor, iW
~ Onsite Radio 1cgical Assessment Coordinator, Offsite Radiological Assessment Cuordinator, Radiation Protection Coordinator and those CPSES Emergency Organization Radiological Assessment personnel who are responsible for ensuring that offsite dose g
projections are performed. 1 2.2 This procedure shall be implemented in the following manner: 1 1 2.2.1 Prior toiactivation of the Technical Support Center (TSC), the on duty Shif t Technical Advisor shall implement this procedure as time permits and as requested by the Shift
- Supervisor. -
h 2.2.2 Following activation of the TSC, but prior to the activation of the Emergency Operations Facility (EOF), the p Onsite Radiological Assessment Coordinator shall implement i this procedure. The on duty Shift Technical Advisor (CR) should cease release calculations / dispersion / dose accumulations. 2.2.3 Upon activation of the E0F, the Offsite Radiological
., Assessment Coordinator shall implement this procedure. ,
The onsite Radiological Assessment Coordinator (TSC) should cease release calculations /disper'sion/ dose accumulations.
) #
3.0 Definitions '- c -
3.1 Channel
A channel is the medium for measuring and/or recording
. effluent releases. There are two kinds of channels; real and dusuny. A real channel is associated with a single channel on an b RM-80 effluent monitor. A real channel provides averaged measurements of ef fluent releases in units of microcuries/sec. A dummy channel is an artificial construct that allows manual entry of effluent release data.
L Every channel, whether real or dummy, is associated with an
.. effluent pathway.
Each channel in an RM-11/RM-21 RAM-300 system is identified by a unique six-character code called a channel name. si t l 4 l 4 . N35 Q} M E E Q WE5 F W '.* */" ";E
' ~ " '
m . .wr ..w . -, ; . 7 --- ., ,-- . _ . l l- CPSES
- ISSUE DATE PROCEDURE NO.
EMERGENCY PLAN MANUAL ""-'* OCT 261984 h COMPUTER ASSESSMENT OF 1 h RADIOLOGICAL CONDITIONS REVISION NO. O PAGE 3 0F 65
3.2 Depletion
In the context of offsite dose calculations, depletion means the lessening of content, concentration or value .
; of. ionizing radiation during release and transport.
i 4
3.3 Deposition
Referring to airborne or liquid radioactive
- substance settling onto a surface.
3.4 Dispersion / Dose Accumulation The maximum individual dose is computed using the dispersion / dose accumulation program. The cumulative dose to each receptor in all sectors of the EPZ is calculated for a user-specified time period. A cumulative dose file may be updated with the results - of these calculations to provide a summary of doses over the full h term of the effluent release. Two file types, designated as LAST j and TOTAL are provided to implement the accumulation feature. j' The dispersion / dose accumulation program writes results of calculations on the LAST (latest) files. A print routine which is associated with the calculational routines allows review and t printout of the results on the LAST file or these results may be f added to previous results in the TOTAL file. l h The flexibility provided by the LAST and TOTAL files requires that attention be paid to the dates of data stored on the respective file. The start and end date of data is provided by { . i l all routines where manipulation of LAST and TOTAL files is F allowed. Y
- Doses are evaluated over a given time period following an y accidental release for the following pathways
- 1. Whole-body (gansna} dose from immersion in the plume
- 2. Whole-body (gamma) dose from shine from the overhead plume j ; 3. Skin dose from immersion in the plume 3
- 4. Thyroid dose to children from iodine inhalation i 5. Thyroid dose to inf ants from milk ingestion a
4
- The item 1, 3, 4 and 5 doses are centerline values while the item j- 2 dose is the sector average value. All radionuclide i concentration values used in the dose calculations are determined
] taking into account decay of act.ivity during transport. Twenty receptor locations are evaluated for each sector out to 50 miles. 3
.e. The results of the individual dose computations are available as
^
contour plots on the terminal screen. The data in the cumulative dose file may also be compared to preset technical specifications i - a mzm276t?vb "D%WT";_ , 3 __ X Q T ' 7 Q .W v' ""V7 T v ~ ^ ~ ,~ ,
- _:~-
CPSES ISSL'E DATE PROCEDURE NO. i EPP-301 EMERGENCY PLAN MANUAL ggg j ,.3 COMPUTER ASSESSMENT OF i '[g RADIOLOGICAL CONDITIONS REVISION No. O PAGE 4 0F 65 or Protective Action Guide limits and these results may also be k displayed on terminal screen. This plot provides plant operators with an assessment tool with which to quickly evaluate conditions in the EPZ. 3.5 Dose: A quantity of radiation absorbed or adsorbed by body tissue, organs or the whole body. f 5 3.6 Dose Rate: Absorbed dose delivere,d per unit time (units are in rea/hr.), t 3.7 Effective Age: Effective age is defined as the time elapsed from the instant reactor core power generation was halted until the { dose is received from the released mixture. The effective age ( consists of two time components: (1) effective age at the time t of the onset of the release, and (2) the transit time from the [ point of release to the arrival at the key locations. I 3.8 Emergency Classification: A classification system of emergency
, severity based on. operational, radiological and meteorological conditions at or near the plant site.
{ i y h 3.9 Emergency Conditions: Situations occurring which cause or may threaten to cause radiological hazards affecting the health and i safety of onsite personnel or the public, or which may result in g damage to property. 3.10 Emergency Planning Zone (EPZ): That area surrounding the Station in which emergency preparedness planning is conducted for the i protection of the public. With respect to protecting the public l from the plume exposure resulting from an incident, the EPZ f . encompasses an area with a radius of approximately 10 miles { surrounding the facility. With respect to the ingestion exposure pathway, the EPZ encompasses an area with a radius of about 50 miles.
; 3.11 Exclusion Area Boundary (EAB): That area surrounding the -
3 Station, in which the utility has the authority to determine all I activities including exclusion or removal of personnel and property from the area.
]
2 y 3.12 Gaseous Release Isopleth Calculations i The gaseous release isopleth program provides rapid estimates and projections of atmospheric effluent transport and diffusion d during and immediately after an accidental release of radioactive gaseous effluent. The purpose of these projections is to provide g'. input to support the assessment of the consequence of such a release to the atmosphere and to help make appropriate emergency l response decisions, i .
- k. _ .
.. .~~ , . . . ..
m_ , CPSES VSSUE DATE PROCEDURE NO.
] EMERGENCY PLAN MANUAL EPP-301 007 2R 1ond 1 COMPUTER ASSESSMENT OF j h RADIOLOGICAL CONDITIONS REVISION NO. O PAGE 5 0F 65 1
il t
? Dose rates for the following pathways are evaluated:
i . i 1. Whole-body (gamma) dose from immersion in the plume 1 1 2. Whole-body (gamma) dose from shine from the overhead plume - 4 9
- 3. Skin dose from immersion in the plume
]
- 4. Thyroid dose to children from iodine inhalation
- 5. Thyroid dose to infants from milk ingestion t The item 1, 3, 4 and 5 doses are centerline values while the item q 2 dose is the sector average value. All radionuclide 4
concentration values used in the dose calculations are determined taking into account decay of activity during transport. I Dispersion, whole body gamma dose, skin dose, child inhalation thyroid dose and infant milk ingestion thyroid dose are computed in two dimensions (downwind and crosswind) from a selected release point. Sixteen crosswind values for each of 32 downwind I values are computed for each of the five calculated quantities. () The results of these computations are available as iso-dose contours (isopleths) plotted on a graphics CRT screen or as tabular-form printouts on a.nongraphics terminal or line printer. The contour lines are plotted on a background map of the reactor site. 3.13 Insolation: The rate of delivery of all direct solar energy per
; unit of horizontal surface. ;t i "
3.14 Normalized Relative Concentration (Xu/Q): The normalized
] relative concentration is a measure of the dispersion i characteristicsofanairmassasdeterminedbytheexisyng atmospheric stability classification (units are in meter ).
3.15 Pasquill Atmopsheric Stability Classifications: The Pasquill -- i atmospheric stability classifications are a measure of the stability or instability of an air mass based upon the vertical
) temperature differential between two points. At CPSES, this u temperature differential is determined between the 60 meter and j- 10 meter levels of the primary meteorological tower.
3,16 Projected Dose: That dose of ionizing radiation that is likely j to be received by a population group if no protective action measures are implemented. 3.17 Protective Actions: Those emergency measures taken for the fi ]k purpose of preventing or minimizing radiological exposures to y affected population groups. 2 i . J
~. -..m 7- ~ .m - -.- - y .g. ~~~~~.7-,-s.. .. -. . .. --..yv.,-- . . . . , . - . .
}
CPSES ISSE DATE PROCEDURE NO. I EMERGENCY PLAN MANUAL EPP-301 3, - OCT 261984 i COMPUTER ASSESSMENT OF (f4._.,? RADIOLOGICAL CONDITIONS REVISION NO. O PAGE 6 0F 65 i l
- 3.18 Protective Action Guides (PAG): Projected radiological dose j values to individuals in the general population that warrant .
;j protective action. Protective actions would be warranted
; provided that the reduction in individual dose expected to be
} achieved by carrying out the selected protective action is not -
offset by excessive risks to individual safety in taking that protective action. W n I 3.19 Receptor Location: The receptor location is a point in the af fected downwind sector which will be used as a reference point at which offsite doses are calculated. j 3.20 Receptor Distance: The receptor distances is the number of miles
.j (meters) between the receptor location and the point of release.
3.21 Relative Concentration (X/Q): The relative concentration is the
] normalized relative concentration divided by the wind speed in ! meters per second (units are in sec/ meter3 ).
i j 3.22 Release Point: A release point is a set of channels. The j channels in a set may be real, dummy, or both. No channel may be i assigned to more than one release point. In addition, all Q channels for a given release point are of a single generic type, gas or liquid, consistent with the type of effluent. Similarly 1 each release point is a single generic type, gas or liquid, consistent with the type of effluent. A release point (up to 8 for a given unit) is identified by its number (1 through 4) and type. 3.23 Release Rate: The average quantity of radioactive material released to the environment from a nuclear power reactor during normal operations and anticipated operational occurances. J" 3.24 Source Term: In the context of offsite dose calculations, this term refers to the isotopic distribution of radioactive materials i used in evaluating the impact of radioactive releases on the ,
)i environment. -
1 4 3.25 Unit: A unit is a set of release points. It is usually a set associated with a physical unit in a nuclear plant. Up to 8 i release points (4 gas and 4 liquid) are allowed in a unit. No .j release point may be assigned to more than one unit. A unit is o identified by a 2-character identifier U1 or U2. a j 3.26 Wind Direction: Wind direction is the direcion from which the
- wind is blowing.
3 J d,., e 9 'wm ew s-emm e M
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_.- -H -- > _ 3-CPS ES - ISSUE DATE PROCEDURE NO. EMERGENCY PLAN. MANUAL EPP-301 '4 ' OCT 261984 COMPUTER ASSESSMENT OF j () RADIOLOGICAL CONDITIONS REVISION NO. O PAGE 7 0F 65 y 4.0 Instructions l . 4.1 Precautions 4 4.1.1 Ensure that the meteorological data acquisition system is operating properly. ,3 4.1.2 Ensure that either the effluent release monitors are
; operating and providing input to the RM-21 or the release q rates and isotopic mix are known.
[' 4.1.3 Prior to generating hard copies of displayed data, ensure that hard copy device is "0N" and in working order. Allow j sufficient warm up time. i 4.2 Initial Actions The RM-21 system allows evaluation of accident situations at two
. levels of resolution. . The highest resolution level uses 15-min meteorological ~ data and 10-min radiological data to produce s Gaseous Release Isopleths that allow rapid evaluation of the direction of plume travel for the period of 15 min to 2 hr af ter 3
j (]) the onset of the accident. These data are also used with the emergency dose accumulation routine to do detailed analyses of the integrated effects of the release (i.e. , dispersion / dose
,l accumulation). The lowest level of resolution uses the hourly 1 data files in conjunction with the routine analysis sof tware as backup for the 15-min data calculations.
4.2.1 Loa-on Depress the return key on the terminal. Within a few seconds, the prompt ">" should appear.
Response
I Enter: "YOUR PASSWORD" -- Depress: Return Key
't The following should be displayed:
i WELCOME TO RSX-11M V3.2 TIMESHARING 1 1 * *
- RM-21 SYSTEM * *
- d a
2 Enter: RM-21 ( _ ,, N.i Depress: Return key to enter
._. .<-.s.-<= ,op * -7"'r=*** =q e** *e*+ %~~- r;*=<=**=e -e.*-t=*Pe* - .*e-*
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- we-y e-*= w==
_ = %
, -. . . . , . . . , _ . , .,-- u, - , , i - , . - , -. - .
7 _ i [j CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL EPP-301 OCT 26 m COMPUTER ASSESSMENT OF l (., RADIOLOGICAL CONDITIONS REVISION NO. O PAGE 8 0F 65 Enter: Your initials. 4 . Depress: Return key.
>4 Enter Site: CP 1
i 1 b Depress Return Key A j Enter Unit: 1 ] Depress Return Key 'i j 4.2.2 The RM-21 should respond by displaying the site, unit, .; user, current date and time and the Level 1 options list. j For RM-21 Emergency Release Calculations Options Tree, see j Attachment 1. a j NOTE: If difficulty is encountered, repeat the above sequences, j If log on still cannot be achieved, consult a system i specialist or the RM-21 User Manual E-115-1220, Section ]' entitled "Using the RM-21" or implement EPP-303,
" Emergency Dose Assessment Supplemental Computer Program".
'l - [' '] RM-21 OPTIONS (Level 1) l
- 1 - Terminate 2 - Site Specific Data Base Creation and Editing 3 - Radiological Data Collection and Processing g 4 - Meteorological Data Collection and Processing j 5 - Routine Release Calculations a 6 - Emergency Release Calculations 7 - Miscellaneous '
f For Emergency Release Calculations Options: 2 )s 4.2.2.1 Depress Numerical Key #6. ) 4.2.2.2 Depress Return Key to Enter. l - 4 4.2.3 The following Level 2 option list should be displayed. Select the desired emergency function. EMERGENCY RELEASE CALCULATIONS OPTIONS (LEVEL 2) 4 l 1 - Return to Level 1 2 - Data Base Edit and Review l 3 - Gaseous Release Isopleth Calculations 4 - Dispersion / Dose Accumulations l
. . . ._ _ - - . ._,._.n_ y,_,_,..,,.,._
7, ,
~ -
- - - - - z- _ - . _
I CPSES ISSUE DATE PROCEDURE NO.
.i EMERGENCY PLAN MANUAL OCT 261984 EPP-301
- 1 COMPUTER ASSESSMENT OF
) h-. RADIOLOGICAL CONDITIONS REVISION NO. O PAGE 9 0F 65 1
i
) NOTE: For Option 2 continue. ! For option 3, turn to para. 4.2.5. ] For Option 4, complete Option 3 first.
4.2.4 The DATA BASE EDIT AND REVIEW provides functions to create j and review portions of the emergency data base. This
;i review can be made using printed reports or output plotted j -
on the graphic display terminal with hard copy capability. j Meteorological data and radiological release rate data may 1 be plotted to allow review of the data base used in the [ emergency dispersion / dose accumulations. The options available for data base edit and review are
;) selected from the following level 3 options list.
3 4 4.2.4.1 DATA BASE EDIT AND REVIEW OPTIONS (LEVEL 3) 3-
- j. 1 - Return to Level 1 3
2 - Emergency Q-File Editing j 3 - Emergency Data Graphic Display
]; Option 2, Emergency Q-File Editing, is ] h subdivided by the option list shown below. ..l 4.2.4.1.1 Emergency Release Q-File Editing q Options 9
4 1 - Terminate j Edit 10-Min Real-Time Release
) Q-File j 3 - Edit Postulated Accident Q-File ] 4 - Edit Simulated Release Q-File f
j Option 2 is used to enter, edit or 1 -review the latest 10-minute emergency J release Q-file-data. These data are
) used by either the Gaseous Release -
} Isepleth Calculation Option or the
- Dispersion / Dose Accumulation Option.
Refer to Attachment 2 for additional
, details.
s Option 3 is used to create a Q-file
; containing as many as 10 postulated j accidents. These data are used in conjunction with the Gaseous Isopleth Calculation Option. Refer to ' [, Attachment 3 for additional details.
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1 1 j CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAI, EPP-301 OCT 261984 COMPUTER ASSESSMENT OF I h RADIOLOGICAL CONDITIONS REVISION NO. O PAGE 10 0F 65
)_
Option 4 is used to create a Q-file ( i allowing entry or edit of a simulated - [ release to recreate a previous
; condition or to create a hypothetical i situation. These data are used in ) conjunction with the Dispersion / Dose Accumulation Option. Refer to l Attachment 4 for additional details.
[ ' p j option 3, the Emergency Data Graphic Display, is subdivided by the option list shown below, i 4.2.4.1.2 Emergency Data Graphic Display Options L 1 - Terminate 2 - Meteorological Trend Plots 3 - Radiological Trend Plots 4 - Vent Flow Trend Plots a Option 2 is used to plot data in the 15-min meteorological or 15-min h workspace file. See At,tachment 5, Examples 1 and 2. Option 3 is used to plot data in the I 10-minute emergency Q-file or the
- 1. simluated release Q-file. For f examples of prompts to produce a 10-minute data gaseous trend plot and t -
a plot, see Attachment 6, Examples 1 and 2. j Option 4 is used to plot vent flow j data in the simulated release Q-file, f. Upon completion of data base edit and review - functions, depress return key as many times as is necessary to return to the level 2 " Emergency Release Calculations" options list. Continue
! with option 3 (Gaseous Release Isopleth 4
Calculations). 4.2.5 Gaseous Release Isopleth Calculations The GASEOUS RELEASE ISOPLETH option 3 provides operators with a tool for rapid assessment of dispersion and dose during and immediately after an accidental release of radioactive gaseous effluent. Dispersion, whole body gamma dose, skin dose, child inhalation thyroid dose, and I l 1
)
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d CPSES ISSUE DATE PROCEDURE NO. EMERCENCY PLAN MANUAL EPP-301 OCT 261984 COMPUTER ASSESSMENT OF
]
RADIOLOGICAL CONDITIONS REVISION NO. 0 PAGE 11,0F 65 f p infant milk ingestion thyroid dose are computed in two dimensions (downwind and crosswind) for all "on" release . [ points and optionally may be printed in tabular format or plocted as lines of constant dispersion or dose overlayed on a site map. The Gaussian centerline plume model is used for the dispersion calculations, g The X/Q cnd related dispersion calculations use data from j the hourly or hourly workspace files, the 15-min or 15-min
- workspace files, the most recent data files or manually
[ entered data (see Attachment 7). The type of release for CPSES will be ground only. Elevated, or wake-split are not used. Refer to parameter 3 of the RELEASE POINT f PARAMETERS option list [2,2,2]. e Dispersion and dose results for the five calculated f < quantities are computed simultaneously and stored in memory to allow review of all results without recalculation. Results may be reviewed at the graphics g terminal and saved using the hard copy device or may be printed on the printer. h
- 4.2.5.1 Once Option 3 of the Emergency Release Calculations List has been selected depress
! return key. The following prompts requiring operator responses will be displayed: GASEOUS RELEASE ISOPLETH CALCULATIONS RELEASE POINT STATUS j 1 -- ON 2 - ON 3 -- 0FF 4 - 0FF NOTE: 1 = MAIN STEAM i 2 = VENT STACK
} 3 = UNASSIGNED 4 = UNASSIGNED -
I ENTER RELEASE POINT [1-4]: . j RESPONSE: 2 1 i DO YOU WANT SUBMERSION [ S ] OR FINITE [ F ] GAMMA?: (Finite not used at CPSES.) RESPONSE: S l
] DO YOU WANT TO ENTER MET AND RAD DATA MANUALLY?
[Y OR N]:
! RESPONSE: N e
i, .
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g-CPSES ISSUE DATE PROCEDURE NO. hi EMERGENCY PLAN MANUAL OCT 261984 EPP-301 I ' I COMPUTER ASSESSMENT OF h; RADIOLOGICAL CONDITIONS REVISION NO. O PAGE 12 0F 65 DO YOU WANT TO USE THE MOST RECENT MET AND RAD DATA? [Y OR N]: . t E RESPONSE: Y NOTE: In the event that the most recent met f or rad data are not available, .j continue to follow the prompts. Upon ] completion the system will return to j this point. u .j ENTER MAXIMUM DOWNWIND DISTANCE IN MILES [ j N.N > 0.5 ): 10 .i
- 7. (10 = EPZ, 50 = Maximum Distance)
)j ENTER [ C ] TO ERASE SCREEN AND CONTINUE: C 3 The following prompt should be displayed: d 3 - - - DATA BEING PROCESSED - - - The Gaseous Release Isopleth Calculations data
'Q 4.2.5.2 summary containing the following information should now.be displayed:
4.2.5.2.1 Site, Unit, User and Date } 'l ]q. 4.2.5.2.2 , Gaseous Release Data Summary I 4.2.5.2.3 Summary of Meteorological Data
- (
.] NOTE: Each printed numerical value is j followed by one of the following 1 alphanumeric symbols: P, S, T, M or i *. These symbols indicate the source d of the data and have the following _ meaning: P - PRIMARY S'ENSOR DATA
] S - SECONDARY SENSOR DATA 1
j T -- TERTIARY SENSOR DATA i ] M -- MANUALLY ENTERED DATA 3
, * -- DATA NOT APPLICABLE FOR THIS b.C- RELEASE TYPE 4.2.5.2.4 Summary of Isotopic Release Rate Data 1 (Micro-ci/Sec)
~
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, e e.;- _ , , ; - { T g . M p p { m *?J g. g .g g) ylg;g*,- Q 'f.g!' g . y -~
_ . _ _ , j . _ ._ _ _ . . . . . _ _ . . _ . . mr. _; _ 1 CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL OCT 26 984 EPP-301 s 1 COMPUTER ASSESSMENT OF ff; RADIOLOGICAL CONDITIONS REVISION NO. O PAGE 13 OF 65 4.2.5.2.5 Sum.ary of Effluent Discharge Rate t (i.e., Vent Flow Rate) - { 4.2.5.2.6 Peak X/Q and Dose Rate at or Beyond j Site Boundary 't
! NOTE: An example of the data summary N is given in Attachment 8. )
j 4.2.5.3 After reviewing the data, a hard copy may be i made of all data displayed. Ensure that the i hard copy device is turned on and has had sufficient warm up time.
- 4.2.5.3.1 Depress copy switch above and to the
! right of the keyboard. A hard copy
- will automatically be generated.
j
] 4.2.5.4 If the hard copy is satisfactory. enter "C" to .
j erase screen and continue: C The following options and prompts will be displayed: OPTIONS [ 1 -- X/Q ISOPLETH 2 -- WHOLE BODY GAMMA ISOPLETH 3 -- SKIN ISOPLETH 4 -- INHALATION THYROID ISOPLETH 5 -- MILK INGESTION THYROID ISOPLETH NOTE: The option selected will depend upon the isotopes released or the type of j accident selected if postulated j accident data is selected. d l ENTER OPTION SELECTION [1-5]: l s DO YOU WANT RESULTS PLOTTED? [Y OR N]: Y DO YOU WISH TO MODIFY CONTOUR INTERVAL SPACING?
. {Y OR N]: N k NOTE: Under stable atmospheric conditions j
; the plume will be very narrow j resulting in very close spacing of the concour lines on the isopleth. To (b3 -
t I modify interval spacing refer to l; Attachment 9, Examples 1 and 2. i
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a
- f. CPSES ISSUE DATE PROCEDURE NO.
4 EMERGENCY PLAN MAW AL EPP-301 OCT 261984 c, COMPUTER ASSESSMENT OF l w) .- RADIOLOGICAL CONDITIONS REVISION NO. O PAGE 14 0F 65 i ENTER [C] TO ERASE SCREEN AND CONTINUE: C 4 j The plot plus tabular data should be displayed
) on the CRT.
4 j If a hard copy is desired, ensure that all data
; are displayed before depressing the copy switch.
Refer to section 4.3 " Subsequent Actions" prior
; to continuing.
j 4.2.6 Dispersion / Dose Accumulation i i The DISPERSION / DOSE ACCUMULATIONS option (4) provides the operator with several functions to compute and review the
- f. integrated effects of a release over a specified time
! period. The available options are as follows.
l EMERGENCY DISPERSION / DOSE OPTIONS j 1 - Terminate t- _ 2 - Dispersion / Dose Calculations 3 - Print Dispersion / Dose Results [ i (J 4 - Plot Dispersion / Dose Results [ 5 - Receptor Exposure Plot
.e 4
I Details of the options available on the Emergency Dispersion / Dose Calculations option list are presented as attachments which include descriptions of the operator interface used with each option. I Option 2 is used to perform the dispersion and dose calculations (see Attachment 10, Examples 1 aind 2). Option 3 is used to print the accumulated results computed
$ by option 2 (see Attachment 11, Examples 1 and 2). } _.
d Option 4 is used to draw contour plots of dispersion or
. dose (see Attachment 12. Examples 1 and 2).
f Option 5 draws a circular plot which shows the integrated effects of a release within the emergency planning zone [.
; (see Attachment 13. Examples 1 and 2).
i 4.3 Subsequent Actions 4.3.1 All calculations and results shall be reviewed by the
. onsite Radiological Assessment Coordinator for accuracy
- 7) before release, b
3 e
]
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y ' W - , G l CPSES
- ISSUE DATE PROCEDURE NO.
EMERGENCY PLAN MANUAL EPP-301 OCT 261984 i j - 3 COMPUTER ASSESSMENT OF
, 'g RADIOLOGICAL CONDITIONS REVISION NO. O PAGE 15,0F 65 1
4 4.3.2 Any release should be evaluated using the classification criteria provided in EPP-201 " Assessment of Emergency . Action Levels, Emergency Classification and Plan Activation. 4.3.3 Protective actions shall be recommended as applicable in
- accordance with EPP-304, " Protective Action Guides."
5.0 References lt - 5.1 CPSES Emergency Plan, Section 7.1. 5.2 EPP-201, " Assessment of Emergency Action Levels, Emergency
) Classification and Plan Activation",
t 5.3 EPP-300, " Manual Calculation of Release Rates"
) 5.4 EPP-302, " Manual Assessment of Radiological Conditions" li 5.5 EPP-303, " Emergency Dose Assessment Supplemental Computer j Program" h 5.6 EPP-304, " Protective Action Guides" 5.7 C. A. Technologies RM-21 Report Processor User's Guide E-115-1220, May 1984
$( 6.0 Attachments 6.1 Attachment 1, RM-21 Emergency Release Calculations Options Tree e f 6.2 Attachment 2,Edkt 10-Minute Real Time Release Q-File-Prompts to $ Print Data for Relerse Point 2 h 6.3 Attachment 3, Edit 10-Minute Real Time Release Q-File-Prompts to 3 Edit Data for Ref. ease Point 2 g s , _- 6.4 Attachment 4, Edit 10-Minute Real Time Release Q-File-Prompts to Perform File Init_ialization 6.5 Attachment 5, A 15 Minute Data Meteorological Trend Plot { g 6.6 Attachment 6. Radiological Trend Plots 4 l 6.7 Attachment 7, Files Associated with Gaseous Release Isopleth y Calculation y 6.8 Attachment 8. Gaseous Release Isopleth Calculations - Data j Summary 4 5 . l 1 50 _ 5 n k$Yl I *
. - $0YN?AN t $ fk" i 2 fk
__ . _ ,r. . .. - i l- ,, H fi CPSES ISSUE DATE PROCEDURE NO. 1 EMERGENCY PLAN MANUAL g gg g EPP-301 COMPUTER ASSESSMENT OF f,,,
.) RADIOLOGICAL CONDITIONS REVISION NO. O L) PAGE 16.0F 65 r
i .j 6.9 Attachment 9. Gaseous Release Isopleth Calculations [ 6.10 Attachment 10, Dispersion / Dose Accumulation Prompts J fj 6.11 Attachment 11, Print Dispersion / Dose Results 4 6.12 Attachment 12, Plot Dispersion / Dose Results 6.13 Attachment 13, Receptor Exposure P. lot s a d (' 1 1 n
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! CPSES D PROCEDURE 50.
06Fks 6E4
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EMERGENCY PLAN MANUE EPP-301 .i
,c3 COMPUTER ASSESSMENT OF i G RADIOLOGICAL CONDITIONS REVISION NO. O PAGE 17.0F 65 j ATTACHMENT I j PAGE 1 0F 2 -
RM-21 Options for Emergency Release Calculations. . RM-21 OPTIONS (LEVEL 1)
; 1 - TERMINATE 2 - SITE SPECIFIC DATA BASE CREATION AND EDITING 3 - RADIOLOGICAL DATA COLLECTION AND PROCESSING 3
4 - METEOROLOGICAL DATA COLLECTION AND PROCESSING j 5 - ROUTINE RELEASE CALCULATIONS 6 - EMERGENCY RELEASE CALCULATION 7 - MISCELLANEOUS 9 3 1
\/
4
~
h EMERGENCY RELEASE CALCULATIONS (LEVEL 2) b 1 - RETURN TO LEVEL 1
- 2 - DATA BASE EDIT AND REVIEW
! 3 - CASEOUS RELEASE ISOPLETH CALCULATIONS 4 - DISPERSION / DOSE ACCUMULATION-4 N/ DATA BASE EDIT AND REVIEW OPTIONS (LEVEL 3)
~
]i 1 - TERMINATE I 2 - EMERGENCY Q-FILE EDITING -
, 3 - EMERGENCY DATA GRAPHIC DISPLAY la J
j- l l v V l { Continued on next page. ) I 1 1 1 wc m xw w w w w w w..; w ~ = -- = ~ -- - - T
.. . . ~_
i i CPSES D PROCEDURE NO. i EMERGENCY PLAN MANUAL 0@Uis 4 EPP-301
?
l COMPUTER ASSESSMENT OF hs RADIOLOGICAL CONDITIONS REVISION NO. O PAGE 18.0F 65 ATTACHMENT 1 h PAGE 2 0F 2 - l; V g + . l DISPERSION / DOSE ACCUMULATIONS (LEVEL 3) I 1 - TERMINATE 2 - DISPERSION OR DOSE ACCUMULATION 3 - PRINT DISPERSION OR DOSE ACCUMULATION [ 4 - PLOT DISPERSION OR DOSE RESULTS 5 - RECEPTOR EXPOSURE PLOT h i: v Q-FILE EDIT OPTIONS (LEVEL 4) t. [ l - TERMINATE y 2 - EDIT 10-MINUTE REAL-TIME RELEASE Q-FILE 3 - EDIT POSTULATED ACCIDENT Q-FILE f 4 - EDIT SIMULATED RELEASE Q-FILE ll c . l _ i .6 i 1
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4 CPSES ISSUE DATE PROCEDURE EO. I EMERGENCY PLAN MANUAL El>P-301 OCT 261984 COMPUTER ASSESSMENT OF
,1 gh
.q RADIOLOGICAL CONDITIONS REVISION NO. O PAGE 19,0F 65 t
ATTACHMENT 2 PAGE 1 0F 5 { EDIT 10-MIN. REAL-TIME RELEASE Q-FILE - 3 d The abbreviation "RTQ-file" will be used in the following pages to refer to yj the 10-min real time release Q-file.
)
.[, The appropriate prompts to enter a release point number will be displayed. After specifying which release point is being referenced, select which of
; the three options is to be performed.from the following list:
OPTIONS i 1 - PRINT DATA FOR THIS RELEASE POINT r P. 2 - EDIT DATA FOR THIS RELEASE POINT [ 5'. j 3 - CLEAR DATA FOR THIS RELEASE . POINT Each of these options is discussed in the following pages of this ? Attachment. [ Prine Data for This Release Point t ( 3 This option displays data in the RTQ-file for the specified release point. & The prompt to specify whether the data are to be displayed on the printer j or on the terminal appears. The data- are then displayed as shown in Example 1. 4-It h If no data record exists for the specified release point, the following g message is displayed: ]
*** NO DATA ON DISK FOR THIS RELEASE POINT X ***
h,t 4 (X = the selected release point). 1 t 1 . j Edit Data for This Release Point 1 This option allows the use to change existing RTQ-file data. The current data for this release point are displayed along with the following prompt: 4 '; DO YOU WANT TO CHANGE THE DATE? [ Y OR N ]: j A Y (yes) response will result in a prompt for a new date. j I' The next prompt is to enter the release mode if the current mode is not the desired one. , f
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. - - , r. ,
CPSES ISSUE DATE PROCEDURE NO.
], EMERGENCY PLAN MANUAL EPP-301 OCT 26 B84 . ! COMPUTER ASSESSMENT OF 1 b. ,. , RADIOLOGICAL CONDITIONS REVISION NO. O PAGE 20 0F 65
!i 0 ATTACHMENT 2 d PAGE 2 0:7 5 . 3 'J 1 ]i The system next prints out a list of al.1 gaseous isotopes and prompts for a number which corresponds to one of the 1sotopes. After entry of the i number, the system displays the current value that is stored in that record j for that isotope. The prompt to enter .a new value follows. The system then asks if editing of isotope data is to continue. If yes, the system }(; redisplays the isotope list and the opt; ion to select and change another
- isotope is given. This procedure may be repeated as many times as desired i
until no more modifications are to be made. An example of this option is shown in Example 2. Clear Data for This Release Point This option clears the RTQ-file for the selected release points. <[ The following message is printed when the clear is complete.
--- FILE INITIALIZATION COMPLETE ---
- An example of this option is shown in Example 3.
I: 5 l d
.1 3
4 k, 1 l 4 i (,.--.. -. .n. .-,----.-..;,. . e .-.- . . . . . . . . - . . . . . - - .- , . - . ~ . .
j . 4 CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL EPP-301 OCT 261984 i q COMPUTER ASSESSMENT OF 3 MS RADIOLOGICAL CONDITIONS REVISION NO. O PAGE 21.0F 65 i ATTACHMENT 2 f; PAGE 3 0F 5
^
EXAMPLE 1 EDIT REAL-TINE GASEQUS RELEASE Q-FILE a g ENTER RELEASE POINT C1-4] : 2 OPTIONS 1 - PRINT DATA FOR THIS RELEASE POINT 2 - EDIT DATA FOR THIS RELEASE POINT V [ 3 -- CLEAR DATA FOR THIS RELEASE POINT f ENTER OPTION SELECTION C1-3] : 1 t; REPORT ON PRINTER? C Y OR M ] : N ENTER I C ] TO EPASE SCREEN AND CONTINUE : C I SITE: SORRENIO VALLEY 0 UNIT: U1 I USER: EEE DATE: 4/23/84 11:24 P.EAL-TIME GASEQUS RELEASE 0-FILE DATA
} }
1 0 YALUES (NICRO-CI/SEC) FOR DATE: 6/ 1/79 0 0
) RELEASE POINT: 2 -
RELEASE M DE: CONTINUOUS j . ISOTOPES NOT PRINTED ARE ZERO i AR41 : 1.0000E+06 XE138 : 1.0000E+06 l l DO YOU WANT TO CONTINUE WORK WITH THIS OPTION? C Y OR N ] : Y ' l Edit 10-min real time release Q-file - prompts to print
! - data for release point 2 l
(sj
) '
i _ .-,----,.-ng.y.....-n....~.- - gm.:er,: m-
- ;-,,..-; p ;;;;-~
7 ._ r 1 d' CPSES I PROCEDURE NO. j EMERGENCY PLAN MANUAL 0@dAE4 EPP-301 - 1
' COMPUTER ASSESSMENT OF k~) RADIOLOGICAL CONDITIONS REVISION NO. O PAGE 22 0F 65 DIT REAL-TIME 6ASEOUS RELEASE 0-FILE ATTACHMENT 2 PAGE 4 0F 5 l
ENTER RELEASE POINT C1-43 2 j EXAMPLE 2 J l OPTIONS J 1 - PRINT DATA FOR THIS RELEASE POINT 2 - DIT DATA FOR THIS RELEASE POINT 2 - CLEAR DATA FOR THIS RELEASE POINT STER OPTION SELECTION ti-33 : 2 1
$ 0 YALLES (MICRO-CI/SEC) FOR DATE: 0/ 0/ 0 0: 0 i RELEASE POINT: 2
]1 ?.ELEASE n0DE: CONTINU0US ISOTOPES NOT PRINT D ARE ZERO
]
a j DO TOU W T TO CHANGE THE DATE? [ Y OR N 3 : Y { BTER START DATE [ M/DD/YY HH:M 3 : 6/1/79 0:0 .
] 00 YOU M T TO C M GE THE RELEASE NODE? [ Y OR W 3 : N 6ASEDUS ISOTOPE ,
OPTIONS 1 4-KR83 5-10tB5M 6-10tB5 7-10tS7 1-H3 2-C14 3-AR41 j 8-KRBS 9-NR89 I H R90 11-XE131M 12-XE133M 13-XE133 14-XE135N 19-MN54 20-FE39 21-C058 J 15-XE135 16-XE137 17-XE138 18-CR51 27-58124 28-CS134 l 22-C060 23-ZN65 24-SR89 25-SR90 29-CS136 30-CS137 31-8A140 32-CE141 33-CE144 ,34-1131 26-ZR95 35-1133 i 36 .6ASES 37 .PART 38 . ALPHA BTER IS0 TOPE SELECTION [ 1-38 3 : 3
) ! CURRENT WLUE FOR ISOTOPE AR41 : 7 0000E-01 a
ENTE NEW VALUE (MICRO-CI/SEC) I N.N > 0 3 : 1 0E6 .' 90 YOU WT TO CONTINtf DITINGt [ Y OR N 3: Y
', 6ASEQUS ISOTOPE OPTIONS 1
.i 4-10t93M 5-10t95M 6-lut85 M R87 2-C14 3-AR41 j 1-N3 8-KR88 9-lut99 1(H0t90 11-XE131M 12-XE133N 13-XE133 14-XE135h i 19-MN54 20-FE59 21-C058 1 15-XE135 16-XE137 17-XE138 18-CR51 27-$8124 28-CS134 23-2N65 24-SR89 25-SR90 26-ZR95 i 22-C060 35-1133 29-CS136 30-CS137 31-9A140 32-CE141 33-CE144 34-1131 3 36 . GASES 37 .PART 38 . ALPHA
' 17 ENTER ISORFE SELECTION C 1-38 3 i
* - CURRENT VALUE FOR'!!0 TOPE XE138 : 0.0000E-01 l ('.-
ENTE NEW VAL!E (MICRO-CI/SEC) C N.N > 0 3 : 1.0E6 i l'0 YOU WT TO CONTINUE DITIN8? E Y OR N J: N 00 fou MT TO CONTINUE WORK WITH THIS WTION? C Y St N 3 : Y l' 3 Edit 10-ein real time release Q-file - prompts to edit data for release point 2 i
' ' - ,,, ~~ **
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7 4 1 CPSES ISSUE DATE PROCEDURE NO. I EMERGENCY. PLAN MANUAL EPP-301 OCT 26 W COMPUTER ASSESSMENT OF I h RADIOLOGICAL CONDITIONS REVISION NO. O PAGE 23 0F 65
) ATTACHMENT 2
.l PAGE 5 0F 5 - u I EXAMPLE 3 p EDIT REAL-TIME GASEOUS RELEASE Q-FILE j ENTER RELEASE POINT [1-43 : 2 OPTIOMS 1 - PRINT DATA FOR THIS RELEASE POINT I 2 - EDIT DATA FOR THIS RELEASE POINT 3 - CLEAR DATA FOR THIS RELEASE POINT
] ENTER OPTION SELECTION [1-33 : 3 I ~
- FILE INITIALIIATION COMPLETE -
Q- D0 YOU WANT TO CONTI.YJE WORK WITH THIS OPTION? [ Y OR N 3 : N Edit 10-min real time release Q-file - prompts to perform file initialization 1 - 1 l 1 1-k 4 4 i i i 5 1 a ll, i a i 4
- - -~~ - - - ---m ;- g y .;....
f y r c - 7 . ., ,
y- . 3_ 3 4 1 h CPSES ISSUE DATE PROCEDURE NO.' EMERGENCY PLAN MANUAL EPP-301 0CT 261984 COMPUTER ASSESSMENT OF j ths RADIOLOGICAL CONDITIONS REVISION NO. O PACE 24 0F 65 1 1 1 ATTACHMENT 3 l PAGE 1 0F 7 . l j , EDIT POSTULATED ACCIDENT Q-FILE The abbreviation "PAQ-file" will be used in the following section to refer
..2 to the postulated accident Q-file, g Operator Interface: The prompt appears:
f
, DO YOU WANT TO EDIT ACCIDENT TIME (A] OR DATA [D]?:
1 j If the response is A, then a list of the accident types currently stored will be displayed. Example 1 shows a list of five accident types and five blank items. The remainder of the example shows the addition of one more j accident type to the list. If D is entered in response to the first prompt, the current accident list Fj is displayed. Next the prompt to select which of the three options is to j be performed from the following list appears: 1 1 OPTIONS i .: 4 1 - PRINT DATA FOR THIS ACCIDENT TYPE 3 A 2 - EDIT DATA FOR THIS ACCIDENT TYPE b ( 3 - CLEAR DATA FOR THIS ACCIDENT TYPE 4 Each of these options is discussed in the following sections. Print Data for This Accident Type This option displays data in the PAQ-file for the selected accident type.
] The prompt to specify whether the data are to be displayed on the printer
] or on the terminal follows. The data are then displayed as shown.in - j Example 2. Y If no data record exists for the specified release point [ the following I message is displayed: 4 *** NO DATA ON DISK FOR THIS ACCIDENT TYPE *** 1; 9 4 . d rm j Cd Li II d 'I . I k
%:E m m m .x .v wms w m es m w w y'mr; 7 ~ v -
- p ,- -
CPSES TSSUE DATE PROCEDURE NO. [] EMERGENCY PLAN MANUAL OCT 261984 EPP-301 I} p,.) COMPUTER ASSESSMENT OF 4 b RADIOLOGICAL CONDITIONS REVISION NO. O PAGE 25 0F 65 j ATTACHMENT 3 it PAGE 2 0F 7 - ti 1 Edit Data for This Accident Type d H lj . This option allows change of existing PAQ-file data. The current data for j the selected accident type are displayed. The system then prints out a list of all gaseous isotopes and prompts the user to enter a number which corresponds to one of the isotopes. Af ter entry of the number, the system
] displays the current value that is stored in that record for that isotope. ] The prompt to enter a new value follows. The system then asks if editing of isotope data is to continue. If yes, the system redisplays the isotope list and the option to select and change another isotope is given. This procedure may be repeated as many times as desired until no more )
modifications are to be made. )j An example of this option is shown in Example 3. i Clear Data for This Accident Type h This option clears the PAQ-file for the selected accident type, t- The following message is printed when the clear is complete. p
--- FILE INITIALIZATION COMPLETE --
An example of this option is shown in-Example 4. ]u i k, t.
'l ).
t
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t. U
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2 A 1 4
, yef ' ,. * .' _= * * . F - ._
7_ ._ _ _. _ _ CPSES ISSUE DATE PROCEDURE NO.
- EMERGENCY PLAN MANUAL OCT 261984 EPP-301
,, p* COMPUTER ASSESSMENT OF i- c RADIOLOGICAL CONDITIONS REVISION NO. O PAGE 26.0F 65 i ] ATTACHMENT 3 j PAGE 3 0F 7 - B q EXAMPLE 1 (j GIT POSTULATD ACCIDENT 0-FILI l DO YOU WANT TD D IT ACCIDENT TYPE [ A J OR DATA C D J? : A 1 2 POSTULATD ACCIDENT OPTIONS I - FIACTOR SCRAA 1b , * - LOCA 3 - FEEDidATCk FIFE EW. 4 - ALL N02'C &*SS3 k 5 - ALL IO?.7c? 6-7- g_ I h o-10 -
)
l ENTER OPTION *":Urdi E I-IO 3 : 6 l ENTER DESCRIPTION FDR ACCIDENT 6 I 48 CHARS. tlAX 3
} ALL NOBLE SASSES AND IDDINES 1
i DO YOU liANT TO CONTINUE DITIN6 ACCIDENT DESCRIPTIONS? C Y OR N J : W
~
i DO YOU liANT TO CONTINLE liORK WITH THIS OPTION? I Y OR N 3 : Y r s Edit postulated accident Q-file - prompts showing addition of j accident ALL NOBLE GASES AND IODINES to list f i. i i 1 e
)
}
=
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- q ' u ,;
i I d ' CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL EPP-301 gg g i COMPUTER ASSESSMENT OF
) -Ag3 RADIOLOGICAL CONDITIONS REVISION NO. O PAGE 27 0F 65 j
[y ! ATTACHMENT 3 DIT POSTULATD ACCIDENT Q-FILE PAGE 4 0F 7 - [ EXAMPLE 2 DO YOU WANT TO DIT ACCIDST TYPE C A J OR DATA C D J? : 0 l ? POSTULATO ACCIDENT OPTIONS r i 1 - REACTOR SCRAN 2 - LOCA N-3 - FEDWATER PIPE BREAK 4 - ALL NOBLE 6 ASSES 5 - E 10 DINES 'I 6 - E NOBLE GASSES AND 10 DINES ! 7- } : 9 [ , 9-10 - i - j ENTER 0? TION SELECTION C 1-10 3 : 5 f , OPTIONS b 1 - PRINT DATA FOR THIS ACCIDENT TYPE i : 2 - DIT DATA FOR THIS ACCIDENT TYPE [ : 3 - CLEAR DATA FOR THIS ACCIDENT TYPE ENTER OPTION SELECTION C1-33 : 1 . { REPORT ON PRINTER? C Y OR N 3 : N
, ENTER C C J TO ERASE SCREEN AND CONTINUE : C i
f SITE: UNIT: U1 g USER: EEEE DATE: 4/23/84 13:36 l POSTULATED ACCIDENT Q-FILE DATA 4
.i ACCIDENT DESCRIPTION: E 10 DINES ly ISOTOPES NOT PRINTD ARE ZERO a
a 7131 : 1.0000E+06 4 1133 : 1 0000Ef06 1 h DO YOU WANT TO CONTINUE WORK WITH THIS OPTION? C Y OR N J N Edit postulated accident Q-file - prompts showing print of data for accident type 5 ' 4 D7M , []
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CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL EPP-301 OCT 961984 1
; COMPUTER ASSESSMENT OF j ,
%,- RADIOLOGICAL CONDITIONS REVISION NO. O PAGE 28.OF 65 d
a 3 ATTACHMENT 3 PAGE 5 0F 7 - DIT POSTULATD ACCIDDT 9-FILE 1 EXAMPLE 3
)4 M mt wi TO DIT ACCIEENT TYPE C A 3 3 MTA [ 3 J? : 3 ?. POSTULATD ACCIMNT OPTIONS j
1 - REACTOR Satm 2 - LOCA 3 - FENATB PIPE 3 REM 4 - ALL ND3LI GASSES y 5 - ALL 10 DINES , e - ALL N08LE GASSES ANB 10BIES 1-9- r-10 - EM'G TTION SELECTION ( 1-10 J : 5 0FTIONS h f r 1 - PRINT MTA FOR THIS ACCISENT TYPE 2 - DIT MTA FOR THIS ACCIMNT TYPE 3 - C. EAR MTA FOR THIS ACCDENT TTPE DTU P! ION SELECTION Il-331 2 P0iT1ATD ACCIMNT G-FILE MTA v;CIENT MSCRIPTION: ALL IDDIES
!$0TTES NOT PRINTD ARE ZERO
!!31 : 1 00000 06
!!33 : 1.0C00Ef06 uASEcc5 ISOTOPE OPTIONS l 1-3 2-C14 3-AR41 4-083M 5-085M 640tf5 7-007 1 H R06 940te? 1 Hot 90 11-XE1318 12-XE133M 13-XE133 14-XE135M 3
15-XE135 16-XE137 17-XE138 18-CR51 19-!sI54 20-FE59 21-CD50 -
.; 22-C060 23-IN65 24-SRB 9 25-Spf0 26-ZR95 27-H124 29-CS134 .. 29-CS136 30-CS137 31-M140 32-CE141 33-CE144 34-1131 35-1133 ] 3e .tisSES 37 .PART 30 . ALPHA j 1NTG ISut0PE SELECTION 1 1-38 3 1 34 U D.119T 5
VALLE FOR 150TWE 1131 : 1 0000E+0e EFER (d 94LtE (MICRO-CI/SEC) I N.N > 0 3 : 1.0E2 DJ rev WANT TO CONTDRE DITIIE? E T OR W J: T
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1-M3 2-C14 3-AR41 4HutB3M l Hut 95M Hat 05 7-10ts7
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1 Edit postulated accident Q-rile - prompts to edit data for . j accident type 5 (sheet 1 of 2) t
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. CPSES ISSUE DATE PROCEDURE NO.
1- EMERGENCY PLAN MANUAL EPP-301 .i. OCT 261984 l - COMPUTER ASSESSMENT OF j h RADIOLOGICAL CONDITIONS REVISION NO. O PAGE 29 0F 65 ATTACHMENT 3 PAGE 6 0F 7 - i .{ EXAMPLE 3 '! SHEET 2
)
j 22-C060 23-ZN45 24-SA89 25-SR90 26-ZR?5 27-SB124 28-CS134 .; 29-CS136 30-CS137 31-BA140 32-CE141 33-CE144 34-1131 35-I!33 34 .0ASES 37 .PART 38 . ALPHA .) ENTER ISOTOPE SELECTION C 1-38 3 : 35 CUPIENT VALUE FOR ISOTOPE I133 : 1.0000Et06 j ENTER NEW VALUE (MICRO-CI/SEC) [ N.N > 0 3 : 1.0E2 a DO YOU WANT TO CONTINUE EDITING? E Y OR N 3: N j 1 00 YOU WANT TO CONTINUE WORK WITH THIS OPTION? E Y OR N 3 : N 4 J Edit postulated accident Q-file - prompts to edit data for j
@ accident type 5 (sheet 2 of 2)
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EMERGENCY PLAN MANUAL EPP-301 OCT 261984 If ',- COMPUTER ASSESSMENT OF 1 RADIOLOGICAL CONDITIONS REVISION NO. O PAGE 30.0F 65 J ATTACHMENT 3 't PAGE 7 0F 7 -
, EXAMPLE 4 a
DIT POSTIA.ATD EIDENT G-FILE ; 1
.D0 70U HANT TO DIT ACCIDENT TYPE C A 3 OR MTA C D 3? : D
-l 1 . POSTILATD ACCIDENT OPTIONS i 1 - REACTOR SCRAN l 2 - LOCA .. 3 - FEEDWATER PIPE BREAK
! 4 - ALL NOBLE GASSES 5 - ALL 10 DINES 6 - ALL il0BLE 6 ASSES AND IODINES . 7-i 8-9-
-j (h 10 - 1 -) ENTER OPTION SELECTION C 1-10 3 : 6 OPTIONS i '1 1 - PRINT MTA FOR THIS ACCIDENT TYPE 2 - DIT MTA FOR THIS ACCIDENT TYPE 3 - CLEAft MTA FOR THIS ACCIDENT TYPE p-
-ENTER OPTION SELECTION CI-33 3
- FILE INITIALIIATION C0hPLETE -
4 - DO YOU WANT TO CONTIIRE WORK WITH THIS OPTION' C Y OR N 3 i N J % a j Edit postulated accident Q-file - proarpts to initialize file 4 i f$ D V)
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- CPSES, ISSUE DATE PROCEDURE NO.
[1 t EMERGENCY PLAN MANUAL OCT 261984 EPP-301 f- COMPUTER ASSESSMENT OF (f ), RADIOLOGICAL CONDITIONS REVISION NO. O PAGE 26.0F 65 e Y ' ATTACHMENT 3 PAGE 3 0F 7 - @ EXAMPLE 1 h { u DIT POSTULATD ACCIDENT 9-FILI I l q- DO YOU WANT TO DIT ACCIDENT TYPE [ A 3 OR DATA I D 37 : A
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) POSTULATD ACCIDENT OPTIONS h
1 - PIACTOR SCRAM f: - 2 - t0CA
; 3 - FEEDWATER PIPE DREAK L 4 - ALL N0DLE 6 ASSES li 5 - ALL 10 DINES . ', 6-fj - 7- ,
H , s-1 O, e-
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4 n , ENTG OPTION SELECTION I 1-10 J 6 L. p ENTER ..- DESCRIPTIO!i FDR ACCIDENT 6 C 48 CHARS. MAX 3 p - ALL NO3LE SASSES AND I0 DINES i fl:.
. DO YOU WANT TO CONTINUE DITIN6 ACCIDENT DESCRIPTIONS? # C Y OR N J i
! DO YOU WANT TO CONTIMJE WORK WITH THIS OPTION? I Y OR N 3 : Y a
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] CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MAWE EPP-301 OCT 261984 !I COMPUTER ASSESSMENT OF d (- ih RADIOLOGICAL CONDITIONS REVISION NO. O PAGE 27.0F 65 ATTACHMENT 3 , DIT POSTULATO ACCIDENT Q-FILE PAGE 4 0F 7
-l EXAMPLE 2 a DO YOU WANT TO DIT ACCIDENT TYPE C A 3 OR DATA C D ]? : D
) POSTULATO ACCIDENT OPTIONS 1 p 1 - REACTOR SCRAN 4 2 - LOCA f 3 - FEEDWATER PIPE BREAK b 4 - Att N0sLE SASSES bj 5 - ALL 10 DINES h 4 - ALL NOBLE 6 ASSES AND 10 DINES 7-ff e -- { a L
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] ACCIDENT DESCRIPTION: ALL 10 DINES d
j, ISOTOPES NOT PRINTO ARE ZERO F I131 : 1.0000E+06
, 1133 : 1.0000Et06
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I CPSES TSSUE DATE PROCEDURE NO. 1 q EMERGENCY PLAN MANUAL OCT 961984 EPP-301 1 ..l - COMPUTER ASSESSMENT OF
) RADIOLOGICAL CONDITIONS REVISION NO. O PAGE 28 0F 65 t
i ATTACHMENT 3 -l PAGE 5 0F 7 .
! 01i POSRAATD ACCIMNT HI!.E EXAMPLE 3 ? 00 feu hAni TO DIT ACCDENT TYPE I A 3 3 MTA C D 3? : I lii POSTILATD ACCIMNT OPTIDMS i ? ! - REACTOR SQtm 2 - LOCA 3 - FEE 4AfD PIPE NEM
- { 4 - ALL NOILE SAGSES 5 - ALL IDDINES ,
A - E NOILE GASSES AND 10 BINES % 1- .j f-4 23 .- 1 l DiC2 TTION SELECTION I 1-10 J : 5 .] OPTIONS i j 1 - PRINT MTA FOR THIS ACCIDENT TYPE , 2 - DIT NTA FOR THIS ACCIDENT TYPE
, 3 - CLEAR NTA FOR THIS ACCIDENT TYPE
'--. - DTD W! ION SELECTION [1-33 : 2 .
Ii '.; PCST1ATD ACCIMNT HILE MTA i
- 4 V.CIDENT DESCRIPTION: ALL 10BIES
.I nt !!OTTES NOT PRINTD ARE ZERO P " 31 : 1 0000E+04
,j !!33 : 1.0c00Et44 .j 6A!EDUS ISOTOP! 0PTIons 1-3 2-C14 3-AR41 4-083M 540ts5n H RI5 7-KR07 9- 0 08 940tet 1040t90 11-E131M 12- E133M 13-E133 14-XE135M 15-E135 16-E137 17-XE138 Il-CR51 19-9154 20-FE59 21-CD50 _ 22-CD40 23-IN45 24-SRtf 25-SR90 24-ZRf5 27- 9 124 29-CS134 29-CS13s 30-CS137 31-94140 32-CE141 33-CE144 34-1131 15-1133 36 .tii.SES 37 .P4RT 38 . ALPHA tNTE 15ut0PE SELECTION I 1-38 3 : 34 C'.421mf VALUE FOR ISOTOPE 1131 : 1.0000E+06 DT. du YAttlE (MICRO-CI/SEC) I N.N > 0 3 : 1.0E2 D3 f00 MNT TO CONTIJRE DITINET C Y OR # 3: Y IAIEDUS !$0TtFE (FTINS
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CPSES ISSUE DATE PROCEDURE NO. j- EMERGENCY PLAN MANUAL EPP-301 - COMPUTER ASSESSMENT OF h RADIOLOGICAL CONDITIONS REVISION NO. O PAGE 29.0F 65 I ATTACHMENT 3 i [ PAGE 6 0F 7 - EXAMPLE 3 SHEET 2 i i
- t. 22-C040 23-ZN65 24-SR89 25-SR90 26-R?5 27-SB124 28-CS134 l 29-CS136 30-CS137 31-BA140 32-CE141 33-CE144 34-1131 35-1133
{ 34 .0ASES 37 .PART 38 . ALPHA ENTER ISOTOPE SELECTION C 1-38 3 : 35 g, CURP.ENT VALUE FOR ISOTOPE I133 : 1.0000Ef06 l ENTER NEW VALUE (NICRO-C!/SEC) C N.M > 0 3 : 1.0E2 s DO YOU WANT TO CONTINUE EDITING? E Y OR N 3: N t 6
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EMERGENCY- PLAN MANUAL EPP-301 0CT 261984 l . COMPUTER ASSESSMENT OF RADIOLOGICAL CONDITIONS REVISION NO. O PAGE 30.0F 65 ATTACHMENT 3 PAGE 7 0F 7 - [ EXAMPLE 4 i, DIT POSTULATO ACCIMNT 0-FILE
; D0 TOU HANT TO DIT ACCIDENT TYPE [ A 3 OR MTA [ D ]? ! D i .
i POSTULATD ACCIDENT DPTIONS i l 1 - REACTOR SCRAN i 2 - LEA l 3 - FEENATER PIPE BREAK l 4 - ALL NOBLE SASSES I 5 - ALL 10 DIES 4 - ALL N0BLE 6 ASSES AND 10 DINES
), 7.
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OPTIONS
; 1 - PRINT NTA FOR THIS ACCIDENT TYPE 1
2 - DIT NTA FOR THIS ACCIDENT TYPE CLEAR MTA FOR THIS ACCIDENT TYPE
. ENTER OPTION SELECTION [1-33 : 3 ! - FILE INITIALIZATION COMPLETE -
j _
; DO YOU WANT TO CONTINUE WORK VITH THIS OPTION? [ Y OR N 3 : N I
i j Edit postulated accident Q-file - prompts to initialize file i i ie 4,; ,
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!' EMERGENCY PLAN MANUAL EPP-301 COMPUTER ASSESSMENT OF h RADIOLOGICAL CONDITIONS REVISION NO. O PAGE 31.0F 65 11 ATTACHMENT 4 PAGE 1 0F 10 -
f f Q-FILE-PROMPTS hr The abbreviation SRQ-file will be used in the following sections to refer i to the simulated release Q-file. L The prompt to enter a release point number will be displayed. After specifying which release point is being referenced, select which of the j
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five options is to be performed from the following list: a! OPTIONS 1 - PRINT DATA FOR THIS RELEASE POINT n
'! 2 - EDIT DATA FOR THIS RELEASE POINT
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'i _ 3 - INSERT 1 RECORD IN FILE FOR THIS RELEASE POINT 4 - DELETE 1 RECORD FROM FILE FOR THIS RELEASE POINT
]h 5 - INITIALIZE FILE FOR "ALL" RELEASE POINTS Each of these options is discussed in the following sections.
1 1 Print Data for This Release Point - 1 J This option displays data in the SRQ-file for the specified release point. The prompt to enter the data to start printing is displayed. No prompt for [] an ending data is given; the ending data is considered to be the end of the h file. Specifies whether the data is to be displayed on the printer or on 4 Ll* the terminal. For the former, the entire portion of the file between the
.i starting data and the end of the file is printed; for the latter, the
, records are displayed sequentially one at a time, specify whether or not to
] view the next record. ~
An example of this option is given in Example 1.- cl t j j Edit Data for This Release Point i j This option allows changes to be made to existing SRQ-file data. (To add j new data records to the Q-file, refer to the next page which describes how d to insert records into the file.)
! .w y
a j ; e - - i_ C " ??$ ~3;f % :. ' ' WE1????WQ?W(?1$5,G.5?-55Q_?_T&f&?&
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k CPSES TE D PROCEDURE NO. EMERGENCY PLAN MANUAL EPP-301 COMPUTER ASSESSMENT OF (h RADIOLOGICAL CONDITIONS REVISION NO. O PAGE 32 0F 65 )' ATTACHMENT 4 PAGE 2 0F 10 - } Q-FILE-PROMPTS 3 i The prompt to enter a start date, which is actually the date of the data j record in the Q-file appears. If a date for which no Q-file data currently exist is specified, the following message is displayed on the terminal.
;- *** NO DATA ON DISK FOR THIS DATA ***
i If data exist for that date, the data currently in the record are displayed on the terminal. The system then prints out a list of all gaseous isotopes and prompts the l user to enter a number which corresponds to one of the isotopes. After
- j. entry of the number, the system displays the current value that is stored 1 in that record for that isotope. The prompt to enter a new value follows.
]. The system then asks editing of isotope date is to continue. If yes, the j system redisplays the isotope list and allows the option to select and change another isotope is given. This procedure may be repeated as many times as desired until no more modifications are to be made. After the
[ t h isotope data are entered, the following prompt appears: i IS RELEASE DUE TO A STEAM LEAK [ Y OR N ];
; If Y (yes) is entered, then the next prompt is for steam flow rate L ENTER STEAM FLOW RATE (LB/HR) [N.N>0]:
If N (no) is entered then the next prompt is for vent flow rate f a { ENTER VENT FLOW RATE (CFM) [N.N>0): j An example of this option is shown in Example 2. 8 4 _ l; Insert One Record in File for This Release Point 3 - 1 This option allows new data records to be inserted into the SRQ-file, l. j The prompt to enter a start date is displayed, which is the date that will j uniquely identify the data record for this Q-file and release point, and
.; the prompt to specify the release mode as either continuous or batch is also displayed. The system then prints out a list of all the gaseors isotopes and requests that an isotope be specified by entering the number which corresponds to it in the list. The current value of the isotope is ,
then displayed, followed by a prompt to enter a new value. The system then i i 3
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_. . , - - - , - . ~ - l CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL EPP-301 OCT 2s W COMPUTER ASSESSMENT OF l b- .. , RADIOLOGICAL CONDITIONS REVISION NO. O PAGE 33,0F 65 j-l ATTACHMENT 4 J PAGE 3 0F 10 - 1 Q-FILE-PROMPTS a ( asks if more modifications are to be made. If the response is yes, the system redisplays the isotope list and allows selection and change of another isotope. This procedure may be repeated as many times as desired until no more modifications are to be made. After the isotope data are j ~ entered, the prompt to enter steam flow or vent flow rate is given as was described above. An example of this procedure is shown in Example 3. ]) i 1 .j Delete One Record From File for This Release Point y This option allows the user to delete data records from the gaseous release H i Q-file. 1 q The prompt is given to enter a start date, which is the date that uniquely identifies the data record in the SRQ-file for the release point. After
')
1 l
+
- the date is entered, the record is deleted and the following message is
] displayed on the terminali l
-- RECORD DELETION COMPLETE --
If no data record exists for the specified date, the following message is 1 displayed: - e
!' *** NO DATA ON DISK FOR THIS DATE ***
~
An example of this option is shown in Example 4. Initialize File for All Release Points This option deletes all the data in the SRQ-file for all release points, not merely for the release point that -was specified by the user prior to requesting this option. The user should therefore be careful when i requesting this option. i, When this option is requested, a warning is displayed and the system , J requests confirmation with the following messages
- I I
] ----WARNING--- 1 l j ALL EXISTING DATA IN THIS FILE WILL BE DESTROYED!
' I' DO YOU WISH TO CONTINUE WITH THE INITIALIZATION? [Y OR N]: 's i 82 % L 4;,VMTNM%MPW52ESTd?%Eil?W%?%WW " ' ' ?'Y l.
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g_ - - - - _ 'I a CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL EPP-301 WT o 61984 1 COMPUTER ASSESSMENT OF f'[h RADIOLOGICAL CONDITIONS REVISION NO. O PAGE 34.0F 65 l ATTACHMENT 4
- I PAGE 4 OF 10 -
?
l Q-FILE-PROMPTS j- - If the reply is N (no), the operation will terminate. If the reply is Y (yes), the file will be initialized, af ter which the following message is printed out: FILE INITIALIZATION COMPLETE --- An example of this option is shown in Example 5. f . I I-i P f 8 6. F e 4' h 4 9 h ' 1 I i ) s
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y y- : _ i CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL EPP-301 COMPUTER ASSESSMENT OF I'h RADIOLOGICAL CONDITIONS REVISION NO. O PAGE 35.0F 65 l'; ATTACHMENT 4 } PAGE 5 0F 10 EXAMPLE 1 y SHEET 1 11 'la 1 EDIT 15-MIN SIMULATED RELEASE G-FILE i ! ENTER RELEASE POINT C1-43 2 l 1 DPTIONS .i. J 1 - PRINT DATA FOR THIS RELEASE POINT 2 - EDIT DATA FOR THIS RELEASE POINT 3 - INSERT 1 RECORD IN FILE FOR THIS RELEASE POINT 4 - DELETE 1 RECORD FROM FILE FOR THIS RELEASE POINT [ i h 5 -INITIALIZE FILE FOR *ALL' RELEASE POINTS d ENTER OPTION SELECTION C1-53 : 1 i REPORT ON PRINTER 7 I Y OR N J : if [j
- ENTER C C J TO ERASE SCREEN AND CONTINUE : C 1
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t 1 1 CPSES ISSUE DATE . PROCEDURE NO. EMERGENCY PLAN MANUAL OCT 261984 EPP-301 COMPUTER ASSESSMENT OF j RADIOLOGICAL CONDITIONS REVISION NO. O PAGE 36 0F 65 1 I *ITE: ATTACHMENT 4 a VNIT: U1 PAGE 6 0F 10 - 8 USER: EEEE DATE: 5/11/94 13:3e EXAMPLE 1 1"-a!N $1nULATED RELEASE 0-FILE DATA SHEET 2 T 0 VALUES (MICRO-CI/SEC) FOR DATE: s/ 1/79 0: 0
. RELEASE POINT: 2 ARS"M = 5.0000E+05 (E133 = 3.S500E+07 1131 = 4.0000E H4 VENT FLOW RATE (CFM): 3.6163E+04 D0 f0U WANT TO VIEW THE NEXT CECORD' C = OR N 3 : Y i
0 VALUES (MICRO-CI/SEC) FOR DATE: :/ 1/?9 1: 0 El *ELEASE POINT: 2 KR85M = 1.0000E+04 xE133 = 2 0000EH4 1131 = 1.c000E+03 VENT FLOW RATE (CFM): 1.5000E+0: DO YOU WANT TO VIEW THE NEXT RECORD' C Y OR N 3 : f G YoLUES (MICRO-CI/SEC) FOR DATE: 6/ 2/79 0: 0
=ELEASE POINT: 2 AR41 = 1 0000E+06 KR83M = 1.0000E+06 kR9:M= 1 0000E+06 AF9: = :.0900Et0!
NR97 = 1.0000E+04 KK89 = 1.0000E+06 ER39 = 1.0000E+0e RR90 = 1.2000t+1s
'u" XE131M= 1.0000EM6 XE133M3 1.0000EH6 XE133 = 1.0000E+06 XE13:M3 1 900"Et0e AE135 = 1.0000E+06 XE137 = 1.0000E+04 XE138 = 1.0000EH6 1131 = :.00%E H9 1133 = 1.0000EH6 VENT FLOW RATE (CFM): 3.4 ? SSEH4 i
00 (GU WANT TO VIEW THE NEXT RECORD' C Y OR N 3 : f 0 VALUES (MICRO-CI/SEC) rCR DATE: 4/ 2/79 4: 0. RELEASE POINT: 2 AR41 = 5.0000E+05 %K83M = 5.N00EH5 kka:M= 5.0000EH5 995 = !.M 00E+0 AR87 = 5.0000E&O5 RR88 = 5.0000E+0" sR99 = 5.0000E+0 .R90 - :.0000E+.:
. (E131M= 5.0000EH: XE133M= 5.0000Eto: XE133 = .0000Et0: .'E I!M= !.0000i+M XE135 = 5.0000E H5 XE137 = 5.0000E+0: XE139 = .0000E H5 IIII * !.000eEH5 I 33 = 5.0000E+0 4
4 VENT FLOW RATE (CFMe: 1.9093E M4 I D0 YOU JANT TO VIEW THE NEAT RECORD? C Y OR N 3 : Y a _ 0 VALUES (MICFO-0!/SEC$ FOR DATE: e/ 2/7' 10: 0 RELEASE POINT: 2 AR41 = 1.0000E+06 NR93M = 1.0000EM6 FRS!M = 1 0000E-)$ KRS: 3 1. 900 . EH-KR97 = 1.0000EM6 p.R39 = 1.0000E+0e NR?9 = 1.0000C+44 sR99 = 1 0000E+0-l XE131n= 1 0000E H 6 XE133M= 1.0000E+06 (E133 = i M 00E M6 YE13!.** : .90NE+06 j XE135 = 1.0000E+06 XE137 = 1.0000E+0a (E133 = 1.uc00i+06 113: * :.0000E+06 j 1133 = 1.0000E M6 i 4 VENT FLOW RATE (CFM): 3.4184EH4
. DO YOU WANT TO VIEW THE NEXT RECORD 3 C Y OR N 2 : Y l
*** END OF FILE INCOUNTERED sse l
D0 YOU WANT TO CONTINUE WORK WITH THIS CPTION? C f CR N ] P Edit 15-min simulated release Q-file - prompts to print
,l data for release point 2 (sheet 2 of 2) mmmmmm-- - -
'r - - - - - , . CPSES ISSUE UATE PROCEDURE NO.
EMERGENCY PLAN MANUAL OCT 261984 EPP-301 ; i , COMPUTER ASSESSMENT OF
' 1
(,.}. RADIOLOGICAL CONDITIONS REVISION NO. O PAGE 37.0F 65 ATTACHMENT 4 l g PAGE 7 0F 10 - i t ' { EXAMPLE 2 EDIT 15-MIN SIMULATED RELEASE 0-FILE d ENTER RELEASE POINT C1-43 2 OPTIONS l} 1 - PRINT DATA FOR THIS RELEASE POINT f 2 - EDIT DATA FOR THIS RELEASE POINT J ) 3 - INSERT 1 RECORD IN FILE FOR THIS RELEASE POINT . 8 4 - DELETE 1 RECORD FROM FILE FOR THIS RELEASE POINT l 5 - INITIALIZE FILE FOR ' ALL' RELEASE POINTS
- ENTER OPTION SELECTION C1-5]
- 2 y ENTER START DATE C MM/DD/YY HH:MM J : 6/1/79 0:0 l
I h 0 VALUES (MICRO-CI/SEC) FOR DATE: 6/ 1/79 0: 0 f RELEASE POINT: 2 KR85M = 5.0000E+05 XE133 = 3.8500E+07 1131 = 4.0000E+04 { . 9 i YENT FLOW RATE (CFM)! 3.6163E+04 BASE 00S ISOTOPE OPTIONS - i 1 1-H3' 2-C14 3-AR41 4-KR83M 5-KR85M 6-KR85 7-KR87 % 8-KR88 9-KR89 10-KR90 11-XE131M 12-XE133M 13-XE133 14-XE135M 15-XE135 16-XE137 17-XE138 18-CR51 19-MN54 20-FE59 21-C058 l 25-SR90 26-ZR95 27-SB124 28-CS134
- 22-C060 23-ZN65 24-SR89 3 29-CS136 30-CS137 31-BA140 32-CE141 33-CE144 34-1131 35-1133 34 . GASES 37 .PART 38 . ALPHA '
ENTER ISOTOPE SELECTION C 1-38 3 34 ( S CURRENT VALUE FOR ISOTOPE 1131 : 4.0000E+04 - i j ENTER NEW VALUE (MICRO-CI/SEC) : 1.0E2 i DO YOU WANT TO CONTINUE EDITING ISOTOPE DATA 7 C Y OR N 3: N IS RELEASE DUE TO A STEAM LEAK C Y OR N 3 : N I ENTER VENT FLOW RATE (CFM) C N.N > 0 3 : 36163. I DO YOU WANT TO CONTINUE WORK WITH THIS OPTION? E Y OR N 3 : N l C Edit 15-min simulated release Q-file - prompts to edit data for release point 2 P w n-.7,.7.- --. ,- ..-. . - .- - - _ __ . _ _ _
~ =~ ~ ~ ~
.- _. . . . u-I
. CPSES ISSUE DATE PROCEDURE NO.
EMERGENCY PLAN MANUAL g EPP-301 COMPUTER ASSESSMENT OF I [d. s-RADIOLOGICAL CONDITIONS REVISION NO. O PAGE 38 .0F 65 h i EDIT 15-MIN SIMULATED WELEASE Q-f!LE
; -- ATTACHMENT 4 ;* PAGE 8 0F 10 -
i ENTER RELEASE POINT C1-43 : 2 l EXAMPLE 3 1 0PTIONS 1 1 - PRINT DATA FOR THIS RELEASE POINT I - 2 - EDIT DATA FOR THIS RELEASE POINT j *
! - INSERT 1 RECORD IN FILE FOR THIS RELEASE POINT 4 - DELETE 1 RECCRD FROM FILE FOR THIS RELEASE POINT 5 - INITIALI:E FILE FOR 'ALL' RELEASE POINTS ENTER OPTION SELECTION C1-53 : 3 ENTER $ TART DATE C MM/DD/YY HH:nM 3 : v 1/ N 0:30 SASEQUS ISOTCPE OPTIONS 1-H3 2-C14 3-AR41 4-KRS3M 5-KRe:M 64525 7-SR87 D-hRSS 9-KR89 10-hR90 11-XE131M 12-xE133M 13-vE133 14-xE135M
,' 15-XE135 16-XE137 17-XE139 18-CR51 19-MN54 20-FE59 21-C058 22-C040 23-ZN65 24-SR89 25-SR90 :&-IR95 27-531:4 09-CS134 1 29-CS134 30-CS137 31-94140 32-CE141 33-CE144 34-!!31 35-1133 4( 34 . GASES 37 .PART 38 . ALPHA ENTER ISOTOPE SELECTION C 1-38 J : 5 CURRENT VALUE FOR ISOTCPE KR85M : 0.0000E-01 h / 1 ENTER NEW VALUE (MICRO-CI/SEC) : 2 0E4 DO YOU WANT TO CONTINUE EDITING ISOTOPE DATA ' C Y OR N J: f GASEQUS ISOTOPE OPTIONS 1-H3 2-C14 3-AR41 4-sR83M 54R95M 6-*RS5 74R87 8-AR$8 9-KR99 10-AR90 11-XE131M 12-XE133M 13-tE133 14-XE135M 15-XE135 16-XE137 17-XE138 19-CR51 19-MN54 00-FE59 21-CD58 27-!B1:4 29-CS13d s 22-C040 23-ZNe5 24-SR89 25-SR90 24-ZR95 07-CS13e 30-CS137 31-94140 32-CE141 33-CE144 34-1131 35-1133 34 . GASES 37 .PART 38 .ALFHA k ENTER ISOT0FE SELECTION C 1-38 3 : 13 CURRENT VALUE FOR !!0 TOPE xE133 1 0.0000E-01 1 ENTER NEW VALUE (MICRO-CI/SEC) : 3.3E5 00 YOU WANT TO C2NTINUE EDITING ISOT0FE DATA
- C T OR 1 2: Y _
I GASEQUS ISOTCPE OPTIONS 4%R8tM 5-sRS5M :-AR$5 7-ER87 1-H3 l-C14 3-AR41 9-nR89 10-nR90 11-XE131M 12-tE133M 13-4E133 14-YE135M S-AR88 15-XE135 16-XE137 17-XE138 18-CR51 19-MN54 20-FE59 01-C058 3 22-C040 23-ZNe5 24-SR99 25-SR90 24-ZR95 27-58124 29-CS134
$ 35-I133 ; 29-CS134 30-CS137 31-BA140 32-CE141 33-CE144 34-1131 j 34 . GASES 37 .PART 38 . ALPHA j EN'ER ISOTOPE SELECTION C 1-38 3 : 34 s
4 CURRENT VALUE FOR ISOTOPE 1131 : 0.0000E-01 EF?ER NEW VALUE (MICRO-CI/SEC) : 500. N fou WANT TO CONTINUE EDITING IE0 TOPE DATA ? C Y OR N 3: N ("O] IS RELEASE DOE TO A STEAM LEAN C f OR N 3 : 1 36313 ENTER VENT n.0W PATE (CFM) C N.N > 0 3 [ D0 foU WANT 'O CONTINUE WORK WITH THIS OPTION? C f OR 4 3 : N z
! Edit 15-min simulated release Q-file - prompts to insert -
1 record in file for release point 2 i i) .. . s o- ,, - .#, , __.
[ CPSES ISSUE DATE PROCEDURE NO. I EMERCENCY PLAN MANUAL OCT 261984 EPP-301
, g) COMPUTER ASSESSMENT OF e u RADIOLOGICAL CONDITIONS REVISION NO. O PAGE 39,0F 65 l
l ATTACHMENT 4 [ PAGE 9 0F 10 - t i EXAMPLE 4 t EDIT 15-MIN SIMULATED RELEASE Q-FILE l ENTER RELEASE POINT C1-43 : 2 OPTIONS
, 1 - PRINT DATA FOR TNIS RELEASE POINT 2 - EDIT DATA FOR THIS RELEASE POINT 3 - INSERT 1 RECORD IN FILE FOR THIS RELEASE POINT 4 - DELETE 1 RECORD FROM FILE FOR TNIS RELEASE POINT , 5 - INITIALIZE FILE FOR ' ALL' RELEASE POINTS I
ENTER. OPTION SELECTION El-53 : 4 ENTER START DATE -C MM/DD/YY HH MM J : 6/2/79 10:0
- RECORD DELETION COMPLETE -
a Edit 15-min simulated release Q-file - prompts to delete 1 record for release point 2 1 i (
n - - . . - - - _ . , CPSES ISSUE DATE PROCEDURE NO.
! EMERGENCY PLAN MANUAL EPP-301 1
COMPUTER ASSESSMENT OF
,1 I- RADIOLOGICAL CONDITIONS REVISION NO. O PAGE 40 0F 65 ATTACHMENT 4 , PAGE 10 0F 10 -
EXAMPLE 5 4 EDIT 15-NIN SIMULATED RELEASE Q-FILE ENTER RELEASE POINT C1-43 : 2 1
, OPTIONS 1 - PRINT DATA FOR THIS RELEASE POINT J
2 - EDIT DATA FOR THIS RELEASE POINT 3 - IhSERT 1 RECORD IN FILE FOR THIS RELEASE POINT 4 - DELETE 1 RECORD FRON FILE FOR THIS RELEASE POINT 5 - INITIALIZE FILE FOR 'ALL' RELEASE POINTS ENTER OPTION SELECTION C1-53 : 5 WARNING 3 b> ALL EXISTING DATA IN THIS FILE WILL BE DESTROYED! .
.- DO YOU WISH TO CONTINUE WITH THE INITIALIZATION? C Y OR N 3 : Y 1
-- FILE INITIALIZATION COMPLETE --
DO YOU WANT TO CONTINUE WORK WITH THIS OPTION? E Y OR N 3 : N Edit 15-min simulated release Q-file - prompts to initialize file for all release points e i . e -9
+
e mg wsip q h ,a e- g* p --*1 M4" * $ *; dh**" ( # ' N ' g
- _- ;- . u-- - -
i j CPSES TSSUE DATE PROCEDURE NO. I EMERGENCY PLAN MANUAL EPP-301
- o. OCT 281984
.i COMPUTER. ASSESSMENT OF h) RADIOLOGICAL CONDITIONS REVISION NO. O PAGE 41.0F 65 l ATTACHMENT 5 PAGE 1 0F 3 - .~l - METEOROLOGICAL TREND PLOTS 3
i The METEOROLOGICAL TREND PLOTS option allows review the 15-min 1 meteorological data being used by the emergency computational routines. This option plots traces of meteorological data from the 15-min workspace i files. It plots four graphs per page with up to two traces per graph. The 3 horizontal axis is labeled with the date and hour of the data. Each hour l of data is bounded with solid vertical lines with short vertical lines q i indicating the 15-min points. I j Vertical axis scales are preselected to correspond to the parameter being
] plotted. This program uses edited scaling factors and selectors for each j parameter to be plotted. Parameter and scale selection are user controlled J through an edit function within the trend plot program. These edits are i retained on file for future runs.
1 q Operator Interface: A sample of _ the computer prompts and corresponding j user responses required to generate a trend plot is shown in Example 1 .
- ! , The resulting trend plot is shown in Example 2.
1
, (.
~=!.) .
l 1 4 i d i> .-
'l i
j 1
]
3 .1 i i
--er%.. =e w g aw ertwo... wa s .ee e, estr==**==- ,-.+.*--e-==spM*==w. . esw= ** * * * ** . = *
- e+==
7 }s = * *
*;*"**#- 'j * ' +' * '* { P
- M '9t
. ,, - . - _.~ -- -
4 I CPSES XSSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL EPP-301 OCT 261984 j COMPUTER ASSESSMENT OF "I (... r RADIOLOGICAL CONDITIONS REVISION NO. O PAGE 42,0F 65 i 1 ATTACHMENT 5 ] PAGE 2 0F 3 . i -! EXAMPLE 1 0 l METEOROLOGICAL TREND PLOTS I'0-YOU WANT 15-MIN C F 3 OR 15-MIN 90fe.5 PACE C W J METEOROLOGICAL I'ATA? : W ENTER MODE. SELECTION, EDIT C E 3 OR PLOT C P J
- P l ENTER START DATE C MM/DD/YY NH MM J : e/I/?9 0:0
' ENTER END DATE C MM/DD/YY HH:MM J : $/4/79 10:0 d
00 !OU WANT AUTOMATIC HARD COPY GENERATION? C f CR H 3: lj} ENTER C C 3 TO ERASE SCREEN AND CONTINUE : C i l Prompts to produce 15-min data meteorological trend plot
- ! (sb1.) -
) l l -
.l 1
4 ) 1
~
j i i a 5
*V9- 3 m*--=-*w +wey _ reope ,. _p%
- _,.. , , ,-,,,._,a,__.,9q, .,
,g, , , ,. , ,,
. -- ~ ; CPSES ISSUE DATE PROCEDURE NO.
j EMERGENCY PLAN MANUAL EPP-301 1, 4 OCT 261984 COMPUTER ASSESSMENT OF l> D
- - j RADIOLOGICAL CONDITIONS REVISION NO. O PAGE 43.0F 65
- ?
.A
- } AKACHMENT 5 i
FAGE 3 0F 3 - EXAMPLE 2 l -j 517Es
- 4 . .= US UN.IT3 MfEI 6/ttes4 tiles ts-nts wsp. M7tomotoaICAL tot START oefta es 4/M es e gne enige si gets ses a
't to-alg MTronoLoescat esta k s.e
. 1 #' . l. .l. .l. .l. .R. .1.
(i. .1. }:; . i Q gg,,,g4
~60 0 t
see.0 F 78.AT.L
$ +
78 88.L 'l '. ,,, i1. .l. . l. .1. .l. b
.l. .l. .N _
see.e Ts.as.L ,i yms"' ~'% A_ ? ~ y 7 78.Be.8 1 ,.. . .l. . T. .w .i. .t.4 .1 .n i. .i. il
- 1 40.e
.I f g 78.or.L ? M C Ts.or.s 1
... .i.
M .l. .i. I .ek v i
- l. .ia i l
%"' TN" t#" i/e'" TY" W" i?* T4" C " i.Y" o.rc -%-m .
A 15-min data meteorological trend plot t .t 1 O : , l i y =*ww+ y+'+ % F w. M * - * * ~
,.w-.,%,,nr
*&'M'** # *'m
~ ..*' ,(l *_'l - , * ***"***, _" " i
- ' ' ~~
w - - .
- _ - -~ -
- ~ ~
t i
- f.
4 CPSES ISSUE DATE PROCEDURE NO. I EFERGENCY PLAN MANUAL EPP-301 g OCT 261984 f s h COMPUTER ASSESSMENT OF RADIOLOGICAL CONDITIONS REVISION NO. O PAGE 44 .0F 65 } . ATTACHMENT 6
- PAGE 1 0F 3 -
RADIOLOGICAL TREND PLOTS 1 The RADIOLOGICAL TREND PLOTS option enables inspection of isotopic data l stored in either the emergency Q-file or the simulated release Q-file prior jo to making dose calculations. Ten hours' data for a selected release point and for one to five selected isotopes are shown on a semi-log plot, h Individual isotopic rates for up to five isotopes and/or the total release el rates for all isotopes may be plotted. Example i shows a sample of the computer prompts and the corresponding user responses required to generate a gaseous release trend plot. A sample f . gaseous release trend plot is shown in Example 2. I ' G L I
~
L r k i 1
.f I
b i [
.~
t og- .,=m.e--+.-p-%* - * ==- e ssm ee w--
,e.-en.--*g---ww-**==ys *g-se, e - * * * * -
***P*'i***p***gy*****%
- 9*** ,"***8**h4 p M8 P ' * **mf
i' l j CPSES EMERGESCY PLAN MANUAL ISSUE DATE PROCEDURE NO. EPP-301 OCT 261984
) m COMPUTER ASSESSMENT OF Q) RADIOLOGICAL CONDITIONS REVISION NO. O PAGE 45.0F 65
[ ATTACHMENT 6 PAGE 2 0F 3 . D EXAMPLE 1 g 1 GASEOUS RELEASE TREND PLOTS
], __ ___ __
ENTER START DAIE C MM/DD/fY HH:MM 3 : f/Ir19 0l0
't 4 ENTER END DATE C MM/DDnY HH:MM 3 : 6/1/79 5:0
}
EFTER RELEASE POINT C 1-4 3 : 2
.) ENTER THE NUMBEP OF CURVES DESIRED ON PLOT C 1-5 3 : 2 lp GASEOUS ISOTOPE OPTIONS 7-hR87 1-H3 2-C14 3-AR41 4-KR83M 5-KR85M 6-KR95 8-KR98 ?-KR89 10-KR90 11-XE131M 12-XE132M 13-XE133 14-XE135M J
18-CK51 10-r.N54 20-FE59 21-0059 i 15-XE135- 16-XE137 23-ZN65 17-XE138 24-SR99 25-SR?0 26-IR95 27-S2124 29 -C9134 22-C060
)l 29-CS136 30-tS137 31-9A140 32-CE141 33-CEl H 34-1131 35-1133
. 36 . GASES 37 .PART 39 . ALPHA 39-TOTAL p
~
ENTER ISOTOPE SELECTION FOR CURVE 1 C 1-39 3 : 3 i E"TER ISOTOPE SELECTION FOR CURVE 2 C 1-3? 3 : 17 DO YOU WANT AUTOMATIC HARD COPY GENERATION? E v CR N 3 N ENTER C C 3 TO ERASE SCREEN AND CONTINUE : C Prompts to produce 10-min data gaseous release trend plot d j .. 4 a i l i q
\
l ; i O 1 i i l l q j
**"'**-*-e--*y,= ,y < qg g,. =5*r *
?- p ,, ,
t
't CPSES ISSUE DATE PROCEDURE NO.
EMERGENCY PLAN MANUAL EPP-301 Dr.T 2 6 BM q COMPUTER ASSESSMENT OF
' ' Yg' RADIOLOGICAL CONDITIONS
-(<J. REVISION NO. O PAGE 46 0F 65 ATTACHMENT 6 i PAGE 3 0F 3 -
F EXAMPLE 2 . V i 16-Hiss GASE0uS Ilof0PE AELEAGE $ATA gggg, tg
] Lasifs ut 1
uggas Ettg q? pff s 6/14/04 R$a 6 i
#' sTm f arcs e, i,M es e
'l Este Daft a 6e seM Ss e H MLEAEE MINTS 3
>1 Sh ' .?
j Isoterrs Amet et
$f a El38 t
l
~
h I 81 j (h Ii
# 1
,,p - _ . . .
j .<, SN1 l D' ENTES C C 3 TO CONFIIGE.
. I,
,, 4 n. isi n.In nals. s.In. al.. ..li. . l.. ..l.. . l.a ..l.a C 8 3 70 Ster s M Ye No Yo Y. UsM ., Y Yo# Ue' M I5k o
}j 2 A 10-ein data gaseous release trend plot A, I i ( i t
')
I f i) i A-mm m m. p _ e--.-me-ow- wgm _, . , ,,, ., , , ,
- 2 . ..:ag :.
^
1 if CPSES ISSUE DATE PROCEDURE NO, EMERGENCY PLAN MANUAL EPP-301 OCT 261984 COMPUTER ASSESSMENT OF j h RADIOLOGICAL CONDITIONS REVISION NO. O PAGE 47.0F 65 1 ATTACHMENT 7 PAGE 1 0F 1 - FILES ASSOCIATED WITH GASEOUS RELEASE ISOPLETH CALCULATION
'l 1 }
I
) [ MET D 1 ( O
15-MIN
< Ma >
WQRESPACE 15 MIN MET
% J HOURLY MEQ WORKSPAC MANUALLY QNTERED MEM M
i _ 3 [ A0 DATA MOST RECENT O FILE j GASECUS RELEASE o 10-MIN EMERGENCY ! !$0PLETH CALCULATICNS ( 0 FILE j q POSTULATED Q OENT 0F p a WANUAur ENTERED ( DATA j - r m -
< J SITE SPECIFIC Y )
Files associated with gaseous release isopleth calculation i p-~.,,,,,,.-- 3,.nc- -,,y -~~
-.---, y, .,p 3 7g p, ; _. _ , , , ,,3rg ~ggr;;9;ggcgy;qqy_ p ?q,3y,";7- c
.:e . __. _ . - y 1
- CPSES w ISSUE DATE PROCEDURE NO.
EMERGENCY PLAN MANUAL EPP-301 OCT 261984 COMPUTER ASSESSMENT OF 3
.f f ))
.-. RADIOLOGICAL CONDITIONS REVISION NO. O PAGE 48 .0F 65 1
i ATTACHMENT 8 PAGE L OF 1 - GASEOUS RELEASE ISOPLETH CALCULATIONS - DATA
SUMMARY
^
}
- rE CO-es:-c :Ee UNIT. 01 UEE~. CJP I.
IA~E: s/26/E4 15:25 C-ASE0VS RELEASE Da7 A EU.7 DAD
- I MET DATA F0cl c'26/94 15: 0 FELEa9E FOIN7! 2 : ELE !? it E' C;0'-
;6: I4TA POR: 4/26/54 15:15 1
3
- SUhMADY OF METEOCOLOGICAL DATA i GF.00ND ELEVATED
{ ,. WIND SPEED (MPH): 6.1 P 00
- 3 (F L'I4D DIRECTION (DEG): SU F N t 4
DELTA-TEMF (DEO-r) -4.7 F 0.0 *
' IIU4 -THETA (DEG): 25.0 0 00 t a a.E!ENT TEMP (DEO-F): 0.0
- 0.0
- g
+J.m i ? Si'BILITY: A L E 9' STABILITY:
~ A Suom!RY OF 150T0FIC RELEASE RATE DATA (MICRO-CI/5EC.' t IE0 TOPE 3 NOT POINTED AFE ZERO +
-Pai =
5.0394E-04 XE139 = 5.9394E-04 I131 = 1133 = 5.03:4E-06
$.9394E-06 * ~~
EUMMARY OF EFFLUENT DISCHARGE RATE "ENT FLOW RATE (CFM): 0 0000E-01 PEAF X/0 AND DOSE AT OF BEYOND SITE 50VNDARY UHOLE BODY INuaL4 TION INGES7ICn DAMMA SNIN THYFOID THYR 0*I PEAK DOSE RATE (REM /uR): ('} .UO AT rEAN (SEC/M* $ 3): 3 375E-13 5.173E-13 4 334E-12 4 272E-4! 0*stadCE 'O PEAE '*ETEF5): 3.614E-07 3.414E-07 3 614E-07 3 614E " 1.6COEf03 1 60oE+03 !.d*(E'03 1. 6(0E" t 7E:f'!N At CEAh ;*ETEL?i: C '00E-01 v,00?E-01 0.At?E-01 0.00^E- - 92 U t CC: 'O ERafi i:'EEN add E0"TI*JE
- C
]
e-*yF{ { ' FTT ("FC*M[. Qp*','(G5 N77 %
. b.9*) ' '
g,, - . _ _ . _ ~ , 3 CPSES ISSUE *DATE PROCEDURE NO. EMERGENCY PLAN MANUAL g gg g EPP-301 COMPUTER ASSESSMENT OF b]j RADIOLOGICAL CONDITIONS REVISION NO. O PAGE 49.OF 65 ATTACHMENT 9 B PAGE 1 0F 2 ~
.i EXAMPLE 1 1
g GASE0US RELEASE ISOPLETH CALCULATIONS - PROMPTS FOR GENERATION OF WHOLE BODY GAMMA ISOPLETH PLOT (CONTOUR SPACING = 2)
)
4 D0 YOU WANT TO CONTINUE REVIEWING RESULTS? E Y OR N 3 ~! Y OPTIONS h y 1 - X/0 ISOPLETH E ' 2 - WHOLE BODY GAMNA ISOPLETH 3 - SKIN ISOPLETH 4 - INHALATION THYROID ISOPLETH h 5 - MILK INGESTION THYROID ISOPLETH
- ENTER OPTION SELECTION C 1-5 3 : 2 g
DO YOU WANT RESULTS PLOTTED? C Y OR N 3 : Y$ g DO YOU WISH TO NODIFY CONTOUR INTERVAL SPACIN07 C Y OR N 3 : Y L CONTOUR SPACING INTERVALS BY STABILITY CLASS ){ A= 1 B= 1 C= 1 De 1 E= 1 F= 1 0= 1 if i ENTER STABILITY CLASS CA-03 : A d;1, ENTER NUMBER OF INTERVALS BETWEEN CONTOURS C1-93 2 DO YOU WISN TO MAKE MORE MODIFICATIONS? C Y OR N 3: N
, ENTER C C 3 TO ERASE SCREEN AND CONTINUE : C I
i
,V o
L. 4 .i l
- NOTE: If your answer is "N", a new prompt will appear:
f Report on printer? (Y OR N] A "Y" response will generate a printed output for a X/Q isopleth. Results are given for 32
' (^.]
downwind distances and 20 crosswind distances. All distances are in meters. 1 1 . i
~' ' " ~~~~~
p"?l'yi,[. " ;;f _ .qqq'*;hTWg\W!F.*(7?7,K'~~T" ~ '*" * "'" ~'
1 CPSFS ISSUE DATE PROCEDURE NO. I EMERGENCY PLAN MANUAL OCT 261984 EPP-301 i
-s COMPUTER ASSESSMENT OF t s J RADIOLOGICAL CONDITIONS REVISION NO. O PAGE 50 0F 65 1
i ATTACHMENT 9 PAGE 2 0F 2 EXAMPLE 2 satte ] Qg m em ' * '
. 3 tmtfs ut i . p ustaa Esta j , / _ _ _ . _ +
Detta Seate84 88834
~f I /.d
.\' /
- ss/'
s a
.' I'- -
*t att min ontts s,ae,e4 sts e sa8 0474 taits Geste 84 48e85
} \ ' SPittinPeet 5.3
' %.~'%'-
/ \ 8iM E110N EnE f
,f '.
\ .
~'I W . .* LAP 5teDre teleMil 4..
*D e s Sf at!Lifv CLA$$ 4 k ! / '. PtM UnLad 4.6476-06 j / \ PEM L0c4TieretRI 3.leesee3 e
; , ,/ ., ,/* 3 l l l p
q g 7- ,_,.' y g e.e s.e scats (Attss s.e
\
y.<;' . . . . . . . . , \ utraw eartinrewct<wc
/ a.,/** \ N TOTAL 8.Hete46
1 % PICBLE GA6 8.65 m +6 f '. I 1 \ 80Dird 8.M?te03
.',j I
\ ittfrog tagn eas r*s ' l s s .en-e 3
...__._.,(t*.'"'.
/ a s.est-ee 3 3.eu-os
/
I
. . . . . . .s i /
A. . s i .en-4. i.eu-e,
. s s.est-ce t./...
/
1 s.eet-ee j e s. set-te t !
\ l
\ /
~
~~~ ,,/
\ '/
f ' f--~~,, l ,- I
/ j s'
] / Jt ',/ s
! /
/
f' _-
,/ Entre e c 3 to contima e 1 .
3 Gasenus release isopleth calculations - whole body gasssa Isopleth plot ~ (contour spacing a 2) } } ) 1 i E*g ' _bf $fa ', ,
~_ .- ,
- r -
~
2 'i j CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL EPP-301 j OCT 26 m4 COMPUTER. ASSESSMENT OF
- (} RADIOLOGICAL CONDITIONS REVISION NO. O PAGE 51.0F 65
[
- ATTACHMENT 10 3
PAGE 1 0F 5 - I DISPERSION / DOSE ACCUMULATION PROMPTS t Dispersion / Dose Calculations
Description:
The DISPERSION / DOSE CALCULATIONS option (6,4,2] is used to obtain dispersion and dose accumulations during emergencies. Dispersion, depletion, deposition, whole body gamma dose, skin dose, child inhalation thyroid dose and infant milk ingestion thyroid dose are computed for all "on" release points. The Gaussian centerline plume model is used for the dispersion calculations. Calculations are made for the 20 distances specified using the X/Q PARAMETER option [2,2,3] of the EDIT SITE SPECIFIC DATA option list. {- Calculations may also be made at the site boundary, but accumulations are $ not made for site boundary calculations. The X/Q and related dispersion calculations use either the 15-min meteorological or 15-min workspace data files, the most recent data files, or manually entered data. The ground release is the only type used at CPSES. The attached (Example 1) is an example of dispersion / dose calculations prompts illustrating the use of 15 minute meteorological data file and 10 minute radiological data file. Example 2 is a summary of meteorological g data for this option. [ See Attachment 11 to " Print Dispersion / Dose Results". l Results of accumulations are stored on the X/Q LAST and DOSE LAST f,iles (Attachment 11). The data on these files may be printed, plotted as l isodose contours on a site map, or plotted as a receptor exposure plot using options 3, 4 and 5 of the DISPERSION / DOSE ACCUMULATION (LEVEL 2) option list. Functions are provided as part of the PRINT DISPERSION / DOSE ,
~
RESULTS option to add the results in the LAST files to the results in the TOTAL files and then print the TOTALS. If additional details are required j see operator's guide, E-115-1220, section 8.3.3.3. if
- 1 1
G i m_ . .
c_- - CPSES ISSUE DATE PROCEDURE NO. j EMERGENCY PLAN MANUAL 0CT 261984 EPP-301 ]1 COMPUTER ASSESSMENT OF (f RADIOLOGICAL CONDITIONS REVISION NO. O PAGE 52 0F 65 1 ATTACHMENT 10 PAGE 2 0F 5 - EXAMPLE 1 s DISPERSION / DOSE ACCUMULATION - PROMPTS k l EMERGENCY DISPERSION / DOSE OPTIONS
!) -
P 1 - TERMINATE 2 - DISPERSION / DOSE CALCULATIONS 3 - PRINT DISPERSION / DOSE RESULTS 4 4 - PLOT DISPERSION / DOSE RESULTS 5 - RECEPTOR EXPOSURE PLOT b y ENTER OPTION SELECTION C1-53 : 2 f.. DISPERSION / DOSE CALCULATIONS I RELEASE POINT STATUS
~..
, 1 - 0FF 2 -- ON 3 - 0FF 4 - 0FF /' 4
- CALCULATIONS WILL PE MADE FOR ALL 'ON* RELEASE POINTS -
4 DO YOU WANT TO ENTER MET AND RAD DATA MANUALLY? C Y OR N 3 : N l' DO YOU WANT TO USE TNE MOST RECENT MET AND RAD DATA? C Y OR H 3 : N DO YOU WANT 15-MIN C F 3 OR 15-MIN WORKSPACE C W 3 METEOROLOGICAL DATA? : F ,) DO YOU WANT TO USE 10-MIN C T J OR SIMULATED C S 3 RAD DATA? : T ENTER DATES FOR ACCUMULATION 3 P. ENTER START DATE C MM/DD/YY NN:MM J : 5/24/84 10:0 l ENTER END DATE C MM/DD/YY NN:MM J : 5/24/84 12:0 l - DO YOU WANT TO BE PROMPTED TO REPLACE BAD MET DATA? C Y OR N 3 : N
, DO YOU WANT NRC TERRAIN CORRECTION FACTORS? C Y OR N 3 : N DO YOU WANT SUBMERSION C S 3 OR FINITE C F 3 GAMMA? : S $ DO YOU WANT PEAK VALUES C P 3 OR SITE BOUNDARY VALUES C S 3 : P
{ REPORT ON PRINTER? C Y OR N 3 : N j ' ENTER C C 3 TO ERASE SCREEN AND CONTINUE : C "r VENT FLOW DATA ENTRY FOR RELEASE POINT 2 , h-DO YOU WANT TO USE COMPUTED VENT FLOW RATE? C Y OR N 3 : Y L ENTER C C 3 TO ERASE SCREEN AND CONTINUE ! C I +
.i
_ . -~. --, =
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a m _ _ _ _ {42__' _
~.- 7 - --
.i CPSES ISSUE DATE PROCEDURE NO.
, EMERGENCY PLAN MANUAL EPP-301 OCT 261984 ij g COMPUTER ASSESSMENT OF j () RADIOLOGICAL CONDITIONS REVISION NO. O PAGE 53,0F 65 u
ATTACHMENT 10 et PAGE 3 0F 5 - n il y EXAMPLE 2 10F 3 T: U1 DISPERSION $0SE ACNWION PROMS USER: EEEE
~
DATE: 5/24/84 12:57 w MET DATA FOR: 5/24/84 10: 0 RELEASE POINT: 2 RELEASE TYPE:
$ s. RAD DATA FOR: 5/24/84 10: 5
SUMMARY
OF METEOROLOGICAL DATA
- i J
P GROUND ELEVATED 1 - j WIND SPEED (MPH): 1.4 P 14 P WIND DIRECTION (DEG): N P N P s DELTA-TEMP (DEG-F): -1.1 P -1.1 P _s SIGMA-THETA (DEG): 0.0 P 0.0 P AMBIENT TEMP (DEG-F): 0.0
- 67.1 P HORIZ STABILITY: B j B
~ VERT STABILITY: B~ B e
SUMMARY
OF ISOTOPIC RELEASE RATE DATA (MICRO-CI/SEC) A j ' ISOTOPES NOT PRINTED ARE ZERO
.) -
d ' AR41 = 1 3285E+05 XE138 =~~ 1.3285E+05 I131 = 1 3285Et03 4 I133 = 1.3285E+03
SUMMARY
OF EFFLUENT DISCHARGE RATE
~
VENT FLOW RATE (CFM): 3.6186E+04
- .- 15-MIN PEAK X/0 AND DOSE RATE '
m
.. X/0,X/QD DISTdfCE DOSE RATE DISTANCE d
(SEC/M3) (METERS) (REM /HR) (METERS) ] X/G WK SPLT 1.628E-05 1 804.0 W.B. GAMMA (S): 2.79E-03 804.0 j DEPLETION: 1 619E-05 804 0 SKIN: 4.24E-03 804.0 INHAL. THY.: 4.92E-02 804.0 [h.: D/G DISTANCE INGES. THY.: 1.31E+01 804.0
' (1/M2) (METERS) l DEPOSITION: 8.116E-08 804.0 F ENTER C C 3 TO ERASE SCRE.IN AND CONTINUE ! C
. . - - - . , _ . . . . _ , . - . r. .._ - , -
1 CPSES 8SSUE DATE j EMERGENCY PLAN MANUAL ggg PROCEDURE NO. EPP-301 h t. COMPUTER ASSESSMENT OF j ($i RADIOLOGICAL CONDITIONS REVISION NO. O PAGE 54 0F 65 l! l , ATTACHMENT 10
. PAGE 4 0F 5 -
EXAMPLE 2 [1 j ' 2 0F 3 n SITE: F UNIT: U1 DISPERSION / DOSE ACCUMULATION - DATE PROMPTS ] USER: EEEE a DATE: 5/24/84 12:59 p j MET DATA FOR: 5/24/84 11: 0 RELEASE POINT: 2 RELEASE TYPE: ] RAD DATA FOR: 5/24/84 11: 5 J 4 SUMARY OF METEOROLOGICAL DATA 6} / GROUND ELEVATED 1
. - WIND SPEED (MPH): 5.3 P 5.3 P , WIND DIRECTION (DEG): ENE P ENE P j~ DELTA-TEMP (DEG-F): -4.7 P -4 7 P
] SIGMA-THETA (DEG): 3.0 P 3.0 P p A AMBIENT TEMP (DEG-F): 0.0
- 75.0 P
'l E/ HORIZ STABILITY: A A
] YERT STABILITY: A A
)1 '
SUMMARY
OF ISOTOPIC RELEASE RATE DATA (MICRO-CI/SEC) ISOTOPES NOT PRINTED ARE ZERO AR41 = 1.3285Ef05 XE138 = 1.3285E+05 I131 = 1.3285E+03 hj I133 = 1.3285E+03 4 )
SUMMARY
OF EFFLUENT DISCHARGE RATE b h YENT FLOW RATE (CFM): 3.6186E+04 - Y 15-MIN PEAK X/Q AND DOSE RATE t c l ' X/GrX/QD DISTANCE DOSE RATE DISTANCE 1 (SEC/M3) (METERS) (REM /HR) (METERS) j X/G WK SPLT: 1.899E-06 804.0 W.B. GAMMA (S): 4.45E-04 804.0 1 DEPLETION: 1.855E-04 804.0 SKIN: 6.86E-04 804.0
! INHAL. THY.: 5.65E-03 804.0 Q >
D/0 (1/M2) DISTANCE (METERS) INGES. THY.: 1.45E+01 804.0 DEPOSITION: 8.992E-08 804.0 ENTER C C J TO ERASE SCREEN AND CONTINUE : C
-w
.. w, ., se-- ...-. ., , . . , , - . + . - -,,.e,...3 ,%.- - - - , ,,y . - - . ...e , -p. . .vr w e t-w qy m9 - =
# * . ~ P - . ,, .
CPSES VSSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL ET26W EPP-301 i COMPUTER ASSESSMENT OF O. RADI0t0cICAt CONDITIONS REv1SIOx NO. O PACE 55 Or 65 ATTACHMENT 10 PAGE 5 0F 5 7 SITE: EXAMPLE 2 l UNIT: U1 3 0F 3 1 USER: EEEE i DATE: 5/24/84 13: 2 DISPERSION / DOSE ACCUMULATION - DATA PROMPTS 1 MET DATA FOR: 5/24/84 12: 0 RELEASE POINT: 2 RELEASE TYPE: I RAD DATA FOR: 5/24/84 12: 5
}
t SUMARY OF METEOROLDOICAL DATA I i GROUND ELEVATED WIND SPEED (MPH): 1.9 P 19 P WIND DIRECTION (DEG): E P EP DELTA-TEMP'(DEG-F): 2.2 P 2.2 P SIGMA-THETA (DEG): 3.0 P 3.0' P AMDIENT TEMP (DEG-F): 0.0
- 74.9 P HORIZ STABILITY: F F VERT STABILITY: F F
. (3 D
SUMMARY
OF ISOTOPIC RELEASE RATE DATA (MICRO-CI/SEC)
; IS0 TOPES NOT PRINTED ARE ZERO AR41 = 1.3285EM5 XE138 = 1.3295EM5 I131 = 1.3285EM3 I133 = 1.3285EM3 SumARY OF EFFLUGT DISCHARGE RATE 1
I VENT FLOW RATE (CFM): 3.4184EM4 V f, 15-MIN PEAK X/0 AND DOSE RATE i
- f. !
i
- X/0,X/QD DISTANCE DOSE RATE DISTANCE (SEC/M3) (METERS) (RD/HR) (METERS) b X/G WK SPLT: 1.408E-04 2414.0 W.B. GAMMA (S): 2.05E-02 2414.0 DEPLETION: 1.387E-04 2414.0 SKIN: 3.04E-02 2414.0 3 INHAL. THY.: 4.20E-01 2414.0 l D/G DISTANCE INGES. THY.: 1.28EH1 2414.0 p (1/M2) (METERS)
H '] DEPOSITION: 7.934E-08 2414.0 . r ', ENTER C 6 3 TO ERASE SCREEN AND CONTINUE : C (/
- ACCUMULATION COMPLETE -
D0 YOU WISH TO CONTINUE WORK WITH THIS OPTION? C Y OR N 3 : N y
- . c.. ,.-._ -- _ _ , _ . . _
;; w
(! i
- CPSES ISSUE DATE PROCEDt'RE NO.
EMERGENCY PLAN MANUAL ggg EPP-301 COMPUTER ASSESSMENT OF $j h, RADIOLOGICAL CONDITIONS REVISION NO. O PAGE 56 0F 65 4 ATTACHMENT 11 PAGE 10F 4 " PRINT DISPERSION / DOSE RESULTS . N 9 Description. The PRINT DISPERSION / DOSE RESULTS option [6,4,3] is used to d print the accumulated dispersion, depletion, and deposition or dose results ij calculated using the DISPERSION / DOSE CALCULATIONS option [6,4,2].
- l j Dispersion or dose may be printed for 16 directions and the 20 distances y specified in parameter 25 of the X/Q PARAMETERS (2,2,3] option. Whole body q gamma (submersion or finite), skin, child inhalation thyroid and infant Q ingestion thyroid dora may be printed.
e In order to provide a subtotal result of dispersion / dose accumulations, two d files of each type X/Q and dose (labeled LAST accumulation and TOTAL q accumulation) are provided. Results computed by the DISPERSION / DOSE b CALCULATION option (6,4,2) are stort i in the LAST files. The user may check intermediate results in the LAST file prior to adding these LAST accumulations to the TOTALS. Values in either the LAST or TOTAL files can 1 be printed for 20 distances and 16 directions. An option is provided that ij can be used to add the LAST accumulation results to the TOTAL file, d 2!' h' The addition of the LAST accumulation to TOTAL accumulation is performed tj differently for X/Q than the addition for dose. X/Q results are added for y each individual release point and are stored in the TOTAL file.by release 1~ point. Dose results from the LAST file are summed for all "on" release d points, and the total for all release points is stored in the TOTAL file. U An option is provided to clear dates of accumulation and zero the tables. fj The first option sets both start and end date of total accumulations to the
- LAST start and end dates. The second option enables the end date to be i updated to the last accumulation end date when processing the second or
- it more addition of the LAST file to the TOTAL file. It is up to the user to 3 determine which option should be used.
N r y When printing X/Q results, the release type in the release point parameters ~ Q table dictates the tables to be printed. When a ground release is selected j and an accumulation is made, this print option only allows printing of
- .! ground dispersion, depletion and deposition. For additional details see Ij operator's guide E-115-1220, section 8.3.3.2.
The attached (Example 1) illustrates computer prompts and operator responses required to print the last whole body file. The corresponding q printout is shown in the attached (Example 2). The 20 values shown for j each direction are the whole body gamma dose at each of the 20 distances shown at the bottom of Example 2. b . i j U., . , a a 4 i V g .
, 4
~ .
_. . - ~ '~
. 1~
i d- CPSES TSSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL EPP-301 COMPUTER ASSESSMENT OF
.h RADIOLOGICAL CONDITIONS REVISION NO. O PAGE 57.0F 65 i
ATTACHMENT 11 PAGE 2 0F 4 - p PRINT DISPERSION DOSE RESULTS
] EXAMPLE 1 Li t
1 i! u ]j. PRINT DISPERSION OR DOSE RESULTS i OPTIONS [j _ _ _ _ _ _ d 1 -- C'_ EAR LAST OR TOTAL TABLES 4 2 -- PRINT SELECTED FILES I 3 - ADD I AST ACCUNULATION TO TOTAL
- l 3 ENTER OPTION SELECTION C1-33 2
'j DO YOU WANT TO WORK WITH X/0 C X 3 OR DOSE C D 3 : D ! hq DO YOU WANT TO OPERATE ON LAST C L 3 OR TOTAL C T 3 ACCUMULATION ARRAYS? : L i
RELEASE POINT STATUS
.; 1 -- 0FF 2 - ON 3 - 0FF 4 - 0FF ENTER RELEASE POINT C 1-4 3 : 2 REPORT ON PRINTER? C Y OR N 3 : N ] DOSE OPTIONS -
J l 1 - WHOLE 30DY GAMMA ;
} 2 - SKIN '
3 - INHALATION THYROID - 4 - MILK INGESTION THYROID F , ENTER OPTION SELECTION C1-43 : 1 H ENTER C C 3 TO ERASE SCREEN AND CONTINUE : C y I Dispersion / Dose accumulation - prompts to print DOSE results
)i in LAST accumulation file l
l- 2 l I I 4
, .y -, :---.;r- .- e = - .... - c,
) CPSES TSSUE DATE PROCEDURE NO. 'i EMERGENCY PLAN MANUAL EPP-301 1 OCT 261984 d COMPUTER ASSESSMENT OF j h- RADIOLOGICAL CONDITIONS REVISION No. O PAGE 58 0F 65 e
N 1 ATTACHMENT 11 9 PAGE 3 0F 4 . 2 U1 4 USER: EEEE ]. DATE: 5/24/84 13: 2 PRINT DISPERSION / DOSE RESULTS d DATES OF LAST DOSE ACCUMULATION : 5/24/84 10: 0 TO 5/24/84 12: 0 DOSE ACCUMULATION FOR WHOLE 80DY GAMMA (REM) FOR RELEASE POINT: 2
- S : 4.9794E-04 2.1126E-04 6 1889E-05 2.6949E-05 1.283X-05 :~
- : 7.1744E-04 4.4404E-04 3.1242E-04 2.1754E-04 1.5408E-04 :
- 1.1018E-04 7.9455E-07 1.6877E-07 3.9523-08 9.8941E-09 :
? : : 2.5477E-09 6.7999E-10 1.8395E-10 5.0312E-11 1.3939E-11 : 4
- SSW ; 4.8959E-04 2.3758E-04 4 0496E-04 2.2945E-03 2.4091E-03 :
", : : 1.3449E-03 9.2235E-04 6.6148E-04 5.0443E-04 3.9716E-04 :
- : 3.1885E-04 2.4010E-04 1.0970E-04 5.4314E-05 2.9834E-05 :
- . : 1.7053E-05
- 1.0458E-05 6 5982E-04 4.2149E-04 2.7414E-04 :
1 : 3W : 8.4035E-05 3.3330E-04 5.5505E-04 4.0335E-04 1.8111E-04 : U : : 9.8890E-05 6.3937E-05 4.3817E-05 3.2442E-05 2.4848E-05 : I } : 1.9332E-05 1.5242E-05 5.3008E-04 2.1777E-04 1.028K-04 :
'} : : 5.0502E-07 2.5724E-07 1.3408E-07 7.1042E-08 3.8528E-08 :
- a. .
4: : WSW : 3.8937E-04 8.1399E-05 4.0825E-05 2.8554E-05 1.4744E-05 : d : : 1 1216E-05 8.1971E-04 4.2745E-04 5.0544E-04 4 1704E-06 : a : : 3.4888E-04 2.9508E-04 1 4178E-04 7.4079E-07 4.3936E-07 : 1 : : 2.4308E-07 1.4972E-07 1.1227E-07 7.4974E-08 5.0650E-08 :
- W : 5.841X-04 2.4932E-04 7.5389E-03 4.2558E-03 1.9043E-03 :
y : 1 0402E-03 6.5116E-04 4.2555E-04 3.0185E-04 2.2059E-04 : J : : 1 6314E-04 1.2191E-04 3.1785E-05 9.4218E-04 3.3172E-04 : l : : 1 1927E-06 4.5158E-07 1.7559E-07 6.9344E-08 2.7941E-08 : WNW : 0.0000E-01 0.0000E-01 0.0000E 0.0000E-01 0.0000E-01 :
- : 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 :
- : 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 :
- : 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 :
': NW : 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 :
- : 0.0000E-01 0.0000E-01 0.0000E-01 0 0000E-01 0.0000E-01 :
- 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 :
- : 0.0000E-01 0.0000E-01 0.0000E-01 0 0000E-01 0.0000E-01 :
- NNW : 0.0000E-01 0.0000E-01 0 0000E-01 0.0000E-01 0.0000E-01 :
- : 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 :
- : 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 :
] : : 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 : 0 DISTANCES USED IN CALCtLATIONS (METERS) 804 0 1609.0 2414 0 3218.0 4828.0 , ,' 6437.0 8044.0 7654.0 11265.0 12874.0 14484.0 16093.0 24140.0 32184.0 40233.0 2 48280.0 54327.0 44373.0 72420.0 80447.0 ENTER C C 3 TO ERASE SCREEN AND CONTINUE : C ' ~C .. . 2ME3MI 'O J~I7 "2P2UWESZ3E? 2FY
_- s - g .. ~ :-- i CPSES ISSUE DATE PROCEDURE No. EMERGENCY PLAN MANUAL EPP-301 OCT H B84 COMPUTER ASSESSMENT oF O RADiotoorCAt CoND1TroNS Rtv1S1oN No. o PicE 39.or es ATTACHMENT 11 PAGE 4 oF 4 . U1 USER: EEEE DATE: 5/24/84 13: 3 PRINT DISPERSION / DOSE RESULTS DATES OF LAST DOSE ACCUMULATION : 5/24/84 10: 0 TO 5/24/84 12: 0 DOSE ACCUMULATION FOR I440LE 80DY 8AMMA (REM) FOR RELEASE POINT: 2
- N : 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 :
p : : 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 :
- : 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 :
y :
- 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 *
- NNE : 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 :
! : : 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 :
p : : 0.0000E-01 0 0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 :
- : 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 :
j : NE : 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 :
- : 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 :
i ? h :
- 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-0; :
0.0000E-01 :
- ENE : 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 :
- : 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 :
- : 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 0 0000E-01 :
[ : : 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 : Le 8
- E : 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 :
- : 0.0000E-01 0 0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 : ,
j : : 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 0 0000E-01 : 1
- : 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 : !
] ! : ESE : 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 :
l : : 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 : . i : : 0.0000E-01 0 0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 : _ i j : 0.0000E-01 0 0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 : ; j SE : 0 0000E-01 0.0000E-01 0 0000E-01 0.0000E-01 0.0000E-01 : 3 : : 0.0000E-01 0.0000E-01 0 0000E-01 0.0000E-01 0.0000E-01 :
- : 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 :
, : 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 :
p SSE : 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 : i : : 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 :
. : : 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 :
' : : 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 0.0000E-01 : DISTANCES USED IN CALCULATIONS (METERS) 804.0 1609.0 2414.0 3218.0 4828.0 6437.0 8044.0 9454.0 11265.0 12874.0 14484.0 16093.0 24140.0 32184.0 40233.0 1 48280.0 54327.0 44373.0 72420.0 80467.0 i
'O l Y "e'*~ # ~'*'T****'
[*" ** [', a ~*~.~~*'w~~-*-=f**y -ym e* y wme ;
.: - - ~
_ - _- ~ _.z. -
. .33 .
CPSES ISSUE DATE . PROCEDURE NO. EMERGENCY PLAN MANUAL EPP-301 rmT o e 10AA
~ ~ ' ~ ~
COMPUTER ASSESSMENT OF f[> RADIOLOGICAL CONDITIONS REVISION NO. O PAGE 60,0F 65 ATTACHMENT 12 PAGE 1 0F 3 - c PLOT DISPERSION / DOSE RESULTS It Description'. The PLOT DISPERSION / DOSE RESULTS option [6,4,3] is used to Ii display contours of constant dispersion or dose on a map of the plant site. 1 j It can be used to estimate potential for exceeding offsite dose limits, and has the application after unintentional releases to determine extent of j offsite effects.
'l l Dispersion, or plume dose computed from accumulation runs made with the 3 DISPERSION / DOSE CALCULATION option [6,4,2] may be plotted. Data in either j the LAST or TOTAL accumulation files may be selected for plotting.
J j The map of the plant site r0gion shows roads, towns, rivers and other a topographical features. The program draws the background map to the scale j selected by the user. For specific details see operator's guide, section i 8.3.3.3. .1 . L The attached (Example 1) illustrates prompts and operator responses required to produce a plot of dispersion or dose results. - Example 2 1 th illustrates a typical dispersion / dose accumulation - whole body gamma contour plot. M l o i _ I t '
)
lt h' f.J o 4 9
- we yw = - m e%y - ve-==e.
-.e=**.$ eye ; -y= w -e===.=ge -. e-a p r,* **
.=M + - y mg-=* peep. - y *
!=7 e ;
1 sg c t- *q
_ _. .:-< - - . - - - - - r_ . u -<- CPSES ISSUE @ ATE PROCEDURE EO. BERGENCY PLAN MANUAI. EPI'-301 OCT 261984 l COMPUTER ASSESSMENT OF j RADIOLOGICAL CONDITIONS REVISION NO. O PAGE 61 0F 65 ATTACHMENT 12 PAGE 2 0F 3 . j PLOT DISPERSION / DOSE RESULTS EXAMPLE 1 H t 4 I 'j PLOT DISPERSION OR DOSE RESULTS 1 l l ENTER PLOT TYPEr X/0 C X 3 OR DOSE C D 3 : D j ENTER DESIRED ACCUMULATION, LAST C L 3 OR TOTAL E T 3 : L 1 RELEASE POINT STATUS ]s - - 1 - 0FF 2 - ON 3 - 0FF 4 - 0FF ENTER RELEASE POINT C 1-4 3 2 DOSE OPTIONS j 1 - VHOLE-BODY GAMMA a 2 - SKIN j 3 - INHALATION TNYROID j
^
4 - MILK INGESTION THYROID H j ENTER OPTION SELECTION C1-43 : 1 ENTER MINIMUM CONTOUR VALUE C N.N > 0 3 : 1.0E-4
- ENTER MAXIhuM DISTANCE DOWNWIND (MILES) C N.N > 0 3 : 10 ENTER C C 3 TO ERASE SCREEN AND CONTINUE : C
]
5 Dispersion / Dose accumulation - prompts to plot contour plots using dose results in LAST accumulation file a,
'l i
i 't i
, ,jpgg,;,q,-
_. 7 r
a . -- : ,. 3 J t 1 . CPSES ISSUE DATE PROCEDURE NO.
] EMERGENCY PLAN MANUAI. EPP-301 OCT 261984 COMPUTER ASSESSMENT OF 9 RADIOLOGICAL CONDITIONS REVISION NO. O h PAGE 62 0F 65 j ATTACHMENT 12
) 3 PAGE 3 0F 3 . PLOT DISPERSION / DOSE RESULTS 'J q EXAMPLE 2 fi 3
$1TE s l lastis ut unsas rarc Saft s Se44e94 83s 7 wens-.cov sessus setas
,.M.A ri\f e"~- V N g e
,# % Last ST am=m atten .4 les .
s . - - ~ as.aa,f,D,afts Ge24e..
,e. e ,.s .
_ ,e' /
^-
/4 stumes p.stnis a
)
o n,
-/
/ /
I i
\
c,"L44)
-
- Vf e scau casuss
,1 \ 2/
ms
\ ,/
(\ t i (mv i , c . N v ' bj ,
,, g fr s, s
< ,.* :=u. ,.c.,
- f. - l i
l-
/ / } %
1 4 (M X. I N lt/
,#d' ,s
,/ g j
~ h.=f i*
( ~% I s - a s
$<*$.~Pw\I_.rsj 4~J g s
~
~
k t'ss',' l ~
\ s,/
')' j ,g \.
%,- sensa t c 3 7. contasu i 1: _, .. .
i ] Dispersion / Dose accumulation - whole body gasuma contour plot 4
/33 (y
i '--*-*=--+ w~s-_y =_ar-wp y7 e w emeg 7 ..g= _- . . , . ,
*gw=e+ __*-a,, j= , ge ;+ =y .e 9
- e n.
- ~ -
CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL EPP-301 OCT 261984 8
,._ COMPUTER ASSESSMENT OF RADIOLOGICAL CONDITIONS REVISION NO. O PAGE 63.0F 65 j ~a.- 'l ATTACHMENT 13 PAGE 1 0F 3 -
RECEPTOR EXPOSURE PLOT l -
Description:
The RECEPTOR EXPOSURE PLOT option [6,4,5] is provided to give ! the operator a tool for rapid assessment of conditiors in the emergency l j planning zone. The data plotted is based on dose accumulations calculated ;
; using the DISPERSION / DOSE CALCULATIONS option [6,4,2]. The plot consists of a circular grid divided into 16 pie-shaped sectors, each divided into 10 l radial segments. The appropriate segments are darkened to indicate j exposure in the segment. The amount of exposure in a segment is indicated j by shading the segment with one of 5 shades to represent less than 0.01%, ,; 0.01 to 0.1%, 0.1 to .1%, I to 10% and 10 to 100% of the limit for the j selected dose type. If additional details are required see operator's guide E-115-1220, section 8.3.3.4. ] The attached (Example 1) delineates the prompts and operator responses to j generate a receptor exposure plot. Example 2 is a typical receptor +
exposure plot of dispersion / dose accumulation. , 1 :rs a W l I4 1 I le m-e
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I 1 j Dispersion / Dose accumulation - prompts to plot receptor - I exposure plot using data from LAST dose accumulation i 1
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,j RADIOLOGICAL CONDITIONS REVISION NO. O PAGE 65 0F 65
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lj O j PROCEDURE NO. EPP-302 i REVISION NO. 3 i 1 8 ora e1 j COPY 2 CO SUBMITTED BY: . SUPERIMEKDENT, SUPPORT SERVICES b DATE: /!-M.8 / g (, APPROVED BY: ' r DATE: / - [ C pGEMTO DPERATIONS
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- l- CPSES ISSUE DATE PROCEDURE NO.
f EMERGENCY PLAN MANUAL EPP-302 JAN 091985 MANUAL ASSESSMENT OF [hd RADIOLOGICAL CONDITIONS REVISION NO. 3 PAGE 2 0.F 43 i 1.0 Purpose The purpose of this procedure is to provide guidance and instructions
; for estimating offsite dose rates and integrated doses to the whole body and thyroid in the event of a release of airborne radioactive
{ material from CPSES. 2.0 Applicability 2.1 This procedure is applicable to the Shift Technical Advisor, j Onsite Radiological Assessment Coordinator, Offsite Radiological Assessment Coordinator, Radiation Protection Coordinator and those CPSES Emergency Organization radiological assessment personnel who are responsible for ensuring that offsite dose j projections are performed. t 2.2 This procedure shall be utilized in the event that the General Atomic RM-21 Computer is inoperable during a declared emergency of the Alert class or higher. 2.3 The projected offsite doses calculated in accordance with this l procedure shall be used in conjunction with Procedure EPP-304, ({} " Protective Action Guides", as a basis for determining any offsite protective actions to be recommended to State and local
; officials.
2.4 This procedure shall be implemented by CPSES emergency response personnel in the following manner: 2.4.1 Prior to the activation of the Technical Support Center (TSC), the on-duty Shift Technical Advisor shall implement
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this procedure. 2.4.2 Following the activation of the TSC, but prior to the activation of the Emergency Operations Facility (EOF), the Onsite Radiological Assessment Coordinator shall implement this procedure. -- 2.4.3 Upon activation of the EOF, the Offsite Radiological e Assessment Coordinator or the Radiation Protection Coordinator shall implement this procedure. 2.5 This procedure becomes effective when issued. 3.0 Definitions 3.1 Emergency Conditions - Situations occurring which cause or may threaten to cause radiological hazards affecting the health and {r}5 safety of onsite personnel or the public, or which may result in damage to property. f ,,- ,_m.-.. . ---- 77p ., -. . , , -
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1 CPSES ISSUE DATE PROCEDURE NO.
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EMERGENCY PLAN MANUAL M0925 EPP-302 MANUAL ASSESSMENT OF. h RADIOLOGICAL CONDITIONS REVISION NO. 3 PAGE 3 0F 43 1 3.2 Emergency Action Level (EAL) - A classification system of emergency severity based on operational, radiological and - meteorological conditions at or near the plant site. 3.3 Exclusion Area Boundarv (EAB) - That area surrounding the Station, in which TUGC0 has the authority to determine all j sctivities including exclusion or removal of personnel and ]. property from the area. 3.4 Emergency Planning Zone (EPZ) - That area surrounding the Station h in which emergency preparedness planning is conducted for the protection of the public. With respect to protecting the public 4 from the plume exposure resulting from an incident, the EPZ encompasses an area with a radius of approximately 10 miles f surrounding the facility. With respect to the ingestion exposure [ pathway, the EPZ encompasses an area with a radius of about 50 f miles, j 3.5 Projected Dose - That dose of ionizing radiation that is likely j to be received by a population group if no protective action measures are implemented.
@ 3.6 Protective Actions - Those emergency measures taken for the purpose of preventing or mini'aizing radiological exposures to affected population groups.
s 3.7 Protective Action Guides (PAG) - Projected radiological dose values to individuals in the general population that warrant 1 protective action. Protective actions would be warranted
' provided that the reduction in individual dose expected to be 3
achieved by carrying out the selected protective action is not j offset by excessive risks to individual safety in taking that _ l protective action. 3.8 Insolation - The rate of delivery of all direct solar energy per
!. unit of horizontal surface.
a 3.9 Effective Age - Effective age is defined as the time elapsed from ] 4 the instant reactor core power generation was halted until the dose is received from the released mixture. For the purpose of this procedure, consicer the effective age to consist of two time components: (1) effective age at the time of the onset of the release, and (2) the transit time from the point of release to the arrival at the key receptor locations, h 3.10 Source Term - In the context of offsite dose calculations, this term refers to the characteristics and release rate of the Q radioactive material. 14 1 4
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l EMERGENCY PLAN MANUAL MMM EPP-302 j ., . . . - - - - MANUAL ASSESSMENT OF h RADIOLOGICAL CONDITIONS REVISION NO. 3 PAGE 4 0F 43 3.11 Pasquill Atmospheric Stability Classifications - The Pasquill atmospheric stability classifications are a measure of the - stability or instability of an air mass based upon the vertical i temperature differential between two points. At CPSES, this { temperature differential is determined between the 60 meter and 10 meter levels of the meteorological tower. 1 3.12 Normalized Relative Concentration (Xu/Q) - The normalized
) relative concentration is a measure of the dispersion 3
characteristics of an air mass as determined by the exisgng
] atmospheric stability classification (units are in meter ). )) 3.13 Relative Concentration (X/Q) - The relative concentration is the j normalized relative concentration divided by the wind speed in ij meters per second (units are in sec/ meter8 ). ~
j 3.14 Wind Direction - Wind direction is the direction from which the wind is blowing. r . 3.15 Receptor Location - The receptor location is a point in the j affected downwind sector which will be used as a reference point at which offsite doses are to be calculated. O 3.16 Receptor Distance - The receptor distance is the number of miles between the receptor -location and the point of release. 4.0 Instructions 4.1 Precautions - 4 2 4.1.1 The primary method of determining offaite doses shall
) utilize the General Atomic RM-21 computer as prescribed in Procedure EPP-301, " Computer Assessment of Radiological 1 Conditions." This procedure serves only as a backup
{j method. 1
! 4.1.2 The dose projection capabilities of the manual -
d calculational method depend solely upon onsite j - meteorological data, which becomes less exact at greater
} distances from the release point and/or at longer time intervals after the release.
4.1.3 The onsite meteorological monitoring systems are most j effective up to 2 hours, with limited accuracy beyond 8 1 hours, and up to 3 miles, with limited accuracy beyond 10 j miles, n I 4 p l 1
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- j. EMERGENCY PLAN MANUAL JAN 09 dE5 EPP-302 1
,,, MANUAL ASSESSMENT OF
, - () RADIOLOGICAL CONDITIONS REVISION NO. 3 PAGE 5 0F 43 4.1.4 When collecting wind speed and wind direction data from E the primary meteorological system, backup meteorological - system or the National Weather Service Forecast Office [ care must be taken to ensure that a fif teen minute average value is used when making these dose projections and not an instantaneous reading. 4.1.5 At greater distances and for longer time intervals, s, regional meteorological data not available in the Control J Room may be required to formulate offsite dose .i proj ections. This information can be obtained from the
- National Weather Service Focal Point Air Pollution
, Meteorologist. The types of information which can be obtained from this office includes t'emperature, wind j speed, wind direction, cloud height, cloud cover and lapse rate. The correct address and telephone number is:
! National Weather Service Forecast Office 819 Taylor Street, Room 10A44 3{ Fort Worth, Texas 76102 .
1 Telephone: (817) 334-3401 1
@ 4.2 Initial Actions J 4.2.1 Obtain the dose assessment material from the TSC, EOF or S Control Room storage lockers. This material consists of J the following equipment:
}~ 4.2.1.1 A base map. covering a 10-mile radius out from F the Station (Plume Exposure EPZ). u - ] 4.2.1.2 An overlay of concentric circles around the f Station for prediction of the plume movement outward from the Station. ] Note: The base maps and overlays are 3 permanently installed in the TSC and ] EOF. j . j 4.2.1.3 A set of seven plume overlays, one for each of ? the seven Pasquill atmospheric stability classes. These overlays are used to estimate the location of the affected downwind areas as a l result of the plume expansion. 4.2.1.4 A TI-59 programmable calculator, programmed magnetic cards and a set of manual offsite dose D calculation worksheets.
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i l CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MAh M EPP-302 JAN 091985
, MANUAL ASSESSMENT OF
(- w.
- RADIOLOGICAL CONDITIONS REVISION NO. 3 PAGE 6 0F 43 l
4.2.2 Obtain the necessary meteorological and radiological
! information and complete Attachment 1, Form EPP-302-1, -
" Manual Offsite Dose Calculations".
; Note: For specific instructions on how to perform
, offsite dose calculations along with instructions on how to complete Form EPP-302-1, l " Manual Offsite Dose Calculations" refer to
] Attachment 2, " Instructions for Performing Offsite Dose Calculations".
4.2.3 Upon completion of an offsite dose calculatien, compare the whole body and thyroid does estimates with the values specified in Procedure EPP-304, " Protective A.etion Guides." If the whole body or thyroid dose estimates exceed any of the protective action guides, proceed as follows: 4.2.3.1 Prior to activation of the TSC it is the
) responsibility of the Shif t-Technical Advisors to perform these calculations and inform the 3 Emergency Coordinator.
4.2.3.2 Following activation of the TSC, the Onsite Radiological Assessment Coordinator shall be
; responsible for having the calculations performed and for reviewing the results. He shall inform the Emergency Coordinator immediately after reviewing the results.
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4.2.3.3 Following activation of the EOF, the Offsite 9 Radiological Assessment Coordinator is responsible for having these calculations performed. The Offsite Radiological Assessment Coordinator.shall forward the results after he has reviewed tl}em to the Radiation Protection Coordinator who in turn shall inform the - E Emergency Coordinator as quickly as possible. 4.3 Subsequent Actions t 4.3.1 Offsite dose projection calculations should be performed at least once per hour during the first eight hours after the accident unless it is determined that releases of airborne radioactivity from the plant have been terminated. l 4 1
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T CPSES ISSUE DAT PROCEDURE NO. i EMERGENCY PLAN MANUAL M 09 EPP-302 MANUAL ASSESSMENT OF j
; h RADIOLOGICAL CONDITIONS REVISION NO. 3 PAGE 7 0F 43 i
4.3.2 Offsite dose projection calculations should be updated if
]j any of the following conditions occur: - ;t i 4.3.2.1 Release rates increase by more than 25 percent, l 4.3.2.2 Wind direction changes by more than 22.5*, , 4.3.2.3 Atmospheric stability classification changes, 3
1 P 4.3.2.4 Wind speed changes by more than 50 percent; or i 4.3.2.5 Prior to any planned releases. 4.3.3 All personnel performing offsite dose calculations at the TSC should keep the Onsite Radiological Assessment Coordinator informed as to the status of all offsite dose
; projection calculation results. As appropriate, the ; Onsite Radiological Assessment Coordinator shall advise H
the Radiation Protection Coordinator or the-Emergency f Coordinator regarding the status of offsite dose calculations and provide recommendations if dose projections warrant implementation of protective actions. L i 4.3.4 All personnel performing offsite dose calculations at the
! EOF should keep the Offsite Radiological Assessment h Coordinator and the Radiation Protection Coordinator
[ informed as to the status of all offsite dose projection calculation results. The Radiation Protection Coordinator shall advise the Emergency Coordinator regarding the p status of offsite dose calculations and provide [ recommendations if dose projections warrant implementation j , of protective actions.
} 4.3.5 Following the completion of offsite dose calculations the j Emergency Coordinator and radiological assessment personnel shall compare the results with the Plume Exposure Pathway Protective Action Guides found in -
Attachment 3 of EPP-304, " Protective Action Guides". [; Based upon this comparison, current plant status and current weather conditions the Emergency Coordinator shall [ make protective action recommendations to offsite authorities. [ 5.0 References s 5.1 CPSES Emergency Plan, Section 7.0 ) . g 5.2 EPP-300, " Manual calculation of Release Rates" a 4 4
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- p %, MANUAL ASSESSMENT OF
; p_) RADIOLOGICAL CONDITIONS REVISION NO. 3 PAGE 8 0F 43 i
5.3 EPP-301, " Computer Assessment of Radiological Conditions"
! 5.4 EPP-304, " Protective Action Guides" j 5.5 USNRC Regulatory Guide 1.109, " Calculation of Annual Doses to q Man from Routine Releases of Reactor Effluents for the Purpose of a
Evaluating Compliance with 10CFR50, Appendix 1" (Rev. 1, October
) 1977) 5.6 USNRC Regulatory Guide 1.111. " Methods for Estimating Atmospheric j Transport and Dispersion of Gaseous Effluents in Routine Releases j from Light Water Cooled Reactors" (Rev. 1, July 1977) $ 5.7 USNRC Regulatory Guide 1.145, " Atmospheric Dispersion Models for j- Potential Accident Consequence Assessments at Nuclear Power Plants" (August 1979) 5.8 USNRC Regulatory Guide 1.23, " Meteorological Procrams in Support of Nuclear Power Plants" (September 1980)
[ 5.9 USNRC Regulatory Guide 1.4 " Assumptions Used for Evaluating the
? Potential Radiological Consequences of a Loss of Coolant Accident h for Pressprized Water Reactors" (Rev. 2, June 1974) h 5.10 Dames and Moore " Instructions for Using the Emergency Assessment Kit" (March 1977)
I 6.0 Attachments f 2
} 6.1 Attachment 1, Form EPP-302-1, " Manual Offsite Dose Calculations" 3
6.2 Attachment 2. " Instructions for Performing Offsite Dose Calculations" l
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6.3 Attachment 3. " Emergency Planning Zone Information" 6.4 Attachment 4, " Atmospheric Stability Classifications" - I; 6.5 Attachment 5, " Normalized Relative Concentration Values" I 6.6 Attachment 6, " Averaged Gamma Decay Energy for Noble Gas Mixtures" 6.7 Attachment 7, " Iodine Dose Correction Factor" l 6.8 Attachment 8, " Manual Offsite Dose Calculation Methodology" I g GS 4M MM WW T W 2=^"n M " E TTP Q W % ^* - *W~~'~"~"
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1 J CPSES PROCEDURE NO. 4 EMERGENCY PLAN MANUAL ISSUE JAN0c Df385 spp_302 2 MANUAL ASSESSMENT OF
-- RADIOLOGICAL CONDITIONS REVISION NO. 3 PAGE 9 0F 43
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'3 J ATTACHMENT 1 3
PAGE 1 0F 2 d Texas Utilities Generating Cornpany 0 Comanche Peak Steam Electric Station l
) MANUAL OFFSITE DOSE CALCULATIONS j pose 1 se 2 l; .
A. CENE1 tat. INTORMATION q Calculation No.: Date: Time Affected Unit (I or 2): Reactor Shutdown: Date: Times j Radiological Source Term:
. Digital Radiation :*onitorint System 5smple Analyses FSAR Source Term Estimate Release Data obtained: Date: Ti:ne Noble Gas Release Rate: C1/sec lodine-131 Release Rate: C1/see i
Duration of Release: hrs Analyst 51cnature: '
- 8. MtTt0 Rot.0CicAt. CONDITTONS d Wind Direction: (4116): (8), or
, ~(4126): (') , o r (4115): (') -
Wind Speed: (4118): MFN. or b (4128): MFM. or (4117):
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j MFH Delta T: (4120): (on or (4119): (OT) Sigma-Theca: (4130): (*) or (4136): (0) l Net Radiation Index (Attachment 4): Atmospheric Stability Class (Attachment 4): .1
~t Affected Downwind Sectors (Attachaeot 3): . .
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.; CPSES ISSCE DATE PROCEDURE NO. ' EMERGENCY PLAN MANUAL EPP-302 M 091985 1 MANUAL ASSESSMENT OF
! RADIOLOGICAL CONDITIONS REVISION No. 3 PAGE 10 0F 43 i d-1 4 ATTACHMENT 1
] 1 PAGE 2 0F 2 d
- ] Texas Utilities Generating Company l
j Comanche Peak Steam Eectric Station MANUAL OFFSITE DOSE CALCULATIONS pose 2 et 2 g C. EXPostatt St.WY Receptor Whole Body Whole Body Child Thyroid Child Thyroid
.f Distance Dose Dose Rate Dose Dose Race (miles) (Rem) (Rem /hr) (Rem) (Rem /hr) f EAA-2 2
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j CPSES ISSUE DATE j EMERGENCY PLAN MANUAL JM 09 W PROCEDURE NO. EPP-302 5 '
. MANUAL ASSESSMENT OF
;} RADIOLOGICAL CONDITIONS REVISION No. 3 PAGE 11.0F 43 1 ATTACHMENT 2 PAGE 1 0F 15 -
I j Instructions for Performing Offsite Dose Calculations
- I. Instructions for Completing Form EPP-302-1 " Manual Offsite Dose Calculations A. GENERAL INFORMATION Calculation No.: A.1 Date: A.1 Time: A.1 i Affected Unit (1 or 2): A.2 Reactor Shutdown: Date: A.3 Time: A.3 l
l Radiological Source Term: - I j A.4.1 DIGITAL RADIATION MONITORING SYSTEM: A.4.1 1 A.4.2 Sample Analyses [. A.4.3 FSAR Source Term Estimate
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l Release Data Obtained: Date: A.5 Time: A.5 Noble Gas Release Rate: A.6 Ci/sec l . 73 Iodine-131 Release Rate: A.6 Ci/sec
"~' Duration of Release: A.7 hrs Analyst Signature: A.8 ,
A.0 This section of the worksheet addresses the general information requirements. l j A.1 The calculation number is required to identify each separate calculation r so as to avoid confusion when referring to the results. The numbering l format should start with 1 and be preceded by either TSC or EOF to signify where the calculation was performed (e.g., EOF-1 or TSC-1). A.2 Identify the affected unit by entering 1 or 2 into this space for Unit 1 -- l r or Unit 2 respectively. l' A.3 Enter the date and time that the reactor was shut down. This information is required to calculate the effective age of the gas mixture. A.4 Identify the radiological source term used to determine the release rate (if appropriate, refer to Procedure EPP-300, " Manual Calculation of Release Rates"). 1 A.4.1 If the radiological source term was determined by using the
; process radiation monitors, check this space and enter the process k:J/ radiation monitor identifier.
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L ~. . . . . ~ = , _ CPSES' ISSUE DATE PROCEDURE NO. }-t EMERGENCY PLAN MANUAL M 09 M EPP-302 MANUAL ASSESSMENT OF j .p RADIOLOGICAL CONDITIONS REVISION NO. 3 PAGE 12 0F 43 ATTACHMENT 2 l PAGE 2 0F 15 - A.4.2 If the radiological source term was determined by in-plant sample j a analysis, check this space, j A.4.3 If the radiological source terms was determined utilizing FSAR design basis accident criteria, check this space. ] A.5 Enter the date and time that the release data was obtained or calculated. I i A.6 Enter the noble gas and iodine-131 release rates in the appropriate j spaces. These values should have units of Ci/sec. The release rate
; values may be determined from calculations performed in accordance with j EPP-300, " Manual Calculation of Release Rates", may be obtained from 1 Digital Radiation Monitoring System readouts or may be chosen from 1 Attachment 20. " Design Basis Accident Data" found in Procedure EPP-300.
i l CAUTION: If the plant release rates used in making dose j projections are from the Digital Radiction Monitoring j System or Design Basis Accident Information they must be { _ entered into the program memory manually along with the
-]
U release duration. The release rates are measured in l units of Ci/sec and the release duration is measured in j units of hours. .The noble gas release rate is stored by I entering the value in the calculator display and then j pressing STO 01. The Iodine release rate is stored by pressing STO 02.and the release rate is stored by pressing STO 05. These values should be placed into the calculator memory af ter the dose program has been i inputted in the calculator. i l A.7 Enter the actual or estimated release duration, in hours, in this space. J If the actual release duration is not known an estimate of the length of 1 time it will take to terminate the release can be used. This estimate l should be made by Operations personnel that are familiar with the plant
- condition at that particular time. If an estimate cannot be made then a -
release duration of eight (8) hours should be used to make dose
)! proj ections.
l A.8 The analyst who performs the calculation shall sign the form. During an
, Alert condition, the form will normally be reviewed by the Onsite j- Radiological Assessment Coordinator at the TSC. During a Site Area Emergency or General Emergency condition, this form will normally be
)) reviewed by the Offsite Radiological Assessment Coordinator or the Radiation Protection Coordinator at the EOF. e
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- PAGE 3 0F 15 -
I j B. METEOROLOGICAL CONDITIONS Wind Direction: (4116): B.1.1 (*), or
- (4126): B.1.2 (*), or (4115): B.1.3 (*)
Wind Speed: (4118): B.2.1 MPH, or j (4128): B.2.2 MPH, or l (4117): B.2.3 MPH I' Delta T: (4120): B.3.1.1 (*F) or .(4119): B.3.1.2 (*F) Sigma-Theta: (4130): B.3.2.1 (*) or (4136): B.3.2.2 (*) } Net Radiation Index (Attachment 4): B.3.3 h., [ Atmospheric Stability Class (Attachment 4): B.4 Affected Downwind Sectors (Attachment 3): B.S , B.5 , B.5 B.O This section of the worksheet addresses the meteorological data requirements for making dose projections. f , B.1 The wind direction is used to determine which downwind sectors may be j affected by-any radioactive material released from CPSES. The wind I direction is measured in units of degrees from the North. The wind i direction is always reported as blowing from a particular direction. For I example, a wind direction of 90* means the wind is blowing directly from f the East. - I CAUTION: When using any of three indicators identified below to report the wind direction, the average wind direction measured over a fifteen minute time interval as indicated on the strip chart ! recorder and not the instantaneous wind direction as indicated by the recorder pen shall be recorded.
! CAUTION: The wind direction shall be checked at least once per hour to ! verify the wind direction. If a wind direction change of 22.5*
or more has occurred new dose projections shall be made and the l affected downwind sectors reevaluated. f i 4,_;- . . . _ . - - ._ -..m. .- . r - ,yy , _. .3 -.3-..,- - . - . , -- p, . ; rc , ,- --
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-CPSES ISSUE DATE PROCEDURE NO.
l EMERGENCY PLAN MANUAL EPP-302 JAN 091985 F
, MANUAL ASSESSMENT OF RADIOLOGICAL CONDITIONS REVISION No. 3 PAGE 14.0F 43
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i q' t ATTACHMENT 2 l PAGE 4 0F 15 - d B.1.1 The 10 meter primary meteorological system wind direction as h- displayed on recorder X-ZR-4115/16 by indicator 4116 is the primary indicator to be used to determine the wind direction.
- This recorder is located in the Control Room on vertical control board CPX-ECPRCV-05. Enter a fifteen minute average j wind direction into this space, y
J B.1.2 If the 10 meter primary meteorological system wind direction is ? unavailable then the 10 meter backup meteorological system wind direction should be utilized. The backup meteorological system ) wind direction is also displayed on recorder X-ZR-4115/16 by ]b indicator 4126. During normal operations the primary meteorological system data will be displayed. To display the i backup meteorological system data, instrumentation and control personnel must manually switch the inputs to the recorders in y the P2500 computer room. After the switch has been made allow
._ at least fifteen minutes of information to be recorded, if L
possible, so that a good average value can be obtained. Enter j the average value into this space. 1 1- ) B.1.3 If neither of the 10 meter wind direction indicators are i operable then the 60 meter wind direction indicator located on 4 the primary meteorological tower may be used. The 60 meter
. wind direction is also displayed on recorder X-ZR-4115/16 by ] indicator 4115.
If none of the wind direction measuring devices are j) . NOTE: operable then regional meteorological data may be used.
] This information should be obtained from the National J Weather Service Forecast Office.
I j B.2 The wind speed is used to determine how fast a quantity of radioactive material will reach a specific receptor location downwind in the event of f] a release from CPSES. The wind speed is always measured in units of - ) miles per hour (mph). 1- - 1- CAUTION: When using any of the three indicators identified below to
) report the wind speed, the average wind speed measured over a i fifteen minute time interval as indicated on the strip chart +
recorder and not the instantaneous wind direction as indicated by the recorder pen shall be recorded. i, CAUTION: The wind speed shall be checked at least once per hour to i verify the wind speed. If a wind speed change of 50 percent or
~. more has occurred new dose projections shall be made and the appropriate actions instituted.
s
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. ~ d ~ CPSES' ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL 2PP-302 M 091985 MANUAL ASSESSMENT OF }, th RADIOLOGICAL CONDITIONS REVISION NO. 3 PA'GE 15. 0F 43 A ]j ATTACHMENT 2 PAGE 5 0F 14 *
! B.2.1 The 10 meter primary meteorological system wind speed as 1 displayed on recorder X-SR-4117/18 by indicator 4118 is the primary indicator to be used to determine the wind speed.
This recorder is located in the Control Room on vertical control board CPX-ECPRCV-05. Enter a fifteen minute average wind speed into this space. B.2.2 If the 10 meter primary meteorological system. wind speed is unavailable then the 10 meter backup meteorological system vind j speed should be utilized. The backup met system wind speed is W also displayed on recorder X-SR-4117/18 by indicator 4128.
) During normal operations the primary meteorological system data j will be displayed. To df. splay the backup meteorological system j data, I and C personnel must manually switch the inputs to the j recorders in ti'e P2500 computer room. After this switch has y been made . allow at least fif teen minutes of. information to be recorded, if possible, so that a good average value can be ,i obtained. Enter the average value into this space. ] @- B.2.3 If neither of the 10 meter wind speed indicators are operable j then the 60 meter wind ' speed displayed on recorder X-SR-4117/18 l by indicator 4117 can be used to estimate the 10 meter wind j speed. The 60 meter wind speed e.an be converted to a wind 4 speed at 10 meters by reference to the atmospheric stability f class, using the following equation:
1 - V10 " Y60 F where: 9 1 V equa s the velocity at the M meter level, 10 .
! V equals the velocity at the 60 meter level, 60 4
F equals 0.64 for stability classes A, B, C, or D and F equals 0.41. for stability classes E, F, or G. For example, during stability class G conditions, the 10 meter i level wind speed is: V 10 " 60 (0.40 I Af ter the 60 meter wind speed conversion has been made enter
, the result in,to the indicated space for the 60 meter recording.
4 i
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k . A l CPSES ISSUE DATE PROCEDURE NO. ElfERGENCY PLAN MANUAL EPP-302 M 09 E k ., MANUAL ASSESSMENT OF RADIOLOGICAL CONDITIONS REVISION No. 3 PAGE 16 0F 43 i: } ATTACHMENT 2 PAGE 6 0F 15 -1 B.3 The Pasquill atmospheric stability classification will be based upon three alternative methods. The primary method will utilize one of the temperature differential readings recorded by the primary meteorological s tower. There are two separate temperature differential indicators located on the primary meteorological tower which will be used to report the delta T values. The second method which may be used is the standard dev1ation of the variation in the wind direction (sigma-theta value).
, There are two sigma-theta recorders. The primary indicator is located on the primary meteorological tower and the backup indicator is located on L ,
the backup meteorological tower. The final method to use when 1 determining the stability class invloved the determination of the Net ! Radiation Index. The instructions on how to use this method are contained in Attachment 4, " Atmospheric Stability Classification". [ e ( B.3.1 The primary method used to. determine the existing atmospheric
^ '-
. stability class utilizes the temperature difference between 60 meters and 10 meters as measured by instrumentation located on p 3 -
the primary meteorological tower. The delta T values are [ reported in units of degrees Fahrenheit (*F). These values are [ @ used with Table 2. " Atmospheric Stability Classes" to identify ? . the existing stability class. E '. N B.3.1.1 Enter the temperature differential reading displayed h on recorder X-UR-4120/25/30 by indicator 4120 in this L space. This recorder is located in the Control Room i on vertical control board CPX-ECPRCV-05. This sensor l shall be the primary delta T indicator used in atmospheric stability class determinations. ) B.3.1.2 Enter the temperature differential reading displayed on recorder X-UR-4119/23/31 by indicator 4119 in this 1 . space. This recorder is also located on vertical control board CPX-ECPRCV-05. This sensor shall be 4 used as the backup delta T indicator used in - l atmospheric stability class determinations. B.3.2 The secondary method used to determine the existing atmospheric stability class utilizes the standard deviation of the variation in the wind direction. The sigma theta value recorded by primary meteorological tower instrumentation shall i be the indicator of first choice. The sigma theta value recorded by instrumentation located on the backup meteorological tower will be used as the secondary value. The sigma-theta values are reported in units of degrees (*). These i values are used with Table 2 " Atmospheric Stability Classes"
% to identify the existing stability class.
i i i m m. , 7= mm .
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i , M 1 1 CPSES ISSUE DATE PROCEDURE NO. jj EMERGENCY PLAN MANUAL JAN 091985 EPP-302 i 2 MANUAL ASSESSMENT OF I ? D RADIOLOGICAL CONDITIONS REVISION NO. 3 PAGE 17,OF 43 -4 q / ATTACHMENT 2 PAGE 7 0F 15 - ( B.3.2.1 Enter the primary meteorological system sigma-theta value as displayed on recorder X-UR-4120/25/30 by indicator 4130.in this space. This recorder is located in the Control Room on vertical control board CPX-ECPRCV-05. I ) B.3.2.2 Enter the backup meteorological system sigma-theta f; value as displayed on recorder X-UR-4120/25/30 by j indicator 4136 in this space. During normal operations the primary met system data will be
/ / displayed. To display the backup met system data,
.. /, operations or I&C personnel must manually switch the
/
j' inpute to recorders in the P2500 computer room. Af ter the switch has been made allow at least fif teen I minutes of information to be recorded, if possible, so that a good average value can be obtained. Enter the average value into this space. CAUTION: When using the sigma-theta value to h determine the atmospheric stability class, the average sigma-theta value measured over l a fif teen minute time interval as indicated on the strip chart recorder and not the g instantaneous sigma-theta value as f indicated by the recorder pen shall be f recorded. f CAUTION: The sigma-theta value shall be checked at i least,once per hour to verify the stability 1 8 class. If the value has changed such that a new stability class is indicated new dose projections shall be made. 1
- j. B.3.3 If both the primary and backup delta T and -
sigma-theta indicators are unavailable or inoperable then the atmospheric stability class will be i determined using the Net Radiation Index (NRI). Instructions on how to determine the Net Radiation j Index are found in Attachment 4. " Atmospheric ). ,
~
Stability Classifications." After the NRI has been J determined enter the value into this space. B.4 Determine the atmospheric stability from Attachment 4. " Atmospheric h fStabilityClassifications". Instructions on how to determine the proper !! n ^ classification are found in the attachment. ? V. b b e n
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1 N CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL EPP-302 L M 09 E MANUAL ASSESSMENT OF h.m RADIOLOGICAL CONDITIONS REVISION NO. 3 PAGE 18 0F 43 i ATTACHMENT 2 PAGE 8 0F 15 - B.5 Determine the affected downwind sectors by referring to the map in Attachment 3 and the wind direction determined in paragraph B.1 above. B.S.1 For example, if the wind direction is from the North (sector a), the affected downwind sector is J. l l B.5.2 Also include the sectors immediately adjacent to the primary i sector (e.g., sectors H and K, if sector J is the primary a
, downwind sector affected).
i l C. EXPOSURE
SUMMARY
Receptor Whole Body Whole Body Child Thyroid Child Thyroid 1 Distance Dose Dose Rate Dose Dose Rate j (miles) (Rem) (Rem / hour) (Rem) (Rem /hr) 3 EAB- C.1 C.3 C.4 C.5 C.6 ih 2 C.3 C.4 C.5 C.6 j 5 C.3 C.4 C.5 C.6 3 10 C.3 C.4 C.5 C.6
- l d C.2 C.3 C.4 .
C.5 C.6 I c.2 C.3 C.4 C.5 C.6 1 1 l C.0 This section of the worksheet address the summarization of the dose il projections. -
- 1 a
[j C.1 Enter the distance in miles to the EAB in the primary affected ]1 sector. These values can be found in Attachment 3. C.2 Enter the distac.e in miles to any other receptor locations of l- interest. ) C.3 Enter the projected whole body doses, in Rem, into the appropriate spaces. These values are printed on the strip chart printout. g C.4 Enter the projected whole body dose rates, in Rem /hr, into the appropriate spaces. These values are printed out on the strip chart printout.
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!}
CPSES ZSSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL g gg g EPP-302 MANUAL ASSESSMENT OF
't ,,1 h RADIOLOGICAL CONDITIONS REVISION NO. 3 PAGE 19.0F !.3 s ATTACHMENT 2 j PAGE 9 0F 15 -
3, C.5 Enter the projected child thyroid doses, in Rem, into the appropriate spaces. These values are printed out on the strip chart printout. C.6 Enter the projected child thyroid dose rates, in Rem /hr, into the appropriate spaces. These values are printed out on the strip chart
; printout.
D. Attach TI-59 Printout Here D.0 Attach all the strip chart printouts supporting the dose projections entered into Section C of Form EPP-302-1, " Manual Offsite Dose Calculations" in this space. II. Operating Instructions for the TI-59 Calculator / Printer A. After obtaining the calculator / printer from its storage location, plug it into a 120 volt AC power supply. The calculator / printer can not be -
! operated using the calculator battery pack.
7 l ;g B. Turn on both the calculator and the printer. The printer ,on-off J switch is located on the right hand side of the printer. A zero , j should be displayed on the calculator and the red light on the printer i will be lit when the power is turned on. 4 C. Select the magnetic card marked " Dose Calculation" from the black vinyl card file. . D. Enter the program into.the calculator by inserting Side 1 of the card I . into the reader slot found on the top right hand side of the calculator. A good feed is indicated by the number 1 being displayed on the calculator. Press the CLR button and repeat for Side 2. The number 2 will be displayed af ter a good feed. A flashing 1 or 2 indicates a poor feed and that side must be re-entered. To do
- j. so just press CLR and insert that side into the reader slot.
A CAUTION: THE CALCULATOR DISPLAY MUST HAVE A ZERO IN IT IN ORDER FOR N THE MAGNETIC CARDS TO BE READ. E. To initiate the program, press RST and the R/S. The first prompt will appear on the strip chart recorder. a F. Information can now be inputted by entering the appropriate values as y prompted by the program. Enter the value and press R/S for inputting i data. The value will be printed and the next prompt will appear on f g3 the strip chart. Be sure to check all values entered prior to d W pressing R/S. If a wrong value is printed out, press RST and then R/S b to reset the program and then start entering data from the beginning as prompted by the strip chart. I~I l %mvmmpwnmIryv;myw.;.m:mesymmmwwn77=:~
_ ~. .. .
-- y i CPSES ISSUE DATE PROCEDURE NO. l
[ EMERGENCY PLAN MANUAL EPP-302 JAN 091985 I
, 1 I
MANUAL ASSESSMENT OF I i h- RADIOLOGICAL CONDITIONS REVISION NO. 3 PAGE 20 OF 43 l ATTACHMENT 2 PAGE 10 0F 15 - G. In order to perform the analysis provided by this program several , i inputs must be made when prompted by the calculation / printer. These l prompts, statements and inputs are described in the following ' I paragraphs. I i G.1 WIND SPD = MPH? This prompt asks for the wind speed as measured in miles per hour. The wind speed can be obtained from Section B of Form EPP-302-1, " Manual Offsite Dose Calculations". i,- G.2 AGE OF MX = HRS? This prompt asks for the age of the mixture in hours at { the time of release. For example, if a release occurred from a leaking i gas decay tank and the tank had been isolated for 24 hours prior to the l release the age of the mixture would be 24 hours. This value is utilized ' to project the effective age of gaseous mixture at the receptor location. This value is found in Section A of the dose calculation worksheet. G.3 REC DIST = MILES? EAB This prompt asks for the distance from the plant to the Exclusion Area Boundary (EAB) in the primary affected sector. This value is obtained from Attachment 3. " Emergency Planning Zone Q , Informarion". All distances are reported in miles. G.4 XUQ = M+-27 This prompt asks for the normalized relative concentration values to be inputted for the various downwind receptor locations. These values are obtained from Attachment 5, " Normalized Relative Concentration Values". These values are dependent upon the atmospheric stability class ,. present, the downwind distance of the receptor location and the distance i off the plume centerline. For most calculations the values found in i Table 5, " Exclusion Area Boundary Normalized Relative Concentration Values" should be utilized. All normalized relative concentration values are reported in meters z, G.4.1 EAB Enter the normalized relative concentration value for the distance identified in paragraph G3 above as the distance to the exclusion area boundary into the program at this time. - G.4.2 2 MILES Enter the normalized relative concentration value for 2 miles into the program at this time. G.4.3 5 MILES Enter the normalized relative concentration value for 5 miles into the program at this time. G.4.4 10 MILES Enter the normalized relative concentration value for 10 miles into the program at this time.
'h i
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y _ s-CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL JAllgg g EPP-302 MANUAL ASSESSMENT OF e
- h. RADIOLOGICAL CONDITIONS REVISION NO. 3 PAGE 21.0F 43
!, = ATTACHMENT 2 l PAGE 11 0F 15 C.5 EFF AGE = (HRS) This statement provides dose assessment personnel with the age of the mixture at the receptor location. It consists of the plume transit time in hours and age of mixture at the time of release in hours. This value is used with Attachments 6 and 7 to determine the j; average gamma decay energy for noble gas mixtures and the iodine dose correction factor respectively.
I G.5.1 EAB This statement provides the age of the mixture at the exclusion area boundary. i G.5.2 2 MILES This statement provides the age of the mixture at.2 miles down wind of the release point. B - G.5.3 5 MILES This statement provides the age of the mixture at 5 miles down wind of the release point. G.5.4 10 MILES This statement provides the age of the mixture at'10 miles'down wind of the release point. h G.6 READ CARD 2 Enter the program contained on card number two into the program memory as instructed in Paragraph II.D. of this attachment.
,t CAUTION: Do not erase the information which is contained in the program , memory.
I [ G.7 AVG NG E = MEV/ DIS? This prompt asks for the average gamma decay energy for the noble gas mixtures. These values are read from Attachment 6,
, " Average Gannia Decay Energy for Noble Gas Mixtures". This value is l- dependent upon the effective age of the noble gas mixture, therefore the j value will be different for each downwind receptor location.
G.7.1 EAB Enter the average gamma decay energy for the noble gas mixture at the exclusion area boundary. ) ; G.7.2 2 MILES Enter the average gamma decay energy for the noble gas mixture at 2 miles downwind from the release point. G.7.3 5 MILES Enter the average gamma decay energy for the noble gas mixture at 5 miles downwind from the release point. P G.7.4 10 MILES Enter the-average gamma decay energy for the noble gas mixture at 10 miles downwind from the release point. G.8 IODINE CRT FCT? This prompt asks for the iodine dose correction factor {} for the gas mixture. These values are read from Attachment 7. " Iodine Dose Correction Factors." These values are also dependent on the l effective age of the mixture, therefore the value will be different for each downwind receptor location, l i-F7 M'"T UG F M ET7'T m W "?~~ C Z. Z Z Z ' TlT~J T1..1,_. ~ ~ _ _ J T
.aa...
_a ._ . 1 l CPSES ISSUE DATE PROCEDURE NO.
;. EMERGENCY PLAN MANUAL Jgg g ggg EPP-302 i *
~ MANUAL ASSESSMENT OF d' h) RADIOLOGICAL CONDITIONS REVISION No. 3 PAGE 22.0F 43 ATTACHMENT 2 PAGE 12 0F 15 -
G.8.1 EAB Enter the iodine dose correction factor for the gas ( mixture at the exclusion area boundary. G.8.2 2 MILES Enter the iodine dose correction factor for the gas mixture at 2 miles downwind from the release point. G.8.3 5 MILES Enter the iodine dose correction factor for the gas ( mixture at 5 miles downwind from the release point. G.8.4 10 MILES Enter the iodine dose correction factor for the gas mixture at 10 miles downwind from the release point. 2 F G.9 READ CARD 3 Enter the program contained on card number three into the f program memory as instructed in Paragraph II.D of this attachment. b CAUTION: Do not erase the information which is contained in the program [ + memory. b G.10 WB DR = (REM /HR) This statement indicates that the whole body dose rate r h projections as measured in Rem /hr will be printed out in the following sections. t l G.10.1 EAB This statement provides the projected whole body dose rate [ at the exclusion area boundary. i ( G.10.2 2 MILES This statement provides the projected whole body dose p rate 2 miles downwind from the release point. I G.10.3 5 MILES This statement provides the projected whole body dose rate 5 miles downwind from the release point. f f G.10.4 10 MILES This statement provides the projected whole body dose [ rate 10 miles downwind from the release point.
~
i 1 G.11 WB DOSE = (REM) This statement indicates that the whole body dose projections as measured in Rem will be printed out in the following sections. 1
- G.11.1 EAB This statement provides the projected whole body dose at i the exclusion area boundary.
] j G.11.2 2 MILES This statement provides the projected whole body dose 2 miles downwind from the release point. g G.11.3 5 MILES This statement provides the projected whole body dose 5 miles downwind from the release point. l G.11.4 10 MILES This statement provides the projected whole body dose 10 miles downwind from the release point. l i wwn . .. .
E N CPSES ISSUE DATE PROCEDURE NO. j EMERGENCY PLAN MANUAL JAN 091985 EPP-302 , i l i e MANUAL ASSESSMENT OF !
;# RADIOLOGICAL CONDITIONS REVISION NO. 3 PAGE 23.0F 43 j-7 ATTACHMENT 2 PAGE 13 0F 15 -
l G.12 CH TH DR = (REM /HR) This statement indicates that the child thyroid dose J A rates as measured in Rem /hr will be printed out in the following f sections. G.12.1 EAB This statement provides the projected child thyroid dose rate at the exclusion area boundary. G.12.2 2 MILES This statement provides the projected child thyroid dose rate 2 miles downwind from the release point. ( G.12.3 5 MILES This statement provides the projected child thyroid i dose rate 5 miles downwind from the release point. G.12.4 10 MILES This statement provides the projected child thyroid [i dose rate 10 miles downwind from the release point. 0 . a G.13 CH TH DOSE = (REM) This statement indicates that -the child thyroid doses I as measured in Rem will be printed out in the following sections. h G.13.1 EAB This statemant provides the projected child thyroid dose at the exclusion area boundary. G.13.2 2 NELES This statement provides the projected child thyroid dose 2 miles downwind from the release point. [ G.13.3 5 MILES This statement provides the projected child thyroid [ dose 5 miles downwind from the release point. )T G.13.4 10 MILES This statement provides the projected child thyroid i dose 10 miles downwind from the release point. ) H. Normally dose calculations are performed af ter determining the noble gas and ? iodine release rates. When these calculations are performed in this manner q the release rates and the release duration remain in the memory of the calculator when the dose program is initiated. If dose calculations are being j - performed without doing release rate calculations , i.e., DBA release data j input, then these values must be entered into the calculator af ter the dose program has been initiated. The noble gas release rate in Ci/see is entered by entering the value on the display and pressing STO 01, the iodine release rate 2 in Ci/see by pressing STO 02 and the release duration in hours by pressing STO
- 05. The release rate and release duration values can be found in Section A of
- the dose calculation worksheet.
I. When all dose calculations have been made for a particulare receptor g e h location (s) the strip chart should be attached to the space provided in the dose calculation worksheet. L J ' ! .i
, , . , .., ..-y- . . ..
l
; CPSES' ISSUE DATE PROCEDURE NO.
EMERGENCY PLAN MANUAL EPP-302 [ _ LAM AG 1GRC MANUAL ASSESSMENT OF -l
) RADIOLOGICAL CONDITIONS REVISION NO. 3 PAGE 24.0F 43 ATTACHMENT 2
- PAGE 14 0F 15 -
$ J. When performing calculations using the TI-59 programs be sure that the calculator / printer remains on at all times, if power should be cut off the
. programs must be reinitiated and the data re-entered.
K. Figure 1, " Dose Calculation Strip Chart Printout", below contains an example of the strip chart produced as a result of using this dose calculation 3 program. t I - 1 n s l s
~
4 I i 4 n% h i a v s ** -- - + --;w . - , . . . ,. . . , ,
* -' W *' ' *-- e- - , - Q 4 g .._y g , y _ _ , , _ , , _ _ y
__ ..._.. _~ _ . _ . ... 'i CPSES ISSUE DATE j EMERGENCY PLAN MANUAL PROCEDURE NO. EPP-302
.lA N A G 1Qft$
MANUAL ASSESSMENT OF I_...
,) RADIOLOGICAL CONDITIONS REVISION NO. 3 PAGE 25.0F 43 ATTACHMENT 2 4 PAGE 15 0F 15 -
DOSE CALCULATION STRIP CHART PRINTOUT l
- (
l FIGURE 1
.' '4TF1IEE5': - "I "35YN*'.:- y~= t. - D,SPDMS[.[,(
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w.;TG M I LES' '::, AGE'DF itlX= HRS?- - , *.-: w-i 1 i 1. 1. j ' REC DIST= MILES? READ CARD 3 ERE: kiB DR= (REM /PR)
' EAB i 1. .
4 XU/0= Mt-2? 0.
] ERS: , 2 MILES:
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. . O.
; 2 MILES - 5 MILES:
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5 MILES: 10 MILES: C. k]
- 1. .
10 MILES . WB DCSE= (Rein
. 1. E9E EFF AGE = (HRS) O.
5 EAS:
- 2 MILES:
3.237136465 0.
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i [ J ~ 2 !!ILESt t . 5 MILES: 5.474272931 C. 5 MILES: 10 MILES:
,
- 12.18568233 .
. O.
. :.,.,10 MILES; CH TH DR= (REM /HR) 23*37136465 7 -/ .-
. . . ERB;
! .kERD CARD2 '
- 0. , 3'.
l AVG.NG'E= MEV/ DIS? ; ~
. . 2 MILES:
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- g. ERS: g,b ,4 0.,r.&T', -. 1 )* i. 5 MILES:~ ; ;.. ' - 2' MILES:- .; 0. -
- 1. 10 MILES:
I 5 MILES: O. l 1. ' CH TH 30$E= ' (REM) i 10 MILES: ERS: i 1. O. IDDINE CRT FCT? 2 MILES: ERS: 0.- :
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q - CPSES ISSUE DATE PROCEDURE NO. i EMERGENCY PLAN MANUAL JM 09 E EPP-302 MANUAL ASSESSMENT OF
.;,1 RADIOLOGICAL CONDITIONS REVISION NO. 3 PAGE 26 0F 43 i
ATTACHMENT 3 l PAGE 1 0F 1 - EMERGENCY PLANNING ZONE INFORMATION , EPZ SECTOR DATA TABLE 1 .i
; Distance To Areas Covered By Sector EAB Sector (Miles) (Degrees) i E A 1.33 348.76 - 11.25 B 1.61 11.26 - 33.75 j C 1.66 33.76 - 56.25
) D 1.61 56.26 - 78.75 E 1.60 78.76 - 101.25 F 1.37 101.26 _123.75 G 1.39 123.76 - 146.25 H 1.37 146.26 - 168.75 J 1.27 168.76 - 191.25 h-. K 1.07 191.26 - 213.75
- .96 213.76 - 236.25 L
M .96 236.26 - 258.75 N 1.19 258.76 - 281.25
- P 1.48 281.26 - 303.75 Q 1.31 303.76 - 326.25
, R 1.29 - 326.26 - 348.75 EPZ Sector Designation Figure 2 j i R A N E l Q *w ** me l C ' ! Nw g i P D / > N wm l l
,,,, g )
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! CPSES ISSUE DATE PROCEDURE NO.
l EMERGENCY PLAN MANUAL JAN 091985 EPP-302 i ( MANUAL ASSESSMENT OF j hg RADIOLOGICAL CONDITIONS REVISION NO. 3 PAGE 27.0F 43 a b-
- ATTACHMENT 4 l PAGE 1 0F 5 -
I' j ATMOSPHERIC STABILITY CLASSIFICATIONS i ' 1.0 The primary method for determining the atmospheric stability class (Pasquill category) utilizes the temperature difference between the 60 i meter and 10 meter elevations. The delta T values are automatically j available from instrumentation associated with the primary
- meteorological tower. If these indicators are unavailable the delta T
{ value can be easily computed by simply subtracting the 10 meter j temperature from the 60 meter temperature. Once the delta T value has been determined simply locate the value in the appropriate column in
- Table 2 below to determine the Pasquill class.
? l ATMOSPHERIC STABILITY CLASSIFICATIONS j (Table 2) Stability Pasquill T(60m - 10m) Sigma-Theta
, Classification Class (*F) (*)
d Extremely unstable A *1.71
> 22.5 Moderately unstable B -1.71 to -1.53 17.5 to 22.5 Slightly unstable C -1.52 to -1.35 12.5 to 17.5 Neutral D -1.34 to -0.45 7.5 to 12.5 Slightly stable E -0.44 to 1.35 3.8 to 7.5 Moderately stable F 1.36 to 3.60 2.1 to 3.8 Extremely stable G 3.60 < 2.1 2.0 If both the primary and secondary delta-T sensors are inoperative, the Pasquill stability class may be defined using the variation in the l wind direction. This value is called sigma-theta and it represents i the standard deviation of the horizontal wind direction fluctuation. ~
l table 2 above lists the sigma-theta values for each Pasquill stability ! class. Once the sigma-theta value has been determined, simply locate the value in the appropriate column in Table 2 above to determine the Pasquill class. I I L
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, 1 j CPSES ISSUE DATE PROCEDURE NO. l EMERGENCY PLAN MANUAL JAN 091RRg EPP-302 MANUAL ASSESSMENT OF
, I)
, RADIOLOGICAL CONDITIONS REVISION NO. 3 PAGE 28 0F 43 ATTACHMENT 4 PAGE 2 0F 5 -
I j 3.0 If both the primary and secondary delta-T (and sigma-theta) sensors
; are inoperative, the Pasquill-Turner method for defining Pasquill j stability classes may be used. This nethod is based on the principle j that stability near the ground is dependent primarily upon net s radiation and wind speed. Determination of stability class as a function of wind speed and net radiation is given in Attachment 4,
)l 1 Table 4. In this system, insolation is estimated by solar attitude and modified for existing conditions of total cloud cover and cloud I ceiling height. At night, estimates of outgoing radiation are made by considering cloud cover. The net radiation index is determined by j using either the flow chart (Attachment 4, Figure 3) or the 'following
; description in conjunction with Attachment 4, Table 3 " Insolation as
- a Function of Solar Attitude".
l 3.1 This determination is accomplished in the following manner: ] 3.1.1 Determine the class number from Table 3 below by i estimating the solar attitude. The solar attitude is a { (,;) measure of the position of the sun in the sky and is measured in units of degrees. 4 INSOLATION AS A FUNCTION OF SOL AR ATTITUDE .; (Table 3) i i Solar Attitude (a) Insolation Class Number 4 60* < (a) Strong .4 4 35' < (a) < 60* Moderate 3 15' < (a) < 35' Slight 2 (a) < 15' Weak 1 Example: At noon the sun is located directly overhead. The solar attitude would be 90*. This position is determined to be class number 4. 3.1.2 The class number is now modified by the cloud cover and ceiling height to determine the Net Radiation Index using either the descriptive instructions or the branching diagram (Figure 3) 1 from which they were derived shown below. s i
.-~s -- y . . - - . , . , . . . - . . - .- ..,',..n r,,.~..,-,- ---r---. - -
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I E CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL _ggg gg g g EPP-302 MANUAL ASSESSMENT OF i ft.h RADIOLOGICAL CONDITIONS REVISION No. 3 PAGE 29.0F 43 i ATTACHMENT 4 l-PAGE 3 0F 5 - l 1 l 1 3.1.2.1 For daytime conditions where: h F Cloud cover is equal to 10/10 and l ceiling height is less than 7000 feet, use -1 for net radiation index; t h' Cloud cover is equal to 10/10 and ceiling height is equal to or greater than 7000 feet, subtract 1 from class number but do not use less than 1 for i net radiation index; L ! Cloud cover is less than 10/10 but greater than 5/10 and ceiling height is less than 7000 feet, subtract 2'
~ from class number but do not use less than 1 for net radiation index;
[j Cloud c#over is less than 10/10 but greater than 5/10 and ceiling height
; is equal to or greater than 7000 feet i
but less than 16,000 feet, substract 1 from class number but doe not use less than 1 for net radiation index; Cloud cover is less than 10/10 but greater than 5/10 and ceiling height is ( equal to .or greater than 16,000 feet, V, use class number given;
)I '
Cloud cover is less than or equal to 5/10 and ceiling height is any value, i use class number given. ~ i 3.1.2.2 For night-time conditions where: l Cloud cover is greater than 4/10 and ceiling height is any value, use -1 j for net radiation index;
};
Cloud cover is less than or equal to 4/10 and ceiling height is any value,
;. use -2 for net radiation index.
L0 l
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y- -- - - - f ') l CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL M 09 m .EPP-302
,. .. MANUAL ASSESSMENT OF ] (] RADIOLOGICAL CONDITIONS REVISION NO. 3 PAGE 30.0F 43 ATTACHMENT 4 PAGE 4 OF 5 - ?
NOTE: For additional details, refer k to the Dames and Meore " Dose 1 ' Assessment Kit Instructions". Assistance in the use of the y Pasquill-Turner method can be j provided by the National Weather Service, Focal Point l Air Pollution Meteorologist in .l Fort Worth, Texas. j 3 j . NET RADIATION INDEX AS A FUNCTION OF CLOUD COVER 3- AND CEILING HEIGHT j (Figure 3) 1 4 Yee 3. Canditions
~ & ,.. ...
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.g 3 CPSES ISSUE DATE PROCEDURE NO.
EMERGENCY PLAN MANUAL JM09 m EPP-302 _ MANUAL ASSESSMENT OF Q) RADIOLOGICAL CONDITIONS REVISION No. 3 PAGE 31.0F 43 ATTACHMENT 4 )
, PAGE 5 0F 5 - '
I f 3.1.3 Af ter the net radiation index has been determined it is g used, along with the vind speed in meters per second, in Table 4 below to determine the stability class. The f.i stability class is determined by locating which range the
} wind speed falls into the left hand column and proceeding i across to the appropriate net radiation index column.
3 Af ter the stability class has been determined it is used i to determine the normalized relative concentration values { at the various receptor locations in Attachment 5. C Y \ STABILITY CLASS AS A FUNCTION OF NET RADIATION AND WIND SPEED (Table 4) i I Wind Speed (mph) Net Radiation Index h 4 3 2 1 , 0 -1 -2 4 0- 1.6 A A B C D F G
} 1.7 - 3.9 A B B C D F G
; 4.0 - 6.2 A B C D D E F t 6.3 - 7.4 B B C D D E F l 7.5 - 8.5 . B B C D D D E
; 8.6 - 10.8 B C C D D D E l 10.9 - 12.0 C C D D D D E
~
12.1 - 13.1 C C D D D D D i 13.2 C D D D D' D D i i i i - 1 4 s I i i 4 % r y J s 4 k . 4 4.+e_-*$ 7* +:e> > e e- - , m -
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CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL g gg i g EPP-302 3 ,.c. MANUAL ASSESSMENT OF j d RADIOLOGICAL CONDITIONS REVISION NO. 3 PAGE 32.0F 43
) ATTACHMENT 5 PAGE 1 0F 9 -
NORMALIZED RELATIVE CONCENTRATION VALUES 4 1 1.0 This attachment contains the normalized relative concentration values
] (Xu/Q) used to estimate plume dispersion as the plume travels downwind j af ter being released. These values were generated using the RM-21 , Report Processor and a 1 meter /see wind speed. This attachment contains eight (8) tables listing the normalized relative concentration values under various conditions and for various downwind I and crosswind distances. To determine the appropriate value the Pasquill atmospheric stability class must first be determined in l~ accordance with the instructions found in Attachment 4, " Atmospheric ; Stability Classification."
f 2.0 Tables 5 through 12.contain the Xu/Q values which shall be used for j performing dose projections. All distances are.reportad in units of j miles and all Xu/Q values are reported in units of met cs8 t 2.1 Table 5 contains a list of each exclusion area boundary distance
~}
' and the corresponding Xu/Q value for each stability class. This table also contains the Xu/Q values for 2, 5 and 10 miles
{ downwind. These values are the centerline values for estimating l plume dispersion and should be used in most dose projections. l [ 2.2 Tables 6-12 contain Xu/Q values which should be used to perform
, dose projections at downwind and crosswind distances not normally chosen. After finding the appropriate table locate the intersection of the crosswind and downwind distances of interest.
j The value found at the intersection is the normalized relative concentration (Xu/Q) value which should be entered into the l program. When a crossvind distance is not specified the plume centerline (zero miles crosswind distance) should be used for projecting offsite doses. L l 1 C i
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4 CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL JAN 09 MS EPP-302 1 - d a MANUAL ASSESSMENT OF
.f h,1 RADIOLOGICAL CONDITIONS REVISION NO. 3 PAGE 33 0F 43 ?
I i ATTACHMENT 5 j PAGE 2 0F 9 - Exclusion Area Boundary Normalized Relative Concentration Values
; (Table 5) l Xu/Q Values (M 2) ] Sector EAB Atmospheric Stability Class j Distance (miles) A B C D E F G , A 1.33 7.12E-07 1.90E-06 9.68E-06 3.22E-05 6.18E-05 1.32E-04 2.32E-04
{ . B 1.61 6.13E-07 1.15E-06 7.06E-06 2.47E-05 4.83E-05 1.09E-04 1.93E-04 C 1.66 5.99E-07 1.07E-06 6.71E-06 2.37E-05 4.65E-05 1.06E-04 1.88E-04 j D 1.61 6.13E-07 1.15E-06 7.06E-06 2.47E-05 4.83E-05 1.09E-04 1.93E-04 ^ E 1.60 6.16E-07 1.17E-06 7.14E-06 2.50E-05 4.87E-05 1.10E-04 1.95E-04 0 F 1.37 6.96E-07 1.76E-06 9.22E-06 3.10E-05 5.95E-05 1.28E-04 2.25E-04 1 G 1.39 6.88E-07 1.69E-06 9.01E-06 3.03E-5 5.84E-05 1.26E-04 2.22E-04 H 1.37 6.96E-07 1.76E-06 9.22E-06 3.10E-05 5.95E-05 1.28E-04 2.2SE-04 J 1.27 7.73E-07 2.17E-06 1.04E-05 3.43E-05 6.55E-05 1.39E-04 2.41E-04 i K 1.07 8.65E-07 3.50E-06 1.37E-05 4.27E-05 8.04E-05 1.66E-04 2.79E-04 L 0.96 1.04E-06 4.33E-06 1.64E-05 4.96E-05 9.10E-05 1.84E-04 3.02E-04 M 0.96 1.04E-06 4.33E-06 1.64E-05 4.96E-05 9.10E-05 1.84E-04 3.02E-04 N 1.19 7.74E-07 2.62E-06 1.16E-05 3.73E-05 7.09E-05 1.49E-04 2.55E-04 4 g P 1.48 6.55E-07 1.43E-06 8.13E-06 2.78E-05 5.39E-05 1.19E-04 1.18E-04 t. I Q 1.31 7.20E-07 1.99E-06 9.92E-06 3.29E-05 6.30E-05 1.34E-04 2.35E-04 R 1.29 7.29E-07 2.07E-06 1.02E-05 3.36E-05 6.42E-05 1.36E-04 2.38E-04 2 5.18E-07 8.27E-07 5.03E-05 1.85E- M 3.65E-05 8.77E-05 1.55E-04 5 2.43E-7 3.19E-07 1.15E-06 5.03E-06 1.11E-05 2.97E-05 6.30E-05 10 1.41E-7 1.83E-07 4.00E-07 2.04E-06 5.23E-06 1.43E-05 3.27E-05 i U
; ,y77-nmpwq7p.my yqp.mnmpmmn. ry,m w:m :m 3- , . ~ .-
CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL EPP-302 JAN 09125 MANUAL ASSESSMENT OF ih RADIOLOGICAL CONDITIONS REVISION NO. 3 PAGE 34 0F 43 1 j ATTACHMENT 5 l! PAGE 3 0F 9 - 4 3 PASQUILL CLASS A
$ (Table 6) 1 , !j Xu/Q Values (M ')
1
'j DOWNWIND OROSSWIND DISTANCE (MILES)
DISTANCE (MILES) E 0.13 0.19 0.25 0.31 l 0.13 3.84E-05 3.14E-06 1.37E-07 1.71E-09 6.llE-12 0.25 1.17E-05 3.59E-06 8.17E-07 1.03E-07 7.19E-09 (L 0.38 5.07E-06 2.51E-06 1.04E-06 3.02E-07 6.18E-08 0.50 2.89E-06 1.81E-06 1.01E-06 4.45E-07 1.55E-07 1 0.63 2.08E-06 1.49E-06 9.77E-07 5.42E-07 2.54E-07 3 0.75 1.57E-06 1.22E-06 8.89E-07 5.71E-07 3. 22E-07 l 0.88 1.23E-06 1.01E-06 7.88E-07 5.57E-07 3.57E-07 1.00 9.89E-07 8.43E-07 6.91E-07 5.24E-07 3. 66 E-07 1.13 8.16E-07 7.16E-07 6.08E-07 4.84E-07 3.61E 1.25 7.54E-07 6.74E-07 5.87E-07 4.83E-07 3. 76 E-07 1.56 6.34E-07 5.86E-07 5.31E-07 4.63E-07 3.87E-07 L 1.88 5.49E-07 5.18E-07 4.81E-07 4.33E-07 3. 79E-07 2.19 4.86E-07 4.64E-07 4.38E-07 4.04E-07 3.64E-07 2.50 4.37E-07 4.21E-07 4.01E-07 3.76E-07 3. 46E-07 2.81 3.96E-07 3.84E-07 3.69E-07 3.50E-07 3.27E-07 l 3.13 3.62E-07 3.53E-07 3.42E-07 3.27E-07 3.08E-07 3.44 3.34E-07 3.27E-07 3.18E-07 3.06E-07 2.91E-07 3.75 3.10E-07 3.05E-07 . 2.97E-07 2.88E-07 2. 76E-07 4.06 2.91E-07 2.86E-07 2.80E-07 2.72E-07 2. 62E-07 4.38 2.74E-07 2.70E-07 2.65E-07 2.58E-07 2.50E-07 i 4.69 2.59E-07 2.55E-07 2.51E-07 2.45E-07 2.38E-07 4.97 2.45E-07 2.42E-07 2.39E-07 2.34E-07 2.28E-07 h 5.31 2.33E-07 2.30E-07 2.27E-07 2.23E-07 2.18E-07 [ 5.63 2.22E-07 2.19E-07 2.17E-07 2.13E-07 2.09E-07 5.94 2.llE-07 2.10E-07 - 2.07E-07 2.04E-07 2.00E-07 , 6.25 2.03E-07 2.01E-07 1.99E-07 1.96E-07 1.93E-07 -- l 6.88 1.89E-07 1.88E-07 1.86E-07 1.84E-07 1.81E-07 7.50 1.78E-07 1.76E-07 1.75E-07 1.73E-07 1.71E-07 i n 8.13 1.67E-07 1.66E-07 1.65E-07 1.63E-07 1.61E-07 ? 8.75 1.58E-07 1.57E-07 1.56E-07 1.55E-07 1.53E-07 9.38 1.49E-07 1.49E-07 1.48E-07 1.47E-07 1.45E-07 9.94 1.42E-07 1.41E-07 1.41E-07 1.40E-07 1.39E-07 1 O 4 l l - i 1 .
= --
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7"^Q. t CPSES. ISSUE DATE PROCEDURE NO. o EMERGENCY PLAN MANUAL JAN 091985 EPP-302 1 l ,m MANUAL ASSESSMENT OF [3) PADI0 LOGICAL CONDITIONS REVISION NO. 3 PACE 35 ,0F 43 ATTACHMENT 5
- 1. PAGE 4 0F 9 -
1 PASQUILL CLASS B 3 (Table 7)
~
Xu/Q Values (M ) DOWNWIND CROSSWIND DISTANCE (MILES) J DISTANCE (MILES) E 0.13 0.19 0.25 0.31 1 d 0.13 1.08E-04 1.07E-06 3.33E-09 1.03E-12 3.15E-17 0.25 4.77E-05 5.33E-06 3.44E-07 7.44E-09 5.37E-11 0.38 2.64E-05 7.17E-06 1.41E-06 1.44E-07 7.70E-09 , 0.50 1.66E-05 7.02E-06 2.39E-06 5.28E-07 7.58E-08 l 0.63 1.05E-05 5.65E-06 2.60E-06 8.77E-07 2.17E-07 0.75 7.27E-06 4.55E-06 2.54E-06 1.12E-06 3.90E-07 l 0.88 5.34E-06 3.71E-06 2.35E-06 1.24E-06 5.43E-07 4 1.00 4.09E-06 3.05E-06 2.11E-06 1.27E-06 6.54E-07 j 1.13 3.22E-06 2.53E-06 1.87E-06 1.23E-06 7.14E-07 1.25 2.33E-06 1.90E-06 1. 48 E-06 1.03E-06 6.55E-07 1.56 1.27E-06' 1.10E-06 9.25E-07 7.24E-07 5.28E-07 ( h 1.88 2.19 8.93E-07 7.59E-07 8.05E-07 7.00E-07 7.07E-07 6.32E-07 5.90S 07 5.49E-07 4.67E-07 4.57E-07 2.50 6.54E-07 6.13E-07 5.65E-07 5.04E-07 4.36E-07 2.81 5.71E-07 5.41E-07 .5.06E-07 4.61E-07 4.09E-07 3.13 5.04E-07 4.82E-07 4.56E-07 4.21E-07 3.81E-07 3.44 4.48E-07 4.31E-07 4.12E-07 3.85E-07 3.54E-07 y[ 3.75 4.08E-07 3.95E-07 - 3.79E-07 3.58E-07 3.33E-07 4 4.06 3.83E-07 3.72E-07 3.59E-07 3.41E-07 3.20E-07 l 4.38 3.60E-07 3.51E-07 3.40E-07 3.25E-07 3.07E-07 i 4.69 3.40E-07 3.32E-07 3.23E-07 3.10E-07 2.95E-07
; 4.97 3.22E-07 3.15E-07 3.07E-07 2.97E-07 2.83E-07 , 5.31 3.06E-07 3.002-07 2.93E-07 2.84E-07 2.73E-07 5.63 2.91E-07 2.86E-07 -2.80E-07 2.72E-07 2.62E-07 1 5.94 2.78E-07 2.74E-07 2.68E-07 2.61E-07 2.53E-07 7 6.25 2.66E-07 2.63E-07 2.58E-07 2.52E-07 2.44E-07 -
6.88 2.48E-07 2.45E-07 2.41E-07 2.36E-07 2.30E-07 l 7.50 2.32E-07 2.30E-07 2.27E-07 2.23E-07 2.17E-07 i 8.13 2.18E-07 2.16E-07 2.14E-07 2.10E-07 2.06E-07 [ 8.75 2.06E-07 2.04E-07 2.02E-07 1.99E-07 1.95E-07 h 9.38 1.95E-07 1.93E-07 1.91E-07 1.89E-07 1.86E-07 9.94 1.85E-07 1.83E-07 1.82E-07 1.80E-07 1.77E-07 i fh L . s . s T- } % ] _' be, l , , *.e - 5"
u
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CPSES ISSUE DATE PROCEDURE NO. ] EMERGENCY PLAN MANUAL JAN 091985 EPP-302 3 j e MANUAL ASSESSMENT OF
%1 RADIOLOGICAL CONDITIONS REVISION NO. 3 PAGE 36.0F 43 ATTACHMENT 5 PAGE 5 0F 9 -
PASQUILL CLASS C (Table 8) 4 . u Xu/Q Values (M- )
~ . DOWNWIND CROSSWIND DISTANCE (MILES) l DISTANCE (MILES) E 0.13 0.19 0.25 0.31 L
j 0.13 2.35E-04 4.04E-08 7.95E-13 2.05E-19 9.99E-22 L 0.25 1.14E-04 1.74E-06 9.33E-09 6.19E-12 5.07E-16 j 0.38 6.78E-05 5.60E-06 2.48E-07 3.16E-09 1.16E-11 0.50 4.50E-05 8.60E-06 1.08E-06 5.98E-08 1. 44 E-09
- 0.63 3.27E-05 9.84E-06 2.20E-06 2.69E-07 1.81E-08 L 0.75 2.48E-05 9.98E-06 3.20E-06 6.52E-07 8.42E-08 0 0.88 1.94E-05 9.52E-06 3.91E-06 1.12E-06 2.26E-07 1.00 1.56E-05 8.81E-06 4.30E-06 1.58E-06 4.33E-07
{ 1.13 1.29E-05 8.03E 4.45E-06 1.95E-06 6.75E-07 i 1.25 1.09E-05 7.33E-06 4.47E-06 2.24E-06 9.19E-07 1.56 7.54E-06 5.76E-06 4.llE-06 2.57E-06 1.40E-06 (h 1.88 2.19 5.62E-06 4.43E-06 4.61E-06 3.79E-06 3.59E-06 3.12E-06 2.54E-06 2.38E-06 1.62E-06 1.68E-06 I 2.50 3.58E-06 3.16E-06 2.71E-06 2.18E-06 1.65E-06 I 2.81 2.96E-06 2.67E-06 2.35E-06 1.96E-06 1.56E-06 ! 3.13 2.48E-06 2.28E-06 2. 05 E-06 1.76E-06 1.46E-06 3.44 2.11E-06 1.97E-06 1.80E-06 1.58E-06 1.34E-06 3.75 1.83E-06 1.72E-06 . 1.59E-06 1.43E-06 1. 24 E-06 4.06 1.62E-06 1.53E-06 1.43E-06 1.30E-06 1.15E-06 , 4.38 1.44E-06 1.37E-06 1.29E-06 1.19E-06 1.06E-06 , 4.69 1.29E-06 1.24E-06 1.17E-06 1.09E-06 9.85E-07 4.97 1.17E-06 1.12E-06 1.07E-06 9.97E-07 9.13E-07 l 5.31 1.06E-06 1.02E-06 9.75E-07 9.17E-07 8.47E-07 5.63 9.61E-07 9.30E-07 8.94E-07 8.45E-07 7.87E-07 5.94 8.78E-07 8.53E-07 8.22E-07 7.81E-07 7.32E-07
. 6.25 8.11E-07 7.89E-07 7.63E-07 7.28E-07 6. 86 E-07 --
6.88 7.09E-07 6.93E-07 6.73E-07 6.47E-07 6.14E-07 7.50 6.26E-07 6.13E-07 5.98E-07 5.78E-07 5.52E-07 8.13 5.50E-07 5.46E-07 5.35E-07 5.18E-07 4.98E-07 l 8.75 4.98E-07 4.90E-07 4.81E-07 4.68E-07 4.52E-07 1 9.38 4.48E-07 4.42E-07 4.34E-07 4.24E-07 4.11E-07 i 9.94 4.05E-07 4.00E-07 3.94E-07 3.86E-07 3.75E-07 I I
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l CPSES ISSUE DATE PROCEDdRE NO. s EMERGENCY PLAN MANUAL JAN Os 1985 EPP-302 1 q 4, MJ MANUAL ASSESSMENT OF RADIOLOGICAL CONDITIONS REVISION NO. 3 PAGE 37 .0F 43 j ATTACHMENT 5 PAGE 6 0F 9 - .) PASQUILL CLASS D 1 (Table 9) ! l h Xu/Q Values (M~) 3 DOWNWIND CROSSWIND DISTANCE (MILES) DISTANCE (MILES) E 0.13 0.19 0.25 0,31 0.13 4.27E-04 9.62E-10 8.40E-17 1.81E-21 1.81E-21 0.25 2.47E-04 2.12E-07 3.11E-11 1.34E-16 1.05E-21 0.38 1.61E-04 1.93E-06 7.62E-09 3.29E-12 1.56E-16 0.50 1.16E-04 5.42E-06 1.18E-07 5.54E-10 5.63E-13 0.63 8.92E-05 9.28E-06 5.48E-07 1.04E-08 6.42E-11 0.75 7.08E-05 1.24E-05 1.41E-06 6.72E-08 1.34E-09 { 0.88 5.76E-05 1.45E-05 2.58E-06 2.31E-07 1.04E-08 h 1.00 4.77E-05 1.56E-05 3.84E-06 5.40E-07 4.34E-08 f 1.13 4.07E-05 1.60E-05 4.96E-06 9.64E-07 1.17E-07 1.25 3.55E-05 1.60E-05 5.88E-06 1.45E-06 2.40E-07 [( 1.56 2.62E-05 1.49E-05 7.34E-06 2.73E-06 ~7.67E-07 lp. h 1.88 2.19 2.04E-05 1.65E-05 1.33E-05 1.18E-05 7.82E-06 7.76E-06 3.71E-06 4.31E-06 1.42E-06 2.03 E-06 9 2.50 1.36E-05 1.04E-05 7.41E-06 4.61E-06 2.51E-06 2.81 1.14E-05 9.15E-06 6.92E-06 4.68E-06 2.83E-06 3.13 9.75E-06 8.08E-06 6.40E-06 4.61E-06 3.02E-06 u 3.44 8.41E-06 7.17E-06 5.87E-06 4.44E-06 3.10E-06 7 3.75 7.45E-06 6.49E-06 - 5.46E-06 4.28E-06 3.13E-05 4.06 6.73E-06 5.95E-06 5.11E-06 4.12E-06 3.13E-06 k 4.38 6.10E-06 5.47E-06 4.78E-06 3.95E-06 3.09E-06 4.69 5.57E-06 5.05E-06 4.47E-06 3.77E-06 3.03E-06 4.97 5.10E-06 4.67E-06 4.18E-06 3.59E-06 2.94E-06 5.31 4.68E-06 4.32E-06 3.92E-06 3.41E-06 2.85E-06 5.63 4.32E-06 4.02E-06 3.67E-06 3.23E-06 2.75E-06 g 5.94 4.00E-06 3.74E-06 3.44E-06 3.07E-06 2.64E-06 1 6.25 3.74E-06 3.52E-06 3.26E-06 2.93E-06 2.56E-06 - A 6.88 3.34E-06 3.17E-06 2.97E-06 2.71E-06 2.40E-06 ,. 7.50 3.01E-06 2.87E-06 2.71E-06 2.50E-06 2.25E 8.13 2.72E-06 2.61E-06 2.48E-06 2.31E-06 2.10E-06 3 8.75 2.47E-06 2.38E-06 2.28E-06 2.13E-06 1.97E-06 9 9.38 2.25E-06 2.18E-06 2.09E-06 1.98E-06 1.84E-06 j 9.94 2.07E-06 2.01E-06 1.93E-06 1.84E-06 1.72E-06 ] l O e u b 3 - e n.m,7_m. ._ .
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) CPSES ISSUE DATE PROCEDURE NO. l j EMERGENCY PLAN MANUAI. JAN 09125 EPP-302 '
9 'l m MANUAL ASSESSMENT OF 3 ' lLj RADIOLOGICAL CONDITIONS REVISION No. 3 PAGE 38.0F 43 3
- l ;
, i J ATTACHMENT 5
- PAGE 7 0F 9
- PASQUILL CLASS E '
I l (Table 10) 'l .i Xu/Q Values (M~) .J. 1 DOWNWIND CROSSWIND DISTANCE (MILES) DISTANCE (MILES) E 0.13 0.19 0.25 0.31 0.13 5.49E-04 2.36E-10 2.60E-18 2.33E-21 2.33E-21
. 0.25 3.56E-04 4.73E-08 6.76E-13 1.llE-19 1.51E-21 f 0.38 2.54E-04 5.83E-07 2.94E-10 7.10E-15 8.22E-21 0.50 1.95E-04 2.20E-06 8.08E-09 3.15E-12 1.31E-16 , 0.63 1.54E-04 4.92E-06 6.62E-08 1.59E-10 6.82E-14 O 75 1.25E-04 8.18E-06 2.69E-07 2.26E-09 4.85E-12 5 0.88 1.04E-04 1.13E-05 7.09E-07 1.46E-08 9.98E-11 1 1.00 8.83E-05 1.40E-05 1.40E-06 5.54E-08 8. 76E-10 1.13 7.70E-05 1.61E-05 2.26E-06 1.46E-07 4. 29E-09 1.25 6.77E-05 1.76E-05 3.26E-06 3.07E-07 1.48E-08 1.56 5.08E-05 1.93E-05 5.76E-06 1.06E-06 1.20E-07 hm 1.88 4.02E-05 1.92E-05 7.64E-06 2.10E-06 4.00E-07 2.19 3.26E-05 1.82E-05 8.82E-06 3.19E-06 8.63E-07 2.50 2.70E-05 1.69E-05 9. 39 E-06 4.13E-06 1.43E-06 3 2.81 2.28E-05 1.54E-05 9.52E-06 4.83E-06 2.02E-06 f 3.13 1.94E-05 1.40E-05 9.35E-06 5.29E-06 2. 55 E-06 3.44 1.68E-05 1.27E-05 9.01E-06 5.55E-06 2. 98E-06
, 3.75 1.53E-05 1.20E-05 . 8. 87 E-06 5.79E-06 3. 35E-06 3 4.06 1.41E-05 1.14E-05 8.67E-06 5.94E-06 3.65E-06 } 4.38 1.30E-05 1.07E-05 8.44E-06 6.01E-06 3.89E-06 l ^ 4.69 1.21E-05 1.02E-05 8.17E-06 6.03E-06 4. 07 E-06 l 4.97 1.12E-05 9.61E-06 7.89E-06 5.99E-06 4.21E-06 i 5.31 1.05E-05 9.09E-06 7.60E-06 5.92E-06 4. 29E-06 4 5.63 9.81E-06 8.61E-06 7. 31E-06 5.82E-06 4. 34 E-06 e 5.94 9.19E-06 8.16E-06 7.03E-06 5.70E-06 4.36E-06 , 6.25 8.74E-06 7.83E-06 6.81E-06 5.61E-06 4.37E-06 - 6.88 7.95E-06 7.22E-06 6.40E-06 5.40E-06 4.34E-06 7.50 7.27E-06 6.68E-06 6. ole-06 5.17E-06 4. 2 7E-06
+
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'.1 a CPSES ISSUE DATE PROCEDURE NO. q EMERGENCY PLAN MANUAL JAN 091985 EPP-302 U MANUAL ASSESSMENT OF () RADIOLOGICAL CONDITIONS REVISION NO. 3 PAGE 39.0F 43 0 ATTACHMENT 5 s PAGE 8 0F 9 - PASQUILL CLASS F (Table 11) f{ Xu/Q Values (M" ) y b DOWWIND CROSSWIND DISTANCE (MILES)
! DISTANCE (MILES) E 0.13 0.19 0.25 0.31 3
U 0.13 6.86E-04 2.57E-10 2.38E-18 2.92E-21 2.92E-21 1 0.25 5.21E-04 1.21E-08 1.96E-14 2.21E-21 2.21E-21
.I 0.38 4.13E-04 1.26E-07 5.06E-12 3.55E-18 1.75E-21 M 0.50 3.36E-04 5.83E-07 2.07E-10 3.06E-15 1.89E-21 0.63 2.78E-04 1.66E-06 2.76E-09 3.55E-13 3.52E-18
} 0.75 2.35E-04 3.47E-06 1.79E-08 1.13E-11 8.60E-16 3 0.88 2.04E-04 5.90E-06 7.04E-08 1.43E-10 4.93E-14 d 1.00 1.80E-04 8.75E-06 2.00E-07 1.01E-09 1.12E-12
, 1.13 1.60E-04 1.17E-05 4.50E-07 4.67E-09 1.31E-11
- 3 1.25 1.43E-04 1.47E-05 8.53E-07 1.59E-08 9.47E-11 M 1.56 1.14E-04 2.46E-06 j 1.88 9.48E-05 2.07E-05 2.48E-05 4.65E-06 1.25E-07 4.46E-07 2.70E-09 2.19E-08 2.19
] 8.03E-05 2.73E-05 7.06E-06 1.06E-06 9.34E-08 .g 2.50 6.90E-05 2.83E-05 9.30E-06 1.96E-06 2.64E-07 3 2.81 5.99E-05 2.84E-05 1.12E-05 3.03E-06 5.64E-07 d 3.13 5.26E-05 2.79E-05 1.26E-05 4.15E-06 9.95E-07 3.44 4.69E-05 2.71E-05 1.36E-05 5.20E-06 1. 51 E-06
-) 3.75 4.25E-05 2.62E-05 1.43E-06 6.14E-06 2.07E-06 j 4.06 3.87E-05 2.52E-05 1.48E-05 6.97E-06 2.66E-06 3 4.38 3.54E-05 2.42E-05 1.50E-05 7.67E-06 3.24E-06 4.69 3.26E-05 2.31E-05 1.50E-05 8.23E-06 3.80E-06 4.97 3.00E-05 2.20E-05 1.49E-05 8.67E-06 4.31E-06
]j 5.31 2.78E-05 2.09E-05 1.47E-05 9.00E-06 4.77E-06 4 5.63 2.58E-05 1.99E-05 1.45E-05 9.22E-06 5.18E-06 m 5.94 2.43E-05 1.92E-05 1.42E-05 9.41E-06 5.52E-06 ij 6.25 2.32E-05 1.86E-05 1.41E-05 9.59E-06 5.84E-06 - ! 6.88 2.12E-05 1.75E-05 1.37E-05 9.80E-06 6.35 E-06 7.50 1.95E-05 1.64E-05 -
1.33E-05 9.87E-06 6. 74 E-06
- ! 8.13 1.80E-05 1.55E-05 1.28E-05 9.84E-06 7.00E-06 8.75 1.67E-05 1.46E-05 1.23E-05 9.71E-06 7.17E-06 IlI 9.38 1.55E-05 1.37E-05 1.18E-05 9.53E-06 7.26E-06
- l 9.94 1.44E-05 1.29E-05 1.13E-05 9.31E-06 7.28E-06 a
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CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL EPP-302 JM 09 MBE
, ,, MANUAL ASSESSMENT OF
!;) RADIOLOGICAL CONDITIONS REVISION NO. 3 PAGE 40.0F 43 ATTACHMENT 5
?{ PAGE 9 0F 9 - ' PASQUILL CLASS C N (Table 12) i! 4 Xu/Q Values (M~) .I 'i DOWNWIND CROSSWIND DISTANCE (MILES) 1 DISTANCE (MILES) E 0.13 0.19 0.25 0.31 'i 9 0.13 7.66E-04 2.91E-09 4.89E-16 3.26E-21 3.26E-21 0.25 6.22E-04 3.24E-08 1.43E-13 4.57E-21 2.64E-21 j 0.38 5.14E-04 1.74E-07 8.01E-12 6.78E-18 2.19E-21 i 0.50 4.43E-04 5.22E-07 1.14E-10 8.57E-16 1.88E-21 0.63 3.97E-04 1.05E-06 6.34E-10 1.96 E-14 3.13E-20 0.75 3.59E-04 1.86E-06 2.60E-09 2.61E-13 1.89E-18 0 0.88 3.25E-04 2.97E-06 8.39E-09 2.26E-12 5.84E-17 , 1.00 2.96E-04 4.37E-06 2.24E-08 1.40E-11 1.06E-15 ( 1.13 2.71E-04 6.26E-06 5.65E-08 7.75E-11 1.62E-14 1.25 2.47E-04 8.83E-06 1.37E-07 4.02E-10 2.23E-13
. 1.56 2.01E-04 1.61E-05 6.84E-07 8.22E-09 2.79E-11 1.88 1.67E-04 2.31E-05 1.94E-06 6.05E-011 7.01E-10
,j (#'T 2.19 1.41E-04 2.87E-05 3.91E-06 2.40E-07 6.62E-09 H 2.50 1.21E-04 3.27E-05 6.34E-06 6.38E-07 3.33E-08 2.81 1.05E-04 3.51E-05 8.90E-06 1.30E-06 1.10E-07 3.13 9.50E-05 3.62E-05 1.08E-05 1.99E-06 2.27E-07 3.44 8.83E-05 3.66E-05 1.22E-05 2.61E-06 3.61E-07 i i 3.75 8.23E-05 3.68E 1.35E-05 3.29E-06 5.38E-07 ', 4.06 7.69E-05 3.67E-05 1.46E-05 4.00E-06 7.58E-07
- 4.38 7.21E-05 3.65E-05 1.56E-05 4.73E-06 1.02E-06 4.69 6.77E-05 3.61E-05 1.64E-05 5.45E-06 1.32E-06 4.97 6.36E-05 3.55E-05 1.71E-05 6.16E-06 1.66E-06 e 5.31 6.00E-05 3.49E-05 1.77E-05 6.85E-06 2.02E-06 j 5.63 5.70E-05 3.44E-05 1.83E-05 7.56E-06 2.43E-06
', 5.94 5.44E-05 3.40E-05 1.69E-05 8.28E-06 2.87E-06 6.25 5.20E-05 3.35E-05 1.93E-05 8.96E-06 3.33E-06 -- 6.88 4.78E-05 3.25E-05 2.00E-05 1.02E-05 4.27E-06
, 7.50 4.41E-05 3.13E-05 2.04E-05 1.12E-05 5.19E-06 g 8.13 4.08E-05 3.01E-05 2.05E-05 1.20E-05 6.06E-06
- . 8.75 3.79E-05 2.88E-05 2.05E-05 1.27E-05 6.85E-06 l 9.38 3.53E-05 2.76E-05 2.03E-05 1.31E-05 7.54E-06
; 9.94 3.30E-05 2.64E-05 1.99E-05 1.35E-05 8.14E-06 i
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CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL .JAN 091985 EPe-302
) MANUAL ASSESSMENT OF j p RADIOLOGICAL CONDITIONS REVISION NO. 3 PAGE 42 0F 43
-yj k e ATTACHMENT 7 l PAGE 1 0F 1 1 .
IODINE DOSE CORRECTION FACTOR
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! CPSES ISSUE DATE PROCEDURE NO.
EMERGENCY PLAN MANUAL EPP-302 .] 1 M 09 M Li MANUAL ASSESSMENT OF j b* -) RADIOLOGICAL CONDITIONS REVISION NO. 3 PAGE 43 0F 43 I a 1 ATTACHMENT 8 PAGE 1 0F 1 . ] MANUAL OFFSITE DOSE CALCULATION METHODOLOGY l .1- 1.0 This attachment provides a description of the calculations which have ~ l been entered onto magnetic cards for use with the TI-59
- i calculator / printer when projecting whole body and thyroid doses as a result of radioactive material being released during emergency ~
situations. These calculations cover four basic areas of interest, these areas are: 1) the effective age of the gaseous mixture released; , 2) the integrated whole body dose; 3) the child thyroid dose rate and - j 4) the integrated adult / child thyroid dose. This attachment only 9 provides the calculations used in making projections and does not ' ] offer any justification for this methodology nor is it intended to do so. s I d 2.0 Effective Age of Mixture Equation 1 j Receptor Wind Speed Age of Mixture at Effective Age of Distance + (miles / hour) + Time of Release = Mixture 3 (miles) (hours) (hours) 1 \ $ (' / . / 3.0 Integrated Whole Body Equation J Normalized Relative Wind . Noble Gas Average Gamma
; Concentration Value Speed X Release Rate X Energy X
.i (M 2) (m/sec) , (C1/sec) (MeV/ dis) Li j Dose Conversion Whole Body Release Integrated Whole i Rem - dis - M 8 = Dose Rate X Duration = Body D.ose d MeV - C1 - hr (Rem /hr) (hrs) (Rem) l 4.0 child Thyroid Dose Rate Equation a _ l Normalized Relative Wind I-131 Dose"Conversian r Concentration Value Speed X Release Rate X Factor. X
' 3 (M a) (m/sec) (Ci/sec) (Rem-m /Ci-hr)
.~-
Iodine Dose Adult Thyroid Child Thyroid Child Thyroid Correction Factor = Dose Rate X Factor = Dose Rate 2 (Rem /hr) (2) (Rem /hr) 5.0 Adult / Child Integrated Dose Equation c Adult Thyroid Release Adult Thyroid Child Thyroid Child Thyroid Dose Rate X Duration = Dose X Factor = Dose (Rem /hr) (hrs) (Rem) (2) (Rem)
-*.:==.ww =
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= -
p COMANCHE PEAK STEAM ELECTRIC STATION i EMERGENCY PLAN MANUAL ] 1 1 i 1 MICRO-. COMPUTER BASED, EMERGENCY DOSE ASSESSMENT 1 , )v CPSES CONY;gng, [\ , y PROCEDURE NO. EPP-303 I i REVISION NO. O O d Copy { o COW i ~ . i ' SAFETY-RELATED f i SUBMITTED BY: M DATE: #" t SUPERINTENDENT, SUPPORT SERVICES APPROVID'BY:( _ /w DATE: ,6f- ff
'f
/ NUCLEAR' OPERATIONS
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i CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUA: NOV -51984 EPP-303 [ ' L MICRO-COMPUTER' BASED, EMERGENCY DOSE ASSESSMENT REVISION NO. O PAGE 2 0F 11 1.0 Purpose 4 This procedure provides instructions for using a micro-computer based dose assessment program. I 2.0 Applicability i l This procedure is implemented by Radiological Assessment personnel j i either when the RM-21 computer is inoperable or to provide supplemental dose information. g 3.0 Definitions [' ' 3.1 Interactive Dose Assessment Model (IRDAM) - A computer program utilized by the NRC which has been modified to be site specific for CPSES. NUREG/CR 3012. PNL-4510, provides the documentation j for the unmodified program. 4.0 Instructions 1 4.1 Precautions ! - I 4.1.1 The computer equipment should be handled with care (see I t Attachment 1 for details). f 4.1.2 Handle the software with care, see Attachment 1. l* Additional copies exist; however, considerable time would be lost while the copies were retrieved. 3 4.1.3 If the printer is noi: functional, use the appropriate form ? (Attachment 2) to record the information from the screen. { 4.2 Initial Actions i
; 4.2.1 The RMS Operators bear the primary responsibility for setting up and operating the computer; however, any dose j assessment personnel may set up the computer. (See j Attachment i for details.)
l 4.2.2 IRDAM is a menu driven, user-friendly program; however, i the RMS operator should rely upon the Radiological [ Assessment Coordinator for guidance concerning data input. I 4.2.3 Data used to perform the dose projection calculations, are I obtained from the RM-11 or the RM-23 terminals in the .I control room. In addition, DBA data may be used if these terminals are not functioning. h NOTE: EPP-300 may be utilized to manually calculate a release rate not covered by the IRDAM program. l' l n s w:gr :- - = m y ;x. ~ w mnmnw m aw
d CPSES ISSUE DATE PROCEDURE NO.
] EMERGENCY PLAN MANUAL NOV -s 1984 EPP-303 MICRO-COMPUTER BASED, EMERGENCY DOSE ASSESSMENT REVISION NO. O PAGE 3 0F 11 l 4.2.4 The RMS operator shall provide the printout or Form t EPP-303-1, 2 or 3 to their Radiological Assessment j Coordinator for evaluation.
I r; 4.3 Subsequent Actions 4.3.1 Dose projections should continue until the release has
) terminated or until otherwise instructed by the j Radiological Assessment Coordinator (s).
4.3.2 The records generated from this procedure as a result of ] an emergency shall be filled in accordance with STA-302, g " Station Records". b -g 5.0 References 7,1 5.1 CPSES Emergency Plan, Section 7.0 5.2 Procedure EPP-300, " Manual Calculation of Release Rates" i 5.3 CPSES Final Safety Analysis Report
?;
~
5.4 NUREG/CR 3012. PNL-4510 (3 Volumes), " Interactive Rapid Dose Assessment Model (IRDAM)" 5.5 Procedure STA-302, " Station Records" l 6.0 Attachments ' 6.1 Set Up and Use of the Micro-computer. 8 6.2 Forms .
- h x u
- ,,,,.s,-:- - - ,- - , - - , - -
g.
;,g ..,, y _. pypy r-- y- . , ,
. . ..-.. w ,; CPSES ISSUE DATE PROCEDL'RE NO.
j EMERGENCY PLAN MANUAL - NOV -51984 EPP-303 MICRO-COMPUTER BASED, EMERGENCY DOSE ASSESSMENT REVISION NO. O PAGE 4 0F 11 s ATTACHMENT 1 H PAGE 1 0F 5 h - + p SET UP AND USE OF THE MICRO-COMPUTER i 1.0 Ensure that each piece of equipment is in the "off" position prior to I plugging into any power supply. 2.0 Handling Diskettes. 2.1 Do not expose diskette surfaces to food, smoke or touch with
., hands.
2.2 Do not write on diskette surfaces with any utensil except a sof t
? felt-tip pen. Never erase on diskette surfaces.
l
, 2.3 Keep diskettes in their protective covers when not in use.
1 l 2.4 Do not flex, band, crimp or paper clip diskettes. 4 j 2.5 Do not stack books, papers, or any heavy objects on top of j diskettes. h 2.6 Do not set diskettes near telephones, motors, clip holders or any other object which produces a magnetic field. 3.0 Setting up the KAYPRO:
- 3.1 If used, connect the " MINUTE MAN" uninterruptable power supply
'- (UPS) to a 110 VAC power supply. 3.2 Connect the KAYPRO computer and the OKIDATA printer to the L'PS. 3.3 Connect the keyboard to the computer terminal.
! 3.4 Connect the printer to the parallel port on the computer. (Refer i to page 4 of this Attachment.)
~
l
} 3.5 Turn on the UPS. ,
j 3.6 Turn on the OKIDATA printer, the " POWER" and "SEL" indicator 3 lights should illuminate and the print head should return to its ! far left " ready" position. l 3.7 Turn the KAYPRO computer on; the " POWER" indicator light should f illuminate, and the "A" drive should be operating with the red indicator light illuminated on drive "A". After a few seconds, the CRT will illuminate the following prompt:
"*KAYPRO*"
"Please place your diskette into Drive A" (Flushing)
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J. CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PL'AN MANUAL NOV -51984 EPP-303 MICRO-COMPUTER BASED, EMERGENCY DOSE ASSESSMENT REVISION NO. O PAGE 5 0F 11 ATTACHMENT 1 i PAGE 2 0F 5 . 3.8 Insert the diskette into drive "A". The program will load
] automatically and the following information should appear on the a
j screen:
.I -
j NOTE: If the KAYPRO does not auto-load the program and the
! following does not appear on the screen, refer to section j 4.0 of this attachment.
I KAYPRO II 64K CP/M Version 2.2 i'! Basic-80 Revision 5.21 (CP/M Version]
,; Copyright 1977-1981 (c) by Microsofe Created: 28-Jul-81 j 34872 bytes free 1
~
u * *
- THIS IS THE INTERACTIVE RAPID DOSE
- ASSESSMENT MODEL (IRDAM). FOLLOW
- h
- THE RESPONSE INSTRUCTIONS EXPLICITLY TO OPERATE THE PROGRAM. YOU WILL
- HAVE AN OPPORTUNITY TO REVIEW AND *
!
- CHANGE ALL INPUTS PRIOR TO ANY
- j
- CALCULATIONS. *
}y **********+***************
1
- 1 (j 3.9 The program is now ready'~to calculate dose projections.
?] 4.0 To manually load both the BASIC Language and the dose assessment a program, type the following:
~
Computer Prompt User Response 4 fj . A> MBASIC < Return > 3 OK RUN "CPIRDAM" < Return > 1
) Continue as if the program was loaded automatically.
- i
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- .m m? - q- -r ., + : a-ym-, 3 yq::pyggp p app;ggz. g g , -
CPSES TSSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL EPP-303 NOV -51984 MICRO-COMPUTER BASED, 4 j
^ EMERGENCY DOSE ASSESSMENT REVISIO!; NO. O PAGE 6 0F 11
(~ a
- ATTACHMENT 1 PAGE 3 0F 5 POWER ON DISK DRIVE INDICATOR LIGHTS Small, red light on front panel beside ' Small, red lights next to the door of disk drives tells you that the power each disk drive tell you which drive is ON. was selected last.
+ \s f
s A D, _.. 47: 1 A
-}.
n a
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r ^ V h' t 1 1 Il ...: Y I o 1 i _ . . . A R Q.A_ dl X2Oi AM-AwahhTr4mA 6 ve cy - 1 ( _Ne mh"] dk'\ f i
- n- cg m g,,o m A
e. V. J . i ,l ,i n KAYPRO COMPUTER ( k + r 0;<, . _ 1 c; j 3 I G l U i OKIDATA PRINTER ! 1 1 i ,
.- .- - -. y - ,- - x HZT '7"Env7':c7pyrgy;j.;&c- y :.py.g.qgy,ym g.7, e. .r- . _ .
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CPSES ISSUE DATE PROCEDURE NO. 1 EMERGENCY PLAN MANITAL EPP-303 NOV -51984 MICRO-COMPUTER BASED, y r." EMERGENCY DOSE ASSESSMENT REVISION NO. O PAGE 7 0F 11 j \ ".} 4 j ATTACHMENT 1 l 4 PAGE 4 0F 5 - PROCEDURE i j '
- l. Ensure the terminal power j ,, switch is in the off j position.
se. .t .. E '. .N . r. ..mten ,o
- 2. Ensure the printer power
.eset sutten ca woeru uo switch is in the off
\ 5 Position.
I / \ M 3. Insert the modular phone cord !l );, b. / y provided into the back of the
, g gg g g g ggggggggggggg g gy g _@6 terminal and 4. into the back of the keyboard.
4 g s2!:: .gw. p 5. Plug the parallel connector j h i di
~
into the back of the terminal l O- ~W M ;g-; and 6. into the back of the
- m printer.
l l' F~ 768 Connect both the terminal 110 c VAC plug and the printer 110
; gyl' russ - e.'ontmess =~ce VAC plug into standard 110
( Vac outlet (see note). ' 7 NOTE: If a minute man j uninterruptable power y supply is (UPS) used, L plug both 7 & 8 into I the back of the UPS and I /7,*M'E ' W[ .m plug the UPS into a K scandard 110 Vac
~
I rs j KEYBOARD I , outlet. i . t I a i e v , ! ..,~1. , 4 i @ j ::= ^9 cc -v g ' a gt . o
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c CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL EPP-303 NOV -51984 1 MICRO-COMPUTER BASED,
' m, EMERGENCY DOSE ASSESSMENT REVISION NO. O PAGE 8 0F 11
,j d
4 ATTACHMENT 1 PAGE 5 0F 5 i f OKIDATA PRINTER 1 j # m j' FORM SEL PAPER POWER LENGTH O O O f g 0 ,T , , j TOF gg FORM UNE j SET FEED FEED i t'E > . . c I i 4 y i . FRONT OPERATING PANEL t j Control Euttons: The SEL (Select) Button turns the SEL light on or off.
! FORM LENGTH. SELECTION DIAL specifies the form length of the paper you are using. Ensure the form length selection dial is set at 7.
O.. . L T0F (Top of Form) SET Button With the T0F SET button you can set th'e position where printing will start j on a page. It functions only when the SEL light is off. ? When the printer is ON:
- 1. Turn the SEL light of f by pdshing the SEL button, j 2. Move the paper to the position you want.
- 3. Push the TOF SET button.
) 4. Push the SEL button to select the printer again.
j 5. Top of Form is set. j NOTE: The Top of Form position is automatically set when the printer is
- ' turned on. _
FORM FEED Button Use this button to nove the paper to the next top-of-form position. It y functions only when the SEL light is off. 1 1. Turn the SEL light off by pushing the SEL button, l 2. Push the FORM FEED button. I 3. The paper will move to the next top of form position.
- 4. Push the SEL button again to select the printer.
f LINE FEED Button i Use this button to advance the paper one or more lines. This button j j functions only when the SEL light is off. y 1. Turn the SEL light of f by pushing the SEL button.
; 2. Push the LINE FEED button. ] 3. The paper will move up one line.
I ~
- -~ ~ ~
r y p p h m p n p r C-7' M e m ~
f CPSES
. ISSUE D FROCEDURE NO.
EMERGENCY PLAN MANUAL. NOV -5 Ed4 EPP-303 MICRO-COMPUTER BASED, 5
) EMERGENCY DOSE ASSESSMENT REVISION NO. O PAGE 9 0F 11 l
l ATTACHMENT 2 PAGE 1 0F 3 . !, FORMS i i Texas Utilities Generating Company Comanche Peak Steam sectric Station ll STACK RELEASE CALCULATION Page 1 of 1 1
, A. STACK RELEASE:
i
- 1. Date: Time:
. 2. Calculation numbers: Completed by:
- 3. Wind Speed (MPH): ; Direction (From):
4 Stability Class: l B. RILEASE DATA: I ! 1. Total Stack Flow Rate (CFN): l l 2. Data using RM-11. RM-23 or Cross sample re. sics: ! ('lI a. b. Woble gas cone (mC1/ec): Iodine cone (sci /ce): _
- 3. Data using specific isotopes:
I Isotope Conc (aci/cc) Isotope Cone (aci/cc) ! Kr-83M Ie-135 i Kr-85M Ie-137 Kr-85 Ie-138
~
Kr-87 Ca-134 l Kr-88 Cs-137 Kr-89 I-131 Ze-13ta I-132 l Ze-133e 1-133 ) Ze-133 1-134 Ie-135e I-135 NOTE: When using #3. 1sotopes with no entry for the concentration are assumed to not be present. 4 Release duration (HRS): C. RESULTS:
. Downwind Plume Travel Whole Body Child Thyroid Distance Time (hrsteins) Dose (RDtS) Dose (RZMS)
EAR 2 miles 5 miles 10 miles
/ O. REVIEVD /DATE:
sj RAntotoGICAL ASSESSMENT COORDINATOR REV.102984 EPP-3o3-1 _,...;.._.._..__ _ _ - . _ . . . _ . _ . . ___.,_.m.- .- _ . - .
-. 7, . ~ . . . -
l CPSES ISSUE DATE PROCEDURE NO. j EMERGENCY PLAN MANUAL NOV -51984 EPP-303 MICRO-COMPUTER BASED, l O EMERGENCY DOSE ASSESSMENT REVISION NO. O PAGE 10 0F 11 1 Q/ ATTACHMENT 2 PAGE 2 OF 3 k j FORMS 4 4 1 Texas UtMtles Generating Company l Comanche Peak Steam Bectric Station I CONTAINMENT LEAKAGE CALCULATION k Pete 1 of 1 j 1 A. CONTAINhCNTLEAKAGE: a
- 1. Date Time: J
]4 2. Calculation numbers: Completed by: j
- 3. iifnd Speed (MPH): ; Direction (From): )
4 Stability Class: s
- 8. RELEASE DATA:
- 1. Containment Leak Rate (E Free Air Vol/ Day):
)
(m)
- 2. Source Origin Coolant Inventory
.j Cap Inventory j Fuel Melt i Containment Monitor Readings (R/VR): ,l 3. Iodines in the release _ No; skip to 4 i a. Yes: Iodine-Noble Cas Ratio: j b. todine Filtered: _ Yes; _ No 1 4 Time Reactor Shutdown to Release began (hours):
- 5. Duration of the Release (hours):
i 6. Time of sample or measurement to Release began (hours): .); C. RESULTS: h Whole Body Child Thyroid Dowmrind Plume Travel { Distance Time (hrs: mins) Dese (REMS) Dose (REMS) j { M - j f 1 2 miles - 5 miles 10 miles l
, D. REVIEVD/DATE:
RADIOLOGICAL ASSESSMENT COORDINATOR {-,
" 'd REV.102984 EPP-303-2 i
f
- - - -- s..,, _~ _., . _ . . , , , ,,. , , , , , , ,
7 . , . _ _ _
CPSES ISSUE DATE PROCEDURE t40. EMERGENCY PLXi MANUAL NOV -51984 EPP-303 MICRO-COMPUTER BASED, I EMERGENCY DOSE ASSESSMENT REVISION NO. O PAGE 11 0F 11
; @u i
j ATTACHMENT 2
; PAGE 3 0F 3 .
FORMS
- i a
lI Texas Utilities Generating Company j Comanche Peak Steam Electric Station STEAM GENERATOR TUBE LEAK Page 1 of 1 A. STEAM CENERATOR TUBE LEAK:
- 1. Date: Times
- 2. Calculation numbers: Completed by:
- 3. Wind Speed Otra): ; Direction (From):
4 Stability Class
.\
J I
- 3. RELEASE DATA:
- 1. Rate of Coolant Loss (CFM):
- 2. Total Activity of the Coolant .
'j _ aC1/ gram:
j _ Ci/11ters o aci/ce: [ default (635 aci/ce)
- 3. Iodines in the release: Nor skip to 4
, s. Tes: Iodine - NobleTs Ratio
- b. Iodines Filtered? _ Tes; _ No '
! 4 Time Reactor Shutdown to Release began (hours):
- 5. Duration of the Release (houra):
]
- 6. Time of saeple or measurement to Release began (hours):
C. RESULTS: Downwind Flume Travel , Whole Body Child Thyroid Distance Time (hrstains) Dose (RDiS) Dose (REMS) s EAR 2 miles 5 miles 10 miles i D. REVIEWED /DATE: RADIOLOGICAL ASSESSMENT COORDINATOR } 4 ( REY.102984 . ,i EPP-303-3 A 1 i ! t I.e y _---*w,
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; COMANCHE PEAK STEAM ELECTRIC STATION f
i (] EMERCENCY PLAN MANUAL .I i f 3 h s i i PROTECTIVE ACTION GUIDES O . 9 PROCEDURE NO. EPP-304 REVISION NO. 5 1 0 ME.S i SAFUMELATEDt- O 4 .
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SUBMITTED BY: DATE: -/0 i g
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j' CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL "'-3 ' NOV -6 684 1 i
- f' ?.
%.)
PROTECTIVE ACTION GUIDES REVISION NO. 5 PAGE 2 0F 18 1.0 Purpose
^
This procedure describes the basis for and mechanisms by which
- protective action measures are formulated and then recommended to the appropriate State and county authorities in the event of an emergency -
3 condition at CPSES. ' N 4 2.0 Applicability I e l This procedure is applicable to the Emergency Coordinator and those ? CPSES Emergency Organization personnel who are responsible for formu-lating protective action recommendations. t j This procedure becomes effective when issued. 1 i 3.0 Definitions ) 3.1 Emergency Planning Zone (E.P.Z.) - That area surrounding the ] Station in which emergency preparedness planning is conducted for y ~
- j the protection of the public.
i
'~
3.1.1 10-Mile E.P.Z. - That area, approximately 10 miles in
.o radius from the center of CPSES, for which emergency planning considerations of the plume exposure pathway have y been given in order to assure that prompt and effective actions can be taken to protect the public and property in
, the event of an accident. 3.1.2 50-Mile E.P.Z. - That area, approximately 50 miles in ) radius from the center of CPSES, for which emergency j j planning considerations of the ingestion exposure pathway , d has been given in order to assure that effective actions ~ can be taken to protect the public. e 3.2 Minimum Affected Area - The minimum affected area is defined as that sector containing the centerline of the plume and the i,_ contiguous 22.5* sectors en either side of the plume centerline. __ g 3.3, Minimum Response Area - That area of land within the 10 mile EPZ j that is bordered by easily recognizable landmarks, that a approximates 25% of the 10 mile EPZ and is the minimum area that j local governments will recommend protective actions for. This j area consists of four quadrants listed as Area 1 Area 2 Area 3 j and Area 4. j 3.4 Projected Dose (Exposure Projection) - A calculated or expected j exposure that would be received by population-at-risk j ,_ individual (s) from direct radiation from a radioactive gaseous j ('{) plume resulting from a radiological emergency if no protection
, actions are taken.
I 1 i J
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. CPSES ISSUE DATE PROCEDURE NO. l EMERGENCY PLAN MANUAL g4g EPP-304 l
PROTECTIVE ACTION GUIDES REVISION NO. 5 PAGE 3 OF 18
!] !. 3.5 Protective Actions - Those emergency measures taken for the purpose of preventing or minimizing radiological exposures to ,
affected population groups. 3.6 Protective Action Guides (PAG) - Projected radiological dose - values to individuals in the general population that warrant protective action. Protective actions would be warranted provided that the reduction in individual dose expected to be achieved by carrying out the selected protective action is not f offset by excessive risks to individual safety in taking that I protective action. i 3.7 Protective Action Guide - Numerical Projected doses which act as
; trigger points to initiate protective action.
; 3.8 Protective Action Recommendation - A recommendation for protective action designed to provide information concerning the j action to be taken based upon Protective Action Guides.
~
- 4.0 Instruction s' I
4.1 Precautions f, < 4.1.1 The Emergency Coordinator is responsible for selecting the protective action recommendations and for ensuring that i the protective action recommendations are communicated to the State and county authorities in a timely manner. ! 4.1.1.1 These recommendations generally concern the l 10-mile EPZ, however, Protective Action [ Recommendations may be provided to State j authorities for any potentially affected areas ! beyond the-10-m11e EPZ. 4.1.2 The county authorities have the final decision-making authority regarding Protective Actions and are responsible for the implementation of those actions. State officials, _ l upon request from the county authority, provide assistance
. to ensure proper implementation of these actions. Texas Utilities has no authority with respect to imposing protective response options beyond the boundaries of its
. site. l l 4.1.3 Recommendations should be timely in order to achieve the i desired degree of protection for the public. Conceivably, I there is a 30 to 60 minute time lag from the time the Protective Action Recommendations are made by the utility until the public is informed of the selected Protective
.) Action Recommendation.
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l CPSES TSSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL NOV -61984 EPP-304
'l .
3 {
! ([]
.s PROTECTIVE ACTION GUIDES REVISION No. 5 PAGE 4 OF 18 i
4.2 Initial Actions 4.2.1 The initial Protective Action Recommendation by the Emergency Coordinator (on-duty Shif t Supervisor) to State and county authorities may be. based upon plant conditions, radiation data available or dose projection data if
? available. The initial recommendation shall be provided within 15 minutes of a General Emergency, and follow-up recommendations shall be provided as conditions warrant, with a target of at least every 60 minutes.
Y y NOTE: There is a 15-minute time limit for providing j information to the State and county authorities. A Since this may not be sufficient time to calculate the initial dose projections, Protective Action Recommendations may be based on instrument readings and actual plant conditions (Attachment 1, EPP-304-1, " Protective Action Guide", Attachment 2,
" Protective Action Guides, Plume Exposure Pathway" )3 and EPP-306, "Use of Thyroid Blocking Agents" for l } the Protective. Action Recommendation process).
1 { (33 In addition to the above listed factors, the following
) k G' factors should also be considered when making a Protective j Action Recommendation:
i i 4.2.1.1 The Population-at-Risk: Including special concerns in the area of the release. 4.2.1.2 Response Time: Including the time to assemble needed resources in order to implement the 6 recommendation. 4.2.1.3 Weather: Current Conditions, short term and f long term Forecasts and changes in Wind j Direction. 4 4.2.3.4 Physical and Environmental Conditions: Limiting 1 factors which will affect the response time of I. the offsite agencies. I I NOTE: All precautionary considerations to { ensure safety of the public shall be j based upon the available data, to ensure 3 the safety of the population-at-risk, i The Emergency Coordinator shall consider
} the action to be taken, how much time is ! available to take the action and the ! (. ) potential effects of the recommended
- P. action.
i
- 4 .
2 mmmem rmmwacmmmwgyg;r,mygw :mww=wnrn ~=~
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J CPSES ISSL'E DATE PROCEDURE NO. 4 EMERGENCY PLAN MANUAL EM-304 NOV -s toga 1
; PROTECTIVE ACTION CUIDES REVISION NO. 5 PAGE 5 0F 18 I
- j 4.2.3.5 In the event of a non-radiological release of 6
toxic materials, the Emergency Coordinator shall , implement EPP-211, " Release of Toxic Material"
; and follow EPP-304-1, " Protective Action Recommendation Guide" (Attachment 1) to make any ) -
needed Protective Action Recommendation to
,i ' offsite agencies.
H 4
). 4.2.2 Upon classification of an emergency at CPSES, implement EPP-304-1, "Protactive Action Recommendation Guide"
( (Attachment 1) as needed until the emergency condition has j terminated, and it has been determined that the protective N actions are no longer needed or required. I J ' 4.2.5 Protection Action Recomendation Objectives - The minimum affected area and minimum response area shall be provided [ to the State and county authorities in accordance with the j message formats in Procedure EPP-203, " Emergency Notifica-J tion". _ I ._ NOTE: In the event of a loss of the primary meteorological tower, the protective action t t- recommendation should be expanded to consider a minimum of five (5) sectors (two on either side of {j the Centerline sector). [
4.3 Responsibilities
i(l The Emergency Coordinator is responsible for protective action [ recommendations to offsite ' authorities and for ensuring that station personnel are properly protected. Information concerning protective action recommendations are provided to the Emergency Coordinator from the following sources: [ .I
- a. Plant Conditions - Shif t Technical Advisor, TSC Engineering Team, EOF Engineering Team. _
} b. Radiological Conditions - Shift Technical Advisor, Onsite-
- Radiological Assessment Coordinator and Radiological y Protection Coordinator.
4.4 Subsequent Actions l 4.4.1 As plant or meteorological conditions change or are projected to change or additional information becomes available, the protective action recommendations shall be reevaluated and any changes shall be transmitted to the j h- State and county authorities in accordance with the follow-up message in EPP-203. I 1 - 1 [ ; M $g '#'
3 CPSES ISSUE DATE PROCEDURE NO. b EMERGENCY PLAN MANUAL EPP-304 NOV -61984 !1-4 J / ;'% PROTECTIVE ACTION GUIDES REVISION NO. 5 PAGE 6 0F 18
- i,
'J 1
3 4.4.2 Additional information and assistance for evaluating j subsequent Protective Action recommendations is located in i] Attachments 3 thru 7. ij
? 5.0 References d.
5.1 CPSES Emergency Plan, Section 8.0, and Section 15.0, Appendix N
] 5.2 State of Texas Emergency Management Plan j 5.3 Hood County Emergency Operations Plan 1
j 5.4 Somervell County Emergency Operations Plan n
- ] 5.5 EPA-520/1-75-001, " Manual of Protective Action Guides and Protective Actions for Nuclear Incidents", U.S. Environmental Q
j Protection Agency, September, 1975 (revised June, 1980). d 5.6 EPP-201, " Assessment of Emergency Action Levels, Emergency
, Classifications and Plan Activation" I 5.7 EPP-203, " Emergency Notification" 6.0 Attachments 6.1 Attachment 1, " Protective Action Recommendation Guide" j$ 6.2 Attachment 2 " Protective Action Guides, Plume Exposure Pathway" j'
~
6.3 Attachment 3, " Protective Action Guides, Ingestion Exposure 3 Pathway" 2 j 6.4 Attachment 4, " Plume Exposure EPZ Evacuation Time Estimates and d Population Distribution and Primary Evacuation Routes" ' b 6.5 Attachment 5 " Reduction in External Camma Doses From Passing i] Cloud and Inhalation Shielding Factors for a Wood House with Snug Doors and Closed Windows" q q . ] 6.6 Attachment 6 "Special Facilities" I ] 6.7 Attachment 7. " Comanche Peak Steam Electric Station Public ] Response Areas" d 2 i
?
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l CPSES ISSUE DATE PROCEDURE NO. j EMERGENCY PLAN MANUAL EPP-304 t, NOV -61984 z3 PROTECTIVE ACTION GUIDES REVISION No. 5 PAGE 7 0F 18 ? ATTACHMENT 1 %s PAGE 1 0F 2 .
, Protective Action Recommendation Guide
.] d / Texas Utiuties Generating Company ) Comanche Peak Steam Electric Station PROTECTIVE ACTION RECOMMENDATION GUIDE 2 4 p.e.1.e 2 ERIEftWBICT 5 DECLAMD MEWAua4TE , (Epp-tell CosemoseS ' C :
!P r N 1 i 2 i g SITE AMA M8ERAL ERAERGE80CY ERIEftGDeCY 1r ir f
IIECotSIAENDAT900e* REC 0esaseIDAftose' SesELTEn AnEA 2 & 4 EVACUATE AU. AREAS STAMON con mLE nAssuS Excerr a con S-amLE RADIUS A010 S0WLTER [. , STATUS annasaanna IWSPOfGEE
- A' AREA POR S-estLE f STASLE RADIUS I ' I '
l 1 UINTASLE OR CONSIOct A DEGRADmG
- ggggy,,g RECOtseAENOATIO90 RECOestseIDATIO90 DOSE SASED ON STATUS SSCT IDE'OluRAT3001 2 gyggggggg 1
a : PROV OE PflECAUTICISARY ,,,, 1 .'.",iCm ~~ ~ "T'"*" S,ECiAL = eLAnT FACIUTIES , STATUS i)
- A8e C0802510888 E
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CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL EPP-304
, NOV -61984
.s PROTECTIVE ACTION GUIDES REVISION NO. 5 PAGE 8 0F 18 1
i C'l) 1 ATTACHMENT 1 PAGE 2 0F 2 3 Protective Action Recommendation Guide
} Texas utstfee Generating Company i Comanche Peek Steem Electric Station PROTECTIVE ACTION RECOtaM3mATION GUCE es 2eet i
l Section 1 Does toformation (Based on Dose Proisettoes) liBOLE BODY e 1 RZM Eo Acties Required CEILD TET302 e5m , UgoLE BODY > 1 REN but e 5 REM Shelter G ILD TETROD E5REMbute25 RIM
, iiWOLE BODY > 5 REM
,, Evacuation j GILD TNTROD > 25 RIM g Section 2 Plant Status l
Loss or probable lose of assessment capabilit e Possibility of asether effleest pathway. Loss or probable loss of safety systems. Probable increase in source tern. . 14ee or probable loss of esy remaining fissise product barriere. Loss or probable loss of accese systems to cool down plant eyetene. Amy other chasses or probable changes is plast conditions which may potentially degrade plant status or increase the hasard to the public. Sectios 3 Other Factore - g tiestbert Good Inclement Special Facilities: At w ht 6'
- Time of Day: Daylight Night Schools. Campgrounds, etc.
j Forecast Inclement leopense Times e 1 hr or > 1 hour
$pecial Concerne Pregnant women )
and small children l_ Pluma Trevel Time Arrival and Passage Agricultural Concorries Dairy, a Livestock. Crope. Water. ". Section 4 Examples of Modifications to Protective Action - $' Recosmondatton
. I j a. Shelter Response Areae 2 and 4 out to a radius of 2 miles and the minimum response area out to a redine of 5 milee,
- b. Evacuate Response Areae 2 and 4 out to a radius of 2 milee and the minimum response area out to a radius of 5 miles and shelter out to 10 miles.
- c. Evacuate response areas 2 & 4 to 2 miles sod the minimum response area to 10 miles shelter remeising areas to 5 asles.
EPP-304-1b \ i G s m e e-i.
- + - ~ - * * ~
,, . -. , ., - . + . . . - . + , - . - _ . - - - :--- . ----,: - - - , - - .- --------'
l- CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL EPP-304 NOV -61984 4 e I ". PROTECTIVE ACTION GUIDES REVISION No. 5 PAGE 9 0F 18
! =s
,1 j ATTACHMENT 2 PAGE 1 0F 2 . 1 Protective Action Guides Plume Exposure Pathway l (NOTE 3) - Projected Total Dose (In' Rem) l To The Population Recommended Actions (NOTE 1) Comments Whole Body - Less than 1.0 No planned protective actions Previously recom-required (NOTE 2). Offsite mended protective - Thyroid - Less than 5.0 authorities may issue an actions may be j advissry to seek shelter reconsidered or j and await further in- terminated, j structions. Monitor en-J vironmental radiation levels. . ]' 4 Whole Body - 1.0 to 5.0 Seek shelter as a minimum. If constraints ]
. Consider evacuation unless exist which pre-Thyroid - 5.0 to 25.0 constraints make it in- . clude a full-practical. Monitor environ- scale evacua-mental radiation levels. tion, special con-(jis ' Control access to the sideration should NaY affected area. be given to evacuating chil-dren and pregnant women.
l 7 Whole Body - 5.0 and above Conduct mand,atory evacua- Sheltering is an g tion. Monitor environ- alternative if J Thyroid - 25.0 and above mental radiation levels . evacuation can-
- and adjust affected area not be promptly j for mandatory evacuation accomplished.
! based upon these levels.
1- Control access to the affected area. t NOTE 1: These actions are recommended for planning purposes only. Practical 1 action decisions at the time of e incident must take the existing
; conditions into consideration (e.g., weather and plume arrival time).
.I NOTE 2: At the time of the incident, officials may implement low-impact protective ] action measures in keeping with the principle of maintaining radiation exposure as low as reasonably achievable (ALARA). j NOTE 3: These protective action recommendations are based on the EPA " Manual of j Protective Action Guides..." and are consistent with the PAG's utilized by the State of Texas Emergency Management Plan. 1 4 i f
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CPSES ISSUE DATE PROCEDURE NO. EMERGENCY PLAN MANUAL g ,,g EPP-304 l- ] s, PROTECTIVE ACTION GUIDES REVISION NO. 5 PAGE 10 0F 18 i / t ATTACHMENT 2
, PAGE 2 0F 2 Protective Action Guides Plue:e Exposure Pathway l'
In conjunction with the initial protective action recommendations derived from Attachment 1, " Protective Action Recommendation Flow", the following are additional considerations for the formulation of new protective action j recommendations: s Possible Recommendation Options Dependent Upon Conditions: j a. Evacuate Response Areas 2 and 4 to 2 miles and the minimum response a area to 5 miles and shelter to 10 miles. ) -
! b. Evacuate Response Areas 2 and 4 to 2 miles and the minimum response area to 10 miles and shelter beyond 10 miles in the affected downwind jl sectors. May even consider sheltering out to 5 miles in all Response , Areas.
l
- c. As warranted by the existing conditions. i i
j Some ezamples of plant conditions which may indicate the need for increasing j d7 Protective Action Recommendations: i 1
- 1. Loss or imminent loss of assessment capability. !
I f 2. Possibility of another effluent pathway. j l
- 3. Loss or imminent loss of additional safety systems, i l
; 4. Occurrences or potential occurre'nces of non-radiological releases l which may preseni hazards to the public.
l 5. Any increases in source term. i i
- 6. Loss or imminent loss of 3 fission barriers.
- 7. Loss or imminent loss of cooling water inventory.
- 8. Loss or imminent loss of access systems to cool down plant systems.
- 9. Any changes in plant conditions which may potentially degrade the ,
overall plant status. ! (?.) a 1 l
..,..,.-.7-. .,
-l
; CPSES . ISSUE DATE PROCEDURE NO.
EMERGENCY PLAN MANUAL EPP-304 NOV -6 t984 y PROTECTIVE ACTION GUIDES REVISION NO. 5 PAGE 11 0F 18 c;)
- ATTACHMENT 3
% PAGE 1 0F 2 1; j Protective Action Guides Ingestion Exposure Pathway )5 The following information was extracted from the State of Texas Emergency
- ! Management Plan. This material is for information only; however, this material
-I may be utilized to strengthen a protective action recommendation.
. Radionuclide Response Levels Equivalent To Ingestion Pathway PAGs Response Level for Preventative PAG Tj I-131 Cs-137 Sr-90 Sr-89 l Initial Deposition (uCi/m 2) 0.14 1.7 0.34 6 2i Peak Activity:
Pasture (uci/kg). 0.27 3.5 0.7 13 Milk (uci/1) 0.012 0.34 0.007 0.13 Total Intake (uC1) 0.09 7 0.2 2.6
)
d s Response Level for Emergency PAC I-131 Cs-137 Sr-90 Sr-89 Infant Adult Infant Adult Infant Adult Infant Adult Initial Deposition ~ 1.4 18 17 65 3.4 25 60 3000
, (uC1/m*)
Peak Ac'tivity:
~
Pasture 2.7 37 35 50 7 50 130 6000 Milk (uCi/1) 0.12 1.7 3.4 22 0.006 0.55 1.3 60
, Total Intake (uci) 0.9 10 70 110 12 12 26 1000 l
l l 9
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CPSES -ISSUE DATE PROCEDURE NO.
, EMERGENCY PLAN MANUAL EPP-304 , NOV - A MM i
j r
, e:S PROTECTIVE ACTION GUIDES REVISION No. 5 PAGE 12 0F 18 ? kJ ATTACHMENT 3 f PAGE 2 0F 2 4
Protective Action Levels for Ground Contamination l
? A. Action Levels 1
1 1. Projected whole body dose above the ground is greater than or equal to i 1 Rem. a j 2. Ground contamination levels exceeding 200 pCi/m 2 at t = 1 hr j post-accident. 4 9
- 3. Exposure rate exceeding 12 mR/hr at 1 meter above ground at t= 1 hr j af ter the Release has been terminated.
a 2
] B. ' Recommended Protective Actions
.) 1. Evacuate affected areas, i i 2. Restrict entry to contaminated of fsite areas until the radiation h levels have decreased to State-approved levels. , s
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M N M N d O P1 O H % (n M M Dietence free Plant (Miles) O to 2 c n W 0 to 5 0 to lo *1 d O M N M N O Quadrant NE SE SW .m - f,' NW NE SE SW NW NE SE SW NW > O N to h
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.... < ~ p-en 8 Permanent Population p o 4 0 4 64 13 495 2793 430 201 8389 4692 960 1589
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'J m O rt C i l' Permanent Population Total s H Evacuation Times (Minutes)
O d O g H > Q l] Under Normal Conditions 0 43 45 41 44 62 44 ' 40 116 77 46 31 to
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,,; under Adverse Conditions 0 54 57 51 52 70 56 40 125 83 57 58 M O
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' t, Special Population 0 0 0 0 0 1353 450 0 3444 1875 458 o
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'k Special Population Total Evacuation Times (Minutes) h OH N
Q P-* e d linder Normal Conditions 0 0 0 0 0 55 50 0 42 52 50 o
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@ O Under Adverse Conditions 0 0 0 0 0 54 60 0 45 57 61 0 rt O
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j.. e ' i (*) - Includes transients, schools, hospitals, recrescion areas, convalescent homes, etc. r"v e1 N N e > W M cf O O c M MO . N t1 rt e >== Nv O M l C d LJ W O OM
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CPSES ISSUE DATE PROCEDURE NO. 4 EMERGENCY PLAN MANUAL EPP-304 NOV -61984 -l 1 i ,
. PROTECTIVE ACTION GUIDES REVISION NO. 5 PAGE 14 0F 18
,;t V. ; 1 ATTACHMENT 4 .; PAGE 2 0F 2 1 - I. Primary Evacuation Routes from CPSES 1 q 1. Plant access road to Hwy FM201; North on Hwy FM201 to Hwy FM 51 and Hwy FM204; .]* North on Hwy FM51 to Hwy US-377 at Granbury (16 miles); West on Hwy US-377 to Stephenville (34 miles)
- 2. Plant Access Road to Hwy FM201;
, South on Hwy FM201 to Hwy US-67 at Glen Rose (8 miles);
East on Hwy US-67 to Cleburne (24 miles). } IA. Alternate Routes
- f 1A North on Hwy FM201 to Hwy FM51 and Hwy FM204 j North on Hwy FM201 to Hwy US-377 at Tolar (10 miles); .
i West _on Hwy.US-377 to Stephenville (24 miles);
, 1B to Granbury; .
d East on Hwy US-377 to Hwy FM171 at Cresson (13 miles); a South on Hwy FM171 to Cleburne (20 miles) i 2A to Glen Rose; j 1 () West on Hwy US-67 to Stephenville (35 miles).
., II. Preselected Monitoring Locations are described in Procedure EPP-310, j "Offsite Radiological Monitoring" .i III. The primary relocation centers are:
the High School in Stephenville; and the High School in Cleburne , k o-4 O l .
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1 i* ' CPSES ISSUE DATE PROCEDURE NO.
' EMERGENCY PLAN MANUAL NOV -61984 EPP-304 PROTECTIVE ACTION GUIDES REVISION NO. 5 PAGE 15 0F 18 m
( ATTACHMENT 5 PAGE 1 0F 2 l Reduction In External Gamma Dose From Passing Cloud 1 .1
-STRUCTURE OR LOCATION SHIELDING FACTOR (Note 1)
AVERAGE RANGE Outside 1.0 -- Vehicles 1.0 --- f I ' Wooden frame house (no basement) (Note 2) 0.9 --- 5 . Basement of wooden frame house 0.6 0.1 to 0.7 (Note 3) { Masonry house (no basement) - 0.6 0.4 to 0.7 (Note 3) f Basement of masonry house 0.4 0.1 to 0.5 (Note 3) } L h Large' office or industrial building 0.2 0.1 to 0.3 (Notes 3,4) 1 l f Note 1: The ratio of the interior dose to the exterior dose.
- )
( Note 2: A wooden frame house with brick or scono veneer is
! approximately equivalent to.,a masonry house for shielding ; purposes. ; Note 3: This range is mainly due to different wall materials and different geometries.
1
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i Note 4: The shielding factor depends upon where the individuals are located within the building (e.g. , the basement or an inside room). s
' Note 5: Once the plume has passed the area, structures should be f opened and aired to allow any concentration buildup to l dissipate into the environment.
Reference:
WASH-1400, " Reactor Safety Study", Appendix VI, October ( F]'
- 1975.
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; CPSES XSSUE DATE PROCEDURE NO.
j 1 EMERGENCY PLAN MANUAL gy g jgg EPP-304 'i . .l , PROTECTIVE ACTION GUIDES REVISION No. 5 PAGE 16 0F 18 j .y! ATTACHMENT 5 j PAGE 2 0F 2 Inhalation Shielding Factors for a Wood House, .y Snug Doors, Closed Windows
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.i i The above curve assumes the house remains closed up for the duration of the emergency condition. Actually, the dose inside the house can be further
; reduced by opening the doors and windows after the plume cloud has passed 't and purging the house with fresh air.
1
Reference:
WASH-1400, " Reactor Safety Study", Appendix VI, October 1975. Li 4
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s CPSES ISSUE DATE PROCEDURE NO. j EMERGENCY PLAN MANUAL EPP-304 NOV -61984 ,_ 1 1
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5 p. PROTECTIVE ACTION GUIDES REVISION NO. 5 PAGE 17 0F 18 f \ 4 ATTACHMENT 6 PAGE 1 0F 1 - l . I Special Facilities x .j N I e I k 7 *~ g" ,g- $ 1.. j\g'],./;-a.3,,-
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EMERGENCY PLAN MANUAL EPP-304 ,1 1984 s t PRO 1ECTIVE ACTION GUIDES REVISION No. 5 PAGE 18 0F 18'
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,l! i ATTACHMENT 7 PAGE 1 0F 1 l ' i s s Comanche Peak Steam Electric Station j 10 miles EPZ Public Response Areas i s s
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