ML20024B954
| ML20024B954 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 05/23/1983 |
| From: | Krich R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | |
| Shared Package | |
| ML18051A484 | List: |
| References | |
| PROC-830523-01, NUDOCS 8307120044 | |
| Download: ML20024B954 (227) | |
Text
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Proc No EI-4.1
. Revision 4 Date 5/23/83 PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTATION PROCEDURE Revision and Approval Summary TITLE: TECHNICAL SUPPORT CENTER
- 1. Prepared 2. QA Concurrence
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- 5. Approved 6. ATMS Incorporated W Art M l#3 N Plantdang Date JMte-
- 7. Biennial Review Date G
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ei0780-0007f154* 1
PALISADES NUCLEAR PLANT Proc No EI-4.1 EMERGE'CY N IMPLEMENTATION PROCEDURE Revision 4 Page i TITLE: TECHNICAL SUPPORT CENTER ,
Table of Contents Pagg 1.0 PERSONNEL RESPONSIBILITY . . . . . . . . . . . . . . . . . . . . . 1 2.0 PURPOSE . . . . .. . . . . . . . . . . . . . . . . . . . . . . . 1 3.0 INITIAL CONDITIONS AND/OR REQUIREMENTS . . . . . . . . . . . . . . 1 4.0 PROCEDURE . . . . . . . . . . . . . . . . . . . . . . . . . . . . I 4.1 FACILITY DESCRIPTION . . . . . . . . . . . . . . . . . . . . . . . 1 4.2 ACTIVATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 4.3 ORGANIZATION . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 4
4.3.1 Site Emergency Director (SED) . . . . . . . . . . . . . . . . . . 2 4.3.2 Technical Support Group . . . . . . . . . . . . . . . . . . . . . 2 4.3.3 Maintenance Support Group . . . . . . . . . . . . . . . . . . . . 2 i
l 4.3.4 Communications Support Group . . . . . . . . . . . . . . . . . . . 2 4.3.5 Administrative Support Group . . . . . . . . . . . . . . . . . . . 3 4.3.6 Chemistry / Health Physics Support Group . . . . . . . . . . . . . . 3 4.3.7 Operations Support Group . . . . . . . . . . . . . . . . . . . . . 4 4.4 EQUIPMENT . . . ... . . . . .. . . . . . . . . . . . . . . . . 4 4.5 EVACUATION . . . ... . . . . . . . . . . . . . . . . . . . . . . 5 5.0 ATTACHMENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 ATTACHMENTS Attachment 1, " Technical Support Center Floor Plan" Attachment 2, " Technical Support Center Organization and Interfaces" Attachment 3, " Communications Matrix" i
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PALISADES NUCLEAR PLANT Proc No EI-4.1 I EMERGENCY IMPLEMENTATION PROCEDURE Revision 4 Page 1 of 5 TITLE: TECHNICAL SUPPORT CENTER 1.0 PERSONNEL RESPONSIBILITY The Site Emergency Director (SED) shall implement this procedure.
2.0 PURPOSE i
To provide a Technical Support Center (TSC) that will provide the following functions:
- a. Provide Plant management and technical support to' Plant Operations personnel during emergency conditions.
- b. Relieve the Reactor Operators of peripheral duties and communications not directly related to reactor systems manipulations.
- c. Prevent congestion in the Control Room,
- d. Perform EOF functions for the Alert class and for Si e Area Emergency and General Emergency class until the Gene al Office Control Center / Emergency Operations Facility 'is funct nal.
3.0 INITIAL CONDITIONS AND/OR REQUIREMENTS The TSC shall be activated at the Alert or higher emergency classification. The TSC may be activated before this time at the option of the SED.
4.0 PROCEDURE 4.1 FACILITY DESCRIPTION The TSC consists of the area directly outside the Control Room, including the viewing gallery and Shift Supervisor office.
Attachment 1 provides a floor plan of the TSC.
4.2 ACTIVATION Upon sounding the emergency siren, or at the direction of the SED, personnel assigned to the TSC shall proceed to that assembly area and report to the Assembly Area Leader. Personnel accountability shall be performed per EI-12.
4.3 ORGANIZATION TSC organization and interfaces are detailed in Attachment 2. <
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PALISADES NUCLEAR PLANT Proc No EI-4.1 EMERGENCY IMPLEMENTATION PROCEDURE Revision 4 Page 2 of S TITLE: TECHNICAL SUPPORT CENTER 4.3.1 Site Emergency Director (SED)
In addition to the duties listed in EI-1 and EI-2.1, the SED shall direct the TSC, with all TSC support groups listed below and reporting to him.
4.3.2 Technical Support Group
- a. ' The senior member of the Technical Department available in the TSC shall function as the Technical Support Group Leader, reporting to the SED.
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- b. The Technical Support Group shall provide technical assistance to the Plant emergency organization.
- c. The Engineering Support Center (ESC, located outside the TSC) shall report to the Technical Group Leader and assist the Technical Support Group in performing the above mentioned functions.
- d. The General Office Engineering Support Team shall provide support per GOCC/ EOF Emergency Implementing Procedures. ;
4.3.3 Maintenance Support Group
- a. The senior member of the Maintenance Department available in the TSC shall function as the Maintenance Support Group Leader, reporting to the SED.
- b. The Maintenance Support Group shall provide maintenance support to the Plant emergency organization.
shall report to the Maintenance Support Group Leader and assist the Maintenance Support Group in performing the above mentioned functions.
4.3.4 Communications Support Group
- a. The Plant Technical Engineer shall function as the Communications Support Group Leader, reporting to the SED. In the absence of the Technical Engineer, the SED shall assign this task to available ,
TSC personnel.
- b. The Communications Support Group shall coordinate communications in the TSC including all notifications / updates as required per EI-2.1 snd EI-3.
- c. The Communications Support Group shall update TSC status boards as information becomes available.
ei0780-0007a154-89 n- v u
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'l PALhSADES NUCLEAR PLANT Proc No EI-6.1 EMERGENCY IMPLEMENTATION PROCEDURE Revision 4 Page 3 of 5 TITLE: TECHNICAL SUPPORT CENTER
- d. Communications methods, are detailed on Attachment 3.
- e. The General Office Communications Support Team shall provide support per GOCC/ EOF Emergency Implementing Procedures.
Routine notifications / updates should be transferred to the GOCC/ EOF as soon as practicable.
4.3.5 Administrative Support Group
- a. The senior member of the Administrative Department available in the TSC shall function as the Administrative Support Group Leader, reporting to the SED.
- b. The Administrative Support Group Leader shall function as the TSC Public Affairs liaison in the absence of the Plant Public Affairs Director. The TSC Public Affairs liaison shall gather information for the GOCC Public Affairs Department.
- c. The Administrative Support Group Leader shall ensure TSC status boards are updated with information obtained from other TSC support groups. The Administrative Support Group Leader shall also ensure that an Emergency Notification Form (EI-3, Attachment 1) is completed at approximately 15 minute intervals or sooner if conditions warrant. This form shall be forwarded to the Communications Support Group af ter the information has been verified by the Administrative Support Group Leader.
- d. The Administrative Support Group shall provide logistic support to the Plant emergency organization including, but not limited to:
- 1. Copying, typing.
- 2. Supplying food and drink.
- 3. Providing office supplies.
- 4. Obtaining Plant documents.
- e. The Administrative Support Center, (ASC, located outside the TSC) shall report to the Administrative Group Leider and assist the Administrative Group in performing the above mentioned functions,
- f. The General Office Logistics Support Team shall provide support per GOCC/ EOF Emergency Implementing Procedures.
4.3.6 Chemistry / Health Physics Support Group
- a. The senior member of the Chemistry / Health Physics Department available in the TSC shall function as the Chemistry / Health Physics Support Group Leader, reporting to the SED. ,
e10780-0007a154-89
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PALISADES NUCLEAR PLANT Proc No EI-4.1 EMERGENCY IMPLEMENTATION PROCEDURE Revision 4 Page 4 of 5 TITLE: TECHNICAL SUPPORT CENTER
- b. The Chemistry / Health Physics Support Group shall perform the following functions:
- 1. Calculate offsite dose and provide recommendations for offsite protective actions to the SED (Reference EI-6.0).
- 2. Ensure habitability is monitored in onsite assembly areas (References EI-8 and EI-12).
- 3. Ensure onsite and offsite monitoring is performed (Refer-ence EI-8 and EI-9).
- 4. Provide Technical Support to the Plant emergency organization.
- 5. Ensure contaminated personnel are segregated in the Security Building during Accountability and at the evacuation monitoring point during an evacuation. Ensure decontamination is performed as necessary (References EI-14 and HP 2.18).
- 6. Ensure Radiation Safety support for Operations, Maintenance and Chemi stry emergeccy activities.
shall report to the Chemistry / Health Physics Support , Group Laader and assist the Chemistry / Health Physics Support Group in performing the above mentioned functions (Reference EI-4.2).
- d. The General Office Health Physics Support Team shall provide support per GOCC/ EOF Emergency Implementing Procedure.
4.3.7 Operations Support Group
- a. The senior member of the Operations Department available in the TSC shall function as the Operational Support Group Leader.
- b. The Operations Support Group shall have administrative control of and provide technical support for the Control Room staff.
- c. In the event close support is needed for the Control Room staff, members of the Operations Support Group may function in the Shift Supervisor's office or Control Foom.
NOTE: Access to the Control Room shall be limited to essential personnel to prevent overcrowding, confusion and high noise levels.
4.4 EQUIPMENT TSC Emergency Equipment shall be as described in EI-16,1.
ei0780-0007a154-89
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1 PALISADES NUCLEAR PLANT Proc No EI-4.1 l EMERGENCY IMPLEMENTATION PROCEDURE Revision 4 Page 5 of 5 TITLE: TECHNICAL SUPPORT CENTER l
4.5 EVACUATION
- a. If airborne contamination levels warrant (greater than 20% MPC) or radiation levels exceed 100 mrem /hr, the SED shall consider evacuation, relocation or use of protective measure (including respiratory protection or thyroid blocking agent).
- b. Relocation or evacuation should be initiated only if adequate support for the Control Room can be maintained (eg, by the General Office Control Center / Emergency Operational Facility), or personnel are likely to exceed CPCo administrative dose limits.
Reference HP 1.0, " Health Physics Policy" for normal dose limits or EI-14, " Radiological Medical Care For Emergency Dose Limits"
- c. Evacuation / relocation shall require the concurrence of the SED.
The evacuation / relocation should be announced over the Public Address System.
5.0 ATTACHMENTS 5.1 Attachment 1, " Technical Support Center Floor Plan" 5.2 Attachment 2, " Technical Support Center Organization and Interfaces"
, 5.3 Attachment 3, " Communications Matrix" e
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Proc No EI-4.1
.'.ttachment 2 Revision 4 '
Page 1 of 1 TECHNICAL SUPPORT CENTER ORGANIZATION AND INTERFACES Site Emergency Director i (SEP)
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Operations Technical Maintenance Chemistry / Health Communications Administrative >
l Support Support Support Physics Support Support Support l Group Group Group Group Group Group
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j j Engineering Maintenance Operational Administrative Plant Support
- Crntrol Support Support Support Support Groups Center Center Room Center Center (ESC) (MSC) (OSC) (ASC)
, Conf Rm #3&4 Main Locker Rm Lunchroom Doc Control Lunchroom ONSITE 0FFSITE
- Engineering Health Physics Communications Logistics Support Support Support Support Public Affairs Team Team Team Team
- 1 eio780-0007c154-89 General Office Central Center /
Emergency Operations Facility e
. 4 Proc No EI-4.1 Communic'ations Matrix Attachment 3 Revision 4 l Page 1 of 1 )
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EOC Michigan State A2,B A*,B B B A*,B B B ---
Police NRC A*,B A*,B B B A*,B B ---
Offsite Power A*,B A*,B B B B
,f Controller Emergency A*,B, A*,B, B,C, A*,B E.F,H*
Operations C,D C,D D*
Facility General Office A*,B A*,B B E Control Center Operational B,C* A*,B, E Support Center D C D,Ft Technical B,C*,
Support Center E,F,G E'G*
Control Room E A = Dedicated telephones B = Co==ercial telephones C = Intraplant telephones D = Radio E = Face-to-face F = Intercom G = Sound powered telephon'es H = PA System I -
i e10780-0007d-93 * = Preferred method l
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! Proc No EI-3 Revision 5 Date 5/23/83 PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTATION PROCEDURs Revision and Approval Summary ,
TITLE: COMMUNICATIONS AND NOTIFICATIONS
- 1. Prepared 2. QA Concurrence f $ Nb ri'~~ator 'Date Date Ogon5
- 3. Recommend royal /Q-List e No ' 4. PRC Reviewed D
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. 5. Approved 6. ATMS Incorporated -
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- 7. Biennial Review Date l
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, eil180-0007g154*
k PALISADES NUCLEAR PLANT Proc No EI-3 l EMERGENCY IMPLEMENTATION PROCEDURE Revision 5 Page i TITLE: COMMUNICATIONS AND NOTIFICATIONS Table of Contents i
Page 1.0 PERSONNEL RESPONSIBILITY . . . . . . . . . . . . . . . . . . . . . 1 2.0 PURPOSE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I 3.0 INITIAL CONDITIONS AND/OR REQUIREMINTS . . . . . . . . . . . . . . I 4.0 COMMUNICATIONS AND NOTIFICATIONS . . . . . . . . . . . . . . . . . I 4.1 ONSITE NOTIFICATIONS . . . . . . . . . . . . . . . . . . . . . . . I 4.2 0FFSITE NOTIFICATIONS . . . . . . . . . . . . . . . . . . . . . . I 4.2.1 Power Controller /Generai Office Control Center / Emergency Operations Facility, State, County and NRC . . . . . . . . . . . . 1 4.2.2 Hospital Notification . . . . . . . . . . . . . . . . . . . . . . 2 4.2.3 Message Authentication . . . . . . . . . . . . . . . . . . . . . . 2 5.0 ATTACHMENTS . . . . . .....................2 ATTACHhENTS Attachment 1, " Emergency Notification Form" Attachment 2, " Hospital Notification Form" Attachment 3, " Communications Matrix" Attachment 4, " Emergency Call List" I .
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. 4 Ph'LISADESNUCLEARPLANT Proc No EI-3 EMERGE}ici IMPLEMENTATION PROCEDITRE Revision 5 Page 1 of 2 TITLE: COMMUNICATIONS AND NOTIFICATIONS 1.0 PERSONNEL RESPONSIBILITY
- a. The Site Emergency Director (SED) shall assure offsite notifications are performed per EI-2.1 and onsite notifications are performed per this procedure.
- b. Upon activation of the Technical Support Center (TSC), the Communicator (described in EI-4.1) shall perform the notifications requiring regular updates, . including Power Controller / General Office Control Center / Emergency Operations Facility, State, County and Nuclear Regulatory Commission. Prior to activation of the TSO, the SED shall delegate this function.
2.0 PURPOSE To provide for emergency cor.munications to onsite personnel and offsite agencies.
3.0 INITIAL CONDITIONS AND/OR REQUIREMENTS a.
Initial notification shall be made at Unusual Event. Followup notification shall be made as conditions warrant or the emergency escalates.
- b. Alert and above followup notifications shall be made at approximately 15 minute intervals.
4.0 COMMUNICATIONS AND NOTIFICATIONS 4.1 ONSITE NOTIFICATIONS
- a. The emergency siren shall be sounded at the Alert, Site Area Emergency or General Emergency.
- b. The emergency siren shall be a continuous two minute blast.
- c. The Plant Public Address System shall be used to notify Plant personnel of the location and nature of the emergency.
- d. Additional information shall be provided to Plant personnel over the Public Address System as conditions warrant or the emergency escalates.
4.2 0FFSITE NOTIFICATIONS 4.2.1 Power Controller / General Office Control Center / Emergency Operations Facility, State, County and NRC
- a. The Communicator shall use Attachment I to provide. notification to above listed agencies as required in Initial Conditions and/or Require =ents.
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Pf%ISADESNUCLEARPLANT Proc No EI-3 EMERGENCP IMPLEMENTATION PROCEDURE Revision 5 Page 2 of 2 TITLE: COMMUNICATIONS AND NOTIFICATIONS
- b. Information to complete Attachment 1 may be obtained from TSC Status Boards.
- c. Notifications to the State, County and NRC should be turned over to the General Office Control Center or Emergency Operations Facility as soon as possible.
- d. A final call sho'uld be made to all agencies before notification turn over is completed to clearly establish the new point of contact.
4.2.2 Hospital Notification Notification of hospitals receiving contaminated injured victims should be performed using Attachment 2, " Hospital Notification Form".
4.2.3 Message Authentication
- a. In the event commercial telephones are used to send,or receive emergency notifications, the following method may be used to ensure the authenticity of a message.
s b. Message authentication should be performed in the following cases:
- 1. The validity of the message is in doubt.
- 2. The identity of the caller is in doubt.
- 3. The message requires extreme or unusual action (for example, public evacuation).
- 4. At the option of the SED, Communicator, or offsite. contact.
c.
Message authentication by the Palisades Staff shall be perfor'med by informing the offsite caller that you will return the call.
Return the call using the telephone number listed in EI-2.1 or EI-3. Re-establish contact with the original caller.
- d. Message authentication by offsite organizations shall be performed at their request. Request that the organization return the call using the Palisades Plant telephone number listed in their emergency plan, procedure or call list. After contact is re-established, re-transmit the message.
5.0 ATTACHMENTS
- a. Attachment 1, " Emergency Notification Form"
- b. Attachment 2, " Hospital Notification Form" ,
- c. Attachment 3, " Communications Matrix"
- d. Attachment 4, " Emergency Call List"
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Proc No EI-3 Attachment 1 Revision 5 Page 1 of 3 EMERGENCY NOTIFICATION FORM
- 1. NAME/ TITLE / TELEPHONE # PLANT COMMUNICATOR:
- 2. LOCATION - PALISADES PLANT A. Message # Date: Time:
B. Control Room C. Technical Support Center
- 3. THIS IS IS NOT A DRILL OR EXERCISE (CRECK ONE)
- 4. CLASS OF EMERGENCY (check one)
A. Time declared D. Site Area B. Unusual Event E. General C. Alert
- 5. DESCRIPTION OF EVENT; CHANGE OF STATUS:
- 6. PROGNOSIS (CHECK ONE)
A. Stable C. De-Escalating B. Escalating D. Terminating
- 7. PLANT EMERGENCY RESPONSE ACTIONS UNDERWAY (CHECK)
A. Offsite assistance previously requested: Yes No B. Fire D. Ambulance
- C. Police E. Hospital F. Other G. Site Evacuation
- Yes No Limited l
H. Onsite Monitoring Teams Dispatched: Yes No 1
I. Offsite Monitoring Teams Dispatched: Yes No i
i eil180-0007b-154-89 a
Proc No EI-3 Attachment 1 Revision 5 Page 2 of 3 EMERGENCY NOTIFICATION FORM
- 8. RADIOLOGICAL RELEASE DATA A. Potential for release: Yes No B. Actual Release: Yes No C. Time of Release D. Airborne E. Waterborne F. Surface Spill G. Potential Release Duration, hours (estimated)
- 9. METEOROLOGICAL DATA A. Stability Class Based on AT (*C) aZ(m) or Sigma Theta (degrees)
B. Wind Speed, mph C. Wind Direction, degrees (from)
D. Downwind Sector:
- 10. OFFSITE DOSE RADIOLOGICAL RELEASE DATA A. Estimated Measured (check one)
B. Effluent Point:
C. Noble Gas Release Rate, Ci/See:
D. Average Energency per Disintegration, E, MeV:
E. Equivalent I-131 Release Rate, Ci/sec:
F. Potential Release Duration, hours:
- 11. CALCULATED OFFSITE DOSE Site Boundary A. Distance, miles .5 2 5 10 B. Whole Body Gamma Dose Rate, rem /hr C. Whole Body Gamma Dose, rem D. Child Thyroid Dose i Rate, rem /hr E. Child Thyroid Dose, i
i rem l
F. Additional Data:
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Proc No EI-3 Attachment 1 Revision 5 Page 3 of 3 EMERGENCY NOTIFICATION FORM
- 12. PROTECTIVE ACTION RECOMMENDATIONS Sector (s) Miles t A. None B. Sheltering C. Precautionary Evacuation D. Evacuation E. Contamination Control
- F. Food Water G.
H. Milk 4
I. Other
- 13. REMARKS / ADDITIONAL INFORMATION:
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- 14. THIS IS IS NOT A DRILL / EXERCISE (CHECK ONE) s i
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Proc No EI-3 Attachment 2 Revision 5 Page' 1 of I HOSPITAL NOTIFICATION FOR[_I
- 1. Communicator A. Name:
B.
Title:
C. Telephone Number:
- 2. Location: Palisades Plant
- 3. Number of vicuims:
- 4. Method of transport:
Estimated time of arrival:
- 5. Extent of injuries:
- 6. First aid and/or decontamination procedures initiated:
- 7. Contamination levels:
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Proc No EI-3 Communications Matrix Attachment 3 Revision 5 Page 1 of 1 E
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EOC Michigan State A*,B A*,B B A*,B B B B ---
Police NRC A*,B B B A*,B B ---
Offsite A*,Bl Power A*,3 A*,B B B B ---
Controller Emergency A*,B, A*,B, B,C, A*,B E,F,H*
Operations C,D C,D D*
Facility General Office A*,B A*,B B E Control Center Operational B,C*, A*,B, E Support Center D C,D.F Technical B,C*,
Support Center E,F,G E.G*
Control Room E A = Dedicated telephones B = Commercial telephones C = Intraplant telephones D = Radio E = Face-to-face F = Intercom
. G = Sound powered telephon'es l H = PA System i * = Preferred method l
eil180-0007d-93
t Proc No EI-3 Attachment 4 4 Revision 5
, Page 1 of 1 EMERGENCY CALL LIST Medical Memorial Hospital, St Joseph Mercy Hospital, Benton Harbor South Haven Community Hospital Dale K Morgan, MD, South Haven David B Witte, MD, South Haven .
Local Resoonse City of South Haven Board of Public Utilities State Response Michigan State Police Emergency Services Division, Lansing Michigan State Water Resources Commission Indiana Civil Defense Indiana State Police Federal Response Department of Energy
, Radiological Assistance Program Insurers American Nuclear Insurers Nuclear Mutual Limited .
Insurers k
, . Technical Support
' Institute of Nuclear Power Operations -
t REMS-c Radiation Emergency Management i. .- 7 u - .A. S + < . . 3:
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, eill80-0007e-154-89 l
4 Proc No EI-5 Revision 1 Date 5/23/33 PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTATION PROCEDURE Revision and Approval Summary TITLE: REENTRY / RECOVERY
- 1. Prepared 2. QA Concurrence
$OriginatcF G 0Y T-/9-73 Date A/* / Ze< vin d Date
- 3. Recommend Approval /Q-List h No 4. PRC Reviewed l} ..* i
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Y 10 Auw w uem .S ~ M @ N"'/lblt4[I $ !?N5 Department Head Date '
' Da te GO'/ lt '63 ^6fC
- 5. Approved ' 6. ATMS Incorporated w k s11a in 5/23k7
' Plant Manager Date
/ JVate' I
i
! 7. Biennial Review l
l Date ~
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ei1180-0003e-154-89
PALISADES NUCLEAR PLANT Proc No EI-5 EMERGENCY IMPLEMENTATION PROCEDURE Revision 1 Page i TITLE: REENTRY / RECOVERY Table of Contents PalLe 1.0 PURPOSE
. . . . . . . . . .. . ... . . . . . .. .. . . . . . I 2.0 INITIAL CONDITIONS AND/OR REQUIREMENTS . . . . . . .. .. . . . . 1 3.0 PROCEDURE . . . . . . . . .. ... . .. . .. .. . . . . . . . 1 3.1 GUIDELINES FOR INITIATING REENTRY PHASE . . . . .. . . . . .. . 1 i
3.2 RECOVERY . . . . . . . . . . . ... . . . ... . .. .. . . . . 2 3.3 LONG-TERM RECOVERY ORGANIZATION GUIDELINES . . . .. .. ..... 4 4.0 ATTACHMENTS . . . . . . . . . . .. . . . . . . . . .. . . . . . 5 A_TTACHMENTS Attachment 1, Record of Major Actions Performed Attachment 2, Record of Major Actions Performed, Continuation Page 1
4 ei1180-0003d154-89
_ - - _ _ _ __. _ . ,, ~ - - - - - . . . . . _ . . - _ .,
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PALISADES NUCLEAR PLANT Proc No EI-5 EMERGENCY IMPLEMENTATION PROCEDURE Revision 1 Page 1 of 8 TITLE: REENTRY / RECOVERY 1.0 PURPOSE To provide guidelines for reentry / recovery of the plant following im-plementation of Site Emergency Plan. Specific actions are dependent on circumstances.
2.0 INITIAL CONDITIONS AND/OR REQUIREMENTS 2.1 Specific reentry / recovery procedures are prepared by Technical Support Center staff at the direction of the Site Emergency Director or by the EOF staff at the direction of the Ekmergency Officer. ,
2.2 All reentry / recovery acticus will be deliberate and preplanned using personnel whose experience and expertise are best suited to the required actions.
2.3 Radiation exposure of personnel involved in reentry / recovery shall be as low as reasonably achievable. Limits imposed may be dependent upon specific circumstances and risk versus benefit. In any case, radia-tion exposure should be controlled within the limits of Administrative Procedure 7.04.
2.4 A log should be maintained of important actions and persons performing the actions, using Attachments 1 and 2 to this procedure.
2.5 Personnel responsible:
2.5.1 Site Emergency Director or Emergency Officer is responsible for escalating, downgrading or terminating the cmergency. .
eil180-0003a154-89
1 PALISADES NUCLEAR PLANT Proc No EI-5 EFERGENCY IMPLEtIENTATION PROCEDURE Revision 1 Page 2 of 8 TITLE: REENTRY / RECOVERY 2.5.2 Technical Support Center staff or EOF staff is responsible for providing reentry / recovery procedures.
3.0 PROCEDURE 3.1 GUIDELINES FOR INITIATING REENTRY PHASE 1
3.1.1 When initiating the reentry phase the plant should be in a stable condition assessed by the Site Emergency Director. '
3.1.2 Prior to aathorizing reentry, determine the following:
- a. Plant areas potentially affected by radiation / contamination from 4
radiation surveillance data.
- b. That adequate radiation survey instrumentation is available.
- c. Radiation exposures of personnel expected to participate in reentry.
3.1.3 Prepida survey team activities to include:
- a. Areas to be surveyed
- b. Anticipated radiation and contamination levels i
l
- c. Radiation survey equipment l
- d. Shielding availability
- e. Protective clothing and equipment required .
- f. Access control procedures -
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PALISADES NUCLEAR PLANT Proc No EI-5 EMERGENCY IMPLEMENTATION PROCEDURE Revision 1 Page 3 of 8 TITLE: REENTRY / RECOVERY
- g. Exposure limits and dosimetry requirements
- h. Decontamination requirements
- i. Communications required 3.1.4 Designate a reentry team consisting of the following as required:
- a. Operations personnel (1)
- b. Chemistry / Health Physics personnel (1)
- c. Maintenance personnel (1)
~
- d. Engineering / Supervisory personnel (1) 3.1.5 Reentry into areas should encompass the following goals (in order of priority):
- a. Determination of initial required recovery operations.
- b. Visual observations of hazards or potential hazards associated with recovery operations.
- c. Conduct radiation survey of plant areas and define radiological problem areas.
- d. Isolate and post plant radiation areas, high radiation areas and contaninated areas.
ei1180-0003a154-89
-7
PALISADES NUCLEAR PLANT Proc No EI-5 EMERGENCY IMPLEMENTATION PROCEDURE Revision 1 Page 4 of 8 TITLE: REENTRY / RECOVERY 3.1.6 After reentry team procedures are complete, assess the data, determine the extent of recovery operation required and initiate Section 3.2 -
Recovery.
3.2 RECOVERY Recovery will occur in three phases.
3.2.1 When recovery is to commence, the Site Emergency Director or Emergency Officer is responsible for notification of offsite organizations (ie, NRC, Consumers Power Company, Van Buren and Berrien Counties, State of Michigan, etc).
3.2.2 Phase 1 recovery operations:
- a. Designate applicable recovery teams to perform the following:
- 1. Assessment of equipment damage
- 2. Installation of shielding
- 3. Posting of controlled areas
- 4. Application of clearance tags L
- 5. Decontamination and cleanup necessary to place plant in an l acceptable long-term condition.
l b. Evaluate all results from Phase 1 recovery operations and l
determine areas affected by the emergency. Do not initiste ei1180-0003a154-89
.e
- PALISADES NUCLEAR PLANT Proc No EI-5 EMERGENCY IMPLEMENTATION PROCEDURE Revision 1 Page 5 of 8 TITLE: REENTRY / RECOVERY Phase 2 recovery operations until Phase 1 has been completed and has clearly defined affected areas of the plant.
3.2.3 Phase 2 recovery operations:
I
- a. Designate applicable recovery teams to perform the following:
- 1. Detailed investigation into the accident causes and consequences to the plant and the environment.
- 2. Evaluate work required to repair / modify plant equipment or operating procedures.
- 3. Make necessary repairs / modifications as authorized.
, 4. Develop and institute testing procedures to determine fitness of plant components and systems for return to service.
- b. Phase 3 may be initiated at the completion of Phase 2 operations or upon termination of the emergency, whichever occurs sooner.
3.2.4 Phase 3 recovery operations:
Develop a report to be forwarded to Consumers Power Company management to inform them of the extent of recovery operations which will be required following termination of the emergency. Management will form a long-term recovery organization in accordance with Section 3.3 of this procedure.
i ei1180-0003al54-89 l
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PALISADES NUCLEAR PLANT Proc No EI-5 i
EMERGENCY IMPLEMENTATION PROCEDURE Revision 1 Page 6 of 8 TITLE: REENTRY / REC 0VERY 3.3 LONG-TERM RECOVERY ORGANIZATION GUIDELINES 3.3.1 Upon termination of the emergency, at the discretion of management and the Site Emergency Director, a long-term recovery organization will be set and may consist of at least the following:
- a. Recovery Operations Manager
- b. Technical Working Group
- c. Task Management / Scheduling Group
- d. Technical Support Group
- e. Plant Operations / Maintenance Group
- f. Waste Management Group
- g. Plant Modifications Group
- h. Industrial Advisory Group ,
- i. Public/ Government Affairs Group
- j. Administration and Logistics Group 74 Chemistry / Health Physics Support Group The structure of the long-term recovery organization is dependent on the nature of the accident and the situation af ter the accident.
! 3.3.2 The Recovery Operations Manager may be the Plant Manager and will be responsible for recovery activities including technical decisions -
ei1180-0003a154-89
O O PALISADES NUCLEAR PLANT Proc No EI-5 EMERGENCY IMPLEMENTATION PROCEDURE Revision 1 Page 7 of 8 TITLE: REENTRY / RECOVERY
>$out courses of action. He will coordinate the functional activities of the various groups.
3.3.3 The Technical Working Group will propose and evaluate course of action and address other major t'echnical aspects of the recovery operations.
It will include the heads of the various Palisades technical groups in the recovery organization as well as outside vendors, Architect-Engineers, NRC experts and others as appropriate.
3.3.4 The Task Management / Scheduling Group will consist of persons desig-nated by the Recovery Operations Manager and will identify and plan tasks and monitor and coordinate tasks in progress.
3.3.5 The Technical Support Group will provide engineering analysis support, procedures development, data analysis, technical support to the Control Room and other technical tasks as required.
3.3.6 The Plant Operations / Maintenance Group will be responsible for plant operations and maintenance and all other routine activities in and around the plant.
3.3.7 The Waste Management Group is responsible for proper management of waste processing and disposal, including onsite decontamination of facilities contaminated during the emergency.
3.3.8 The Plant Modifications Group is responsible for providing engineer-ing, design, materials and construction necessary for any required modifications to plant systems, components or structures.
l l
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l ei1180-0003a154-89 l
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PALISADES NUCLEAR PLANT Proc No EI-5 EliERGENCY IMPLEMENTATION PROCEDURE Revision 1 Page 8 of 8 TITLE: REENTRY / RECOVERY 3.3.9 The Industry Advisory Group will be staffed by experts from outside
! Consumers Power Company to augment the technical abilities of the long-term recovery organization and provide independent technical assessment based on experience rather than engineering analysis.
l 3.3.10 The Public/ Government Affairs Group will coordinate the exchange of information with public and government agencies regarding recovery operaticas. Legal council will also be part of this organization.
3.3.11 The Administration and Logistics Group will provide general services such as manpower, communications, transportation and temporary office space as required.
3.3.12 The Chemistry / Health Physics Group will provide chemical analysis servicds and health physics support such as dose assessment, isotope identification, job coverage and ALARA planning as' required.
4.0 ATTACHMENTS 4.1 Attachment 1, Record of Major Actions Performed 4.2 Attachment 2, Record of Major Actions Performed, Continuation Page 1
4
~
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. o s Proc No EI-5 Attachment 1 Revision 1 Page 1 of 1 RECORD OF MAJOR ACTIONS PERFORMED Date/ Time of Emergency:
Date/ Time Recovery Action Accomplished By Reviewed By 1
ei1180-0003bl54-89
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- 1 Attachment 2 l Revision-1 Page 1 of 1 RECORD OF PfAJOR ACTIONS PERFORMED (Continuation Page)
Date/ Time Recovery Action Accomplished By Reviewed By 4
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Proc No EI 4.3 Reeision 0 Date 5/23/81 PALISADES NUCLEAR PIANT EMERGENCY IMPLEMENTATION PROCEDURE {
Revision and Approval Summary TITLE: GENERAL OFFICE CONTROL CENTER /
EMERGENCY OPERATIONS FACILITY ACTIVATION
- 1. Prepared 2. QA Concurrence 9
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'Date Date
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- 3. Reco n Approval /Q-List No 4. PRC Reviewed NVbriba D ar mhnt Head 6l18)?3
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- 5. Approved . 6. ATMS Incorporated eIw 6'fs, /u PJ3-0 I
Plant Manage Date ~ Date
- 7. Biennial Review Date
( eiO583-0011f154 l
PALISADES NUCLEAR PLANT Proc ho EI 4.3 EMERGENCY IMPLEMENTATION PROCEDURE Revision 4 Page i TITLE: GENERAL OFFICE CONTROL CENTER /
EMERGENCY OPERATIONS FACILITY ACTIVATION Table of Contents Pj!.ge 1.0 PERSONNEL RESPONSIBILITIES . . . . . . . . . . . . . . . . . . .. I 2.0 PURPOSE . . . .. . . . . . . . . . . . . . . . . . . . . . . .. 1 3.0 INITIAL CONDITIONS AND/OR REQUIREMENTS . . . . . . . . . . . . .. 1 4.0 ACTIVATION OF THE EMERGENCY OPERATIONS FACILITY . . . . . . . .. 1 4.1. FACILITY DESCRIPTION . . . . . . . . . . . . . . . . . . . . . .. 1 4.2 ACTIVATION . . . . .. . . . . . . . . . . . . . . . . . . . . . . 1 4.3 ORGANIZATION . .. . . . . . . . . . . . . . . . . . . . . . . .. 2 4.4 COMMUNICATION .. ... . . . . . . . . . . . . . . . . . . . .. 2 4.5 EQUIPMENT . .. ..... . . . . . . . . . . . . . . . . . . .. 2 4.6 EVACUATION . . . .... . . . . . . . . . . . . . . . . . . . .. 2 S.0 ATTACHMENTS . . . ,. . . . . . . . . . . . . . . . . . . . . .. 2 Attachments Attachment 1, " Emergency Operations Facility Floor Plan" Attachment 2, " Communications Matrix Attachment 3, " Palisades Nuclear Plant Emergency Operating Facility Location Map" s .
eiO583-0011e154
PALISADES NUCLEAR PLANT Proc No EI 4.3 EMERGENCY IMPLEMENTATION PROCEDURE Revision 4 Page 1 of 2 TITLE: GENERAL OFFICE CONTROL CENTER /
EMERGENCY OPERATIONS FACILITY ACTIVATION 1.0 PERSONNEL RESPONSIBILITIES The Site Emergency Director (SED) shall implement this procedure.
2.0 PURPOSE To provide a means of activating the Emergency Operations Facility (EOF) in preparation for staffing by General Office personnel. Also, to provide interface capabilities with the General Office Control Center.
3.0 INITIAL CONDITIONS AND/OR REQUIREMENTS
- a. The EOF shall be activated at the Site Area Emergency classification or above. The EOF may be activated before this time at the option of the SED, or at the request of the General Office Con:rol Center Director.
- b. The General Office Control Center shall function as the EOF until such time the EOF is adequately manned.
4.0 ACTIVATION OF THE EMERGENCY OPERATIONS FACILITY 4.1 FACILITY DESCRIPTION
- a. The EOF consists of the South Haven Conference Center with headquarters located in the conference building. Refer to Attachment 1 for a floor plan.
- b. Additional buildings are available to support lodging and food se rvices .
c.
i The EOF location is detailed on Attachment 3.
4.2 ACTIVATION
- a. The SED shall dispatch plant personnel generally Chemistry / Health Physics personnel from the Operational Support Center) to the EOF.
l b. Plant personnel should perform habitability monitoring during activation of the EOF until this function can be transfered to GO personnel.
- c. Plant personnel should arrange the facility in accordance with i
i Attachment 1.
l
- eiO583-0011a154 l
PALISADES NUCLEAR PLANT Proc No EI 4.3 EMERGENCY IMPLEMENTATION PROCEDURE Revision 4 Page 2 of 2 TITLE: GENERAL OFFICE CONTROL CENTER /
EMERGENCY OPERATIONS FACILITY ACTIVATION 4.3 ORGANIZATION 1
The EOF organization shall be as described in the G0CC/ EOF Emergency Implementation Procedures.
4.4 COMMUNICATION Communications methods and alternates are identified on Attachment 2.
4.5 EQUIPMENT EOF equipment shall be as described in EI-16.1.
4.6 EVACUATION a.
If airborne contamination levels warrant (>20% MPC) or radiation levels exceed 100 mrem /hr the EOF Director shall consider evacuation / relocation, or use of protective measures (including respiratory protection of thyroid blocking agent).
- b. Before full staffing the plant personnel should perform habitability monitoring to ensure these levels are not exceeded.
5.0- ATTACHMENTS 5.1 Attachment 1, " Emergency Operations Facility Floor Plan" 7.2 Attachment 2, " Communications Matrix" 7.3 Attachment 3, " Palisades Nuclear Plant / Emergency Operating Facility Location Map" '
l v
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Offsite -
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Controller Emergency A*,B, A*,B, Operations B,C, A*.B E,F H*
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Facility General Office A*,B A*,B B E Control Center Operational B,C*, A*,B, E Support Center D C.D,F Technical B,C*,
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- B = Commercial telephones C = Intraplant telephones D = Radio E = Face-to-face F = Intercom G = Sound powered telephones H = PA System eiO583-0011c-93-154 * = Preferred method
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Proc No EI-4.3 PALISADES NUCLEAR PLANT /DiERGENCY Attachment 3 OPERATIONS FACILITY LOCATION MAP To Holland Rc sion 0 C South Haven Conference Center (i u Emergency Operations Facility (EOF) 109th Ave T
/
N Shore Dr m
South Haven ,_, Phoenix Rd D
CR 380 ss To Bangor &
Palisades Kalamazoo Nuclear Plant [
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T Lake flichigan College Community Center
~ St Joseph /
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Exit 30 Napier Ave -
siO583-0011d-93-154 9
Proc No EI 4.3 Revision h Date 5/23/83 PALISADES NUCLEAR PLANT EFERGENCY IMPLEMENTATION PROCEDURE Revision and Approval Summary TITLE: GENERAL OFFICE CONTROL CENTER /
EMERGENCY OPERATIONS FACILITY ACTIVATION
- 1. Prepared 2. QA Concurrence
/ I D 0 h/b a ' Date Date
- 3. Reconunen pproval/Q-List No 4. PRC Reviewed N0/Y}llL at mhnt Head 6/g)?3
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- 5. Approved .
- 6. ATMS Incorporated '
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& kk Date ~
l{_f ["O 5 N Date
- 7. Biennial Review Date i
eiO583-0011f154
PALISADES NUCLEAR PLANT Proc No EI 4.3 EMERCENCY IMPLEMENTATION PROCEDURE Revision 4 Page i TITLE: GENERAL OFFICE CONTROL CENTER /
EMERGENCY OPERATIONS FACILITY ACTIVATION Table of Contents Pagp 1.0 PERSONNEL RESPONSIBILITIES . . . . . . . . . . . . . . . . . . .. 1 2.0 PURPOSE ... . ... . . . . . . . . . . . . . . . . . . . . .. 1 3.0 INITIAL CONDITIONS AND/OR REQUIREMENTS . . . . . . . . . . . . .. 1 4.0 ACTIVATION OF THE EMERGENCY OPERATIONS FACILITY . . . . . . . .. 1 4.1 FACILITY DESCRIPTION . . . . . . . . . . . . . . . . . . . . . .. 1 J
4.2 ACTIVATION . . . ..... . . . . . . . . . . . . . . . . . . .. 1 4.3 ORGANIZATION . . ...... . . . . . . . . . . . . . . . . . .. 2 4.4 COMMUNICATION . .... . . . . . . . . . . . . . . . . . . . .. 2 4.5 EQUIPMENT .. . ... . . . . . . . . . . . . . . . . . . . . .. 2 4.6 EVACUATION . . .
............ . . . . . . . . . . . .. 2 5.0 ATTACHMENTS . . .... . . . . . . . . . . . . . . . . . . .. 2 Attach'ents m
Attachment 1, " Emergency Operations Facility Floor Plan" Attachment 2, " Communications Matrix" Attachment 3, " Palisades Nuclear Plant Emergency Operating Facility Location Map" i
1 l
l eiO583-0011e154 I
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PALISADES NUCLEAR PLANT Proc No EI 4.3 <
- EMERGENCY IMPLEMENTATION PROCEDURE Revision 4 Page 1 of 2 TITLE: GENERAL OFFICE CONTROL CENTER /
EMERGENCY OPERATIONS FACILITY ACTIVATION 1.0 PERSONNEL RESPONSIBILITIES The Site Emergency Director (SED) shall implement this procedure.
t 2.0 PURPOSE To provide a means of activating the Emergency Operations Facility (EOF) in preparation for staffing by General Office personnel. Also, to provide interface capabilities with the General Office Control Center.
3.0 INITIAL CONDITIONS AND/OR REQUIREMENTS
- a. The EOF shall be activated at the Site Area Emergency classification or above. The EOF may be activated before this time at, the option of the SED, or at the request of the General Office Control Center Director.
- b. The General Office Control Center shall function as the EOF until such time the EOF is adequately manned.
4.0 ACTIVATION OF THE EMERGENCY OPERATIONS FACILITY 4.1 FACILITY DESCRIPTION
- a. The EOF consists of the South Haven Conference Center with headquarters located in the conference building. Refer to Attachment 1 for a floor plan.
- b. Ad,ditional buildings are available to support lodging and food .
services.
- c. The EOF location is detailed on Attachment 3.
4.2 ACTIVATION
- a. The SED shall dispatch plant personnel generally Chemistry / Health l
Physics personnel from the Operational Support Center) to the EOF.
- b. Plant personnel should perform habitability monitoring during activation of the EOF until thia function can be transfered to GO personnel.
l c. Plant personnel should arrange the facility in accordance with l
l Attachment 1.
I i
eiO583-0011a154
. - . - ,_ - .- . ~ - . . - - - . . . - - -
PALISADES NUCLEAR PLANT Proc No EI 4.3 EMERGENCY IMPLEMENTATION PROCEDURE Revision 4 Page 2 of 2 TITLE: GENERAL OFFICE CONTROL CENTER /
EMERGENCY OPERATIONS FACILITY ACTIVATION 4.3 ORGANIZATION The EOF organization shall be as described in the GOCC/E0F Emergency Implementation Procedures.
4 4.4 COMMUNICATION Communications methods and alternates are identified on Attachment 2.
4.5 EQUIPMENT EOF equipment shall be as described in EI-16.1.
4.6 EVACUATION
- a. If airborne contamination levels warrant (>20% MPC) or radiation levels exceed 100 mrem /hr the EOF Director shall consider evacuation / relocation, or use of protective measures (including respiratory protection of thyroid blocking agent).
- b. Before full staffing the plant personnel should perform habitability monitoring to, ensure these levels are not exceeded.
5.0 ATTACHMEh'_TS 5.1 Attachment 1, " Emergency Operations Facility Floor Plan" 7.2
. Attachment 2, " Communications Matrix" 7.3 Attachment 3, " Palisades Nuclear Plant / Emergency Operating Facility i Location Map" i
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Proc No EI-4.3 Communications Matrix Attachment 2
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Offsite Power A*,B A*,B B B B ---
Controller Emergency A*,B, A*,B, B,C, A*,B E,F H*
Operations C.D C.D D*
Facility General Office A*,B A*,B B E Control Center Operational B.C* A*,B, E Support Center D C.D.F - . -.
Technical B,C*,
Support Center E.F,G E.G*
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B = Commercial telephones C = Intraplant telephones D = Radio E = Face-to-face F = Intercom .
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^ "C s PALISADES NUCLEAR PLANT /D1ERGENCY To Holland Re '*"f 3
OPERATIONS FACILITY LOCATION MAP , s(o South Haven Conference Center O C Emergency Operations Facility (EOF) 109th Ave ni tt Shore Dr
-r-SouthHaven/- , Phoenix Rd
+V, CR 380 Palisades k To Bangor &
Kalamazoo Nuclear Plant .
CR 378
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Covert h "
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- Hagar Shore Rd
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Coloma Watervliet To Kalamazoo
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~ @M g<,. " Exit 34 Benton / B1 I-94 Harbor /
- ~
Lake Michigan College Community Center
"' Joseph y Joint Public Information Center (JPIC)
Exit 30 flapier Ave ~
To Chicago -
siO583-0011d-93-154
--n- - - - ----_---,----------__---------------_--._-----,___J
t l
Proc No EI-2.1 Revision 9 Date 5/23/83 PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTATION PROCEDURE i
Revision and Approval Summary l l
1 TITLE: EMERGENCY ACTIONS / NOTIFICATIONS / RESPONSIBILITIES
- 1. Prepared 2. QA Concurrence 9
) / l $b
'D' ate Date
//O'r WpnatorRA rkw4
- 3. deco 4.
ndgproval/Q-List No PRC Keviewed D
/ hltAL $ik rts nt Head 'Date Miwi g5Mrs
,-?j,/(g yg cp )-/ Date
- 5. Approved 6. ATMS Incorporated m k Aneib Plant Manage (f Date 5 .25-83 Date
?
- 7. Biennial Review i Date .
I-ei0780-0006d154 i
PALISADES NUCLEAR PLANT Proc No EI-2.1 EMERGENCY IMPLEMENTATION PROCEDURE Revision 9 Page i TITLE: EMERGENCY ACTIONS / NOTIFICATIONS / RESPONSIBILITIES Table'of Contents Page
-1.0 PERSONAL RESPONSIBILITIES . . . . . . . . . . . . . . . . . . . . I 2.0 PURPOSE . .. . . .. . . . . . . . . . . . . . . . . . . . . . . 1 3.0 INITIAL CONDITIONS AND/OR REQUIREMENTS . . . . . . . . . . . . . 1 4.0 EMERGENCY ACTIONS / NOTIFICATIONS / RESPONSIBILITIES . . . . . . . . . 1 4.1 EMERGENCY ACTIONS / NOTIFICATIONS . . . . . . . . . . . . . . . . . 1 4.2 SITE EMERGENCY DIRECTOR RESPONSIBILITIES . . . . . . . . . . . . . 2 5.0 ATTACHMENTS .. . .. . . . . . . . . . . . . . . . . . . . .. . 3 Attachments Attachment 1, Emergency Actions / Notifications 3
, ei0780-0006c154
+. - .-. . . . . . . ,- - . . - . - - , . . - , - - . - . . . - - . . . . , . . . - . . _ . . . . --
. o .
PALISADES NITCLEAR PLANT Proc No El 2.1 EMERGENCY IMPLEMENTING PROCEDURE Revision 9
. Page 1 of 3 TITLE: EMERGENCY ACTIONS / NOTIFICATIONS / RESPONSIBILITIES 1.0 PERSONAL RESPONSIBILITIES The Site Emergency Director (SED) shall implement this procedure.
2.0 PURPOSE 2.1 To provide the SED with a prepared course of action for each emergency identified in EI-1, Activation of the Site Emergency Plan / Emergency Classification.
2.2 To define the SEDs responsibilities in an emergency.
3.0 INITIAL CONDITIONS AND/OR REQUIREMENTS This procedure shall be implemented after completion of EI-1.
4.0 EMERGENCY ACTIONS / NOTIFICATIONS / RESPONSIBILITIES 4.1 EMERGENCY ACTIONS / NOTIFICATIONS
- a. The SED shall delegate the Actions / Notifications identified in EI-l and marked on Attachment 1. Normally assigned personnel / groups are identified in fourth column.
- b. The assignee should note the category of action as ~m arked in column 1.
- 1. Mandatory Actions (M) - Actions that should be performed within one hour.
- 2. Subsequent Actions (S) - Actions that should be performed in an expeditious manner as conditions, time and personnel ,
permit.
t
- 3. If Needed Actions (I) - Actions that are not required in every case, but may be needed.
- c. The assignee shall note the frequency the action should be performed in Column 5.
- d. Appropriate actions / notifications should be turned over upon activation of the General Office Control Center or Emergency Operations Facility. Note the time of turnover on Attachment I and notify the SED.
NOTE: A line through the box for time of turnover indicates this action / notification may not be appropriate for turned pver to the GOCC/ EOF.
~
ei0780-0006aI54 t
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PALISADES NUCLEAR PLANT Proc No EI 2.1 EMERGENCY IMPLEMENTING PROCEDURE Revision 9 Page 2 of 3 TITLE: EMERGENCY ACTIONS / NOTIFICATIONS / RESPONSIBILITIES 4.2 SITE EMERGENCY DIRECTOR RESPONSIBILITIES
, a. In addition to the responsibilities listed in Attachment 1, the SED shall also perform or delegate those actions and responsibilities listed below.
- 1. Command and control of the Technical Support Center and Operational Support Center. Refer to EI-4.1 and EI-4.2.
- 2. Approve recommendations to state and local agencies regarding protective actions for the public. Refer to EI-6.
- 3. Approve decisions regarding Site evacuation. Refer to EI-13.
- 4. Maintain a log of events and actions during the cmergency and subsequent recovery.
- 5. Request Federal assistance as necessary.
- 6. Have PA c.nnouncements regarding emergency conditions made at regular intervals or when significant changes occur.
- 7. Limit personnel access to the site.
- 8. Encure on site first aid is performed and accident victims are transported to hospitals as necessary. Reier to EI-14.
- 9. Authorization to exceed the 10CFR20 dose limits for emergency workers. The following guidelines should be used to establish
. emergency dose limits:
I-l t
l ei0780-0006a154 i _ -. __ _. . .- -
PALISADES NUCLEAR PLANT Proc No EI 2.1 EMERGENCY IMPLEMENTING PROCEDURE Revision 9 Page 3 of 3 TITLE: EMERGENCY ACTIONS / NOTIFICATIONS / RESPONSIBILITIES ,
Projected Dose (Rem) to Emergency Team Workers Category Comments Whole Body 25 Control exposure of Although respirators emergency team members and stable iodine should Thyroid 125 to these levels except be used where effective for lifesaving missions. to control dose to emer-(Appropriate controls gency team workers, thy-for emergency workers, roid dose may not be a include time limita- limiting factor for tions, respirators, and lifesaving missions.
stable iodine.)
Whole body 75 Control exposure of emergency team members Thyroid (**) performing lifesaving missions to this level.
(Control of tirue of ex-posure will be most ,
effective.)
These actions are recommended for planning purposes. Protective action decisions at the time of the incident must take into consideration the impact of existing constraints.
- No specific upper limit is given for thyroid exposure since complete loss might be an acceptable penalty for a life saved.
5.0 ATTACHMENTS Attachment 1, Emergency Actions / Notifications
- Indicates a responsibility that shall not be delegated.
eio780-0006a154
Proc No _.-2.1 ,
Attachment 1 Revision 9 Page 1 of 6 EMERGENCY / ACTIONS / NOTIFICATIONS i
Action Type Turnover to H, S, or I .= 'P Normally GOCC/ EOF (From EI-1) Action / Notification _ _ Referenc.e/ Telephone No Assigned To Frequency (Time)
, ~',:G?F
- 1. Notification of Duty and Duty Cali List SED /Comm Initially Call Superintendent ,g/ at Unusual ------
Event
- 2. Perform Emergency Staff Contact Property Protection SED /Comm Initially Augmentation Supervisor or Security at Unusual ------
Shift Leader - EI-2.2 Event
- 3. General Office Notification Dedicated phone or SED /Comm Initially Power Controller 517-788-0990 at Unusual ------
upon activation transfer notification to Dedicated phone or Event COCC 82-87001 Every 15 Upon activation transfer notification to Dedicated phone cy min above
. Technical Support Center Unusual Event
- 4. NRCNotif[ cation 1. Dedicated phone or SED /Conun Initially
- 2. 202-951-0550 at Unusual Bethseda Op Ctr or Event
- 3. 301-427-4056 Every 15 Silver Springs or min above
- 4. licalth Physics Network Unusual
- 22 (touch tone) Event
- 22 (dial phone) or
- 5. 301-492-7000 Bethseda Central Office 4 .
eio780-0006bl54 -
Proc No .-2.1 ,
Attachment I Revision 9 Page 2 of 6 EMERGENCY / ACTIONS / NOTIFICATIONS Action Type M, S, or I
\s
% Turnover to Normally GOCC/ EOF (From EI-1) Action / Notification Reference / Telephone No Assigned To Frequency (Time)
- 5. State Notification Dedicated Phone or SED /Comm Initially
<- South Haven State Police Post 616-637-2125 or at Unusual Security Radio Event Every 15 i
min above Unusual Event
- 6. Local Notification Dedicated Phone or SED /Comm, Initially Van Buren County Sheriff 616-657-3101 at Unusual Event i Every IS min above Unusual Event 1
- 7. Initiate Fire Protection Plan' Fire Protection SED /SS Initially ------
j mplementing Procedures
- 8. Covert Fire Dept and Ambulance Service 616-764-1313 SED As Needed ------
- 9. Backup Ambulance Service
- MEDIC 1 (St Joseph) 925-2141 SED As Needed ------
South Haven Ambulance 637-3305 a
ei0780-0006bl54 f
I
Proc No -2.1 Attachment 1 Revision 9 Page 3 of 6 2
EMERGENCY / ACTIONS / NOTIFICATIONS Action Type Turnover to M. S, or 1 Normally COCC/ EOF (From EI-1) Action / Notification Reference / Telephone No Assigned To Frequency (Time)
- 10. Ilospitals:
Benton Harbor Mercy 616-927-5241 or SED 616-927-5242 As Needed South llaven Community 616-637-5271
- 11. Property Protection Supervisor Day: Call List SED Initially Night: At Site Area ------
Emergency Only 616-468-6370 _
- 12. Initiate Onsite Monitoring El-8 Chem /f!P Contin- ------
, uously
- 13. Initiate Offsite Monitoring EI-9 Chem / IIP Contin- ------
uously 14'. Perform Offsite Dose Estimates, EI-6.0 Chem / IIP Per EI-6.0 .
Obtain Meteorological Data
- 15. Perform Post-Accident Sampling EI-7 Chem / IIP As Needed ------
- 16. Perform Environmental Assessment EI-10 As_Needed Chem / IIP jg,: .,. 17. Activate the Technical EI-4.1 SED Initially ------
Support Center (TSC) at Alert e10780-0006bl54
e i
Y Pree No 12 .1
- Attachment 1.
Revision 9 Page 4 of 6 EMERGENCY / ACTIONS / NOTIFICATIONS Action Type Turnover to M, S, or I Normally GOCC/ EOF (From EI-1) Action / Notification Reference / Telephone No Assigned To Frequency (Time)
- 18. Activate the Operational .
EI-4.2 SED Initially ------
Support Center (OSC) at Alert
- 19. Activate the Emergency EI-4.3 SED Initially ------
Operations Facility (EOF) at Site Area Emerg
- 20. Activate the Joint Public Nuclear Plar.t Emergency Plant Initially Infornation Center (JPIC) Fublic Information Policies Public ------
and Procedures Affairs Director ___
- 21. Dispatch liasons to local Emergency SED Initially Operations Centers at Site. ------
Area Emerg
- 22. Perform Personnel Accountability EI-12 SED / Initially ------
Security at Alert
- 23. Evacuate non-essential personnel EI-13 SED / Initially Chem / IIP / at Site ------
~
Security Area Emerg
- 24. Notify Plant Public Affairs Director Call List: (Days) 637-8769 or (night) SED Initially 82-80333 or at Unusual ------
517-788-0333 Event cio780-0005bl54
Proc No -.-2.1 .
Attachment 1 Revision 9 Page 5 of 6 EMERGENCY / ACTIONS / NOTIFICATIONS Action Type M, S, or I Turnover to Normally GOCC/ EOF (From EI-1) Action / Notification Reference / Telephone No Assigned To Frequency (Time)
- 25. Perform Estimate Core Damage EI-11 Tech As Needed
- 26. Backup Local Notification Berrien County AND 616-983-7141 SED /Conun As Needed Allegan County 616-673-5441
- 27. Michigan Dept of Public Health 517-373-1578 (Days) Chem / IIP As Needed 517-373-0800 (Night)
- 28. US Coast Guard Notification SED /Comm As Needed St Joseph 616-983-1371 Muskegon 616-759-0951
- 29. South llaven Water Dept 616-637-5211 (Days)
SED /Conun As Needed Notification 616-637-5151 (Nights)
- 30. Palisades Park Manager Notification 616-764-8272 SED /Comm As Needed
- 31. Van Buren State Park Manager 616-637-2788 SED /Comm As Needed Notification
- 32. Federal Aviation Administration 616-637-8075 SED /Comm If light South Bend, IN fails on Met Tower
- 33. Initiate reentry / recovery EI-5 SED ----- ------
ei0780-0006bl54 e
_ _ ._. ,. . _ . . ~- . . , - .
Proc No._ 12.1
- Attachment 1-Revision 9 Page 6 of 6 EMERGENCY / ACTIONS / NOTIFICATIONS Action Type Turnover to M, S, or I Normally GOCC/ EOF (From EI-1) Action / Notification Reference / Telephone No Assigned To Frequency (Time)
- 34. Initiate Event Report Admin Procedures SED Within 24 No 3.04 hrs at ------
l' Unusual
, Event within 8 hrs above i
Unusual Event i
4 N
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4 ei0780-0006bl54 e
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Proc No EI-6.6 Revision 0 Date 5/23/83 PALISADES NUCLEAR PIANT
- ~ EMERGENCY IMPLEMENTATION PROCEDURE Revision and Approvs1 Summary TITLE: GAMMA E DETERMINATION
- 1. Prepared 2. QA Concurrence -
ll I k
'Date Date y0r$inator n 2A DQu%
- 3. Recommend Approval /Q-List No 4. PRC Reviewed
/hthijf?{Q 5/6/83 Th&ccg gjg&3 a ent Head Date -y7g g 3 -gfp ' Da'te
- 5. Approved 6. ATMS Incorporated W h DD /O 6-2 -23 QPlantManagerQ Date Date
- 7. Biennial Review Date .
eiO383-0043d154
..- . 1 i
PALISADES NUCLEAR PLANT Proc No EI-6.6 EMERGENCY IMPLEMENTATION PROCEDURE Revision 0
_ Page i i
TITLE: GAMMA E DETERMINATION Table of Contents Page 1.0 PERSONNEL RESPONSIBILITY . . . . . . . . . . . . . . . . . . . . . 1 2.0 PURPOSE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 3.0 INITIAL CONDITIONS AND/OR REQUIREMENTS . . . . . . . . . . . . . . 1 4.0 - 5 DETERMINATION . . . . . . . .. . . . . . . . . . . . . . . . . 1 5.0- ATTACHMENTS . . . . . . . . . .. . . . . . . . . . . . . . . . . 2
=
ATTAClefENTS Attachment 1, " Energy Per Disintegration vs Decay Time Prior to Release for Noble Gas" A
4 i
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1 e -
PALISADES NUCLEAR PLANT Proc No EI-6.6 3 EMERGENCY IMPLEMENTATION PROCEDURE Revision 0 !
_ Page 1 of 2 TITLE: GAMMA E DETERMINATION 1.0 PERSONNEL RESPONSBILITY The Chemistry / Health Physics Support Group Leader shall implement this procedure. In the absence of a Chemistry / Health Physics Support Group Leader, the Site Emergency Director shall delegate this responsibility.
2.0 PURPOSE This procedure provides a gamma 5 (average gamma energy per disintegration) for input into offsite dose calculations.
3.0 INITIAL CONDITIONS AND/OR REOUIREMENTS
- a. This procedure shall be implemented as required per El-6.0.
- b. Data and results from this procedure should be recorded on the Offsite Dose Worksheet, Attachment 1 to EI-6.0, in Section II,1.
- c. 5 is dependent on the source of the radionuclide release, the type of accident / release and the time of decay (or time after reactor shutdown. Those parameters should be known prior to performing this procedure. In the event these parameters cannot be determined, the default case for E of 0.7 MeV should be used.
4.0 E
]ETERMINATION
- a. Determine the source of the release,
- b. Determine the decay time in hours and record on worksheet, item (A).
- c. Determine 5 from the appropriate section below:
- 1. Fuel Melt of Fuel Failure - using the time after reactor shutdown as the decay time prior to release, determine E using Attachment 1. Fuel melt accidents ~ predominate when determining E.
NOTE: Fuel failure may be determined using EI-11.
- 2. Mainsteam and Offgas (Air Ejector) Releases - If the release is coming from a primary to secondary leak and fuel failure or fuel melt is involved, determine E from Attachment 1 and use time after shutdown _as decay time prior to release. For all other cases use an E of 0.134 MeV.
- 3. Surge Tank, Volume Control Tank, and Degasifie.r Releases - Use the.E that corresponds to the six hour time in Attachment 1 (0.180 MeV). This corresponds to a release from the Primary
_ Coolant System (excluding mainsteam releases) without fuel -
eiO383-0043a154 4 ? e 5:.
PALISADES NUCLEAR PLANT Proc No EI-6.6 EMERGENCY IMPLEMENTATION PROCEDURE Revision 0
, Page 2 of 2 TITLE: GAMMA E DETERMINATION damage. This value may be used far any release that involves fresh primary coolant.
- 4. Waste Gas Decay Tank - If the decay time for activity in a kaste Gas Decay Tank is known, then E should be determined using Attachment 1 by using six hours as the starting point.
For example, if the tank contains activity that has decayed for two days, then the E from attachment is equal to that for the 48 + 6 = 54 hour6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 months <br /> time period.
- 5. Fuel Handling, Sipping and Cask Drop Releases - if the release is coming from a fresh spent fuel bundle (directly out of the reactor core and less than 30 days old), then determine E using time after reactor shutdown and Attachment 1. If_the release is coming from an old fuel bundle, then use an E of 0.035 MeV.
Mark release type and record 5 on worksheet, items (B) and (C) respectively.
- d. Proceed to next procedure as required, per EI-6.0.
5.0 A'ITACMIENTS Attachment 1, " Energy Per Disintegration vs Decay Time Prior to Release for Noble Gas" l
i l
i I
i i
eiO383-0043a154
4 I Proc No EI-6.6 Attachment 1 Revision A l Page 1 of 1 ENERGY PER DISINTEGRATION vs DECAY TIME PRIOR TO RELEASE FOR NOBLE GAS i I III e e c:
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Proc No EI-6.13 Revision 0 Date 5/23/83 PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTATION PRCCEDURE Revision and Approval Summary TITLE: PROTECTIVE ACTION RECOMMENDATIONS FOR OFFSITE POPULATION
- 1. Prepared 2. QA Concurrence
/h M y0rgnator Ge ~ Date m
Date RK l'A N/BJS
- 3. Recommend Approval /Q-List No 4. PRC Reviewed b b /Yb c /' $~Y(k3 y p Q ent Head Date
fyg gj .3y9 / Da te
- 5. Approved 6. ATMS Incorporated
~ ^ :Ln_J ~ wk 6134 ib 6* db'0 lant Manager 0 ' Date Date l
, 7. Biennial Review
! l Date eiO383-0049c154
~;..
l
'I 8
PALISADES NUCLEAR PLANT Proc No EI-6.13 EMERGENCY IMPLEMENTATION PROCEDURE Revision 0 Page i ,
TITLE: PROTECTIVE ACTION RECOMMENDATIONS FOR OFFSITE POPULATION Table of Contents Page 1.0 PERSONNEL RESPONSIBILITY . . . . . . . . . . . . . . . . . . . . . 1 2.0 euRPOSE . .. . . . . . . . . . . . . . . . . . . . . . . . . . . 1 1
3.0 INITIAL CONDITIONS AND/OR REQUIREMENTS . . . . . . . . . . . . . . 1 4.0 PROTECTIVE ACTION RECOMMENDATIONS . . . . . . . . . . . . . . . . 1 4.1 DEVELOPING PROTECTIVE ACTION . . . . . . . . . . . . . . . . . .. 1 4.2 REVIEW OF RECOMMENDATIONS . . . . . . . . . . . . . . . . . . . . 3 4.3 RECOMMENDATIONS TO THE STATE , . . . . . . . . . . . . . . . . . . 4 5.0 ATTACHMENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 1
i i
s l-4 G
eiO383-0049bl54 i
_, - - _ - . , .. . ,. . - - - . . , - . ~ , . - - - - - . - - - - - - , , - - - -- -- - - -
0 PALISADES NUCLEAR PLANT Proc No EI-6.13 EMERGENCY IMPLEMENTATION PROCEDURE Revision 0 Page 1 of 4 TITLE: PROTECTIVE ACTION RECOMMENDATIONS FOR OFFSITE POPULATION 1.0 PERSONNEL RESPONSIBILITY
- a. The Site Emergency Director (SED) shall make recommendations for protective actions to offsite agencies. This responsibility shall not be delegated.
- b. The Chemistry / Health Physics Group Leader shall implement this procedure and make recommendations to the SED with respect to protective actions. In the absence of a Chemistry / Health Physics Group Leader, the SED shall delegate this responsbility.
2.0 PURPOSE This procedure provides a basis for making recommendations for offsite protective actions based on offsite dose calculations and offsite monitoring results.
3.0 INITIAL CONDITIONS AND/OR REQUIREMElfrS
- a. This procedure shall be implemented as required in' EI-6.0.
- b. Data and results from this section should be recorded on the Offsite Dose Worksheet, Attachment 1 of EI-6.0,Section VI.
- c. Input to this section is obtained from previously completed sections of the Offsite Dose Worksheet. Pertinent data is enclosed in boxes for rapid identification.
4.0 PROTECTIVE ACTION RECOMMENDATIONS 4 .. I , DEVELOPING PROTECTIVE ACTION
- a. Compare the integrated doses calculated in EI-6.9, EI-6.10 or EI-6.11 (Worksheet,Section IV), to the recommended protective actions listed below.
eiO383-0049a154
PALISADES NUCLEAR PLANT Proc No EI-6.13 EMERGENCE IMPLEMENTATION PROCEDURE Revision 0 Page 2 of 4
- TITLE: PROTECTIVE ACTION RECCMMENDATIONS FOR OFFSITE POPULATION 4
TABLE 1
- RECOMMENDED PROTECTIVE ACTIONS TO REDUCE WHOLEBODY AND THYROID DOSE TO OFFSITE POPULATION FROM EXPOSURE TO A GASEOUS PLUME
+
Projected Dose (Rem) to the Population Recommended Actions (*) Comments l
Wholebody < 0.5 No required protective actions ( ) Previously re-State may issue an advisory to seek commended pro-shelter and await further tective actions l instructions, may be recon-Thyroid- <5 Monitor environmental radiation sidered or term-levels. inated.
Wholebody 0.5 to < 5 Seet shelter as a minimum. If constraints Consider evacuation. Evacuate exist, special unless constraints make it consideration Thyroid 5 to < 25 impractical. should be given i
' Monitor environmental radiation for evacuation levels. of children and Control access. pregnant womer.
I Wholebody 5 and above- Conduet mandatory evacuatIion. Seeking shelter
' Monitor environmental radiation would be an al-
- levels and adjust area for ternative if
. Thyroid 25 and above mandatory evacuation based on these evacuation where levels. not immediately Control access. possible.
1
, (a) These actions are recommended for planning purposes. Protective action decisions at the time of the incident must take existing conditions into 1
consideration.
(
l At the time of the incident, state officials may implement low-impact l protective actions in keeping with the principle of maintaining radiation exposures as-low as reasonably achievable.
- b. ' Check the appropriate recommendations in Worksheet,Section VI, i
item (A). If no protective actions are required, write "NONE" in
- item (A) and go to Step 4.1.e.
l c. . Affected downwind sectors should be determined on -Table 2, using l
wind direction as determined in EI-6.7 or EI-6.8. (Worksheet,
, Section III) .
l eiO383-0049a154
5
~
PALISADES NUCLEAR PLANT Proc No EI-6.13 EMERGENCY IMPLEMENTATION PROCEDURE Revision 0
, Page 3 of 4 f TITLE: PROTECTIVE ACTION RECOMMENDATIONS FOR OFFSITE POPULATION TABLE 2 Wind Direction Affected Sectors Degrees Degrees Centerline Adjacent From To Sector Sectors 168.76 - 191.25 348.75 - 11.25 N NNW NNE 191.26 - 213.75 11.26 - 33.75 NNE N NE 213.76 - 236.25 33.76 - 56.25 NE NNE ENE 236.26 - 258.75 56.26 - 78.75 ENE NE E 258.76 - 281.25 78.76 - 101.25 E ENE ESE 281.26 - 303.75 101.26 - 123.75 ESE E SE 303.76 - 326.25 123.76 - 146.25 SE E5E SSE 326.26 - 348.74 146.26 - 168.75 SSE SE S 348.75 - 11.25 168.76 - 191.25 S SSE SSW 11.26 - 33.75 191.26 - 213.75 SSW S SW 33.76 - 56.25 213.76 - 236.25 SW SSW WSW 56.26 - '78.75 236.26 - 258.75 WSW SW W 78.76 - 101.25 258.76 - 261.25 W WSW WNW 101.26 - 123.75 281.25 - 303.75 WNW W NW 123.76 - 146.25 303.76 - 326.25 NW WNW NNW 146.26 - 168.75 326.26 - 348.74 NNW NW N Record affected sectors on Worksheet, item (B).
For example: A wind direction from 35* would indicate affected sectors of W, WSW, and WNW. Include the area within two miles of the plant (all sectors) in any recommended actions.
- d. Record the basis for the recommended action, (eg, Whole body dose ,
or Thyroid dose), on Worksheet,Section VI, item (C).
- e. Record on Worksheet,Section VI, item (D) whether doses are based on actual or potential release (per Worksheet,Section IV).
- f. Sign the Worksheet, include date and time and give worksheet to the Chemistry / Health Physics Group Leader. -If the Chemis-try/ Health Physics Group Leader is not .available, give the T
worksheet to the SED.
i 4.2 REVIEW OF RECOMMENDATIONS
- a. The Chemistry / Health Physics Group Leader should review the results of Section 4.1 before making recommendations to the Site Emergency Director (SED).
eiO383-0049a154 L
PALISADES NUCLEAR PLANT Proc No EI-6.13 EMERGENCY IMPLEMENTATION PROCEDURE Revision 0 Page 4 cf 4 TITLE: PROTECTIVE ACTION RECOMMENDATIONS FOR OFFSITE POPULATION
- b. As time permits and conditions warrant, include a review of offsite monitoring data per EI-6.12.
- c. Sign the worksheet, include date and time. Provide a recommendation and the worksheet to the SED based on the review of Worksheet,Section VI.
4.3 RECOMMENDATIONS TO THE STATE 4
- a. The SED shall make the decision to make protective action recommendations to the state through the Michigan State Police.
This decision shall not be delegated.
The recommendations should include:
- 1. Recommended Protective Action.
- 2. Affected Sectors including a two mile radial area.
- 3. Projected Doses (thyroid and/or whole body).
- 4. Whether doses are actual nr projected.
5.0 ATTACHMENTS None eiO383-0049a154 g- >-
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Proc No EI 7.2
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Revision 0 Date 5/23/83 PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE Revision and Approval Sumary TITLE: POST ACCIDENT ANALYSIS I. Prepared 2. QA Concurrence b m/vtw 8. /7/?3 Date Hriginatorg Date
- 3. Recom9nd A ova,1/Q-List Yes No 4. PRC Reviewed A~
art
?N - Sk 7 23 t Head 'Da t.e 3 /n L L c4sd 7 lDate
, . 4gg g3.c;/c.
- 5. Approved 6. ATMS Incorporated s -
N k biM/h S~d3" N Plant Manage (d ' Date Date
- 7. Biennial Review Date ,
I j ei1182-0022d!54 L
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PALISADES NUCLEAR PLANT Proc No EI 7.2 Revision 0 EMERGENCY IMPLEMENTATION PROCEDURE 4
Page i TITLE: POST ACCIDENT ANALYSIS t
Table of Contents - --
Page i- 1.0 PURPOSE
. . . . .. . . . . . . . . . . . . . . . . . . . . . . . 1
2.0 REFERENCES
1 3.0 PREREQUISITES . .. . . . . . . . . . . . . . . . . . . . . . . . 1 3.1 DOSIMETRY REQUIREMENTS . . . . . . . . . . . . . . . . . . . . . . 1 3.2 ANTI-C. CLOTHING REQUIREMENTS . . . . . . . . . . . . . . . . . . .
I
- 4.0 PRECAUTIONS AND LIMITATIONS . . . . . . . . . . . . . . . . . . . 1 5.0 PROCEDURE
. . . . .. . . . . . . . . . . . . . . . . . . . . . . 2 5.1 PRE-ANALYSIS PREPARATION . . . . . . . . . . . . . . . . . . . . . 2 5.1.1 Baseline Gas Chromatograph . . . . . . . . . . . . . . . . . . . . 2
, 5.1.2 pH Analysis
. . ... . . . . . . . . . . . . . . . . . . . . . . 3 5.1.3 Boron Analysis .
. ... . . . . . . . . . . . . . . . . . . . . . 4 5.2 SAMPLE ANALYSIS
... . . . . . . . . . . . . . . . . . . . . . . 5 5.2.1 Primary Coolant Hydrogen Gas Analysis . . . . . . . . . . . . . . 5 5.2.2 PCS Offgas Radioactivity Analysis . . . . . . . . . . . . . . . . 5 t
5.2.3 PCS Liquid pH
.. .. . . . . . . . . . . . . . . . . . . . . . . 5 5.2.4 PCS Boron Analysis . . . . . . . . . . . . . . . . . . . . . . . .
6 i
5.2.5 PCS Liquid Radioactivity Analysis. . . . . . . . . . . . . . . . . 6 5.2.7 PCS Chloride Analysis
- _ . . . . . . . . . . . . . . . . . . . . . . 6 5.2.3 PCS Dissolved Oxygen Aaalysis . . . . . . . . . . . . . . . . . . 7 l 4.0 ATTACHNENTS . . . . . . . . . . . . . . . . . , . . . . . . . . . 7 Attachments i
Attachment 1, " Post Accident Analytical Data" ,
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PALISADES NUCLEAR PLANT Proc No EI 7.2 EMERGENCY IMPLEMENTATION PROCEDURE Revision 0 Page 1 of 7 TITLE: POST ACCIDENT ANALYSIS 1.0 PURPOSE i
To describe the sequential method of analyzing the Primary Coolant System samples obtained from the post accident sample panel during a post accident condition.
2.0 REFERENCES
2.1 Emergency Implementation Procedure EI-7.1 2.2 Emergency Implementation Procedure, EI-7.3 2.3 Emergency Implementation Procedure, EI-7.4 2.4 Emergency Implementation Procedure, EI-7.5 2.5 Emergency Implementation Procedure, EI-7.6 3.0 PREREQUISITES 3.1 DOSIMETRY REQUIREMENTS Each individual that may handle a post accident sample shall as a minimum wear beta / gamma TLDs on their chest and on the inside of both wrists. Additionally, a ring TLD shall be vorn on both index fingers with the TLD face inward.
3.2 ANTI-C CLOTHING REQUIREMENTS Minimum clothing shall consist of full Anti-Cs, wetsuit with all seams taped, and an SCBA Breathing unit. A lapel air sampler should be worn by the sampling te'chnician. Any persons who will handle samples shall wear lineman's gloves in addition to their other clothing.
4.0 PRECAUTIONS AND LIMITATIONS 4.1 Hand handling of samples should be minimized. When samples must be handled, a Beta radiation dose rate deduction of 90% can be assumed for lineman's gloves. Dose to the extremities shall be limited to 7.5R as measured by the ring TLD pending a dose determination based on the beta / gamma TLDs.
4.2 When not being handled, samples shall be stored in a shielded or removed location. All unsealed samples shall be handled in vent hoods.
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I PALISADES NUCLEAR PLANT Proc No EI 7.2 ,
EMERGENCY IMPLEMENTATION PROCEDURE Revision 0 Page 2 of 7 TITLE: POST ACCIDENT ANALYSIS 5.0 PROCEDURE 5.1 PRE-ANALYSIS PREPARATION 5.1.1 Baseline Gas Chromatograph
- a. Disconnect Gas Chromatograph
- 1. Turn detector off (inside GC Cabinet)
CAUTION:
Do not shut off carrier gas flow with detector turned on.
- 2. Close all calibration isolation valves.
- 3. Place GC in manual and clear.
- 4. Enter "13", "14", "23" then "24" at I second intervals to bleed off calibration gas pressure.
- 5. Repeat Step 4 until all calibration gases are bled off.
- 6. Close eductor and valve op supply valve.
- 7. Enter "23", wait 5 seconds then "24" to bleed eductor supply.
- 8. Turn Gas Chromatograph off (back of instrument)
- 9. Close Carrier Gas Isolation Valve
- 10. Disconnect the carrier gas, all calibration gases and the Eductor and Valve Op connections at the supply end.
- 11. Unplug the recorder and place it on top of the Gas Chromatograph. Unplug Gas Chromatograph, place sample block on top of Gas Chromatograph.
- ~ -
- 12. Carefully lift the Gas Chromatograph and place on cart,
- b. Connect Gas Chromatograph to Cart
- 1. Connect the gas lines to the proper connections are marked.
- 2. . Plug in Gas Chromatograph and Recorder to cart.
- 3. Back off all regulators (CCW) '
ei1182-0022a154 1
PALISADES NUCLEAR PLANT Proc No EI 7.2 EMERGENCY IMPLEMENTATION PROCEDURE Revision 0 Page 3 of 7 TITLE: POST ACCIDENT ANALYSIS
- 4. Open carrier and calibration gas bottle valves.
5 Adjust regulators for pressure as follows:
- 1. Eductor and Valve Op - 80 psig
- 2. Carrier Gas - 30 psig
- 3. Calibration Gases 3 psig
- 6. Place recorder in proper location on cart.
- 7. Place sample block in shield.
- 8. Turn recorder, Gas Chromatograph and detector switches on.
NOTE: There shculd not be any power available at cart as of yet,
- c. Move cart to use location and plug cart into 110 Vac.
- d. With GC in " manual, cleat- and enter "45" when trace flattens out, GC is ready for use; enter "00".
- e. Place GC in " enter" and " clear" enter 08, 03, 31, 13. Exit the
" enter" mode and " clear" (read mode). Verify program by entering step numbers (01, 02, .. 50). Program sequence es listed in E 7.3, Appendix I.
- f. Verify recorder settings Upper pen Pressure MV/V 50 mv
$ set at Left Margin with pen in standby Lower pen TCD Output MV/V 0.100 Volts
@ set at right "10" with pen in standby.
Speed 5 cm/ min 5.1.2 gH Analysis
- a. Remove the pH lead shield brick frdm the emergency kit and put it i in the hood.
- b. Take a 15-cc wide mouth vial from the emergency kit and place it in the pH lead shield brick. Remove the-cap and label the cap l with "pH" and the time /date. Set the cap aside. -
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- c. Shield the vial with at least more than 4" of lead brick.
- d. Remove a pH probe from the emergency kit and place it inside the hood in a beaker of demineralized water to soak. The probe must soak 30 minutes before use.
- e. Place a pH meter inside the hood and hook-up the pH probe.
5.1.3 Boron Analysis
- a. Set up the autocatic titrator in the hood.
- b. Place a 100 ml beaker in the automatic titrator. Add 30 ml of demineralized water to the beaker.
' emergency kit into the 100 ml beaker.
- d. Turn on the magnetic stirrer and adjust for moderate speed. Place the pH probe in the 100 ml beaker.
- e. Adjust the temperature control for the sample and press the start button to adjust the pH to 7.00. If the meter needle swings to the left, add 1 ml of 0.01N HNO 3 and press the start button again until a small amount of titrant is used. This will bring the initial pH to 7.
- f. Adjust the dosimat to 0 by pushing the down arrow.
- g. Add 3 ml of SM Mannitol solution to the 100 ml beaker.
- h. Adjust the titrator for sample temperature and push the start '
button to start titration.
- i. At the end of the titration, add an additional 3 ml of Mannitol solution and continue the titration to the pH = 7.0 endpoint.
J. Calculate the volumetric factor, Ng, using the following equation:
Ng (ppm boron /ml NaOH) = 1000 ppm Boron + ml NaOH titrant used
~ Record the volumetric factor, Ng , on Attachment 1.
- k. Remove the pH probe from the 100 ml beaker, rinse it with demineralized water, and put it back into the demineralized water to soak.
ei1182-0022a154
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. EMERGENCY IMPLEMENTATION PROCEDURE Revision 0 l Page 5 of 7 l I
TITLE: POST ACCIDENT ANALYSIS 5.2- SAMPLE ANALYSIS 5.2.1 Primary Coolant Hydrogen Gas Analysis 1
- a. Place recorder chart switch in the cm/ min position.
- b. Place the sample vial end of the sample tong transported from the PASM panel into the shielded tong holder on the Gas Chromatograph cart. Rotate the sample tong to-lock in place.
- c. Conduct hydrogen analysis using Procedure EI 7.3.
- d. Dispose of the sample vial by holding the sample tong over the disposal cask. Rotate the. sample tong handle until the sample vial drops into the cask, d
5.2.2 PCS Offgas Radioactivity Analysis
, a. Transport the 15 cc vial to the counting facility for gamma i
i-spectral analysis using Procedure EI-7.4. Wrap the ' sample vial in poly sheeting before placing the sample vial on the detector.
- b. Upon completion of EI-7.4, dispose of the vial in the disposal cask.
5.2.3 PCS Liquid pH
- a. Using the shielded syringe fror,the Emergency Kit, insert the syringe needle into the sample cask top until it cannot be inserted any further.
-b. Slowly withdraw the syringe plunger to the preset stop. '
- c. Withdraw the syringe needle from the sample cask and insert the needle into the shielded 15 ml Tritium vial.
- d. Depress the syringe plunger to the mechanical stop to transfer the t
PCS liquid sample to the analytical beaker.
[ e. Rinse the, shielded syringe using demineralized water in the i laboratory sink or the disposal cask.
i j f.
Place the pH probe in the shielded sample. When the pH meter has stabilized, record the PCS pH on Attachment 1.
g.
Remove the pH probe frca the shielded 15 ml Tritium vial and place it in the 30 ml of water in the automatic titrator.
i
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4 PALISADES NUCLEAR PLANT Proc No EI 7.2 EMERGENCY IMPLEMENTATION PROCEDURE Revision 0 Page 6 of 7 TITLE: POST ACCIDENT ANALYSIS 5.2.4 PCS Boron Analysis
- a. Pipette a 1 ml aliquot of the sample into the 100 ml beaker containing 30 ml of water using a 1 ml Eppendorph Pipctte.
i b. Conduct Boron titration on the sample using Procedure EI 7.5.
- c. Using lab tongs, dispose of the Boron sample solution in the '
Laboratory hood drain. Rinse the 100 ml beaker thoroughly using j decineralized water. '
- d. Using lab tongs, place the cap on the 15 ml PCS pH sample vial.
Hove the sample vial and the lead shield to a shielded storage location. The sample shall be retained for chloride analysis i within 4 days.
5.2.5 PCS Liquid Radioactivity Analysis i WARNING i
Wear lineman's gloves while conducting Steps a and b.
- a. Using a 2.5 ce syringe, collect 1.0 cc of the diluted PCS liquid 4
sample in the 15 cc Tritium sample vial. * '
- b. Inject the 1.0 cc diluted PCS sample into an evacuated 15 cc gas vial. Dispose of the Tritium sample vial containing the PCS sample from the PASH in the disposal cask. Fill the 15 cc gas vial containing the 1.0, cc sample by injecting 14 cc of demineralized water into the vial,
- c. Transport the 15 cc sample gas vial in a sample tong to the counting facility for gamma spectral analysis using Procedure EI-7.4. Wrap the sample vial in poly sheeting before placing the sample vial on the detector.
- d. Upon completion of EI-7.4 dispose of the contents of the vial in a
- lab hood and dispose of the vial in the disposal cask.
5.2.6 Forward the completed data sheet to the Technical Support Center for review by the Chemical Engineer. The data sheet shall remain in the TSC until required for further analysis.
( 5.2.7 PCS Chloride Analysis .
Conduct PCS Chloride Analysis using Procedure EI 7.6 within 4 days of the sample time. Use the sample stored in Step 3.2.3.d. -
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PALISADES NUCLEAR PLANT Proc No EI 7.2 EFERGENCY IMPLEMENTATION PROCEDURE Revision 0 Page 7 of 7 TITLE: POST ACCIDENT ANALYSIS 5.2.8 PCS Dissolved Oxygen Analysis Dissolved Oxygen analysis shall be conducted using the Modified Winkler method CH-4.5A until a polargraphic probe method can be developed.
4.0 ATTACIDENTS j Attachment 1, Post Accident Analytical Data
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W Proc No EI 7.2 Attachment 1 Revision 0 Page 1 of 1 POST ACCIDENT ANALYTICAL DATA Sample Time /
Date Time PCS HYDROGEN ANALYSIS PROCEDURE / STEP EI 7.1/3.3.1.e
- 1. H2 Pressure initial (PI-1903) psia EI 7.1/3.41
- 2. H2 Pressure final (PI-1903) psia EI 7.1/3.4p
- 3. H2 Concentration ppm cc/kg EI 7.3/3.4
- 4. PCS H 2 Concentration ec/kg (Item 2 x Item 3 x 2.2E-4)
PCS OFFGAS RADIOACTIVITY ANALYSIS
- 7. Volumetric factor, N g ppm Boron /ml NaOH EI 7.2/5.1.3j
- 8. Titrant Volume '
ml EI 7.5/5.7
- 9. Doron Concentration ppm EI 7.5/5.8 (Item 7 x Item 8) .
PCS LIQUID RADIOACTIVITY ANALYSIS
- 11. PCS Chloride Concentration ppm EI 7.6/5.5 PCS DISSOLVED OXYGEN ANALYSIS PCS EO Concentration _ ppm EI 7.8/
CONTAINMENT AIR HYDROGEN AND ACTIVITY ANALYSIS Containment Air H2 Concentration % .
EI 7.3/
Containment Gas Activity Concentration pCi/cc EI 7.4/ .
Technician ei1182-0022bl54 Supervisor
Proc No EI-7.3 Revision 0 Date 5/23/83 PALISADES NUCLEAR PLANT EFERGENCY IMPLEMENTATION PROCEDURE Revision and Approval Summary TITLE: IlYDR0 GEN ANALYSIS OF POST ACCIDENT SAMPLES
- 1. Prepared 2. QA Concurrence
/ M Ab?/!3. I Originatg Date Date
- 3. Pecomme proval /Q-List No 4. PRC Reviewed yta
/ // C s/e eat Head Date zwar/g y3-g/c see Date l
. 5. Approved 6. ATMS Incorporated
= s_x_ n- is M%l h -S'33' O W Plant Manage @
~
Date Date
- 7. Biennial Review i
l Date l
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PALISADES NUCLEAR PLANT Proc No EI-7.3 EMERGENCY IMPLEMENTATION PROCEDLRE Revision 0 Page i TITLE: HYDROGEN ANALYSIS OF POST ACCIDENT SAMPLES Table of Contents Pagg 1.0 PURPOSE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 4
2.0 INITIAL CONDITIONS . . . . . . . . . . . . . . . . . . . . . . . . 1 3.0 PROCEDURE . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 4.0 ATTACHMENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 ATTACHMENTS Attachment 1, Appendix 1 " Program Sequence" i
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PALISADES NUCLEAR PLANT Proc No EI-7.3 EMERGENCY IMPLEMENTATION PROCEDURE Revision 0 Page 1 of 1 TITLE: HYDROGEN ANALYSIS OF POST ACCIDENT SAMPLES 1.0 PURPOSE This document describes the procedural steps necessary to determine the Hydrogen concentrations from a gas sample collected at the PASM panel.
2.0 INITIAL CONDITIONS 2.1 The instrument shall be set up in accordance with EI-7.2.
2.2 The program sequencer shall be set up in accordance with Appendix 1 to this procedure.
2.3 Attentuate and multiplier shall both be set to "5" and "X10" respectively.
2.4 Six port valve shall be in position " Cal 1". Manually enter 13, 14; as necessary to advance to " Cal 1".
3.0 PROCEDURE 3.1 With GC in " Auto" mode, push and release " clear".
3.2 After 25 minutes, turn recorder chart switch to "0FF" and remove chart trace to low background area.
3.3 Calculate ppm Hydrogen in accordance with the following equation:
H2 ppm = 9000 x Hydrogen Net Peak height in chart units Pressure transmitter chart units 3.4 Record ppm H2 on Attachment 1 of Procedure El-7.2.
3.5 Chart trace shall be identified with Date/ Time, standards used, sample location and Technician performing analysis and shall be placed in Ziploc Bag and retained as directed by the Plant Chemical Engineer.
4.0 ATTACHMENTS Attachment 1, Appendix 1 " Program Sequence" i
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Proc No EI-7.3 Attachment 1 Revision 0 Page 1 of 2 BASELINE GAS CHROMAT0 GRAPH PROGRAM Step Time Code Comment 01 00:01 23 Eductor on 02 00:03 24 Eductor off 03 00:05 03 Inject 04 00:06 25 Detector on 05 00:50 04 Precut to vent 06 01:08 01 Recorder on (and 9) 07 03:45 00 Recorder off 08 03:46 13 Advance 6 Port Valve 09 03:47 14 PASM reset 6 port 10 03:48 23 Repeat for Cal #2 11 03:50 24 12 03:52 03 13 03:53 25 14 04:37 04 15 04:55 01 16 07:32 00 17 07:33 13 18 07:34 14 19 07:35 23 Repeat for Cal #3 20 07:37 24 21 07:39 03 22 07:40 25 23 08:24 04 24 08:42 01 25 11:19 00 -
26 11:20 13 27 11:21 14 Evaluate Collection Vial 28 11:22 23 29 11:24 24 PASM Sample 30 11:30 13 31 11:31 '14 32 11:35 03 33 11:36 25 34 12:20 04 35 12:38 01 36 15:15 00 Exhaust sample vial to hood 37 15:16 23 38' 15:20 24
- 39 15
- 21 13 40 15:22 14 Cal #4 or Argon 41 15:23 23 42 15:25 24 43 15:27 03 44 15:28 25 l
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Proc No EI-7.
4 Attachment 1 Revision 0 Page 2 of 2 BASELINE CAS CHROMATOGRAPH PROGRAM Step Time Code Comment i 45 16:12 04
- 46 16:30 01 47 19:07 00 48 19:08 13 49 19:09 14 50 19:10 00 51 19:11 -
99
- 99 (00
- 00) 00 Recycle (time in hours: minutes)
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Proc No EI-6.7 Revision 0 Date 5/23/83 PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTATION PROCEDURE Revision and Approval Summary TITLE: PLANT SITE METER 0 LOGICAL SYSTEM
- 1. Prepared 2. QA Concurrence i ,
ator Date Date DvM
- 3. Reco$end pproval/Q-List No 4. PRC Reviewed
/) int1km Head Wl9b6
' Da' e
?Ab6Ncd MYO
' Date artp! t / //gr S)-f/d
- 5. Approved 6. ATMS Incorporated w L s1oeln Date 5.33-23 ~
Q Plant ManageW ' Date
- 7. Biennial Review Date ,
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PALISADES NUCLEAR PLANT Proc No EI-6.7 EMERGENCY IMPLEMENTATION PROCEDURE Revision 0 Page i TITLE: PLANT SITE METEOROLOGICAL SYSTEM Table of Contents Page 1.0 PERSONNEL RESPONSIBILITY . . . . . . . . . . . . . . . . . . . . . I 2.0 PURPOSE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 3.0 INITIAL CONDITIONS AND/OR REQUIREMENTS . . . . . . . . . . . . . . 1 4.0 PROCEDURE . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 4.1 USING CONTROL ROOM METEOROLOGICAL DISPLAY . . . . . . . . . . . . 1 4.2 USING REMOTE ACCESS METEOROLOGICAL DISPLAY . . . . . . . . . . . . 4 5.0 ATTACHMENTS . . . . . . . . . . . . . . . . . . . . . . . . 8 ATTACHMENTS Attachment 1, " Palisades Meteorological System Parameter Status Codes and System Status Codes" l
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PALISADES NUCLEAR PLANT Proc No EI-6.7 EMERGENCY I!PLE.'IENTATION PROCEDURE Revision 0 Page 1 of 8 TITLE: PLANT SITE t!ETEOROLOGICAL SYSTE:1 1.0 PERSONNEL RESPONSIBILITY The Chemistry / Health Physics Support Group Leader is responsible for the implementation of this procedure. In the absence of a Chemis-try/licalth Physics Support Group Leader, the Site Emergency Director shall delegate this responsibility.
2.0 PURPOSE To provide a procedure to access the Plant site meteorological system for meteorological data required in the Offsite Dose Caiculations.
3.0 INITIAL CONDITIONS AND/0R REQUIREMENTS
- a. This procedure shall be implemented as required per EI-6.0.
- b. Data and results from this procedure should be recorded on the Offsite Dose Worksheet, Attachment 1 of EI-6.0 in Section III.1.
, c. A TI silent 700 Terminal is required for remote access (Sec-tion 4.2).
4.0 P?.0CEDURE 4.1 USING CONTROL ROOM METEOROLOGICAL DISPLAY 4.1.1 This is the preferred method; if the meteorological data display is not available in the Control Room, go to Part 4.2.
eiO383-0044a154
PALISADES NUCLEAR PLANT Proc No EI-6.7 EMERGENCY IMPLEMENTATION PROCEDURE Revision 0 Page 2 of 8 TITLE: PLANT SITE METEOROLOGICAL SYSTEM 4.1.2 The meteorological display in the Control Room is updated every 15 minutes automatically. The printout should be in the form of the following example:
SITE PALI PALI PALI PALI PALI PALI PALI PALI HEIGHT 10-M 6010 10-M 10-M 10-M 60-M 60-M 60-M PARAMETER TEMP DELT WS WD SGMH WS WD SGMH UNITS C C MPH DEG DEG MPH DEG DEG 1
AVG ENDINGS-EST
- 03/27/83 22:00 3.4 -0.38 7.45 54. 11.8 11.85 60. 6.0 STATUS 00* 0** 0 0 0 0 0 0 0 03/27/83 22:15 3.2 -0.40 7.42 52. 11.6 11.56 58. 6.3 :"
STATUS 00 0 0 0 0 0 0 0 0 ',
03/27/83 22:30 3.1 -0.40 7.40 51. 13.8 11.52 53. 6.2 STATUS 00 0 0 0 0 0 0 0 0
' 03/27/83 22:45 3.0 -0.40 8.35 35. 12.0 11.66 44. 8.0 STATUS 00 0 0 0 0 0 0 0 0 03/27/83 23:00 2.6 -0.40 8.00 10. 10.8 12.23 20. 5.6 i STATUS 00 0 0 0 0 0 0 0 1 0
03/27/83 23:15 2.2 -0.41 9.21 3. 13.3 12.84 13. 7.1 '
STATUS 00 0 0 0 0 0 0 0 0 g it
- = System Status
- 3
- = Parameter Status ~!
Where: ~
TEMP = Air temperature *C ' '
DWPT = Dew Point *C '
DELT = Temperature. difference between 60 meters and 10 meters
= Wind speed in miles per hour WS -
WD =
. Wind direction from which the wind is blowing (degrees) '
. SGMA = Sigma theta (horizontal wind direction standard deviation in degrees) s .
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t PALISADES NUCLEAR PLANT Proc No EI-6.7 i
EMERGENCY IMPLEMENTATION PROCEDURE Revision 0 Page 3 of 3 TITLE: PLANT SITE METEOROLOGICAL SYSTEM ~
t NOTE: The above display is repeated after six 15 minute periods have been printed. Status information is described in Attachment 1.
E 4.1.3 Verify the parameter status to be less thsa 100 for the "10-M WS" and "10-M WD" c31umns (10-meter wind speed (mph) and 10-meter wind direction from which wind is coming from, respectively). Record readings on worksheet, items (A) and (B) respectively. Mark 10 meters on worksheet.
NOTE: If parameter status is not less than 100 for the 10 meter wind data, check the status for "60-M WS" and "60-M WD" column. If status is less than 100, multiply WS by .77 and record data on worksheet, j items (A) and (B) respectively. Mark 60 meters on worksheet. If it is not less than 100, go to Procedure EI-6.8 to obtain meteorological data.
4.1.4 Verify the parameter status to be less than 100 for the "6010 DELT" column (60-10 meter temperature differential) and record value on worksheet, item (C).
1 NorE: If status is not less than 100, go to , Step 4.1.6.
4.1.5 Use Table 4.1 of this procedure in conjunction with Parameter DELT to determine stability class.
TABLE 4.1 Stability DELT Class Pa rameter
- v. A <-0.95 B .95 to -0.85
.84 to -0.75 C
D .74 to -0.25 E .24 to +0.75 F +.76 to +2.0 G >+2.0 i
Record the stability class on worksheet, item (D). All required meteorological data has now been recorded; continue with next j procedure as required per EI-6.0.
l j- *******
Steps 4.1.6-4.1.7 are needed only if temperature 4**f*e
- ?**<
j differential-data are not available. *******
l 4.1.6 Verify the parameter status to be less than 100 for the ."10-M SGMA" column (10-meter sigma theta) and record the value on worksheet, item (C).
NOTE: If the parameter status for the 10-meter sigma theta is not less than i 100, verify the parameter status for "60-M SGMA" to be less than 100 '
l and reccrd on worksheet, item (C). If it is not less than 100, go to Procedure EI-6.8 to get meteorological data.
eiO383-0044a154
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PALISADES NUCLEAR PLANT Prce No EI-6.7 EMERGENCY IMPLEMENTATION PROCEDURE Revision 0 Page 4 of 8 TITLE: PLANT SITE METEOROLOGICAL SYSTEM
~4.1.7 Use Table 4.2 and the parameter SGMA to determine stability class.
TABLE 4.2 Stability
- Class SGMA A >22.5 B 17.6 tc,22.5 C 12.5 to 17.5 D 7.5 to 12.4 E 3.8 to 7.4 I
F 2.1 to 3.7 G .
< 2.1 Record stability class worksheet,' item (D). All required meteorological data has now been recorded; continue with next procedure as required per EI-6.0.
4.2 USING REMOTE ACCESS METEOROLOGICAL DISPLAY To be used when the Control Room meteorological display is not i available or to obtain a Plant site meteorological display outside of the Control Room.
4.2.1 Power Up the Terminal Connect the power supply cord to the terminal and plug the cord into a power socket.
- NOTE: To use the Control Room meteorological terminal to obtain meteorological data remotely, the terminal must be unplugged from the modem (black line) and the bl'ack plug Inserted in its place.
4.2.2 Move the toggle switch located on the rear right-hand side of the
. terminal to the "on" position. You should be able to hear the terminal fan motor start up.
, 4.2.3 There are three rocker switches located on the front right-hand side of the terminal. They are labeled low speed, half dup, and on line.
- a. Deptess the right side of the one labeled low speed.
.b. Depress the left side of the one labeled half dup.
at. Depress the left side of the one labeled on line.
' 4.2.4 There is one rocker switch located on the front left-hand side of the terminal labeled "NUM". Depress the right-hand side of this switch.
eiO383-0044a154 '
l
.~
. - . ~ .
PALISADES NUCLEAR PLANT Proc No El-6.7 EMERGENCY IMPLEMENTATION PROCEDURE Revision 0 Page 3 of 8 TITLE: PLANT SITE l1ETEGR0 LOGICAL SYSTEM NOTE: The above display is repeated af ter six 15 minute periods have been printed. Status information is described in Attachment 1.
4.1.3 Verify the parameter status to be less than 100 for the "10-M WS" and "10-M WD" columns (10-meter wind speed (mph) and 10-meter wind direction from which wind is coming from, respectively). Record readings on worksheet, items (A) and (B) respectively. Mark 10 meters on worksheet.
NOTE: If parameter status is not less than 100 for the 10-meter wind data, check the status for "60-M WS" and "60-M WD" column. If status is less than 100, multiply WS by .77 and record data on worksheet, items (A) and'(B) respectively. Mark 60 meters on worksheet. If it is not less than 100, go to Procedure EI-6.8 to obtain meteorological data.
4.1.4 Verify the parameter status to be less than 100 for the "6010 DELT" column (60-10 meter temperature differential) and record value on worksheet, item (C).
NOTE: If status is not less than 100, go to Step 4.1.6.
4.1.5 Use Table 4.1 of this procedure in ccajunction with Parameter DELT to determine stability class.
TABLE 4.1 Stability DELT Class Pa rameter A <-0.95 B .95 to -0.85 C .84 to -0.75 D .74 to -0.25 E .24 to +0.75 F +.76 to +2.0 G >+2.0 Record the stability class on worksheet, item (D). All required meteorological data has now been recorded; continue with next procedure as required per EI-6.0.
- f* M
- f* M Steps 4.1.6-4.1.7 are needed only if temperature *** M differential data are not available. **W*
4.1.6 Verify the parameter status to be less than 100 for the "10-M SGMA" column (10-meter sigma. theta) and record the value on worksheet,
{ item (C). -
NOTE: If the parameter status for the 10-meter sigma theta is not less than 100, verify tha parameter status for "60-M SGMA" to be less than 100 -
i and record on worksheet, item (C). If it is not less than 100, go to
!- Procedure EI-6.8 to get meteorological data.
eiO383-0044a154 L-
)
PALISADES NUCLEAR PLANT Proc No EI-6.7 EMERGENCY IMPLEMENTATION PROCEDURE Revision 0 Page 4 of 8 TITLE: PLANT SITE METEOROLOGICAL SYSTEM 4.1.7 Use Table 4.2 and the parameter SGMA to determine stability class.
TABLE 4.2 Stability
- Class SGMA A >22.5 B 17.6 to 22.5 C 12.5 to 17.5 D 7.5 to 12.4 E 3.8 to 7.4 F 2.1 to 3.7 G < 2.1 Record stability class worksheet, item (D). All required' meteorological data has now been recorded; continue with next procedure as required per EI-6.0.
, 4.2 USING REMOTE ACCESS METEOROLOGICAL DISPLAY
~
To be used when the Control Room meteorological display is not available or to obtain a Plant site meteorological display outside of the Control Room.
4.2.1 Power Up the Terminal m
Connect the power supply cord to the terminal and plug the cord into a 3
power socket.
l
. NOTE: To use the Control Room meteorological terminal to obtain meteorological data remotely, the terminal must be unplugged from the modem (black line) and the black plug inserted in its place.
1 4.2.2 Move the toggle switch located on the rear right-hand side of the
, terminal to the "on" position. You should be able to hear the l terminal fan motor start up.
4.2.3 There are three rocker switches located on the front right-hand side o, ' of the terminal. They are labeled low speed, half dup, and on line.
A a. Depress the right side of the one labeled low speed.
, b. Depress the left side of the one labeled half dup, g c. Depress the left side of the one labeled on line. '
4.2.4 There is one rocker switch located on the front left-hand side of the C terminal labeled "NUM". Depress the right-hand side of this switch.
6 eiO383-0044a154
. . ~ . . . . .s. -
s .
PALISADES NUCLEAR PLANT Proc No EI-6.7 {
. EMERGENCY IMPLE.'!ENTATION PROCEDl:RE Revision 0 Page 5 of 8 TITLE: PLANT SITE MSTEOROLOGICAL SYSTE:1 4.2.5 Dialing In Dial:
764-8287 or 764-8288 (or portion needed for call) and wait for a tone. Place the telephone receiver in cradle cups with cord on the lef t side.
4.2.6 Logging In The green light next to the shift key should light.
4.2.7 Press the orange " RETURN" key. (The computer will ask for "PW?". )
4.2.8 T'jpe "C0" RETURN.
4.2.9 The computer will print a "?" when it is ready to accept command.
Display Meteorological Data NOTE: Occasionally, a poor telephone connection may cause some data to be incorrectly transmitted. If the computer does not " understand" a command which was apparently typed correctly or if computer output is garbled, simply re-enter.the command.
4.2.10 To receive the last averaging period's data, type "AV" and RETURN.
Parameter status is also given during the "AV" command. This status is in the form of a number. O is perfect. A value between 1 and 99 indicates one or more scans were invalidated. Between 100 and 999 indicates there was not enough valid data to calculate an average.
The last two digits of the status indicate the problem. Invalid data is displayed with all 9s. (Status comments are explained in Attach-ment 1.)
For example:
?AV SITE PALI PALI PALI PALI PALI PALI PALI PALI PALI HEIGHT 10-M 10-M 6010 10-M 10-M 10-M 60-M 60-M 60-M PARAMETER TEMP DWPT DELT WS WD SGMA WS WD SGMA
- UNITS C C C MPH DEG DEG MPH DEG DEG l AVG ENDING-EST 01/14/83 13
- 00 2.0 -1.1 -0.51 20.24 271. 13.0 28.88 266. 7.3 i STATUS 00* 0** 0 0 0 0 0 0 0
- = System status
- = Parameter status eiO383-0044a154
PALISADES NUCLEAR PI. ANT Proc No EI-6.7 EMERGENCY IMPLEMENTATION FROCEDURE Revision 0 Page 6 of 8 TITLE: PLANT SITE METEOROLOGICAL SYSTEM SITE PALI PALI PALI PALI PALI PALI PALI HEIGHT SHED 10-M 10-M 10-M 10-M 10-M 10-M PARAMETER TEMP WS-A WD-A WG-A WS-B WD-B SG-B UNITS C MPH DEG DEG MPH DEG DEG AVE ENDING-EST 01/14/83 13:00 22.0 20.24 271. 13.0 19.34 266. 12.2 STATUS 00 0 0 0 0 0 0 0 Where:
TEMP = Air temperature *C DWPT = Dew point *C DELT = Temperature difference between 60 meters and 10 meters WS = Wind speed in miles per hour WD = Wind direction from which the wind is blowing (degrees)
SGMA = Sigma theta (horizontal wind direction standard deviation in degrees)
NOTE: The second row of data beginning with the paramter "SHED TEMP" is provided for information purposes only and is to be ignored. When data for several averaging periods are printed out, all of the "first row" averages are printed first, followed by all of the "second row" averages.
4.2.11 Verify the parameter status to be less than 100 for the "10-M WS" and "10-M WD" columns (10-meter wind speed (mph) and 10-meter wind direction respectively). Record readings on worksheet, items (A) and (B) respectively. Mark 10 meters on worksheet.
. NOTE: If the parameter status is not less than 100 for the 10-meter wind
.c data, check the status for "60-M WS" and "60-M WD" column. If parameter status is less than 100, multiply WS by .77 and record data on worksheet, items (A) and (B) respectively. Mark 60 meters on worksheet. If it is not less than 100, go to Procedure 6.8 to obtaia meteorological data.
4.2.12 Verify the parameter status to be less than 100 for the "6010 DELT" column (60-10 meter temperature differential) and record value on worksheet, item (C).
NOTE: If parameter status is not less than 100, go to Step 4.2.14.
-eiO383-0044a154 j J 'r X - - --
PALISADES NUCLEAR PLANT Proc No El-6.7 T.MERGENCY IMPLEMENTATI0h PROCEDURE Revision 0 Page 7 of 8 TITLE: PLANT SITE METEOROLOGICAL SYSTEM 4.2.13 Use Table 4.1 of this procedure in conjunction with Parameter DELT to j determine stability class.
TABLE 4.1 Stability DELT Class Pa rame te r A <-0.95 B .95 to -0.85
, C .84 to -0.75 i D .74 to -0.25 l E .24 to +0.75 F +.76 to +2.0
, G >+2.0 Record the stability class on worksheet, item (D). All required meteorological data has now been recorded; continue to next procedure as required per EI-6.0.
l *f*** Steps 4.2.14 through 4.2.15 are needed only if f***
- f**** temperature differential data is not available, f****
1 4.2.14 Verify the parameter status to be less than 100 for the "10-M SGMA" column (10-meter sigma theta) and record the value on worksheet, 4
item (C).
NOTE: If the parameter status for the 10-meter sigma theta is not less than 100, verify the status for "60-M 3GMA" to be less than 100 and reccrd on worksheet, item (C). If it is not less than 100, go to Procedure i EI-6.8 to obtain meteorological data.
4.2.15 Use Table 4.2 and the parameter SGMA to determine stability class.
TABLE 4.2 1
j Stability
- Class SGMA i
A >22.5 B 17.6 to 22.5 C 12.5 to 17.5 D 7.5 to 12.4 E 3.8 to 7.4 i F 2.1 to 3.7 G < 2.1 i
Record stability class on worksheet, item (D). All required meteorological data has now been recorded; continue to next procedure as required per EI-6.0.
4.2.16 To terminate a session, type "BB" and return. The program may be restarted by typing the orange " RETURN" key.
- eiO383-0044a154-t
1 l
PALISADES NUCLEAR PLANT Proc No EI-6.7 EMERGENCY IMPLEMENTATION PROCEDURE Revision 0 Page 8 of 8 TITLE: PLANT SITE METEOROLOGICAL SYSTEM l When done, hang up the phone.
Steps 4.2.17-4.2.19 are used only if meteorological data for ******
prior periods or for specified time intervals are needed. ******
4.2.17 To receive the last n averaging period's data, type "AV,T= n" where n is an integer typed from the keyboard.
NOTE: Caution should be used in printing a large number of past averages.
Once the command is entered and the computer starts printing the averages, there is no way to stop the printing until all requested averages have been printed. If the phone is hung up and then re-dialed, the computer will continue to print the rest of the averages as soon as the telephone connection has been re-established.
4.2.18 To receive the average for a period ending at ddhhmm, where dd is a day of the month, hh is the time in hours and mm is the time in minutes, type "AV,T=ddhhmm" and RETURN. If dd is not submitted, the default is the current day. Minutes cust be entered in quarter hour increments, ie, 00, 15, 30 and 45.
4.2.19 To receive the average for periods between two times, type "AV,T=ddhhmmt-ddhhmm2." Again the default for dd is the current date.
4.3 Continue with next procedure as re, quired, per EI-6.0.
5.0 ATTACHMENTS Attachment 1, " Palisades Meteorolegical System Parameter Status Codes and System Status Codes" l
I l
1 eiO383-0044a154
- n.
- . ~
.y _
Proc No EI-o.7 Attachment 1 Revision 0 Page 1 of 1 PALISADES METEOROLOGICAL SYSTES!
PARA >lETER STATUS CODES AND SYSTEM STATUS CODES Parameter status codes indicat e any abnormal or non-ambient condition present for a specific parameter. Parameter statuses listed with the "AV" ccmmand reflect the " worst" (highest numbered) status f;r the entirc averaging period.
PARAMETER STATUS CODES Code Meaning 0 Normal 1 Wind Direction or Sigma Theta Cannot Be Calculated 10 Data Acquisition Disabled Via "AC" Command 30 Analyzer in Span Recovery Period 31' Analyzer in Zero Mode 32 Analyzer in Span Mode 40 Input Voltage Cannot Be Converted 41 Instantaneous Value Too Low 42 Instantaneous Value Too High 50 Transmission Time-Out on Status Request 51 Transmission Time-out on Data Request 52 Transmission Error on Status Request 53 Transmission Error on Data Request 60 Analyzer Flame Out 70 Instrument Out of Service 71 Aspirator Failure A value of 100 is added to the above codes for an invalid average.
- SYSTEM STATUS CODES System status codes indicate any abnormal condition which may have occurred during a given averaging period. The status is reset to 0 at the beginning of each averaging period.
Code Meaning 0 No rmal 1
Time Correction 2 Storage Reallocated 3 Power Failure 4 System Start-Up or Restart 5 Instrument Shelter Temperature Low 6 Instrument Shelter Temperature High eiO383-0044bl54
1 l
Proc h "I-6.4 '
Revision 0 Date 5/2?/83 PALISADES NUCLEAR PLANT EMERGENCY I!!PLEMENTA'rION PROCEDURE Revision and Approval Summary TITLE: RELEASE / POTENTIAL RELEASE DETERMINATION FROM C0h"rAINMENT HIGli RANGE MONITORS i
l
- 1. Prepared 2. .QA Concurrence
]/ b bM N $lik6 datio r 'Date
/VA Date h e RAffht)g
- 3. Pecommend Approval /Q-List es No 4. PRC Reviewed 1
l //n 'Nifik i 5lN/?3
'Da tie TA%c dL O'd2 rgmentHead - /y,/g,,5'3 , f a Date I
- 5. Approved 6. ATMS Incorporated w3 A-7% /h J
5 9 3 <S_3 i QPlantMan'geC a Date Date
- 7. Biennial Review Date eiO383-0042dl54
PALISADES NUCLEAR PLANT Proc No El-6.4 EMERGENCY IMPLEt!ENTATION l'ROCEDt*RE Revision 0 Page i
~
TITLE: RELEASE / POTENTIAL RELEASE DETERMINATION FRO 1 CONTAINMENT llIGli RANGE MONITORS Table of Contents Page 1.0 PERSONNEL RESPONSIBILITY . . . . . . . . . . . . . . . . . . . . I 2.0 PURPOSE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 3.0 INITIAL CONDITIONS AND/OR REQUIREMENTS . . . . . . . . . . . . . . 1 4.0 RELEASE RATE . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 4.1 IIIGli RANGE EFFLUENT MONITOR READING . . . . . . . . . . . . . . . 1 5.0 ATTAClfMENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 ATTACliMENTS Attachment 1, "Cantainment liigh Range Monitor Conversion Factors" eiO383-0042c154
_ - . - - . ... ._ _ _ - - __ .-- . - _ - _ . . . = .
3 PALISADES NUCLEAR PLANT Proc No EI-6.4 EMERGENCY IMPLEMENTATION PROCEDURE Revision 0 Page 1 of 2 TITLE: RELEASE / POTENTIAL RELEASE DETERMINATION FROM CONTAINMENT IIIdi! RANGE MONITORS 1.0 PERSOMNEL RESPONSBILITY The Chemistry /liealth Physics Support Group Leader shall implement this procedure. In the absence of a Chemistry /Ilealth Physics Support Group Leader, the Site Emergency Director shall delegate this responsibility.
2.0 PURPOSE This procedure provides a release rate / potential release rate from radioactive material released into containment. This data is used as input to offsite dose calculations.
3.0 INITIAL CONDITIONS AND/OR REQUIREMENTS
- a. This procedure shall be implemented as required per EI-6.0.
- b. This procedure assumes a release from the Primary Coolant System into the Containment atmosphere.
- c. If there is a breach in containment, the leak rate should be determined by the best method available.
4.0 RELEASE RATE 4.1 HIGli RANGE EFFLUENT MONITOR READING
- a. Determine if there has been or is a' release from the Primary Coolant System to the containment atmosphere.
- b. Determine the time past shutdown (hours) and record on worksheet, I
item (A).
- c. Mark the monitor frca. which the reading is taken on worksheet, item (B), RIA-2321 or HIA-2322.
- d. Record the monitor reading on worksheet, item (C), in R/hr above background. The readout for both monitors is on Control Room Panel C-11A or the Critical Functions Monitor.
- e. Obtain from Attachment I the YI " conversion factors for the specifiedtimepastshutdownfgfhnoble gas. Record on worksheet, ..
item (D).
f.
Determine the containment leak rate in ec/sec. If no breach of
- containment has occurred, then the design leak rate should be used (0.1%/ day = 537.0 cc/sec). If there is a breach in containment,
' then the leak rate must be determined by the best available method. Record on worksheet, item (E).
eiO383-0042a154 r
_ _ . - - . . _ . , . _ . , - . _ ._- . . . . - - , ~ , _ . _ _ , - - , _ , . , , . . -. .-
4 PALISADES NUCLEAR PLANT P oc No EI-6.4 EMERGENCY IMPLEMENTATION PROCEDURE Revision 0 Page 2 of 2 TITLE: RELEASE / POTENTIAL RELEASE DETERMINATION FROM CONTAINMENT llIGl! RANGE MONITORS
- g. Calculate noble gas release rate (QN) as follows:
" "' # Noble gas pCi/cc (D:
QN =
reading R/hr (C) x conversion R/hr x
- factor -
-6 -
leak rate ec/sec (E) x 1 x 10 Ci/pci Record on worksheet, item (F)
- h. Calculate the I-131 dose equivalent release rate (QI) as follows:
QN (F) x 1.UE-3 Record on worksheet, item (G) 4.1.1 Proceed to next procedure as required, per EI-6.0, 5.0, ATTACHMENTS Attachment 1, " Containment High Range Monitor Conversion Factors" 7 .
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Proc No EI-6.3 Revision 0 Date 5/23/2' PALISADES NUCLEAR PLANT E.'!E."0FNCY It!PLE!!ENTATION PROCELL'RE F.evision and Approval Summary TITLE: RELEASE RATE DETER!!INATION FR0!! IIIGli RANGE EFFLUENT t!ONITORS
- 1. Prepared 2. QA Concurrence
// ll $ ? 53 0 g/ginaior 11a te Date f? } Y { Tlf55
- 3. Recomme4 Approval /Q-List No 4. PRC Reviewed
?,
3[/?V$r!~ 5//9/T3
~
pa Date A. W he4 ..-f-m ?
~ g. 5.d ci(-
i ent llead *Date
- 5. Approved ; 6. ATt!S Incorporated m
wPlant4<3 flanage
_fn 5heIB Date 5 Q3--f 3 Date
- 7. Biennial Review Date eiO383-0041g154
PALISADES NUCLEAR PLANT Proc No EI-6.3 EMERGENCY IMPLEMENTATION PROCEDURE Revision 0 Page i TITLE: RELEASE RATE DETERMINATION FROM IIIGH RANGE EFFLUENT MONITORS l Table of Contents l Page 1.0 PERSONNEL RESPONSIBILITY . . . . . . . . . . . . . . . . . . . . . 1
.; 2.0 PURPOSE ......... . . . . . . . . . . . . . . . . . . . . 1 3.0 INITIAL CONDITIONS AND/OR REQUIREMENTS .
t
. . . . . . . . . . . . . I 4.0 RELEASE RATE DETERMINATION . . . . . . . . . . . . . . . . . . . . 1 4.1 HIGH RANGE EFFLUENT MONITOR READING . . . . . . . . . . . . . . . 1 4.2 MONITOR RESPONSE FACTOR . . . . . . . . . . . . . . . . . . . . . 1 4.3 RELEASE R,}TE .
. . . . . . . . . . . . . . . . . . . . . . . . . 2 i
5.0 ATTACHMENTS a
...... . . . . . . . . . . . . . . . . . . . . . 2 ATTACHMENTS 3
Attachment I, " Stack Monitor Response (0 to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />)"
Attachment 2, " Stack Monitor Response (0 to 30 days)"
Attachment 3, " Steam Dump Monitor Response (0 to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />)"
Attachment 4, " Steam Dump Moniter Response (0 to 30 days)"
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PALISADES NUCLEAR PLANT Proc No EI-6.3 EMERGENCY IpPLEMENTATION PROCEDURE Revision 0 Pa ge 1 o f 2 TITLE: RELEASE RATE DETERMINATION FROM HIGH RANGE EFFLUENT MONITORS 1.0 PERSONNEL RESPONSBILITY The Chemistry / Health Physics Support Group Leader shall implement this procedure. In the absence of a Chemistry / Health Physics Support Group Leader, the Site Emergency Director shall delegate this responsibility.
2.0 PURPOSE This procedure provides a release rate for radioactive effluents from the Plant stack or steam dumps. This data is used as input to offsite dose calculations.
3.0 INITIAL CONDITIONS AND/OR REQUIREMENTS
- a. This procedure shall be ieplemented as required per EI-6.0.
- b. Data and results from this procedure should be recorded on the
, Offsite Dose Worksheet, Attachment 1 to EI-6.0, in Section I.3.
- c. High activity levels in the Penetration Fan Room filter box, (629' level), may cause unusually high readings on these instruments, whi:h would indicate a higher release rate than is actually occurring.
4.0 RELEASE RATE DETEPMINATION 4.1 HIGH RANGE EFFLUENT MONITOR READING
- a. Monitor readouts are installed in the northeast corner of the viewing gallery.
- b. An operational check should be performed on the monitors per HP 9.14 with one exception. Due to the remote location of the l detector, the detector should not be exposed to a radiation field l
l during the check. Other checks including battery test and two l
minute warm-up should be performed.
- c. Obtain a reading from the affected monitor. Record monitor reading on worksheat, item (A). Note affected monitor on worksheet.
l
, d. Convert monitor reading from mR/hr to R/hr by multiplying original reading by 1.0 E-3. Record on worksheet, item (B).
4.2 MONITOR RESPONSE FACTOR
- a. Obtain Response Factor as marked on appropriate monitor. Record on worksheet, item (C).
eiO383-0041a154
9 PALISADES NUCLEAR PLANT Proc No EI-6.3 EMERGENCY IMPLEMENTATION PROCEDURE Revisien 0 Page 2 of 2 TITLE: RELEASE RATE DETERMINATION FROM HIGH RANGE EFFLUENT MONITORS'
, b. Multiply monitor reading (R/hr), Item (B) by -Response Factor, Item (C) to obtain a corrected reading. Record on worksheet, j item (D). 1 4.3 RELEASE RATE I
- a. Determine elapsed time between reactor shutdown and monitor reading. If elapsed time is 5 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, record elapsed time on worksheet, item (E) in hours. If elapsed time is > 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,
^
record elapsed time on worksheet, item (E) in days. Circle appropriate units on the worksheet. .a
- b. Use the table below to determine which attachment to use to obtain
- the conversion factor, R/hr to Ci/sec. j
, ELAPSED TIME ,J 5 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> > 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> . ]
i ,
Stack Monitor Attachment 1 Attachment 2 j 4
Steam Dump Monitor Attachment 3 Attachment 4 ;)
-- .y Record conversion factor on worksheet, item (F) and mark j -j attachment used. '- fj EA
~
- c. Divide corrected monitor reading (D) by conversion factor (F) to x) obtain noble gas release rate, QN. Record on worksheet, item (G). f!
.a
- d. Multiply noble gas release rate (G) by 1.0E-3 to obtain Iodine-131 i dose equivalent release rate, QI. Record on worksheet, item (H).
4 4.4 Proceed to next procedure, per 'EI-6.0. -
5.0 ATTACHMENTS ,
5.1 Attachment 1, " Stack Monitor Response (0 to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />)" '
-5.2 Attachment' 2, " Stack Monitor Response (0 to 30 days)"
- 5.3 Attachment 3, " Steam Dump Monitor Response (0 to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />)"
- Attachment ["SteamDumpMonitorResponse(0to30 days)"
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1 Proc-No EI-6.9 I
Revision 0 Date 3/23/33 PALISADES NUCLEAR PLANT EMERGENCY It!PLE!!ENTATION PROCEDURE
, , Revision and Approval Summary TITLE: OFFSITE DOSE CALCULATION - STRAIGIIT LINE GAUSSIAN (CALCULATOR METHOD l
- 1. ared 2. QA Concurrence Prep!
ko E!1 kd i SMk2
//gr - nator' 'Date tm Date L' w,ap /2 4 J W a f 5
- 3. No 4. PRC Reviewed Recommend. Approval /Q-List (Yes r
l1/ilm she at Head Date XMLA
/ ,' );g f3 t'/O z
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Date
- 5. . Approved 6. ATMS Incorporated m wk Sl%e)t3 5 A3-23 Plant Managed ' Date Date
- 7. Biennial Review Date eiO383-0046c15'4
O O PALISADES NUCLEAR PLANT Proc No EI-6.9 EMERGENCY IMPLEMENTATION PR0CEDURE ,
Revision 0 Page i TITLE: OFFSITE DOSE CALCULATION - STRAIGliT LINE GAUSSIAN (CALCULATOR METHOD)
Table of Contents Page 1.0 PERSONNEL RESPONSIBILITY . . . . . . . . . . . . . . . I 2.0 PURPOSE . . . . . . . . . . . . . . . . . . . . . . . . 1 3.0 INITIAL CONDITIONS AND/OR REQUIREMENTS . . . . . . . . . . 1 4.0 PROCEDURE . . . . . . . . . . . . . . . . . . . . . . . . . . . I 4.1 ASSEMBLING CALCULATOR AND PRINTER . . . . . . . . . . . . . . . 1 4.2 INITIALIZATION OF CALCULATOR AND PRINTER . . . . . . . . . 1 4.3 RUNNING THE PROGRAM . . . . . . . . . . . . . . . . . . . . . . 2 4.4 READING THE PRINTOUT . . . . . . . . . . . . . . . . . . . . . . 3 4.5 RECORDING DATA . . . . . . . . . . . . . . . . . . . . . . . . 3 5.0 ATTACHMENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 eiO383-0046bl54
PALISADES NUCLEAR PLANT Proc No EI-6.9 EMERGENCY IMPLEMENTATION PROCEDURE Revision 0 Page 1 of 4 TITLE: OFFSITE DOSE CALCULATION - STRAIGHT LINE GAUSSIAN (CALCULATOR PETHOD) 1.0 PERS'ONNEL RESPONSIBILITY The Chemistry / Health Physics Support Group Leader is responsible for the implementation of this procedure. In the absence of a Chemis-try/ Health Physics Support Group Leader, the Site Emergency Director .
shall delegate this responsibility.
2.0 PURPOSE To provide a procedure to utilize the Hewlett Packard HP-41CV calculator to provide offsite dose assessment calculations.
3.0 INITIAL CONDITIONS AND/OR REQUIREMENTS
- a. This procedure shall be implemented as required pe'r EI-6.0.
- b. Data and results from this procedure should be recorded on the I
Offsite Dose Worksheet, Attachment I to EI-6.0 in Section IV.I.
- c. A pre programmed Hewlett-Packard HP-41CV is required to perform this procedure. If this calculator is unavailable, go to EI-6.10 to' calculate offsite dose.
i d. Input to this section is obtained from previously completed sections of the Offsite Dose Worksheet. Pertinent data is
- enclosed in boxes for rapi,d identification.
4.0 PROCEDURE 4.1 ASSEMBLING CALCULATOR AND PRLNTER NOTE: The calculator and printer should both be "0FF" prior to interconnec-ting the units. Make sure that both the calculator and printer are connected to the charging unit (s).
Calculator may have card reader attached to top of calculator. If card reader is in place only one port is visible to connect printer.
If card reader is not attached, use any port on bottom rear of calculator. A protective cover may have to be removed to gain access to a port. The printer plug in unit should be inserted so that the stepped side is at the bottom and the flat side on top.
] 4.2 INITIALIZATION OF CALCULATOR AND PRINTER 4.2.1 Turn printer "0N". Red " POWER" light should come on. Set the " Mode" switch to the " Norm" position and the " Intensity" switch to the miodle position.
- NOTE: If the red power light does not come on or the battery light does come ,
on, proceed to the manual dose assessment procedure EI-6.10.
eiO383-0046a154
PALISADES NUCLEAR PLANT Proc No EI-6.9 EMERGENCY IMPLEMENTATION PROCEDURE Revision 0 Page 2 of 4 TITLE: OFFSITE DOSE CALCULATION - STRAIGHT LINE GAUSSTAN (CALCULATOR METHOD) 4.2.2 Turn calculator "0N". If the word " USER" does not appear in the display, press the " USER" switch to activate the mode.
NOTE: If the calculator display does not light up, proceed to the manual dose assessment procedure EI-6.10. .
4.3 RUNNING THE PROGRAM 4.3.1 Press the " SIN" button, (2nd Row, 3rd button from the left).
4.3.2 The first interrogation, "QN? CI/SEC", prompts for the noble gas release rate. Key in the proper number from the dose worksheet Sec-tion I and press the "R/S" key (lower right-hand corner).
NOTE: If an error is made while entering the data, the "+" key (middle right) can be pressed to erase the data prior to pressing the "R/S" key. If the "R/S" has been pressed, the program must be restarted by pressing the " SIN" button.
4.3.3 The next interrogation, "E-BAR N GAS MEV" prompts for the average ,
energy per disintegration. Key in the proper number from the dose .c worksheet Section II and press the "R/S" key.
4.3.4 The next. interrogation, "QI 131E CI/SEC", prompts for the dose equivalent Iodine-131 release rate. Key in the proper number from the dose worksheet Section I and press the "R/S" key.
. 4.3.5 The next interrogation, "REL HGT? METERS", prompts for the release height. Etter 9 (ground level) and press the "R/S" key.
4.3.6 The next interrogation, "U BAR?. MI/HR", prompts for the wind speed.
Key in the proper number from the dose worksheet Section III and press the "R/S" key.
l 4.3.7 The next interrogation, " START POINT", prompts for the distance in miles at which the dose assessments should start. Enter 9 and press t
the "R/S" key.
l NOTE: When a 9 is entered, the program will print doses for .5,1,1.5, 2.0, 5.0 and 10 miles. If a distance other than is entered, the program will start at that distance. The State of Michigan requires that dose assessment be done for .5, 2, 5 and 10 miles.
4.3.8 The final interrogation, " STABILITY?", prompts the user to select the Pasquill stability classification (A-G).
NOTE: Pressing the blue key starts the program running. Do N'OT push the "R/S" key to start the program running. Once the program is running, the "R/S" key can be pressed to stop the program and pressed again to -
restart the program at the point it was stopped. Pressing the " SIN" key will restart the program from the beginning. The calculator
" BEEP" function is activated by the program when the noble gas (whole eiO383-0046aI54
PALISADES NUCLEAR PLANT Proc No EI-6.9 EMERGENCY IMPLEMENTATION PROCEDURE Revision 0 Page 3 of 4 TITLE: OFFSITE DOSE CALCULATION - STRAIGilT LINE GAUSSIAN (CALCULATOR !!ETIf0D) body) dose rate reaches 500 mrem /hr and/or when the child thyroid dose rate reaches 1000 mrem /hr which represent Protective Action Guidelines for consideration of evacuation.
4.4 READING THE PRINTOUT Distance from release point " DISTANCE MILE" Iodine 131 dose equivalent concentration (Ci/m3 ) "CONCEN IODINE" Child thyroid dose rate (mrem /hr) " MREM /IIR C-TIIY" Noble gas concentration (Ci/m a) "CONCEN N GAS" Finite cloud whole body dose
, rate (mrem /hr) " MREM /HR W BODY" Off axis whole body dose rate (distance units are the same as downwind distance units) " MREM /HR DIS FROM X-AXIS" Vertical distance to .1 mrem /hr whole.
body dose rate (distance units are the same as downwind distance units) " ALT 0 .1 MR/HR" Plume arrival time (minutes) at the specified downwind distance "ARR TIME MIN" Relative concentration (X/Q sec/m3 value at the specified downwind distance "glII OVER Q" 4.5 RECORDING DATA 4.5.1 Record the child thyroid dose cate on the dose worksheet, Sec-tion IV.1, item (A) for .5, 2, 5 and 10 miles and for any other specific distance of interest.
4.5.2 Record the I-131 dose equivalent concentration on the dose worksheet,.
Section IV.1, item (B) for .5, 2, 5 and 10 miles and for any other specific distances of interest.
4.5.3 Record the finite cloud while body dose rate on the dose worksheet,Section IV.1, item (C) for .5, 2, 5 and 10 miles and for any other specific distance of interest.
4.5.4 Estimate duration of release. Use two hours as a defa~ ult value.
Record on worksheet,Section IV.1, item (D).
4.5.5 Multiply child thyroid dose rate (A) by estimated duration (D) to obtain child thyroid dose commitment. Record the child thyroid dose commitment on the dose worksheet,Section IV.1, item (E).
eiO383-0046a154
PALISADES NUCLEAR PLANT Proc No EI-6.9 EMERGENCY IMPLEMENTATION PROCEDURE Revision 0 Page 4 of 4 TITLE: OFFSITE DOSE CALCULATION - STRAIGHT LINE GAUSSIAN
, (CALCULATOR METHOD) 4.5.6 Calculate the finite cloud whole body dose commitment by multiplying the whole body dose rate (C) by the estimated duration (D). Record on worksheet,Section IV.1, item (F),
4.5.7 Note on worksheet,Section IV.1, item (G) whether the doses are based on actual or potential releases.
4.5.8 Proceed to the next procedure as required per EI-6.0.
5.0 ATTACHMENTS 4
None 1
2 4
L i
eiO383-0046a154
- , , .;. 7 . _ ~ . _
4 Proc No EI-6.8 Revision 0 Date 5/23.'53 PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTATION PROCEDURE Revision and Approval Summary TITLE: BACKUP AND SUPPLEMENTAL METEOROLOGY
- 1. Prepared 2. QA Concurrence q
AJ ff 0/0 Nb
- i'gi a' tor Date Date hi $A SO&
- 3. Reco d proval /Q-List No 4. PRC Reviewed AhhwL 5% Date w%s; sub U,}'g g y tqig;' Date arjdt{t' Head
- 5. Approved 6. 'ATMS Incorporated 5
' ^ ' ^ '
' Plant ManageC W b diW/h Date
' .T~Q3-h3 Date l
- 7. Biennial Review I
Date
~
eiO383-0045d154
PALISADES NUCLEAR PLANT Proc No EI-6.8 EMERGENCY IMPLEMENTATION PROCEDURE Revision 0 Page i TITLE: BACKUP AND SUPPLEMENTAL METEOROLOGY Tabic of Contents Page 1.0 PERSONNEL RESPONSIBILITY . . . . . . . . . . . . . . I 2.0 PURPOSE . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 3.0 INITIAL CONDITIONS AND/OR REQUIREMENTS . . . . . . . . . . . . . 1 4.0 PROCEDURE . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 4.1 -ACCESSING TIIE WSI WEATHER SYSTEM . . . . . . . . . . . . . . . 1 4.2 DISPLAY SUPPLEMENTAL METEOROLOGICAL DATA AND FORECAST . . . . . 5 5.0 ATTAcaMtNTS . . . . . . . . . . . . . . . . . . . . . . 7 ATTACIIMENTS Attachment 1, " Supplemental Information" eiO383-0045c154 l
PALISADES NUCLEAR PLANT Proc No El-6.8 EMERGENCY IMPLEMENTATION PROCEDURE Revision 0 Page 1 of 7 TITLE: BACKUP AND SUPPLEMENTAL METCOROLOGY 1.0 PERSONNEL RESPONSIBILITY The Chemistry /llealth Physics Support Group Leader is responsible for the implementation of this procedure. In the absence of a Chemis-try/llealth Physics Support Group Leader, the Site Emergency Director shall delegate this responsibility.
2.0 PURPOSE To provide a backup procedure to access the Weather Services International (WSI) meteorological system and obtain meteorological data required in the of fsite dose calculations when onsite meteorolagical data is not available and to provide a procedure to obtain supplemental regional meteorological data, site specific meteorological forecast and precipitation data as required.
3.0 INITIAL CONDITIONS AND/OR REQUIREMENTS
- a. This procedure shall be implemented as required per EI-6.0.
- b. Steps 4.1.1 through 4.1.15 of this procedure shall be implemented when there is a potential for or an actual release of radioactive material and onsite meteorological data is not available.
Steps 4.2.1 through 4.2.7 of this procedure shall be implemented when there is a need for regional meteorological data, site-specific meteorological forecast and precipitation data.
- c. Data and results from this procedure should be recorded on the Offsite Dose Worksheet, Attachment 1 of EI-6.0 in Section III.2.
- d. A TI silent 700 Terminal is required to perform this procedure.
4.0 PROCEDURE 4.1 ACCESSING THE WSI WEATHER SYSTEM Power Up the Terminal 4.1.1 Connect the pcwer supply cord to the terminal and plug the cord into a power socket.
NOTE:
To use the Control Room meteorological terminal to obtain meteorologi-cal data from the WSI system, the terminal must be unplugged from the modem (black line) and the black plug inserted in its place.
4.1.2 Move the toggle switch located on the rear right-hand side of the terminal to the "on" position. You should be able to hear the terminal fan motor start up.
eiO383-0045a154 L_ .
PALISADES MUCLEAR PLANT Proc No EI-6.8 EMERGENCY IMPLEMENTATION PROCEDURE Revision 0 Page 2 of 7 ,
TITLE: BACKUP AND SUPPLEMENTAL METEOROLOGY 4.1.3 There are three rocker switches located on the front right-hand side of the terminal. They are labeled low speed, half dup and on line.
- a. Depress the right side of the one labeled low speed.
- b. Depress the right side of the one labeled half dup.
- c. Depress the left side of the one labeled on line.
4.1.4 There is one rocker switch located on the front left-hand side of the terminal labeled "NUM". Depress the right-hand side of this switch.
Dialing In _
,[
4.1.5 Using the telephone, obtain an outside line and dial-Alternate Numbers 7
[
4.1.6 Place the telephone receiver into the acoustic coupler located on the back part of the terminal. The orientation of the telephone receiver in the acoustic coupler is pictured on the rear of the terminal by the acoustic coupler.
4.1.7 When the green light on the terminal comes on, hit the return button twice.
NOTE: If the green light does not come on within two minutes, return to Step 4.1.5.
NOTE: The system will give you a port identification number and ask you to identify your terminal by printing " TERMINAL =".
4.1.8 Type "TI45" and hit the return key once.
4.1.9 The system will respond with an "@" character. Type the letter "C" followed by a space, then the following number "617133" and hit the return key once.
The system will respond with one of the following connection messages:
- a. "617 133 connected" (if this, go to 4.1.11)
- b. "617 133 not reachable" (if this, go to 4.1.10)
- c. "617 133 not operating" (if this, go to 4.1.10) .
4.1.10 If the "not reachable" or "not operating" message is given, remove the telephone receiver from the acoustic coupler and hang up. ,
l
- a. Using the 1clephone, obtain an outside line and then dial
_1-617:275:3300.
eiO383-0045a154
. o .
PALISADES NUCLEAR PLANT Proc No EI-6.8 EMERGENCY IMPLEMENTATION PROCEDURE Revision 0 Page 3 of 7 TITLE: BACKUP AND SUPPLEMENTAL METEOROLOGY .
- b. Place the telephone receiver in the acoustic coupler.
l
- c. When the green light on the terminal comes on, hit the return button twice.
NOTE: If the green light does not come on within one or two minutes, return to Step 4.1.10. If this connection cannot be established, go to Step 4.1.16.
- d. The system will respond with the following message:
t Please login
+
Proceed to Step 4.1.12 Logging In a
4.1.11 To log in, hit.the return key once.
1 NOTE: The system will respond with the following message:
Please login
+
4.1.12 Type in "LOGIN PAL" NOTE: The system will respond with the word " PASSWORD;" followed by a field of overtyping.
4.1.13 Type the word " POWER" and hit the return key.
NOTE: The system will respond with an introduction message followed by a "+"
sign., You have now logged in to the Weather Information System. The system will always type a plus sign "+" when it'is ready to accept commands from the user. The user must always hit the return key after
- each command string. See Attachment 1 for further information if required.
Display Meterological Data 4.1.14 Type "USINF0" followed by a 3-letter-station-code followed by "WZQ,"
then hit the return key. This will print the data for the current hour at a selected weather station.
NOTE: The'following are the 3-letter-station-codes. They are given in the order they shall be used, the first being the primary and'the second to be used only if the first is not available.
- 1. Benton Harbor-BEH 2, Muskegon-MKG eiO383-0045al54
8 O PALISADES NUCLEAR PLANT Proc No'EI-6.R EMERGENCY IMPLEMENTATION PROCEDURE Revision 0 Page 4 of 7 TITLE: BACKUP AND SUPPLEMENTAL METEOROLOGY For example, the following command would give the current hourly meteorological data at Benton Harbor:
USINFO BEH WZQ The data would appear in the following format:
Observations for 8PM(01Z) 1-DEC-82 Station Name Wind PS
==
Benton Harbor, MI 2710 D Where:
Wind = Wind direction first two digits in tens of degrees from which wind is blowing and wind speed to the nearest knot, ie, 2710 = 270 degrees at 10 knots PS = Pasquill stability category (A-G)
Record the wind direction, the wind speed, and Pasquill stability class on the worksheet, items (A), (B) and (D) respectively. Convert wind speed to mph by multiplying wind speed (B) by 1.15 mph / knot.
Record on worksheet,. item (C).
All required meteorological data have now been recorded. Log out and proceed to the next procedure as required per EI-6.0.
4.1.15 Logging Out When you are done with all your work on the system, you should log out. To log out, type: LOGOUT NOTE: Step 4.1.16 is needed only if the connection to the WSI system can not be established.
4.1.16 Dial the Grand Rapids National Weather Service directly (616-949-0640).
Identify yourself as a Palisades Plant representative and request the following data from the meteorologist on duty:
- a. Wind direction, degrees from
- b. Wind speed in mph.
Record on worksheet, items (A) and (C) respectively.
Stability class must be estimated as follows:
- a. night time or cloudy =E b, day time and clear =D Record on worksheet, item (D).
eiO383-0045a154
PALISADES NUCLEAR PLANT Proc No EI-6.8 EMERGENCY IMPLEMENTATION PROCEDURE Revision 0 Page 5 of 7 TITLE: BACKUP AND SUPPLEMENTAL METEOROLOGY Continue to the next procedure as required per EI-6.G.
- M STEPS 4.2.1-4.2.7 PROVIDE SUPPLEMENTAL METEOROLOGICAL INFORMATION ONLY ******
- '*** THESE STEPS ARE TO BE IMPLEMENTED ONLY IF TIME PERMITS. ****
4.2 DISPLAY SUPPLEMENTAL METEOROLOGICAL DATA AND FORECAST 4.2.1 To print the current data for 'more than one station, type each station code separated by a comma. For example, to print the current data for Benton Harbor and Muskegon, type:
USINFO BEH,MKG WZQ NOTE: Data can also be printed from previous hours, or a set of hours. Data for most stations are stored for three days (72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />). The command format-is the same for the current hour except a time period is added after the "WZQ". The following codes are used to specify time periods:
A A.M.
B P.M.
The format for specifying the time periods is:
i start time-end time 12 A represents midnight 12 P represents noon ,
4.2.2 To print the hourly Bentor Harbor data from 1 AM through 7 AM, type:
4 USINFO BEH WZQ IA-7A i
If you want the data from all the hours since a certain time, leave the end time blank. To print all the hours at Benton Harbor since 1 AM, type: -
, USINFO BEH WZQ IA-f 4.2.3 To print data for one particular hour (1 AM), type:
USINFO BEH WZQ IA NOTE: The same format is used for multiple stations. If the meteorological data for a station is missing for a particular hour, nothing will be displayed for that particular parameter.
I Display Weather Forecast 1
The National Weather Service' prepares a numerical weath'er forecast for .
select cities around the United States twice a day at 00Z (7:00 PM EST) and 12Z (7:00 AM EST). This forecast is called Model Output Statisticst(MOS). The output from this forecast is used to obtain a site specific 48-hour forecast in 6-hour increments for the Palisades eiO383-0045a154
PALISADES EUCLEAR PLANT Proc No EI-6.8 EMERGENCY IMPLEMENTATION PROCEDURE Revision 0 Page 6 of 7 TITLE: BACKUP AND SUPPLEMENTAL METEOROLOGY Nuclear Plant. The Plant forecast parameters are wind direction (tens of degrees), wind speed (mph), cloud cover (tenths), cloud ceiling height (ft) and Pasquill stability category. The wind direction and wind speed values are printed to the nearest ten degrees and mph respectively. A value of 2710 would be interpreted as wind coming from 270* at 10 mph. The forecast is available through WSI at approximately 10 AM and 10 PM.
4.2.4 To obtain the forecast for the Palisades Plant, type:
-MOSPAL 00 or 12 depending on which forecast you want The forecast will appear as:
DATE/GMT 27/18 28/00 28/06 28/12 28/18 29/00 29/06 29/12 DATE/EST 27/13 27/19 28/01 28/07 28/13 28/19 29/01 29/07 WIND-MP 0910 0711 0813 0811 0610 1511 2109 3303 CLDS .1 10 10 10 10 10 10 8 2 HGT-FT 6100 6450 4750 3750 3150 5650 5500 5500 PAS D D D D D D D C Where:
DATE = Day of the month GMT = Greenwich Mean Time EST = Eastern Standard Time WIND-MP = Wind direction (tens of degrees) and wind speed (mph) value.
CLDS .1 = Cloud cover in tenths HGT-FT = Cloud height in feet Pasquill stability category PAS =
Display Radar Maps (Precipitation) 4.2.5 To display the most recent radar map for the Palisades Plant area, type:
- RADMAP MKG (Radar station located in Muskegon, Michigan)
NOTE: The map produced will be centered on the National Weather Service
, Radar Station. Digits indicating intensity of radar echoes will be superimposed on the map. Every hour, radar stations across the country take radar observations and deteruine the itensity of precipitation. The intensity at a particular location is reported as a single digit. The digits are defined as:
Digit Precipitation Intensity 1 Light 2 Moderate
- 3 Heavy 4 Very Heavy 5 Intense .
6 Extreme 8 Unknown, but probably light to moderate 9 Unknown, but probably heavy eiO383-0045a154
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PALISADES NUCEEAR PLANT Proc No EI-6.8 EMERGENCY IMPLEMENTATION PROCEDURE Revision 0 Page 7 of 7 i TITLE: BACKUP AND SUPPLEMENTAL METEOROLOGY
- Indicates that a valid report has been received for the station at that location.
MM Indicates that the station at that location has been reported out of service.
If no report is received from a station, neither ** nor 101 will be displayed. If an echo (levels 1-6, 8-9) is reported at the station, the echo will be typed, otherwise ** indicates the location of the station.
Display Regional Meteorological Data 4.2.6 To display-a weather map of wind data for the State of Michigan, type:
MIC W NOTE: The system will print "OK" to indicate that it is processing the command.
NOTE: Wind direction is reported in tens of degrees (first two digits of display) from which the wind is blowing and wind speed in nearest knot (last two digits of display).
4.2.7 To display a weather map of stability classes for the State of Michigan, type:
MIC ' (' = an apostrophe, uppercase 7 on keyboard)
NOTE: The system will print "OK" to indicate that it is processing the con.ma nd .
5.0 ATTACHMENTS Attachment 1, " Supplemental Information"
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Attachment I l Revision 0 Page 1 of I SUPPLEMENTAL INFORMATION A. Correcting Typing Mistakes If you make a mistake while typing a command, there are two methods to correct the mistake. One corrects the characters on the line, and one erases the entire line and lets you start again.
- 1. To correct mistakes on a line, you use the "Pubout" key. To correct an error, type the rubout key once for each character that you would like to erase. The system will indicate the use of this function by typing a black slash "/" followed by the characters that are being erased. (In some modes, the system will only type the characters that are being erased.and not the black slash). Now type the correct characters.
These characters can include spaces, letters and numbers. Once the return key has been typed, you cannot erase any chara.cters f rom that line.
If you were trying to type "USINF0" and mistakenly type "USDSRF", you could do the following:
USDSFR/RFSD/ INFO or USDSFRRFSDINFO The rubout key was typed four times, followed by the correct characters.
If at any time you would like to see the corrected portion of the line before you hit the return key, hit the paper adv key and then hit the CTRL key while at the same time hitting the letter "R".
- 2. To erase an entire line, hit the CTRL key, at the same time hit the letter "U". The terminal will return to a new line. Even though the system does not type a "+", you may en.ter the command.
B. Stopping Programs and Output If at any time you wish to cancel a command, stop a program execution, completely halt a printout, or stop anything else on the system, hit the CTRL key and the letter C simultaneously two times. Note that it might take a few seconds before the system recognizes the command. If after a few seconds, the system fails to halt execution, retype the above sequence.
C. Problem Assistance If you encounter problems at any time, call the WSI Bedford Systems Consulting Group at 617-275-8860-172. ,
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, o Proc No EI-6.0 Revision 0 Date 5/23/83 PALISADES NUCLEAR PLANT
, E!!ERGENCY It!PLE!!ENTATION PROCEDURE Revision and Approval Summary TITLE: OFFSITE DOSE CALCULATION MD RECO?L'!ENDATIONS FOR PROTECTIVE ACTIONS
- 1. Prepared 2. QA Concurrence Y
< 'f[ll'% $19f3 bN
[)origfnator Date Date V W ('J) W D Rf
- 3. Reco end .4pproval/Q-Lis t No 4. PRC Reviewed
/' ('
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$l$?0 / ! L'S O ?
rtrd nt Head 'Da te - /,y_t T3 e d Date
- 5. Approved 6. ATt!S Incorporated M dA4 / d " 2- 3 Plant flanagq Ih - '~Date / pdite
- 7. Biennial Review Date eiO383-0027e154
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PALISADES NUCLEAR PLANT Proc No EI-6.0
-EMERGENCY IMPLEMENTATION PROCEDURE Revision-0 Page i TITLE: OFFSITE DOSE CALCULATION AND RECOMMENDATIONS FOR PROTECTIVE ACTIONS 1
Table of Contents Page 1.0 PERSONNEL RESPONSIBILITY . . . . . . . . . . . . . . . . . . . . . 1 2.0 PURPOSE , . . . . . . . . . . . . . . . . . . . . . . . . . . . . I a
3.0 INITIAL CONDITIONS AND/OR REQUIREMENTS . . . . . . . . . . . . . . 1 i 4.0 PROCEDURE . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 4.1 OVERVIEW . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 4.2 RELEASE RATE . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 j 4.3 AVERAGE GAMMA ENERGY-(5) . . . . . . . . . . . . . . . . . . . . . 2 4.4 METEOROLOGICAL DATA . . . . . . . . . . . . . . . . . . . . . . . 2 4.5 CALCULATIONAL METHODS . . . . . . . . . . . . . . . . . . . . . . 2
) 4.6 0FFSITE MONITORING . . . . . . . . . . . . . . . . . . . . . . . 3 4.7 0FFSITE PROTECTIVE ACTIONS . . . . . . . . . . . . . . . . . . . . 3 4.8 COMPLETION OF REQUIRED CALCULATIONS . . . . . . . . . . . . . . . 3 5.0 ATTACHMENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 ATTACHMENTS -
Attachment 1, "Offsite Dose Worksheet" t
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PALISADES NUCLEAR PLANT Proc No EI-6.0 EMERGENCY IMPLEffENTATION PROCEDURE Revision 0 Page 1 of 3 TITLE: OFFSITE DOSE CALCULATION AND RECOMMENDATIONS FOR PROTECTIVE ACTIONS 1.0 PERSONNEL RESPONSIBILITY The Chemistry / Health Physics Support Group Leader shall implement this procedure. In the absence of a Chemistry / Health Physics Support Group Leader, the Site Emergency Director shall delegate this function.
2.0 PURPOSE To determine the appropriate steps required to calculate offsite dose and recommend offsite protective actions.
3.0 INITIAL CONDITIONS AND/OR REQUIREMENTS This procedure shall be implemented when there is a potential for, or an actual significant release of radioactive materials from the Plant site, per EI-2.1.
4.0 PROCEDURE 4.1 OVERVIEW
- a. All procedures in Emergency Implementation Procedures, Sec-tion EI-6 are for calculation of offsite dose and making recommendations for offsite protective actions. Not all procedures in this section are applicable to all release categories. The following paragraphs will direct the user to the appropriate procedures to complet,e this task.
- b. Use Attachment 1 of this procedure, (Offsite Dose Worksheet), when completing this procedure. Mark the blank in the left margin ot
,. the worksheet to designate which procedures should be performed, per the following' paragraphs.
4.2 RELEASE RATE
~
This section selects the appropriate procedure to determine a release rate (Ci/sec) for input into the Offsite Dose calculation.
4.2.1 If the release is occuring through the Plant stack, the release rate-should be determined in EI-6.1. Mark Section-I.1 on the worksheet if this paragraph applies to the release.
4.2.2 If the release is occuring through .the steam dump, the release rate should be determined in EI-6.2. Mark Section I.2 on the worksheet if this paragraph applies to the release.
4.2.3 If the release is occuring through the stack or steam dump and the stack monitors or main steam line gamma monitors respectively, are not functional, the release rate should be determined in EI-6.3. Mark .
Section I.3 on the worksheet if this paragraph applies to the release.
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TITLE: OFfSITE DOSE CALCULATION AND RECOMMENDATIONS FOR PROTECTIVE ACTIONS 4.2.4 If the radioactivity is confined to the containment building with a potential for release or an actual release taking place, the release rate should be calculated in EI-6.4, using the high range containment monitors. Mark Section I.4 on the worksheet if this paragraph applies to the (potential) release.
4.2.5 If the results from Post-Accident Sampling (EI-7) are available, confirmation of potential or actual release rates from the containment building or the Primary Coolant System may be determined in EI-6.5.
This procedure may serve as a backup for EI-6.3 in the case of a containment building release, as time permits. Implementation of this procedure should not delay completion of Offsite Dose Calculations.
Mark Section I.5 of the worksheet if the above conditions are met for the use of Post-Accident Sampling input.
4.3 AVERAGE GAMMA ENERGY (5)
EI-6.6 shall be used to determine the average gamma energy per disintegration to be used for Offsite Dose calculations.Section II.1 is already marked on the worksheet.
t 4.4 METEOROLOGICAL DATA This section selects the primary and backup methods of obtaining meteorological data, including wind speed, wind direction and stability class.
4.4.1 If the site meteorological station is functioning, current weather conditions should be determined in EI-6.7. Mark Section III.1 on the i
worksheet if onsite meteorological data is available.
-4.4.2 Backup meteorological data and weather forecasts are.obtained in EI-6.8. The backup system should be used when the onsite system is not available. Weather forecasts may be used to anticipate changing
! conditions. Forecasts should be made only if staffing and time
' permits. Mark Section III.2 on the worksheet if backup meteorology is used.
1 4.5 CALCULATIONAL METHODS t
This section describes the method (s) which :hould be useo to calculate offsite dose.
, a 4.5.1 The straight-line Gaussian method described in EI-6.9 should be used to determine offsite dose. This method requires a pre programmed Hewlett-Packard 41 CV calculator (normally stored with Technical Support Center emergency equipment). This method is ih agreement with l
the state method and should be the primary used until the Technical Support Center is staffed. Mark Section IV.1 on the worksheets if the ,
above conditions are met, eiO383-0027a-154-89 4
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. a PALISADES NUCLEAR PLANT Proc No EI-6.0 EMERGENCY IMPLEMENTATION PROCEDURE Revision 0 Page 3 of 3 TITLE: OFFSITE DOSE CALCULATION AND RECOMMENDATIONS FOR PROTECTIVE ACTIONS 4.5.2 If a pre programmed Hewlett-Packard 41 CV is not available, EI-6.10 should be used to determine offsite dose. The methodology and results are essentially identical to those in EI-6.9, but no calculator is required. Mark Section IV.2 on the worksheet if the backup method is used.
4.5.3 Segmented Gaussian Method, EI-6.11 - to be developed.
s 4.6 0FFSITE MONITORING EI-6.12 compares offsite manitoring results (EI-9), to Offsite Dose calculations made in this section. This comparison should be made as data becomes available and time permits. Mark section V.1 on the worksheet if the above conditions are met.
4.7 0FFSITE PROTECTIVE ACTIONS EI-6.13 shall be used to determine recommendations for offsite protective actions.Section VI.1 is already marked on the worksheet.
4.8 COMPLETION OF REQUIRED CALCULATIONS Initiate the first procedure as identified on the workshect. Proceed to the next procedure identified on the worksheet upon completion of the first. Omit unmarked sections of the worksheet.
5.0 ATTACIRIENTS Attachment 1, "Offsite Dose Worksheet" L
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Release Rate 4
( )Section I.1, Reference EI-6.1, Release Rate Determination from Stack Gas Monitors
. 1. Current stack gas monitor reading = cpm (A) **RIA-2318 ( )
- RIA-2319 ( )
- 2. Stack monitor background reading = cpm (B)
- 3. Net stack monitor. count rate = (A)-(B) = cpm (C)
- 4. Stack gas flow rate =
ft 3/ min'(D)
- 5. Stack gas flow rate m3 s (D) ft /3 min x 4.72E-4 f 3j
=
m3 /sec (E)
- 6. Conversion factor = Ci/m3 cpm F)
- 7. QN, Noble gas release rate =
(C) x (E) x (F) =
Ci/sec (G)
- 8. QI, Iodine release rate = (G) x (1.0E-3) =
-Ci/sec'(H) i T
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()Section I.2, Reference EI-6.2, Release Rate Determination from Steam Line Monitors.
- 1. -Steam Dump Start Date (A)
Time (B)
- 2. Steam Line Monitor Reading A S/G, **RIA-2324 = net epm (C)
Steam Line Monitor Reading
] B S/G, **RIA-2323 = net epm (D) j
~
- 3. QN , noble gas release rate A S/G =
A(C) x (1.7 x 3E-2) = Ci/sec (E)
QN , n e gas release rate B S/G =
B(D) x (17.3E-2) =
Ci/sec (F)
- 4. QN, noble gas release rate =
if release is from one S/G QN = (E) or (F) =
if release is from both S/G QN = (E) + (F) =
Ci/sec (G) 2 i
- 5. QI, I-131 dose equivalent release rate =
(G) x (1.0E-3) = Ci/sec (H)
Date: Time: Completed By:
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Page 3 of 15 0FFSITE DOSE WORKSHEET CONFIRMATION i ()Section I.2, Reference EI-6.2, Release Rate Determination from Steam Line Monitors.
f 1. Date: Time:
- 2. Steam Dump Start Date: Time:
- 3. T F avg .
- 4. PCP on? Yes: No:
- 5. Secondary Pressure psia
- 6. Fully Open Dump Valve Saturated Steam Flow Rate cc/sec
- 7. T error avg
- 8. Fraction Valve Open Actual Steam F' low Rate from one Dump Valv'e cc/sec l 10. S/G A dumps open? Yes: No:
- 11. **RIA-2324 reading -cpm
- 12. S/G A Total Radionuclide. Concentration pCi/cc
- 13. S/G A Radionuclide Release Rate pCi/sec f
- 14. S/G A Noble Gas Release Rate pCi/sec S/G A Radioiodine Release Rate pCi/sec
- 15. S/G B dumps open? Yes: No:
- 16. **RIA-2323 reading cpm
- 17. S/G B Total Radionuclide Concentration pCi/cc
- 18. S/G B Radionuclide Release Rate pCi/sec
, 19. S/G B Noble Cas Release Rate pCi/sec I'
S/G B Radioiodine Release Rate pCi/sec
~
- s. Bypass Valve open? Yes: No:
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- 21. S/G A MSIVs open? Yes: No:
S/G B MSIVs open? Yes: No:
- 22. Bypass Valve Noble Gas Release Rate pCi/sec
- 23. QN = Ci/sec QI = Ci/sec
- 24. S/G A T cold F S/G B T cold F
- 25. S/G A Pressure psia S/G B Pressure psia
- 26. Fully Open Dump Valve Flow Rates:
S/G A cc/sec S/G B cc/sec
- 27. T error avg
- 28. Fraction Valve Open
- 29. S/G A Actual Steam Flow Rate ___ cc/sec S/G B Actual Steam Flow Rate cc/sec Date: Time: Completed By:
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() I.3, Reference EI-6.3, Release Rate Determination From High Range Effluent Monitors.
- 1. High range effluent monitor reading mR/hr (A)
High range effluent monitor,
( ) stack
( ) steam dump
- 2. High range effluent monitor reading = (A) x (1.0E-3) = R/hr (B)
- 3. Response factor (C)
- 4. Cor,rected monitor reading = (B) x (C) = R/hr (D)
- 5. Elapsed time from reactor shutdown to monitor reading = hours, days (E)
(circle one)
- 6. Conversion factor =
C / ec (F) from: Attachment 1, ( )
Attachment 2 ( )
Attachment 3 ( )
Attachment 4 ( )
~ .
- 7. QN, noble gas release rate = (D) + (F) = Ci/sec (G)
I
- 8. QI, I-131 dose equivalent release rate =
(G) x (1.0E-3) =
Ci/sec (H)
Date: Time: Completed By:
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() I.4, Reference EI-6.4, Release / Potential Release Determination From Containment liigh Range Monitors.
- 1. Time past shutdown = hours (A)
- 2. Monitor number ( ) **RIA-2321 (B)
( ) **RIA-2322
- 3. Monitor reading = R/hr (C)
- 4. Noble gas con"ersion factor = pCi/c
. R/hr (D)
- 5. Leak rate = cc/sec (E) 6 QN, noble gas release rate =
(C) x (D) x (E) x (1.0E-6) =
Ci/sec (F)
- 7. QI, I-131 dose equivalent release rate =
(F) x (1.0E-3) = Ci/sec (G)
Date: Time: Completed By:
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- 1. Decay time hours (A)
- 2. Source of release ( ) Fuel Melt or Fuel Failure (B)
() Main Steam or Offgas (Air Ejector) Releases
() Surge Tank, Volume Control Tank, and Degasifier Releases
() Waste Gas Decay Tank Releases
() Fuel Handling, Sipping and Cask Drop Releases
- 3. 5= MeV (C)
Date: Time: Completed By:
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() III.1, Reference EI-6.7, Plant Site Meteorological System
- 1. WS, Wind Speed = mph (A) ( ) 10 meters
( ) 60 meters, corrected
- 2. WD, Wind Direction =
- from (B) () 10 meters
( ) 60 meters
- 3. 6010 DELT = (C) preferred SE
( ) 10-M SGMA = (C) alternate
( ) 60-M SCMA =
- 4. Stability Class = (D)
Date: Time: Completed By:
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() III.2, Reference EI-6.8, Backup and Supplemental tieteorology.
- 1. Wind direction = ___
- From (A)
- 2. Wind speed = knots (B)
- 3. Wind speed = (B) x (1.15) mph / knot = mph (C)
- 4. .Pasquill Stability Class = (D) default for stability class: night time or cloudy = E day time and clear =D Late: Time: Completed By:
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0FFSITE DOSE CALCULATION 4
() IV.1, Reference EI-6.9 Calculation of Offsite Dose - Straight Line Gaussian (Calculator Method)
Required Calculations Optional Calculations i Distance from Plant Site l Boun-dary
.5 mi 2 mi 5 mi 10 mi
- 1. Child thyroid dose rate, mrem /hr = (A)
- 2. I-131 Dose equivalent cone, Ci/m3 =
(B)
- 3. Finite cloud whole body dose rate, mrem /hr =
(C)
'. Estimated releasd duration = hrs.(D) Note: default is two hours.
- 5. Child Thyroid dose, mrem =
(A) x (D) =
(E) i
- 6. Finite Cloud Whole Body dose,-mrem = (C) x (D) =
(F) i, l
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- 7. Above doses-are based on actual / potential (circle one) releases. (G) l t
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, OFFSITE DOSE WORKSIIEET 3
- () . IV.2, Reference EI-6.10 Offsite Dose calculation - Straight Line laussian (Manual i Method) 1
- Required Calculations Optional Calculations Site Boun-dary
.5 mi 2 mi 5 mi 10 mi (A)
Ci (mph)
- 1. XP/Q =
(B) m" Ci/sec
- 2. X/Q (sec/m3 ) =
(B) + wind speed (m*.h) =
(C)
- 3. Semi-infinite cloud whole dose rate (mrem /hr) =
4 (C) x (QN) x (E) x (9.0E+5) =
(D) 4
- 4. Finite cloud correction factor =
(E)
]
1 5. Finite cloud whole body
, dose rate (mrem /hr =
(D) + (E) =
(F)
]
! 6. Estimated release duration (hours) (G)
]
- 7. Finite Cloud Whole body i dose commitment (mrem) =
(F) x (G) =
(II)
I s
I 8. I-131 dose equivalent concentration (Ci/m3= (QI) x (C) =
(I)
]
4
- 9. Child thyroid dose rate (mrem /hr) =
(I) x (1.85E9) =
(J)
- 10. Child thyroid dose commitment (mrem) =
(J) x (G) =
(K) i
.. Abave doses based on actual / potential (circle one) releases. (L)
Date: Time: Completed By:
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Page 14 of 15 OFFSITE DOSE WORKSHEET V Offsite Monitoring
() V.1, Reference EI-6.12 Comparison of Offsite Monitoring with Offsite Dose Calculations Distance = Site boun-dary
.5 mi 2 mi 5 mi 10 mi
- 1. Offsite Monitoring Data Whole Body dose rate (mrem /hr) =
(A)
I-131 dose equivalent cone (pCi/ce) = (B)
- 2. Plume direction = degrees to (C)
- 3. Offsite Dose Calculations Finite Cloud Whole Body dose rate (mrem /hr) =
__ (D)
I-131 dose equivalent conc (pCi/cc) =
, (E)
- 4. Wind direction = degrees from (F)
Wind direction = degrees to (G)
- 5. Data Comparison (A) - (D) =
(H)
(B) - (E) =
(I)
If (H) or (I) > 0, circle in red.
(D) + (A) =
(J)
(E) + (B) =
(K)
If (J) or (K) > 2.0, circle in red.
[(C) - (G)] = degrees (L)
If (L) > 10*, circle in red.
Date: Time: Completed By: D eiO383-0027bl54-89
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OFFSITE DORE WORKSifEET Pro <- No El-6.0 Att .imen t I
_ VI Protect.ive Actions Revision 0 -
Page 15 of 15 (x) VI.1, Reference El-6.13, Protect.ive Action Reconunendation for Offsite Population 1.
REC 0ftMENDED PROTECTIVE ACTIONS TO REDUCE W110LE BODY AND THYROID DOSE TO OFFSITE POPULATION FROM EXPOSURE TO A GASEOUS PlutlE '
Basis Reconunended (A) Affected* for (C)
Protective Sectors Protective Projected Dose (Rem) .
Action (B) Actions to the Populat. ion Recommended Actions (a) Conunen t s Wholebody < 0.5 No respaired protective actions (b) Previously reconunended State may issue an advisory protective actions may Thyroid < 5 to seek shelter and await be reconsidered or further instructions. terminated.
Monitor envi ronmental radiat. ion levels.
Wholebody 0.5 to < 5 Seek shelter as a minimum. If constraints exist,
, Consider evacuation. Evacuate special consiileration Thyroid 5 to < 25 unless constraints make it should be given for impractical. Monitor evacuation of children envi ronmental radiation and pregnant women.
levels. Control access.
Wholebody 5 and above Conduct. mandatory evacuation. Seeking shelter would be Monitor environmental radia- an alternative if Thyroid 25 and above Lion levels and adjust area for evacuation were not mandatory evacuation based on inunediately possible. ;
3 these levels. Control access. ;
4 (a)These act. ions are reconunended for planning purposes. Protective action decisions at the time of the incident must take '
existing conditions into considerat. ion. l (b)At. the time of the incident, state officials may implement low-impact protective actions in keeping with the principle of maintaining radiation exposures as low as reasonably achievable.
J
- 2. These dose rates are based on actual / potential (circle one) releases. (D) ,
' NOTE: Include the area within two miles of the plant (all sectors) in any reconunended actions, i
Date ' Time Completed By:
Reviewed By:
Site Emergency Director:
, eiO383-0027c154-89 4 w
T Proc No EI-6.10 Revision 0 Date 5/23/S3 L
PALISADES NUCLEAR PLANT EMERGENCY IrlPLE!!ENTATION PROCEDURE j Revision and Approval Summary l 5
TITLE: OFFSITE DOSE CALCULATION - STRAIGIIT LINE GAUSSIAN j (f!ANUAL ?!ETif0D l
l 1
l l 1. Prepared 2. QA Concurrence m
/ if nator 5/7 23 Date
& Date L mowq 4
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- 3. Reco nd pproval/Q-List 'es No 4. PRC Reviewed i f/
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A' .pgi .g _ yj) Date i 5. Approved 6. ATMS Incorporated I
i ud 6704 /f5 6W O i
QPlant flanageg Date ~ Date t
i l 7. Biennial Review s
- Date 4
I
.eiO383-0047e154
i +
l PALISADES NUCLEAR-PLANT Proc No EI-6.10 EMERGENCY I:!PLE!!ENTATION PROCECURE Revision 0 Page i TITLE: 0FFSITE DOSE CALCULATION - STRAIGilT LINE GAUSSIAN
(!!ANUAL METHOD)
Table of Contents Page 1.0 PERSONNEL RESPONSIBILITY . . . . . . . . . . . . . . . . . . . . I 2.0 PURPOSE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 3.0 INITIAL CONDITIONS AND/0R REQUIREffEpiTS . . . . . . . . . . . . . 1 4.0 PROCEDURE . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 5.0 ATTACIIMENTS . . . . . . . . . . . . . . . . . . . . . . . . . . 3 Attachments Attachment 1, "KU/Q Curves by Stability Category" Attachment 2, " Finite Cloud Correction Factors"
?
I l
eiO383-0047d154 l
i l
l l
- * ^
PALISADES NUCLEAR PLANT Proc No EI-6.10 EffERGENCY IMPLEMENTATION PROCEDURE Revision 0 Page 1 of 3 TITLE: OFFSITE DOSE CALCULATION - STRAIGHT LINE GAUSSIAN (MANUAL METHOD) 1.0 PURPOSE The Chemistry / Health Physics Group Leader is responsible for the implementation of this procedure. In the absence of a Chemis-try/ Health Physics Group Leader, the Site Emergency Director shall delegate this responsibility.
2.0 PURPOSE To provide a hand calculation procedure to provide offsite dose assessment calculations whenever the automated dose assessment procedur'es EI-6.9 and/or EI-6.11 are not operable.
3.0 INITIAL CONDITIONS AND/OR REQUIREMENTS
- a. This procedure shall be implemented as required per EI-6.0.
- b. Data and results from this procedure should be recorded on the Offsite Dose.Worksheet, Attachment I to EI-6.0, in Section IV.2.
- c. Input to this section is obtained from previously completed sections of the Offsite Dose Worksheet. Pertinent data is enclosed in boxes for rapid identification.
4.0 PROCEDURE 4.1 On the dose worksheet, item (A), record any special interest dose assessment distance (s) other than the mandatory .5, 2, 5 and 10 miles.
4.2 Select appropriate XU/Q figure from Attachment I based on the Pasquill stability category obtained in Section III o.f the dose worksheet.
4.3 Determine the appropriate XU/Q values from the selected figure for the mandatory downwind distance of .5, 2, 5 and 10 miles and for any special interest distance (s), record on the dose worksheet, item (B).
NOTE: The XU/Q ,a g value is read off the vertical axis (labeled XU/Q) directlyacros[Iromthepointonthecurvewhichliesabovethe downwind distance of interest.
! 4.4 Determine X/Q (Sec/m 3
) values by dividing the XU/Q values (B) by the wind speed (mph) obtained in Section III of the dose worksheet.
Record the X/Q values on the dose worksheet, item (C).
4.5 Determine the semi-infinite cloud whole body dose rate (mrem /hr) by multiplying together X/Q(s), sec/m3 (C), the noble gas release rate, j
QNCi/sec,fromSectionIofdoseworksheekRek'HS'f# S
- S**'i " II of dose worksheet and the constant 9.0 E5 f r each distance. hr - Ci - MeV l
eiO383-0047a154 I' I
- . - - .- _ w
PALISADES NUCLEAR PLANT Proc No EI-6.10 EMERGENCY IMPLEMENTATION PROCEDURE Revision 0 Page 2 of 3 TITLE: OFFSITE DOSE CALCULATION - STRAIGHT LINE GAUSSIAN (MANUAL METHOD)
Semi-infinice cloud whole body dose rate (mrem /hr) = (X/Q) x (g) x (E) x (9.0 ES)
Record on the dose worksheet, item (D).
4.6 Determine finite cloud correction factor from Attachment 2 at the downwind distance (s) recorded on the dose assessment worksheet and for the appropriate stability class determined in Section III of the dose worksheet.
NOTE: The finite cloud correction factor (s) is determined by (1) locating the downwind distance of interest on the horizontal axis and reading .
up to the appropriate stability curve and (2) reading the finite cloud correction factor off the vertical axis directly across from the intersection point on the curve.
Record on the dose worksheet, item (E).
4.7 Determine finite cloud whole body dose rate (mrem /hr) by dividing ,
semi-infinite cloud whole body dose rates (D) by the finite cloud '
correction factor (s( (E). .
i finite cloud whole body _ (semi-infinite cloud whole body dose rate) dose rate (mrem /hr) (finite cloud correction factor)
Record on the dose worksheet, item (F).
4.8 Estimate duration of release in hours and record on worksheet, item (G).
4.9 Determine finite cloud whole body dose commitment by multiplying the whole body dose rates (F) by the estimated release duration (G).
Record on the dose assessment worksheet, item (H).
4.10 Determine the I-131 dose equivalent concentration (Ci/m3 ) by multiplying the I-131 dose equivalent release rate, QI from Section I of the worksheet by X/Q (C).
Record on worksheet, item I.
4.11 Determine the child thyroid dose rate by multiplying the I-131 dose equivalent concentration (I) by the constant 1.85 E9 "[**{ .
Record on worksheet, item (J).
4.12 Determine the child thyroid Jose commitment (mrem) by multiplying the child thyroid dose rates (I) by the estimated release duration (G).
Record on the dose assessment worksheet, item (J).
eiO383-0047a154
)
l
i
, . - j l
PALISADES NUCLEAR PLANT Proc No EI-6,10 l EMERGENCY IMPLEMENTATION PROCEDL*RE Revision 0 i Page 3 of 3 TITLE: OFFSITE DOSE CALCULATION - STRAIGIIT LINE GAUSSIAN (MANUAL METHOD) 4.13 Note on the worksheet, item (K), whether the doses are based on actual or potential releases.
4.14 Continue to next procedure as required per EI-6.0.
5.0 ATTACHMENTS 5.1 Attachment 1, "XU/Q Curves by Stability Category" 5.2 Attachment 2, " Finite Cloud Correction Factors" l
i l
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eiO383-0047a154
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Proc No EI-6.I Revision 0 Date 5/23/33 PALISADES NUCLEAR PLANT Ef!ERGENCY IffPLE!!ENTATION PROCEDURE Revision and Approval Summary TITLE: RELEASE RATE DETERt!INATION FR0!! STACK GAS t!ONITORS e
I. Prepared 2. QA Concurrence m
/ flidm Y/fb3 Date
/M Date k/[{.,fr' inator QT/&
- 3. Reco nd Approval /Q-List No 4. PRC Reviewed D
l 'l rtm t Head l? D
'Da'te '
h ll/ lLf b *
) '? '5
-#gt'g KM/r Date
- 5. Approved 6. ATl!S Incorporatsd 67 h / f3 Plant ?!anag Date '
Date
- 7. Biennial Review Date -
eiO383-0028dI54
l PALISADES NUCLEAR PLANT Proc No EI-6.1 l EMERGENCY It!PLEMLNTATION PROCEDURE Revision 0 I TITLE: RELEASE RATE DETERMINATION FR0!! STACK GAS MONITORS Table of Contents Page 1.0 PERSONNEL RESPONSIBILITY . . . . . . . . . . . . . . . . . . . 1 2.0 PURPOSE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 3.0 INITIAL CONDITIONS AND/OR REQUIREMENTS . . . . . . . . . . . . . . 1 4.0 RELEASE RATE DETERMINATION . . . . . . . . . . . . . . . . . . . . 1 4.1 STACK GAS MONITOR READING . . . . . . . . . . . . . . . . . . . . 1 4.2 STACK FLOW RATE . . . . . . . . . . . . . . . . . . . . . . . . . 1 4.3 RELEASE RATE . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 5.0 ATTACHMENTS . . . . . . . . . . . . . . . . . . . . . . . . . . 2 ATTACRMENTS Attachment 1, " Stack Gas Monitor Conversion Factor" eiO383-0028c-154-89
0 '
PALISADES NUCLEAR PLANT Proc No EI-6.1 EMERGENCY IMPLEMENTATION PROCEDURE Revision 0 Page 1 of 2 TITLE: RELEASE RATE DETER!INATION FROM STACK GAS MONITORS
?
e -
1.0 PERSONNEL RESPONSIBILITY The Chemistry / Health Physics Support Group Leyder.shall implement this procedure. In the absence of a Chemistry / Health Physics Support Group Leader, the Site Emergency Director (SED) shall delegate this responsibility.
2.0 PURPOSE < '
This procedure provides a release rate for radioactive ef fluents from the Plant stack. This data is used as inputtto offsite dose l calculations. -
! 3.0 '
INITIAL CONDITIONS AND/OR REQUIREMENTS -
- a. This procedure shall be implemented as required in EI-6.0.
s ,
- b. Data a'nd results from this section should be recorded on the Dose ~
Assessment Worksheet, Attachment 1 to EI-6.0, in Section I.I.
4.0 RELEASE RATE DETERMINATION -
4.1 STACK GAS MONITOR READING a.
Obtain the stack gas monitor reading from' chart recorder RR-2300 located behind the C-11 panel in the control Room. RIA-2318 is the preferred monitor. RIA-2319 should be"used as a backup.
Record monitor reading on the worksheet, item (A), Mark which monitor was used to provide the data.
- b. Obtain the background reading from the same monitor taken at a time prior to the release. .The default values for background are 1000 cpm for RIA-2318 and 50 cpm for RIA-2319. Record background reading on worksheet Section (B).
- c. Obtain a net count rate by subtracting stack monitor back-ground (B) from current stack monitor reading (A).
Record on worksheet, item (C).
i 4.2 STACK FLOW RATE
- a. Obtain stack gas flow rate from the C-11A panel, located in the Control Room on chart recorder FR-2318. Record on worksheet, l item (D). If a reading is unavailable, use 82,000 ft /3 min as a
! default value. ~
- b. Convert f 3 by 4.72E {ogsygge to m /see by multiplying stack gas flow rate (D) l RecordonworkkbaeeEf" item (E). f .
1 -
eiO383-0028a-154-89
, ,_- , _~ . _ . , _ - - . _ _ - _ . - _ . . _
PALISADES NUCLEAR PLANT Proc No EI-6.1 ENERGENCY IMPLEMENTATION PROCEDURE Revision 0 Page 2 of 2 TITLE: RELEASE RATE DETERMINATION FROM STACK GAS MONITORS 4.3 RELEASE RATE k
- a. Obtain the conversion factor as follows:
- 1. For releases involving fuel melt or fuel failure, obtain the conversion factor from Attachment 1, using time after reactor 1
shutdown as the time past accident.
- 2. For releases other than fuel melt or fuel failure use the following converson factors:
RIA-2318 = 6.1E-8 Ci/m3 cpm RIA-2319 = 7.5E-7 Ci/m3 cpm Record conversion factor on worksheet, item (F).
- b. Calculate the noble ges release rate (QN) as follows:
(QN (Ci/sec) = Net stack gas monitor reading (cpm) x stackgasflowratek7mfsec) c x conversion factor --
cpm Record results on worksheet, item (G).
- c. Calculate the iodine release rate (QI) as follows:
i QI = QN x (1.0E-3)
Record results on worksheet, item,(H).
4.4 Continue with next procedure, per EI-6.0.
5.0 ATTACHMENTS 4
Attachment 1, " Stack Gas Monitor Conversion Factor" A
A eiO383-0028a-154-89
D- a Proc No EI-6.1 Attachment 1 P.evision 0 Page 1 of I STACK CAS MONITOR CONVERSION FACTOR C
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Proc No EI-6.12 Revision 0 i
Date 5/23/33 PALISADES NUCLEAR PLANT E!!ERGENCY I?!PLEt1ENTATION PROCEDURE l Revision and Approval Summary i
4 TITLE: C0!!PARISON OF OFFSITE F10NITORING WITH OFFSITE DOSE CALCULATIONS
( 1. Prepar d 2. QA Concurrence i ) -
~ krigj/nator h lY - . . .
5llW33 Ifate Afl) -
Date 02 & &Nf
- 3. Recommend Approval /Q-List No 4. PRC Reviewed i duIM Dpartmbat Head Ma Date as/K y ,M
, ;g g .,g ,. ,y i Date i
- 5. Approved 6. AT?IS Incorporated 4
fe hi2Al d 8'-33-d3 Q' Plant ?!anagep Date Date
~
i 7. Biennial Review Date eiO383-0048c154 e e g 1* ?..+wevy'.- w-a+g-rt -* T- g- - ='-J '-'F'
PALISADES NUCLEAR PLANT Proc No EI-6.12 EMERGENCY IMPLEMENTATION PROCEDURE Revision 0 Page i TITLE: C0!! PARIS 0N OF OFFSITE MONITORING WITII 0FFSITE DOSE CALCULATIONS Table of Contents Page 1.0 PERSONNEL RESPONSIBILITY . . . . . . . . . . . . . . . . . . . . I 2.0 PURPOSE . . . . . . . . . . . . . . . . . . . . . . 1 3.0 INITIAL CONDITIONS AND/OR REQUIREMENTS . . . . . . . . 1 4.0 PROCEDURE . . . . . . . . . . . . . . . . . . . . . . 1 4.1 0FFSITE MONITORING DATA . . . . . . . . . . . . . . . . . . . . 1 4.2 0FFSITE DOSE CALCULATION DATA . . . . . . . . . . . . . . . . . 1 4.3 DATA COMPARISON . . . . . . . . . . . . . . . . . . . . 2 4.4 REVIEW OF RESULTS . . . . . . . . . . . . . . . . . . . 2 5.0 ATTACl[MENTS . . . . . . . . . . . . . . . . . . . . . . . . . 2 l
i l
l l
eiO383-0048bl54 1
l 1
l
- n. .
PALISADES NUCLEAR PLANT Proc No EI-6.12 EMERGENCY IMPLEMENTATION PROCEDURE Revision 0 Page 1 of 2 TITLE: COMPARISON OF OFFSITE MONITORING WITH OFFSITE DOSE CALCULATIONS 1.0 PURPOSE The Chemistry /llealth Physics Group Leader is responsible for the implementation of this procedure. In the absence of a Chemis-try/ Health Physics Group Leader, the Site Emergency Director shall delegate this responsibility.
2.0 PURPOSE This procedure provides a method for comparison of offsite monitoring results with offsite dose calculations.
3.0 INITIAL CONDITIONS AND/OR REQUIREMENTS
- a. This procedure shall be implemented as required per EI-6.0.
- b. , Data and results from this procedure should be recorded on the Offsite Dose Worksheet, Attachment I to EI-6.0, in Section V.I.
- c. Offsite dose calculations and offsite monitoring results must be available prior to implementing this procedure.
4.0 PROCEDURE 4.1 0FFSITE MONITORING DATA
- a. If available, obtain the most recent offsite monitoring data from the Operational Support Center (OSC) for the following locations:
Site Boundary (.5 mi), 2 miles, 5 miles and 10 miles. Record the finite cloud whole body dose rate and I-131 dose equivalent
, concentration (pCi/ce). Record on worksheet, items (A) and (B).
respectively.
- b. Obtain the observed plume direction from the OSC in degrees and record on worksheet, item (C).
4.2 0FFSITE DOSE CALCULATION DATA a.
Obtain the most recent results from the Offsite Dose Calculation Procedure (worksheet,Section IV) for the following locations:
Site boundary (.5 mi), 2 miles, 5 miles and 10 miles. Record the
. finite cloud whole body dose rates (mrem /hr) and I-131 dose equivalent concentrations (pCi/cc) on worksheet, items (D) and (E) respectively.
l b.
Obtain the wind direction from Section III of the worksheet.
Record on worksheet, item (F). ~
- c. If (F) is 2 0* and < 180*, then (G) = (F) + 180 If (F) is 2 180 and < 360 , then (G) = (F) - 180' Record (G) on worksheet in degrees.
eiO383-0048a154
PALISADES NUCLEAR PLANT Proc No EI-6.12 EMERGENCY IMPLEMENTATION PROCEDURE Revision 0 i
Page 2 of 2 TITLE: COMPARISON OF OFFSITE NONITORING WITH OFFSITE DOSE CALCULATIONS .
4.3 DATA COMPARISON
- a. Subtract calculated finite cloud whole body dose rates (D) from measured whole body dose rates (A) for each distance. Record results on worksheet, item (H). If (H) > 0, circle it in red.
- b. Subtract culculated I-131 dose equivalent concentrations (E) from measured I-131 dose equivalent concentrations (B) for each distance. Record results on worksheet, item (I). If (I) > 0, circle it in red.
- c. Divide the calculated finite cloud whole body. dose rates (D) by measured whole body dose rates (A). Record on worksheet, item (J). If (J) > 2.0, circle it in red.
- d. Divide the calculated I-131 dose equivalent concentrations (E) by the measured I-131 dose equivalent concentrations (B). Record results on worksheet, item (K). If (K) > 2.0, circle it in red.
- e. Subtract the estimated plume direction (C) from the measured wind direction (G). Record on worksheet, item (L). If the absolute value of (L) > 10*, circle it in red.
4.4 REVIEW OF RESULTS
- a. The Chemistry / Health Physics Support Group Leader should review f
the worksheet and note all data circled in red. The following specific areas should be considered:
- 1. Calculational errors.
- 2. Instrument malfunction.
- 3. Inaccurate monitoring team locating.
- b. Offsite monitoring results that are significantly different than calculated results should be taken into consideration when making recommendations for offsite protective actions (Reference EI-6.13).
5.0 ATTACIDfENTS None l -
e l
l eiO383-0048a154 l
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I Proc No EI-l Revision 7 Date 5/23/33 PALISADES NUCLEAR PLANT EFIERGENCY I!!PLEttENTATION PROCEDURE l Revision and Approval Sununary I I TITLE: ACTIVATION OF TIfE SITE Et1ERGENCY PLAN /
EriERGENCY CLASSIFICATION l
- 1. Prepared 2. QA Concurrence 3 ,.
/ IIlfil' D JVA r' fnator ' Ifate Date I l': &lp&
- 3. Recommend, Approval /Q-List No 4. PRC Reviewed D
MIK- rtment IIcad skks bade w&4 .](c'c ,y3-c tv de
/ Date
- 5. Approved 6. ATt!S Incorporated I
' O dm wx d- A a Date b /es SD,P7 ~
PlantManagr Date i
- 7. Biennial Review l
l Date l- .
ei0780-0005el54
PALISADES NUCLEAR PLANT Proc No EI-1 EMERGENCY IMPLEMENTATION PROCEDURE Revision 7
- Page i 5
TITLE: ACTIVATION OF THE SITE EMERGENCY PLAN /
EMERGENCY CLASSIFICATION Table of Contents ,
Page 1.0 PERSONNEL RESPONSIBILITIES . . . . . . . . . . . . . . . . . . . . 1 2.0 _ PURPOSE , . . . . . . . . . . . . . . . . . . . . . . . . . . . 1
! 3.0 INITIAL CONDITIONS AND/OR REQUIREMENTS . . . . . . . . . . . . . . 1-3 4.0 ACTIVATION OF THE SITE EMERGENCY PLAN / EMERGENCY CLASSIFICATION . . 1 4.1 CLASSIFICATION / RECLASSIFICATION . . . . . . . . . . . . . . . . . 1 4.2 DETERMINATION OF EMERGENCY ACTIONS / NOTIFICATIONS . . . . . . . . . 3 l 4.3 TURN OVER OF SED RESPONSIBILITIES . . . . . . . . . . . . . . . . 3 5.0 ATTACHMENTS . . . . . . . . . . . . . . . . . . . . . . . . . . 3 I
ATTACIDIENTS l
Attachment 1, " Site Emergency Plan Classification" Attachment 2, " Emergency Class Description" i
1 i
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e10780-0005d-154-89 l . _
_ _ _ _ __.__.__ - _ - ~ . _ - . - - - _ _ _ . . _ ._:,,_.-.._.___-._,_ -- - - . _ . _ _ . .
___ = _
PALISADES NUCLEAR PLANT Proc No EI-I EMERGENCY IMPLEMENTATION PROCEDURE Revision 7 Page 1 of 3 TITLE: ACTIVATION OF THE SITE EMERGENCY PLAN /
EMERGENCY CLASSIFICATION 4
1.0 PERSONNEL RESPONSIBILITIES 1.1 The Shif t Supervisor shall implement this procedure and assume the title and responsibilities of the Site Emergency Director (SED) until relieved by Plant management identified below.
1.2 The line of succession for the SED is:
- a. Plant Manager (days), Duty and Call Superintendent (nights)
- b. Operations and Maintenance Superintendent (1st alternate)
- c. Operations Superintendent (2nd alternate)
- d. Technical Superintendent (3rd alternate)
, e. Technical Engineer (4th alternate) 2.0 PURPOSE To classify those emergency conditions that necessitate the act'ivation of the Site Emergency Plan. To identify actions that should be taken to mitigate the consequences of an emergency.
3.0 INITIAL CONDITIONS AND/OR REQUIREMENTS i
Thi: proc,edure shall be. implemented any time an event occurs or conditions exist which, in the opinion of the Shif t Supervisor / SED, may require activation of the Site Emergency Plan (SEP).
QR When events occur or conditions exist af ter the activation of the SEP that, in the opinion of the SED, may require reclassification, either upgrading or downgrading.
4.0 ACTIVATION OF THE SITE EMERGENCY PLAN / EMERGENCY CLASSIFICATION
, 4.1 CLASSIFICATION / RECLASSIFICATION
, a. The Shif t Supervisor / SED shall classify emergency condi-j tions/ events as follows:
l -
l l
eio780-0005a-154-89
- . _ . . . ~ , , _ . . _ . - , _ _ . , _ . . , . _ , , . _ _ _ _ , , , .__ ,_. , . _ , _ . , . . , . . , ,
- e PALfSADES NUCLEAR PLANT Proc No EI-I EMERGENCY IMPLEMENTATION PROCEDURE Revision 7
' Page 2 of 3 TITLE: ACTIVATION OF THE SITE EMERGENCY PLAN /
EMERGENCY CLASSIFICATION
. 1. Determine the category that conditions / events best fit from the list of keywords below:
Alarms / Annunciators Communication Loss Containment Integrity Engineered Safety Features Evacuation - Control Room Fire i Fission Product Barriers / Fuel Damage Hazards - General
- ' Inj ury Meteorological Data Loss Miscellaneous Natural Phenomenon 1
- Plant Power - Electrical Primary Coolant System Integrity Primary Coolant System - Temper'ature or Pressure Radiation levels Releases i
{ Safety Injection System Secondary Side j Security 1
- 2. Use the keyword. identified above and Attachment.1, Site Emergency Plan Classification to classify the-condi-tions/ event.
! NOTE: Attachment 2, Emergency Class Description is provided for background information and should not be used for classification. .
l eio780-0005a-154-89 i
i i
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- s ,.i,.,y y y, - , - , - - - - ,. ~y.+ n.-_ , ,- . . .-,-_--v~ , -. ,,
PALTSADES NUCLEAR PLANT Proc No EI-l
~
EMERGENCY IMPLEMENTATION PROCEDURE Revision 7 Page 3 of 3 TITLE: ACTIVATION OF THE SITL EMERGENCY PLAN /
EMERGENCY CLASSIFICATION 4.2 DETERMINATION OF EMERGENCY ACTIONS / NOTIFICATIONS
- a. The numbers in the righthand column of Attachment 1 (Actions / Noti-fications) identifies actions that should be performed for each emergency. These numbers relate to the Actions / Notifications listed in EI-2,1, Attachment 1.
- b. The categories of actions are as follows:
- l. ~ Mandatory Actions - Actions that shall be performed within one hour.
- 2. Subsequent Actions - Action that should be performed in an expeditious manner as conditions, time, and personnel permit.
- 3. If Needed Actions - Actions that are not required, but may be needed.
- c. Af ter determination of the emergency actions / notifications mark the lefthand column of EI-2.1, Attachment I with an M, S or I for Mandatory, Subsequent or If Needed Action respectively, for each identified emergency action. Date EI-2.1, Attachment 1.
NOTE: Emergency actions identified in this section are in addition to the SED responsibilities identified in EI-2.1. -
4.3 TURN OVER OF SED RESPONSIBILITIES
- a. The Shift Supervisor shall turn over the responsibilities of SED to the personnel identified in Section 1.0 as soon as possible, above. Unusual Event. Turn over may occur before this time at th'e option of the Shif t Supervisor or potential SED.
- b. Turn over should include verification of the emergency classification and pertinent information on Plant conditions.
- c. The turn over should be announced in the Technical Support Center (TSC) and Operational Support Center (OSC), if activated, to ensure continuity of command and control.
- d. Proceed to EI-2.1, " Emergency Actions / Notifications / Responsibilities" 5.0 ATTACHMENTS 5.1 Attachment 1, " Site Emergency Plan Classification" 5.2 Attachment 2, " Emergency Class Description" ei0780-0005a-154-89
1 1 roc No r'-l 4
Attachmt 1 Fevision 7 Page 1 of 27 ALARMS /ANNLINCIATORS CLASSIFICATION EMERGENCY ACTION LEVEL !!ETIIOD OF DETECTION ACTIONS Alert. Loss of most or all alarms Observation .
Mandatory: 1,2,3,4,5, (annunciators) in Control' Room. 6, 11, 12, 14 ,-
17, 22
' Subsequent: 18, 24, 33, 34 If Needed: 19, 25, 30 Site Area Loss of most or all alarms observation Mandatory: 1, 2,3,4,5, Emergency (annunciators) for 15 minutes g 6, 11, 12, 13,
' Shift Supervisors opinion that a 14, 17, 22 Plant transient has occurred or is Subsequent: 16, 18, 19, 21 in progress. 23, 24, 33, 34 If Needed: 19, 25, 26 l
l i .
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3 I
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eio780-000'b-154-89
Proc No 1 Attachment I .
Revision 7 Page 2 of 27 C0ffflUNICAT10NS LOSS CLASSIFICATION EFfERGENCY ACTION LEVELS tlETil0D OI' m'TECTION ACTIONS
- Unusual Significant loss of offsite Observat. ion Planda to ry: 1, 3, 4, 5, 6 Event. conununication capability. Subsequent: 24, 34 (eg, loss of all conunercial and If Needed: 2, 26, 33 .
dedicated phones) l 4
I i
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eio780-0005b-154-89
Proc No -1 Attachuient 1 Revision 7 Page 3 of 27 CONTAINt!ENT INTEGRITY CLASSIFICATION Ef!ERGENCY ACTION LEVEL t!ETIIOD OF DETECTION ACTIONS Unusual Loss of Containment integrity Leak Rate Test Results flanda tory: 1, 3, 4, 5, 6 Event requiring shutdown due to OR Penetration Test Result.s Subsequent: 24, 34 Technical Specifications . 013 Observation If Needed: 2, 26, 33 NOTE: For incidents involving loss of containment integrity AND loss of- a second fission product. barrier A_ND potential loss of the third fission product. barrier, see FISSION PRODLICT BARRIER /FliEL DAtlAGE.
eio780-0005b-154-89
. 1 l
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Proc No 1 A t ta ciunen t 1 7-Revision 7 a
Page 4 of 27 ,
j ENGINEERED SAFETY FEATURES .
I CLASSlFICATION ErlERGENCY ACTION LEVEL HETil0D OF DETECTION ACTIONS
- Unusual Loss of engineered safety Observation Handatory
- 1,3,4,5,6
- Event features requiring Plant shut- Subsequent: 24,-~34 1
down due to Technical Speci- If Needed: 2, 26, 33 fications 3.2, 3.3, 3.4.
4 Loss of fire protection system Observation y requiring Plant shutdown due to i Technical Specifications.
. Alert Failure of Reactor Protec. tion Nuclear instrumentat. ion Handatory: 1,2,3,4,5 system to initiat.e and complete AND Rod posit. ion indicator 6, 11, 12, 14 a trip ANI) the reactor is not 17, 22 subcritical. -
Subsequent: 18, 24, 34 ,
3 If Needed: 19, 25, 26 i
Complete loss of any functions needed for Plant cold shutdown l ie, Loss. of Auxiliary Feed System t
{ and Shutdown Cooling Systems. !
I -
i :
Site Area Complete loss of any function Annunciation Handatory: 1,2,3,4,5, '
Emergencv needed for hot shutdown OR 6, 11, 12, 13, 4
Observation 14, 17, 22 Subsequent: 16, 18, 19, 21, 23, 24, 33, 34 If Needed: 15, 25, 26 i
Transient- requiring operation Nuclea r instrumentation
- of shutdown systems with failure ,1NI) Rod position indicator j to trip (continued power *
- generation, but no core damage immediately evident). >
eio780-0005b-154-89 '
1 Proc No 1 Attachment 1 -
Revision 7 Page 5 of 27 EVACUATION, CONTROL ROOM CLASSIFICATION Et!ERGENCY ACTION LEVEL tlETil0D OF DETECTION ACTIONS Alert Evacuation of Control Room Observation flandatory: 1,2,3,4,5, anticipated or required with 6, 11, 12, 14, i control of shutdown system 17, 22 established at local stations. Subsequent: 18, 24, 33, 34 If Needed: 19, 25, 26 Site Area Evacuation of Control Room and Observation Plandatory: 1, 2, 3, 4, S Emergency control of shutdown systems not 6, 11, 12, 13, established at local stat. ions 14, 17, 22 within 15 minutes. Subseqiient : 16, 18, 19, 21 23, 24, 33, 34 If Needed: 15, 25, 26 eio780-0005b-154-89 e
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Proc No 1 Attachment 1 -
Revision 7 Page 6 of 27 FIRE CLASSIFICATION ENERGENCY ACTION I.EVEL tlET110D OF DETECTION ACTIONS ~
Unusual Fire within the Plant lasting Observation Manilatory: 1,3,4,5,6, Event. more than 10 minutes. OR 7, 1I 5 ire iletection alarm con- Subseignen t : 24, 34 firmeil by observaLion. I f Neeileil: 2, 8, 26, 33 Alert. Fire potent.ially affects a safety Shift Supervisor's opinion Ma nila to ry : 1, 2, 3, 4, 5, systems. 6, 7, 11, 12, 14, 17, 22 Subsequent.: 24, 34 If Neeileil: 2, 8, 26, 33 Site Area Fire compromising the function of Observation Manila to ry : 1, 2, 3,-4, 5, Emergency sa fety systems. 6, 7, 11, 12, 13, 14, 17, 22 Subseiluent: 16, 18, 19, 21, 23, 24, 33, 34 ,
I f Neeileil: 8, 15, 25, 26
, ei0780-0005b-154-89
Proc No 1 .
Attachment 1 -
Revision 7 Page 7 o f 27 j FISSION PRODUCT BARRIERS / FUEL DAtlAGE CLASSIFICATION EffERGENCY ACTION LEVEL ffETi!0D OF DETECTION ACTIONS Unusual Primary Coolant Iodine-131 dose Failed Fuel rionitor !!anda tory: 1, 3, 4, 5, 6 Event ' concentration equivalent (**RIA-0202) Alarm confirmed Subsequent: 24, 34
> 1.0pCi/gm for more than 72 hrs. by sample analysis, if Needed: 2, 26, 33 F
> 0.1% increase in failed fuel Observation
- within 30 minutes. **RIA-0202 1 Alert Primary Coolant Iodine-131 dose Failed Fuel flonitor flandatory
- 1,2,3,4,5 equivalent concentration (**RIA-0202) off scale high 6, 11, 12, 14, -
> 300pCi/gm confirmed by sample analysis. 17, 22 Subsequent": 18, 24, 33, 34 If Needed: 19, 25, 26 J
> 1% increase in failed fuel Observation within 30 minutes.
e
> 5% total failed fuel. Failed Fuel rionitor
(**RIA-0202) off scale high
, confirmed by sample analysts OR observation 1
Fuel damage accident with release Radiation monitor alarm con-of radioactivity to Containment firmed af ter observation of i
or Fuel liandling Building. accident OR
, Observation of accident
! confirmed by sample analysis
- OR blif t Supervisor / SED's opinion i
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Proc No . 1 i -
Attachment 1 Revision 7 Page 11 of 27 IIAZARDS - GENERAL CLASSIFICATION EPIERGENCY ACTION LEVEL flETIIOD OF DETECTION ACTIONS Site Area Aircraft crash affecting vital Observation Handatory: 1,2,3,4,5, Emergency structures by impact or fire AND 6, 11, 12, 13, Plant not in cold shutdown. 14, 17, 22 Subsequent: 16, 18, 19, 21,
+
23, 24, 33, 34 I f Needed: 15, 25, 26 Severe damage to equipment re-quired for safe shutdown from missile explosion - see ENGINEERED SAFETY FEATURES Entry of uncontrolled flammable Observation OR gas into vital areas OR Entry Detection with portable of uncontrolled toxic gas into instrumentation.
vital areas that constitutes a .
safety problem AND Plant not in Cold Shutdown.
4
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3 ei0780-0005b-154-89
Proc No -1 At t a ciunent 1 -*-
Revision 7 Page 12 of 27 INJIIRY CLASSIFICATION EMERGENCY ACTION LEVEL tlETl!OD OF DETECTION ACTIONS Unusual Transportation of injured contam- Oleservation flandatory: 1, 3,4,5,6,8, Event inated individual from site to 10 offsite hospital. Sul> sequent: 24, 34 If Needed: 2, 9, 26 Notify county to whicia victim is taken.
eio780-0005b-154-89
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Proc Mo 1 A t t a clunen t 1 -
Revision 7 Page 14 of 27 -
tilSCELLANEOUS CLASSIFICATION EtlERGENCY ACTION LEVEL tlETil0D OF DETECTION ACTIONS Unusual Plant conditions exist that war- Shi f t Supervisor / SED's opinion flandatory: 1,3,4,5,6 Event rant increased awareness on the Subsequent: 24, 34 part of the Plant. staff or State If Needed: 2, 26, 33 and/or local authorities OR
- require Plant. shutdown under Technical Specifications require-ments OR involve other than norma 1 shutdawn.
Alert Plant condit. ions exist that. war- Shift Supervisor / SED's opinion !!andatory: 1, 2, 3, 4, ",,
rant precautionary activat. ion 6, 11, 12, 14 of Technical Support Center and 17, 22 placing Emergency Operations Subsequent.: 18, 24, 33, 34 Facility and other emergency If Needed: 19, 25, 26 personnel on standby.
Site Area Plant conditions warrent the Shift Supervisor / SED's opinion ?!andatory: 1,2,3,4,5, Emergency activation of emergency centers 6, 11, 12, 13, and monitoring teams or a precau- 14, 17, 22 Subsequent:
tionary notification to the 16, 18, 19, 21, ,
public near the site. 23, 24, 33, 34 If Needed: 15, 25, 26 General Condit. ions exist that make Shif t Supervisor / SED's opinion flandatory: 1, 2, 3, 4, 5, Emergency release of large amounts of radio- 6, 11, 12, 13, activity in a short time possible, 14, 17, 22 (eg, any core melt situat. ion) Subsequent: 16, 18, 19, 21, 23, 24, 33, 34 If Needed: 15, 25, 26 eio780-0005b-154-89
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Proc No -1 Attachment 1 .
lievision 7 Page 16 of 27 PLANT POWER - ELECTRICAL CLASSIFICATION EMERGENCY ACTION LEVEL NET 110D OF DETECTION ACTIONS Unusual Loss of offsite power Annunciation switchyard non- flandatory: 1,3,4,5,6 Event critical alarms OR startup t rans former t roul>~Ie alarm OR Subse<1uent: 24, 34 Automatic start of Emergency
. Diesel Generator. If Needed: 2, 26, 32, 33 Loss of all onsite AC power Chservation: both Emergency Diesel Generators inoperable Alert Loss of offsite power AND loss of llus IC & ID low voltage !!anda to ry : 1, 2, 3, 4, 5, all onsite AC power for less than alarms 6, 11, 12, 14, 15 minutes. 17, 22 Subseiluent : 18, 24, 33, 34 If Needed: 19, 25, 26, 32 Loss of all onsite DC power for DC Bus #1 and #2 low voltage less than 15 minutes alarms.
Site Area Loss of of fsite power AND loss of Observation Handatory: 1,2,3,4,5, Emergency onsite AC for more than 6, 11, 12, 13, 15 minutes. 14, 17, 22 Subsestuen t : 16, 18, 19, 21, 23, 24, 33, 34 1f Needed: 15, 25, 26, 32 Loss of all vital onsite DC power Observation for more than 15 minutes, AND Plant not in cold shutdown.
ei0780-0005b-154-89
Proc No -1 Attachment 1 -
, Revision 7 Page 17 of 27 PRIMARY COOLANT SYSTEM INTEGRITY CLASSIFICATION EMERGENCY ACTION LEVEL METil0D OF DETECTION ACTIONS
. Unusual Primary Coolant System leakage in PCS leak rate determination Mandatory: 1,3,4,5,6 Event' excess of Technical Specifications (D/WO-1) Subsequent: 24, 34 .
but < 50 GPM If Needed: 2, 26, 33 Steam Generator secondary water Chemical analysis ,
activity > 0.1pCi/gm of dose equivalent I-131.
Primary to secondary leakage rate Offgas monitor (**RIA-0631) exceeds Technical Specifications alarm confirmed by chemical limits of 0.3 GPM steady state or analysis i,
0.6 CPM for transients, but-
< 50 GPM.
i l Alert Rapid gross failure of one Steam Offgas monitor (**RIA-0631) Mandatory: 1,2,3,4,5 Generator tube with loss of alarm confirmed by sample 6, 11, 12, 14, offsite power. . ,
analysis AND Decreasing 17, 22 pressurizer level AND Obser-vation of loss of offsite 4
power Rapid failure of Steam Generator Offgas monitor (**RIA-0631) Subsequent: 18, 24, 33, 34
! tubes resulting in primary to alarm confirmed by sample secondary leak rate of several analysis OR Rapidly de-hundred CPM.
creasing pressurizer low If heeded: '19, 25, 26 level (**LI-0103A) i Steam line_ break with > 10 GPM Increased containment pressure primary to secondary leak rate. OR Increased Containment
- radiation levels; Decreasing pressurizer levels, OR Of fgas flonitor (**RIA-0631) alarm confirmed by sample analysis eio780-0005b-154-89 ,
Proc No 1 Attachment 1 .
Revision 7 Page 18 of 27 PRIMARY COOLANT SYSTEt! INTEGRITY CLASSIFICATION EtIERGENCY ACTION LEVEL ?!ETIIOD OF DETECTION ACTIONS Primary Coolant System le,ak Containment sump high level
> 50 GPfl but less than charging alarms Ay mismatch between pump capacity. charging flow and letdown flow Site Area Loss of coolant accident greater Low-low pressurizer level llanda t o ry: 1,2,3,4,5, Emergency than charging pump capacity. (**LIC-0101 A) OR Safety 6, 11, 12, 13, Injection actuation alarm OR_ 14, 17, 22 Pressurizer low pressure alarm Subsequent: 16, 18, 19, 21, 011 Containment high pressure 23, 24, 33, 34 alarm If Needed: 15, 25, 26 Rapid failure of Steam Generator .Offgas monitor (**RIA-0631) tubes (several hundred GPr!) with alarm confirmed by sample i
loss of offsite power, analysis AND Pressurizer level decreat,e AND Observation of loss of of fsite power.
Steam line break AND > 50 GPfl Increased Containment pressure primary to secondary leak rate OR Increased Containment AND indication of fuel radiation levels OR decreasing
, damage. pressurizer levels OR Steam Generator pressure instruments OR PCS leak rate determination
}
- Tii/WO-1) AND Offgas flonitor 4
(1*<RIA-0631) alarm confirmed -
by sample analysis AND Failed Fuel flonitor Alarm confirmed OR PCS sample analysis confi rms fuel damage.
NOTE: For incidents involving loss of Primary Coolant System Integrity ANi}
v loss of a second fission product barrier AND potential loss of the_
third fission product barrier, see FISSION PRODUCT BAhl!IER/FtIEL DAtlAGE.
(
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Proc No . 1 f,ttachment 1 .*
Revision 7 Page 21 of 27 RELEASES CLASSIFICATION EMERGENCY ACTION LEVEL ?!ETilOD OF DETECTION ACTIONS 1 .
Unusual Short term radiological effluent. Stack monitor (**RIA-2318) flandatory: 1, '1, 4, 5, 6 ;
- Event Technical Specifications exceeded. reaches high alarm setpoint Subsequent
- 24, 34 f or two or more hours. If Needed: 2, 12, 13, 26 ;
Confirmed by Lab sample 33 analysis. i Liquid waste discharge monitor ,
(**RIA-1049) reaches alarm setpoint and automatic dis-charge trip function fails. .
Confirmed.by Lab sample analysis.
s Significant solid or liquid waste Observation confirmed by spill outside restricted areas survey results.
, with threatened offsite release. '
i Alert Radiological effluents > 10 times A valid stack monitor flanda tory: 1, 2, 3, 4, 5, the Technical Specifications (**RI A-2318) reading of 6, 11, 12, 14, 3 limits (an instantaneous rate 2 4400 cpm above background 17, 22 which, if continued over two for longer than 15 minutes. Subsequent: 18, 24, 33, 34 hours3.935185e-4 days <br />0.00944 hours <br />5.621693e-5 weeks <br />1.2937e-5 months <br /> would result in a dose of OR_ If Neede1: 13, 19, 25, 26, approximately 1 mR at the site Liquid kfaste Discharge tionitor 27, 28, 39, 30, boundary under average meteor- (* ARIA-1049) reaches 10 times 31 ological conditions). alarm setpoint and automatic
, discharge trip function fills.
Confirmed by Lab sample ,
analysis.
l [
- 4. eio780-0005b-154-89 1 ,
i
Proc No 1 A t t a ciunen t 1 .
Revision 7 Page 22 of 27 RELEASES CLASSIFICATION Et!ERGENCY ACTION LEVEL t!ET110D OF DETECTION ACTIONS 1
Site Area Effluent monitors detect levels Auy of the following valid !!anda tory: 1,2,3,4,5, '
Emergency corresponding to > 50 mR/hr radiation monitor readings 6, 11, 12, 13, for la hour or > 500,mR/hr whole for longer than 0.5 hour: 14, 17, 22 body for 2 minutes (or 5 times Stack monitor (**RIA-2318); Subsertuent : 16, 18, 19, 21 these levels to the child thyroid) 2 3.75Et5 cpm above bkgd. 23, 24, 33, 34 at the site boundary for adverse liain Steam tionitors if Needed: 15, 25, 26, 27, meteorological conditions. These *f RI A-2323 or **RI A-2324) 28, 29, 30, 31 levels are projected based on with a main steam release other Plant parameters (eg, radi- occurring; ation level in containment with 2 850 cpm above bkgd leak rate appropriate for exist- and confirmation of dose ing containment pressure) or from procedure EI-6.0 are measured in the environs. Containment high range moni-EPA Protective Action Guide- tors (**RfA-2321 or *4RIA-2322) lines (see El-6.13) are pro- with no breach of con-jected to be exceeded outside tainment; the site boundary. 2 2.4Et4 R/hr above bkgd.
O_R Any of the following valid radiation monitor readings for longer than 2 minutes:
Stack tionitor (**RIA-2318) is of fscale and the liigh Range Stack flonitor is s 3.2E-3 R/hi above hkgd.
flain Steam flonitors (**RIA-2323 or f1RI A-2324) with a main steam release occurring; 2 8500 cpm above bkgd and confirmation of dose projection f rom procedure El-6.0 e10780-000Sb-154-89
- - _ _ . _ , _ _ . _ - _ _ _ _ _ . . _ _ _ . . - _ __ - . _ . _ . .._ .- . . _ . - - _ _ _ _ . _ .._ _ - . _ - ~ ~.
Proc No . -1 Attachment. 1 -
Revision 7 Page 23 of 27 REl. EASES CLASSIFICATION EtlERGENCY ACTION LEVEL ttETil0D OF DETECTION
- ACTIONS Site Area Contairunent liigh Range tioni-Emergency tors (**RIA-2321 or **RIA-2322)
(cont'd) with no breach of contain- '
ment; 2 2.4E+5 R/hr above bkgd.
1 OR +
1 Radiat. ion monitoring teams at the site boundary measure
- i. hole body dose rates
> 50 mrem /hr for 0.5 hr or
> 500 mrem /hr for 2 min or i
thyroid dose rates ,
> 250 mrem /hr (1.95E-7 pCi/cc dose esguivalent I-131) for 0.5 hr or 2500 mrem /hr (1.95E-6 pCi/cc dose eiguivalent
- 1 I-131) for 2 minutes.
General Effluent. monitors detect. levels Any of the following valid flanda to ry: 1, 2, 3, 4, 5,
! Emergency corresponding to I rem /hr whole radiation monitor readings mg ,
6, 11, 12, 13, !
body or 5 rem /hr thyroid at the indicate a General Emergency 14, 17, 22 site boundary under actual meteor- Classification: Subsesguent: 16, 18, 19, 21,
, ological conditions. These levels Stack monitor (*?RIA-2318) 23, 24, 33, 34
- are projected based on other Plant is offscale and the high if Needed
- 15, 25, 26, 27, l parameters (eg, radiat. ion levels range stack monitor is: 28, 29, 30, 31 in containment with leak rate 2 6.3E-3 R/hr above bkgd; 4
appropriate for existing contain- flain Steam fronitors (**RIA-2323 ment pressure) or are measured or RI A-2324) wit h a main
] in the environs. steam release occuring is:
4 1 17,000 cpm above bkgd.
l ei0780-0005b-154-89 1
t
O r
Proc No -1 Attachment 1 . >
Revision 7 ;
Page 24 of 27 [
RELEASES !
l t
CLASSIFICATION Et!EhGENCY ACTION LEVEL ?!ET110D OF DETECTION ACTIONS i
General Containment High Range flon-Emergency i t o rs (**RI A-2321.o r **RI A-2322)
(cont'd) with no leakage greater than design leakage limit, 2 4.8E+5 R/hr above bkgd. !
' NOTE: Consider evacuation only within A General Emergency is indica- !
about 2 miles of the site boundary ted if the dose projection f rom i
, unless these site boundary levels procedure El-6.0 is 2 1 New/hr i are exceeded by a factor of 10 or whole body or 2 5 Rem /hr .
projected to continue for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> thyroid at the site boundary ,
or EPA Protective Action Guide- for the existing meteorolo- t 1ines exposure levels (see gical conditions.
j EI-6.13) are predicted to be O_R cxceeded at longer distances. Radiation monitoring teams at j the site boundary measure a whole body dose rate 2 1 Rem /hr
'l or a thyroid dose rate 2 5 Rem /hr (3.9E-6 pCi/cc i dose' equivalent I-131) 1 l 1
L t
l
.i I i
i l .
1
~
eio780-000Sh-154-89
- - _ . . _ _ - - - - , - - , .~ - - - - - - - , - - - -.-e .--
Proc Wo 1 A t t a ctuacn t I .
Revision 7 Page 25 of 27 SAFETY INJECTION SYSTE!!
CLASSIFICATION EMERGENCY ACTION LEVEL tlETIIOD OF DETECTION ACTIONS Unusual Safety Injection initiated and Annunciation flow verified ?!andatory: 1, 3, 4, 5, 6 Event discharged to vessel (Cktl, Ckt2) 24, 34 Subs e<nuent :
11 Needed: 2, 26, 33 4
eio780-000Sb-154-89
I l l
Proc No I Attachment 1 , i Revision 7 Pap,e 26 of 2/
SECONDARY SIDE l l
CI.ASSIFICATION EMERGENCY ACTION I.EVEf. ?!ETi!0D OF DETECTION ACTIONS l
Unusual Failure of a safety or relief Annunciatior. AND Mandatory: 1, 3, 4, 5, 6 Event valve in a safety related system pressure indications, OR Subscinuent: 24, 34 -l to close following reduction of Observation If Needed: 2, 26, 33 applicable pressure.
l l
Rapid depressurization of Low Steam Generator pressure secondary side alarm for accidents involving primary to secondary leakage see "Pri-mary Coolant System Integritv" l
eio780-0005h-154-89
. r Proc No ... 1 r
At tactuuen t I ,
Revision 7 Page 27 of 27 ,
CLASSIFICATION Et!ERGENCY ACTION LEVEL tlETil0D OF DETECTION ACTIONS I
Unusual Security threat or Attempted entry Security alarms OR Event Handatory: 1, 3, 4, 5, 6, or Attempted sabotage Observat. ion AND Subsequent: 24, 34 Activation of Safeguards If Needed: 2, 26, 33 Contingency Procedures.
} ,
T, 4 Alert Security threat exists that Security Alarms OR tlanda to ry: 1,2,3,4,5,
' results in adversaries conunan- Observation AND 6, 11, 12, 14, decring an area of the Plant, but Activation of Safeguards 17, 22 1 not control over shutdown capa- Contingency Procedures Subsequent: 18, 24, 33, 34
- bility or of any vital areas if Needed
- 19, 25, 26 i
Site Area Physical attach on the Plant Security alarms OR Emergency flandatory: 1,2,3,4,5, l involving inuninent occupancy of Observation AND 6, 11, 12, 13 the Control Room, auxiliary shut- Activation of Safeguards 14, 17, 22 down panels, or other vital Contingency Procedures Subsequent:
}, 16, 18, 19, 21, a rea s .
23, 24, 33, 34 If Needed: 15, 25, 26 General Physical attack on the Plant has Security alarms OR Emergency Mandatory: 1, 2, 3, 4, 5,
! resulted in unauthorized personnel Observation AND 6, 11, 12, 13, l occupying the Control Room or any Activation of Safeguards 14, 17, 22 other vital areas. Contingency Procedures Subsequent: 16, 18, 19, 21,
)
23, 24, 33, 34 l
If Needed: 15, 25, 26 4
a 1
I' eio780-0005b-154-89
Proc No EI-6.2 Revision 0 Date 3/M V :-
PALISADES NUCLEAR PLANT Ef!ERGENCY It!PLE!!ENTATION PROCEDURE Revision and Approval Summary TITLE: RELEASE RATE DETERt!INATION FRO?! STEA'l LINE !!ONITORS MRIA-2323 AND M RIA-2324 FOR STEAM RELEASES TifROUGH ATitr. cpl!ERIC DU!!P VALVES
- 1. Prepared 2. QA Concurrence No
/ h ! $l 6ll9l23 bl$
m}inator Dath Date (tVL PA Q1'm6
- 3. Reco end Approval /Q-List 4'e s No 4. PRC Reviewed AWlllMN 'I/9lh3 7///6 e n -lW. ? .
D a'rg/ntllead (Da t'e pi' . Si :/4' 'Date
- 5. Approved 6. ATt!S Incorporated QPlant?!anage 19 S12elb Date S2 'FT date
- 7. Biennial Review Date ciO483-0014e154
PALISADES NUCLEAR PLA!!T Proc No EI-6.2
- E!!ERGENCY It!PLEt1ENTATION PROCEDURE Revision 0 Page i TITLE: RELEASE RATE DETER!!INATION FR0!! STEA!! LINE t!ONITORS
- RIA-2323 AND **RIA-2324 FOR STEA!! RELEASES TliROUGli ATt!OSPIIFRIC DUflP VALVES Taole of Contents Page 1.0 PERSONNEL RESPONSIBILITY . . . . . . . . . . . . . . . . . . . . . I 2.0 PURPOSE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 3.0 INITIAL CONDITIONS AND/OR REQUIRESIENTS . . . . . . . . . . . . . 1 4.0 RELEASE RATE ESTIt!ATION . . . . . . . . . . . . . . . . . . . . . 1 5.0 C0!IFIRMATION OF RELEASE RATE ESTIttATE . . . . . . . . . . . . . . 2 6.0 ATTACIIMENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 ATTACIIMENTS ,
Attachment 1, " Properties of Saturated Steam and Saturated Water (Temperature)"
Attachment 2, " Steam Pressure vs Dump Valve Flow Rate Graph" 6
eiO483-0014d-154-89
4 I
PALISADES NUCLEAR PLA[{T Proc No EI-6.2 EMERGENCY IMPLEMENTATION PROCEDURE Revision 0 1 Page 1 of 7 TITLE: RELEASE RATE DETERMINATION FROM STEAM LINE MONITORS
- RIA-2323 AND **RIA-2324 FOR STEAM RELEASES .
4 TIIROUGli ATMOSPHERIC DUMP VALVES
! 1.0 PERSONNEL RESPONSIBILITY The Chemistry /llealth Physics Support Group Leader shall implement this p rocedu re . In the absence of a Chemistry /ilealth Physics Support Group
, Leader, the Site Emergency Director shall delegate this ;
responsibility. ;
4 2.0 PURPOSE i This procedure provides a release rate for radicactive effluents from the atmospheric dump valves. This data is used as input to offsite dose calculaticns.
3.0 INITIAL CONDITIONS AND/OR REQUIREMENTS
- a. This procedure shall be implemented as required per EI-6.0.
- b. Data and results from this procedure should be recorded on the Offsite Dose Worksheet, Attachment I to EI-6.0 in Section I.2.
- c. This procedure presupposes that a steam dump has occurred or is occurring.
- d. For initial dose estimation, use release rate estimated in Sec-tion 4.0. As data becomes available and time permits, the release rate should be confirmed using Section 5.0.
j 4.0 RELEASE RATE ESTIMATION 4.1 Record date and time on worksheet.
4.2 Record date and time at which steam dump started on worksheet, items (A) and (B) respectively.
4.3 Obtain steam line monitor readings in net counts per minute from
- RIA-2323 (Steam Generator "B") and **RIA-2324 (Steam Generator "A")
l or **RR-2324 from Control Room Panel **EC-11A. Record on worksheet,
] items (C) and (D) respectively.
I 4.4 Multiply ngt CPM for each monitor from Step 4.3 by i 1.73 x 10 Ci/sec/ cpm to obtain release rate, QN in Ci/sec. Record on worksheet, items (E) and (F) respectively.
-2 QN A = CPM x (1.73 x 10 Ci/sec/ cpm)
-2 QN B
= CPt!B x (1.73 x 10 Ci/sec/ cpm) l 4.5 If only one Steam Generator is dumping, use appropriate QN, dose ,
estimation procedures. If both Steam Generators are dumping, use both release rates to determine an average value for QN. Record on worksheet, item (G).
eiO483-0014a-154-89 e-. - .- , . ,-, . - , - . - .- .- - -
=
PALISADES NUCLEAR PLANT Proc No EI-6.2 ENERGENCY IMPLEMENTATION PROCEDURE Revision 0 Page 2 of 7 TITLE: RELEASE RATE DETERMINATION FROM STEA>! LINE MONITORS
. **RIA-2323 AND **RIA-2324 FOR STEAM RELEASES THROUGH ATMOSPHERIC DUMP VALVES 4.6 Obtain Iodine-131 dose equivalent release rate by multiplying noble gas release rate QN, item (G), by 1.0E-3. Record on worksheet, item (ii) .
4.7 The above steps provide suf ficient information to continue of fsite dose calculations. Continue with next procedure, per EI-6.0. Return to Section 5.0 for confirmation of release rates as time permits and data becomes available.
5.0 CONFIRMATION OF RELEASE RATE ESTIMATE 5.1 Record date and time on worksheet.
5.2 Record date and time at which steam dump started on worksheet.
5.3 Obtain and record on worksheet rea or average temperature (T )
reading in 'F from Control Room Panel **EC-2 (CO2), from reco$30rs
- TR-0111 and **TR-0121 or from the Critical Functions Monitor.
5.4 Are Primary Coolant Pumps on? Indicate on worksheet. If pumps are on, proceed to Step 5.5. If pumps are not on, proceed to Step 5.26.
5.5 Assume T equals the steam temperature. Refer to Table 1, "Properts"E of Saturated Steam and Saturated Water (Temperature)".
Enter the table in Column I with the value for T . Record on worksheet the corresponding pressure ,in psia from"Eolumn 2. This is the secondary system steam pressure.
5.6 Enter Attachment 2 with the pressure determined in Step 5.5. Read the Fully Open Dump Valve Saturated Steam Flow Rate in cc/sec corresponding to this pressure. This is the flow rate for one valve in the fully open condition. Record on worksheet.
5.7 Determine and record on worksheet the primary coolant average temperature errors as defined by:
T error = T - 532 F avg avg T,y was recorded in Step 5.3.
5.8 Use the T,y error to determine the fraction the dump valves are open.
If T,y error >25, then fraction = 1.0 If T,y error <25, then fraction the valve is open is determined by:
Fraction valve open = (T,y error x 0.04545) - 0.1346 Recore on worksheet.
eiO483-C014a-154-89 l l
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PALISADES NUCLEAR PLANT Proc No EI-6.2 E!!ERGENCY It!PLE!!ENTATION PROCEDURE Revision 0 4
Page 3 of 7 TITLE: RELEASE RATE DETERMINATION FR0f! STEA!! LINE ?!0NITORS
- RIA-2323 AND **RIA-2324 FOR STEAtt RELEASES T!! ROUGH ATt!OSPHERIC DUt!P VALVES 5.9 Determine and record on worksheet the actual steam flow rate from one dump valve by multiplying together the results form Step 5.6 and Step 5.8 Step 5.6 Step 5.8
, Fully Open Fraction Flow Rate x Valve is = Actual Steam Flow Rate in cc/sec cc/sec open If and only if the necessary information is unavailable, use ,a steam
, flow rate default value determined by the peak secondary pressure of 922 psia which is reached upon turbine trip while operating at.
2450 ini(t). From Attachment 2, 6
922 psia = 4.60 x 10 ccj,ec 5.10 Are steam dumps from Steam Generator "A" open? Indicate on worksheet.
If they are, proceed to Step 5.11. If they are noe, proceed to Step 5.15.
5.11 Obtain reading from ?!ain Steam Line flonitor **RIA-2324 from Control Room Panel **EC-11A. A record is available on Recorder **RR-2324.
Indicate reading in counts per minute (cpm) on worksheet.
5.12 Using the Victoreen calibration of 531 cpm per pCi/ce, obtain total radionuclide concentration from Steam Generator "A" by dividing monitor reading from Step 5.11 by the calibration constant:
- RIA-2324 cpm ,
53.1 cpm = Total Radionuclide Concentration from Steam pCi/cc Generator "A" in pCi/cc Record on worksheet.
5.13 Determine the Steam Generator "A" radionuclide release rate in pCi/sec by multiplying together the concentration from Step 5.12, the actual steam flow rate from Step 9 and a factor of 2 to account for two dumps l valves open. Record result on worksheet.
i Step 5.12 Step 51 9 2 x (concentration pCi/cc) x (Steam Flow Rate cc/sec) ,
= Steam Generator "A" Radionuclide Release Rate pCi/sec 5.14 Steam Generator "A" noble gas release rate in pCi/sec = Step 5.13.
Steam Generator "A" noble gas release rate in pCi/sec = 1.0E-3 x . .-
Step 5.13.
Compute and record on worksheet.
eiO483-0014a-154-89
a PALISADES NUCLEAR PLANT Proc No EI-6 2 EMERGENCY IMPLEMENTATION PROCEDURE Revision 0 Page 4 of 7 TITLE: RELEASE RATE DETERMINATION FROM STEAM LINE MONITORS
- RIA-2323 AND **RIA-2324 FOR STEAM RELEASES TifROUGli ATM0SPifERIC DUMP VALVES 5.15 Are steam dumps from Steam Generator "B" open? Indicate on worksheet.
If they are, proceed to Step 5.16. If they are not, proceed to Step 5.20.
5.16 Obtain reading from Main Steam Line Monitor **RIA-2323 from Control Room Panel **EC-11A. A record is available on Recorder **RR-2324.
Indicate reading in epm on worksheet.
5.17 Using the Victorcen calibration of 531 cpm per pCi/cc, obtain total radionuclide concentration from Steam Generator "B" by dividing monitor reading from Step 5.16 by the calibration constant:
- RIA-2323 cpm 531 cpm = Total Radionuclide Concentration from Steam pCi/cc Generator "B" in pCi/cc Record on worksheet.
5.18 Determine the Steam Generator "B" radionuclide release rate in pCi/sec by multiplying together the concentration from Step 5.17 the actual steam flow rate from Step 5.9 and a factor of 2 to account for two dump valves open. Record result on worksheet.
Step 5.17 Step 5.9 2 x (concentration pCi/cc) x (Steam flow rate cc/sec)
= Steam Generator "B" Radionuclide Release Rate pCi/sec 5.19 Steam Generator "B" noble gas release rate in pCi/sec = Stap 5.18.
Steam Generator "B" radionuclide release rate in pCi/sec = 1.0E-3 x Step 5.18.
Compute and record'on worksheet.
5.20 Is Bypass Valve open? Indicate on worksheet. Bypass Valve will normally be open during a steam dump'unless condenser vacuum has been lost. If Bypass Valve is not open, proceed to Step 5.24. If Bypass i
Valve is open, continue with Step 5.21, 5.21 Obtain Main Steam Isolation Valve position from Control Room Panel
t .
, 5.22 Since both MSIVs are open, steam flowing through Bypass Valve is a mix j
of steam from both Steam Generators. This steam enters condenser and -
I noble gases will exit through condenser air ejector. Radioiodines will become entrained in hotwell and can be ignored. Noble gases release rate will be average of noble gas release rates determined in eiO483-0014a-154-89
._ . . _ . . _ _ _ - _ _ _ _ _ . _ ~ . _ _
PALISADES NUCLEAR PLANT Proc No EI-6.2 EMERGENCY IMPLEMENTATION PROCEDURE Revision 0 Page 5 of 7 TITLE: RELEASE RATE DETERMINATION FROM STEAM LINE MONITORS
- RIA-2323 AND **RIA-2324 FOR STEAM R" LEASES '
TIIROUGli ATMOSPHERIC DL?!P VALVES l
) Steps 5.14 and 5.19 multiplied by 2/3 to account for the flow limits in the bypass valve and by a factor of 1/2 to account for only one i j valve being present. !
Step 5.14 Step 5.19
\
S/G A Noble S/G B Noble i R e e ate pCi sec *
"",[**** "*
R 2
i Record on worksheet.
l
~
5.23 If one MSIV is closed, steam flowing through bypass valve must originate in the Steam Generator not isolated. Noble gases release rate through the condenser air ejector can be determined by multiplying the noble gas release rate from the unisolated Steam Generator as determined in either Step 5.14 or 5.19 by a factor of 2/3 to account for the flow limiter in the bypass valve and by a factor of 1/2 to account for only one valve being present.
Step 5.14 4 Bypass Valve Noble Gas e gas
! Release Rate in pCi/see = 2/3 x 1/2 x /G Release A Rate
) if only S/G A MSIV is open, or Step 5.19 I
= 2/3 x 1/2 x S/G B Noble gas Helease Rate if only S/G B MSIV is open.
Record appropriate result on worksheet as Item 22.
I i
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1
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s
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i eiO483-0014a-154 t_ _ _ . - - _ - . - - - - - - - .-._-- - -
PALISADES NUCLEAR PLANT Proc No EI-6.2 EMERGENCY I!!PLEf!ENTATION PROCEDURE Revision 0 Pa ge 6 o f 7 TITLE: RELEASE RATE DETER 11INATION FR0!! STEXI LINE MONITORS
- RIA 2323 AND **RIA 2324 FOR STEA!! RELEASES THROUGli ATl!OSPHERIC DUt!P VALVES 5.24 Determine the total noble gas release rate by summing the rates calculated in Steps 5.14, 5.19 and 5.22.
QN = Total Noble Gas Release Rato in Ci/sec Step 5.14 Step 5.19 Step 5.22
= S/G A Noble S/G B Noble Bypass Valve Noble Gas Release + Gas Release + Gas Release Rate x 10
-6 Ci Rate Rate pCI Record on worksheet as Item 23. ,
Determine the total radioiodine release rate by summing those calculated in Steps 5.14 and 5.19. '
QI = Total Radiciodine Release Rate in Ci/sec Step 5.14 Step 5.19
= S/G A Radio- + S/G B Radio-iodine Release rate x 10-6 iodine Release Rate Ci pCI Record on worksheet as item 23, 5.25 Repeat Steps 5.1 through 5.24 with the data recorded during the steam dump at 15 second time intervals for the duration of the dump. This step provides a time-dependent record of the radionuclide release rates during the steam sump. -
END OF RELEASE RATE DETER?!INATION 5.26 If Primary Coolant Pumps are off, natural convection circulation has been established. Obtain the Cold Leg Temperatures, T for both SteamGeneratorsfromControlRoomPanel**EC-12orfrombritical Functions Monitor. Choose any of the four channels for each Steam
! Generator and record the readings on worksheet as item 26.
5.27 Assume T old equals the steam temperature. Refer to Table 1
" Properties of Staturated Steam and Saturated Water (Temperature)".
For each T , enter the table in Column 1 and record on Attachment I thecorrespSkdingpressureinpsiafromColumn2. These will be the Steam Generator pressures.
5.28 Enter Attachment 2 with the pressure determined in Step 5.27. Read the Fully Open Dump Valve Saturated Steam Flow Rate in ec/sec correspondi'ng to these pressures. These are flow rates for one fully -
open valve. Record on worksheet.
( eiO483-0014a-154-89 I
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PALISADES NUCLEAR PLANT Proc No EI-6.2 E!!ERGENCY IrlPLE!!ENTATION PROCEDURE Revision 0 Page 7 of 7 TITLE: RELEASE RATE DETER 111 NATION FR0!! STEAN LINE !!0NITORS
- RIA-2323 AND M RIA-2324 FOR STEAtt RELEASES THROUGH ATt!0 SPHERIC DUMP VALVES 5.29 Determine and record on worksheet, the primary coolant average temperature error as defined by:
T avg error - T avg - 532 F T,y was recorded in Step 5.3.
5.30 Use T avg error to determine the fraction the dump valves are open.
If T,y >25 then fraction = 1.0 If T,y <25 then fraction valve is open is determined by:
Fraction valve open = (T rror x 0.04545) - 0.1346 ava Record on worksheet.
5.31 Determine and record on worksheet, the actual steam flow rate from one dump valve by multiplying together the results from Step 5.28 and 5.30 '
for both Steam Generators.
Step 5.28 Step 5.30 S/G A Fully Open Fraction valve = S/G A Actual Steam Flow Rate ec/sec x is open Flow Rate in ec/sec S/G B Fully Open Fraction valve = S/G B Actual Steam Flow Rate ec/sec x is open Flow Rate in ec/sec 5.32 Return to Step 5.10.
NOTE: In Step 5.13, when "the steam flow rate from Step 5.9" is referred to, insert the Steam Generator "A" Actual Steam Flow Rate calculated in Step 5.31.
In Step 5.18, when "the steam flow rate from Step 5.9" is referred to, insert the Steam Generator "B" Actual Steam Flow Rate calculated in Step 5.31.
6.0 ATTACH 11ENTS 6.1 Attachment 1, " Properties of Saturated Steam and Saturated Water (Temperature)"
6.2 Attachment 2, " Steam Pressure vs Dump Valve Flow Rate Graph" eiO483-0014a-154-89
1
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Proc No EI-6.2 Properties of Saturated steam and Saturated Eater (Temperature) % chment 1 Revision 0 Page 1 of 3 R ep. Pres s. Volume, ftlLm Enthalpy, Btu /lbm Er.trepy, Btu lbm , R Temp.
psia Water Evap. Steam Water Evap. Steam n ater Evap. Steam F
- # # b # #
f fs g f is s f fa g 705.47 2244.2 0.05078 0 00000 0 05078 906 0 00 906.0 1.0612 0 0000 1 0612 705.=7 7c5.0 2194.J 0.0==27 0.G120* 0 05720 872 0 61.m 92=.= 1.c229 0 0527 1 0e56 705.0 70s.5 21e?.e 0.0*233 0 01422 0.06055 261 9 45 2 %=7.2 1 022= 0 0722 1 0967 70s.5
- 70. 0 2177 2 0.05108 0 02192 0 06300 e5e.2 102.0 956 2 1 0169 0 0876 1 10 6 704.0 703 5 3166.e 0.0e015 0 02ee9 0 0450e tee.2 115.2 963.5 1 011e 0 0991 1 1109 703 5 702.0 2126 3 0.039e0 0 02754 0 046te te3 2 126.e 969.4 1.0076 0 1047 1 1163 703 0 702 5 31e5 9 0.03874 0 02969 0 06847 828 9 136.1 974.9 1.0029 0 1171 1 1210 702.5 702 0 2135 5 0.0282e 0 03173 0.06997 825 0 !==.7 979.7 1 0006 0 1246 1 8252 702.0 701 5 31s5.2 0 02777 0 02241 0 0713e 231 5 152.6 Ste.0 0.9977 0 121e 1 1291 701.5 70t.0 311e.9 0.03735 0.h3526 0 07271 228 2 159.2 98A.0 0.99st 0 1377 1 1226 701 0 70u.5 3104 6 0 02697 0 03701 0 07297 425 2 166.5 991 7 0.9924 0 1425 1 1259 700.5 70h.0 Jose.J 0.026e2 0.G3t!? 0 07519 e22.e 172 7 995 2 0.9901 0 1490 1 1290 700.0 699 0 3073.9 0 02600 0. bel *9 0 077 9 817 3 104 2 2001.5 0.9858 0 1590 1 1*e7 699.0 694 0 2053.6 0.03546 0.De=20 0 07966 812 6 19e.6 1007.2 G.9818 0 1621 1 1499 694.0 497 0 2033 5 0 03498 0 0*67# 0 04172 ene.* 20=.0 1912.= 0.9783 0 17te 1 1547 697 0 695 0 3013.4 0.03*55 0 04916 0 08371 204 4 212 4 1017.2 0.9749 0 1tet 1 1591 696.0 695 0 2993.5 0.03415 0 05147 0 04563 200 6 221.0 1021 7 0.9718 0 191e 1 1622 695.0 699 0 2973 7 0 03379 0.05370 0 087#9 797 1 228.e 1025.9 0.96e9 0 19t3 1 1671 694.0 693 0 295e.0 0.033e5 0 05587 0 0e931 *793 8 236 1 1029.9 0.9660 0 20ee 1 1708 693.0 692 0 2939.5 0.03313 0 05797 0 09110 790 5 2*3 1 1033 6 0.9634 0 2110 1 1744 692.0 690 0 2095.7 0.02256 0 06203 0 09e59 70s.5 256 1 1040.6 0.9583 0.2227 1 1810 690.0 626.0 28t?.e 0.0320e 0 06595 0 09799 778 8 268 2 1047.0 0.9535 0 2327 1 1872 680.0 483 0 2019.5 0.03157 0 06976 0 10123 773.e 279.5 1052.9 0.9490 0 2429 1 1930 6e6.0 6e4 0 2742 1 0.03114 0 073e9 0 10e63 768 2 290 2 105s.e 0.9447 0 2537 1 1984 6e4.0 682 0 27e5 1 0 03074 0 07716 0 10790 763 3 306.e 1063 6 0.9406 0 2631 1 2036 642 0 480 0 2708 6 0.03037 0 00000 0 11117 758 5 310 1 1968 5 0.9365 0 2720 1 2006 640.0 678 0 2672 5 0.03002 0 0ee40 0 11*e2 753 4 319.4 1073.2 0.9326 0 2407 1 2133 67s.0 676 0 2636 4 0.02970 0 08799 0 11769 749 2 328.5 1077.6 0.9287 0 2892 1 2179 676.0 67e.0 2601 5 0 02939 0 09156 0 12096 744 7 337 2 1081.9 0.9249 0 2974 1 2223 679.0 674 0 25e6 6 0 02911 0 0151m 0 12e2e 740 2 3#5.7 1085 9 0.9212 0 3014 1 2266 672.0 679 0 2532 2 0 0286* 0 09271 0 12755 735 0 35s.0 1089 4 0.917e 0 3123 1 2307 670.0 esp
- 2e94 1 0.02458 0 10229 0 13047 731 5 362 1 1093 5 *0.9137 0 3210 1 22e7 668.0 te 2ete.* 0.02834 0 10524 0 13*21 727 1 370.0 1097.1 0.9100 0.3286 1 2287 466.0 64 2431.1 0.02811 0 109e7 0 13757 722 9 377.7 1100.6 0.9064 0 3341 1 2e25 66e.0 642 0 2398 2 0.027e9 0 11306 0 1eC95 718 4 305 1 1103.9 0.9028 0 2e24 1 2562 662.0 610 0 23e5.7 0.02768 0.11663 0 16#31 714 9 392.1 1807.0 0 8995 0 3502 1 2490 660.0 45s.0 2233 5 0 027ee 0 12023 0 14771 711 1 399 0 1180 1 0.e963 0 3570 1 2533 658.0 654.0 .23^1.7 0.02728 0 12287 0 15115 707.e =05 7 1113.1 0.t931 0 3437 . 1 2557 656.0 654 0 22<0.3 0 02709 0.12754 0 15*63 703 7 412 2 1115.9 0.8899 0 3702 1 2601 654.0 652 0 2239 2 0.02691 0 1312e 0 15816 700 0 418 7 1118 7 0.e460 0 3767 1 2639 652 0 650.0 2208 4 0 02674 0 13e99 0 16173 694.4 e25.0 1121 4 0.es37 0 3820 1 2667 650.0 6*e.0 2178 1 0.02657 0 13476 0 14534 492 9 431 1 1124 0 0 2906 0 3893 1 2699 648.8 6e6 0 21=e.0 0.02641 0 14258 0 16899 489.4 437.2 1826.6 0.e776 0 3954 1 2730 666.0 t44 0 2118.3 0.02625 0 146et 0 17269 685 9 443 1 1129.0 0 8746 0.n015 1 2761 64e.0 442 0 20es.9 0 02610 0 15033 2 17643 662 5 **e.9 1131 4 0 8716 0.4075 1 2791 642 0 -
6t0 0 2059.9 0.02595 0 15=27 0 14021 679 1 'e5*.6 1133 7 0.8606 0.e134 1 2821 640.8 632 0 2031 2 0 025e0 0 1582e 0 1t*05 675 8 460 2 1136.0 0 8657 0.9193 1 2250 638.0 433 0 20u2.e 0.02566 0 16226 0 14792 672 9 e65.7 1134 1 0.462e 0 4251 1 2879 636.e 434 0 197m.7 0 02553 0 16633 0 19105 669 1 471 1 1140 2 0.e599 0.a207 1 2907 634.0 432 0 19=7.0 0.02539 0 17044 0 19503 665 9 476 4 1142 2 0.8571 0.4364 1 2934 632.0 420 0 1919 5 0.02526 0 17e59 0 19986 _ 662 7 481 6 11te.2 0.e542 0.4419 1 2962 630.0 420 0 1892.e 0.02514 0 17400 0 20394 659 5 est.7 1146 1 0 851e 0.447e 1 2948 628.0 (25 0 1965 6 0.02501 0 18206 0 20407 456 3 491.7 11ee.0 0.se86 0.4529 1 3015 626.0 62e.0 1839.0 0.02489 0 18737 0 21226 653 1 496 6 1149.4 0.e454 0.45t3 1 30e1 624.0 t22 0 1812.4 0.02477 0 19173 0 21650 450 0 501 5 1151.5 0.ee30 0 4636 1 3066 622.0 c20 0 1786.9 0.02466 0 19615 0 22001 646 9 506 3 1153 2 0.se03 0.46e9 1 3092 620.0 618 0 1761 2 0.02e55 0 20063 0 22517 6e3.s 511.0 115e.8 0 8375 0.47e2 1 3117 618.0 416 0 1735.9 0.02*ee 0 20516 0 22960 640 4 515 6 1156.= 0 8348 0.e794 1 2141 616.0 614 0 1710.8 0.02433 0 20976 0 22409 637 4 520.2 1158 0 0 8321 0.4445 1 3166 614.0 612 0 1666 1 0.02422 0 21t*2 0 23e65 63e.e 52=.7 1159 5 0.8294 0.ne96 1 3190 612.0 610.0 16et.6 0.02e12 0 21915 0 2e327 631 4 529 2 1860.9 0.e267 0.4941 1 2214 610.e (C9 0 1637 3 0 02*02 0 22294 0 2e796 428 0 533 6 1862 4 0.8240 0.o997 1 323e 600.0 405 0 te13.e 0.02392 0 22881 0 25273 625 9 537.9 1863 8 0.e214 0.50ee 1 2261 606.0 404 0 1589.7 0.023e2 0 23274 0 25757 622 9 542 2 1165 1 0. ele? 0.5097 1 328e 604.0 602 0 !!st.3 0.02373 0 23075 0 242*e 620 0 546 4 1166 4 C.8161 0.*147 1 3307 602.0 400.0 15 3 2 0.0236= 0 242te 0 267t? 417 1 550.6 1167.7 C.e13e - 0.*196 1 3330 600.0 59e.0 1520.e 0.0235e 6 2t900 0 272*! tit.3 55=.7 1169.0 0 41Ce 0.!2e5 1 2253 598.0 591.0 1497.8 0.02345 6 21 25 0 27770 til.= 558.e 1170.2 C.ece2 0.5292 1 2375 596 0 5' 1*?5.e 0.02337 C.2*9*e 0 2829* 400 6 562 4 1171.m C.0056 0.*2=2 1 3299 59*.0 5' !=52 3 0 023Je 9.i6 99 0 28827 605 7 566 0 1172 6 C.8020 0 5390 1 2e20 592.0 ,
590.G !=31 5 0.02319 0 270e9 0 29368 602 9 570 4 1173 7 C.200e 0.8 27 1.: set 590.0 528 0 te10.0 0.02311 0 27400 0 29419 600 1 57*.7 117e.e C.7978 0.5 25 1.*e64 588.0 544 0 12et.6 0.02303 0 28176 6 30*?e 597 3 578 5 1175 9 C.7953 0.!!22 1 2ee5 Set.0 544 0 1267.6 0.022%5 6 28753 0 210*e 596 6 SP2.e 1176.9 C.7927 0.5500 1 2507 See.0 583 6 13 4 7 0 02287 C.292o0 0 31627 591 8 586 1 1170 0 C.7902 0 5e27 1 3520 542 0 540 0 1344.2 0.02279 C.29927 0 22214 589 1 5t9.9 1179.0 C.7t?6 0 5473 1 3550 500.0
. e .
Proc No EI-6.2 Attachment 1 Properties of :..aturated Steam and Saturated Kater (Temp. rature' Revision 0 Page 2 of 3 Enthalpy, Btu ' Ibm Er.tropy. Bru lbm . R T .p.
Ter Press. Volume. ft'/lbm E psia Bater Evap. Steam Water Evan. Steam Lter Evap. 5 tea : F b 3 3 #
I'f g f fg f fg g I'f I'g g 100 0 1326.17 0.0227% 0.29937 0 32214 589 1 589.9 1179.0 0.7876 0 5t73 1 3*t5 Sf0.0 .
0.7851 0.5720 1 3171 57f.0 l 170 0 1305 84 0 02271 9 205ee 0 32416 S84 4 593.6 1179.9
- 183 7 597.2 1180.9 0.7825 0.5766 1 3592 576.0 576 0 1285.74 0.022ee 0 31162 0.33=26 1 3613 57=.0 0 02256 0 31790 0 3e0*4 581 0 600 9 1161 8 0.7800 0 5e13 .
57s.0 1245 09 6.7775 0.S859 1 363 572.0 172 0 12*4 26 0 02249 0 32e29 0 3=678 578 3 60s.S 1182 7 575 6 600 0 1883 6 0 7750 0 5901 1 365 570.0 570 0 .226.48 0.022=2 0 33079 0 35321 564.0 0.02235 0 33tet 0 35975 172 9 611.5 11ee.S 0.7725 0 5950 1 3675 514.0 1207.72 1185 3 0.7699 0.5996 1 3t96 566.0
$66 0 1148.e9 0 0222e 0 3= ele 0 366=2 570 3 615 0 56e.0 0.02221 0 35099 0 37320 567 6 618.5 1186 1 0.767e 0.60=1 1 3714 .
$$e.0 1170.10 0.7650 0 6047 1 3726 562.0 S62 0 1151 43 0.0221e 0 3579? 0 34011 S65 0 621 9 1886 9 562.e 625 3 11e?.7 0.7625 0 6132 1 3757 560.0 160 0 1133 38 0.02207 0 36507 0 38719 0.6177 1 3777 55e.0 S18 0 1115 36 0 02201 0 37230 0 39e31 559 4 628 6 11ee.* 0.7600 632.0 1189 2 0.7575 0 6222 1 3197 S*6.0 553 0 1097.55 0 0219e 0 37966 0.e0160 557 2 S5=.0 0 40903 635.3 1189.9 0.7*50 0 6267 1 3817 e
$$e.0 1079.96 0 021ee 0 02182 0 38715 0 39479 0 41640 554 6 552 0 638.S 1190 4 0.7525 0.4311 1 3837 552.0 j 552 0 1062.59 0.7501 0 6356 1 2856 550 0 f 550 0 10eS e3 0.02176 0.=0256 0.e2*32 S=9 5 641.s 1191.2
- 695 0 1191 9 0.7476 0 6=00 1 3876 See.0 514 0 . 1028.n9 0.02169 0.e10=4 0 43217 $*6 9 566.0 0.32163 0.=1855 0.e e 016 See.e 6ee.1 1192.5 0.7=S1 0 6=*S 1 2e96 S54 0 1011 75 0.7e27 0 6ee9 1 3915 See.0 SD4 0 993 22 0.02157 0 42477 0 4443e 541 4 651 3 1193 1 539 3 1193 7 0.7e02 0 6533 1 3935 S=2.0 St2 0 974.90- 0.02151 0.=3Sle 0.-5665 65*.e 0.e6513 536 4 657 5 1194 3 0.7374 0 6577 1 395= Sec.0
- Ste.0 962.79 0 021=6 0.e4367 0.7353 0 6621 1 3974 538.0
$30 0 9*4.48 0 021*0 0.e5237 0 47377 53e.2 660.6 1194 4 0 44257 531 7 663 6 1195.e 0.7329 0 6665 1 3993 536.0 533 0 931 17 0.0213e 0.e6123 0 670s 1.=012 539.0 534.0 915.64- 0.02129 0.e7024 0.e9155 529 2 666 6 1195 9 0.7204 0 02123 0.e794 7 0 50070 126.e 469 6 1196 4 0.7200 0 6752 1.e032 532.0
- S32 0 900 3e-0 51004 529 3 672 6 1196.9 0.7255 0 6796 1.*051 530.0 S30 0 885 23 0.02110 0 48806 528 0 870.J1 0.02112 0.e9843 0 51955 121 8 675 1 1197 3 0.7231 0.6839 1.*070 524 0 0.7206 0 6803 1 40e9 526.0
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S*S.11 0 01992 0 62958 0.ee950 eSt.9 7en.$ 1204.3 0.6599 0 7956 1.e555 476.0 473 0 0 7199 1.e57e 47e.0 474 0 534.41 0 01900 0.ee632 0 86621 457 3 746.9 1204.4 -0.6575 529 67 0 01984 0.e63*S 0 48329 455 2 749.3 120s.S 0.65S1 0 40e2 1.e192 472.0 472 0 0.0;980 0.65,7 0.00e9 e,0.0
.70.0 Sie.6, 0 00095 0.,0076 452 9 ,$i.6 120s.6 i.etit 509.43 0.01976 0 49445 0 91062 450 7 75m.0 120s.4 0.6502 0.8127 1.e429 e68.0 GC8.0 8.6=78 0 8170 1.o6ea e66 0 466.0 495.12 0 01973 0.91716 0 93609 tee.4 756 3 120s.7 0 01969 0 93548 0 95557 ettet 750 6 120s.7 0 4*54 0 8213 1 4667 e64.0 e63s0 405 56 0 0256 1 4645 462 0 462:0 476.19 0.01965 0 9550e 0 97*69 **3 0 741 0 1204.4 0.6=29 ete.e? 0 01961 0 97m63 0 99e2e **1 5 763 2 1204 0 0.6905 0 8299 1 4704 e60.0 e60.0 eSt.0 (Sese eS7.73 0 01958 0 99547 1 01e25 439 3 765.5 120s.e 0.6341 0.0392 1.e722 0.0195* 1.01518 1 03e72 437 0 767 4 120s.4 0 6356 0 83e5 1 47e1 eS6.0 553 0 **0 73 0.6332 1 4759 45e.0 (53 0 #3%.87 0.01910 1 03616 1 05547 m3e.7 770.0 120s.8 0.eele
=31 19 0 01947 1 05764 1 07711 432 5 772 3 1279.e 0 6304 0.e971 1.e778 452 0 ES2 0 e22 51 0.019*3 1 07962 1 09905 430 2 77e.S 1204.7 0.6283 0.e51e 1 4797 450.0 (10 0 mae.0 ese ele.09 0 01940 1 10212 1 12152 e2e.0 776 7 120m.7 0.6219 0.8517 1 4e15 0.01936 1 12S15 1 1*eS2 e25 7 778 9 120s.6 0 623= 0.e400 1..e3= =e4.0 es =05.76 *=e.0 tes 397 56 0 01933 1 1*e7e 1 16406 e23 5 781.1 120s.6 0 6210 0 86e! 1.e853 ,
0.01929 1 17288 1 19217 e21 3 783 2 120s.S 0 618S 0 8646 1.e472 me2.0 es2 0 389.=9 0.01926 1 19761 1 21647 e19 0 745 4 1204.9 0.6141 0.8729 1 4e90 e=0.0 6te.0 381.Se m!8.0 434.0 373 72 0.01$23 1 22293 1 2=216 ele.e 787.5 120s.3 0.6126 0.e??3 1.mec9 1 2=e87 1 26806 ele.4 7e9.7 120e.2 0 6112 0.e814 1.*926 m36.0 633 0 366.03 0.01919 e3e.0 433 0 358.e6 0 01916 1 2?See 1 29460 ett.e 791.e 120s.1 0 6087 0.ee* 9 1.*9e7 1 32179 410 1 793 9 120e.0 0.6063 0 4503 1.=966 m32.0 4;2 0 251 00 0 01913 1.30264 1.33055 1 3*965 407.9 796 0 1203 9 0 6030 0.e9=6 1. 945 e33.0 430 0 343.47 0.01949
e
- Proc 3h) EI-6.2 Properties of Saturated iteam and daturated Kater (Temp ratures Attachment i Revision 0 Page 3 of 3 Temp. Pres s. Volume, ft2 /lbm Enthalpy, Bru/lbm Entropy. Bru lbm x R Temp.
e psia Water Evap. Steam uater Evan. Steam nater Evap. Steam F
- U V b b 1 te g i ig g 't *ts 's etc.0 3=3 67* 0.01909 1.3206 1.2=94 =07 9 796 0 1202 9 m28 0 326.e63 0.6cte 0.e9e6 1.=945 m30.0 0.01906 1 3591 1.27e2 oc5 7 798.0 1203 7 0.6cle 0 8950 1 500* #28.0 m26 0 229 369 0.01903 1.3884 1.4075 =02 5 80C.1 1202.6 m24 0 322.291 0 5989 0 902e 1 5022 426.0 0 01900 1.e18e 1.e37e *01 2 802 2 1202 5 0.9077 1 50*2 622 0 315.529 0 01897 1.me92 1 4682 0 59t* =2=.0 299 1 40s.2 1202 2 0 59*0 0 9121 1 5061 422.0 620.0 308.780 0 01894 1.4808 1.4997 296 9 806.2 1202 1 302 143 0 5915 0.9165 1 5080 420.0 e18 0 0 01e90 1 5131 1.5220 21e.7 80s.2 1202.9 0 5e90 0.9209 1 5099 416 0 295.617 0 01887 1 5=63 1.5651 41e.0 292 5 810 2 1202.8 0.5866 0.9212 1 5118 416.0
- 14 0 289.201 0.01884 1 5403 1 5991 290 3 812 2 Z202.6 412 0 282 89e 0 5e=1 0.9297 1 5127 ele.0 0 01881 1 6152 1 6340 288 1 81=.2 1202.e 0 5816 0 93*1 1 5157 412.0 e10 0 276 69e 0 01878 1 6510 1.6697 286 0 816 2 1202 1 0 5791 400 0 270 600 0 01875 0.92e1 1 5176 410.0 1 68?? 1.706e 283 8 814 2 1201 9 0.5766 0.9*29 1 5195 408.0
=03 0 26e.611 0 01872 1.7253 1.74*1 281 4 820 1 1201 7 eos.0 258.725 0 01870 0.57*2 0.9=72 1 5215 4Ct.0 1 76e0 1.7827 279.e 822 0 1201 5 0 5717 0.951e 1 5224 404.0 402 0 252.9e2 0 01867 1 8037 1.4223 277 3 82e.0 1201 2 0 5692 0 9*t2 1 525e 402.0 400 0 247.259 0.01864 1 8ete 1.8630 275 1 825.9 1201.0 Ste.0 2=1.677 0.01861 0 5667 0.9607 1 527e 400.0 1 4862 1 90*8 272 9 827.8 1200.7 0 56e2 0.9651 1 5293 398.0 396 0 226 193 0 01858 1 9291 1.9477 270 8 1200.4 394 0 220.807 0.01e55 829.7 0 5617 0 9696 1 5313 396.0 1 9721 1.9917 268 6 831.6 1200 2 0.5592 0.97e1 1 5223 394.0 392.t 225.516 0.01853 2 0184 2.0369 266 5 433 4 1199.9 0 5567 0 97e6 1 5352 392.0 300 220.321 0.01850 2.0649 2.0833 26e.3 835 3 1199.6 388 0 215 220 0.01897 0 55=2 0.9821 1 5372 390.0 2 1126 2.1311 262 2 837 2 1199.3 0 5516 0.9476 1 5392 388.0 38%.0 210.211 0.01844 2 1616 2.1801 260 0 829.0 1199 0 383 0 205 294 0 5491 0.9921 1 5412 386.0 0.01842 2 2120 2.230e 257 9 840.8 1198.7 0 5466 0.9966 382 0 200.=67 0.0183% 2.2634 2.2821 1 5432 284.0 255 7 8*2 7 1198.* 9 5441 1 0012 1 5452 382.0 270 0 195.729 0 01836 2.3170 2.2253 253 6 8==.5 1198.0 370.0 191 0a0 0.01834 0 5e16 1 0057 1 5*73 380.0 2 3716 2.2900 251 4 846 3 1197.7 0.5390 1 0103 1 5*93 378.0 374 0 146 517 0 01831 2 4279 2.e#62 249 3 8e8 1 1197.m 374 0 182 0e0 0 01829 0 5365 1 014e 1 5513 376.0 2 4857 2.5039 2e?.2 849 4 1197.0 0.53e0 1 019e 1 553e 374.0
@'2 0 177.698 0.01826 2 5e51 2.5633 245 0 851 6 1896.7 0 5314 1 0240 1 5554 372 0 370 0 173.339 0 01823 2.6062 2.6244 2e2 9 853 4 1196.3 368.0' 169 113 0.01821 0.52e9 1 02tt 1 5575 370.0 2 6691 2.6872 2e0 8 855 1 1195.9 0.5263 1 0222 1 5595 368 164.964 0 01818 2.7337 2.7519 368.0 238.7 85e.9 1195 6 0 5228 1.027e 1 5616 366.0 34 160.903 0.01816 2.8002 2.818e 226 5 858.6 1195 2
- 36. 156.917 0 01813 2 8687 0 5212 1 0ett 1 5637 364.0 2.8868 234.e 860.4 1194.8 0 5187 1 0e71 1 5658 362 0 360 0 153.010 0.01811 2.9392 2.9573 222 3 862 1 119e.= 0 5161 334 0 1#9.179 0.01809 3.0117 3.0298 1 0517 1 5678 360.0 230 2 863 8 1194.0 0 5125 1 0564 1 5499 358.0 336 0 !=5.e2e 0.01806 3.0863 3.10*e 228 1 465 5 1193.6 35e.0 141.74e 0.01804 0 5110 1 0611 1 5721 359.0 3.1632 3.1812 226 0 867 2 1193 2 0.508e 1 06*P 1 5?a2 332 0 134 138 0 01801 3 2e23 3.2603 223 9 354 0 468.9. 1192 7 0 5058 1 0705 1 5763 352 0 330 0 13*.604 0 01799 3.3238 3.3418 221 8 470.4 1192 3 346 0 131.le2 0 01797 0 5032 1 0752 1 5764 350.0 3.4078 3.e258 219 7 872 2 1891 9 0 5006 1 0799 1 5006 344.0 324 0 127.751 0.01794 3 49=3 3 5122 217 6 873.9 344 0 124.430 0 01792 1191'. a 0.e9e4 1.0e47 1 5827 346 0 3.5834 3.6013 215 5 875 5 1191 0 0.4954 1 0494 1 50e9 342 0 121 177 3 6752 3.6931 213 4 344.0 0 01799 877 2 1190 5 0.4928 1 0942 1 5871 342.0 1 340 8 117.992 0 01787 3 7699 3.7878 211 3 474 4 1190 1 3*8.0 114 873 S.4902 1.0990 1 5e92 340 0 0 01785 3 4675 3.8853 209 2 000.5 1189.6 0.e876 1 1028 335 0 111 820 0 01143 3 9681 3.9859 1 5914 338 0 207 1 802 1 1189.1 0.e480 1 1086 1 5934 336 0 33s.0 108.432 0 01781 m.0718 4.0496 205 0 883.7 1184 7 0.4824 332.0 105.907 0.01779 4 1788 1 1130 1 5958 334 0 4.1964 202 9 885 3 1184 2 9.4794 1 1182 1 5981 332.0 320 0 1G3.0e5 0 01776 ,4 2892 6.3A&$ 200 4 886.9 1187.7 0 4772 328 0 100,2e5 0.0177e 1.1231 1 6003 330.0 4.4030 4.4208\ 294 7 888 5 1187.2' O.e745 1 1200 1 6025 324 0 226.0 97 506 0.01772 e.5205 4.5282 296 6 890 1 1884.7 314.0 9e.826 0.01770 0.4719 1 1329 1 60e4 326.0 4.6418 4.659* 294 6 891 6 1186.2 9.4692 1 1278 1 6071 324.0 322 0 92 205 0 01768 4.7669 4.7846 292 5 893 2 1885.7 0.4666 1.le27 1 6093 322 0 320 0 49.6e3 0 01766 4.4961 4.9134 290.e 89e.8 1185 2 0.46=0 318 0 87 137 0.0176e 1 1477 1 4116 320.0 5 0295 5 0471 288 3 896.3 1884.7 8.4613 1 1526 1 6139 316 0 44.648 0.01761 5 1673 5.1849 310.0 296 3 897.9 11ee.1 0.4586 1 1576 1 6162 316.0 314 0 82 293 0 01759 5 3096 5.3272 284 2 899.4 1883.6 0.e560 212 0 19.953 0.01757 5 4566 161626 1 6185 31e.0 5.4742 282 1 901 0 1883 1 0.4523 1 1676 1 6209 312.0 310 0 77 667 0.01755 5 6085 5.6260 200 0 902 5 !!82 5 308 0 75.433 0.01753 0.e506 1 1726 1 4232 310 0 5 7655 5.7830 278 0 904 0 1182 0 0.e479 1 1776 1 6256 Sc6 0 73 251 0.01751 5 9277 5 9e52 275 9 308.0 905.5 1101 4 0.4653 1 1827 1 6279 324.0 304 0 71 119 0.01749 6.0955 4.1130 273 8 907.0 1880.9 302 0 69.G28 0 017e7 6 2689 4.2864 271 8 904 5 0.ne26 1 1877 1 6303 304.0 1180 3 c.4299 1 1924 1 6327 302.0 300 0 67 005 0 017e5 6 4443 6.=658 264.7 910.0 1179.7 298 0 65.021 0.01743 6.6339 0.4372 . 1.1979 1 6351 300.0 6.6513 267.7 911 5 1179.2 0.=2*5 1 20!! 1 6375 298.0 296 0 62.04* 0.017=1 6 4259 6 8423 26*.6 913 0 1178.6 0.e217 1 2002 29e.4 61 19e 0.01729 7.02e5 1 6400 296.0 7.0=19 gg3 2t3 5 91=.5 1878.0 0.e290 1.2124 1 6e2e 294.0 29 59 250 0.01738 7 2201 7.2e75 261 5 915 9 1177.4 0.*263 1 2184 1 6e49 292.0 "
290.0 57 550 0 01736 7.e=30 7.e60? 259.e 917.4 1176 8 0.n226 218 0 55.795 0 0173= 7.6634 7.6407 1 222e 1 4e73 290.0 2*?.= 918.0 1176.2 0.4208 1 2290 1 6*98 284.0 286 0 *=.082 0 01732 7.8916 7.9c89 255 2 920.3 1175.6 1 22e2 20s.0 52.=1= 0 01720 8.1280 0.elet 1 6523 286.0 8.1452 252 3 921 7 1875.0 0.et!* 1 2295 1 65=8 2en.0 282 0 50.7t6 0.01728 8 3729 8 2902 251 2 922 2 117e.= 0.e126 1 2**e 1 6*7a 282.0 280 0 e9 200 0 01726 4 6267 8.6=39 292 92=.6 1172 4 0.=098 1 2501 1 6899 200.0
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Proc No EI-7.4 Revision 0 Date 5/20/H PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTATION PROCEDURE Revision and Approval Summary i TITLE: POST ACCIDENT GAS AND LIQUID ACTIVITY ANALYSIS i i i
! I
- 1. Prepared 2. QA Concurrence bk _S//C/E,5 4f -_ ,
f-/6 - O l Originato$ Date V /[ j Date 1
- 3. Recommen proval /Q-List h No 4. PRC Reviewed
/ l ^
f//k'b& .:Ib;7th D ar dt Head 'Date ';ug g gf-cp7 / Date l i- 5. Approved 6. ATMS Incorporated M Plant Manager deks Date tb7 /ba/ n
- 7. Biennial Review Date ,
i i i eiO583-0004c154-93 i
PALISADES NUCLEAR PLANT Proc No EI-7.4 EffERGENCY It!PLE!!ENTATION PPOCEDURE R2Vi::icn 0 Page i TITLE: POST ACCIDENT GAS AND LIQUID ACTIVITY ANALYSIS Table of Contents Page 1.0 PURPOSE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I
2.0 REFERENCES
. . . . . . . . . . . . . . . . . . . . . . . . . . . . I 3.0 PREREQUISITES . . . . . . . . . . . . . . . . . . . . . . . . . . 1 4.0 PRECAUTIONS AND LIMITATIONS . . . . . . . . . . . . . . . . . . . 1 5.0 PROCEDURE . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 6.0 ACCEPTANCE CRITERIA . . . . . . . . . . . . . . . . . . . . . . . 3 7.0 RECORDS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 l
l [ 1 l l l eiO583-0004bl54-89
o t . 4
-PALISADES NUCLEAR PLANT Proc No EI-7.4 EMERGENCY IMPLEMENTATION PROCEDURE Revision 0 Page 1 of 4 TITLE: POST ACCIDENT CAS AND LIQUID ACTIVITY ANALYSIS a
1.0 PURPOSE The purpose of this procedure is to outline the steps of operation necessary to analyze samples for gamma activity on the ND6620 counting system during a post accident condition.
2.0 REFERENCES
2.1 ND6600 Data Acquisition and Processing System Operational Instruction Document, Nuclear Data Inc, 1978 2.2 Palisades Nuclear Plant Emergency Implementation Procedure, EI-7.1 2.3 Palisades Nuclear Plant Emergency Implementation Procedure, EI-7.2 2.4 Chemistry Procedure CH-4.40 3.0 PREREQUISITES 3.1 NE6620 acquisition system with associated software. 3.2 Up-to-date calibration of the system. 3.3 One 15 cc gas sample or one 15 cc liquid sample collected from the PASM Panel wrapped in poly sheeting. 3.4 System disc drives on line. 3.5 Line printer on line. 3.6 Tape deck on line. 3.7 Computer display terminal is operational. - i 3.8 Detector high voltage is set at proper voltage. 3.9 Linemans gloves for sample handling. 4.0 PRECAUTIONS AND LIMITATIONS 4.1 If a situation develops in which the disk drives are either automatically (such as during a power failure) or manually taken off line, DO NOT (t) bring them back on line until the " safe light" indicators are on, or else extreme damage could result to the computer. Refer to Procedure F4.40 for bringing the system on line. 4.2 In a power-down situation, always take the disk drive units off line i first, before shutting down the main power. Refer to, procedure F4.40. 4.3 In a problem situation,,do not attempt to bring the system on line (Procedure F4.40) unless you are thoroughly familiar with the ND6620. . It is better to notify the appropriate personnel than to risk damaging the equipment. eiO583-0004a154-89
PALISADES NUCLEAR PLANT droc No EI-7.4 EMERGENCY IMPLEMENTATION PROCEDURE Revision 0 Page 2 of 4 TITLE: POST ACCIDENT GAS AND LIQUID ACTIVITY ANALYSIS 4.4 Linemans gloves shall be worn when handling the sample vials. 4.5 The counting room shoul1 be cleared of all unnecessary sources of radiation while counting is taking place. 5.0 PROCEDURE 5.1 Conduct a "100 second background" analysis. 5.2 Verify that a daily source check count has been taken, to show that the equipment is performing at the calibrated efficiencies / kev. 5.3 To access and execute job streams:
- a. First, make the sample entry in the logbook, noting description, time sampled, volume, etc. -
- b. Use the chart on the wall to determine which job stream user number applies to the sample you want analyzed, and enter that user number in the logbook. For example, if you wanted to count a one liter evaporator distillation sample for 1000 seconds in the low level counting room, you would use " user 12", since the job stream for this user analyzes a one liter liquid sample in a 1000 second acquisition time in the low level counting room. (A different user number would apply in the high level counting room for the same sample, as shown on the chart).
- c. Enter WHO on the keyboard and depress the " return" key. If a user-is signed on, enter BYE UN and depress the " return" key, where "UN" is the user number signed on.
- d. To sign on as the user which applies to ycar sample, you should enter IIELLO UN.A on- the keyboard, where "UN" is the user number you want, and then depress the " return" key. The ",A" is very important, because this is what accesses the job strean. In the above example you would enter HELLO 12,A and then depress the
, " return" key, i i
- c. If the spectrum display screen is showing on the terminal, depress the "page" key located in the display board keys. The display
! screen will get either larger or smaller. If it gets larger, i I depress the "+ " key and release it. Then depress the "page" key again until the display screen completely disappears.
- f. Follow carefully the instructions printed on the screen. Enter the requested information, such as sample identification, time sampled, etc, exactly as instructed, and in the form of the examples as shown_on the screen. It is necessary.to tell the computer the information it needs in the form that it understands.
eiO583-0004al54-89 l
I . PALISADES NUCLEAR PLANT Proc No EI-7.4 EMERGENCY IMPLEMENTATION PROCEDURE Revision 0 Page 3 of 4 TITLE: POST ACCIDENT GAS AND LIQUID ACTIVITY ANALYSIS
- g. Af ter all requested information has been entered, the computer will count, record and print out the analyzed data. If you wish to observe the spectrum during acquisition, again depress the "+ "
key, and then the "page" key to bring the spectrum display back into view. Adjust the size of the spectrum display as you wish.
- h. " Job Stream completed" will appear on the terminal display when the program is finished.
- i. Note the acquisition date and time on the header of the printout.
Enter this into the logbook under the count time. To remove the printout from the line printer, first depress the " select switch" to cause the " select indicator" lamp to go out. This releases the line printer from the computer's control. Then depress the " top of form" button until you have enough paper to tear it at its proper perforation. Then depress the " select switch" again, to return the line printer to computer control. NOTE: It is important to sign off as the user you signed on as, in order to allow the next user to sign on. To sign off, first depress the "CRTL" (control) key on the keyboard. While holding it down, depress the "P" key. This forces the computer to ente'r a " prompt" character on the screen, which is needed in order to sign off. Enter BYE UN, where "UN" is the user number you signed on as, and depress the return key. In the above example, you would sign off by entering BYE 12 and then i depressing the " return" key.
5.4 Calculations
- a. For the Post Accident Gas activity analysis, use the following equation:
Total Gas. Activity, pCi/cc x 8000 cc/gm = Sample gas activity pCi/gm. Record the sample gas activity in pCi/gm on EI 7.2 Attachment 1.
- b. For the post accident liquid activity analysis, use the following equation:
Total Liquid Activity, pCi/ml x 15,000 = Sample Liquid Activity pCi/gm Record the sample liquid activity in pCi/gm on EI 7.2 Attachment 1. 5.5- Label the analysis printout with the analysts initials and the analysis time and date. 6.0 ACCEPTANCE CRITERIA , None eiO583-0004a154-89
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E!!ERGENCY CLASS DESCRIPTION Proc No EI-l Attachment 2 Revision 7 Page 1 of 7 UNUSUAL EVENT State and/or Local Off-Site Class Licensee Actions Authority Actions UNUSUAL EVENT 1. Promptly inform 1. Provide fire- . State and/or local or security Class Description - off-site authori- assistance if ties of nature of requested. Events are in process or have unusual condition occurred which indicate a po- as soon as dis- 2. Escalate to a
' tential degradation of the level covered. more severe of safety of the plant. No class, if releases of radioactive material 2. Augment on-shift appropriate, requiring off-site response or resources as needed.
monitoring are expected unless 3. Stand by un-further degradation of safety 3. Assess and respond. til verbal systems occurs. closeout.
- 4. Escalate to a more Purpose severe class, if appropriate, Purpose of off-site notification is to (1) assure that the first or step in any response later found to be necessary has been carried 5. Close out with ver-out, (2) bring the operating bal summary to off-staff to a state of readiness site authorities; and (3) provide systematic followed by written handling of Unusual Events summary, information and decision making.
e b o e/ 0780-0005c-93 l J
EMERGENCY CLASS DESCRIPTION Proc No EI-I Attachment 2 Revision 7 Page 2 of 7 ALERT State and/or Local Off-Site Class Licensee Actions __ Authority Actions ALERT 1, Promptly inform 1. Provide fire State and/or local or security Class Description authorities of assistance if alert status and requested. Events are in process or have reason for alert as occurred which involve an soon as discovered. 2. Augment re-actual or potential substantial sources and degradation of the level of 2. Augment resources bring primary safety of the plant. Any and activate on- response cen-releases expected to be site Technical Sup- ters and Emerg-limited to small fractions port Center and gency Broadcast of the EPA Protective Action on-site Operational System (EBS) to Guideline exposure levels. Support Center. standby status. Bring Emergency Purpose Operations Facility 3, Alert to (EOF) and other key standby Purpose of off-site alert is emergency personnel status key to (1) assure that emergency to standby status. emergency personnel are readily available personnel in-to respond if situation 3. Assess and respond. cluding moni-becomes more serious or to toring teams perform confirmatory radiation 4. Dispatch on-site and associ-monitoring if required, and monitoring teams ated communi-(2) provide off-site authorities and associated cations. current status information. communications.
- 4. Pravide con-S. Provide periodic firma to ry plant status up- off-site ra-dates to off-site diation moni-authorities (at toring and least every inj es tion 15 minutes). pathway dose p roj ections
- 6. Provide periodic if actual re-meteorological as- leases sub sessments to off- stantially site authorities exceed Tech and, if any nical Speci-releases are occur- fication ring, dose esti- limits.
mates for actual releases. 5. Escalate to a more severe class, if
- 7. Escalate to a more appropriate. .
severe class, if-appropriate. es 0780-0005c-93
,- r
e o EMERGENCY CLASS DESCRIPTION Proc No El-1
' Attachment 2 Revision 7 Page 3 of 7 ALERT State and/or Local Off-Site Class Licensee Actions Authority Actions
- 6. Maintain Alert status
- 8. Close out or rec- until verbal ommend reduction closeout or in emergency class reduction of by verbal summary emergency to off-site author- class, ities followed by written summary.
1 e:0780-0005c-93 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ U
o .. EMERGENCY CLASS DESCRIPTION Proc No EI-1 Attachment 2 Revision 7 Page 4 of 7 SITE AREA EMEEGENCY Class State and/or Local Off-Site Licensee Actions Authority Actions SITE AREA 1. Promptly inform State 1. Provide any assistance EMERGENCY and/or local of f-site requested. authorities of Site Area Class Description Emergency status and 2. If sheltering near the reason for emergency as site is desirabic, acti-Events are in soon as discovered. vate public notification process or have system within at least occurred which 2. Augment resources by ac- two miles of the plant. involve actual or tivating on-site Tech-likely major nical Support Center, 3. Provide public within at failures of plant on-site Operational least about 10 miles functions needed Support Center and near- periodic updates on for protection of site Emergency Opera- emergency status. the public. Any ations Facility (EOF). releases not ex- 4. Augment resources by pected to exceed 3. Assess and respond. activating primary EPA Protective response centers. Action Guideline 4. Dispatch on-site and exposure levels off-site monitoring except near site
- 5. Dispatch key emergency teams and associated personnel including mon-boundary. communications, itoring teams and asso-Purpose ciated communications.
- 5. Designate an individual for plant status updates 6. Alert to standby status Purpose of the '
to off-site authorities other emergency person-Site Area and periodic press nel (eg, those needed Emergency briefings (perhaps declaration is to for evacuation) and joint with off-site . dispatch personnel to (1) assure that authorities). near-site duty stations. response centers are manned, 6. Make senior technical 7. Provide off-site moni-(2) assure that and management staff on toring results to li-monitoring teams site available for con- censee, DOE and others are dispatched, sultation with NRC and and jointly assess them. (3) assure that State on a periodic personnel re- basis. 8. Continuously assess in-quired for formation from licensee evacuation of 7. Provide meteorological and off-site monitoring near-site areas and dose estimates to with regard to changes are at duty sta- off-site authorities for to protective actions tions if situa- actual releases via a already initiated for tion becomes more designated individual or public and mobilizing serious, (4) pro-- automated data trans- evacuation resources. vide consultation mission. ' with off-site 9. Recommend placing milk authorities and 8. Provide release and dose animals within two miles l (5) provide up- projections based on a- on stored feed and dates for the vailable plant condition assess need to extend el0780-0005c-93 l
E!!ERGENCY CLASS DESCRIPTION Proc No EI-I Attachment 2 Revision 7 Page 5 of 7 SITE AREA EMERGENCY State and/or Local Of f-Site 2 Class Licensee Actions Authority Actions public through information and fore- distance. o f f-s i te seeable contingencies, authorities. 10. Provide press briefings,
- 9. Escalate to General perhaps with licensee.
Emergency class, if appropriate, 11. Escalate to General Emergency class, if or appropriate.
- 10. Close out or recommend 12. Maintain Site Area reduction in emergency Emergency status until class by briefing of closecut or reduction off-site authorities at of emergency class.
EOF and by phone fol-lowed by written summary. i I l t l e,; 0780-0005c-93
r - i EMERGENCY CLASS DESCRIPTION Proc No EI-I Attachment 2 Revision 7 Page 6 of 7 GENERAL EMERGENCY State and/or Local Off-Site Class Licensee Actions Authority Actions GENERAL EMERGENCY 1. Promptly inform State 1. Provide any assistance and local off-site requested. Class Description authorities of General Emergency status and 2. Activate immediate pub-Events are in reason for emergency as lic notification of process or have soon as discovered Emergency status and occurred which (parallel notification provide public periodic involve actual or of State / local). updates. imminent substan-tial core degra- 2. Augment resources by ac- 3. Recommend sheltering for dation or melting tivating on-site Tech- two-mile radius and five with potential nical Support Center, miles downwind and as-for loss of con- on-site Operational sess need to extend tainment integ- Support Center and near- distances. Consider ad-rity. Releases site Emergency Opera- visability of evacuation can be reasonably ations Facility (EOF). (projected time avail-expected to ex- able vs estimated evac-ceed EPA Protec- 3. Assess and respond. uation times), tive Action Guideline expo- 4. Dispatch on-site and 4. Augment resources by sure levels off off-site monitoring activating primary site for more teams and associated response centers. than the imme- communications. diate site area. 5. Dispatch key emer'gency
- 5. Designate an individual personnel including mon-Purpose for plant status updates itoring teams and asso-to off-site authorities ciated communications.
Purpose of the and periodic press General Emergency briefings (perhaps 6. Dispatch other emergency declaration is to joint with off site personnel to duty sta-(1) initiate pre- authorities). tions within five-mile determined pro- . radius and alett all tective actions 6. Make senior technical others to standby
- for the public, and management staff on status, i (2) provide site available for con-continuous sultation with NRC and 7. Provide off-site moni-assessment of State on a periodic toring results to li-information from basis. censee, DOE and others licensee and off- and jointly assess them.
site organization 7. Provide meteorological measurements, and dose estimates to 8. Continuorsly assess in-(3) initiate ad- off-site authorities for formation from licensee ditional measures actual releases via a and off-site monitoring-as indicated by designated individual or with regard to changes actual or poten- automated data trans- to protective actions tial releases, mission. already initiated for . (4) provide public and mobilizing consultation with 8. Provide release and dose evacuation resources. ei0780-0005c-93 L-
- o. ~.
E!!ERGENCY CLASS DESCRIPTION Proc No El-1 Attachment 2 Revision 7 Page 7 of 7 GENERAL E!!ERGENCY State and/or Local Off-Site Class Licensee Actions Authority Actions off-site author- projections based on a-ities and vailable plant condition 9. Recommend placing milk (5) provide up- information and fore- animals within 10 miles dates for the seeable contingencies. on stored feed and public through assess need to extend off-site author- 9. Close out or recommend distance. ities. reduction in emergency class by briefing of 10. Provide press briefings off-site authorities at with licensee. EOF and by phone fol-lowed by written summary. 11. ?!aintain General Emer-gency status until closcout or reduction of emergency class. e.i 0780-0005c-93 l}}