ML20063D509
| ML20063D509 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 03/25/1982 |
| From: | CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | |
| Shared Package | |
| ML18047A540 | List: |
| References | |
| PROC-820325-01, NUDOCS 8208270615 | |
| Download: ML20063D509 (202) | |
Text
{{#Wiki_filter:T 3/25/E2 Page 1
. Palisades Nuclear Plant h Emergency Implementation Procedure List of Effective Pages EI-1,
Title:
Activation of Emergency Plan Cover Sheet, Rev. 3 Page 1, Rev. 3 Page 2, Rev. 3 Page 3, Rev. 3 Attachment 1, Page 1, Rev. 3 1 Attachment 1, Page 2, Rev. 3 i Attachment 1, Page 3, Rev. 3 Attachment 1, Page 4, Rev. 3 Attachment 1, Page 5, Rev. 3 Attachment 1, Page 6, Rev. 3 Attachment 1, Page 7, Rev. 3 Attachment 1, Page 8, Rev. 3 Attachment 1, Page 9, Rev. 3 Attachment 1, Page 10, Rev. 3 Attachment 1, Page 11, Rev. 3 Attachment 1, Page 12, Rev. 3 Attachment 1, Page 13, Rev. 3 Attachment 1, Page 14, Rev. 3
,- Attachment 1, Page 15, Rev. 3 1
d Attachment Attachment 1, 1, Page Page 16, 17, Rev. Rev. 3 3 6 Attachment 1, Page 18; Rev. 3 EI-2,
Title:
Palisades Plant Actions / Notifications During An Emergency Cover Sheet, Rev. 3 Page 1, Rev. 3 Attachment 1, Page 1, Rev. 3 Attachment 1, Page 2, Rev. 3 Attachment 1, Page 3, Rev. Attachment 1, Page 4, Rev. 3 Attachment 1, Page 5, Rev. 3 Attachment 1, Page 6, Rev. 3 Attachment 1, Page 7, Rev. 3 Attachment 1, Page 8, Rev. 3 Attachment 1, Page 9, Rev. 3 Attachment 1, Page 10, Rev. 3 Attachment 1, Page 11, Rev. 3 EI-3,
Title:
Communications & Notification Cover Sheet, Rev. 3 h ", ' # ) Page 1, Rev. 3 Page 2, Rev. 3 Page 3, Rev. 3 8208270615 820816 PDR ADOCK 05000255 F pop
1 3/25/92 Pagn ? List of Effective Pages continued for
,-- Eme'rgency Implementation Procedure i L \~ /
EI-3,
Title:
Communications and Notification continued - Attachment 1, Page 1, Rev. 3 Attachment 2, Page 1, Rev. 3 Attachment 3, Page 1, Rev. 3 Attachment 4, Page 1, Rev. 3 Attachment 5, Page 1, Rev. 3 Attachment 5.1, Page 1, Rev. 3 Attachment 6, Page 1, Rev. 3 EI-4.1
Title:
Activation of Technical Support Center Cover Sheet, Rev. 2 Page 1, Rev. 2 Page 2, Rev. 2 Page 3, Rev. 2 Page 4, Rev. 2 Attachment 1, Page 1, Rev. 2 Attachment 2, Page 1, Rev. 2 Attachment 2.1, Page 1, Rev. 2 Attachment 3, Page 1, Rev. 2 Attachment 4, Page 1, Rev. 2 7- EI-4.2,
Title:
Activation of the On-Site Operations Support Center i \
\~ 4< Cover Sheet, Rev. 1 Page 1, Rev.1 and Page 2, Rev.1 Attachment 1, Page 1, Rev. 1 Attachment 1, Page 2, Rev. 1 Attachment 2, Page 1, Rev. 1 Attachment 2.1, Page 1; Rev. 1 Attachment 3, Page 1 Rev. 1 and Page 2, Rev. 1 i
EI-4.3,
Title:
Activation of the Emergency Operation Facility l Cover Sheet, Rev. 2 I Page 1, Rev. 2 and Page 2 Rev. 2 l Attachment 1, Page 1, Rev. 2 l Attachment 2, Page 1, Rev. 2 Attachment 2.1, Page 1, Rev. 2 EI-5,
Title:
Reentrv/ Recovery l Cover Sheet, Rev. 0 l Page 1, Rev. O Page 2, Rev. O Page 3, Rev. O Page 4, Rev. O Page 5, Rev. O Attachment 1, Page 1, Rev. 0 i 7-~z Attachment 2, Page 1, Rev. 0 l l (Q ) l L _)
3/25/82 Paga 3 List of Effective Pages continued for s Eme~rgency Implementation Procedure
) '
EI-6,
Title:
Estimate of Offsite Dose Cover Sheet,~Rev. 8 Page 1, Rev. 8 Page 2, Rev. 8 Page 3, Rev. 8 Attachment 1, Page 1, Rev. 8 Attachment 1, Page 2, Rev. 8 Attachment 1, Page 3, Rev. 8 Attachment 2, Page 1, Rev. 8 Attachment 3, Page 1, Rev. 8 Table 3.1, Page 1, Rev. 8 Attachment 4, Page 1, Rev. 8 Table 4.1, Page 2, Rev. 8 Page 3, Rev 8 Page 4, Rev. 8 Attachment 5, Page 1, Rev. 8 Attachment 6, Page 1, Rev. 8 Figure 1 Figure 2 Figure 3 Figure 4 Figure 5 [ EI-7,
Title:
Post Accident Sampling
- D)N Cover Sheet, Rev. 1 Page 1, Rev. 1 Page 2, Rev. 1 Page 3, Rev. 1 Page 4, Rev. 1 l Page 5, Rev. 1 Attachment 1, Page 1, Rev. 1 Attachment 2, Page 1, Rev. 1 Attachment 3, Page 1, Rev. 1 Attachment 4, Page 1, Rev. 1 EI-8,
Title:
Onsite Radiological Monitoring Cover Sheet, Rev. 3 Page 1, Rev. 3 Page 2, Rev. 3 Page 3, Rev. 3 Page 4, Rev. 3 Attachment 1, Page 1, Rev. 3 Attachment 2, Page 1, Rev. 3 Attachment 3, Page 1, Rev. 3 Attachment 4, Page 1, Rev. 3 EI-9,
Title:
Offsite Radiological Monitoring Cover Sheet, Rev. 2 Page 1, Rev. 2 , Page 2, Rev. 2 Page 3, Rev. 2 ,
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1 3/25/82 Page 4 Lis.t of Effective Pages continued for f( gs Emergency Implementation Procedure EI-9.
Title:
Offsite Radiological Monitoring continued - Page 4, Rev. 2 Attachment 1, Page 1, Rev. 2 Attachment 2, Page 1, Rev. 2 Attachment 3, Page 1, Rev. 2 Attachment 4, Page 1, Rev. 2 EI-10.
Title:
Environmental Assessment Cover Sheet, Rev. 3 Page 1, Rev. 3 Page 2, Rev. 3 Page 3, Rev. 3 Page 4, Rev. 3 Attachment 1, Page 1, Rev. 3 Attachment 1, Page 2, Rev. 3 Attachment 1, Page 3, Rev. 3 Attachment 1, Page 4, Rev. 3 Attachment 1, Page 5, Rev. 3 Attachment 1, Page 6, Rev. 3 Attachment 1, Page 7. Rev. 3 Attachment 2, Page 1, Rev. 3 Attachment 3, Page 1, Rev. 3 O' ' Attachment 4, Page 1, Rev. 3 Attachment 5, Page 1, Rev. 3 Attachment 5, Page 2, Pev. 3 EI-ll.
Title:
Determination of Extent of Core Damage Cover Sheet, Rev. O Page 1 Page 2 Attachment 1, Page 1, Rev. O Attachment 2, Page 1, Rev. O Attachment 3, Page 1, Rev. O Attachment 4, Page 1, Rev. O Attachment 5, Page 1, Rev. O Attachment 6, Page 1, Rev. O EI-12,
Title:
Personnel Accountability Cover Sheet, Rev. 2 Page 1, Rev. 2 Page 2, Rev. 2 Attachment 1, Page 1, Rev. 2
- Attachment 1, Page 2, Rev. 2 Attachment 1, Page 3, Rev. 2 Attachment 1, Page 4, Rev. 2 w4 9
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3/25/82 Page 5 List of Effective Pages continued for Eme'rgency Implementation Procedure O~. EI-12
Title:
Personnel Accountability continued - Attachment 2, Page 1, Rev. 2 EI-13,
Title:
Evacuation, Reassembly Cover Sheet, Rev. 1 Page 1, Rev. 1 Page 2, Rev. 1 Page 3, Rev. 1 Page 4, Rev. 1 Attachment 1, Page 1, Rev. 1 EI-14,
Title:
Radiological Medical Care Cover Sheet, Rev. O Page 1 Page 2 Page 3 EI-15,
Title:
Training and Drills Cover Sheet, Rev. O Page 1 CN
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- Page 2 Page 3 Attac,hment 1, Page 1, Rev. O Attachment 1, Page 2, Rev. O Attachment 2, Page 1, Rev. O Attachment 3, Page 1, Rev. O Attachment 3, Page 2, Rev. O Attachment 3, Page 3, Rev. O Attachment 3, Page 4, Rev. O Attachment 3, Page 5, Rev. O Attachment 3, Page 6, Rev. O Attachment 3, Page 7, Rev. O Attachment 3, Page 8. Rev. O Attachment.3, Page 9, Rev. O Attachment 3, Page 10, Rev. O Attachment 3, Page 11, Rev. O Attachment 3, Page 12, Rev. O Attachment 3, Page 13, Rev. O Attachment 3, Page 14, Rev. O Attachment 3, Page 15, Rev. O Attachment 3, Page 16, Rev. O References Procedure to Emergency Plan Page 1 G["'$ Page 2 Page 3 ,
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3/25/82 ' Page 6
; List of Effective Pages continued for '
I Emergency Implementation Procedure 1 References continued -
! Emergency Plan To Procedures Page 1 i
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i Emergency Implementation Procedures Revision Sheet I , Activation of Emergency Plan, EI-l TITLE: . Revision PRC Date Approved by Gen. Manager 0 10/30/80 'I 1 4/8/81 2 4/30/81 6fz1/ t/ Ohw
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s o EMERGENCY IMPLEMENTATION PROCEDURE EI-I ACTIVATION OF EMERGENCY PL\N Revision 4 1.0 PERSONNEL RESPONSIBILITY
- 1. Activation of the of the Site Emergency Plan is the responsibility of the on-shift Shift Supervisor until relieved by the Site Emergency Director.
4
- 2. The formal line of succession for the Site Emergency Director (SED) is as follows in order of decreasing preference:
t a. General Manager (or Duty and Call Superintendent)
- b. Operations / Maintenance Superintendent (First Alternate) ,
1
- c. Operations Superintendent (Second Alternate)
- d. Technical Superintendent (Third Alternate)
- e. Technical Engineer (Fourth Alternate)
- f. On-shift Shift Supervisor (Fifth Alternate)
') 2.0 PURPOSE To classify those emergency action levels that will necessitate activation of the Emergency Plan and to list actions that may be taken to mitigate the consequences of the emergency.
3.0 ATTACHMENTS AND RECORDS Attachment 1, Classification of Emergency Conditions f 4.0 SPECIAL INSTRUCTIONS The Site Emergency Director will determine, based on reports and conditions, whether to upgrade / downgrade the emergency classification or to secure from the Emergency Plan. 1 5.0 PROCEDURE 5.1 The Shift Supervisor, based on reports from the Operators and the condition of the plant, will make the inital decision to activate the Emergency Plan and will activate the pl,an as follows:
- a. - Determine the classification of the condition, using " key word," " Emergency Action Level' , and " Event" as listed on Attachment 1.
\-- b. Perform the actions, as listed on this procedure and EI-2, necessary to minimize the effects of the emergency on members of the general public. '
ei0780-0005a154 1
Emergency Implementation Procedure EI-1, Rev 4 Activation of Emergency Plan personnel (when radiological conditions exist) exiting the plant during the Site or General Emergency conditions. ( l i i I l l l 1 i I i l l mg 9 ei0780-0005a154 3 Proofread by: d l fd ,
ATTACHMENT I EI-1 Rev 4 s Page 1
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CLASSI-KEY WORD EMERGENCY ACTION LEVEL EVENT FICATION Ala rm Observation All alarm annunciators lost Site Area Annunciators for more than 15 minutes while Emergency plant is not in cold shutdown and transient initiated or in progress. Containment *0bse rvation Loss of containment integrity Unusual Integrity Surveillance test results requiring plant shutdown. Event Detection method dependent Loss of 2 fission product General upon which barriers fail and, barriers with a potential loss Emergency to some extent, upon mecha- of the third barrier (for ex-nism which causes failure. apmle, loss of' core geometry and PCS boundary and a high potential for loss of contain-ment). Engineered Observation Loss of engineered safety Unusual Safeguards Annunciation (Scheme K13, feature requiring plant shut- Event Panel C13). down. Nuclear instrumentation Failure of RPS to initiate ALERT
/i Rod position indication and complete a scram, such \_,(, RPS alarms that the reactor is not made subcritical.
Loss of Auxiliary Feed System Loss of functions needed to ALERT and Shutdown Cooling System attain or maintain cold shut-down (for example loss of Bus Y01). Obse rvation Loss of functions needed for Site Area plant hot shutdown. Emergency Fire
- Annunciators (smoke Any fire requiring outside Unusual detectors) assistance. Event Observation Fire which affects or ALERT threatens to affect safety systems.
A fire incapacitating safety Site Area systems required to achieve Emergency safe shutdown. Fuel Damage Failed fuel monitor (RIA0202) Coolant activity greater than Unusual alarm confirmed by radiochem- 1.0 pCi/ gram dose equivalent Event f',,)\ istry sample analysis. I-131 for more than 72 con-s, m tinuous hours. h4 9 l ei0780-0005bl54
ATTACHMENT 1 EI-1 l Rev 4 1 s g Page 2 1 CLASSI-KEY '40RD EMERGENCY ACTION LEVEL EVENT FICATION Failed fuel monitor (RIA0202) Severe loss of fuel cladding ALERT off scale, confirmed by pri- resulting in 300 pCi/cc equi-mary coolant sample analysis. valent I-131, or 1% failed fuel in 30 minutes or 5% total failed fuel. Stack monitor (RIA2318) reads Any fuel handling accident ALERT 20 times alarm setpoint 5 -with release of radioactivity setpoint of 0.5 MPC for a to containment or fuel hand-period of two or more hours, ling building. and meteorological tower AT is less than positive 2.0. Observation confirmed by pri- Primary coolant pump seizure ALERT mary coolant sample analysis. leading to fuel failure. Subcooled margin monitor in- Degraded core with possible Site Area dicates PCS temperature loss of coolable geometry. Emergency greater than saturation temp-erature. Observation of damage. Major damage to spent fuel in Site Area containment or fuel handling Emergency
,} building. -
High Area radiation monitors, High radiation levels or high ALERT Radiation reading >1000 times back- airborne contamination which Levels ground. indicate a severe degradation in the control of radio-active materials. Man-Made Observation Aircraft crash, train derail- Unusual External ment or explosion onsite which Event Hazards does not damage any safety-re-lated buildings or structures. Observation and measurement Toxic gas release onsite or Unusual by portable instruments close to plant site not Event (onsite). affecting any plant operating personnel. Notification by offsite authorities (offsite releases). Observation Aircraft crash or missile im- ALERT pact on facility which invol-ves a building or structure, but not resulting in inoperable equipment required to achieve safe shutdown. ei0780-0005bl54
ATTACHMENT 1 EI-I Rev 4
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\~/ CLASSI-KEY WORD EMERCENCY ACTION LEVEL EVENT FICATION Observation Explosion which damages ALERT facility, but does not render inoperable equipment needed to achieve safe shutdown.
Observation and measurement Entry of toxic gas into ALERT with portable instruments. facility. Observation Turbine failure which results ALERT Annunciation (for example, in casing penetration. turbine rotor position eccentricity). Observation Aircraft crash, missiles or Site Area explosions severely damaging Emergency safety-related structures. Observation Entry of toxic gas into areas Site Area which are required to be Emergency manned in order to maintain plant in safe configuration.
/ Natural Observation Earthquake Unusual (s_,(sPhenomena Event Observation Seiche(tidal wave). Unusual Event Observation Tornado near site. Unusual Event Observation Sieche (tidal wave) threating ALERT
- Notification by civil to flood plant structures.
l authorities. Observation Tornado striking facility ALERT Observation Seiche (tidal wave) resulting Site Area in incapacitation of equip- Emergency ment needed to achieve or j maintain safe shutdown. Personnel Observation Transportation of contaminated Unusual Hazards Notification from injured's individual to hospital. Event Injuries Supervisor. Various, depending upon Conditions resulting in ALERT hazard (for example, observa- Control Room evacuation. (} (m,/ tion of smoke, radiation area monitors, observation of texic gas). -. eio780-0005bl54 l
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ATTACHMENT 1 El-1 Rev 4
,_s s Page 4 CLASSI-KEY WORD EMERGENCY ACTION LEVEL EVENT FICATION Prima ry Daily PCS leak rate deter- PCS leakage in excess of Unusual Coolant mination Tecccical Specification . Event System (PCS) limits, but <50gpm.
Integrity S/G secondary water activity Primary to secondary leakage Unusual greater than 0.1 pCi/ gram dose in excess of Technical Spe- Event equivalent I-131 cification limits. Containment sump high-level PCS leak rate >50 gpm, but ALERT alarms (LIA 0358, 0359, LS 0358, < capacity of operable 0360), with charging pumps. Mismatch between charging flow (FIA 0202) and letdown flow (FIC 0202). Off-gas monitor (RIA 0631) Steam generator tube rupture ALERT alarm, and reeniting in primary to i Pressurizer low level secondary. leak rate of (LI 0103A). several hundred gpm. Low-low pressurizer level Loss of Coolant accident which Site Area (LIC 0101A)* (Panel C-12), exceeds charging pump capacity. Emergency (} Q Safety injection actuation alarm (Panel C-13). Pressurizer low-pressure alarm (Panel C-12). Containment high-pressure alarm (Panel C-13).
- Pressurizer level may not be a true indication of PCS fluid j inventory.
l Primary *0PPS operation annunciation Any challenge to Over-pressure Unusual Coolant (SV and/or PORV open). Protection System (OPPS). Event System (PCS) Temperature Temperature recorder (TR 0121 Critical operation at PCS Unusual or Pressure or TR 0111). tcmperature <525*F (except for Event physics tests).
- Annunciation (RPS alarms). Reactor high pressure trip. Unusual Event recorder (Initiating event). Event l
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ATTACHMENT 1 EI-1 Rev 4 s Page 5 s CLASSI-KEY WORD EMERGENCY ACTION LEVEL EVENT FICATION Acoustical monicors (FI 1039, Pressurizer code safety oper- Unusual 1040, 1041). ation. Event
-Quench tank high level (LIA 0116).
-Quench tank high pressure (PIA 0116).
-Quench tank high temperature (TIA 0116).
Discharge temperture alarms (TIA 0107, 0108, 0109). Subcooling margin alarm PCS temperature <50*F sub- ALERT cooled; sustained for more
- than 5 minutes or <50*F sub-cooled, and subcooling margin decreasing. Not applicable when plant is in cold shut-down or refueling shutdown condition.
Public Observation Plant shutdown under uncon- Unusual Interest Instrumentation (for example, trolled conditions (for ex- Event (~'N Notifica- (TR 0111, TR 0121). ample, exceeding cooldown ( ,,) tions limits). Observation Any plant shutdown required Unusual by a Technical Specifications Event LCO. Releases Stack monitor (RIA 2318) Short term radiological Unusual reaches alarm setpoint for effluent Technical Specifica- Event two or more hours. Confirmed tions exceeded. by lab sample analysis. Liquid waste discharge mon-itor (RIA 1049) reaches alarm setpoint and automatic dis-charge trip function fails. Confirmed by lab sample analysis. 3 Observation confirmed by sur- Significant solid or liquid Unusual vey results. waste spill outside restricted Event areas with threatened offsite release. D 9 eio780-0005bl54 n-,w,-
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ATTACHMENT 1 EI-1 Rev 4 s Page 6 V CLASSI-
\ KEY WORD EMERGENCY ACTION LEVEL EVENT FICATION Stack monitor (RIA 2318) Radiological effluents greater ALERT reaches 10 times the alarm than 10 times Technical Speci-setpoint for 2 or more hours. fication limits (an instanta-Confirmed by lab sample neous rate which, if continued analysis. over two hours, would result in a dose of approximately 1 mR at the site boundary under Liquid waste discharge mon- average meteorological itor (RIA 1049) reaches 10 conditions).
times alarm setpoint and auto-matic discharge trip function fails. Confirmed by lab sample analysis. Stack monitor reached 850 Effluent monitors detect Site Area times the alarm setpoint levels corresponding to Emergency (RIA 2318) for 1/2 hour or > 50R/h for 1/2 hour or >500 more. Confirmed by sample mR/h whole body for 2 minutes analysis. Meteorological is (or five times these levels adverse when AT is 1.5*C or to the child thyroid) at the greater. site boundary for adverse mete-orological conditions. Q Accident Assessment Projection of above dose rates Site Area based on appropriate para- Emergency meters (for example, contain-ment building radiation level with containment leak rate appropriate for existing con-tainment pressure). Monitoring teams with survey Measurement of above dose Site Area in' truments rated in environs. Emergency
- Stack monitor reads 50 times Effluent monitors detect General alarm setpoint (RIA 2318) and levels corresponding to 0.5 Emergency the meteorological tower AT is R/2 h, or 5 R/30 days, 250 mR/h
> positive 4.0 or using Emer- for 2 hours or 7 mR/hr 30 days gency Implementation Procedure. to the wholebody at the site The high-range stack raonitor boundary under actual meteor-reads 1.3 mR/hr and the meteor- ological conditions.
ological tower AT is >4.0 or 170 mR/h and the meteorological tower AT is >0. }p.- eio780-0005bl54
ATTACHMENT 1 EI-1 Rev 4 s Page 7 \~-' CLASSI-
' KEY WORD EMERGENCY ACTION LEVEL EVENT FICATION Accident assessment proc- A dose rate of 1 R/h to the General dures. wholebody at the site boundary Emergency projected from radiation levels in containment combined with leak rate appropriate for the existing containmeut .
pressure. Survey teams. 1 R/h measured at the site General bounda ry. Emergency Safety
- Annunciation (SI initiated; Cafety injection Unusual Injection Ckt 1, Ckt 2) . Event System (SIS)
Secondary Low steam generator pressure Rapid depressurization of Unusual Side alarm secondary side. Event Obse rva tion. Steam line break with secondary ALERT Steam generator pressure system activity >0.1 pCi/gm. instruments.
- SIS actuation alarm.
s, Feedwater flow / steam flow instruments. S/G activity determined by analysis (radiochemistry). Off-gas monitor (RIA 0681) Steam generator tube rupture ALERT alarm and pressurizer low with loss of offsite power. level (LI 0103A), and Switchyard noncritical alarms or startup transformer trouble alarm or automatic start of emergency D/G. Safety injection actuation Steam line break with >50 gpm Site Area alarms. primary to secondary leakage Emergency Steam generator pressure and secondary system activity indicators. 2.1 pCi/gm dose equivalent Feedwater flow and steam flow I-131. instruments. Activity determined by analysis. be v -. f ei0780-0005bl54
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F ATTACHMENT 1 EI-1 Rev 4 s Page 8 CLASSI-KEY WORD EMERGENCY ACTION LEVEL EVENT FICATION I Security Activation of Security Plan. Security threat or attempted Unusual Observation entry or attempted sabotage. Event
- Activation of Security Plan Ongoing security compromise. ALERT and notification by Security (For example, discovery of of ongoing security compromise. bomb inside fence perimeter, evidence of forced entry into the protected area or a vital area.)
Observation Imminent loss of physical Site Area Security alarms. - control of the facility. Emergency Activation of Security Plan Loss of physical control of General and loss of capability to shut- facility. Emergency down plant. Radioactive Release of radioactive ALERT Offsite material.to the environs. Spent Fuel Possible exposure to offsite and/or Resin personnel. Shipping Cask Incident ( Station Annunciation switchyard non- Loss of all offsite power and Unusual-Power critical alarms, or startup PCS temperature >325*F. ' Event , transformer trouble alarm, or ; Automatic start of emergency D/G.
- . Loss of both emergency D/G Loss of all onsite a-c sources Unusual and PCS temperature >325*F. Event l D-C lighting energized. Loss of all offsite power and ALERT Bus voltage indication. all onsite a-c power sources
- Alarms on all bus sections. (natural circulation main-
- Loss of both emergency D/G. tained).
Loss of annunciator panels. Loss of all d-c power. ALERT Obse rva tion. Loss of all alarm annunciators ALERT for more than 15 minutes. Voltage and current indi- Loss of all a-c power sources, Site Area cators. and loss of both station Emergency Loss of both emergency D/G. batteries for more than 15 minutes, and PCS and. plant not in cold shutdown or refueling
\ shutdown.
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ATTACHMENT 1 EI-1 Rev 4 Page 9 Im\
\ss/ CLASSI-KEY WORD EMERGENCY ACTION LEVEL EVENT FICATION Other *As determined by Site Emer- Plant conditions exist that Site Area Hazards gency Director. warrant activation of emergency Emergency facilities, deployment of radiation monitoring teams and precautionary public notification.
*0bse rvation Evacuation of Control Room and Site Area control of shutdown systems Emergency not established from local stations in 15 minutes.
Control Room instrumentation. Other plant conditions which General make release of large amounts Emergency of radioactivity in a short-time interval possible (for example, any core melt condition). e i I I i l l l l i A ( x_/ l - l ei0780-0005bl54 I
l ATTACHMENT 1 EI-1 Rev 4 x Page 10 i 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. closecut.
- 4. Escalate to a more Purpose severe class, if appropriate, Q- 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-i staff to a state of readiness site authorities; and (3) provide systematic followed by written
{ handling of Unusual Events summa ry, information and decision making. l l l l ( r i l t
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ATTACHMENT 1 EI-1 Rev 4 f'~ Page 11 N)' ALERT State and/or Local Off-Site Class Licensee Actions Authority Actions ALERT 1. Promptly inform 1. Provide fire State and/or Jocal 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. Provide con-
- 5. Provide periodic firmato ry plant status up- off-site ra-dates to off-site diation moni-authorities (at toring and least every injestion 15 minutes). pathway dose projections
- 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 i releases. 5. Escalate to a more severe a g b
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l ATTACHME.VT 1 EI-1 Rev 4 Page 12.
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ALERT s State and/or Local Off-Site Class Licensee Actions AuthorityActions( _ class, if_ !' 7. Escalate to a more appropriate. j severe class, if appropriate. 6. Maintain
, Alert status 1
- 8. Close out or rec- _until verbal ommend reduction closecut or in emergency. class reduction of by verbal, summary emergency
- to off-site author- class.
ities followed by written summary. 4 i i l f
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ATTACHMENT 1 EI-1 Rev 4 Page 13 SITE AREA EMERGENCY State and/or Local Off-Site Class Licensee Actions Authority Actions SITE AREA 1. Promptly inform State 1. Provide any assistance EMERGENCY and/or local off-site requested. authorities of Site Area Class Description Emergency status and. 2. If sheltering near the reason for emergency as site is desirable, 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 5. Dispatch key emergency (N except near site teams and associated personnel including mon-(,,[ boundary. communications. itoring teams and asso-ciated communications. Purpose 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 for evacuation) and declaration is to 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 O .. 9 eio780-0005h154
ATTACHMENT 1 EI-1 Rev 4 Page 14 t V
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SITE AREA EMERGENCY State and/or Local Off-Site Class Licensee Actions Authority Actions 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 (5) provide up- projections based on a- on stored feed and dates for the vailable plant condition assess need to extend public through information and fore- distance. off-site 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. f\ N y[
- 10. Close out or recommend reduction in emergency
- 12. Maintain Site Area Emergency status until class by briefing of closeout or reduction off-site authorities at of emergency class.
EOF and by phone fol-lowed by written summary. i l l V) -. ei0780-0005bl54
ATTACHMENT 1 ! EI-1 Rev 4 s Page 15 ('_s\
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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 evacuat on can be reasonably ations Facility (E0F). (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 emergency
- 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 alert all tective actions 6. Make senior technical others to standby for the public, and management staff on status. (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. Continuously 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 N) -
ei0780-0005bl54
ATTACHMENT 1-EI-1 Rev 4 Page 16 GENERAL EMERGENCY State and/or Local Off-Site Class Licensee Actions Authority Actions 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. 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. Maintain General Emer-gency status until closeout or reduction of emergency class. Q
%4 9
ei0780-0005bl54
ATTACHMENT 1 EI-1 Rev 4 s
,,, Page 17 (v)
FSAR ACCIDENTS AND EMERGENCY CLASSIFICATIONS The accidents listed below are discussed in detail in Section 14 of the Palisades Plant Final Safety Analysis Report (FSAR). U.mergency Accident Consequences Classification Radioactive Liquid Spill 1. Contamination of area, per- Unusual Event On Site sonnel or equipment.
- 2. Spread of contamination.
Steam Line Rupture 1. No fuel damage. Alert Incident 2. Slight, if any, release of radioactivity off site. Loss of Coolant Accident 1. Possible fuel damage. Alert Greater Than 133 Gpm 2. Possible fission product (Charging Pump Capacity) release.
- 3. Slight, if any, release of radioactivity off site.
Loss of Coolant Accident 1. Fuel damage resulting in Site Area (4-Inch to 43-Inch Break) small fission product re-(}( y, lease.
- 2. Slight, if any, release of radioactivity off site.
Waste Gas Incident 1. Uncontrolled release of Site Area radioactivity to the atmos-phere.
- 2. Maximum site boundary dose 0.500 rem whole body.
Fuel Handling Incident 1. Damage to fuel bundle. Site Area
- 2. Maximum off-site doses less than 0.500 rem whole body.
Steam Generator Tube 1. Radioactivity is released in Site Area Rupture Incident small amounts from steam l dump valves and air ejector discharge.
- 2. Maximum site boundar:r dose 0.500 rem whole body.
MHA (Maximum Hypothetical 1. Release of core fission General Accident) (Major Loss of products. Coolant Accident, 42-Inch 2. Two-hour doses at the site Break) boundary of up to 282 rem
/N thyroid, 2 rem whole body.
( ) w/ ei0780-0005bl54
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ATTACHMENT 1 EI-1 Rev 4
'- Page 18 FSAR ACCIDENTS AND EMERGENCY CLASSIFICATIONS Emergency Accident Consequences Classification Waste Liquid Accident 1. Uncontrolled release of Unusual Event liquid waste to the lake in excess of 10 CFR 20 limits.
- 2. No measurable effect on the nearest water supply intakes (South Haven).
Radioactive Off-Site 1. Release of radioactive Alert Spills - Spent Fuel and/ material to the environs.
! or Resin Shipping Cask 2. Possible exposure to off-site
! Incident personnel. ! Turbine Generator 1. No off-site consequences. ' Alert Overspeed Incident w/ Casing Penetration Control Room Fire 1. No off-site consequences. Unusual Event / Alert ! g Acts of Nature 1. Flooding, tornado, etc. Unusual Event /
.1 Alert Civil Disturbances 1. Possible loss of physical Unusual Event /
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Emergency Implementation Procedures Revision Sheet Palisades Plant Actions / Notifications During an Emergency, EI-2 Revision PRC Date Approved by Gen. Manager 0 10/30/80 85 N80 1 12/5/80 i s/o&[(o 2 10/8/81 hk OCT 3 01981 3 11/5/81 NOV 3 0 1981 o ( 4/5/82 4-gg APR 151982 5 5/12/82 l I
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,. Rev 3, 10/80 TEMPORARY CHANGE 'IO A PROCEDURE Change No. EI'-92 -0 73 Change Date Q27-72 Expiration Date /D -3 7 -7.2 Procedure Type Er Procedure No. 2 Rev No./Date de/ 7 Prccedure Title B /.'s<e/cr P/am4 Aed'~> /Aso Ad'ea /'i n Paragraph No. Figure / Table No. Other ATMS No. -
Synopsis (Concise reason for this change) E_T' z- vr u.c / 4o re,w han d ,'. a //~ a AS/ auavmen-AJ.% C nsr3 flu M ha $7t C ktfo a +ha Ae.4,'a n sewJ: , y Emeg.m Brandan As,.n.ar / un Had . Change: o [! [I- O r a (( c2 / Should change be made permanent? Yes No THE ABOVE DOESYOT CFANGE I:iTE'iT OF ORIGINAL PROCEDURE NO , h Approved
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s Q EMERGENCY IMPLEMENTATION PROCEDURE EI-2 Q PALISADES PLANT ACTIONS / NOTIFICATIONS DURING AN EMERGENCY Rev 5 1.0 PERSONNEL RESPONSIBILITY The Site Emergency Director is responsible for determining actions to be taken during an emergency at Palisades Plant. 2.0 PURPOSE To provide the Site Emergency Director with a prepared course of action for each classification of emergency condition. 3.0 ATTACHMENTS AND RECORDS
- 1. Attachment 1, Immediate Facility Action / Notification Checklist
- 2. Attachment 2, Subsequent Facility Action / Notification Checklist 4.0 SPECIAL INSTRUCTIONS
- 1. Definitions:
- a. Immediate Actions - actions performed within one hour.
fs These actions are primarily notifications.
- b. Subsequent Actions - actions performed in an expeditious manner depending on the emergency.
- c. If Necessary Actions - actions that are not required, but could possibly be needed.
5.0 - PROCUDURE 5.1 Use the emergency classification obtained in EI-1, (ie, Unusual Event, Alert, Site Area Emergency, or General Emergency) to identify Mandatory / Subsequent /If Needed, Actions on Attachment 1. 5.2 Indicate the actions to be taken in the left column of Attachment 2. Use an 'M' to indicate a Mandatory Action, use an 'S' to indicate a Subsequent Action and an 'I' to indicate an If Needed Action. 5.3 Date Attachment 2. 5.4 As the specific action is performed, the following are recorded on Attachment 2.
- 1. Time action was initiated.
- 2. Person performing the action.
f) 3. Any comments pertinent to the action. v
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I i f El-2 ' Al.ERT ATTACPMENT 1 R-v $ Page 4 j O El:Y WORD EVENT DETECTION MANDATORY / SUBSEQUENT, IF i
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NEEDED, ACTIONS Engineered Failure of RPS to initiate and complete a Nuclear instrumentation. mndatory: 1. 2. 3. 5.10 .1 H , (. + 5 scram, such that the reactor is not made Rod position indication. 19,20,22.24,27,32 . Safeguards Systems suberitical. RPS alarms. ' Subsequent: 38,39 4d 11 Needed: 31 y I.oss of functions needed to attain or maintain Annur.ciators (various depending on f unction which is ;Q,f..
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Ai.nunciators (smoke detectors). Mandatory: 1,2,3,5,6,10,IM, l' . . . ! Fire Fire which af f ects ur threatens to af fect 19,20,22,24,27,10.32 safety systems. Observatfun. Subsequent: 38,39 [J*i$ ;J j , If Needed: 31,34,17 '*,,*]y . [ Refer to Fire Protection . Implementing Procedures, dg^ g', ; Sections I and 2. .. A
?qy f Security On-going security compromise, eg, discovery of observation [, I ,
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torced entry into the protected area or a Refer to Sa l e >.na r d s tontto>en-vital area, ty Pr wedurea, Bomb luside fence - Section 2, Forced l Entry - Sections t) & 10 o' < <>""- O "*"i nomena s i<'e <<>a i plant structures.
> <'< < >== ce rie-a Notification by civil authorities.
-"a <erv: i 2 3.s io ie i" 20,22,24,27 Subsequent: 38,39 Tornado striking facility. Observation if Needed: 14,15.31,32 Nu-Made Aircraft crash or missile impact on faca?lty Observation. Mandatory: 1,2,3,5,1Q1F 19 which involves a building or structure, but 20,22.24,27,32 Eu er nal Subsequent: 38,39 t, e Itazards not resulting in inoperable equipment required if Needed: 9,14,15,1h ,.
to schieve safe shutdown, Explosion which damages facil1*y, but does Observation Refer to Safeguards Contingen- ',)
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e Attachment 2 Emerge Action Check 1ist 5 Action Telephone No./ Time Person Type Action Reference Action Perform q (M.S,orI) Init. Action . . . . _
- l. Notify Duty and Call Superintendent Duty Call List
- 2. Power Controller (for CO respone) Note: Red Telephone or '
perform notification #4 once General Office 517-788-0990 Control Center is notified.
- 3. Nuclear Regulatory Commission 1. Direct Line (red l (listed in order of decreasing preference) telephone)
- 2. 301-492-8111 Bethesda Op. Ctr.
- 3. 301-427-4056 Silver Springs
- 4. Ilealth Physics Network Phone
*22 (touch tone) 22 (dial phone)
- 5. 301-492-7000 Bethesda Central Office
- 4. General Office Controi Center / Temporary 82-87001 Emergency Operations Facility, _ _ __ ___. __ _ __ _ _ _ _ _ _ _ _ _ . ,
- 5. Ven Buren County Sheriff Dedicated telephone or 616-657-3101
- 6. Berrien County Sheriff 616--983-7141 . _ . _ _ _ . _ . _ _ . . _ _ _ _ _ _ . _ _
- 7. Allegan County Sheriff 616-673-5441
- 8. Covert Fire Dept. & Ambulance Service 616-764-1313
- 9. Ilospitals:
Mercy llospital 616-927-5241 or 5242 South llaven Community llospital 616-637-5271
- 10. Michigan State Police:
South llaven Post (initial notifications) Dedicated telephone g or 616-637-2125 or i radio in Security , [
2
- 1. Attachment 2 Emergent : tion Checklist 5 e'i Action Telephone No./ Time Person Tgpe Action Reference Action Perfccm
.(Mit s off) . _ _ _ .
Init.. ._ Actiop__ Comments
- 11. Michigan Department of Public IIcalth 517-373-1578 (day) 517-373-0800 (night)'
Saugatuck-on-Scene E.O.C. 616-335-2020 , I
- 12. U.S. Coast Guard; St. . Joseph 616-983-1371
, Maskgeon 616-759-0951
- 13. South llaven Water Department 616-637-5211 (day) 616-637-5151 (night)
- 14. Palisades Park Manager 616-764-8272
- 15. Van Buren State Park Manager 616-637-2788
- 16. Federal Aviation Administration 616-637-8075 South Bend, IN
- 17. Chemistry /llealth Physics Superintendent (call list)
. __. . . _ . . _ . . _ _ ._. . . _ _ . . ._ . _ . ~ . . _ _ . ._
- 18. Property Protection Supervisor Day: (Call list)
Night: this function is performed by the Shift Supervisor, at site area emergency contact Prop Prot Supv, at home.
- 19. Establish Technical Support Center (TSC)
EI-4.1
- 20. Establish Operations Support Center (OSC) EI-4.2
- 21. Establish Emergency Operations Facility (EOF) EI-4.3
- 22. Initiate on-site monitoring EI-8
- 23. Initiate off-site monitoring EI-9
Attachment 2 Emergency n Checklist 5 Page 3 Action Telephone No./ Time Person
. Type Reference Action Performing LM,S,orI)
Actior. Comments _ _ _ _ _ _ Init. Action
- 24. Provide 15-minute updates to #'s 2, 5, 10 and 21 (if established) above.
EI-3 t
- 25. Provide dose estimates EI-6 j
- 26. Perform laboratory analysis of effluents
- 27. Meteorological data-obtain 6 analyze EI-6 l
- 28. Provide release and dose projections El-10 l
- 29. Activate stand-by generators
- 30. Initiate Fire Protection Plan Fire Protection l Implementing Proc. j
- 31. Initiate alternate SCRAM procedures.
,1
- 32. Perform personnel assembly and accounta- f bility EI-12 j
- 33. Evacuate non-critical personnel
-. s . - - - . . ..
- 34. Initiate re-entry / recovery EI-5
- 35. Perform plant call-back j
- 36. Ambulance service (advanced life support? EI-14 MEDIC 1 Ambulance, St. Joseph 925-2141 South llaven Ambulance Service 8 637-3305 l .- -- . _ _ _ _ .
I
- 37. Establish Joint Public Information Center ,
- 38. Notify Plant Public Affairs Director Day: (Call List)
! i f
- 39. Initiate Event Report Admin Procedures No. 3.5.5.2 i l
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l Emergency Implementation Procedures Revision Sheet v . TITLE: Communications and Notification, EI-3 Revision PRC Date Approved by Gen. Manager 0 11/19/80 1 4/8/81 5l14lTrt 7/8/81 2 7!LP[fri 3 2/21/81 9 ( % ,g,y ,
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x EMERGENCY IMPLEMENTATION PROCEDURE EI-3 xm ,/ COMMUNICATIONS AND NOTIFICATION b Rev 3 1.0 PERSONNEL RESPONSIBILITY
- 1. Site Emergency Director Perform / assure immediate notifications per EI-2.
- 2. Technical Engineer Responsible for coordinating Technical Support Center communications to State and local authorities, including periodic updates. Responsible for communications to outside support agencies for assistance (ambulance service, hospital, fire company, etc).
- 3. Control Center Director (General Office)
- a. Notification and coordination between plant and corporate management.
- b. As requested, perform outside agency duplicate notification.
2.0 PURPOSE i
- 1. To describe the communications equipment available for use during an emergency.
- 2. To describe the notifications required in case of an emergency.
3.0 ATTACHMENTS AND RECORDS
- 1. Attachment 1 -
Notification Format
- 2. Attachment 2 - Notification of Hospitals
- 3. Attachment 3 - Offsite Emergency Call List
- 4. attachment 4 - General Office Control Center Notifications
- 5. Attachment 5 - Methods of Communication i
- 6. Attachment 5.1 - Key to Attachment 5
- 7. Attachment 6 - Agency Update Logsheet 4.0 SPECIAL INSTRUCTIONS To assure accuracy, all messages to an off-site agency should be repeated back to the caller, and all messages from an off-site agency
('"')s N, should be repeated back by the caller. pa1180-0007a-89 '
,, ~. - , - , . . - - - . , , . - -
- 4- +., - , , _,,----..,-r -.,
1 Emergsacy Implementation Procedure EI-3, Rev 3 Communications and Notification s Q 5.4.8 Actual or projected dose rates at site boundary and the integrated dose at the site boundary (EI-9)(EI-6). 5.4.9 Projected dose rates and integrated dose about 2, 5 and 10 miles from the site and the sectors affected (EI-6). 5.4.10 Estimate of surface contamination (EI-9). 5.4.11 Actions presently underway. 5.4.12 Actions planned. 5.4.13 Any request for offsite support. 5.4.14 Prognosis for worsening or termination of event. 5.5 TECHNICAL SUPPORT CENTER COMMUNICATIONS 5.5.1 Telephone and face-to-face with Control Room. 5.5.2 Telephone to Security. 5.5.3 Telephone to Operations Support Center. 5.5.4 Direct telephone line to NRC. 5.5.5 Telephone lines to outside agencies. 5.5.6 Company and State Police radios. 5.5.7 Dedicated telephone and radio to Jackson Control Center. 5.6 OPERATIONAL SUPPORT CENTER COMMUNICATIONS 5.6.1 Dedicated intercom to Technical Support Center. 5.6.2 Intraplant telephone system. 5.6.3 Portable radios on company frequency. O pa1180-0007a-89 '
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- EI-3 i Rev 3 s Page 1 O'
ATTACHMENT 1 NOTIFICATION 0F 0FFSITE AGENCIES To inform offsite agencies of an emergency condition the following messages should be transmitted:
"This is the Control Room of the Palisades Nuclear Plant. This telephone call is to notify you of a (unusual e tent, alert, site emergency, general emergency) condition".
"The conditions are as follows:"
(A description of dose predictions, plume exposure pathways, type of release.)
- "The following protective actions are recommended:"
, To assure accuracy, the person receiving the message should repeat it back to the caller. i l l O pa1180-0007b-89 ' l
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- Rev 3 s Page 1
% ATTACHMENT 2 NOTIFICATION OF HOSPITALS
- To inform the agreement. hospital (s) that they .will be receiving contaminated victims, the Hospital's Emergency Department should be contacted and given the j following information:
- 1. The number of victims, the mode of transportation, and the estimated time of arrival (eta) at the hospital.
,! 2. The extent of injuries. t l 4
- 3. Any first aid and/or decontamination procedures instituted.
! 4. The ~ general and specific areas and levels of contamination. 1 i I i i l 1 l l l . 1. pa1180-0007c-89 ' 1 e- ----m-n.,--n--,- . - n-e- ,, - - -- ,-- ,,,----,-,.r---~v,+,. ~ , _ . , , , - - , _ - - - - - . , , , . . --~.n n
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1 EI-3 Rev 3 I Page 1 ATTACHMENT 3 0FFSITE EMERGENCY CALL LIST Energy Research and Development Administration Argonne, Illinois 312-972-2000 Nuclear Regulatory Commission, III Direct telephone or Glen Ellyn, Illinois 312-932-2500 US Coast Guard Station St Joseph 616-983-1371 Muskegon 616-759-0951 1 COVERT FIRE DEPARTMENT 764-1768 Michigan State Police, South Haven 637-2125 Van Buren County Sheriff, Paw Paw 657-3101 Berrien County Sheriff, St Joseph 983-7141 South Haven Ambulance Service 637-3106 Medic 1 Community Emergency Service, Benton Harbor 925-2141 Memorial Hospital, St Joseph 983-8300 Mercy Hospital, Benton Harbor 927-5100 South Haven Community Hospital 637-5271 Dale K Morgan, MD, South Haven 637-3609 David B Witte, MD, South Haven 637-3528 Manager Palisades Park 764-8272 Van Buren State Park Manager 637-2788 City of South Haven 637-5211 or Board of Public Utilities 637-5151 (night) pa1180-0007d-89 ' )
. . ~ . .
- __ . __ - . _ _ _ _ _ _ _ . = _ _ _ _ .. . _ _ . -
i EI-3 ) Rev 3 i s Page 1
-ATTACHMENT 4 9
GENERAL OFFICE CONTROL CENTER NOTIFICATIONS r US Nuclear Regulatory Commission 312-932-2500
- Glen Ellyn, Illinois
! Michigan State Water Resources Commission 517-373-7660 1 Michigan State Police, Emergency Services 517-373-0617 ,i Division, Lansing American Nuclear Insurers 203-677-7305 (D)
- 203-677-7715 (N)-
Nuclear Mutual Limited Insurance 809-295-3278 j Department of Energy, Radiological 312-972-2000 Assistance Program L [ i l t i 1 I l
- r l ;
i i l l l' pa1180-0007e-89 - l l
EI-3 Rev 3 s Page 1 O ATTACHMENT 6 AGENCY UPDATE LOGSHEET Date l AGENCY CONTACT TIME PERSON CONTACTED COMMENTS / DISCUSSION i MADE CONTACT TITLE / POSITION l YES/NO MADE I l l i i i l l l [ O ~ pa1180-0007h-89 ' l _ _. - _ , -- . . - - - . . - . - - ---
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Emergency Implementation Procedures Revision Sheet Activation of Technical Support Center, EI-4.1 TITLE: 4 Revision PRC Date Approved by Gen. Manager l 0 10/30/80 A effit[40 1 7/8/81 h h 7 !2. P ! Ir/ 2 12/21/81 & tiny y (ly;jpy f 3 3/9/82 APR 2 5 g Q -: I f E ! O- .. 9 e
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s
/3 EMERGENCY IMPLEMENTATION PROCEDURE EI-4.1 h ~'
ACTIVATION OF TECHNICAL SUPPORT CENTER (Assembly Areas I and II) Rev 3 1.0 PERSONNEL RESPONSIBILITY Site' Emergency Director has the responsibility. for implementation of this procedure. 2.0 PURPOSE
- 1. To describe actions to be taken to activate the Technical Support Center (TSC) and to list emergency equipment available i
for use at the TSC.
- 2. The TSC is activated for use in dealing with Site, general emergencies and certain alert conditions at Palisades Plant as listed in Emergency Implementation Procedures EI-1 and EI-2 3.0 ATTACHMENTS AND RECORDS
- 1. Attachment 1, Floor plan for the Control Room / Technical Support Center.
- 2. Attachment 2, Preferred and alternate methods of communication.
- 3. Attachment 2.1, Key to Attachment 2.
- 4. Attachment 3, Minimum required personnel by plan.
- 5. Attachment 4, Personnel assigned to the Control Room / Technical Support Center.
4.0 SPECIAL INSTRUCTIONS l If airborne radiation levels warrant or the radiation levels exceed 100 mr/hr in the TSC, an alternate center can be established in the Control Room, Operations Support Center or Feedwater Purity Building. 5.0 PROCEDURE 5.1 ACTIVATION OF THE TECHNICAL SUPPORT CENTER l ! 5.1.1 Emergency equipment and communication systems in the TSC are always j available for use. 5.1.2 Upon sounding of the emergency siren, the following actions will be l performed to activate the TSC: l i 1. Personnel assigned will proceed to the Control Room /TSC j (Assembly Areas I/II). ' (~~h y_,l: ei0780-0007a154 1 '
, - ~ . . . _ -
Energency Irplementation Procedure EI-4.1, Rev 3 Activation of Technical Support Center (Assembly Areas I and II)
- 3. Portable radio.
- 4. Dedicated line to the NRC.
- 5. Dedicated line to the Van Buren Sheriff.
- 6. Company radio.
- 7. Radio to Michigan State Police (via Security).
- 8. Dedicated line to Security headquarters.
- 9. Sound-powered telephones.
5.3.2 The preferred and alternate method of communicating between the Control Room /TSC is shown in Attachment 2. 5.4 EMERGENCY EQUIPMENT 5.4.1 There are two radiological emergency personnel response kits and one radiological emergency monitoring kit stored in the TSC. 5.4.2 The following controlled documents are stored in the TSC: -
- 1. Plant Administrative Procedures
- 2. Plant Operating Procedures
- 3. Plant Emergency Operating Procedures
- 4. Plant drawings
- 5. Technical Specifications
- 6. Plant Site Emergency Plan
- 7. Plant Emergency Implementating Procedures
- 8. Michigan Emergency Preparedness Plan
- 9. Van Buren County Emergency Operations Plan
- 10. Emergency planning zone maps
- 11. Radiation Dose Isopleth Overlays 5.4.3 An area radiation monitor **RE-2310 with readout in the Control Room is installed in the viewing gallery.
y v ei0780-0007a154 3
EI-4.1 Rev 3 Page 1 (m\/
\ 'TTACHMENT 1 't Technical Support Center (Activated)
Shift Supervisor Office NRC Office Office Ext 253 Ext 252 Ext 236 i i : . J. ' I Intercom Table High Range l r
. Health Physics / ;
Monitors . l Chemistry , _ Ext 342, 287 i Table Toilet Maintenance / - Technical Support Ext 294, 243 i, Communications Ext 201 t I i Emergency Phones i l l i l t
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ATTACllho... 2 Preferred and Alternate tietlyods of Communication Communication Control Tech Supp Ops Supp Emergency ' Control Ctr NRC tiich State iVan Buren Room Center . Center Operations Jackson Police / Dept Emergency FRott: TO Facility of llealth . Services I iControl Room 1.--- 1. F to F 1. Intra 1. Intra / Gen 1. Dedic 1. Dedic 1. Gen 1. Dedic 2.--- 2. Intra 2. Walkie 2. Radio 2. Gen 2. Gen 2. ** 2. Gen
- 3. Sound -
Technical Support 1. F to F 1. --- 1. Intra 1. Intra 1. Gen 1. Dedic 1. Gen 1. Gen l Center 2. Intra 2. --- 2. Walkie 2. Gen 2. --- 2. Gen 2. ** 2. --- I I ll Operations 1. Intra 1. Intra 1. --- 1. Intra 1. Gen 1. Gen 1. Gen 1. Gen iSupport Center 2. Walkie 2. Walkie 2. --- 2. Gen 2. --- 2. --- 2 . ** 2. -- fEmergencyOpera- 1. Intra / 1. Intra 1. Intra 1. --- 1. Gen 1. Gen 1. Gen 1. Gen
; Lions Facility Gen 2. Gen 2. Gen 2. --- 2. --- 2. --- 2. ** 2. ---
- 2. Radio l
l Control Center 1. Dedic 1. Gen 1. Gen 1. Gen 1. --- 1. Gen 1. Gen 1. Gen Jackson 2. Cen 2. --- 2. --- 2. --- 2. --- 2. --- 2. ** 2. --- NRC 1. Dedic 1. Dedic 1. Gen- 1. Gen 1. Gen 1. --- 1. Gen 1. Gen
- 2. Gen 2. Gen 2. --- 2. --- 2. --- 2. --- 2. --- 2. ---
t flichigan State i 1. Gen ,1. Gen 1. Gen 1. Gen 1. Gen 1. Gen 1. --- 1. Gen Police / Dept of 2. ** l2. ** 2. ** 2. ** 2. ** 2. --- 2. --- L2. ** l llealth , i j 3 l I l Van Inren County 1. Dedic 1. Gen ,1. Gen 1. Gen 1. Gen 'l. Gen 1. Gen lI. --- l {EmergencyServices 2. Gen l2.'--- ! 2. ---
- 2. --- l2.---
, '2.---
. ,2. ** '2. ---
~
EI-4.l Rev 3 eio7,80-0007h154 Page 1
4 EI-4.1 s Rev 3 i Page 1 ATTACHMENT 2.1. KEY
- Key: F to F = Face to face Intra = Intraplant telephone Dedic = Dedicated telephone Walkie = Portable radio Gen = Normal outside telepone line i
** = State Police radio bank (available through plant security) i Radio = Company radio Sound = Sound-powered telephone NOTE: Portable radios are available in the Control Room for communications to
- and from any area within the plant. In addition, the Control Room is the principle communication center for the plant, therefore all methods of j
communication available in the Control Room can be used as backup for any ("'Ng, f plant assembly area to any offsite location. i I t O ei0780-0007c154 '
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. EI-4.1 s Rev 3
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( ATTACHMENT 3 MINIMUM REQUIRED PERSONNEL BY PLAN (Does not include Chemistry) PREFERRED FIRST ALTERNATE SECOND ALTERNATE Control Room Shift Supervisor Shift Supervisor Shift Supervisor STA STA STA C01 C01 C01 CO2 CO2 CO2 A0 A0 A0 A0 A0 A0 Reactor Engineer Tech Support General Mgr O&M Supt Tech Supt Center Recorder Recorder Recorder HP Supt Plant HP. Rad Pro Supv Tech Eng Chem Supv Ops Supv I&C Supv Maint Suov , I&C Eng Maint Eng Onsite Survey. Senior HP Senior HP Senior HP Senior HP Senior HP Senior HP HP HP HP HP HP HP Offsite Survey Senior HP Senior HP Senior HP Senior HP Senior HP Senior HP Repairman Repairman Repairman Repairman Repairman Repairman Damage Control Maint Supv Maint Supv Elec Supv Repairman Rcpairman Repairman Repairuan Repairman Repairman Repairman Repairman Repairman O eio780-0007d154 '
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ATTACHMENT 4 PERSONNEL ASSIGNED TO THE CONTROL ROOM / TECHNICAL SUPPORT CENTER .
- 1. The following personnel are assigned duties in the TSC when activated.
- A. Command and Control
- 1. Plant General Manager / Site Emergency Director
- 2. Plant Operations and Maintenance Superintendent
- 3. Recorder / Logger
- B. Communications
- 1. Technical Engineer
- 2. Recorder / Logger C. Operations Assistance 1
- 1. Shift Technical Advisor
- 2. Plant Operations Superintendent
( L' D. Engineer Assistance t- 1. Technical Superintendent
- 2. Reactor Engineer
- 3. Engineer
- 4. Plant Chemical Engineer. .
E. Radiological Assessment
- 1. Chemistry / Health Physics Superintendent
- 2. Plant Health Physicist
- 3. General Health Physicist
- 4. Radiological Materials Control Supervisor F. Damage Control
_. 1. Maintenance Superintendent
- 2. Maintenance Engineer
- 3. Instrument and Control Engineer
- 2. Personnel not listed above will require permission of the Site Emergency Director or his designated representative to enter the Technical Support Center complex.
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I Emergency Implementation Procedures, t N _ Revision Sheet r Reentry / Recovery, EI-5 TITLE: i l Revision PRC Date Approved by Gen. Manager I. 0 10/30/80 ub'fh r i i 1 i t 4
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d s EMERGENCY IMPLEMENTATION PROCEDURE EI-5 (A) REENTRY / RECOVERY Rev 0 1.0 PERSONNEL RESPONSIBILITY
- 1. Site Emergency Director is responsible for escalating, downgrading or terminating the emergency.
- 2. Technical support center staff is responsible for providing
, reentry / recovery procedures. 2.0 PURPOSE To provide guidelines for reentry / recovery of plant following implementation of Site Emergency Plan. Specific actions are dependent on circumstances. 3.0 ATTACHMENTS AND RECORDS
- 1. Attachment 1 - Record of Major Recovery Actions Performed (Page 1)
- 2. Attachment 2 - Continuation Page to Record of Major Recovery Actions Performed 4.0 SPECIAL INSTRUCTIONS AND/OR REQUIREMENTS
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()' 1. Specific reentry / recovery procedures are prepared by technical support center staff at the direction of the Site Emergency Director.
- 2. All reentry / recovery actions will be deliberate and preplanned using personnel whose experience and expertise is best suited to the required actions.
- 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, radiation expsure should be' controlled within the limits of Procedure HP 2.4.
- 4. A log should be maintained of important actions and persons performing the actions.
5.0 PROCEDURE 5.1 GUIDELINES FOR INITIATING REENTRY PHASE 5.1.1 When initiating the reentry phase, the plant should be in a stable condition assessed by the Site Emergency Director. b v pa1180-0003a-89 1 '
A - - 2 Emergency Implementation Procedure EI-5, Rev 0 Reentry / Recovery s f-~3\ t N/f
- 4. Isolate and post plant radiation areas, high radiation areas, and contaminated areas.
5.1.6 After reentry team procedures are. complete, assess the data, determine the extent of recovery operation required and initiate Section 5.2 - Recovery. 5.2 RECOVERY Recovery will occur in three phases. 5.2.1 When recovery is to commence, the Site Emergency Director is responsible for notification of offsite organizations (ie NRC, Consumers Power, Van Buren and Berrien Counties, State of Michigan, etc.) 5.2.2 Phase 1 recovery operations
- 1. Designate applicable recovery teams to perform the following:
- a. Assessment of equipment damage
- b. Installation of shielding
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- c. Posting of ccatrolled areas -
- d. Application of clearance tags
- e. Decontamination and cleanup necessary to place plant in a acceptable long term condition.
- 2. Evaluate all results from phase 1 recovery operations and determine areas affected by the emergency. Do not initiate phase 2 recovery operations until phase I has been completed and
.has clearly defined affected areas of the plant.
5.2.3 Phase 2 recovery operations
- 1. Designate applicable recovery teams to perform the following: -
- a. Detailed investigation into the accident causes and consequences co the plant and the environment.
i
- b. Evaluate work required to repair / modify plant equipment or operating procedures.
- c. Make necessary repairs / modifications as authorized,
- d. Develop and institute testing procedures to determine fitness of plant components and systems for return to f T service.
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Emergency Irplerentation Procedure EI-5, Rev 0 Reentry / Recovery V} 'v 5.3.4 The task management / scheduling group'will consist of persons designated by the recovery operations manager and will identify and plan tasks and monitor and coordinate tasks in progress. 5.3.5 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. 5.3.6 The plant operations / maintenance group will be responsible for plant operations and maintenance and all other routine activities in and around the plant. 5.3.7 The waste management group is responsible for proper management of waste processing and disposal, including onsite decontamination of facilities contaminated during the emergency. 5.3.8 The plant modifications group is responsible for providing engineering, design, materials, and construction necessary for any required modifications to plant systems, components or structures. 5.3.9 The industry advisory group will be staffed by experts from outside Consumers Power to augment the technical abilities of the long term recovery organization and provide independent technical assessment based on experience rather than engineering analysis, g, 5.3.10 The public/ government affairs group will coordinate the exchange of information with public and government agencies regarding recovery operations. Legal council will also be part of this organization. 5.3.11 The administration and logistics group will provide general services such as manpower, communications, transportation and temporary office space as required. g ~_ s pa1180-0003a-89 5
ATTACIDfENT 1 s EI-5
% Rev 0 Page 1 s RECORD OF MAJOR ACTIONS PERFORMED Date/ Time of Emergency:
4 Date/ Time Recovery Action Accomplished By Reviewed By O< l f l l l O-pa1180-0003b-89 ~
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ATTACm!ENT 2 s EI-5 O - (CONTINUATION PAGE TO) RECORD OF MAJOR ACTIONS PERFORMED Rev 0 l l Date/ Time Recovery Action Accomplished By Reviewed By O< i k-v' '~ pa1180-0003c-89 <
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Emergency Implementation Procedures Revision Sheet I v Estimate of Offsite Dose, EI-6 TITLE: Revision PRC Date Approved by Gen. Manager 0 12/5/80 ,2f(f po 1 4/1/81 L8 M 2 5/8/81 4. ! M M 3 6/5/81 h 7 17 /
-4 9/2/81 SEP1 7.1981 5 10/8/81 OCT 3 01981 6 11/9/81 MOV 3 0 1981
, 7 12/10/81 L p;.: 1 1 1982 2/4/82
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8 0 4 1982 9 3/9/82 APR 0 31982 O -. N 4
1 s q EMERGENCY IMPLEMEFTATION PROCEDURE EI-6 ESTIMATE OF OFFSITE DOSE Rev 9 1.0 PERSONNEL RESPONSIBLE 1.1 The Chemistry / Health Physics Superintendent or the Plant Health Physicist is, responsible for the implementation of this procedure. 1.2 Members of the Radiation Protection Group will complete parts of this procedure as directed by the Chemistry / Health Physics Superintendent or the-Plant Health Physicist. 1.3 If necessary, it will be the responsibility of the Shift Supervisor in concurrence with the Shift Technical Advisor to notify the Radiation Protection Group to implement this procedure. 2.0 PURPOSE To provide a simplified method for estimating wholebody and child thyroid dose rates due to abnormal releases of radioactive materials to the environment. To provide a method to compare the integrated wholebody and child thyroid doses to the EPA Protective Action Guides (PAG's). 3.0 ATTACHMENTS AND RECORDS
- 1. Attachment 1 - Determination of Release Rates
- 2. Attachment 2 - Estimated Release Rates Due to Steam Generator Tube Rupture.
- 3. Attachment 3 - Approximation of Offsite Dose
- 4. Attachment 4 - Determination of Atmospheric Stability Class
- 5. Attachment 5 - Offsite Dose Data Sheet
- 6. Attachment 6 - Protective Action Guides
- 7. Figure 1 - Stack Monitor Response (0 to 24 Hours)
- 8. Figure 2 - Stack Monitor Response (0 to 30 Days)
- 9. Figure 3 - Steam Dumps Monitor Response (0 to 24 Hours)
- 10. Figure 4 - Steam Dumps Monitor Response (0 to 30 Days)
- 11. Figure 5 - Stack Montior Total Noble Gas eiO581-0001a154 '
Emergency Implexentation Procedure EI-6, Rev 9 3 Estimate,of Offsite Dose n (,s_-) 5.4.2 Dose (thyroid) = (3.69E06)(X/Q)(QI)(2.23/WS) Rem Where: X/Q = (indicated on isopleth at locations specified) QI = Iodine release rate 2.23/WS = Wind speed correction factor 5.4.3 Mark (in spaces provided) calculated wholebody and thyroid dose rates at site boundary (SB) and each mile on isopleths. 5.4.4 Determine and mark plume arrival time in space provided on isopleth. Arrival time = (Distance (miles)/WS) + (Time Release Started) 5.5 Evaluate the hazard to the offsite population as follows: 5.5.1 Determine the two-hour wholebody and child thyroid doses for the following locations: Site Boundary 1 mile 2 miles 5 miles 10 miles
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in direction of release. 5.5.2 Record wholebody and child thyroid doses in Section C of Attachment 5. 5.5.3 Refer to Attachment 6 to determine recommended protective actions offsite. Recommendations should be passed on to the SED to be forwarded to affected offsite agencies. Information should include dose projections, arrival time, and affected map sectors including one map sector either side of the affected sectors. 5.6 Data needed for the offsite dose calculation should be reviewed at least every 1/2-hour until the Site Emergency Director requests longer intervals or determines they are no longer needed. The calculation should be updated if the stability class changes, the affected map sectors change, the release rate increases, or the wind speed decreases. A (v) " eiO581-0001a154 Proofread by: 55 l/kb s
EI-6 Rev 9 s Page 1 tO V ATTACHMENT 1 DETERMINATION OF RELEASE RATES NOTE: If offsite radiological results are known, complece Step 3'.0 of this attachment to calculate release rates.
- 1. Use of Stack Gas Monitor Readings NOTE: **RIA-2318 is the preferred monitor for determining release '
rate, use **RIA-2319 only if **RIA-2318 is not available. 1.1 Obtain stack gas flow rate (ft /3min) from chart recorder **FRC 2318 for the latest two-hour period. Multiply by 0.028 to convert to m / min. 1.2 Obtain pre-release readings in cpm from the stack gas monitors
**RIA-2318 and **RIA-2319 as indicated on chart recorder RR-2300.
1.3 Obtain readings in cpm for **RIA-2318 and **RIA-2319 during the release. 1.4 If both stack gas monitors **RIA-2318 and **RIA-2319 have gone offscale, go to Section 2.0 for this attachment. 1.5 Obtain a. net reading by subtracting pre-release (Step 1.2 above) from the reading during the release (Step 1.3 above). Record appropriate information in Section B of Attachment 5. 1.6 Obtain noble gas release rate as follows: for **RIA-2318 I
'QN (Ci/sec) = (Net cpm)(pCi/cc)*(m3 / min flow)(1/60) cpm i
NOTE: Obtain N !C from Figure 5 for the applicable monitor. Use the six (6) hour time"for release other than fuel melt for holdup times less than 15 days. Use the appropriate decay time on Figure 5 for holdup times greater than 15 days. 1.7 Estimate Iodine release rate from Step 1.6 (above) as follows: QI (Ci/sec) = (QN)(1.0E-03) 1.8 Record release rates on Section B of Attachment 5. l 1.9 Repeat readings approximately every 15 minutes until Health Physicist or Site Emergency Director requests longer intervals or determines they l are no longer needed. Q 1.10 Go to Step 5.2 of the main procedure. eiO581-000lbl54 '
EI-6 Rev 9 x Page 2 (,)
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2.0 Use of High Range Effluent Monitor 2.1 Monitor readouts are installed in NE corner at Technical Support Center near drinking fountain. NOTE: In the event that either of the high-range stack monitors are not functioning properly readings may be obtained by using a Teletector or equivalent instrument. Readings are obtained at the SW corner of elevation 639' (above component cooling room) and making use of shielding in the detector cave that is appropriate for the reading being taken. ABORT ATTEMPT IF AREA BACKGROUND EXCEEDS 100 R/HR. 2.1.1 Check battery function before each use of instruments. 2.1.2 Determine background rates from steam dump detector at a time when no steam release is occurring. 2.2 Obtain reading from stack detector and subtract background rate. NOTE: An unexpectedly high or off-scale background reading may indicate high activity in the Penetration Room filter box on the 629' level. Determine the background contribution from activity in the box f$ by using a high-range extended reach survey meter (Teletector or ( ( '/ equivalent). However, abort the attempt to obtain this reading if area ( dose rate exceeds 100 R/ hour. 2.2.1 Multiply dose rate for stack monitor by response factor (RF) 4.8 to get a corrected exposure rate. 2.2.2 Record appropriate information in Section B of Attachment 5. 2.2.3 Determine amount of time (hours) since reactor was shut down. 2.2.4 Determine dose rate to release rate ratio (R/ hour per Ci/sec) by interpolation from appropriate curve.
- 1. Use Figure 1 for 0-24 hours after shutdown.
- 2. Use Figure 2 for 0-30 days after shutdown.
2.2.5 Actual noble gas release rate is obtained by dividing the net dose rate (2.2.1 above) by the dose rate to release rate (2.2.4 above). 2.3 If necessary, noble gas release rates in steam released from relief valves and steam dumps are also determined in the above manner. [~'h ( V k eiO581-000lbl54 "
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EI-6 Rev 9
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(#/ 2.3.1 . Background may be determined following release. Proceed with a conservative estimate including background until the release stops.
- 1. Use Figure 3 for steam dump releases for 0-24 hours after shutdown.
- 2. Use Figure 4 for steam dump releases for 0-30 days after shutdown.
2.3.2 Multiply dose rates for steam dump monitor by a Response Factor (RF) of 4.8 to get dose rate. Record information in Section B of Attachment 5. 2.4 Iodine release rate may be estimated by multiplying noble gas release rate (2.2.4 or 2.3 above) by 1.0E-03. 2.5 Record release rate in Section B of Attachment 5. 2.6 Readings should be repeated approximately every 15 minutes until the Health Physicist or Site Emergency Director requests longer intervals or determines they are no longer necessary. 2.7 Go to Step 5.2 of the main procedure. 3.0 Offsite Radiological Monitoring NOTE: This method more accurately determined the iodine release rate p which was estimated previously. 3.1 Determine iodine ground concentration CI (pCi/cm )3 using Emergency Implementation Procedure EI-9. 3.2 Calculate the iodine release rate QI (Ci/sec) using the following: QI= CI X/Q Where: QI = Iodine relear.o. rate (Ci/sec) CI = Iodine ground concentration (pCI/cm 3) X/Q = Value from nearest point on isopleth where3 i dine 3 ground concentration was determined (sec/m ) 3.3 Record as appropriate in Section B of Attachment 5. 3.4 Go to Step 5.2 of the main procedure. i i d _. eiO581-000lbl54 -
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EI-6 Rev 9 s Page 1 ATTACHMENT 2 ESTIMATED RELEASE RATES DUE TO STEAM GENERATOR j TUBE RUPTURE ACCIDENT
, 1. 0 Determine Xe-133 Ci release from a steam generator by the following:
QN(CI/sec) = 5 GA VC 3.78 x 10
-3 a t
*5 = average energy of radioactivity in primary coolant.
*GA = gaseous activity present in primary coolant, Nf=(If5 and/or A are unknown use E GA = 100).
- VC = volume of primary coolant (gallons) that has leaked to the secondary system. If unknown use 8.19 x 104 gallons.
t = release period in. seconds
- Obtained from Chemistry report forms.
2.0 Determine I-131 Ci released from a steam generator by the following: g QI(Ci/sec) = D VC 3.78 x 10 -3 t D = dose equivalent I-131 obtained from Chemistry report' forms (if unknown, use 40 pCi/cc). VC = volume of primary coolant (gallons) that has leaked to the secondary system. If unknown, use 8.19 x 104gallons. i 3.0 Record appropriate information in Section B of Attachment 5. l , 4.0 Go to Step 5.2 of the main procedure. l l l l l l i eiO581-0001c154 ' l l-.-.-----.-_-.-.-.--...-.-_.
EI-6 Rev 9 s Page 1 m U, ATTACHMENT 3 APPROXIMATION OF 0FFSITE DOSE 1.0 Determine the following points on the area map in the Technical Support Center in the direction of the release path: Site Boundary 5 miles 10 miles Nearest population point (city, town, etc) 2.0 Determine the X/Q values for the points in Step 1.0 from Table 3.1 (these values are calculated for stability condition E and a wind speed of 2 m/sec). 3.0 Determine wholebody dose (2 hour exposure) for the points in Step 1.0. Dwb = (X/Q)(QN)(8.6x10 ) Rem Were: Dwb = wholebody dose (Rem) X/Q = atmospheric dispersion factor (sec/m3) QN : Noble gas release rate (Ci/sec) (Attachment 1) ' 8.6x102 = 4.3x102 rem /hr x 2 hours Ci/m 3 - 4.0 Determine child thyroid dose (2 hour exposure) for the points in ' Step 1.0 above. . 0 j D = (X/Q)(QI)(7.4x10 ) Rem Were: D et
= child thyroid dose (Rem)
QI = release rate of radioiodines Ci/sec (Attachment 1) 7.4x106 = child thyroid dose conversion factor Rem-m3 Ci 5.0 Record appropriate information in Section C of Attachment 5. l .
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EI-6
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Page 1 1 1 i TABLE-3.1 i , X/Q Versus Distance for Stability Condition E and Wind Speed 2 m/sec T l
- Distance Miles Meters X/Q (sec/m3 )
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.435 700 (Site Boundary) 1.48 x 10 '
l 'I.00 1609 5.33 x 10 -5 I 2.00 1.98 x 10 -5 t - 3219 1 1.20 x 10 -5 l 3.00 - 4828
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N 4.00 8.11 x 10 -6 s 6437 , 5s00 s
-6 B047x 6.25 x 10 l
4.90 x 10 -6
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9656 + l' 4.35 x 10 -6
, 7.00 11265 8.00 ^12875 3.53 x 10 -6 3.26 x 10 -6
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9.00 '1404' 1 10.00 16093 N[,
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EI-6 Rev 9 s Page 1 ( I s s/ ATTACHMENT 4 DETERMINATION OF ATMOSPHERIC STABILITY CLISS 1.0 Using Control Meterological Terminal 1.1 This is the preferred method, if meteorology tower data is unavailable, go to Part 2.0. 1.2 Following the posted instructions in the Control Room, activate the meteorological terminal and obtain a printout. The printout should be in the form of the following example.
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SITE PALI PALI PALI PALI PALI PALI PALI PALI 1[EIGHT 10-M 6010 10-M 10-M 10-M 60-M 60-M 60-M PARAMETER TEMP DELT WS WD SGMA WS WD SGMA UNITS C C MPH DEG DEG MPH DEG DEG [] N~,] AVE ENDING-EST 02/12/80 15:00 -4.7 -0.49 11.70 249. 14.3 14.11 241. 10.2 STATUS 00 0 0 0 0 0 0 0 0 1.3 Verify the " STATUS 00" to be "0" for the "10-M WS" and "10-M WD" columns (10 meter wind speed and wind direction, respectively) and record readings in Section A of Attachment 5. NOTE: If status is other than 0, record "60-M WS" and "60-M WD". 1.4 Verify the " STATUS 00" to be "0" for the "6010 DELT" column (60 meter /10 meter temperature differential) and note reading on Attachment 5. NOTE: If status is other than 0, go to Step 1.6. I 1.5 Use Table 4.1 of this attachment in conjunction with Parameter DELT to determine stability class. Record in Section A of Attachment 5. Return to Step 5.3 of the main procedure l p) ( -. eiO581-0001f154 ' l l l l
EI-6 Rev 9 s Page 2 Table 4.1 O DELT Stability Class
<-0.95 A
-0.95 to -0.85 B
-0.S5 to -0.75 C
-0.75 to -0.25 D
-0.25 to +0.75 E
+0.75 to +2.0 F
>+2.0 G (values adjusted for 50 meter height) 1.6 Verify the " STATUS 00" to be "0" for the "10-M SGMA" column (10 meter sigma theta) and note reading.
NOTE: If status is other than 0, verify " STATUS 00" is "0" for "60-M SGMA" and note this reading. If other than 0 go to Step 2.0. 1.7 Use Table 4.2 and the parameter SGMA of this attachment to determine stability condition. Record in Section A of Attachment 5. Return to Step 5.3 of the main procedure Table 4.2 SGMA Stability Class
>22.5 A 17.6 to 22.5 B 12.5 to 17.5 C 7.5 to 12.5 D 3.75 to 7.5 E 2.1 to 3.75 F
< 2.1 G 2.0 Using Weather Service International (WSI)
An alternate source of information for wind speed, wind direction, stability class, and other weather conditions may be obtained from the l Control Room meteorology terminal using this section. 2.1 Remove the cable connection to the meteorologi al tower at the back of the terminal. Install jumper cable. Place the terminal panel switches in the following alignment: " LOW SPEED" - 0FF, " HALF DUP" - 0FF, "0N LINE" - ON, and "NUM" - 0FF. NOTE: OFF is to the RIGHT ON is to the LEFT O l eiO581-0001f154 - 1 l
EI-6 Rev 9
.s Page 3 2.2 Dial any of the following numbers using the adjacent telephone and place the handset in the telephone coupler at the back of the terminal.
Ann Arbor (313) 996-0351 Detroit (313) 964-5538 Chicago (312) 938-0500 2.2.1 When the green light at the front of the keyboard lights, type two Carriage Returns. Note those items to be entered are in quotes. Do not type quotes. NOTE: If WSI in unavailable, go to Step 3.0. 2.2.2 When the terminal responds with " TERMINAL =" type "T145" then Carriage Return (cr.). 2.2.3 When the terminal responds with "@" type: "C (space 617133" and two more Carriage Returns. 2.2.4 When requested, type "LOGIN PAL" then (cr). % 2.2.5 The password, when requested, is " POWER" then (cr). C1 2.3 Type " NUKE PALI" (cr) 2.3.1 Use the table labeled "Recent Hourly Obs and Pasquill Stability" for Benton Harbor. Wind direction is read from the column labeled " wind", wind direction is given in tens of degrees from true north and wind speed is in knots. The first two digits are wind direction and the last two digits are wind speed. For example: 2213 would represent a wind direction of 220 degrees and a wind speed of 13 knots. 2.3.2 Convert wind speed to miles per hour as follows: Speed Speed x 1.15 (mph / knot) = mph 2.4 Type "LOGOUT" (cr) when the session is over and replace telephone. Reconnect the meteorological tower line. 2.5 Return to Step 5.3 of main procedure. 3.0 Using FAA Information Use this section if there is no information from the meteorology tower or if the status of all of the columns described is not "0". 3.1 Contact the FAA in Benton Harbor and obtain wind speed and wind direction (925-5264). 6 eiO581-0001f154 r
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EI-6 Rev 9 s Page 4 3.2 If physical observation is made that the wind is calm use stability Class F. 3.3 Record above information in Section A of Attachment 5. 3.4 Return to Step 5.3 of the main procedure. e 0 eiO581-0001f154 ,
EI-6 R:.v 9 ATTACHMENT 5 Page 1 s 0FFSITE DOSE DATA SHEET Date (n- ) '. A. Meteorology: Time WS mph WD DEG Stability Class 6010 Delt B. Release Rate:
**RIA-2318 /**RIA-2319 Monitors
- Monitor Reading (cpm) lStackGasFlowRate (Cu Ft/ min) QN QI Calculated Time Gross Bkg Net to Cu Meters / min (Ci/sec) (Ci/sec) By:
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i l' I f I i i High Range Effluent Monitor Dose rate to
' Monitor Reading ( R/hr) release rate QN j QI Calculated Time ,' Gross Bkg Net RF x Net ratio R/hr (Ci/sec) :' (Ci/sec) By:
Ci/sec 4 I I i j - 1 I I
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(n- ) i ! Offsite Measurements i Instrumentation Used i QI Calculated Time Model# Serial # Date Location (Ci/sec) Other By: j i I . t I i i ! l I . i , ; i l i l l 4 . l l l I ! l l 1 : ! l C. Offsite Doses WHOLEB0DY DOSES (REM) CHILD THYROID DOSES (REM) I (2.89E3)(X/Q)(QN)(2.23/WS) (3.69E6)(X/Q)(QI)(2.23/WS) Calculated i l Time .SB 1 mi 2 mi .5 mi 10 mi Other SB 1 mi 2 mi 5 mi 10 mi Other: By: . j
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O ( O'. t Rev 9 Page 1 ATTACHMENT 6 RECOMMENDED PROTECTIVE ACTIONS TO REDUCE WHOLEB0DY AND THYROID DOSE FROM EXPOSURE TO A GASEOUS PLUME t Projected Dose (Rem) to the Population Recommended Actions (,) Comments ] Wholebody <1 No planned protective actions (b) Previously recommended protective State may issue an advisory to seek shelter and await actions may be reconsidered or i further instructions. terminated.
- Thyroid <5 Monitor environmental radiation levels.
a j Wholebody 1 to < 5 Seek .helter as a minimum. If constraints exist, special q Consider evacuation. Evacuate unless constraints make consideration should be given for Thyroid 5 to < 25 it impractical. evacuation of children and Monitor environmental radiation levels. pregnant women. Control access. a Wholebody 5 and above Conduct mandatory evacuation. Seeking shelter would be an Monitor environmental radiation levels and adjust area alternative if evacuation were ! Thyroid 25 and above for mandatory evacuation based on these levels. not immediately possible. ; 3 Control access. Projected Dose (Rem) to Emergency Team Workers Wholpbody 25 Control exposure of emergency team members to these Although respirators and stable i levels except for lifesaving missions. (Appropriate iodine should be.used where j Thyroid 125 controls for emergency workers, include time effective to control dose to limitations, respirators and stable iodine.) emergency team workers, thyroid dose may not be a limiting . Wholebody 75 Control exposure of emergency team members performing lifesaving missions to this level. (Control of time of exposure will be most effective). i (a)These actions are recommended for planning purposes. Protective action decisions at the time of the incident must take existing conditions into consideration. l (b)At the time of the incident, of ficials may implement low-impact protective actions in keeping with the principle of maintaining radiation exposures as low as reasonably achievable. eiOS,81-0001h154
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e Emergency Implementation Procedures Revision Sheet Post Accident Sampling, EI-7 Revision PRC Date Approved by Gen. Manager 0 11/19/80 sif2.L[Po 1 10/8/81 T2/g { OCT 3 01981 2 3/9/82 mmh m APR 15 IS32
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_= . .- i (s' EMERGENCY IMPLEMENTATION PROCEDURE EI-7 POST ACCIDENT SAMPLING Rev 2 1.0 PERSONNEL RESPONSIBILITY Plant Chemistry / Radiation Protection Technicians are responsible for Post Accident Sampling. 2.0 PURPOSE
- 1. Provide methods and radiological precautions for sampling and analysis of highly radioactive reactor coolant.
- 2. Provide a method for sampling and analysis of containment air during emergency conditions.
- 3. Provide a method of determining airborne iodine concentrations in areas within the plant.
3.0 ATTACHMENTS AND RECORDS
- 1. Attachment 1 - Emergency Containment Air Sampling System.
- 2. Attachment 2 - Flow Meter Calibration for Stainless Steel Float
- 4. Attachment 4 - Time to Purge 3 line Volumes at Various System t
Pressures 4.0 SPECIAL INSTRUCTIONS AND EQUIPMENT
- 1. Special Instructions l a. In addition to routine dosimetry provisions, extremity dosimetry for the hands and a high range pocket dosimeter shall be provided to personnel involved in sampling and analysis.
- b. Radiological conditions (radiation levels, air sampling as appropriate) shall be assessed in the vicinity of and during sampling and analysis activities to assure each individual's radiation exposure shall be less than 3 Rem per quarter.
- c. Personnel performing sampling and analysis shall be equipped with a portable survey instrument (Eberline "Teletector",
P6112 or equivalent) to monitor actual radiation levels during sampling and analysis activities.
- d. Do not perform sample if the general area radiation levels at the Sampling Station exceed 100 R/hr. If exposure rates f- s exceed 50 R/hr, sampling and analysis should be performed by
() different individuals. ei1180-0009a154 ~. t
~- ,,_ _
Emerg:ncy Implcmentation Procedure EI-7, Rav 2 2 Post Accident Sampling s O
- e. Anti-Coatamination clothing and respiratory equipment shall be worn as radiological conditions warrant.
- f. When handling samples, use remote handling equipment whenever possible. If samples must be handled directly with hands, do so at arms length.
- g. When not being handled, store samples in a shielded location (lead brick barrier is sufficient) to shield personnel from unnecessary radiation exposure.
- h. Handle unsealed samples in a filtered laboratory hood.
- 2. Special Equipment
- a. H809V air sampler or equivalent
- b. 2k" silver zeolite cartridges
- c. Ratemeter (PRM 16 or equivalent) with Eberline HP-210 probe or equivalent.
5.0 PROCEDURE y 5.1 SAMPLING AND ANALYSIS OF HIGH ACTIVITY REArf0R COOLANT 5.1.1 Conduct a presample survey of the cold chemistry laboratory to determine if radiation levels in the sample room are acceptable (<3 R/hr). 5.1.2 Commence flushing the NSSS Sample Panel sample lines as follows:
- a. Using a high range portable survey instrument, monitor radiation levels in route to sample room.
NOTE: A high radiation field may be encountered in the vicinity of t.he containment access hatch. This may not be indicative of the field in the sample room. If high fields are encountered near containment access hatch, traverse area as quickly as possible, and continue to survey the sample room.
- b. Enter the sample room and initiate flushing of the NSSS Sample Panel Point SX1023 per Chemistry Procedure F3.1.
NOTE: It may be necessary to contact the Control Room to override the containment isolation signal.
- c. Exit the sample room when flushing has started. Flushing and sampling will cause an increase in sample room airborne activity levels.
ei1180-0009a154 .. O f
Emergency Implemrntation Procedura EI-7, Rev 2 3 Post Accident Sampling 5.1.3 Draw the Primary Coolant Sample as follows:
- a. Calculate the stay time and prepare to time the second ent ry.
- b. Obtain a 5 mi sample from sample point SX1023. Cap and bag sample container and place it in shielded sample carrier (available from Radiation Protection equipment storage cage).
- c. Secure sample line and transport shielded sample carrier to hot chemistry laboratory.
5.1.4 Sample Dilution and Preparation,
- a. Prepare aliquots for a boron and gamma spectrum analysis.
- b. For radiation exposure purposes, the boron sample should be prepared using the smallest volume of the reactor coolant sample that will ensure accurate analytical results. Approximately 2-3 ml of reactor coolant sample diluted to a volume required to perform the analysis should be adequate.
- c. Prepare a diluted reactor coolant sample for gamma spectrum analysis. The purpose of sample dilution is to decrease the radioactivity concentration of the sample and thus to limit counting dead time of the spectrum analysis equiment and reduce radiation exposure to the individual performing the analysis.
For highly radioactive samples, perform a 1.0E + 4 to 1 dilution of the reactor coolant sample to prepare the radiological sample.
- d. When the samples are diluted, perform the analysis in the hot laboratory and adjacent counting room. If these areas cannot be used for analysis, perform the boron analysis in the feedwater purity building backup laboratory (if habitable) and the gamma analysis in the low level counting room. DO NOT TRANSFER UNDILUTED SAMPLES TO THESE AREAS.
5.1.5 Sample Analysis
- a. Perform sample analysis per Chemistry Procedures F4.3 and F4.32.
- b. When an analysis is completed, samples should be disposed of in the hot laboratory sink. If the laboratory is not accessible, waste samples should be collected in a shielded liquid waste container.
- c. Report results to Chemistry Supervisor or his designated representative and Site Emergency Director.
O) \ y ei1180-0009a154 -. 9
Emerg:ncy Irplcmentation Procedura EI-7, R:v 2 4 Post Accident Sampling s O 5.2 PROCEDURE FOR SAMPLING CONTAINMENT ATMOSPHERE 5.2.1 Sampling
- a. Prior to entering the sampling room, select sampling location within the containment, as specified by the Site Emergency Director, using HS-2404, located near the Laundry Room.
POITION LOCATION _SV 2 VHX-1 inlet SV-2402-M 3 VHX-1 outlet SV-2402-N 4 CB atmosphere SV-2402-P
- b. Check that gas sample bomb is in place.
- 1. Check that valves **MV-VAS141, **MV-VAS142, **MV-VAS143,
**MV-VAS144, **MV-VAS145, **MV-VAS146, **MV-VAS147 and
**MV-510 are closed.
- 2. Open valves **MV-VAS141 and **MV-VAS142 and note reading on -3 PI #1.
- a. If less than 10 psig, open valves **MV-VAS143 and
**MV-VAS144 and start pump by plugging it in to receptacle on front of sample panel,
- b. If greater than 10 psig, open valve **MV-VAS145.
- c. If these valves are opened for practice, Technical Specification Surveillance R0-32 must be performed.
l Notify Technical Superintendent prior to test.
- 3. Open valve **MV-VAS147 (stack isolation valve).
j 4. Check that needle valve on the flow meter is fully open.
- 5. Establish sample flow by gradually opening valve l **MV-VAS146. Regulate flow on PI #2 to less than 3 psig.
- 6. Check reading on flow meter and determine flow rate from either Figure 2 or Figure 3.
l
- 7. Determine sampling purge time from Figure 4. Establish flow and exit room until purge is completed.
- 8. Unplug pump if running. Close valve **MV-VAS146. Close valve **MV-VAS147.
ei1180-0009a154 .. 1
I Emergency Implementation Procedure EI-7, Rev 2 5 ) Post Accident Sampling
. q I
- 9. Using a syringe, collect a Icc sample for gas partitioner analysis and a 0.01 cc sample for MCA' analysis, i
j 10. To depressurize system, open valves numbered **MV-VAS146 and
) **MV-VAS147. Close valves numbered **MV-VAS141-and i **MV-VAS142. Open valves numbered **MV-VAS143, **MV-VAS144, and **MV-VAS145.
) 11. Close valves numbered **MV-VAS143, **MV-VAS144, **MV-VAS145,
**MV-VAS146 and **MV-VAS149 in sequence.
- 12. Place samples in shielded holders and transport to the
! laboratory. 5.2.2 Analysis With entire 1 cc sample, analyze for hydrogen content using Chemistry Procedure F4.25A.
- a. Perform a gamma spectrum analysis using a multichannel gamma spectrometer. Use a counting time suitable for the apparent sample radioactivity concentration.
- b. Report results to the Chemistry Supervisor and Site Emergency
\ Director.
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EI-7 Rev. 2
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Revision Sheet Onsite Radiological Monitoring, EI-8 TITLE: Revision PRC Date Approved by Gen. Manager 0 10/30/80 ^** ill li 1 12/30/80 g, /g 2 4/8/81 yft(fVf 3 5/8/81 6 fl o, y b (/ l
EMERGENCY IMPLEMENTATION PROCEDURE EI-8 O(- ' ONSITE RADIOLOGICAL MONITORING Rev 3 1.0 PERSONNEL RESPONSIBILITY 1. The Chemistry / Health Physics Superintendent or Plant Health Physicist is responsible for dispatching the monitoring t eams. 2. The Radiation Protection Technicians are responsible for performing Support surveys and reporting accurate data to the Technic Center. a l 2.0 PURPOSE To provide guidelines for performing radiological survey onsit e (inside security fence) during an emergency. 3.0 ATTACHMENTS AND RECORDS 1. Attachment 1, Monitoring Team Outfitting Requirements 2. Attachment 2, Position of Detector Probe and Cartridge for Iodine Determination rossG 3. Attachment 3, Onsite Survey Information Sheet [Ih \ 4. Attachment 4, Sample Analysis Data Sheet
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4.0 SPECIAL INSTRUCTIONS All members of the Radiation Monitoring Teams must perform er th i actions in such a manner that they do not exceed the following maximum permissible quarterly exposure limits: AREA EXPOSED Whole Body ~ ~ EXPOSURE LIMIT (REM) 3.0 Hands, forea rms , feet, ankles Skin of Whole Body 18.75 7.5 5.0 PROCEDURE 5.1 Designate the on-site monitoring teams and have them outfit themselves in(Attachment Requirements accordance with the Monitoring Teamu O tfi tting 1 of this procedure). 5.2 Ensure that monitoring teams are dispatched so the following specific (Attachment 3), loose surface contamination levelslocatio l l es airborne contamination levels (Attachment 4). (Attachment 3) and (~' a. Areas of the plant affected by the emergency.
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Emergency Icplem:ntation ProcIdure EI-8, Rev 3 Onsite Radiological Monitoring s Notify the Site Emergency Director of any intended entries by the monitoring teams into affected plant structures.
- b. Assembly areas that do not have access to radiological emergency monitoring kits. ,
d
- 1. Assembly Area V (Lunchroom)
- 2. Assembly Area VI (Main Locker Room)
- 3. Assembly Area VIII.[3ecurity Building)
- 4. Assembly Area IX (Main Parking Lot)
- c. Security CAS room and SAS.
5.3 Ensure that all monitoring teams are dispatched to their designated area via the best route (not through high radiation areas, etc.). 5.4 If the results of the on-site monitoring verify that a release of radioactive material has occurred, initiate EI-9, "Offsite Radiologi cal Monitoring", and EI-10, " Environmental Assessment", in order to begin collection of data from applicable offsite locations. 5.5 If available, use the low-level counting room in the Service Building Addition to determine particulate and iodine airborne activity. 5.5.1 After the sample has been taken to the counting room area, it should ; be purged of any residual xenon activity before it is counted. This 3 may be accomplished by running the air sampler for an additional two minutes. ] 5.6 If the counting room is unavailable for use due to high radiation levels, pa'rticulate and gross iodine airborne activities can be determined as follows: 5.6.1 Determination of Particulate Airborne Activity
- 1. PRM-6 survey meter with HP-210 probe is required.
- 2. Sample counting shall be done where the background count rate is 5 300 CPM, if necessary use lead bricks for shielding.
- 3. Determine sample time by subtracting time sample started from time sample ended and converting results to units of minutes.
- 4. Determine sample volume by trultiplying sample time (min) by air sampler flow rate (CFM).
- 5. Determine the background count rate with the shield off the probe. (
pa0780-0010a-89-93 2
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Emergency Implementation Procedure EI-8, Rev 3 , Onsite Radiological Monitoring s s s
- 6. Determine the gross particulate CPM (sample & background) by ,
placing the detector (shield off) adjacent to the upstream . (smooth) side of the filter. ,
- a. Handle the filter with forceps only.
- b. Lo not touch the filter with the probe. "-
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- 7. Determine the activity from the following general equation.
Activity (uCi/CC) = (6.7E-ll) ( s - b ) ts s ,: (F1+F) 2 Em " Where: ~. C = Concentration (uCi/cm ) - R = Sample count rate (cmp) < (s = Background. count rate (cpm) F 3
= Initial flow rate (cfm) .
F 2
= Final flow rate (cfm) ,
ts = elapsed sampling time (minutes) 6.7E-11 = conversion factor accounting for units and instrument and filter efficiency. 6 s
- 8. Calculate the activity on Attachment 4 and report the results to the Site Emergency Director.
e c' ' 5.6.2 Determination of I-131 Activity . 4
- 1. Use the Sam-2 with the RD-22 NaI Detector.
- 2. Use detector souce geometry as shown in Attachment 1.
- a. Handle filter with cartridge only.
- b. Cartridge should be wrapped in clear plastic before placing-under detector. .,;
- 3. Depress the reset-start switch to initiate the counting cycle.
- 4. To obtain activity of I-131 on cartridge, multiply cpm readings by (pCi/ cpm) factor shown on calibration sticker. Take average of at least 3 cpm readings. Record on Attachment 4.
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EnergAncy implem2ntation Procedure EI-8, Rev 3 i-Onsite'Padiological Monitoring -
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Example Calibratien Factor = 2.50 ~ pCi/ cpm cpm
,5 Meas. 1 57300- (57313 cpm)(2.5 x 10 ' pCi/ cpm) = 1.43 Ci 2 57412 3 57228.
Avg s. 57353
- i. s N, 5. Determine sample volume by multiplying sample time (min) by air sampler flow rate (cfm).
- 6. To obtain activity coacentration, divide total activity found in
- 4. above by the sample volume.
C(pCi/cc = Average p r m step 6 F1 + F2 ts (2.83EC4) 2 C, Where:
., A
'r C. = Concentration (pCi/cc)
F1 = Initial Flow Rate (cfa) F2 _ = Final Flow Rate (cfm) ts = Elapsed saepling time (minutes) 2.83E04 = Convers!.ca Factor for (cu ft) to (cc)
- 7. Calculate the activity on Attachment 4 and report the results to the Technical Support Center.
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EI-8 Rev 3
% Page 1 ATTACHMENT 1
- MONITORING TEAM OUTFITTING REQUIREMENTS
- 1. All monitoring team members
- 1. Full protective clothing
- 2. Appropriate respiratory equipment
- 3. High range dosimeter (0-5R), and accident dosimeter (0-50R)
- 2. Chemical / Radiation Group team members
- 1. High range survey instrument
- 2. Air sampler
- 3. 10 Silver Zeolite iodine cartridges and 10 particulate filters
- 4. Separate bags and envelopes for each cartridge and filter
- 3. Non-Chemical / Radiation Group team members
- 1. Portable radio
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- 2. Survey maps applicable to the areas to be surveyed
- 3. Smear filters (sufficient quantity for contamination surveys to be performed)
- 4. Separate envelope for each smear filter
- 5. Penci1 or pen
- 6. Onsite Survey Information Sheet i
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6 POSITION OF DETECTOR AND CARTRIDGE FOR IODINE DETERMINATION
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EI-8 7-~s i Rev 3 ( Page 1 ATTACHMENT 3 ONSITE SURVEY INFORMATION SHEET (For use outside of plant structures only) At the assigned survey areas, take two readings by first holding the detector three (3) feet from the ground and then three (3) inches from the ground. Dose Rate Dose Rate Loose Location (MR/Hr) (MR/Hr) Surface (Description) at 3 Ft at 3" Contamination 7-
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ATTACl! MENT 4 SAMPLE ANALYSIS DATA SilEET Date Sample Location Calculated by Time
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Sample Time Sample Volume Time Sampler Time Sampler Sample Sample Sampler 3'" ' "*E Stopped Started Time (Min) Time (Min) (Ft / Min) (Ft 3)'"*" Beg Flow Ending Flow
- = X =
( )+( ) 2 Background Count. Rate (Must be Less than 300 CPM) CPM Count Rate Meter Serial Number Particulate Activity (Ci/M ) Gross CPM (Sample & Bkgd) -= (6.7E-II) x (Gross CPM - Bkgd CPM = ge Sample Volume (Ft") cc 1 , Gross Iodine Activity (Ci/M") Gross CPM (Sample & Bkgd) = (6.7E-II) x (Gross CPM ___ = pc Sample Volume-Bkgg) (Ft CPM cc Air Particulate Gr ss I dine 3 3 Activity Ci/M Activity Ci/M Reviewed by Plant llealth Physicist Reviewed by Site Emergency Director EI-8 Rev 3 pa0760-0010d-89-93 Page 1 .
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Emergency Implementation Procedures Revision Sheet A Offsite Radiological Monitoring, EI-9 Revision PRC Date Approved by Gen. Manager 0 10/30/80 ,,/s, l 5ro 1 12/5/80 '*8 W 10/8/81 r 2 < g% OCT 3 01981 e. i Vs i e 1
s EMERGENCY IMPLEMENTATION PROCEDURE EI-9 0FFSlTE RADIOLOGICAL MONITORING Rev 2 1.0 PERSONNEL RESPONSIBILITY
- 1. The Chemistry / Health Physics Superintendent or Plant Health Physicist is responsible for dispatching the monitoring teams.
- 2. The Radiation Protection Technicians are responsible for performing the surveys and reporting accurate data to the Technical Support Center.
2.0 PURPOSE To provide guidelines for performing radiological surveys offsite (outside security fence) during an emergency. 3.0 ATTACHMENTS AND RECORDS
- 1. Attachment 1, Monitoring Team Outfitting Requirements
- 2. Attachment 2, Position of Detector Probe and Cartridge for Gross Iodine Determination
- 3. Attachment 3, Downwind Survey Information Sheet
- 4. Attachment 4, Sample Analysis Data Sheet 4.0 SPECIAL INSTRUCTIONS All members of the Radiation Monitoring Teams must perform their actions in such a manner that they do not exceed the following maximum permissible quarterly exposure limits:
AREA EXPOSED EXPOSURE LIMIT (REM) Whole Body 3.0 Hands, forearms , feet, ankles 18.75 Skin of Whole Body 7.5 5.0 PROCEDURE 5.1 2esignate the offsite monitoring teams and have them outfit themselves in accordance with the Monitoring Team Outfitting Requirements (Attachment 1 of this procedure). 6 5.2 Determine the affected downwind sectors to be surveyed (these include : the primary 22.5 sector directly downwind plus the 22.5 sector on l either side of the downwind sector) from meteorological computer l output. Monitoring teams should verify wind direction by observing ,' the flag, cooling tower plume, steam release, or other suitable : means. If these observations conflict with information from j s - pa0780-0011a-89 1 - 1
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Emergency Implerentation Procedure EI-9, Rev 2 Offsite Radiological Monitoring s Oe meteorological computer, use the observations to determine affected areas to be monitored. 5.3 Ensure that monitoring teams are dispatched so the following specific locations will be surveyed for whole body radiation dose rates (Attachment 3), loose surface contamination levels (Attachment 3) and airborne contamination levels (Attachment 4)
- a. The nearest downwind population center (town) within the 10 mile Emergency Planning Zone if a center exists.
- b. Three monitoring locations within each of the three 22.5*
downwind sectors that will give a good representation of the width and length of the plume within the 10 mile radius. 5.4 If environmental air samples and TI.D's are to be collected, initiate EI-10, " Environmental Assessment", prior to dispatching the team that will collect the samples. 5.5 Ensure that monitoring teams are dispatched to their designated area via a route that is out of the plume, not through high radiation areas, etc. 5.6 Incorporate acutal radiological data into the projected dose calculations as soon as possible. 5.7 If available, use counting room to determine particulate and gross iodine airborne activities. 5.8 If the counting room is unavailable for use due to high radiation levels or other reasons, particulate and gross iodine airborne l activities can be determined as follows: 5.8.1 Determination of Particulate Airborne Activity
- 1. PRM-6 survey meter with HP-210 probe is required.
- 2. Sample counting shall be done where the background count rate is 5 300 CPM, if necessary use lead bricks for shielding.
- 3. Determine sample time by subtracting time sample started from time sample ended and coverting results to units of minutes.
- 4. Determine sample volume by multiplying sample time (min) by air sampler flow rate (CFM).
- 5. Determine the background count rate with the shield off the i probe.
O pa0780-0011a-89 2 '
Emergency Implementation Procedure EI-9, Rev 2 Offsite Radiological Monitoring U ('
- 6. Determine the gross particulate CPM (sample & background) by placing the detector (shield off) adjacent to the upstream (smooth) side of the filter.
- a. Handle the filter with forceps only.
- b. Do not touch the filter with the probe.
- 7. Determine the activity from the following general equation:
C = (6.7E-11) ( s - b) ts
\(F7+F) 2 Where:
= 3 C Concentration (pCi/cm )
R s
= Sample count rate (cpm)
R = Background count rate (cpm) l F 3
= Initial flow rate (cfm) '
F 2
= Final flow rate (cfm) ts = Elapsed sampling time (minutes) 6.7E-11 = Conversion factor accounting for units sr and instrument and filter efficiency.
_)
- 8. Calculate the activity on Attachment 4 and report the results to the Site Emergency Director.
5.8.2 Determination of gross iodine activity
- 1. PRM-6 survey meter with HP-210 probe is required.
, 2. Sample counting shall be done where the background count rate is 5 300 CPM, if necessary use lead bricks for shielding.
- 3. Determine sample time by subtracting time sample started from l time sample ended and converting results to units of minutes.
- 4. Determine sample volume by multiplying sample time (min) by air sampler flow rate (CFM).
- 5. Determine the background count rate with the shield off the probe.
- 6. Determine the gross iodine activity by placing the detector (shield off) adjacent to the upstream side of tha cartridge (shown in Attachment 2).
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- Emergency Implementation Procedure EI-9, Rev 2 Offsite Radiological Monitoring s
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- 7. Determine the activity from the following equation:
C = (6.7E-11) (R, _ Rb ) ts
'n(F7+F) 2
- 8. Calculate the activity on Attachment 4 and report the results to the Site Emergency Director.
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EI-9
\ Rev 2 Page 1
\ ATTACHMENT 1 ( MONITORING TEAM OUTFITTING REQUIREMENTS 1
- 1. All monitoring team members Low range dosimeter (0-200MR), and high range dosimeter (0-5R)
- 2. Chemical / Radiation Group team members
- 1. High range survey instrument
- 2. Air sampler
- 3. 25 Silver Zeolite iodine cartridges and 25 particulate filters
- 4. Separate bags and envelopes for each cartridge and filter
- 3. Non-Chemical / Radiation Group team members
- 1. Radiocommunication equipment applicable to the expected travel distance from the site
- 2. Survey maps applicable to the areas to be surveyed
- 3. Smear filters (sufficient quantity for contamination surveys to be
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- 4. Separate envelope for each smear filter
- 5. Pencil or pen
- 6. Downwind Survey Information Sheet
- 7. Applicable survey maps
- 9. Transportation vehicles (may use personal vehicles) pa0780-0011b-89 "
EI-9 Rev. 2 Page 1 Attachment 2 s Position of Detector Probe and Cartridge for Gross Iodine Determination s . __P-Probe t I Flow Direction : +--Silver Zeolite Cartridge v I i t POSITION OF DETECTOR PROBE AND CARTRIDGE FOR GROSS IODINE DETERP11 NATION Q .. 4
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EI-9 s Rev 2 Page 1 ATTACHMENT 3 DOWNWIND SURVEY INFORMATION SHEET (For use outside of plant structures only) At the assigned survey areas, take two readings by first holding the detector three (3) feet from the ground and then three (3) inches from the ground. Dose Rate Dose Rate Loose Location (MR/Hr) (MR/Hr) Surface (Description) at 3 Ft at 3" Contamination V pa0780-0011c-89 '
- nD C "O ATTACHMENT 4 i
SAMPLE ANALYSIS DATA SHEET i Date Sample Location Calculated by Time i 1
! Sample Time Sample Volume Time Sampler Time Sampler ' Sample Sample Sampler Flow Rate Samplejolume Stopped 3 Started Time (Min) Time (Min) (Ft / Min) (Ft. )
! Beg Flow Ending Flow
- = X =
1 ( )+( ) i 2 Background Count Rate (Must. be Less than 300 CPM) CPM Count Rate Meter Serial Number i Particulate Activity (Ci/M ) Gross CPM (Sample & Bkgd) -= , (6.7E ) x (Gross CPM - Bkg4 CPM = CJ l Sample Volume (FL') M Gross Iodine Activity (Ci/M") Gross CPM (Sample & Bkgd) = (6.7E ) x (Gross CPM - Bkgd CPM = Cj Sample Volume (Ft.") M Air Particulate Gross Iodine 3 Activity Ci/M Activity Ci/M i i Reviewed by Plant Health Physicist Reviewed by Site Emergency Director l EI-9 ) . Rev 2 ) pa07$0-00lld-89 Page 1
EI-6
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I FIGURE 1 ! i Stack Monitor Response (0 to 24 Hours) ' FIGURE 2 Stack Monitor Response (0 to -30 Days) FIGURE 3 ' i Steam Dumps Monitor Response (0 to 24 Hours) ' i FIGURE 4.
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Emergency Impicmentation Procedures . 1 Revision Sheet i TITLE: Environmental Assessment, EI-10 Revision PRC Date Approved by Gen. Manager 0 11/19/80 88 * !I* 1 12/5/80 isloo/Po 2 2/4/81 #1 %l 3 9/2/81 SEP1 / 19 81 o-l l l i ( O -. f
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O b EMERGENCY IMPLEMENTATION PROCEDURE EI-10 ENVIRONMENTAL ASSESSMENT
\ Rev 3 1.0 PERSONNEL RESPONSIBILITY
- 1. The Chemistry / Health Physics Superintendent or Plant Health Physicist is responsible for dispatching the monitoring teams.
- 2. The Radiation Protection Technicians are responsible for collecting any samples, having the samples properly analyzed and reporting accurate data to the Technical Support Center.
2.0 PURPOSE Provide guidelines for the following during emergency conditions:
- a. Collection and replacement of environmental TLD's.
- b. Obtaining data from environmental air monitoring stations.
- c. Assessment of liquid releases to Lake Michigan.
- d. Obtaining water / milk / vegetation samples.
/,x. 3.0 ATTACHMENTS AND RECORDS D)
- 1. Attachment 1, Environmental TLD Placement i 2. Attachment 2, Air Monitor Sample Collection Sheet i
- 3. Attachment 3, Miscellaneous Radiological Environmental Samples
- 4. Attachment 4, Environmental Data
- 5. . Attachment 5, Table 1 Garden, Cow and Goat Locations 4.0 SPECIAL INSTRUCTIONS The decision to change TLD's and collect samples from environmental l air sampling stations will require knowledge of expected dose rates l under prevailing meteorological conditions.
5.0 PROCEDURE 5.1 Collection and replacement of environmental TLD's and collection of environmental air sample station samples. 5.1.1 Determine, using current meteorological data, the downwind sectors from which the environmental samples will be retrieved. The downwind
-( sectors should include the one directly downwind and the sector on (J ) either side.
l 5.1.2 Mark the collection points on the Envitqpmental Sample Location Map (Attachment 1). - pa1180-0008a-89 1
Emerg;ncy Impler:ntation Procedure EI-10, Rev 3 Environmental Assessment s 5.1.3 Determine the safest routes to the sample points and designate them (O on the map'. The safest route is that which keeps the Offsite Monitoring Team out of the plume as much as possible. 5.1.4 After the Team has been dispatched, continually monitor wind direction in the event it changes and the predetermined travel routes and sample collection points must be changed. 5.1.5 Designate the Team that will retrieve the samples and instruct the team members as follows:
- 1. They are to proceed to the designated sample collection points via the predetermined safest route.
- 2. Radio communication is to be kept open at all times in case sample collection points and travel routes change.
5.1.6 The Team will gather the following equipment: (Equipment may be available in emergency response vehicle.)
- 1. TEDA iodine cartridges in sufficient quantity to replace those that are to be collected.
- 2. TLD's designated for emergency environmental sampling in sufficient quantity to replace those that are to be collected.
- 3. Air particulate filters in sufficient quantity to replace those that are to be collected.
- 4. Sufficient Ziplock Bags such that each TLD, air particulate filter, and iodine cartridge can be kept separate in order to prevent cross contamination and allow for better accountability.
5.1.7 Collection of TLD's.
- 1. Each station contains three TLD's.
l 2. Af ter activation of the Emergency Plan for accidents involving l the release of radioactive material, one TLD at each station I will be replaced daily (for example, on the first day, TLD 1 will be replaced by TLD 4, on the second day, TLD 2 will be replaced by TLD 5, etc). Place the removed TLD in a Ziplock Bag and record the following on the envelope:
- a. Location of the TLD 1
b. Date l c. Time collected l d. TLD number
~.
pa1180-0008a-89 2 1 l M
r_ Emergency Implementation Procedure EI-10, Rev 3 Environmental Assessment s o
- 3. TLD's will be changed daily until discontinued by the Plant Health Physicist or his designated representative.
- 4. TLD's removed during accident conditions will be collected at the Emergency Operations Facility in South Haven.
5.1.8 Collection of air particulate filters and iodine cartridges.
- 1. Turn off the air sampler motor, remove and disassamble the filter assembly.
- 2. Remove the air particulate filter from the metal-backing screen ,
being careful not to tear the filter and place it in an envelope. Record the following on the Ziplock Bag:
- 1. Location
- 2. Date and time
- 3. Volume meter reading
[) s_ c
- 3. Remove the iodine cartridge from the cartridge holder and place it in an envelope.
Record the following on the Ziplock Bag:
- 1. Location
- 2. Date and time
- 3. Volume meter reading
- 4. Place a new filter on the metal back screen with the filter's rough side facing the 0-ring.
- 5. Place a new iodine cartridge in the holder.
- 6. Reassemble the filter holder assembly and reinstall device into the air sampler.
- 7. Turn on the air sampler.
- 8. Record the necessary information on Attachment 2 and have the samples analyzed.
?
pa1180-0008a-89 3
Emergency Implementation Procedure EI-10, Rev 3 Environmental Assessment n 5.2 Liquid and Atmospheric Release Sampling 5.2.1 Following a major liquid or atmoshperic release, initiate collection of environmental samples. These samples may include but are not limited to:
- 1. Collect two (2) gallon samples of milk from the dairy herds listed on Attachment 5 and have the samples analyzed. Record required information on Attachment 3. .
- 2. Collect a one liter sample of representative vegetation (including crops in season) within a 15 mile radius of the plant. Record the required information on Attachment 3 and have the samples analyzed.
- 3. Collect one liter samples from the South Haven Water Treatment Plant (treated and untreated). Record the required information on Attachment 3 and have the samples analyzed.
- 4. Collect one liter samples from Lake Michigan at the shore in the plume sector and the sector on either side. Record the required information on Attachment 3 and have the samples analyzed.
5.2.2 Prior to sending environmental samples offsite for analysis, perform a gross contamination check. If analysis is performed on site, record the sample data on At.tachment 4.
'O pa1180-0008a-89 4
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\ ATTACHMENT I PALISADES PLANT ONSITE ENVIRONMENTAL THERM 0 LUMINESCENT DOSIMETERS NOTE: All stations consist of a conic weather cap suspended approximately 5 ft from ground on a large (8" dia) tree.
STATION CODE LOCATION
#1 (ST) 500 ft east of main gate along Access Road, 25 ft south off edge of road.
#8 (SP) North of plant along Dump Road to property line. As road turns west, station located 10 ft north of road.
#13 (ST) Past #8 along Dump Road. Proceed west up dune path at right of Containment Test Structure.
At first crest, turn north and proceed up adjacent hill to #13 at top (approx 50 yds from 2 crest).
#14 (ST) Along Dump Road to point where fence divides old Blue Star Hwy, 25 yds to east of road.
#15 (ST) North along Blue Star Hwy, 0.75 miles from Access Road, 10 ft off west side of road.
#16 (ST) North along Blue Star Hwy, 0.4 miles from Access Road, 50 ft off west side of road.
#17 (ST) Along Access Road 25 yds south of southern most power line, 15 yds off east side of road.
#18 (ST) 20 yds from Access Road along south road.
40 yds off south side of south road.
#19 (ST) 0.2 miles along south road from Access Road, 30 ft off north side of road.
#20 (ST) 0.4 miles along south road from Access Road, 20 ft off south side of road.
#21 (ST) 0.7 miles along south road from Access Road, 5 ft off east side of road.
v pa1180-0008c-89 -
, EI-10 Rev 3
\ Page 3 s ATTACHMENT 1 PALISADES PLANT :
AIR SAMPLER AND OFFSITE TLD LOCATIONS NOTE: All Air Samplers are mounted in a blue, steel box and suspended on- < telephone poles approximately 6 ft off the ground. They are supplied with 1/10 v electric current. f STATION CODE LOCATION I
#1 (ST) Mounted onsite, 500 ft east of main gate.
- 25 yds south of Access Road next to well.
#2 (TH) Along 48th Ave, 500 ft east of 80th St, 25 ft off north side of road.
#3 (HS) Along 48th Ave, 1/4 mile west of 76th St. In 4
barnyard 50 yds off north side of road.
#4 (JS) Along 36th Ave, 1/2 mile east of M-140. 15 ft off south side of road.
; #5 (PR) Along 30th Ave, 3/4 mile east of M-140, 30 ft off north side of road.
#6 (RB) Along 12th Ave, 1/4 mile west of M-43. 30 ft off south side of road.
l #7 (SD) Along Phoenix Road, directly behind Sherman i Diary. 1/4 mile east of I-196 and Phoenix Road on north side. i~
#8 (SP) Onsite along the dump road, north of Plant.
j 1 mile from main gate. Near State Park j boundary, on north side of road as road turns west.
#9 (TP) Along 32 Ave, 1/4 mile west of Blue Star. 5 ft off south side of road.
I I pa1180-0008c-89 . i -
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b ;'t ATTACHMENT 1 (: PALISADES PLANT Location of Accident TLD'S R1 2 Mile Ring
- 1. Utility pole on south side of road near west end of 20th Avenue.
- 2. Post on east side of Blue Star Hwy, approximately 1.5 miles north of Plant access road.
- 3. Utility pole on northwest corner of 76th St and 24th Avenue.
- 4. Utility pole on west side of 76th St - 0.5 miles south of 24th Avenue.
- 5. Utility pole on southeast corner of 76th St and 28th Avenue.
- 6. Utility pole on south side of road 0.25 miles east of torner of 77.5th St and 30th Avenue.
h N.2
. Utility pole on northwest corner of 77.Sth St and 32nd Avenue.
- 8. Utility pole on northeast corner of 32nd Avenue and Blue Star Hwy.
- 9. Beneath enviromnental air sampler - approximatel3 0.25 miles west of Blue Star Hwy on 32nd Avenue.
R2 5 Mile Ring
- 10. Utility pole on southwest corner of Blue Star Hwy and M-140.
- 11. Utility pole on northeast corner of M-43 and CR 384.
- 12. Utility pole on south side of 20th Avenue - 0.5 miles west of 69th St.
- 13. Utility pole on south side of 26th Avenue - 0.5 miles west of 69th St.
- 14. Utility pole on southeast corner of 70th St and 34th Avenue.
i
- 15. Utility pole on west side of M-140 - 1.0 miles south of 38th Avenue.
- 16. Utility pole approximately 100 yards north of corner of CR 376 and 76th St.
! 17. Utility pole on southwest corner of CF 376 and 80th St.
- 3. Utility pole on southeast corner of CR 376 and 82nd St - approximately 75
\ yards east of Blue Star Hwy.
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\4 EI-10 Rev 3 e?
I Page 6 /\ " 1 ATTACIDfENT 1 ~'. - ' s Date Received:
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EI-10
, Rev 3 s Page 1 ATTACHMENT 5 r.
\s PALISADES PLANT TABLE 1
. Distance to the nearest resident, garden, beef cow, dairy cow and goat in each sector.
SECTOR RESIDENCE GARDEN
- BEEF C0W
- DAIRY COW GOAT N >5 mi >5 mi >5 mi >5 mi >5 mi NNE 1.5 mi 1.5 mi >5 mi >5 mi >5 mi NE 1.75 mi 1.75 mi 3.75 mi 2.9 mi >5 mi ENE 1.5 mi 1.5 mi 3.2 mi 3.2 mi >5 mi E 1.0 mi 1.9 mi 3.3 mi 3.3 mi >5 mi ESE .9 mi 1.0 mi 3.9 mi >5 mi 3.0 mi SE .9 mi 1.2 mi 4.3 mi 4.3 mi >5 mi SSE .75 mi .75 mi >5 mi >5 mi 3.75 mi S .7 mi 4.5 mi 4.8 mi 4.8 mi >5 mi SSW .75 mi 1.5 mi >5 mi >5 mi >5 mi-
- NOTE: A cow of undetermined nature is classified as both a beef cow and a dairy cow.
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g rgency Implementation Procedures _ Revision Sheet TITLE: Determination of Extent of Core Damage, EI-11 i Revision PRC Date Approved by Gen. Manager ,
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s p EMERGENCY IMPLEMENTATION PROCEDURE EI-11 Uls DETERMINA"' ION OF EXTENT OF CORE DAMAGE 1.0 PERSONNEL RESPONSIBILITY The Control Room Operators supported by members of the Technical Support Center Staff are responsible for performance of this procedure. 2.0 PURPOSE To provide a method of estimating the degree of core damage during accident conditions. , 3.0 ATTACHMENTS AND RECORDS
- 1. Attachment 1, Dose Rate vs Time for Control Room Entrance Monitor **RE-2310'
- 2. Attachment 2, Dose Rate vs Time for Containment Monitor
**RE-1805
- 3. Attachment 3, Dose Rate vs Time for Containment Monitor
**RE-1806
- 4. Attachment 4, Dose Rate vs Time for Containment Monitor
**RE-1807
- 5. Attachment 5, Dose Rate vs Time for Containment Monitor
**RE-1808
- 6. Attachment 6, Data Sheet for Determining Extent of Core Damage 4.0 SPECIAL INSTRUCTIONS The -attached tables are based on equilibrium core activities and Reg Guide 1.4 release rates.
NOTE: Depending on core life and operating history at time of i accident, these tables may give conservative results. l ! 5.0 PROCEDURE I 5.1 ESTIMATING EXTENT OF CORE DAMAGE FROM CONTROL ROOM AREA MONITORS 5.1.1 Determine the dose rate from the Control Room entrance radiation monitor. This monitor appears as recorder point No 11 on the area i radiation monitor strip chart recorder (**RR-2302 ). 5.1.2 Absolute dose rate is determined by subtracting normal background (#11 reading before time of accident) from the dose rate after accident occurs. (s-) pa0780-0012a-89 1 " l
Emergency Implementation Proczduro EI-11 D: termination of Extent of Core Damage s O h-5.1.3 Use curves in Attachment 1 to determine percent fuel failed. If point determined is between two curves, state results as between the two curves (ie. , 10-50%). 5.1.4 Record results on Data Sheet, (Attachment 6), and submit it to Plant Health Physicist and Site Emergency Director for review. 5.2 ESTIMATING EXTENT OF CORE DAMAGE FROM CONTAINMENT AREA MONITORS 5.2.1 Determine dose rate from monitors **RIA-1805, **RIA-1806, **RIA-1807,
**RIA-1808. These monitors appear as follows on strip chart recorder
**RR-2302.
RIA No Recorder Point No
**RIA-1805 19
**RIA-1806 20
**RIA-1807 21
**RIA-1808 22 Find absolute dose rate by subtracting normal background (See Step 5.1.2).
5.2.2 Use appropriate curves in Attachments 2-5 to determine core damage estimate for each reading taken and average the values. 5.2.3 Record results on data sheet and submit for review by Heilth Physicist and Site Emergency Director. l 4 pa0780-0012a-89 e 2 '
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EI-11 Rev 0
,~ ~ Pag'e 1 ATTACHMENT 6 (V'!
\ DATA SHEET FOR DETERMINING EXTENT OF CORE DAMAGE Time (Post Accident) Monitor l Dose ' % Failed Hours, Days Number l Data Determined Rate f Fuel !
By i I e , 1 l i i I l i
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( w () c. (sa) Reviewed by Health Physicist pa0780-0012b-89 Reviwed by Site Emerg Director e
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Emergency Implementation Procedures '~') s._/ Revision Sheet N E- Personnel Accountability, EI-12 _ Revision PRC Date Approved by Gen. Manager 0 11/19/80 N # 1 4/8/81 gg g/hf 2 2/4/82 .k-p 04 W 3 \ 3/9/82 gg g 3 g $ m o' <z e
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\ EMERGENCY IMPLEMENTATION PROCEDURE EI-12 N PERSONNEL ACCOUNTABILITY Rev 3 1.0 PERS(NNEL RESPONSIBILITY 1.
The Property Protection Supervisor has overall responsibility for assuring accountability of all individuals onsite. 2. The assembly area leaders for each assembly area are responsible for accountability at that area and reporting results to the Property Protection Supervisor, 2.0 PURPOSE To provide guidelines for personnel accountability after personnel onsite have been directed to proceed to their designated assembly areas. 3.0 ATTACHMENTS AND RECORDS 1. Attachment 1, Assembly Areas and Personnel Assignments
- 2. Attachment 2, Assembly Area Personnel Lists g)
( 4.0 SPECIAL INSTRUCTIONS q 1. Personnel Accountability should be complete within 30 minutes. 2. The Plant Health Physicist should dispatch personnel to the Security Building to ensure that contaminated personnel are segregated. 5.0 PROCEDURE 5.1 Onsite individuals, when notified, shall proceed to their designated assembly areas where personnel accountability checks will be conducted. Personnel assignments for each assembly area are given in Attachment 1. 5.1.1 Emergency Kits are stored in the Technical Support Center and Operations Support Center. Upon arrival at the assembly areas, personnel will be designated by the Chemistry / Health Physics Superintendent or Plant Health Physicist to perform radiation surveys of the area to ensure radiation levels allow assembly. 5.1.2 Supervisors shall be responsible for knowing the location of those personnel not able to report to their designated assembly areas. 5.2 Assembly Area leaders are responsible for accountability at their 7' s) assigned assembly area. NJ' eio780-0016a154-154 1 ~
Emerg:ncy Implementetion Proc dure EI-12, R;v 3 Personnel Accountability s 5.2.1 The Personnel Accountability Checklist for each assembly area is 9 located on a wall within that area and will be completed by the assembly area leader. 5.2.2 Completed Personnel Accountability checklists will be sent to the Property Protection Supervisor in the Security Building if radiologically feasible. 5.2.3 If not radiologically feasible, report personnel accountability to the Property Protection Supervisor or Site Emergency Director by telephone or intercom. 5.3 The Property Protection Supervisor will verify the list of personnel within the protected area by comparing the Personnel Accountability Checklist to the personnel badges within the protected area. If necessary, a iisting of personnel within the protected / vital area may be obtained. 5.3.1 If an Unusual Event or Alert has been declared, the switchboard operator shall be permitted to return to the switchboard to coordinate incoming and outgoing calls. 5.3.2 If a Site or General Emergency has been declared, the switchboard s operator shall be required to evacuate with all other non-essential personnel. 5.4 A list of esecrted visitors and a list of badged individuals not employed at Palisades will be supplied to the Property Protection Supervisor by the Searchguard to verify the accountability of these individuals. 5.5 After verifying the accountability list, the Property Protection Supervisor shall ensure, if radiological conditions permit, that the list is delivered to the Site Emergency Director in the TSC. 5.5.1 If conditions do not permit delivery of the accountability list, the Property Protection Supervisor shall report the results of the accountability check to the Site Emergency Director. l 5.6 Personnel at the assembly areas will remain at the assembly areas until:
- 1. Directed to return to their work area
- 2. Directed to evacuate
- 3. Directed by the assembly leader or alternate ei0780-0016a154-154 2 Proofread by: di/b '
J ( - -
r s EI-12 s Rev 3 , Page 1 ATTACHMENT 1
~
ASSEMBLY AREAS AND PERSONNEL ASSIGNMENTS
- 1. The assembly area locations, personnel in charge and those personnel
- assigned to each area are
- a. Assembly Area I* (Control' Room) 1 1. Shift Supervisor (in charge)(on shift)
- 2. Shift Technical Advisor (on shift) i
- 3. Control Operators (on shift)
- 4. Auxiliary Operators (on shift)
- 5. Operations Supervisor
- 6. Reactor Engineer 1
NOTE: The Shift Supervisor controls access to the Control Room and has the responsibility for restricting access. j b. Assembly Area II* (Technical Support Center - SS Office Area / Viewing Gallery)
- 1. General Manager (in charge) 1
- 2. Operations and Maintenance Superintendent (first alternate)
- 3. Technical Superintendent (second alternate)
- 4. Technical Engineer (s) (third alternate (s)) t 1
- 5. Operations Superintendent
- 6. Maintenance Superintendent
- 7. Chemistry / Health Physics Superintendent or Health Physicist
- 8. Senior Engineer ,
I
- 9. Chemical Engineer
, 10. Instrument and Control Engineer
- 11. Maintenance Engineer 4
l (5s i \. / ei0780-0016bl54-154 -
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EI-12 Rev 3 s Page 2 ATTACHMENT 1 ASSEMBLY AREAS AND PERSONNEL ASSIGNMENTS
- c. Assembly Area III* (Operations Support Center, Area 2 - Service Building Addition, Conference Rooms 3 and 4)
- 1. Senior Member from Technical Group
- 2. Environmental Supervisor (first alternate)
- 3. Administrative Supervisor (second alternate)
- 4. Maintenance Supervisors
- 5. Document Control Supervisor
- 6. Material Services Supervisor
- 7. Quality Control Supervisor
- 8. Building and Grounds Supervisor
- d. Assembly Area IV* (Conference Area of Document Control) )
- 1. Senior Member from Technical Group
- 2. Engineers / Technologists
- 3. Quality Assurance Superintendent (first alternate)
- 4. Quality Assurance Engineers i
- 5. Quality Control Inspectors l
- 6. Clerks
- 7. Personnel Director / Assistant (second alternate)
- 8. Controller / Assistant
- 9. Buildings and Grounds Personnel l
O_. eio780-0016bl54-154 ' l 1
EI-12 x s Rev 3
. Page 3 ATTACHMENT 1 ASSEMBLY AREAS AND PERSONNEL ASSIGNMENTS e.
Assembly Area V* (Operations Support Center, Area 1 - Lunchroom) 1. Radiation Protection Supervisor (in charge) 2. Instrument and Control Supervisor (first alternate)
- 3. Chemistry Supervisor (second alternate)
- 4. Chemistry / Radiation Protection Technicians ~
- 5. Instrument and Control Technicians f.
Assembly Area VI* (Operations Suppor Center, Area 3 - Main Locker - Room) i 1. Assistant Maintenance Supervisor (s) (in charge)
- 2. Assistant Maintenance Supervisor (s) (alternate (s))
m
) 3. Repairmen .
- 4. Stockmen
- g. Assembly Area VII* (Training Center)
- 1. Training Center Coordinator (in charge)
- 2. Training Department Personnel 3.
Fifth Shift Trainees (Shift Supervisor first alternate, COI second alternate) 4 Personnel arriving onsite (oncoming shift personnel will initially report to this area for briefings and further assignment)
- h. Assembly Area VIII* (Security Building)
- 1. Property Protection Supervisor (in charge) 2.
Post Ccaimander (first alternate) I 3. Shift Lieutenant (second alternate) 4. Security personnel (as specified in the Security Plan and Security Implementing Procedures)
\)
eio780-0016bl54-154
- EI-12 Rev 3 s Page 4 ATTACHMENT 1 ASSEMBLY AREAS AND PERSONNEL ASSIGNMENTS '
- i. Assembly Area IX* (Main Parking Lot)
- 1. Property Protection Advisor (in charge)
- 2. All site visitors
- 3. All Construction personnel NOTE: The person in charge of each assembly area may reassign personnel in his area to the particular requirement of the situation. The personnel assignments for each Assembly Area are intended for the initial manning of these areas.
t I I ' l i l l l s_ ei0780-0016bl54-154 '
1 EI-12 Rev 3 Page 1 ATTACHMENT 2 s ASSEMBLY AREA PERSONNEL LISTS 1.0 PERSONNEL RESPONSIBILITY The Health Physics Clerk is responsible for implementing this procedure. 2.0 PURPOSE a To aid in performing the assembly area accountability check by providing names to go with the generic titles in Emergency Plan Implementation Procedure EI-12, Personnel Accountability. !~ 3.0 ATTACHMENTS AND RECORDS / None 4.0 SPECIAL INSTRUCTIONS None 5.0 PROCEDURE
, 5.1 PREPARATION OF LISTS
's, 5.1.1 Using the Assembly Area manning requirements for Assembly Areas I - VI, the Health Physics Clerk will place names next to each title for the six assembly areas. This allows the Assembly Area leader to know more accurately which people are in their area.
5.2 REVIEW 5.2.1 At least quarterly the Health Physics Clerk will verify the accuracy of
- the Assembly assembly areaArea lists.lists and make the changes necessary to update the Q
4;_ e ei0780-0016c154-154 '
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Emergency Implementation Procedures Revision Sheet TITLE: ""* "' ****** 7' Revision PRC Date Approved by Gen. Manager 0 10/30/80 h g)lyffs 1 4/8/81 (ff 4lH 2 4/5/82 My APR 15 last Ot .. Q 4
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, EMERGENCY IMPLEMENTATION PROCEDURE EI-13
\ EVACUATION, REASSEMBLY Rev 2 1.0 PERSONNEL RESPONSIBILITY The Site Emergency Director 'is responsible for directing avacuation of and reassembly at -Palisades Plant.
2.0 PURPOSE To provide _ guidelines to be implemented in event of evacuation and subsequent reassembly of personnel onsite. 3.0 ATTACHMENTS AND RECORDS
- 1. Attachment 1, Evacuation Routes
- 2. Attachment 2, Evacuation Message 4.0 SPECIAL INSTRUCTIONS
- 1. Evacuation of personnel occurs from their designated assembly areas.
~'
- 2. Reasons for evacuation include:
- a. Personnel Safety
- b. High radiation levels (100 mr/hr in assembly areas and 5 R/hr in the Control Room)
- c. High airborne radiation levels
- d. Evacuation of nonessential personnel should be performed at
' Site Area Emergency and above.
5.0 PROCEDURE 5.1 Assembly Area Evacuation 5.1.1 Nonessential personnel should be evacuated from assembly areas when radiation levels at the assembly areas exceed 100 mr/hr or when a Site Area Emergency or above is declared.
- 1. The Site Emergency Director (SED) shall designate the personnel required to stay in the TSC. These personnel should enter the Shift Supervisor's office and close the door, placing them under the Control Room habitability specifications.
- 2. The remainder of the personnel sl.all proceed to the Operations Support Center (OSC).
C) ei0780-0013a154-93 "
Emergency Implem ntetion Proccdure EI-13, Riv 2 2 Evacuation, Re. assembly l
- 3. If the TSC and OSC are not habitable, the TSC and OSC should be transferred to the Feedwater Purity Building Control Room.
~
- 4. If the Feedwater Purity Building becomes uninhabitable, the SED shall designate the alternate TSC/OSC location (s). ;
l 5.1.2 Control Room personnel r, hall be evacuated when the radiation levels exceed 5 R/hr as directed by the Site Emergency Director. 5.2 The Plant Health Physicst shall determine which of three evacuation routes from the Palisades Plant shall be used after the order to evacuate is given by the Site Emergency Director. 5.2.1 The Plant Health Physicist shall notify Security and Radiation Safety of the route to be used. The Plant Health Physicist shall assign personnel to the appropriate control point and monitoring station. 5.3 Evacuation via the Plant Access Road 5.3.1 Radiation Safety and Security shall establish a control point in the Security Building. Personnel evacuating from inside the protected area (security fence) shall do so in the following manner:
- 1. Proceed to the Security Building.
- 2. Drop off security badge.
- 3. Proceed to access road control point / monitoring station (private vehicle may be used).
5.3.2 Personnel outside the protected area shall proceed to the access road control point / monitoring system (private vehicle may be used). 5.4 Evacuation via the beach to the North 5.4.1 Security shall open the north beach gate and station an officer at the gate. Radiation Safety and Security shall establish a control point at the north beach gate. 5.4.2 An alternate route of evacuation is via the beach to the North. Evacuation for personnel inside the Protected area shall be completed in the following manner:
- 1. Proceed to the north beach gate.
- 2. Give security badge to the security officer on duty.
- 3. Proceed north along the beach front to the walkway in Van Buren Park.
e, ei0780-0013a154-93 ' o
7 Emergency Implementat; ion Procedure El-13, R'ev 2
-Evacuation,' Reassembly -- , 3 p , _
() 7 4. Proceed.to the personnel monitoring station in the parking lot at Van Buren State Park. 5.4.3 Personnel outside the protected area shall evacuate as follows: 1. cFollow the north protected area fence to the beach. 2. Proceed.to monitoring station with personnel from inside the protectedJarea. 5.5 Evacuation via the Beach to the Sout!i 5 . 5 .1 ' Security shale ope'n the gates to the south radwaste storage area and
.the south beach = gate. Radiation Safety and Security shall establish a control point at the inner gate to the south radwaste storage area.
- 5. 5. 2-Personnel evacuating from within the protected area via the beach to the south shall do so in the following manner:
~
- 1. Proceed to the south beach gate through the south radwaste storage area.
- 2. Give security badge to the security officer stationed at the inner gate to the south radwaste storage area.
(..( 3. _ Proceed south along beachfrort to the Covert Township Park.
- 4. ' Proceed to the monitoring _ station in the parking lot of the Covert Town' ship' Park.
5.5.3 Personnel outside ' the protected area.shall evacuate the plant site as follows: 1 1. Using the cooling tower access road, proceed to the south gate.
- 2. Proceed to the beach.
- 3. Proceed to the personnel monitoring station with the personnel fron inside the protected area.
5.6 Monitoring- of Evacuees 5.6.1 Personnel arriving at the monitoring station shall be questioned and dosimeters read to determine any case of high external exposure; personal dosimetry shall be collected. 5.6.2 Personnel and/or vehicles shall be monitored to determine the need for decontamination. '
- 1. The priority for decontanination shall be given to persons found U
to have the highest levels of contamination. eio780-0013a154-93 ' 4
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Emerg:ncy Implementation Procedura EI-13, R:v 2 4 Evacuation, Reassembly s 9'
- 2. Vehicles shall be decontaminated af ter personnel decontamination is complete.
5.6.3 Persons suspected, or known, to have injested substantial radioactivity shall be wholebody counted and/or have a bioassay program established as soon as conditions permit. 5.7 Reassembly 5.7)1 For the duration of the emergency, personnel sent home on call or informed while home that they are on call, shall be available as needed during recovery. The following schedule shall be followed:
- 1. Supervisors in the various departments should be on a 12-hour shift rotation.
- 2. Management personnel shall be on a schedule as determined by the Site Emergency Director.
- 3. Personnel other than management and supervisors should be assigned an eight hour shift. The rotation and amount of time spent offsite is determined at the time of the emergency and shall be dependent upon the type and cause of the emergency. ~3
- 4. Control Room personnel should maintain their normal shift rotation.
5.7.2 Supervisors / management should attempt to arrange shift rotation such that the relieving of shifts does not occur simultaneously. 5.7.3 Personnel on shif t rotation shall be informed of their individual shift assignmeats. l l l l l l l i l l ei0780-0013a154-93 Proofread by: [d( l [d,- v -
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. 1 EVACUATION ROUTES ,
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- 1. Preferred Method
- 2. Evacuation to the North y I
- 3. Evacuation to the South **
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EI-13 s Rev 2 Page 1
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ATTACHMENT 2 Evacuation Message The following message will be used to evacuate the site. Fill in the blanks as conditions warrant. Personnel in Assembly Area (s)
- a. I Control Room
- b. II Technical Support Center
- c. III Operation Support Center Area 2 - Service Building Addition, Conference Rooms 3 & 4
- d. IV Conference Area Document Control
- e. V Operations Support Center Area 1 -
Lunchroom
- f. VI Uperations Support Center Area 3 - Main Locker Room
- g. VII Training Center
- h. VIII Security Building
- i. IX Main Parking Lot will evacuate using the (Note: See Plant Health a. Access road Physicist for proper b. North beach evacuation route) c. South beach and
- a. Reassemble at the training facilities on Blue Star Highway
- b. Reassemble at the Emergency Operations I Facility
- c. Go home
! Assembly evacuation. Area Leaders will contact the Emergency Operations Facility after l Q ei0780-0013c154-93 -
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l l Emergency Implementation Procedures 1 i ( ) _ Revision Sheet s .- Radiological Medical Care, EI-14 Revision PRC Date Approved by Gen. Manager 0 t
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s-p Q 3, EMERGENCY IMPLEMENTATION PROCEDURE EI-14 RADIOLOGICAL MEDICAL CARE 1.0 PERSONNEL RESPONSIBILITY 1. Plant Health Physicist or Radiation Protection Supervisor has overall responsibility for radiation exposure control and mitigation. 2. Radiation Protection Technicians - carry out decontamination procedures, conduct inventories of equipemnt and supplies. 2.0 PURPOSE 1. Describe emergency radiation exposure limits. 2. Describe personnel decontamination procedures. 3. Describe the method for use of thyroid blocking agents. 4. Describe the method for transporting contaminated victims to hospitals. 3.0 ATTACHMENTS
/T _ None bk 4.0 SPECIAL INSTRUCTIONS 1.
Contamination over 5,000 cpm and internal contamination (mouth, nose, skin breaks) shall require notification of the Plant Health Physicist or Radiation Protection Supervisor. 2. Chemicals other than soap and water shall not be used other than under the direction of the Plant Health Physicist, Radiation Protection Supervisor, or Physician. 3. Care and body mustskin be openings. taken not to spread contamination, especially to 5.0 PROCEDURE 5.1 EXTERNAL DECONTAMINATION 5.1.1 Wash with warm water in sink or shower depending on the area contaminated, j 5.1.2 Lather with E-Z Scrub pad (or shampoo). 5.1.3 Rinse area.
) 5.1.4 Blot dry.
1 4. pa1180-0006a-89 ~< e a
Erergency Implementation Procedure EI-14 Radiological Medical Care s 5.1.5 If contamination is still present, repeat above steps, not exceeding three showers. 5.1.6 Notify the Plant Health Physicist or Radiation Protection Supervisor of any difficulties encountered. 5.2 EYE CONTAMINATION - FLUSH WITH WATER 5.3 NASAL /0RAL CONTAMINATION - SWAB AFFECTED AREA WITH DAMP Q-TIP 5.4 INJURY CONNECTED CONTAMINATION 5.4.1 In cases of serious injury, immediate lifesaving first aid should be undertaken before decontaminatiou is attempted. 5.4.2 Contaminated clothing should be removed, and decontamination carried out before the ambulance removes the victim. 5.5 TRANSPORTATION OF INJURED / CONTAMINATED PERSONNEL 5.5.1 Determine appropriate transportation mode private or company vehicle, ambulance. 5.5.2 Carry out decontamination procedures. . 5.5.3 Obtain supplies to protect the interior of the ambulance - plastic, blotter paper, tape. 5.5.4 Furnish protective clothing and respirators to ambulance crew. 5.5.5 Accompany the victim to the hospital, and assist in radiological monitoring and contamination control. 5.5.6 Plant personnel will assist the ambulance and hospital in decontaminating their areas and equipment and in disposing of waste. 5.6 EMERGENCY WORKER RADIATION EXPOSURE LIMITS 5.6.1 Whole body dose for non-lifesaving actions. - 25 rem. 5.6.2 Whole body dose ^for lifesaving actions: State of Michigan - 75 rem. 5.6.3 Thyroid dose for non-lifesaving actions - 125 rem. 5.6.4 Thyroid dose for lifesaving actions - no upper limit specified. 5.6.5 General public exposure - no more than 5 rem; should be kept below 500 mrem. t O pa1180-0006a-89 -
Emergency Implementation Procedure EI-14 Radiological Medical Care
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5.7 USE OF THYROID BLOCKING AGENTS 5.7.1 Sampling of airborne iodine concentrations will be in accordance with EI-8. 5.7.2 If radioiodine-concentrations exceed 1.0E-7uci/cm thyroid blocking agents (located in Emergency Kits) will be dispensed to exposed personnel. a. the blocking agent is in the form of 130 mg potassium iodine (KI) tablets and will be taken at the rate of one tablet each day for 10 days.
- b. Substitute blocking agents are available from the Plant Health Physicist for personnel having known allergies to iodine (shellfish, etc) or who exhibit side effects from the potasium iodine. -
c. Personnel are not required to take the blocking agents. i l l l l l l l l I l [ ,
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- Emergency Impl_ementation Procedures Revision Sheet
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TITLE: Training and Drills, EI-15 1 Revision PRC Date Approved by Gen. Manager
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EMERGENCY IMPLEMENTATION PROCEDURE EI-15 A TRAINING AND DRILLS REV 1 1.0 PERSONNEL RESPONSIBILITY 1. The training coordinator or his designated representative is responsible for scheduling all training programs and the maintenance of all training documentation. 2. The Plant Review Committee and the SARB are responsible for the review of critiques of the drills. 3. The Chemistry / Health Physics Superintendent is responsible for approving the drill scenario. 2.0 PURPOSE 1. To establish training requirements to assure that personnel involved during an emergency situation are familiar with their duties and responsibilities.
- 2. To detail the requirements for drills and exercises which test the efficiency of the emergency plan.
3.0 ATTACHMENT AND RECORDS
- 1. Attachment 1, Emergency Plan Training
- 2. Attachment 2, Drill Observer Assignment Sheet
- 3. Attachment 3, Exercise Evaluation Criteria 4.0 SPECIAL INSTRUCTIONS None 5.0 PROCEDURE 5.1 TRAINING 5.1.1 Training Programs will be conducted for both onsite and offsite organization in accordance with Section 8 of the Palisades Plant Emergency Plan, " Maintaining Emergency Preparedness".
5.1.2 The training coordinator is responsible for s.cheduling all training programs and maintenance of all training documentation. 1. The training coordinator may delegate the training fS responsibilitier to those personnel most qualified to perform
< that particular aspect of training.
ei0780-0014a154 1 "
{ Emerg ncy Icplementatica Proc: dure EI-15, Rev 1 Training and Drills s
- 2. All Emergency Plan Training designees are responsible for 9
ensuring that their assigned tasks are performed in accordance with specified procedures, are documented properly, and upon completion, results are forwarded to the Training Coordinator. 5.1.3 Lesson plans or outlines will be provided for each instructor's program and the designated instructor will be responsible for identifying and correcting weak areas within the program. 5.1.4 All onsite Palisades Plant staff and persons listed in Attachment I will be required to atterd, on an annual basis, a training session on the Emergency Plan. 5.1.5 The Emergency Plan Training Program is intended to give all personnel assigned to the Palisades Plant Emergency Organization a thorough knowledge of the Emergency Plan and implementing procedures. 5.1.6 Emergency Plan Training is divided into several modules with the applicable modules being taught to appropriate groups. The course content for each module is indicated in Attachment 1. 5.1.7 Emergency Plan Training will also be provided for appropriate contract personnel as deemed necessary by the Training Coordinator. 5.1.8 Outside agencies that have letters of agreement with Palisades Plant and media agencies as indicated in Palisades Plant Site Emergency Plan, shall be invited on an annual basis to participate in one of the Emergency Plan Training Programs. 5.2 DRILLS AND EXERCISES 5.2.1 Drills are tests of individual components of the emergency organization. Examples of drills and their frequency are:
- a. Communications drills to verify the operability and adequacy of primary and backup communications links, and to demonstrate the capability to warn the public of an emergency. These drills will be conducted with the County and State Emergency Operations Facilities annually.
- b. Emergency medical drills (first aid and decontamination) and radiological monitoring drills will be conducted annually.
5.2.2 Exercises are tests of all the components of the emergency organization. An exercise will be conducteed at least annually. Such exercises should include the activation of the local / state emergency organizations. Exercises may be observed by NRC monitors. O ei0780-0014a154 2 '
Emergency Implementation Procedure EI-15, Rev 1 Training and Drills a ' U s 5.3 PLANNING 5.3.1 Determine the type of exercise to be held and the date and time for the exercise. 5.3.2 Develop the scenario for the exercise. 5.3.3 The ccenario will be forwarded to the Chemistry / Health Physics Superintendent for review and approval. 5.3.4 Personnel who will act as observers during the course of the exercise shall be assigned and the Drill Observer Assignment Sheet completed. (Attachment 2) 5.3.5 A Pre-Freccise Meeting will be held to brief observers on the scope, sequence of eveues, and individual responsibilities. The appropriate Exercise Evaluation Criteria Sheet will be given to observers. (Attachment 3) 5.3.6 Conduct the exercise as scheduled. 5.3.7 Upon completion of the exercise, conduct a post exercise critique. The critique will include:
- 1. Collection of Exercise Evaluation Criteria Sheets.
- 2. Collection of Individual observer comments.
i 5.3.8 Recommendations for improvement of the Emergency Plan and Emergency Implementation Procedures, based on the critique, should be forwarded to the Chemisty/ Health Physics Superintendent for review and action. 5.3.9 All documents generated as a results of the exercise shall be forwarded to the training department, PRC and SARB. l ei0780-0014a154 3 Proofread by: Ek]\fds ,
EI-15 Rev 1 m s Page 1 l ATTACHMENT 1 EMERGENCY PLAN TRAINING
\
TOPICS: Module 1 Introduction to Emergency Planning . Palisades /CPCo Emergency Organization State / County Emergency Organization Role of Federal Agencies Module 2 Notification Procedures Emergency Facilities Emergency Communications Emergency Classification System Emergency Equipment and Supplies Module 3 Basic Health Physics for Offsite Personnel Module 4 n q(,f . Personnel Accountability, Evacuation and Reassembly Radiation Exposure Control for Plant Personnel Module 5 Radiological Assessment Onsite Radiation Monitoring Offsite Radiation Monitoring Protective Action Guidelines Module 6 Protective Actions for the Public 4 Protective Action Guidelines Module 7 Site Access Control During Emergencies 1 Module 8 Facility Layout for Offsite Personnel
- Module 9 i
First Aid / Medical Interface . \,s.
- Module 10 Onsite Fire Protection Equipment -.
Onsite Firefighting Procedures ' i ei0780-0014bl54 '
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l l EI-15 Rev 1 Page 2 I s ATTACHMENT 1 1 EMERGENCY PLAN TRAINING l
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Module 11 Recovery Procedures Module 12 Public Affairs Procedures TRAINING GROUPS: Group 1 Operations Personnel (SS, C01, CO2, AO, STA) Modules 1,2,4,7,9,10,11 Group 2 Management and Supervisory Personnel Modules 1,2,4,5,7,9,10,11,12 Group 3 Radiation Monitoring Teams / Chem-Rad Pro Technicians Modules 1,2,4,5 plus Emergency Facilities Emergency Communications Group 4 Plant Personnel not assigned to the Emergency Organization Modules 1,2,4 Group 5 Security ' Modules 1,2,4,7,9,10 Group 6 l
- State / County Emergency Preparedness Personnel, State / Local Public Relations / Media, i Public Af fairs Director l Modules 1,2,3,6,7,8,9,10,12 I
Group 7 l Hospital / Ambulance Staff l Modules 1,2,3,6,7,8,9 ei0780-0014bl54 ' 1
EI-15 I Rev 1 l s Page 1 I ATTACHMENT 2 I
- s. DRILL OBSERVER ASSIGNMENT SHEET t
l Type of Emergency Date Area of Responsibility Observer
- 1.
2. 3. 4. 5. 6. l 7. 8. 9. 10.
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- - - , . - - - n. , - - . . ,. - - . - - _ _ - , , . . . . , - . . , , - _ . ,
EI-15 Rev 1 Page 1 s O= v
, ATTACHMENT 3 EXERCISE EVALUATION CRITERIA GENERAL PROCEDURES .
1. Each evaluator has been furnished and should be familiar with: a. General Emergency Preparedness Exercise Objectives. b. The Specific Objectives to test the Palisades Plant, Van Buren County, Berrien County, and Michigan Emergency Preparedness Plans as they pertain to the area being surveyed. c. The Exercise scenario, initiating events, and expected courses of action to be undertaken. 2. For each area to be surveyed the following has been prepared and distributed to the evaluators. a. A summary and description of the area's location, emergency mission, and personnel and their emergency responsibilities. s 3. Evaluators will be at their assigned posts between 30 and 45 minutes prior
~ g) . to commencement of the exercise, even though the area being evaluated may not be activated until later in the exercise.
4. If evaluators are to provide information (initiating events, instrumentation readings, environmental monitoring results, etc.) to exercise participants, the information must be provided exactly as prescribed and exactly when prescribed. Failure to provide the information appropriately may invalidate results of the exercise. 5. A Chronological Record must be kept for areas surveyed. The record will i show the . actual time, the event or occurrence, the result or action taken, and elapsed drill time and pertinent comments. t ., 6. Evaluators should offer no information, advice or assistance to the drill participants. Any such requests should be respectfully declined. Evaluators will only interpose themselves if the evaluees are taking an action that will cause the exercise to go far afield of the anticipated time schedule and/or outcome. Examples of problems requiring such interpositions may include: a dose calculation / projection that is so grossly inaccurate that an action level other than the one postulated for the scenario would be instituted; an activity that is taking so much longer than predicted that the exercise scenario is in danger of not progressing as postulated. PERFORMANCE EVALUATION CRITERIA [\- ') To ensure validity of the evaluation, all exercise evaluators utilize the same grading criteria. The following grading standards should be utilized, ei0780-0014d154 " r
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EI-15 R2v 1 Page 2 s I. Recording Times of Actions
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A. For grading purposes, it will be assumed that onsite personnel have been alerted when the emergency siren is sounded. B. For calculating elapsed times, evaluators will be given the actual time the exercise is initiated. This will be T = 0 on all reports. All elapsed time calculations will be based on this time, regardless of when the separate evaluated activities are initiated. C. An EOC or other activity will be deemed to be in service when its personnel accountability check is completed and reported or when the EOC has sufficient manpower present to carry out its mission. D. The " Chronological Events Summary" should be the primary evaluation record, it is intended to be used to complete the evaluation form upon completion of the activity. The form calls for the actual time, the initiating event, the resultant activity, evaluator comments and elapsed drill time (T = ?). II. Evaluation Standards Excellent: Personnel and equipment always functioned without error the first time, every time. There were no problems encountered, and all personnel and equipment functioned at a level much greater than could reasonably be anticipated. Good: Personnel and equipment generally performed better than expectations. Any errors or problems were minor, and easily correctable. Sa tis facto ry: Personnel and equipment performed according to expectations, with some minor exceptions. Any errors noted were not severe and could be corrected without undue labor and expense. Poor: Personnel and equipment generally performed below expectations or there were several significant deficiencies noted. The area's ability to carry out its mission was diminished. Fail: Personnel and equipment consistently failed to perform as required or there were serious deficiencies noted which severely impaired the ability of the area to carry out its mission. III. Categories for Evaluation A. Assess and Evaluate - Mission Performance
- 1. Command Functions - did the area carry out its mission of directing the activities of other components?
- 2. Assessment and Evaluatie ' - was information promptly and correctly received, assessed and evaluated?
ei0780-0014d154
EI-15 Rev 1
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Did personnel know and carry out their duties with, efficiency and without undue direction? 4. Did the area establish and maintain communications with other components? Was the information received and/or transmitted accurate, concise, appropriate, and timely?
- 5. Was the record keeping system designed and implemented to record significant events and actions for future use?
B. Assess and Evaluate - Facilities and Equipment 1. Physical Facilities - Was the area utilized appropriate by virtue of its size and location? Was there enough furniture, ventilation, rest rooms, office supplies, etc. to support the mission? Could the area support the personnel assigned to it?
- 2. Resource Materials - Were resource materials readily available to assess tlne emergency situation and to plan corrective actions
- maps, reference books, copies of emergency plans and procedures?
- 3. Communications Equipment - Was the onsite, offsite, and connecting communications equipment adequate in quantity, operability and availability? Did personnel know how to utilize g
N the equipment efficiently? x 4. Emergency Equipment - Was emergency equipment readily available, completely operable, appropriate to the task or situation, and did personnel know how to use it efficiently? Emergency equipment includes: portable environmental monitoring equipment; personal protective equipment - clothing, respirators; decontamination supplies and equipment; first aid and firefighting equipment; and communications equipment.
- 5. . Personnel Quantity - Was there enough trained personnel to carry out the mission? Too few? Too many?
- 6. Area Access Control - Did all assigned personnel respond to their areas promptly and stay in assigned area for the duration of the exercise? Was the area secured against unauthorized
[ persons / entry? l
- 7. Recordkeeping - Was all data accurately recorded and maintained in a systematic readily retrievable manner for future reference?
C. Interface with Other Areas and Groups ' Although this is not specifically addressed on all evaluation forms, obviously it is an item of extreme importance. An area that (,)
/x performs its own mission satisfactorily but that does not interface adequately with other areas, has not performed in an overall satisfactorily manner. Any deficiencies noted in the areas
, ei0780-0014d154 ' I r . -- ,
EI-15 R;v 1 Page 4 s interfacing with other areas should be noted. Such deficiencies may be due to inadequate communications hardware, organizational \ deficiencies, or inadequacies in plans and procedures. IV. Summary A. Describe any problems noted by the area being evaluated, a description of the problem, its outcome or effect, and any recommended corrective courses of action to mitigate or correct the deficiency. B. After completely filling out the evaluation form total up the number of points the area was awarded. C. The evaluator (s) is to sign the eve.luation form and promptly return it as directed. D. A critique of the exercise will be held the following day with all participants, evaluators and NRC/ FEMA observers present. l l l l l l O ei0780-0014d154 ' S
EI-15 Rev 1
' Page 5 O%
EVALUATOR TIME BEGAN TIME ENDED TECHNICAL SUPPORT CENTER I. Establishment of TSC 0- 5- 10-5 10 15 +15 A. After the emergency was sounded how long did it take before:
- 1. Site Emergency Director 15 10 5 0 arrived
- 2. Other personnel arrive 15 10 -5 0 (personal acct)
- 3. Recordkeeping established 7 5 3 0
- 4. Offsite communications 7 5 3 0
\ established (Jackson, i NRC, State / County)
- 5. Onsite communications 7 5 3 0 established (control, security,.OSC)
- 6. Personnel dispatched to 7 6 5 3 EOF
(+20 = 9) B. TSC Activation
- 1. Was personnel accountability Yes No check performed and reported (5) (0)
- 2. Was radiological survey made of Yes No the area (less than 10 mr/hr) (5) (0)
II. How did the TSC carry out its: EXC GOOD SATIS POOR FAIL
- 1. Overall command functions 10 7 4 1 0
- 2. Assessment and evaluation 10 7 4 1 0 functions .
J 3. Control room support functions 10 7 4 1 0 ei0780-0014d154
- EI-15 Rev 1 Page 6 EXC GOOD SATIS POOR FAIL O
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- 4. Onsite communications 10 7 4 1 0
- 5. Offsite communications 10 7 4 1 0
- 6. First aid coordination 5 4 3 1 0 III. Facilities Rate of adequacy of: EXC GOOD SATIS POOR FAIL A. Physical facilities 10 7 4 1 O B. Resource materials 10 7 4 1 0 C. Communications equipment 10 7 4 1 0 D. Emergency equipment 10 7 4 1 0 E. Personnel quantity 10 7 4 1 0 F. Area access control 10 7 4 1 0 G. Recordkeeping 10 7 4 1 0 IV. Mission Performance No Problems General Satis Unsatis A. Did Site Emergancy Director 25 15 0 take and maintain control?
B. Did all assigned personnel 25 15 0 know and carry out their duties? C. Was information promptly and 25 15 0 correctly assessed? D. Were the corrective actions 25 15 0 , ordered prompt and appropriate? l E. Were communications established 15 10 0 and maintained with offsite agencies adequate updates at 15 minute intervals? V. Describe any problems noted with recommended corrective actions. 1 O ei0780-0014d154 ' l
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EI-15 Rev 1 s Page 7 VI. Summary- AREA MAX SCORE s MIN SCORE ACTUAL I 68 51 II 55 23 III 70 28 IV 115 70 Overall 308 172 i o i I I i ei0780-0014d154 . 4
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T EI-15 Rev 1 Page 8 s. EVALUATOR TIME BEGUN TIME ENDED OPERATIONS SUPPORT CENTER GENERAL EXERCISE EVALUATION CRITERIA I. OSC Activation A. How long did it take after emergency was sounded for the OSC to become functional - ie onsite personnel present 0-5 min (20) 5-10 min (10) 10-15 min (5)
+15 min (0)
B. How long after notification did it take the OSC director to be on location and in charge 0-10 min (10) 10-20 min (5)
+20 min (0)
C. Activation Procedures
- 1. Was radiation survey performed Yes (5) ilo (0)
- 2. Was personnel accountability Yes (5) No (0) check performed and reported to the Property Prot Supervisor II. EXC GOOD SATIS POOR FAIL A. Did assigned personnel know 20 15 10 5 0 and carry out their assigned responsibilities?
B. How did the OSC carry out its:
- 1. Support functions 10 7 5 3 0
- 2. Assessment and Evalua- 10 7 5 3 0 tions
- 3. Onsite communications 10 7 5 3 0
- 4. Personnel control and 10 7 5 3 0 accountability ei0780-0014d154 '
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EI-15 Rev 1 ' I Page 9 l j III. Rate the adequacy of: EXC GOOD SATIS ' POOR FAIL j 'N 4 1 A. Physical facilities 5 4 3 2 0 l B. Resource documents 5 4 3 2 0 C. Communications equipment - 5 4 3 2 0 D. Emergency equipment -5 4 3 2 .0 : E. Personnal quantity 5 4 3 2 0 i F. Area access control 5 4 3 2 0 i
- G. Recordkeeping 5 4 3 2 0 IV. Describe any problems noted with recommended corrective actions.
i l i (,
SUMMARY
- AREA' MAX MIN ACTUAL a
l I 40 25 II 60 30 III 35 21 TOTAL 135 76 ? i i 4 ? 1 i l 1 1 ei0780-0014d154 ' 1 1 i .
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EI-15 Rev 1 Page 10 SECURITY FORCE GENERAL EXERCISE EVALUATION CRITERIA I. How long after the 0-5 5-10 10-15 +15 emergency was sounded did it take for: (minutes) A. Property Protection Super- 7 4 ' 0 visor onsite B. Security Shift Supervisor 7 4 1 0 onsite C. Security Force assembled / 7 4 1 0 accounted D. Access Control established 7 4 1 0 E. Immediate area checked for 7 4 1 0 fishermen, etc. F. Security Officer (s) dis- 7 4 1 0 patched to access road II. Did Security Force personnel EXC GOOD SATIS P0OR FAIL know and correctly carry out their duties? A. Overall 20 15 10 5 0 B. Access Control 15 10 7 3 0 C. Personnel Acountability 15 10 7 3 0 Checks D. Site Evaluation Procedures 20 15 10 5 0 t l E. Coordination with Offsite 10 7 5 2 0 Emergency Response Personnel III. Rate the adequacy of: l l A. Physical Facilities 5 4 3 2 0 i B. Resource Materials 5 4 3 2 0 C. Communications equipment 5 4 3 2 0 D. Personnel quantity 5 4 3 2 0 l E. Recordkeeping 5 4 -3 2 0 l ei0780-0014d154 '
d l EI-15 Rev 1 s Page 11 IV. Describe any problems noted with recommended corrective actions. t SUIDIARY: AREA MAX MIN ACTUAL I 42 24 '
; II 80 39
-)
III 25 15 ! I TOTAL 161 86 l I I t I i I e ei0780-0014d154 -
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EI-15 Rev 1 Page 12 FIRST AID TEAM I. At what time was first aid team notified?
~
(T = 0 for first aid team) II. At what time was first aid t'eam dispatched: T+5 = 10 5 - 10 =7 10 - 15 = 4
+15 =0 -
III. At what time did first aid team reach victim? IV. First Aid Procedures: A. Was radiological survey conducted prior'to treatment? Y N _ B. Was primary body survey conducted immediately? Y N C. Was decontamination conducted prior to treatic-nt? Y N D. Was secondary body survey conducted prior to treatment? Y N E. Were injuries correctly diagnosed and treated? Y N V. Transport Procedures: A. Was ambulance requested promptly? Y N B. Was ambulance emergency kit uti.lized to protect crew Y N and vehicle? C. Was contamination control maintained on way to hospital? Y N D. Was portable air sampler picked up at access control? Y N l VI. Hospitel Procedures: A. Callback ige additi aal personnel Y N B. Evacuate treatment area Y N e10780-0014d154 '
El-15 Rev 1 s Page 13 ( C. Remove / cover equipment in room s Y N D. Assemble needed equipment Y N E. Assemble contamination control supplies Y N F. Cover floors between entrance and treatment Y N G. ED personnel in protective clothing Y N H. Decontamination procedures Y N VII. Evaluate EXC GOOD SATIS POOR FAIR A. Personnel knew and 20 15 10 5 0 carried out their responsibilities B. Performance of first aid 5 4 3 2 0 treatment C. Performance of contamination 5 4 3 2 0 control D. Performance of Decontamina- 5 4 3 2 0 tion control E. Adequacy of equipment 5 4 3 2 0 F. Adequacy of communications 5 4 3 2 0 G. Interface with ambulance 10 7 4 1 0 crew H. Interface with hospital 10 7 4 1 0
SUMMARY
- Maximum Points - 65 Minimum Points - 33 Actual Points -
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EI-15 Rev 1 Page 14 FIRST AID SCENARIO Elapsed Drill Actual Time Time Time T+ T+
- 1. Time injured person intro- I I
duced ' I 2. Time first aid team alerted , I i l
- 3. Time first aid team dispatched ,
, I
- 4. Time first aid team on scene + .
. i l
- 5. Ambulance requested , t
- 6. Ifospital notified i
' l,
- 7. Victim moved to gate ;
- 8. Victim loaded in ambulance 1 l
. l, 1
- 9. Victim arrives at hospital '
I I
- 10. Treatment initiated t ,
, 11. Treatment completed l 1 1
- 12. Decontaminatifon initiated ,
l 1 l i } i
- 13. Decontamination completed i l l I
I i
- 14. All clear I
i Note any problems encountered and recommended corrective actions: O
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EVALUATOR eio780-0014d154 '
x EI-15 Rev 1
' Page 15 l \
EVALUATOR TIME BEGUN TIME ENDED RADIOLOGICAL MONITORING TEAMS I. 0-5 5-10 10-15 +15 A. Activation - How long after the emergency was sounded did it take for:
- 1. Chemical and Rad 15 10 5 0 Super onsite
- 2. Rad Monitoring teams 15 10 5 0 assembled
,7^ ) B. At what time were: \ ! (~' 1. First in plant surveys reported? 0 - 20 min = 10 20 - 30 min = 7 30 - 40 min = 3
+ 40 min = 0
- 2. First offsite fence surveys 0 - 20 = 10 reported?
20 - 40 min = 7 40 - 60 min = 3
+60 min = 0 II. Evaluate adequacy of: EXC GOOD SATIS POOR FAIR A. Physical facilities 5 4 3 2 0 B. Resource materials 5 4 3 2 0 C. Onsite communications 5 4 3 2 0 D. Offsite communications 5 4 3 2 0 E. Portable equipment 5 k 3 2 0 '
eio780-0014d154 '
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EI-15 Rev 1 Page 16 EXC GOOD SATIS POOR FAIL O\ ^ F. Fixed instrumentation 5 4 3 2 0 G. Personnel quantity 5 4 3 2 0 H. Recordkeeping 5 4 3 2 0 III. EXC GOOD SATIS POOR FAIL A. Appropriate Direction & 20 15 10 5 0 supervision by Plant Health Physicist B. Appropriate direction and 20 15 10 5 0 supervision by Chem and Rad Pro Supervisor C. Did personnel know and 20 15 10 5 0 carry out their duties? D. Was information promptly 20 15 10 5 0 and accurately transmitted to HP ' E. Coordination with each 20 15 10 5 0 other rad monitoring teams IV. Technical Evaluation: A. Did personnel know 10 7 4 1 0 location and use of equipment? l l l l l l l l l l l l till ei0780-0014d154 '
Emergency Impicmentation Procedures _ Revision Sheet s. TITLE: Communications Drills, EI-15.2 m Revision PRC Date Approved by Gen. Manager W w Os. . O G
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-' EMERGENCY IMPLEMENTATION PROCEDURE EI-15.2
^ COMMUNICATIONS DRILLS REV 0 1
1.0 PERSONNEL RESPONSIBILITY 1. The Health Physicist-Emergency Planning shall assign personnel, generally a department clerk, to perform the monthly, quarterly and annual telephone number verification drills.
- 2. The Plant Health Physicist shall assign personnel to carry out the Annual Communications Drill, Radio Test (Attachment 4) and to review the results of that test for acceptability.
- 3. The Plant Nuclear Emergency Planning Coordinator shall review completed checklists to ensure completeness and acceptability. '
2.0 PURPOSE The purpose of this procedure is to ensure that the emergency i communications system is functional and that the emergency notifications call list is accurate. Portions of these checks are required specifically by 10CFR50, Appendix E, for the Emergency Notification System (NRC-ENS). 3.0 ATTACHMENTS AND RECORDS
- 1. Attachment 1, Monthly Communications Drill
- 2. Attachment 2, Quarterly Communications Drill, Telephone Number Verification
- 3. Attachment 3, Annual Communications Drill, CPCo Co Telephone
, Number Verification
- 4. Attachment 4, Annual Communications Drill, Radio Test
- 4.0 SPECIAL INSTRUCTIONS The person assigned per Paragraph 1.1 shall update phone numbers in the Emergency Procedures as necessary. Telephone numbers are found in EI-2, EI-3, EI-4.1, EI-4.3 and EI-13.2.
5.0 PROCEDURE 5.1 Communications drills should be completed: 5.1.1 Monthly Communications Drill within the first ten days of the month. 5.1.2 Quarterly Communications Drill within the first month of the quarter. O(j 5.1.3 Annual Communications Drill Telephone Number Verification and Annual Communications Drill Radio Test prior to the Annual Emergency Exercise. t eiO682-0018a154 1
Emergency Irple xntation Procedure EI-15.2, Rev 0 Communications Drills s 5.2 The assigned person performs the designated checks using the 9 applicable attachment. System failures or incorrect telephone numbers shall be marked in red. 5.3 The dedicated telephone lines shall be tested by activating the telephone and transmitting a simulated message. 5.4 The simulated mersage should read:
"This is the Palisades Nuclear Plant testing its emergency communications system. This message is to verify that the system is working and that you are able to respond."
5.5 The commercial and plant telephones should be tested by dialing the appropriate number and transmitting a simulated message (see Paragraph 5.4). NOTE: Some numbers may only be in use during emergency drills and exercises and will require two people to perform the test at other times. 5.6 The intercom system should be tested by activating the system and transmitting a simulated message (see Paragraph 5.4). . NOTE: This test requires two people. 5.7 The radio test shall be performed by activating the radios and transmitting a simulated message (see Paragraph 5.4). The mobile radio team should transmit from within the Primary Emergency Planning Zone (10 mile radius). NOTE: This test requires two people. 5.8 The tests shall be considered acceptable if: 5.8.1 The equipment functions properly and/or telephone numbers are correct. 5.8.2 The simulated message is understood. 5.9 Unacceptable tests shall be promptly reported to the Health Physicist-Emergency Planning for corrective action. 5.10 Completed attachments shall be filed in Document Control after review by the Radiation Safety Supervisor (Attachment 3 only) and the Health Physicist-Emergency Planning. The Health Physicist-Emergency Planning shall review telephone numbers in the Emergency Procedures for required updates.
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eiO682-0018a154 2 Proofread by: Y Ci 6 0 .
EI-15.2
'.s Attachment 1 i Rev 0 Page 1 MONTHLY COMMUNICATIONS DRILL Location
; Equipment Remarks Tested (J)
Technical Support Dedicated Telephone Line Center (TSC) to NRC, Washington, Have call forwarded To Region III - Operations Center TSC Dedicated Telephone Line to General Office TSC Dedicated Telephone Line to Van Buren County TSC Dedicated Telephone Line to Michigan State Police Control Room Dedicated Telephone Line to NRC, Washington. [h Have call forwarded to Region III -
\z / Operations Center Emergency Operations Dedicated Telephone Line Facility (EOF) South to NRC, Washington.
Haven Conference Have call forwarded to Region III - Center Operations Center Performed by: Date Reviewed by Nuclear Emergency Planning Coordinator: Date kJ 4 c:0682-0018bl54 j 950/22*06*01/10 yrs ,
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EI-15.2 Attachment 2 Rev 0
^' Page 1 s,
QUARTERLY COMMUNICATIONS DRILL TELEPHONE NUMBER VERIFICATIONS fOrganization Telephone Number Consumers Power, Responsiblity i Tested (4) Power Controller 517-788-0990 General Office Response County Response and Emergency Operations Van Buren Sheriff 616-657-3101 Berrien Sheriff Center (EOC) 616-983-7141 County Response and EOC Allegan Sheriff 616-673-5441 County Response Allegan County Bldg EOC, Activated only during an exercise Covert Fire / Ambulance 616-764-1313 Fire / Ambulance South Haven Community Hospital 616-637-5271 Medical i Mercy Hospital, 616-927-5241 or Benton Harbor 616-927-5242 Medical Memorial Hospital, St Joseph 616-983-8300 Medical Medic 1 Ambulance 616-925-2141 Ambulance South Haven Ambulance 616-637-3305 Ambulance Michigan State Police 616-335-2020 or h Saugatuck 616-335-9666 s_/ Michigan State Police State EOC ' Emerg Serv Div, Lansing 517-373-0617 State Response Michigan Dept of Public 517-373-1578 (day) Health 517-373-0800 (night) Michigan State Water Protective Actions Resources Commission 517-373-7660 Protective Actions South Haven Water 616-637-5211 (day) Department 616-637-5151 (night) Dale Morgan, MD Protective Actions 616-637-3609 Medical Dale Witte, MD 616-637-3528 Medical Palisades Park Manager 616-637-8272 Protective Actions Van Buren Park Manager 616-637-2788 Protective Actions American Nuclear 203-677-7305 (day) Insurers 203-677-7715 (night) Insurance Nuclear Mutual Limited 809-295-3278 Insurance Federal Aviation Admin 616-637-8075 Protective Actions Nuclear Regulatory Comm Region III _ Headquarters 312-932-2500 Federal Response NRC Operations Center 301-492-8111 Federal Response (via Bethesda) NRC Operations Center 301-427-4053 (via Silver Springs) 301-492-7000 [,)NRCOperator (via Bethesda) ,
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eiO682-0018c154 _ , _ _ , r -- y , . - , . , . - - -r- y
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2 4 EI-15.1 Attachment 2 s Rev 0
)
Page 2
. g. QUARTERLY COMMUNICATIONS DRILL N TELEPHONE NUMBER VERIFICATIONS
- Organization Telephone Number Palisades Public Responsiblity ' Tested (4) 616-637-8769 Public Affairs Response Affairs Director 517-788-0333 (alt)
Dept of Energy 312-972-2000 Coast Guard Federal Response St Joseph 616-983-1371 Muskegon Federal Response 616-759-0951 Federal Response Michigan State Police South Haven 616-637-2125 State Response Indiana Civil Defense 317-232-3830 (day) State Response, Ind 317-232-8250 (night) State Police, ask for-Civil Defense Duty Performed by: Date Reviewed by Nuclear Emergency Planning Coordinator Date () . ', \se / i i eiO682-0018c154
EI-15.2 i Attachment 3 Rev 0 04 ' ANNUAL COMMUNICATIONS DRILL
'Page 1 TELEPHONE NUMBER VERIFICATION (CPCo) i Location Telephone Number l Technical Support l' Comments I Tested (4)
Center (TSC) Ext 342* This # should be i called from the CR i TSC Ext 287* This # should be TSC Ext 294* called from the EOF TSC Ext 243* Emergency Operations Facility (EOF) This # should be 616-637-6695* called from the CR EOF This # should be EOF 616-637-6615* called from the TSC EOF 616-637-6574* EOF i 616-637-6647* i EOF Ext 381* EOF Ext 382* ! EOF Ext 383* I EOF Ext 384* I i EOF Ext 385* ( Operations Support Center, Control Room Ext 386* Intercom Control Room This # should be Ext 253 called from the TSC Control Room This # should be Ext 255 called from the TSC Temporary EOF (Jackson) 82-87001* Temporary EOF I 82-87002* Temporary EOF i 82-87003* Temporary EOF 82-87004* I Temporary EOF i 82-87005* __ Temporary EOF i 82-87006* Temporary EOF 1 82-87007* Temporary EOF
- 82-87008*
Temporary EOF - 82-87009* Temporary EOF I 82-87010* Temporary EOF 1 82-85802* Temporary EOF I 82-80352* Temporary EOF I 82-80355* 4 Performed by: Date Reviewed by Nuclear Emergency Planning Coordinator: Date (/) s-sNOTE.:These numbers are generally connected at the specified locations only during emergency exercises. eiO682-0018d154 %4 e h
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f EI-15.2 ( Attachment 4 [ Rev 0 Page 1 ANNUAL COMMUNICATIONS DRILL, RADIO TEST Location Comments Tested (4) Plant Radio Emergency Operations Facility Radio Hobile Radio (Note location for test) Performed by: Date Reviewed by: Plant Health Physicist: Date Nuclear Emergency Planning Coordinator: Date ( v eiO682-0018e154
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