ML20101U435
| ML20101U435 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 06/18/1984 |
| From: | DETROIT EDISON CO. |
| To: | |
| Shared Package | |
| ML20101U434 | List: |
| References | |
| FOIA-84-552 PROC-840618, NUDOCS 8502070345 | |
| Download: ML20101U435 (836) | |
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- FER-MI-2 EXERCISE MANUAL FERMEX '84-o:
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m .x w FERMI 2 EXERCISE MANUAL TABLE OF CONTENTS
-PART I - ' GENERAL-DESCRIPTION AND OVERVIEW Page
- SECTION'l - INTRODUCTION 1-1 SECTION 2 -
PURPOSE 2-1 s ,SECTION 3 - SCOPE, OBJECTIVES, AND SIMULATIONS FOR FERMEX '84 3-1 s 3.1 Detroit Edison 3-1 L 3.2 Off-Site Response Organizations 3-6
>SECTION.4 .
CONDUCT AND ORGANIZATION 4-1 N:
. 4.1- Exercise, Rules 4-1 4.2 Exercise Organization 4-8
- 4. 3 ' - Exercise Facilities 4 s 4.4' Exercise Conduct 4-14 s
n 4.5 Evaluation and Critique :4-16 SECTION:5. - . EMERGENCY FACILITIES'AND PARTICIPANTS. 5-1 5.1 Emergency Response Facilities 5-1. 5.2 Pa rticipants 5-10
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s TABLE OF CONTENTS Page a SECTION:6,~- MISCELLANEOUS 6-1 6.1 Transportation 6-1 6.2 .Ilow to Get to the Site 6-1 s
~
6.3 Accomodations 6-2
. SECTION-7 - - REFERENCES, ABBREVIATIONS,
~
-DEFINITIONS 7-1
':V 7.1 References 7-1 f(
-7.2'. Abbreviations 7-2 s
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7.3 Definitions 7-5
PART II: EXERCISE SCENARIO:(CONTROLLED INFORMATION).
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- 2.1 Ten-Mile Emergency Planning Zone b
2.2 Fifty-Mile Emergency Planning Zone c- ;. 2.3 Emergency Operation Center
-Interrelationships i 4.1 Technical Support Center (TSC)
, Facility Drawing 4 .'2 T Emergency Operations Facility (EOF)
Facility Drawing j 4.3 Emergency Communications Telephone , Network L5 .1 ' Direct. Ring Telephone: Circuits Between
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Emergency 7 Response Facilities 6.1 . Fermi 2 Location Map
..y x6.2 Fermi 2 7 Location ' Detail Map D
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PART. I: GENERAL DESCRIPTION A N-D OVERVIEW m'
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SECTION'l - INTRODUCTION 4
' The Radiological Lmergency Response Preparedness (RERP) Prog ram for Fermi 2' consists of the RERP Plan, the RERP Implementing Procedures (EPs), RERP-Administrative Procedures (EPAs), and related emergency preparedness plans and procedures of Federal, State, and' local government agencies. The purpose of the program is to. provide protection of plant personnel and the general public, . to restrict the release of radioactivity, and to secure plant systems in a staule and' safe configuration in the event ot
- an-emergency situation at Fermi 2. The Fermi 2 RERP Program has the following objectives:
- o Effective coordination of emergency activities amony on-site and off-site or9anizations having an. emergency response role.
o- carlyLwarning'and~ clear instructions to tue general.public in
- the affected area in the event of a radiological emergency.
o Continued assessment of actual or potential consequences both on-site'and off-site.
-o Effective and timely implementation of emergency neasures.
h Lo- Continued 1uaintenance of an adequate state of emergency. N a V yy The RERP Plan describes the - RURP Program, ' including the- nature of it emergencyJresponse activities-and the available emergency response Tresources and facilities.
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~ 1-1 1
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.o- .. $ '} ( 43 1 e The RERP Plan is applicable to Fermi 2 and its environs, including
'a plume-exposure pethway Emergency Planning Zone (EPZ) extending 31 . 10 miles and an ingestion pathway EPZ extending 50 miles. The 10-
. mile EPZ for the plume-exposure' pathway includes all areas within 10 miles of Fermi 2 in. Monroe County, Michigan, a small portion of
.. tine southern tip of Wayne County, Michigan, and a small portion of ;
' the Province of Ontario,' Canada. The 50-mile ingesti'on pathway includes portions of Michigan, Ohio, and Canada.
- TheLMichigan Emergency Preparedness Plan, the Monroe County Euer-
~
gency Operations Plan, the Wayne County Emergency Operations Plan, and'the Brownstown Township Emergency Operations Plan describe
- the_ emergency planning and response for the respective government agencies. The Fermi'2 RERP Plan describes the interrelationships between the various Emergency Response Organizations.
The ~ RERP Plan provides a description of the. RERP Program as required by-10=CFR 50, Section 50.47. Appropriate criteria frou f '. l.
~
- 14UREG-0654/ FEMA-REP-1, Revision 1, November 1980, " Criteria for Preparation and Evaluation of Radiological Emergency Response Plans an'd Preparedness:in Support of Huclear Power Plants" are
.al so considered. \
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SECTIuti 2 - PURPOSE
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LMadiological Emergency Response Preparedness-(RERP) planning for an incident'at Fermi 2'is a cooperative effort involving Detroit Edison;~ local government agencies (county, city, village, and Ltownship); the States of Michigan and Ohio; Federal Government agencies; local and provincial agencies in Ontario, Canada; and various. organizations that provide support for these agencies. Emergency' Planning Zones (EPZs) nave been established to assist in the. planning ; effort and are shown in Figures 2.1 and 2. 2. Each organization has the responsibility to assure, through
. coordinated planning and regularly scheduled exercises, such as FURMEX-'84, that it can provide an effective emergency response 24 hours a day.
$ The interrelationships of the organizations supporting the Fermi 2 emergency response are shown in Figure 2.3.
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STATE f OC tLamane georat toes . M M LUC 11TIVl 04 t K't. t 41ML COUNT 1 Lot Agriculture . Cev. Representative Pubite Wealth State Police I """' 8 '8 State Police H ILMA % erattone Social Services **w Enforce **nt Chief teacutive Transportation unNIrueth- U'* PIO b lact Satural Renewrces '8**8; Military Affaire INI DAW 4 TION Cl NTt R , Preparednese Assessenet/ States * "Ch**I Federal Listeen Nuel PIO. A u n m nt Meetue
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- Tremoportetten Pubitt Works Betural Seoewetes School 8111tery Affette elf a Freeldeettel dieseter '
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FIGURE 2.3 EMERGENCY OPERATION Cf.NTER INTERRELATIONSHIPS r i
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m ,-,_ _ _ .,,_ y i r: i 3 SECTION 3-t ? SCOPE, OBJECTIVES, AND SIMULATIONS F0R FERMEX '84 i} t
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-Sectionl3 - SCOPE, OBJECTIVES, AND SIMULATIONS FOR FERMEX 84
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.3.1 DETROIT EDISON 3.1.l' SCOPE
- FERMEX' 84 will simulate an emergency at Fermi 2 that
=
will result in offsite radiological releases that will
; require - response from the Fermi 2, Counties of Monroe and Wayne, and State of Michigan Emergency kesponse Organizations. The EXERCISE is designed to test Edison's response to various plant euergencies; to establish the
- s. communications and coordination betwe'- Edison and offsite governmental Emergency Responst rganizations and Facilities;.and address the specific responsibilities,. capabilities, and interfaces of each organized element of the Fermi 2 RERP Plan and Implementing Procedures.
i A simulated abnormal radiological incident at Ferui 2
- will escalate-progressively from an UNUSUAL EVEUT to a-GENERAL EMERGENCY. The emergency will thenLdeescalate
.to the Reentry and Recovery Phase where it will terminate.
L
~
As the capabilities of' Edison and the various offsite governmental response organizations are brought into L play, the effectiveness and efficiency of the organi-sations' response will be independently evaluated by the [' 'NRC and FEMA. l . c(.
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- 3-1 052984 w ~- . .
g, - - s j e ,._~ I3.1.2 OBJ ECTIVES
$kD -Since FERMEX U2, Edison has completed its permanent
' Emergency-Response Facilities, (OSC, TSC, EOF),
. including.the closed-circuit television in the TSC, and.has established the permanent Emergency _ Response Organization. The Emergency Response Information bystem (ERIS), which includes SPDS, plant _ parameters and trends, dose assessment, and real-time meteorology is installed but-not functional.
T The overall objectives of FERMEX 64 are to demonstrate that- tne ERFs are adequate and operational, the RERP Plan and Procedures are in place, and Emergency Response Organization personnel are trained and capable of
' ' responding to a radiological event at Fermi 2 without ERIS functional'.-
4
.o The . specific objectives of FERMEX 84 will demonstratet
- 1. The adequacy of tlie RERP Plan and its Impleuenting Procedures and test the proficiency of the Emer-Lyency Response' Organization to select and use the
- appropriate' procedure for response to the
' -emergency.
- 2. The integrated capability of the Emergency Response organization to respond to a simulated situation.
'3.. The effectiveness of-the interfaces among the Control. Room and the' permanent Emergency Response 4
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. Facilities, including the Operational Support
. Center, Technical Support Center, and Emergency k Operations Facility.
- 4. The adequacy and ef fectiveness of the permanent
= emergency communications network among Fermi 2 and State, local, and Canadian agencies and the HRC 's Emergency Hotification System, liealth Physics Hetwork, and, Federal Telecommunciations System.
- 5. Proficiency in recognizing, understanding, and applying the Emergency Action Levels in classifying emergency conditions.
- 6.- .The capability of the Control Room to properly use the: procedures and forms provided for notification of the State, local and Canadian (when required)
. governmental agencies within 15 minutes of classi-fication of the event.
r.
- 7. The capability of the Control Rooia to notify the HRC within 1 hour and maintain contact with-6 technically qualified person.
- 8. .The capability of'the TSC and"COF to properly
~
notify State and local governmental-agencies within 15 minutes of classification of the event.
- 9. The capability of all Fermi 2 Emergency Response Facilities to provide follow-up reports- to State and local agencies and to the HRC on a periodic basic.
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JEz? - [10. The capability to activate the Joint Public Infor- " mation. Center and to produce public information l [< releases and respond to public inquires on a timely
- basis.
'll. The ' capability. to perform timely and effective
, Loff site Edose' assessment based on the use of a
' microcomputer..
- 12. :The capability to obtain real-time meteorological data .from the Fermi' 2 60-meter tower and weather forecasts using the dial-up terminals in each
-facility until such time as the release occurs. !
h .
- 13. L The capability to recomraend to the responsible State officials' protective actions for the general
, i public.in the 10-mile EPZ based on plant
. conditions, potential and/or actual radiological ;
~
releases, and meteorological data onr a timely basis ,
+
(within~15 minutes.of declaring a GENERAL
. EMERGENCY). .
, T14. - Tue capability of.the Offaite RETs to' locate the
. plume,'to obtain air samples'for iodine, and to
, collect environmental samples (soil, snow, milk,. l vegetation as appropriate for season) andideliver them to the . EOF Laboratory. .
15'. Thef capability of the EOF Laboratory to analyze the environmental-. samples on a timely basis.
+
- 16. The use of personnelE dosimetry for the ' entire ,
. ' Emergency Response Organization in the Control-
. Room, OSC, TSC, EOF, etc. and operation of !!ealth Physics control point at the' entrance to the~TSCS and EUF.
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- 17. . The " capability of Health Physics personnel to
[L perfori. in-plant surveys with the proper procedures dh and-instrumentation. J
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- 18. The use of documentation in the Information Centers
-. in the TSC 'and EOF by emergency response personnel.
- 19. -The l capability to conduct a fire drill using off-site fire department assisstance
- 20. The' organization and_ initial operation of the
. Recovery Organization.
- 21. LThe continued operation, support, and communications at the EOF with off-site response
, agencies during_ reentry and recovery.
3.1. 3 - ~-SIMULATED CONDITIONS i For the purpose of FURMEX 84, Fermi 2 is simulated as a licensed' fully . operational f acility. The simulated
- power level history and-other aspects such as nonopera-V' tional equipment .are defined ine the scenario sumraary and
_ data; sheets. 2Since Fermi 2 has not as yet-loaded fuel, for. purposes Jof the scenario, the-following actions are simulated:
- 1. - Activation of ERFs via the call-out/ notification procedure.
i 3 3 , a -
y e: c' L2.- . Assembly, accountability, and evacuation of protected area.
-[-
- 3. Potassium Iodide distribution.
- 3. 2 OFF-SITE RESPOllSU ORGANIZATIOllS 3.2.1- ' STATE OBJECTIVES
- 1. . Demonstrate the ability to fully staff facilities and maintain starfing around the clock (staffing will be with a shift change or double staffin9 in some' positions as identified in the exercise
., manual).
- 2. Demonstrate the ability to make decisions and to cooruinate emergency activities (command and
. control fur.ctions at/between EOCs) .
l 4
- 3. Demonstrate the adequacy of facilities and displays to support emergency operations (SEOC, OSEOC, . JPIC, and ancillary facilities).
- 4. Demonstrate the ability to communicate witti all appropriate-locations, organizations, and field personnel (using appropriate communication channels such as primary (phone), and secondary (LEIll) to
< fixed facilities, ano MSP' radio to field personnel.
- 5. Demonstrate the ability to deploy - field r.cnitoring teams in :a tiinely .f ashion. (Teams will-. be i prestaged in the area as will all staff f forces.)
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.6. -Demonstrate appropriate equipment and procedures for uetermining ambient radiation levels.
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.. '7.- Demonstrate appropriate equipment and procedures f or Jiaeasurement of airborne radioiodine i
~
concentrations as low as 10-7 uCi/CC in the presence;of noble gas.
-- '8. Demonstrate appropriate equipment and procedures for collection, transport, and analysis of samples of soil, vegetation, and water.
M
~ '9. Demonstrate-ability to project dosage to the public 7
via plume exposure, based on plant and field data, and to determine appropriate protective measures, based on'PAGs, available. shelter, evacuation time
-estimates, and all other appropriate factors.
-10. Demonstrate ability to project dosage to the public via ingestion pathway exposure, based on field data,oand to. determine appropriate protective measures, based 1on- PAG 's and other relevant factors.
-11. Demonstrate ability.to alert the public within the 10 mile EPZ-and' disseminate an initial i' -
instructional message within 15 minutes. (Contact with - EBS ~ willi be made by county DOC 's with initial Lcontact. message that this is a test. Sirens will not be sounded.) L
~
'12; . Demonstrate ability to formulate appropriate
- 5; , yk instructions to the public in 'a timely . fashion.
-(Via the:JPIC and simulated EDS contact.)
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- 13. Demonstrate the organizational ability necessary to
~~
manage an _ orderly evacuation of all or part of the ( plume EPZ. o
- 14. . Demonstrate the organizational ability necessary to
. deal with cimpediments to evacuation as inclement weather or-traffic obstructions (via simulated message play).
+
. 15 ~. - Demonstrate tne organizational ability necessary to control access to an evacuated area.
- 16. - Demonstrate. ability to continuously-monitor and
.. control emergency worker exposure.
- 17. - Demonstrate the ability to make the decision based on predetermined criteria whether to issue KI to emergency workers and/or the general population.
r( - " - 18.- Deroonotrate L the ability to supply and aduinister KI once the decision has been made to do so.
- 19. Deiaonstrate ability to brief the media in a clear,
-1 accurate, and_ tinaely manner at the JPIC.
y 20.- Demonstrate ability to provide advance coordination of information r released (at : the EOC 's and JPIC) .
- x. ,
- 21. Demonstrate adequate procedures for decontamination of-emergency workers, equipment, and vehicles in (support of-county operations at decontamination
. facility.
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- 22. Demonstrate ability to- identify need for, request, and obtain federal assistance.
k
- 23. Demonstrate ability to estimate total population exposure.
~24. ' Demonstrate ability to determine appropriate Emeasures for controlled recovery and reentry.
(Actions in this area include close out of recep-tion / congregate care / decontamination facilities, public:information releases (including measures to 1, be taken upon reentry), decision making at EOC 's, and pickup /close out of access control / traffic control points. More details will be provided in the scenario.)
- 3.' 2. 2 : ~ WAYNE COUNTY ib s. 1. -Demonstrate the ability to fully staf f facilities and' maintain staffing around the clock (staffing will be with a shif t . change or ' double staffing in someLpositions as' identified in the exercise Laanual).
- 2. !
Demonstrate the' ability to make. decisions and to
' coordinate emergency activities (coramand and control functions ' at/between the EOC 's) .
- 3. . Demonstrate the adequacy of facilities and displays-to : support emergency Loperations (County EOC and ancillary facilities).
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- 4. Demonstrate the ability to communicate with all
~
' appropriate locations, organizations (using g
appropriate communication channels as primary and
< ~
secondary systems). E- ' 5.- Demonstrate ability to alert the public within the 10 mile EPZ and disseminate an initial (Contact
. instructional message within 15 minutes.
with EBS will be made by.the County EOC with an
' initial-Lessage that this is a test. Sirens will not be sounded. )
_. 6. Der.ionstrate ability to formulate appropriate
-instructions to the public in a timely fashion.
-(Via the JPIC and simulated EDS contact.)
- 7. Demonstrate the organizational ability necessary to D manage an orderly ~ evacuation of all or part of the plutae EPZ :(with' demonstration of a limited number of persons).
i 8. : Demonstrate 1the organizational ability necessary to deal with impediments to1 evacuation such as
. inclement weather or traffic obstructions (via
. simulated message-play).
L ,
'9.- Demonstrate ' the organizational ability necessary to
'. control access to an evacuated area (with demon =
~
' stration' of limited manned control points using
- sherif t and/or road .commisssiont personnel and y ,
vehicles).
- 10. ; Demonstrate the' organizational ability necessary ' to
~~
e , effect an orderly evacuation of mobility-impaired-
.individiuals within the plume EPZ (with a limited demonstration of resources).-
4- - 3-10 a R
- k;--
e , 3 S'-' \p " li. . .bemonstrate ability to continuously monitor and
," control emergency worker exposure.
- 12. Demonstrate the ability to supply and administer K1
, m once the decision has been made to do so.
- 13. : Demonstrate ability to brief the media in a clear, accurate, and timely manner at the JPIC.
- 14. Demonstrate ability to provide advance coordination of information released (at the EOC 's and JPIC) .
- 15. Demonstrate adequacy of procedures for registration
..1 and radiological monitoring of evacuees (using a limited number of persons and simulating use of actual decontamination).
- 16. Demonstrate adequacy of facilities for mass care of evacuees (by establishing one facility).
O
- 17. Demonstrate adequate equipment ano procedures for
~
-decontamination of' emergency workers, equipment, and vehicles at a reception / decontamination center.) ,
7
- 18. Demonstrate ability to determine appropriate measures for controlled recovery -and reentry.
g
'(Actions in this area include close -out of recep-tion / congregate care / decontamination-facilities, public information1relenses.(including ueasures to be taken upon reentry), decision making at.EOC's,.
[ ~ andl pickup /close out of access control / traffic U, control points. More details' will be provided in the scenario.). g [ t
' .[
t 3-11
$ *T , :=
9 i' 3.2.3' B R O W 14 S T O W 14 T O W14 S ti 1 P
- l. Demonstrate the ability to fully staff facilities and maintain staffing around the clock (staffing
~will be'with a shift change or double staffing in some positions as identified in the exercise manual).
2.- Demonstrate the ability to make decisions and to coordinate- emergency activities (cowaand and control functions at/between the EOC's).
- 3. Demonstrate the adequacy of facilities and displays
- to support emergency operations (County LOC and ancillary facilities).
- 4. Demonstrate -the ability to comiaunicate with all appropriate locations, organizations (using appropriate. communication channels as primary-and secondary systems).
-5. Deinonstrate ability to alert the public within the 10 mile UPZ and-disseminate an initial instructional message within 15 minutes. (Contact with EDS will be made by the County DOC with an initial message that'this is a test. Sirens will not be_ sounded.)
- 6. Deraonstrate ability to forlaulate appropriate instructions to the public'in a timely fashion.-
i
-(Via the JPIC and simulated EDS contact.)
e T
'b 3-12'
3 _
- 7. Demonstrate the organizational ability necessary to manage an orderly evacuation of all or part of the i I plume EPZ (with demonstration of a limited number _
of persons). j i
- 8. Demonstrate the organizational ability necessary to ls deal with impediments to evacuation such as incle-ment weather or traffic obstructions (via siuulated
+ message play). _
t
- 9. Demonstrate the organizational ability necessary to control access to an evacuated area (with a demon- [
stration of limited manned control points using 3 police and/or Department of Public Works personnel and vehicles). l
- 10. Demonstrate the organizational ability and resources necessary to effect an orderly evacuation -
of mobility-impaired individuals within the plume EPZ (with a limited demonstration). -
- 11. Demonstrate ability to continuously i.ionitor and control emergency worker ~ exposure.
d 5
- 12. . Demonstrate the ability to supply and administer KI once the decision has been made to do so. 1 m
- 13. Demonstrate ability to brief the media in a clear, accurate, and timely manner at the JPIC. ,
i
- 14. Demonstrate ability to provide advance coordination of information-released (at the EOC's and JPIC).
A a. 3-13 j A
=
c3 - 0?b 1. 3.c , 115. Demonstrate adequacy of procedures for registration
.- 'andEradiological monitoring of evacuees (using a
- .'d3 N -limited number of' persons and simulating use of actual decontamination).
,. c ? D
- 16. Demonstrate adequate equipment and procedures for decontamination of emergency workers,' equipment and vehicles.
- 17. (Demonstrate ability.to determine appropriate
+
~
measures 'for controlled recovery and reentry.
~ ( Actions in this area include close out of recep-
+ l tion / congregate care / decontamination facilities,
..~ .public information releases (including measures-to be taken upon reentry), decision making at EOC's, a'nd pickup /close out of access control / traffic control points. Mo're . details will be provided in
.the scenario.)
; i.
.-3
^
E 3.2.4 MONROE COUNTY n . . l.- . Demonstrate the ' ability;to fully staf f facilities
.and maintain staffing around'.the clock (staffing will in 'with a shif t_ change or double staf fing in
-someLpositions as identified in-the exercise
. manual).
-o
~
.2. Demonstrate .the ability to make decisions and 'to Ecoordinate emergency activities-(command and
. ' control functions at/between the .EOC 's) .
u- t ,
*
- n+- - ~i'
- c. ,
6 3-14 w
3.- Demonstrate the adequacy of facilities and displays j: l to support emergency operations (Monroe County DOC and ancillary facilities).
- 4. Demonstrate the ability to communicate with all appropriate locations, organizations (using appro-
~
priate communication channels as primary and secondary systems).
- 5 . -- Demonstrate ability to alert the public within the 10 mile EPZ and disseminate an initial instruc-tionalumessage within 15 minutes. (Contact with EBS wille be made by the County DOC with an initial
~
% . message that this is a test. Sirens will not be
. sounded.')
P
- 6. Demonstrate . ability to foriaulate L appropriate
- instructions to the public in a timely fashion.
3::' , (Via the JPIC and'aimulated EBS contact.') R b> -
-7. Demonstrate the organizational ability necessary. to manage'an orderly-evacuation of all or part of the
~
plume EPZ-(with.a demonstration o* a limited evacuation).
.I
~
' - 8.. Demonstratenthe organizationel ability necessary.to deal.with'.iupediments~to evacuacion.suchlas
- - .]
s iinclement weather.or traffic obstructions 1(via
- < simulated message ~ play).
Demonstrate. the organizational ability : necessary to u , ,
. . 9.-
' ^ -
. . .e . . .
. controlTaccess to an evacuatedf area '(with .a. limited.
demonstration of1 access contro11using sheriff S'# V ' fand/or road: commission-personnel and vehicles).
, ,r
-f - p + 4, .-' g
?i_*~- '
- e x.- :
3-15 C
..T_.
3
. p
-se
, 10. Demonstrate ability to continuously monitor and
;h control emergency worker exposure.
"( ~
c ,
- 11. ' Demonstrate the ability to supply and administer KI once the decision has been made to do so.
- 12. ' Demonstrate-ability to brief the media in a clear, accurate, and timely manner at the JPIC.
. 13. . Demonstrate ability to provide advance coordination of information released (at the EOC's and JPIC).
- 14. : Demonstrate ab'ility to establish and operate rumor
--.. control .in' a coordinated fashion at the JPIC.
1 e
- 15. Demonstrate' adequacy'of procedures,for registration and radiological monit0 ring of evacuees-(using a
. limited number -of persons and simulating use of
, actual decontaminations)' .
T: < [16. Demonstrate adequacy.of facilities for mass care of C
' - -eva'cuees (by testablishing ;one facility) .
- 17. Demonstrate-adequate-equipment and. procedures for
- w
. decontamination of emergency workers, equipment,
,- e s
.and ' vehicles.-
g
-18. ?Demonstirate.. ability to determine and- implement:
k 15 0
- Jappropriatermeasures for controlled recovery and
~
reentry.- -(Actionsiin this area include close out
> - (NE - of f receptio'n/ congregate care / decontamination -
g x t di N ' facilities,'publict information. releases . (including -
~- . .
m l measure to be taken -upon. reentry), ' decision ;uaking 7
-at-EOC's:and pickup /close-out of accessicontrol/
6" ?" _ it raffic control points. More details .will be: , a 1- ~
. 3-16
'E U _ . !
public information releases (including measures to bp taken upon reentry), decision making at EOC 's,
.l and pickup /close out of access control / traffic control points. More~ details will be provided in the scenario.)
br Ss, w
.i .
t N
?
A A
+ 17
-- ~
i 4 0 - SECTION 4-C0NDUCT AND ORGANIZATION OF EXERCISE 1 k . 9
*f 4
I ., e
$d CONTROLLERS may also serve to prompt or initiate R ~ '
certain actions in order to assure continuity of
=k the events described in the exercise scenario.
' CONTROLLERS are the only personnel who will provide information to the PLAYERS, other imputs of infor-mation from personnel not designated a's CONTROLLERS will be ignored by the PLAYERS.
CONTROLLERS'may also serve as EVALUATORS.
^
t
- C. EVALUATORS are peronnel predesignated by DECO, NRC, and FEMA to-provide documentation and assessment of
.. the' exercise. They serve a passive function and lwill'only note actions taken by PLAYERS. These personnel have received specific instructions on what areas to-consider in their evaluation of the
_ : -_ exercise.-EVALUATORS may ask questions of PLhYERS
.'to' clarify actions taken or procedural ~ concerns but f
should not interface.with the flow of events. , , _ x D. ' ; OBSERVERS- are personnel.who serve no evaluation, 4 , control, or_ participatory' function in the exercise.
~
f, , ; Visitors'from NRC, FEMA,.stae agencies, and other - utilities are' expected'toLbe included as~ OBSERVERS. OBSERVERS shall notiinterfere with EVALUATORS, and.
~
particularly,. PLAYERS. Que'stions.from OBSERVERS
'should!be' directed to atCONTROLLER..
~
' Identification of Personnel:-
(, .
~
._ ' A'. -. CONTROLLERS . (Controllers / Evaluators): - Red arm.
~*% , a 'kan'd.
' ~
l . , . >
- e .e i s -t A 4 f
5 ~-{,
^
,7
*~
- V ;g.-
4-2
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J; f ': [4 .hs... U '
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, ,, m -, ,d, _,,,,,,,.m,,_py , E,. y . ,,.5 , % m , h., y ,, , . , .
Section 4 - CONDUCT AND ORGANIZATION OF EXERCISE
\
4.1 EXERCISE RULES To define the~" extent of play" of the exercise PLAYERS and to meet the exercise objectives, th'e following exercise guide-lines have been established: 1.- The exercise will be conducted on June 26, 27, 1984. Since exercise PLAYERS will not be informed of the exercise start' time or initiating events, all personnel should follow their normal routines prior to the
^'
exercise.
; 2.' The exercise will commence with postulated conditions necessitating a declaration of Hotification of Unusual Event and escalate through the four emergency action levels to a General. Emergency.
3.. Four groupsfof' personnel will be in attendance at the sexercise.and will function as described below: A. LPLAYERS are managers; . supervisors; -operators; engi-
- s. neers, - chemistry, health physics, and maintenance perso'nnel,,etc., who have been assigned an-" acting"-
1 role during the emergency. exercise. These people
~
serve to take necessary actions to-mitigate, termi- _p ~nate, correct, 'and/or ~ recover from the simulated r
- emergency.
j;;- B.. -CONTROLLERS.are those predesignated DECO or contractor personnel who serve- an active role in
- t'he exercise . by providing . data to PLAYERS. The
.i- .~ _
- y 4-1 L +
. - 2. ?
Section 4 - CONDUCT AND ORGANIZATION OF EXERCISE I 4.1 EXERCISE RULES
'To define the " extent of play" of the exercise PLAYERS and to meet the' exercise objectives, the following exercise guide-lines have been established:
1.- The exercise will be conducted on June 26, 27, 1984.
'Since exercise PLAYERS will not be informed of the 4
exercise start time or initiating events, all personnel should follow their normal routines prior to the exercise.
- 2. The exercise will commence with postulated conditions necessitating aEdeclaration of Hotification of Unusual
' Event and escalate through the four emergency. action levels to a' General Emergency.
- 3. Four groups of personnel will be in attendance at the exercise'and will function as described below:
A '. LPLAYERS are managers; . supervisors; ' operators; engi-neers,1 chemistry, health physics, and maintenance _ personnel, etc. ,. who have been ~ assigned an " acting" role during the emergency exercise. -These people serve to take necessary actions.to mitigate, termi--
- nate,1 correct, and/or: recover from the simulated emergency.-
^^ ~
-B. ' CONTROLLERS are '.those predesignated DECO or
; : contractor personnel who serve an active role . in the exercise by providing data to PLAYERS. The i, :
4-1
. . ... ., .. . , , . , , - - , . ..-._,-....,.~-_-.,-,m_ . . , - . . . - . - , -
. ., . l CONTROLLERS may also serve to prompt or initiate
~ .certain actions in order to assure continuity of Nh the events described in the exercise scenario.
CONTROLLERS are the only personnel who will provide information to the PLAYERS, other imputs of infor-mation from personnel not designated as CONTROLLERS will be ignored by the PLAYERS. CONTROLLERS may also serve as EVALUATORS. C. EVALUATORS -are peronnel predesignated by DECO, NRC, and FEMA to Provide documentation and assessment of
. - the exercise. They serve a passive function and will only note actions taken by PLAYERS. These personnel have received specific instructions on what areas to' consider in their evaluation of the
-exercise. EVALUATORS ~may ask questions of PLhYERS
~
- to clarify actions taken or. procedural concerns. but
'~
.should not interface with the flow of events. ,
1D. OBSERVERS are personnel who serve no1 evaluation, y control, or. participatory function in the exercise. Visitors from NRC, FEMA, stae agencies,'and other utilities'are' expected to be included.as OBSERVERS.
' OBSERVERS shall not' interfere.with EVALUATORS, and-particul'arly, PLAYERS. Questions from OBSERVERS should be directed:to a CONTROLLER.
c Identification of Personnels.
, 1A.' CONTROLLERST(Controllers / Evaluators): Red arm
- , band.
(. , f
. a:
.4-2' 4
. d
.m
- .. . - . . - . . . . - .. - - - ~ . - ..-- .. -
%,. ~
- 1, g ;; * . .
4 g B. EVALUATORS: Blue arm band.
~
C. OBSERVERS: Blue arm band.
; :D. PLAYERS: White arm band.
4.. Personnel will be assigned as CONTROLLERS at all key functional areas to monitor and control the exercise. 2
, In addition, they will accompany radiological nonitoring ,
teams,Lplant health physics personnel and maintenance
. repair / rescue teams.
n: '5. Message forms will be the mechanisms used to initiate, orchestrate, modify and complete the events comprising the overall scenario. The CONTROLLER will use the
' message forms to place the scenario events in effect and
_ i to' trigger responses from the involved personnel. v
- 6. Each CONTROLLER'will have the time-related plant.and
$N -
. radiological parameters of the' exercise scenario. This.
~
information will be issued upon request to the appropriate exercise. PLAYERS. !
.7. : .The CONTROLLERS-will not provide information'to.the
~
- exercise PLAYERS regarding; scenario development'or resolution of problem areas; encountered. 'The' exercise
- ~ . PLAYERS'areLexpected-to obtain information;through1their Lown organizationsLand exercise their own judgement'in'. c determining . response ~ actions - and resolving prob'lems. ' N
~
s g :8., Plant / Monitoring ; Data : Data)will'be provided at speci-i fie'd intervals : only. .Dataiforfthe time period between Y' Lupdatesfand data;for; future times'are not available;to.
-'; PLAYERS. . PLAYERS shoul'd request from th'e. CONTROLLERS'
-; .any data Lwhichlthey feel are necessary for. the
,'.y
< performance of their functions.
i t. . ;' L 4 .
+
c I
'# , . . _ . . . . , , . . . . , , , , . ~ . , , . ..-.,,.,,,_.,_ -_......m.,__,. _L,,.-,_.
[' -a*j,1
.s ..
- 19. Some exercise PLAYERS may insist that certain phrts of the scenario are unrealistic. Tne CONTROLLERS have the
' authority' with the approval from the EXERCISE CONTROLLER, to clarify any questions regarding scenario
, content.
In some cases, it may be necessary to exercise
" CONTROLLER'S perogative" of countermanding PLAYERS' actions to preserve the continuity and objectives of the exercise. You must, however, accept his/her word as
' final and proceed. Inappropriate actions can delay or speed up the- entire exercise and impact other groups.
- 10. Note that the scenario events are hypothetical. Any z..
portions of the scenario depicting plant system
- operational transients are simulated events. No control room actions, or reactions involving operation of plant systems shall be initiated. All exercise scenario messages shall be prefixed and ~ suf fixed with the words:
<t "TitIS IS A DRILL" .
311. -Postulated accident conditions will result in a simulated radiological release which necessitates the consideration of protective actions for the general public, and will provide the mechanism for off-site authorites to exercise their respective emergency 7 response' plans.
- 12. - A11 on-site and off-site emergency response facilities will' be manned and . perform their prescribed functions as appropraite to -the development of the exercise- scenario.
~ . . . - .13.-iMedia; centers;will be manned and perform their ' ' - prescribed; functions.. ,
gi 4-4
co- s
- t' .e
[. L .14. The' postulated accident conditions uay warrant the simu-lated assembly and evacuation of selective non-essential
,j 3 site personnel. Evacuation of personnel outside the protected area will not be demonstrated. If required by
. the exercise-scenario, emergency alarms should be sounded.
- 15. . Participation by DECO on-site personnel directly involved in respon' ding to an emergency shall be carried out to the fullest extent possible - including the deployment of Fire Brigade, Radiological Monitoring Teams, Damage Control 'and Rescue Teams, and other emergency = workers.
- All" actions are to be played out, as much as possible, in ~accordance with emergency plan and procedures as if
'it4were.a re'al-emergency. Actions' should be identified
.to the. CONTROLLER and whether to play them out or simulate them.
;g g .
- 16. Actual and Simulated : Events: -During the' emergency
~ drill /Jexercise,_certain events and activitties will only. be simulated rather .than . utilize the actual
; employment of(resources.
o' Simulation - involves identification and utiliza-tion'of requirements'and procedures short of actual employment. - 41 -
. 1:.
o- !ActualI- . movement:of' resources and/or physical
' implementation for this' exercise.
.[
~"' [. -
EXAMPLE - Activities: asociated with response to the Post-
~ Accident. Sampling System will-not-be performed-
- butowill'be simulated.
j_ ~ . . 4-5. i ( 9 = '._ y
.,Gi
l y . I i
- 17. Provisions for Actual Emergency: Exercise PLAYERS, i
' col 4 TROLLERS / EVALUATORS,-and OBSERVERS should not take ik ,
any actions which would preclude maintaining emergency l readiness offthe organir,ation and community. If an l actual emergency occurs during the exercise requiring a group to: terminate its participation in the exercise,
.they should notify the EXERCISE CONTROLLER.' All messages: concerning actual. emergency events should be
- preceded with "TalIS IS NOT, REPEAT, DOT A DRILL
' MESSAGE."
. Emergency contact numbers to notify of actual emergen-
.cies or unforeseen contingencies: EXERCISE CONTROLLER (Later)
-18.
- -Communications: Communications between all exercise
. PLAYERS'shall occur in accordance with the procedures'of all/ applicable' emergency response -plans. All communi- ,
. cations, including initial. telephone 1 conversations, l' , radio transmittals, Ili Com announcements, etc., should begin and end with'"THIS IS"A DRILL, REPEAT, TilIS IS A
'^
DRILL" ~.
- 19. . Compliance With All: Laws: .Inteentional violation of any.
" :lawsfis not permitted during any exercise. Exercise'-
~ PLAYERS, CONTROLLERS / EVALUATORS,'AND OBSERVERS'should comply with: all federal, state: and ' local' legal restric-
. tion's. Specifically,Jall. local traffic laws, such as speed limits, should be observed.
^ 12 0 JAvoid PropertyLEndangerment:- Exercise PLAYERS, Si CONTROLLERS / EVALUATORS, and' OBSERVERS'should avoid
.endangeringLproperty.(public or-Private), members of the
~ general public'or,the' environment. -
V ' 4 . ., 4-6 1 r Ja
21.- Min i mize-Public Inconveniences It is not the intent to arouse or inconvenience the public during the conduct of S- an exercise. Also, all communications, particularly in the public relations area, should be prefaced with "THIS IS A DRILL".
.22. Closeout'of Exercise o The EXERCISE COUTROLLER at his/her discretion will notify and release all CONTROLLERS and PLAYERS not
_ participating in the recovery. ol At -tlue appropriate point in the exercise scenario, the EXERCISE -CONTROLLER will initiate termination of the exercise. The EXERCISE CONTROLLER will notify all off-site points of contact to advise that the exercise is being terminated.
;; 23. : Debriefing and Critique 5m
.o~ Each~ LEAD COUTROLLER shall. debrief exercise PLAYERS
~ in his/her functional area.. o CONTROLLERS'within'each facility shall meet at the. HOC Cafeteria and' conduct a critique following exercise termination. LEAD CONTROLLERS shall
' designate PLAYERS who' will attend.
e f
/
1
- 3 7~ -
.'.m.2
.E '4.2 ' CaI:RCISE ORGANIZATION f'X The: exercise._ organization.for FERMEX '84 will consist of the Exercise. Director, the Players, the_ Controllers, the Evalu-a ators, Observers and Escorts as follows:
- TuE' EXERCISE DIRECTOR coordinates EXERCISE preparations; including the development of the EXERCISE plan, and the
~ scenario and controller input messages. The Director con-
..trols ~all aspects 'of the conduct of the EXERCISC; prepares a consolidated evaluation and critique report at the conclusion
- of : the EXERCISE; 'and prepares'and follows up on an itemized list of : corrective ~ actions recommended as a result of the evaluation;and critique.
THE'PLAYERSIinclude all plant'and other Detroit Edison
~
personnel' assigned to perform functions in the Emergency
' Response-Organization as described in the RERP Plan
. 1 -
"; - Procedures. HIn addition, there are .the 'non-Detroit Edison
. players =of:offsite' Emergency Response-Organizations whose roles"are' delineated'in Section 5.0 of this Manual.
y; '
~
- The<successtof'theLEXERCISE is largely dependentiupon Player reaction, knowledge of the RERP Plan Procedures, and an
. : understanding of'the exercise-Plan and_ objectives.- Some
- situations.affecting-Player action or: reaction exist at-the-time : the exercise _ play begins. However,'most-is_ introduced
- y; , through- the use of . controlled exercise message . forms and
_ : messages ' generated by Players as ac result of the RERP
~
ProceduresJfor.the particular emergency activity they, . 1 perform. 1 4-8. N
y.,8! 7, ,. J- ,
^
Simul'ated. plant parameters are provided to the Control Room
, : operators: using. plant data and status sheets. Players,
,(C T
ltherefore,Jare. responsible for initiating actions during the s ' EXERCISE according to procedures, responsibilities, and tasks
~ outlined for.thAir particular function in-the RERP Plan and
- Procedures.
" iPlayers are , reminded not to be overly concerned with the bechanics- or cause of the EXERCISE scenario. The EXERCISE is 5
' designed to ' test DetroitL Edison's RERP Plan and Procedures
~ , "and is not concerned with-the probability, feasibility, or
-detailed l mechanics of'.the simulated accident.
While the
.' EXERCISE is conducted to evaluate the emergency plan, .
- l. procedures' and training, it - is' also a training vehicle for
- Detroit Edison- personnel to practice working tog' ether and
_ -with outside organizations in a.simulatsd emergency environ-ment. _ Players should make. note of any needed improvements that come to their attention during the EXERCISE and submit ltliem'to'the appropriate Controller at.the conclusion of the j, . ., ; , I:XERCISE.- ; P1'ay'ers; will; be fidentified:by wearing WilITE arm. bands and 4A "idehtification badges
~
ICONTROLLERS areTDetroit Edihon personnel or,other. qualified m personnel' selected-to perform. functions as'follows:- t I
- .;3 .
, ;:k ,
~
gg :;- ,
- ,* 1 .
+ - y3 <
'. :, ( -
7 4-9' }h;
^+ 4, _,_,;, J, ,
5 _,,;....,,,__.,._.a_,,,,,,,,_.,,,_
4R 'l J i 4 I
- o. - The' Exercise Controller and Lead Controller Team is made
,{
up of the CR, TSC and EOF controllers. They will help 4 develop'the EXERCISE scenario, pre-written input exer-S" ; cise messages, and a schedule of controller activities. Only Lead Controllers canimodify exercise messages or initiateJfreeplay messages.
- o. TheLControllers will~ deliver " Exercise Messages" to designated exercise Players at various times and pluces during the-EXERCISE; inject or deliver additional
. messages as' may be required to initiate the apropriate
'Playerf response .and keep the exercise action moving
~ '
(( -.... according to'the scenario and exercise objectives; observe the EXERCISE at.their assigned locations;-
-w : prepare evaluation forms and submit written recommen-
~ dations'on corrective actions to the Exercise Director g - : priorito the scheduled critique. The Controllers are
) : provided with a listL oi instructions. in the Exercise
^
. - Scenario.
r' L Controllers :are identified by wearing RED aru bands and Lidentification. badges.. n C J ~EVALUATORSLare Detroit E'disons or other qualified: personnel "a [ ,
"who are. assigned.to judge ltheJeffectiveness"of selected.
< organizations', personnel, functions,'and/or activities of the
. Selection of
' lplantiemergency_ response' plan and procedures.
LEvaluators is ' based on tlieirJe'xpertise in, or. their qualifi-s
, , _ c cations'to'evaluateithe. activity or area' assigned.
When
'* feasible,; persons 1 designated as Controllers for algiven.
j - (f
. .~
- .4-10
. s
[;d, ' < -
\.
- function will also be assigned:as Evaluators of that. func-
, , etion. . Evaluators will record their. observations using an d.I._ evaluation form and provide recommendations on corrective
-actions'to the Exercise = Director prior to the scheduled scritique. They critique exercise performance on the basis of standards or1 requirements contained in the RERP Plan,
~ Procedures,'and exercise messages. They take steps whenever
- possible-to collect-data on the time and motion aspects of the' activity observed.for post exercise use in designing
. system improvements.
Ev$1uators will be identified by wearing BLUE armbands and identification badges. When an Evaluator is serving also in
~
a- Controller role, he/she will wear a RCD arm band. TOBSERVERS from1various Detroit Edison components and from s -other. organizations:may be~ authorized, on a limited basis, q fto participate.in the$ EXERCISE solely for the purpose.of observing exercise. activity for personal education. Observers
~ report ' initially; to the EOrf for : credential review and adait-tance.as authorized.. They;are:provideo with~ orientation
~
information and: appropriate exercise; publications. Escorts
.willUbe: assigne'd 'to ' observers at the Visitors . Center as
~
required. x v Observers are . identified by wearing a BLUE armband. - 4 x -
%,
- 5 g'<
, c e
-y
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s , , 14-11 L"y
c ., Requests to participate as an Observer are made in writing and contain Observer's' full name, home address and phone, and k; Compan'y or-organizational affiliation. Requests to participate as observers will be submitted to the Supervisor, Radiological Emergency Response Preparedness, no later than
.oneLweek before the EXERCISE.
~> . '
ESCORTS are designated to serve as guides for Observers.
~
Escorts'are identified by name tag or other identification. 4.3--EXERCISE FACILITIES
' Control Room
- The Control-Room is the central point for organization of exercise messages and is- the key ' to ensuring that the EXERCISE progresses on schedule.
Since it is necessary that p ^ thel emergency' escalate from an Unusual Event to the General
~
fr , Emergency level to exercise-off-site activities, it may be (' '
- necessary to postulate 'non-credible situations.
' tors should accept the exercise messages as written.
The opera-If-corrective acti'ons could be postulated tiiat would terminate-
-the emergency, they should~be identified to the Lead' Controller so.that the. scenario' progresses as' designed.
~"
; ., . The : exercise: Players are expected to " free play" the scenario to the extent practical,-but not initiate . free play messages.
f Notification's of and contact:with,. supervision,-plant
*& p ,4 h
-c .
4-12 N? . V . 7--
n, _ f 2.c
~
, . management, and_off-site agencies should be made in accor-
~
. ,u .
, -dance with the RERP~ Procedures.
ik Since there are several offsite parts of the scenario that
~ '
oepend'on propercmessages from the Control Room, the Con-troller should : review notification messages prior to their
' J
'issua'nce. Tue-Lead Controller may inject other information
- orJchange a message.in order to ensure that the drill progresses las: planned.
o { Technical Support Center and Emergency Operations Facility Tne~ Technical 1 Support 1 Center (TSC), for on-site-activities
- (see Figure 4.1) ~, t and-' subsequently the Emergency Operations (Facility-(EOF),-'forfoff-site activities (see-Figure 4.2),
Decome the' central coordination points for the emergency b l response' f af ter tlieir' activation. - TSC and EOF personnel
* ' shouldiunderstand that if the-EXERCISE is.to proceed as
; planned andfif-/the off-site organizations- are to be
" exercise ~d, itLmay?.be' necessary to= postulate non-crecible
~ situations. Thist is.done to. ensure-that various aspects of (theisite and. off-sitef emergency response organizations are 4- stested.: TSC and EOF personnel should' accept exercise
~
ay . messages asJwritten.1The^ intended response is not to explain-
* ~
'why.a situation:could not' occur, but to react asuif:it dio'.
IfrcorrectivenactionsEcould'be' postulated that.would l ~ iterminate;the' emergency,Lthey should be noted to the Lead
~
s
- jControllers.
O li 5 w . w .
,14. , ~
71
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1Tne exercise Players in tue TSC and EOF are expected'to " free i u play" the-scenario to the extent practical. Notifications
;y
, .and' contact-with_ supervision, plant management, and off-site
' ~
. agencies-should.be made in accordance with EPs. The scenario is designed to activate on-site and off-site emergency response capabilities.
.Since there' are several- off-site parts of the EXERCISE that depend onuproper messages from the Control Room /TSC/ EOF, notification messages from these contact points should be
-reviewed by the: Lead . Controllers prior to their issuance.
They.may inject other-information or change a message to ensure thatithe drill progresses as planned. _ i4.4 EXERCISE' CONDUCT ~
-The EXERCISE simulates an abnormal radiological incident at
# Fermi 2 and' starts with~an Unusual Event and escalate to a General Emergency 'and require s accidenturecognition and
^ ' classification;? assessment of 'on-site and off-site radiolog--
~
ical consequences; alerting, notification and mobilization of
-various-organizations:and personnel; in-plant corrective-actions; use: of emergency : facilities .and equipment; . effective use' of communications:(Figure 4.3); preparation of- reports, messages:and records; recommending protective action; and maintaining public . relations. The emergency:~will1then
- de-escalate to -Recovery; Status which wi11 ' terminate the'
.- , : EXERCISE.
g s
/
4-14: Y f n g
E During the course of the EXERCISE, incidents arise that
. require response-by off-site agencies and deployment of
'f Detroit Edison and other radiological monitoring teams for off-site monitoring. The SCENARIO and time schedule of simulated plant conditions is contained in Part II (Exercise Scenario) of this document. TilIS WILL BE CONTROLLED INFOR-MATION AND WILL ONLY BE RECEIVED BY Tile NRC, EVALUATORS AND CONTROLLERS.
An actual emergency-operation usually requ' ires the extensive use 'of both telephone .and radio. This EXERCISE, simulating
' an emergency, requires separate communications means for the
_ ,. Controller function. This - applies to separate radio chan-nels; otherwise, the Players could learn in advance of the situation to-which they are to be subjected in testing their response capability.. Because the demand for both telephone x and radio commanications _ usually exceeds supply, all parti-cipants must be aware of this and be prepared to accept com-
. uunications-servicesLwhich are less than desired some of the time.
~.
t
= The? telephone 11s the primaryJcommunications means and should
- be:tried'first. - Radio is secondary; however,' in 'some cases itimay be the onlyJueans. Close cooperationTand-coordination
, between Controllers ~and Evaluators is essential due to the
' number of persons who will be' assigned the dual-Controller /
- Evaluator role.
b S ^ w - h s ,- a s 4-15
- L - - . :
c ..
~
~
4.5 UVALUATION AND CRITIQUE
.p The EXERCISE will be evaluated by Evaluators, as well as the Lead' Controllers who are assigned to key locations and emer-gency response activities. This includes the Emergency Response Facilities as noted in Section 4.0, as well as emergency. response activities to be evaluated.
Following the EXERCISE, Evaluators and Controllers will present their findings at critiques, as scheduled.
; ., 'Any improvements in the RERP Plan and Procedures , training, etc., that are identified through the critique process are doeuraented by the Exercise Director and corrected by the organizations -and individuals who have responsibility for the
- areas offdeficiency identified.
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, s 4-16 E_
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- FIGURE 4.1 ,,,,,,,,,,, ,
j TECHNICAL SUPPORT CENTER (TSC) 1 i
a a -- -- -
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4
-- To MST Network CAS Centrol OSC
- SAS Room MST Detroet
~
re - r - ~ . JPIC = = EF2 TSC De ont le C.- - . ..... @ .............. -EFl
~
NOC NOC g EOF. 1 s Legend:
.- - - Faber Oposs
......... Microwave CoMe
@ 16 Dwect inward Diebng Channels
, @ _26 Detroit Constel Offee Channels
; @ . 90 Emergency Facsheios Channois
. Emergency Reeponse Facihties Are Equipped W Dersca Ring. Lacal Censrel Offsce.
and Off Premios Estensions ICSX NOC) - CTC L Continental Telecommaelestiene Ceepony
- CSX Compusensed Bronch Eschenge
- : MST Michigen SoII Telephone FIGURE 4.3 EMERGENCY COMMUNICATIONS TELEPHONE NETWORK
.p
. le SECTION 5-EMERGENCY FACILITIES AND PARTICIPANTS O i
;; q SECTION 5 - EMERGENCY FACILITIES AND PARTICIPAUTS
[
~5.1 ' EMERGENCY RESPONSE FACILITIES The Emergency Response Facilities (ERFs) have been estab-lished at Fermi 2 to assist Control Room personsel in nitigating the. consequences of accidents and responding to abnormal operating conditions; they are the Technical Support
. Center (TSC), the Operational Support Center (OSC), and the Emergency Operations Facility (EOF).
The ERFs are staffed:by the Emergency Response Organization and are activated as soon as possible af ter an eraergency is declared. The personnel in the emergency organization are
. trained according to their assigned functions.
1
'The ERFs are linked by.a comprehensive communications network ta) provide reliable and timely communications between the Control Roora, the ERFs and offsite Emergency Response Organ-izations. The communication network providen dedicated telephone' lines,' general; business-lines, intercoms, public address sp.eakers, microwave. communications, and -data trans-mission capabilities. -Communication capabilities are shown
-in Figure.5-1.
Emergency-Response Information' System (ERIS) equipment'will
'be provided:to gather,. store and display data as required in the> Control Room, the TSC, and'the LOF to aid the-personnel
[ to analyze plant conditions and to make appropriate
~
s - _ recommendations regarding protective actions for emergency personnel and the public. - 5-1
=
rV. _ The TSC and EOF .have information centers containing the
- necessary up-to-date plant records, procedures, technical 3(I"
~
specifications, and "as-built" drawings to aid emergency
- personnel in'their technical analysis and evaluation of emergency conditions.
~
The ERFs provide adequate.-space to accommodate assigned
; psrsonnel'while performing their functions. There is suffic'ient space for the operation and maintenance of the .
communications and. data transmission equipment, the data acquisition and display equipment, and the instrumentation
~
. re' quired at the respective facilities. Storage space is i ..
~
'provided for the necessary emergency supplies, protective Eequipment, plant documentation, and administrative materials.
e
' The TSC and EOF teach provide. a consultation room and provi-
[ sions for a 'small . staff of Huclear . Regulatory Commission _. u; .. E <, '(HRC) personnel. . Provisions include desks, chairs,'and
', l telephone lines.-
+. - ,
, .5 '.1.1l 1 CONTROL'ROOH-:
x , TheiControl: Room ~'is.;1ocated on the third floor of=the' Jreactor building 'and' is de' signed ' to _ meet- the ' habitability" standards =as? described'in. Chapter'6 and .
- Appendix H -of Lthe FSAR.- The Control Room contains 4
. instrumentation,'controlsf,fand' displays.for monitoring-
~
' ~
f4 -
~
tand) controlling:the plant' operating and safety l systems during the1 evaluation:of emergency conditions:and-for- > mf; ' . m* "
, : mitigating the consequences of.an' emergency.
Safe: 4" 1J73 s I(9 y- ,
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=
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~ ^ *
, *~ ^
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operativn of the reactor and plant manipulations are ? performed by licensea Control Room personnel under the supervision of the Nuclear Shift Supervisor. l Initial emergency response measures, as shown below, are j exercised from the Control Room under the direction of _{ the Emergency Director (Nuclear Shift Supervisor). o _ o Plant operations ?
'r4 o Direction and control _
I o Accident assessment - _r - a
- .E o Corrective actions E f o Radiological assessment !
k =- 5 o Protective actions ' i 4 3 o Communications (licensee /off-site response - organizations) r I 2 i When emergency conditions escalate to an Alert status, 'i coordination of the eraergency response raeasures shif ts _[ from the Control Room to the Technical Support Center
- r under the direction of the Emergency Director (Superin- [
4 tendent - 11uclear Production) . s I-D The Control Room is the initial on-site communications g 1- =- center during an emergency. It has a reliable system g i providing capabilities to the 11RC, Off-Site Emergency 3 p_ Response organizations, OSC, TSC, EOF, and all areas of y the plant. _3 h # w , 5 5-3 1 _f
=
O =
. - .- 7-'
25.1.2~ TECHilICAL SUPPORT CENTER (TSC) l N - _TheJTSCLis~the emegency' operations work area for senior
; -technical , ~ engineering, and runagement personnel; other ilicensee designated' technical and administrative support
,.;~-'
personnel;-and,a small: staff of HRC personnel. The TSC
'provides. plant management and technical support to Con-trol Room personnel and; relieves the reactor operators e of peripheral duties and communications not directly
-n -
related.to reactor system manipulations during an
' emergency. The' Emergency Director coordinates activ-itiescin the.TSCrand theJinterfaces-with.the Control
~
- Room,/the OSC,;and the EOF. TSC personnel perform EOF y f unctions for an : ALERT, and for a SITE AREA and GENERAL f
EMERGENCY as listed -below until the EOF is functional. L
;o- ' Direction and~ control' a-
[ 1 Io: :: Accident L assessment 7 <
. o Corrective actions
. Plant system engineering
~
. -o. -* y RadiologicalJ assessment;
~
o o2 -Protective actions ~(inplant;'off-site until.EOPIis'
, activated):
1 - o- SiteE ac' cess E control
' ~^' ~
3 fo CommOnications .~(licensee /off-site response 1
- l organizations)' -
42 5 _ dje: c . N , l$3 ' , 4 a.n ye --n-
.y . ->
b '
r
'When. activated,.the TSC becomes the primary onsite
;p communications center during an emergency. It has a reliable communications system providing communication c capabilities-with the Control Room, the OSC, the EOF,
- the 11RC, and other off-site agencies.
The system provides for'the immediate exchange of information on plant status . and operations, notifications to Federal, State', and local agencies and intercommunications within
'the.TSC. .The communications system consists of dedi-cated and general ~ business telephone lines, a microwave 1 . system, radios,'the plant intercom, a public address
-system, and. data transmission equipment.
. <A The TSC is located at the southeast end of the plant within.the: security perimeter on the ground floor of a two-story' office services building. The TSC is habit-able :during L postulated radiological emergencies to the sanie degree- as the Control Room (Design Criteria 19) .
a- TSC construction provides'special shielding and an llVAC' systeu designed to facilitate the occupation of all necessary; personnel- fortwinter and summer environmental 7 radiological. accident conditions. Airborne and area
~
. radiation monitors that read continuously and ' alarm -
- locally.are:provided. In the event that the TSC becomes
~
uninhabitable, TSC functions ~are divided between the-Control Room and an alternate facility such as the EOF
- as directed by the Emergency Director.
5.113; OPERATIOlinL SUPPORT CE11TER (OSC) The OSC is a designated assembly pointLnear the Control
- Room. It:is astwo-story! structure located at the north end;of the' third' floor of the' Turbine Building. The-OSC
=&;u . - ;- e
.i 5-5 c=
m: , 1
M 1.J ?. 2 ," m-: ,.
- - provides_an area for the coordination of shift h>ersonnel
.# -4 . to support emergency response operations without causing
_ m "
- congestion _ in the. Control Room.
~ Personnel reporting to
- < athe OSC normally include ~ the Fire Brigaae, the Damage
[ R Control ~and' Rescue Team, the-Personnel Monitoring Teams, the On-Site. Radiological Emergency Teams, instrument
. technicians, engineers not assigned to the' Control Room or other.ERFs, and general maintenance personnel, as The=OSC' Coordinator integrates OSC activities
- : required.
andidispatches emergency personnel on assignments as
- directed by the Emergency Director.
l The OSC has dedicated telephone lines to both the ; Ccntrol Roosa and the TSC and a dial telephone for
~
/ communications with other 1on-site, as _ well as off-site, locations.s Portable radios are also available to r
. complement or serve _as backup.to the telephones.
-f ,
- e
-In:the: event that the- OSC be'colaes uninhabitable, an area
'- ,A _
'. at-i the nortli; end of the. machine shop is designated as, 47 - .
-the alternate OSC. :The? machine (shop is located on the 7 .-n -
7' -
'tirst floor .of . the' Of fice. Services . Building.
4 # ,': ._r I 4 2 i
- w. .-
" , 5.1.4 - EMERGENCY OPERATIONS FACILITY-(EOF)
, , m 'The. EOF is' a comnuand post ' for the. overall management . of e y .theLoff-site; emergency response' including-thef.coordina-j.e -
ftion of radiological and. environmental assessments', the
"~
- determination.of.recomended protective actions for the
'public, land thi management of recoveryf operations -as 7-(~
stated.belowi, - dpgn: ,t;pibe- 9
^
i
. 6 j . t , _ .
r p k? ':l ? ' _ u i :-
m ,
..f .. g I .
^
o. 3 Radiological assessment
' ;j.g 2 4 g-p , :o. Protective-actions off-site c
> 'o' Off-site radiological monitoring
+: o Environmental sample analysis of Public information To .Commun'ications (licensee /off-site response s'gencies) .
The, EOF is ,in ~ the ' basement of the 11uclear Operations x - Center (NUC) and--is approximately 6000 feet southwest of
- the Fermi 32' plant on owner-controlled property. The EOF
~
~ -
will have the 110C as:a supporting facility wnich
-includes -the : plant . simulator, plant training and engi-M
'neering-offices, training' classrooms, space for news Y . reporters,.etc.
~
' Access is'available to the facility nf rom :two= directions via - roads under^ the control' of -
h: 1 1
-Detroit. Edison.
.. JG
. ,_ i :
;g .The" EOF has .been . designed for habitability: in the event -
- of a: postulated; accidental-- radioactive release f rom
- : Fermi 12. The design includes shielding.:(protection b', .
i f actor of : 20 ), an llVAC, system with llEPA - filters,:.~and . e;: cairborne radioactivity and~areaz radiation monitors that
. read: continuously and alsra-loc 611y to: assure that-
' personnel exposures.to radiologicallhazards do-not-
/ ,
, e xceed =.~101 CFRD 20 . limits . - ;
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,N
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- q 1 5-7 1
,s : 'iL_
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^
l 'h 24.
3 The EOF Coordinator will integrate EOF activities and
.j '
the off-site emergency response. The Radiation Protection- Coordinator is responsible for off-site
)
. radiological and environmental assessments. The 1
Environmental Assessment Team performs radiological dose
._ assessment'and projection functions using the ERIS and associated' software and procedures. A micro computer
. dose assessment software package is an available backup method.
, The Radiological Emergency Team (RET) Coordinator coordinates .the Of f-Site RET field surveys by radio, as directed by the Radiation Protection Coordinator, from s - the ' radio room' in the EOF. Direct radiation and . contam-ination' readings are transmitted prohiptly back to the RET Coordinator.
"The EOF counting laboratory is available for the anal-ysis of environmental samples collected by the RET, as
~
well asj a backup . facility to- the in-plant laboratories.
~
An extensive communications system is provided.in the _COF, which includes 1 communications to the Control _ Room,
. _the TSC, the Off-Site RETs, the_URC, the' State and local-Emergency. Operations Centers (EOCs), and intercommunica-itions~within the' EOF. The system consists of dedicated S
- me S
r s b ' 5-8' b;
- . , /
7
', m.
'and general business ~ telephone lines, a microwave
., system, portable radios, the plant intercom, a public
. 1" address system, and data transmission equipment.
An alternate. EOF is located at the Wayne-Monroe Division Headquarters, 22 miles northwest of the Fermi-2 site.
.The facility has adequate communications equipment and
.suf ficient space toiaccommodate the additional personnel required for continuity.of dose projection and decision-making capability, including coordination of the off-site teams. . Portable equipment is provided for the personnel to perform their assigned functions.
.S.1.55 JOINT-PUBLIC INFORMATION CENTER (J PIC )
^
i
--Since the plantjoperations'and technical staff must remain isolated from ' tasks that distract them from their
-immediate: responsibility of containing the emergency and restoring the plant to normal operating conditions, additional Detroit. Edison personnel assigned to organize and implenent all coumunications measures that serve the news uedia; the public; company.employes; and public officials from' Federal, State, and l'ocal levels.
~
A' Company officer who has access to all necessary information' (Group Vice President or alternate) has been
; designated:as the spokesperson for Detroit Edison ~in the
. event'of an emergency at Fermi 2. This spokesperson and his/her staff have communications access to Detroit Edison's emergency centers. Information is released to
_the news; media via this person through the Joint Public
- n ; , , . .
Information. Center (JPIC). d '. s-9
+
. . .- , .=. - .. - , .-
c.: - . . l l J In order to ensure that accurate and consistent informa-3; tion is . presented to the public, a JPIC office will be
, ' located at_the Monroe County Community College. The
;public'information officers from Detroit Edison and Federal,- State, and County groups may congregate here to review all public information releases.
-5.2 . PARTICIPANTS
- Participants are listed as onsite Detroit Edison FERMEX 'd4
. and of fsite- (all other) .
.c. 5.' 2.1 ON-SITE - DETROIT EDISON COMPANY if Fermi 21
. _ . .o ; Control Room (CR)
- L ,
.- o L . Technical / Support Center (TSC)
, _}, ;o .' Operational Support Center (OSC)
.o' . Emergency ' Operations Facility; (EOF) o ~ Joint Public Information Center (JPIC)
-o' . Detroit Edison' General Of fices o- EmergencyjResponse: Teams
~ !;F - On-Site and Off-Site Radiological-Emergencyc
' Teams (On-Site /Off-Site RET) -
,N-
- 5-10 r
3 _h .
- 2. ;- . . -
Personnel Monitoring Team (PMT) [ ~ - Damage and Rescue-Team Fire Brigade Uuclear Security Force
- 5. 2. 2 OFF-SITC-(OTHER THAN DETROIT EDISON COMPANY)
- s Federal o Huclear Regulatory-Commission (NRC) o- -Federal Emergency Management Agency (FEMA)
- u-o Regional-Advisory. Committee _(RAC) chaired by FEMA
-and' comprised of the'following:
Federal Emergency Managenent - Agency- (FEMA); -U. S. Department of Agriculture; U. S. Department of Energy . ( DOE); - U. S. Environmental Protection Agency (EPA); . U. S. Department of Health and Human
,- Services; : U. S. ; Department of Transportation; U. S.
^ Department of'Co.nmercer.and Nuclear Regulatory y '
- Commission (NRC).
)
State of Michigan o L- Department 1 of State Police (Emergency Management Division)-(Lansing) p ~ r & 5-11~
m;.
" :. - j. :
1 O lT Y ~ .
- o~ FlatfRock State Police (On-Scene Emergency
, g, . .
Loperations Center)' lrwm, .
-o- ' Department of Agriculture
.o Departiaent . of Commerce ,
Lo Departiaent of Military Affairs o Departiaent;of Natural Resources o- Department of Public Health (Primary state agency
, for coordination of radiological services) w:- o 'Depa rtment of--- Social Services o Department of' Transportation y
,i~
State of Ohio y- '
~
"~ '
? Adjutant 1 General's' Department, Ohio Disaster Services
; :- : Agency:-
Canada "o Province of-Ontario, Ministry of the Solicitor i General,f Emergency Planning gg f 'o Ministry ofLLabor
^
. 'io Local Canadian government' y %- e' r* ?
5
.4. .,
s 5-12' w 2-- -a
.. c _
Local
' 'o . Monroe County
~
-'o . Wayne' County
[.~ - City of Flat Rock A c.: :- City of~ Gibraltar City of Rockwood
-o Brownstown Township
- t. .
'o Frenchtown Fire Department
- Private
.o ~ luaerican Electric Power Service Corp.
, o. Consumers. Power Company.
- 'o Sargent.& Lundy1 Engineers
.s
'o Impell
~
.g n
g 4-2 ",i(~st- +i - I; s
, '5-13 t
.J 1
m r l- ,
~ '., 9 16 2
h, Z t S
+
g' CAS/SAS TSC- OSC EOF .rtC ONees
% hw
'! l l l l l e.e
-Comnev ' -
Sherdi i 5' EfeS Itsemed
'g 4900 tenhuun
[ m a
+
2
. enese Pthan 2
f 4
- i e
-h 9 FIGURE 5.1' DIRECT RING TELEPHONE CIRCUITS BETWEEN EtERGENCY RESPONSE FACILITIES
,r :
L
.9 e,-
- ( .
'f SECTION 6-MISCELLANE0US-
cz- [1l_ :e L SECTION 6 - MISCELLANEOUS f-
-6.'l TRANSPORTATION Air:
.o.
' Detroit Metropolitan Airport (30 miles from Fermi 2) oL Toledo Express Airport (45 miles from Fermi 2) o- -Persons traveling by air to. Fermi 2 are reconlaended to arrive at Detroit Metropolitan Airport. It is closer to the plant and travel to Fermi 2 via auto is relatively easy.
Busi o . Direct bus service by Greyhound and Trailway to Detroit,
^
Toledo and Ann Arbor. Train
~
L o Amtrak connections in-Detroit, Toledo.and Ann Arbor
. 6.2 'HOW TO GET TO THE SITE Car o Refer to Figure 6-1,'" Fermi 2 Location Map" and~
-Figure 6-2, " Fermi 2 Location Detail Map"..~
, :: ~, 6-1 .
sp - c;7 s-V o- The plant'is:-35 miles southeast of Detroit and 27 miles V
-U' -i north of Toledo.
d. 7 o l Fermi 2;is located approximately 5 miles from I-75 via the Newport Road Exit or.the Nadeau Road Exit. Persons
-traveling-I-75' South or.I-275 South may choose to use
' the Newport Road Exit or persons traveling I-75 South may also' choose :to use the Nadeau Road Exit.
- -- If using the ' Newport Road Exit , take Newport Road (Swan Creek Road) east to North Dixie Ilighway south.
J iFermi-Drive'is about-two miles on your left. c'-
.- Iflusing the Nadeau Road Exit, take Hadeau Road east
. to North Dixie :ilighway., north.
. Fermi Drive is about
-three miles ~on your right.
. -- o Persons (using I-75, North sould ex'it onto llorth Dixie Ilighway ? north -(turn . right ) .-
~
Fermi Drive is about-5'
-y- -
' miles:on your.right.
4
- l6i3CACCOMODATIONS s.- :o ( Detroit Metropolitan Airport -(approximately 30. miles Jfrom Fermi 72)l J- Abbey-Inn-
.8230-Merriman Road-
_ (313).;729-7600 Q a ic
,,~
- lI( ,
< - . oa y ~ .y f'. .; -
O lE.
T 4
)
- Ililton Airport Inn -
, 131500' Wick Road k <
i(313)l292-3400 l J -Iloliday Inn
- 31200' Detroit Industrial Expre.ssway (313)-728-2800 l
- Ifost' International Hotel
- . Detroit 1 Metropolitan. Airport (313) 941-9400
. ; e
- lloward-Johnson's y ,.
45945 Willow-Run Expressway (313)-697-9144
- hichigan llost, Inc.
Detroit ~ Metropolitan Airport (313) 941-2913
+t
-Ramada Inn z u270 Wickham-Road J(313)729-6300 Sheraton-. Motor: Inn Airport l8600 Merriman Road 4
-(313)s728-7900-1 4
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- b. %-
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~o Monroen(within lu miles of Fermi 2) l d ' - !!oliday Inn 1225 North ' Dixie flighway (313) 242-6000
; 11oward Johnson's
'1440 North Dixie-Ilighway
- 4. Toll Free: 1-800-654-2000 (313) 289-4000
- Knights Inn 1250 North Dixie flighway (313) 243-0597 o . Trenton ~(approximately 20 miles from Fermi 2)
~
- Best1 Western Hotel
. 21700-West Road V (313) 676-8000
-Toledo' Express' Airport The' Airport!is located ~18 miles from downtown Toledo.
It is-another'27 miles to FermiE2. Persons arriving at1 Toledo
, Express Airport.would be best served by_ hotels in downtown Toledo-or in Monroe.
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s - (: SECTION 7-REFERENCES, ABBREVIATIONS, D E F I-N I T I O N S t t O g i u
Yi. l
._ +
- SECTION'7 ' REFERENCES, ABBREVIATIONS, DEFINITIONS
.f
7.1 REFERENCES
- 1. . Radiological' Emergency . Response Preparedness (RERP)
Plan --Letroit Edison, Enrico Fermi Atomic ~ Power Plant Unit 2-(Rev. 3)
- 2. . Radiological Emergency Response Preparedness Implementing Procedures 3.- Michigan State Emergency Preparedness Plan
.4. ' State.of10hio Emergency Plan
- 5. County of Monroe Emergency Operations Plan
.6. County of' Wayne Emergency Operations Plan
- z.-
'7.- .Brownstown-Township Emergency ~ Operations Plan
- u. '10 CFR Part -.50. 47 and 10 CFR Pa rt 50.47 Appendix C
'9. 10 CFR 100
- 10. - 44 CFR 350.9
. 11. - HUREG-0654-FLMA-REP-1 6
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SECTION 7 - REFEREllCES, ADDREVIATIONS, DEFINITIONS i-17.2- ABBREVIATIONS
^
AB- - Auxiliary building : AC-
-- Alternating Current ACRS '- Advisory Committee on Reactor Safeguards ADS - Automatic Depressurization Systera APRM~--Average Power Range. Monitor
' ARM ' - Area - Radiation Monitor '
CAM -LContinuous Air Monitor CR - Control' Room
..- CSS -Core Spray System CWPH - Circulating Water Pump House DC; -Direct Current 4 , -DOE. - Departraent ~ of Energy -
.DPM -f Disintegrations per- minute EAL. - Emergency Action' Level
'EBS -- Emergency Broadcast . System -
ECCS - Emergency Core Cooling System
'EDG'4- Emergency Diesel Generator
-EECW.-' Emergency' Equipment Cooling Water ENS. '- Emergency Notifications System (HRC)
-EOC - Emergency Operations Center EOF - Emergency Operations Facility EPs. - Radiological. Emergency Response Preparedness
-Implementing Procedures EPA - Environmental Protection Agency EPAs -' Radiological Emergency Response Preparedness p
Administrative Procedures [' EPZ Emergency Planning Zone g - ERF. - EraergencylResponse Facility ERIS --- Emergency Response 'Information System - m+ :: c ;EsF. -- Engineered Safety. Feature
- FEMA -. Federal Emergency. Management Agency
~
s 7-2 1'
'A
L s, ,. A . FRRP ' Federal' Radiological Response Plan FSAR - Final Safety Analysis Report
- < g7 '
-T FW -- Feedwater.
. GPM - Gallons per minute HP - IIealth Physics
- HPCI - liigh Pressure fCoolant Injection
, IIP 14 - Health Physics Network (NRC)
HVAC - Heating,.: Ventilation and Air Conditioning
, 'IEC - Instrument & Controls
.- ICRP -- International Committee on Radiation Protection INPO Institute of --Nuclear Power Operations p : IRM - Intermediate Range Monitor
'. JPIC'- Joint Public Information Center
- JPIT' ; Joint Public Information Team wCO- -1 Limiting Condition of Operation LOCA-- Loss of Coolant Accident LPCI;- Low Pressure Coolant Injection LSSS - Limiting Safety System Setpoint
- MCCC - Monroe County ~ Community College hEPP - Michigan Emergency Preparedness Plan
' hREM -' Millirem'
- MSIV -; Main Steam' Isolation Valve -
uci/cc~ - Microcuries per cubic. centimeter uci/g - Microcuries per gram. - uci/sec'- Microcuries per second E - NASS - Nuclear Assistant Shift Supervisor NSRG - Nuclear Safety Review Group i RW - Radwaste LRWB,1 - Radwaste Duilding SB - Service Building i SBGTS/ SGTS'- Stand-by. Gas, Treatment System SPDb - Safety Parameter Display System
-l c- N
)
~'
7-3 ,. e I-',
. r-t S10s ' - ~ Source Range Monitor
- SRV - - Safety Relief' Valve
~!
SSE - - Safe Shutdown Earthquake STA..- Shift Technical Advisor TB' - Turbine Building TLD - Thermo-lurainescent Dosimeter
~
TSC -- - Technical Support < Center
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~7.31 DEFINITIONS s
. ' ALERT: LThe second level of. emergency classification.
Indicates events Jare in progress which involve actual or
- potential substantial -degradation of plant safety levels.
ALIQUOT - A fractional part of a larger substance; a
'~ -sampling..
ALPHA' PARTICLE: A positively charged particle containing two
' protons'and-two' neutrons ~(the nucleus of a helium atom) eraitted by1.certainL radioactive. materials. Alph'a particles
- Jcan be stopped by a' sheet of paper, and thus are a health
- concern only--if emitted by radioactive materials ingested
~within :.tlie body.
.n
~
- " g -
ASSESSMENT ACTIONSt. Those actions taken during or after an-
! accident to obtain and ' process information that: is necessarg
[" -
., s
" to make decisions ' to imploraent specific emergency measures.
.t.
ATh0 SPHERIC STABI'LITY CLASS: See Pasquill Stability. Classification. .,
-ATOM: The basic component--of all watter; the smallest part-os ' of an element that has all the chemical properties of that element. 2 Atoms.in turn are made~up of protons,-neutrons and electrons.
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(. i; - I BACKGROUND RADIATION: Radiation-from natural sources M,- iincludingi cosmic rays, radioactive elements within the kh ' ; earth's' crust, and organic materials in our own bodies.
l (Normal background radiat' ion for Americans averages 100 to R.i 1250 - millirem per 3 year.;
iBETA~ PARTICLES- ' A negatively charged particle einitted from
. - ~ - the U nucleus - of lan atom during radioactive decay. ~A beta
# particle is an electron which has a mass equal to 1/1837 the
. mass;of a proton. . A beta particle can- be stopped by less
* 'than-an inch of wood:or a thin sheet of aluminum.
c3 : BOILING' WATER REACTOR (BWR): ' A nuclear reactor in which i , ; water;is'. boiled ;in the core; the resulting steam drives a turbine toLgenerate electricity. Fermi 2 uses a boiling
. water reactor.--
- g
' BREEDER REACTOR: A~ nuclear : reactor that makes pore fuel than
.itE uses to generate energy.
- r. .
T
' CHAIN ' REACTION - J A self-sustaining serias of events occurring .
Lwhen.a? neutron. splits'an atomic. nucleus,-releasing-sufficient
~
4 . neutrons to~cause atEleast.one other nucleus to split-in the same way. [ jCLADDINGs. The outer metal jacket of. nuclear fuel rods. It
~
prevents corrosionLof the fuel'by the coolant.and'the release offfis51on'~ products.into the' coolant. The most= common. p 4
. cladding?materialtis zircaloy, a zirconiu..Jalloy.
COLD SHUTDOWHz The condition of a reactor when :the fission-
- P >
1 process has been . halted by . the insertion of control rods ~1nto thefcore and decay; heatfin .the core has decreased to the er r p % y a ' 6
.w-S
, so 1.
(( x g s
~
y. Jpoint .where natural- circulation can keep the coolant water 7 - -below the boiling point 1(212*F or 100'C) at atmospheric-e < e
;m . pressure. ,
- CULLECTIVE DOSES The. sum of the individual doses received by
. . each'uember of a certain' group of population. It is calcu-11ated by; multiplying the average dose per person by ' the anumber of: persons within a specific . geographic area. Con-
'sequently,: the ' collective dose is expressed in person-rems.
- % 4 For example,na',thousand people each exposed to one rem would
-have a: collective dose.of.1000 person-reus.
4 col 3DE13 SATES L Water that has been condensed from steam af ter
^
, g, passing ' through the ' turbine 'to the condenser. This high-7 purity . water fis then. puraped to the reactor for reuse.
.CONDENSATETBOOSTER PUMPS: Puraps located between the conden-Laate. pumps cand . the _ raain' feedwater pumps.-
l} . . .
.CONDENSATEiFILTER/DEMINERALIZERSt- ' Devices which remove dis-y solved minerals from the: water of the condensers prior to
- being ' returned to 'the core.
s CONDENSATE-PUMPSt. , Pumps inithe'reactorifeedwater. system that-4 pump '. water from the ; condensers to; the condensate filter /
^
'demineralizers.
4
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^
CONDENSER: L A device that cools.:steau..to- water af ter the 1 : steam has passed through the turbine. s CONTAINMENT: Thef structure - housing the nuclear reactor and
', .' Jits supportive equ'ipment. It ? is' designed to contain ~ radio-ws ~ ' active ~ solids,f gases and ' liquids which might: be released from
.th'e reactor c syst'emin an accident. -
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- s J1 . eQ < CONTAMINATION : ; Ingestion, inhalation, or direct contact with
[. $ iwater,yair*,xsoil,-or-tangible objects which are emitting
][' fionizing-radiation.
~
A contaminated object has more than an ( ' 14+n festablished level:of radioactive material adhering to its n surface.c
- ~ ,
f iCONTROL ROD 7 A' rod-containing a material such 'as boron-or
. 4. " ~ ;
'hafniuni' and used to control the'. power of a nuclear reactor.
By? absorbing neutrons, a control rod, whenLinserted into the II' ' ' ' f uel? core, decreases' or halts .the chain reaction by which the
' ~
'freactortgenerates heat..
,c_
fCONTROL' ROOM: The principal on-site location from which the q_} jfreactor is, controlled and from which effective emergency Jcontro1' direction is given. The control room is shielded and
,j . * ; ventilation is Lcontrolled to. afford protection for operating 4
y personnel'against external: radiation and airborne radioactive
., materials in the-event.of 4 major. reactor accident..
H is , ' - ~~ CONTROLLED AREA:
~
The land area surroundingLa nuclear plant
~
' ' +
5, c ,<which'isiowned and secured by_theiutility.
, 5 * -
Each.
~
J', COUTROLLER : A member off an f exercise control : group. _ f controller may'beiassigned to one or more activities or D; functionsifor~the purpose.of; keeping the; action going i' < according L tof a ' scenario ~, resolving differences - (acting as an s
' ~
q'
'Lumpire),l supervising and!otherwise assisting as.needed.
?i-s, - -
~ COOLANT: -Liquid or gas,c'irculated through a~ nuclear reactor
~
; -
- to ressove .. orf tra ns f e r . he'at .
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, 7-8
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COOLING TOWER: The structure where non-radioactive water i g which has been heated in the condenser coil is circulated for S cooling and then returned to the condenser of discharged into [ a body of water. Cooling towers are now common to most newer . power plants, whether they use coal, oil or nuclear fuel to make steam. T!
. CORE: The part of a nuclear reactor containing the fuel A
~
which generates heat by fission.
,4 .
CORE DEGRADATION: Iupairment of the central part of the E reactor that contains the fuel assemblies, usually resulting ( from reduced levels of coolant or breach of fuel cladding. If
. y n
3 ' CORE MELT: The situation in which all or part of the core
.n becomes overheated to the extent that the fuel melts through 5 the cladding.
CORRECTIVE ACTIONS: Emergency measures taken to terminate an Q, emergency situation at or near the source of the problem to h bring tne plant to a stable condition and to prevent an f uncontrolled release of radioactive raterial or to reduce the [ magnitude of the release (e.g., shutting down equipment, fire fighting, repair and damage-control). . - 9 5' = COSMIC RAYS - Very powerful radiation that continuously s showers the earth from outer space. The rays thgt come frou ; space are mostly protons (the heavy, positively charged parts 3 of atoms). As they trave 1'through the earth's atmosphere, ' however, they strike its atoms,-resulting in the emission of = a variety.of atomic fragments. y
=
CRITICAL' MASS: The smallest amount of fuel necessary to
~
sustain.a chain reaction. {._ a m
=
m 7-9 _ 4 mm..m- m
.~
<ir CRITICALITY: The point at which a nuclear reactor is just capableLof sustaining a chain reaction.
'n(- i
-CURIUs~ A ' unit of the intensity of radioactivity in a material. A curie is equal to 37 billion disintegrations i each second,' which is the disintegration rate of one gram of the radioactive element Radium.
l R DECAY IlEAT: Heat generated by decaying radioactive products
'of the fission process.
' DECONTAMINATION:' ' The process by which the body or an object lis relieved'of substances containing radioactivity.
DESIGN BASIS ACCIDEllTS1(DDA): llypothetical accidents evalu-
~
0 , ated during the safety review of -nuclear power reactors.
~
r Plants are required to have safeguards that will ensure that
. _ : radiation releases off-site willibe within NRC limits should.
4 any of these accidents occur. L,
, ID'W' E POINT TEM'PERATURE: The temperature at which- a vapor
- begins to: condense.-
t ,') t ,
~-
' DOSE , The .-amount of . radiatic n exposure received by ' an
- ;in'ividual.-
d Sy b: y - V DOSE ASSESSMENT,2- The; process of estimating- the amount of
- , radiation; a' person with- potentially receive as a result of 'a
^
;Wi radiologica'1_ release.
E
' ~
, DOSE RATE METER:- A metering ~ device used to measure the 4 : ' amount of . radiation exposure received over a specified , period
;of; time'(e.g., 50 millirem /hr.)~.
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~
r 1
~
.Qdj; :. :: - t. DOSIMETER: =A device-which can be worn to measure the radiation : dose- a person receives. Dosimeters can also be xd:sd to: measure the radiation dose at a location over a period of:tiie.
~
' DRILL _ A supervised instruction period aimed at testing,
- - developing and maintaining skills in a particular operation.
3
-EFFLUENTS: Waste materials (such a smoke, steam, liquid l industrial refuse or sewage) discharged into the environment,
.especially-when serving as a pollutant.
L.
' ELECTRON ' A subatomic particle With a negative electrical
.. s charge .and 'a mass 1/183T that of a proton.
~
, EMERGENCY-ACTION LEVELS: These correspond to projected doses to the' population'at risk and to specified initiating conditions at-the nuclear plant. They provide fcc the.
7 actions tot be -taken by the. utility or governnental units Y -'under'certain conditions .- EEMERGENCY CORE COOLING SYSTEM : A series of backup safety 3..
- systems'cesigned to dump thousands of gallons of. cooling Lwater;into the reactor, thus. preventing overheating of the coreLin'the event ~the normal core' cooling system. fails.~
jg & I , . . EMERGENCY DIRECTOR: The'ind'iv'idual Uho directs' corrective
~ actions?from the Control' Room (or'from the Technical Support f..
4 / W CenterLwhen itLis activated).. ,
, < .EMEkGEllCY OPERATIONS CENTER-(EOC): The protected site from o< / 'which. government;' officials exercise direction and control in
+ b ,4 _x~ -an' emergency.. s P N A
. f
c,~ ,
. 7 _111
('l, ' {.' - h,[ ' ]$ .. ' ih, , ' l-L _
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EMERGENCY OPERATIONS FACILITY (EOF): The facility used by J
,( the utility for direction and control of emergency and
< ' recovery: activities with emphasis on the coordination of 1
.off-site activities, such. as dispatching mobile radiological emergency monitoring teams and communications with local, I
state, and Federal agencies and other outside support. 7 EMERGENCY PLANNING ZONES (EPZ): The land areas encompassed within 10 and 50 mile radii of the nuclear plant, in which
; protective actions' may be necessary to protect the public in
'the event of a nuclear plant accident. The 10 mile zone is referred to as the plume Exposure Pathway; the 50 mile zone ,
; is termed the Ingestion Exposure Pathway.
-^ _
. EMERGENCY RESPONSE FACILITY: Any of several on-site and off-
~
site centers which are activated to coordinate emergency actions. Included in this category.are the Control Room, Technical Support Center, . Operational Support . Center, 4 Emergency Operations' Facility, Joint Public-Information
. Center and state and local Emergency Operations Center.
e ,- ate ENRICHED FUEL: Uranium which has been'. modified by increasing
-the concentration of the ~ fissile isotope, -uranium-235.
. Enriched fuel is more able to' sustain a chain reaction and is' ,
use'd as the fuel for' light water reactors.
-FERMI 2:~ Detroit Edison's nuclea jower plant, located near.
Newport, Michigan.
-CVALUATOR : A member of an exercise t auation. group. He or s 4 she nay also serve in a dual capacity as tmth a Controller
. and 'an Evaluator.: Each Evaluator.mayjbe assigned to one or lmore: activities or functions for the purpose of evaluating, 4 recording,-..cr.itiquing, and making recommendati6ns for improvement.
- p -
4 7-12
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t; f ..L , ENVIRONMENTAL SAMPLING: The acquisition of liquid and gaseous samples from primary containment for the purpose of I determining and monitoring reactor status under accident
.. , conditions.
EXERCISE: A controlled event which tests the integrated capability and a major portion of the basic elements existing within emergency preparedness plans and organizations. EXCLUSION AREA: The nuclear plant property, including the site, _ out to a radius of 915 meters, which meets the 10CFR100 definition.
~
FEEDWATER: Condensate water that has been reheated and is pumped to.the reactor for steam production. FISSIONS: The splitting, or breaking apart, of a heavy nucleus into, usually.two,_but sometimes three, new nuclei. When"a heavy nucleus, such as that of a uranium atou, is split in fission, large amounts of energy and one or more neutrons'are also released. FISSIONS-PRODUCTS: The nuclei formed when uranium or _ plutoniuhi is' split by. fission in a nuclear reactor. Most-fission products are radioactive. FISSION PRODUCT BARRIERS: ' Structural deterrents to the releasesoffradioactivity'into'the environment. The_three
- primary barriers are:; (1) the fuel. cladding, (2) the reactor pressurer vessel,c and (3) the containment.
a
'FINA6 SAFETYLANALYSIS REPORT ~ (FSAR): A document that
. describes the reactor and its safety ' features. The report is
* . submitted to ' the NRC as' a part 'of the requirement for an operating License.
, I 7-13
? -
-? _ -
r~ 9 )
- f. 'P FOSSIL FUELS: Coal,. oil, or natural gas. These fuel's are referred to as fossil fuels since they are the remains of l plants'and animals that lived on earth hundreds of millions of years ago.
F FRISKER: An instrument similar to a geiger counter, used to
~
detect the presence of external radioactive contamination. Used primarily for personnel monitoring.
' FUEL ASSEMBLIES:' Fuel rods bundled together. The core of a large commercial nuclear reactor contains several hundred f uel assemblies, and depending on the model, each assembly can contain 49 or more fuel rods.
. FUEL DAMAGE:- The failure of fuel rods (cladding, structural or fuel material) which may or may not result in the release of:the radioactive fission products trapped inside the fuel rods.' Fuel-damage'can occur'without a melting of the reactor's uranium.
f! FUEL MELT: The melting of some of the uranium oxide fuel inside a reactor. Melting occurs at 5000*F and above. FUEL REPROCESSING: .The' processing of used reactor fuel to chemically separate the reusable uranium and plutonium from the' fission. products. FUEL RODS: ;Long tubes,,usually ofca zirconium alloy, which [ are filled with -thimble-sized pellets olf uranium fuel.
^
~ FUSION: .The' nuclear combination of the nuclei of two atoms to ' form more- massive -nucleus. The fusion of light nuclei r -such~as hydrogen. release large amounts of energy, but no
~practicalineans has.yet been. devised to use fusion as a controllable source of energy.
3
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~
GAMMA RAYS: . Penetrating electromagnetic rauiation elaitted from:the nuclei of atoms in radioactive decay, similar to Eb very high energy X-rays.
~
' GEIGER COUNTERS - JLn instrur nt, named after one of its i l
' ir.ventors, for detecting . radiation. It contains a smal3 tube )
of gas which conducts electricity when struck by ionizing ; radiation. This pulse'of electricity operates an indicating
. .o meter and can be amplified to produce an audible clicking
. sound.
' GENERAL: EMERGENCY: The fourth and most severe level of emergency; declared by.the utility if an incident at a nuclear power plant' results in potential or actual radiation
= release that.could affect the general public.
'llALF-LIFEs ~ The t ime. required for a radioactive substance to s lose . 50 % of ~ its activity by decay.
.c . .
- V ,
-HEALTil-PHYSICS: The practice of protecting humans and their environment from the possible hazaros of radiation. .
110T:: Luuclear industry- slang for anything that is
~ ~
7 radioactive.- w{ , ,- llOT'SilUTDOWN-(OR HOT STANDBY):' The situation in which the ~' controllrods'have'been inserted"to bring coolant below.the
' boiling point -but. reactor vesself pressure' is not reduced to
~
w ' i # '
' atmospheric-pressure.:
j~
.i '
M1 ;- INGESTION ' EXPOSURE- PATilWAY: .The principal exposure-from this ({*' pathwayJ would .be from; ingestion of' contarainated water' of . ifoods,1such asimilk or-; fresh' vegetables. The. time.of-
~
potential exposure ..could range in length from tours-- to u months.
's ~
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~
r ~
t. e; ;* INGESTION DuSB: The amount of radiation which conce'ntrates
;in the vita 1Eorgans Jf the body, usually through ingestion of
~
contaminated d food supplies or drinking water. IODINEi 131: A radioactive isotope of iodine, with a half-life of 8.1-days. ION: K Anl atom or group of atoms to which one or nore elec-(trons are added or subtracted, to produce an electrically charged atom. IONIZING RADIATION: Radiation capable of displacing electrons.from atoms; the process' produces electrically-charged atomsDor ions, and can affect chemical changes.
' Forms of ionizing . radiation include gamma rays, X-rays, beta particlesfand alpha particles.
ISOLATION (OR CONTAINMENT ' ISOLATION):; The closing of all penetrations toe containment to contain any radioactive (d)$,. o .' .. . .. jgf fj3 : materials which might'be released in a nuclear accident
' a c, . inside;thefcontainment: building.
~'
' J ' ISOTOPES: ' Different forms.of;the same chemical element which e ; are distinguishe' .d by ' having dif ferent numbers. of neutrons - in
^
.theinucleus.}'A single element maychave many-isotopes, some
, " or all of':which may , be' radioactive. For example, the three
;isotopesfof hydrogen are_ protium,l deuterium.and. tritium.
-Tritium is- radioactive. i 1
. JOINT PUBLIC 'IHFORMATION CENTER E(JPIC): 'The off-site news g'
i l
~
center' whicn assemblesnrepresentatives from the . utility,
~ ' state;and? local 1 governments, and various news media.-
i l
- 1 1 KRYPTON- 851 ' A. radioactive nob 1'e gas, with a hal'f-life ~ of l
~
fl0.7 ? years','-whichlis produced in ! fission - (a fission product) .
<{ ._f._.
- 7-16; c ~
1
e 1 4 .- s ' r ,It-il's not absorbed.ea'sily by body tissues and is soon elim-
.inated by'the. body-if inhaled or ingested.
l
.LIGi!T WATER REACTORS:. Nuclear reactors which use light water
~
;g, 'as f aL coolant ' and/or moderator (as opposed to heavy water, 1which;contains' deuterium). Nearly all the commercial nuclear reactors .in _the United States are water reactors. All PWRs and'BWRs:are'of..this type.
- .LUSS-OF-COOLANT ACCIDENT: An accident involving a broken e >
pipe, stuck-open valve or other leak in the reactor coolant
-system 'that 'results in a loss of cooling water.
. MAXIMUM PERMISSIBLE DOSE: An established limit on the p
radiation': exposure a' person can legally receive from any sourceiof radioactivity ~ such as a nuclear power plant.
- MEGAWATT: - The 'raeasure of power . (usually electrical) equal to
.oneimillion' watts.
, -W , 3 DMELTDOWN:- 'See Core' Melt or Fuel Melt. . D '- MET-TOWERS'(METEOROLOGICAL TOWERS):- Steel towers located to'n-siteJwhich'arefequipped:with.. instrumentation to measure-M ' wind; speed,iand " direction, air teraperature precipitation,- dew
. point?teuperature and sigma'theth.
u* , 1 MILLIREM (MREM):: - A : unit ~ used tto' measure radiationJdosage,
~
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~
r equal f tof;1/l'000 of ' a ' rem. ' Rem stand'sifor Roentgen Equ'ivalent~
; Man,f a' measure of radiation 1 that) indicates . potential impact I:- ., 7.
.f Lonfhuman cells / A chest?X-ray exposes la person to.between)20-
+g '
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- MODERATOR: A Laaterial used in nuclear reactors to slow down the~ neutrons in order to increase the probability of capture by: a fissionable nucleus to produce fission. Water and )
carbon are often'used as nioderators. !
, i
-NEUTRON: Ar. uncharged particle in the nucleus of an atom, with a mass rearly equal to the mass of a proton. Neutrons vrei the particles which sustain a chain reaction in a nuclear
- - rea ctor.
NOBLE GASES: Gases which do not react chemically with other
!saterials. The. noble-gases are helium, neon, argon, krypton, xenon and: radon.
.w L NUCLEAR-POWER PLANT: A' facility using a nuclear reactor to l produce' heat for the: purpose of generating electricity, usually .via: steam and a turbine and generator.
- g. ,; NUCLEAR REACTOR:' ~ The device ~ in which fission chain reaction
- can.'bel. initiated fmaintained'and controlled.
f
~
. NUCLEAR REGULATORY COMMISSION (NRC): ._An agency.of the FederalTgovernment which has_the authority to-license, i
s -regulate, inspe'ct and oversee safety-related activities of nuclear power. plants.-
, 7_y; _q NUCLEUS : The -core or; center of' an Latom',; containing. all the
~
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- =j 'g ~ protons and.neutronsiin.:that-atom.. Although;the nucleus is-
% , only about'1/10,'000 ofithe1 diameter of an atom, it contains
', :nearly5all the--mass'offthe atom.,
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- OFF-SITE:
~ ... -
Areas,which lie outside-theicontrolled-area. A .7 LON-SITE:~ Areas:wh'ichilie1inside.the controlled area. F- 4 g Q- 4: ~ 1 18-P . ' (f\ Y Y
- m. ,
~ ,
c -( i- : OPERATIONAL SUPPORT CENTER: . An emergency response fa'cility
-which serves as an assembly point for shift support personnel L 5' (e.g'. ,1 auxiliary ; operators, technicians and fire brigades) .
-It is also a meeting place for selected emergency response
- teams, and a storage area for emergency equipment and
; supplies.
. OWNER-CONTROLLED PROPERTY:- See Controlled Area.
-PARTICIPANT: An individual who has some part in an exercise, whether.as a; Player, Controller, Evaluator or official Observer.
'PARTICULATES: Minute radioactive substances suspended in air or water.-
PASQUILL STABILITY CLASSIFICATION: A method of classifying
. meteorological conditions, .used for calculating plune
. dispersion.
[ PLANT AREA: The area internal to Fermi 2. PLAY,~ PLAYERS: . The' theme or scenario'of an exercise,'anu ithose whoLcarry out' roles-in it. x _, c_ ,
. PLUME EXPOSURE PATHWAY: The principal exposure sources for
- this' pathway are (1) wholet body . external exposure to' gaiama u- .
radiation from. the' plume and from deposited iaaterial and (2)
~ inhalation exposure -f rota the ~ passing radioactive plume. The 7
time ofopotential exposure could ran99 from hours.to days. s . 1 - PLUTONIUM: ;A heavy metal which.no longer exists in nature
.buttis produced:inside a nuclear reactor.- It Jis made when
?the uranium isotope,U-238: absorbs a' neutron and then under-go'e s : subsequent radioactive decay. Plutonium is a nuclear ifuel.
4 . 7-19 h' '
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J th,.'.,, Materials that strongly absorb neutrons.' They
*^ "POISOIIS"
- 'are used.to-control or stop the fission reaction in a nuclear
)b
~
. reactor.
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POPULATIOli AT RISK Those persons for whom protective action
- are or=would be taken.
. POST-ACCIDEllT GAMPLIliG: The acquisition of liquid and
- gaseous . samples f rom primary containment for the purpose of
~
. ' determining and . monitoring reactor status under accident conditions.
POTASSIUM IODIDE (KI): A chemical which is used as a source J. of non-radioactive iodine. This non-radioactive iodine
)"
readily enters'the thyroid gland when ingested. If taken in sufficient' quantity prior to exposure to radioactive iodine,
/it. canisubstantially reduce the amount of potentially harmful
~
~
m., radioactive ' iodine-131 absorbed by' the thyroid. JPOWER GRID: 'A network of electrical power lines and associatedfequipment ~ used.to transmit and. distribute
; ~
' electrical? power.
PRESSURIZED WATER: REACTORS (PWR) . A nuclear . reactor system. 71
~ , .in wh'ich = reactor . coolant water ;is kept under high pressure to- -
;;p A m e : ,p gg g .- g .s . he ' @-ummme wm
'formsisteam.in'a separateLloop through a steam--generator. ,
Tnis steam'isLused'to drive a turbine.
- E 2 PROTECTED AREA: That? portion of.the controlled area in.close proximity-to thel major' nuclear: plant. facilities (including i s; "theJReactor-Building,: Auxiliary Building,<' Residual. Heat
~
' :n" - NRemoval Complex, Technical . Support Building) :to ' which access
~
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.is restricted;ithe. area:within1the security fence.
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-PROTECTIVE ACTIO!1S Those emergency measures taken af ter an accident or an- uncontrolled release of radioactive materials l
' ^ has' occurred, for the purpose of preventing or minimizing radiological exposures to personnel that would likely occur j if the actions were not taken. PROTECTIVE ACTIO!1S GUIDES (PAGs): Projected ra'diological dose or. dose commitment values to individuals in the general I population,'which warrant protective action following a release of radioactive material. Protective actions would be warranted provided the reduction in individual dose expected to ,be achieved. by carrying out the protective action is not offset by excessive risks to individual safety in taking
-protective action.
- PROTOll:. A' subatomic particle with a positive electric charge and a'uass 1,837~ times that of an electron.
RADI ATIO11 -(OR IO!1IZI!JG RADIATIOti): Energy released from a material in1 the form of rays or particles which are thrown off byf disintegrating nuclei. Alpha, beta, neutron and gamma radiation:arei theimost important types. Light is electro-magnetic radiation -but isinot ionizing. RADIOACTIVE DECAY: The spontaneous process by which an. I 4 ' unstable nucleus releases energy. in the form of radiation to become more stable. V <
.RADIOC11EMISTRY: The branch. of chemistry dealing with ' radio-active substances and phenomena, including tracer studies.
g .7 'kADIOLOGICAL: Of .or . relating to nuclear radiation. 9
" ~
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_ : RADIOLOGICAL': EMERGENCY TEAMS (RETs): Two-person teaias responsible for :donitoring~ radiation levels in the environ-4 l ment and collecting soil, air and water sampics for labora-
; tory ' analysis.
- l. , .
- TURBINE:-BUILDING: -A structure housing the steam turbine, -
-generator and much of the feedwater system.
~
UNUSUAL EVENT: The first level of emergency classification,
- indicating-potential degradation of plant safety levels.
m -URANIUM:: .A naturally occurring radioactive element, the
~
basic 1 fuel.of a nuclear reactor. Uranium oxide, UO2, is
; a. chemical compound of uranium and oxygen which is used as a ifueliin/ nuclear reactors.-
c
' ~
SENON-133:- A. radioactive'. noble gas produced in fission with
-aihalf-life-of 5.3 days. - Ittis not easily absorbed by body Q ftissues and'isJsoon1 eliminated by the body if inhaled or M _ jing ested'.
.c v
WilOLE BODY ' IMMERSION -- DOSE : ' The amount of radiation. received rj ,
~by_~the sody^as a: result.of direct.~-contact with'a: plume of j
e a, -
. gaseous radionuclides or- a . contaminated body ; of1 water or s
; ground surface. . It).may ' resultiin' external body _ contamina-y ._ tion .whicii can T be irelieved'. primarily ; through a cleansing
- c. -.
.;y j-- process .' .
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+:. - , ;3IRCONIOM: LA metallic; element,' highly. resistant:to corro-ision, Tan'a'loy'of'whichiis l used'as cladding on nuc1' ear fuel.
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' CYAYE OF MICHIBAN '
>A?f. >h. *.',,. ;; ...'s N EMcRGeNCY M ANAGeMcNT DIVISION Lowcu t.uvsts
' J AMES J. Bl.ANCH ARo, GOVEMNOR 6[n ,h g*,7eNo",",",$,", ,
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-. DEPARTMENT OF STATE POLICE cT.RANDAZZo .co .. ...oo,,,o,n.c,o.
narch 28, 1984 LAPR 02 884 y
-Mr. EdwardL Roche. Regional Director
_1 ,
- . Federal Emergency.Managenent Agency iRegion V - Chicago.
300 S.: Wacker:lirive, 24th . Floor
; Chicago, Illinois 60606 Re: Enrico Fermi 2 Atomic Power
- Plant Exercise Objectives
Dear Mr. R6che:
nf
' The state'of Michigan, Brownstown Township Monroc, and Wayne counties will i ;be participating with the Detroit Edison Company in the full scale exercise for the Enrico Fermi _2 Atomic-Power Plant. This exercise is scheduled for
' June;26/27i1984. Enclosed'are'the'offsite authority.objectivca for the
~
exercine'. Plea'ne note,ohjectiveu are broken down by each participatiny, entity.- y; The promptfalert notificationisystems (sirens) will-not be ac'tivated during
=the exercise. LUse'of theisystem will be simulated. Notification through 1EBS willcalso' be simulated.R - Details on scenario actions will be provided. ! ^
t with the; scenario submission.
- TIf you liave.any questions, p] ease. feel. free to contact this office.
Sinegroly,- ,
</ .*# -s pj- , '
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~
PINER lt. ' BASol.0, CAPTAIN Deputy State Director of' Emergency Services
^
F 'iPRB:DMS:cah-
- -Enclosure jec:. 1wdrem,Randazzo, Detroit- Edison .
# Don Herrmann,'Brownstown Township.
^
;g . Jon Ehkcrt', Honroe County '
.: Mitchell.Kozak, Wayne County 2 .
, .Wallace Weaver, FEMA - Chicago - ~
Dan .Bement,: FEMA --l Battic Creek -
' Colonel Corald. llough, Michigan. State Police -
jConrad Malleet,fJr;,-Executive office a
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MSP/EMD ee d- . 3/16/84 ENRICO FERMI ~2 RADIOLOGICAL EMERCENCY PREPAREDNESS EXERCISE OBJECTIVES
"~ A. . -State Objectives cl. Demonstrate the ability to fully staff facilities and maintain
? .ataffingfaround the clock (staffing will be with.a shift change or double staffing in some posit.lons as identified in the exercise manual).
;2._ Demonstrate the ability'to make decisions and to coordinate emergency activitics (command and control functionn at/between EOC's).
~.3.- Demonstrate the adequacy of facilities and displays to support
' emergency' operations (SEOC, OSEOC, -JPIC, and ancillary facilitics) .
-;4. ; ~ Demonstrate the ability;to communicate with all ap'propriate
,' ' locations, organizations, :and field personnel (using appropriate Y is communication chanac1s such as primary (phone), and secondary (LEIN) to fixed facilitics,'and.MSP radio to field personnel). 5.- Demonstrate the ability to deploy field monitoring teams in a timely fashion.- '(Teams will be prestaged in the area as will all staff forces.)- ,
'6. = Demonstrate 4 appropriate equipment and procedures for determining .
' ambien t . radia tion - Icvels. .
o._ V
~ t7.. Demonstrate appropriate equipment and~ procedures for measurement of
- airborne radiciodine' concentrations as low as 10- uCi/CC in the
- pre'sence of noble' gases.-
4 s 8.5 l Demonstrate appropriate equipment' and procedures for collection,
, . ' transport, and analysis of sampics lof soll, vegetation, and water.
', 9 .' : Demonstrate ability 'to project dosage to the public via plume
,a '
' exposure. based .on plant..and field data, and to -determine appropriate
, ' protective measurcs, based .on PAC's, availabic shelter, evacuat ion s
? time estimates,' and all other appropriate. factors.
10.xEDemonstrate? ability to project dosage tolthe public via ingestion f pathway exposure, based on field data, and to determine appropriate _ protective measurca, based'on PAC's and other relevant factors... t fil. . Demonstrete -ability to alert the. public within the 10 mile EPZ
^ , ,
land ~ disseminate an initial instructional message within 15 minutes.
;(Contact with.EBS will be made by county EOC's with initial contact C ' ,
message that this cis a test. _ Sirens.will not be sounded.)
'12. . ' Demonstrat'e ability to formulate appropriate instructions to the public .in a timely' fashion. . (',*ia the^ JPIC and simulated EBS contact.) ij
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- 13. :- Demonstrato the org:nizatignr1 chility nscascary to manage en orderly evacuation of' all or part 'of the plume EPZ. .;
14.- Demonstrate the: organizational ability.necessary to deal with impediments to evacuation such as inclement weather or traffic
- obstructions ~(vin simulated message play).
. 115. . Demonstrate the organizational. ability necessary to control access
~
-to an evacuated area.
- 16. .
Demonstrate ' ability to continuously monitor and control emergency - worker exposure. -
- 17. Demonstrntc the ability to make the decision based on predetermined
~
criterja whether: to issue K1 to emergency workers and/or the general
. population..
- 18.< Demonstrate the . ability to supply and administer KI once the decision has been made to do so. -
- 19. - Demonstrate ability to brief the media in a cicar, accurate, and timelp manner at- the JPIC.
w 20.L'DemonstrateLability to provide advance coordination of information released (at the' EOC's and JPIC). 21.. . Demonstrate' adequate procedures for decontamination of emergency workers, ' equipment, andivehicles in support of county operations
- st decontamination facility. .
=22'. l Demonstrate abilityfto. identify need for, requesti and obtain
' federal-assistance.c
- 23. 'Demonstratc? ability to estimate. total population exposure..
124.h / Demonstrate' abilitylto. determine.appropriatc measures for controlled
~
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~ '"
' recovery land reentry. , -(Actions in this area include close out of '
; reception / congregate care / decontamination. facilities, public information s
- relenses - (including measures to be taken upon reentry), decision -
- making at EOC's, Tand pickup /close out of seccas control / traffic ~
control' points. 'More dcLails.w111-be'provided in the scenario.) J ;B[ Wayne' County:
~
1., : Demonstrate the1 ability-to fully staff. facilities and maintain 1 staffing around the clock (staf fing will be' with a shif t change gor' double staffing'in somcL positions as identified in the exercise manual).:
- 42. : Demonstrate the ability to make-decisions and-to coordinate emergency activities l(command and control functions at/between the EOC's).
~
- 3. 1Demunntrate the adequacy 'of facili tica 'and displayn to support
- emergency operations (County EOC and ancillary facilities).
4 7
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'4. Dsmonstrate the ability to' communicate with all appropriate
- locations,' organizations (using appropriate communication channels as primary and secondary systems).
J5. Demonstrate ability to alert the public within the 10 alle EPZ and' disseminate an initial Instructional mesunge within 15 minutes. g ' (Contact with EBS will be made by the County EOC with an initial
? < message that this is a test. Sirens will not be sounded.)
y _ Demonstra'te ' ability - to formulate appropriate instructions to the 6. public in a timely fashion. -(Via the JPIC and simulated EBS contact.) [' -
- 7. . , Demonstrate the organizational ability necennary to manage an orderly evacuation ..of all or. part of the plume EPZ (with demonstration n of-a: limited number of persons).
- 8. . Demonstrate the organizational ability necessary to deal with
-impediments to evacuation such as inclement weather or traffic obstructions-(via' simulated message play).
19.: ' Demonstrate the organizational ability necessary to control access to an evacuated area (with demonstration of limited manned control
~
, points using sheriff and/or road commission personnel and vehicles).
1
- 10. . Demonstrate Lthe organizational ability necessary to cffect an orderly evacuation of. mobility-impaired Individuals within the plume EPZ (with a' limited demonstration of resources).
~
11'.. Demonstrate: ability to continuously monitor and control emergency worker exposure. , i Demonstrate the ability to supply and administer K1 once the
~ ~
- 12.
idecision-has been made to do so.
'13. Demonstraha- ability to brief. the media in a clear, accurate, and
- timely manner at the JPIC.
~
' :14. ; Demonstrate ability;to provide advance coordination of information
. -released-(at;the'EOC's'and*JPIC).
L15. . Demonstrate adequacy ;of. procedurcs for registraticn and radiological
; monitoring of evacuees'.(using.a limited number of persons and simulating use offactual. decontamination).
~
, 1'6., = Demonstrate- adequacy of facilitics = for. mass care of cvacuces (by -
en establishing one r acility).-
- 17. : Demonstrate adequate equipment ~ and proceduresL for decontamination of: emergency workers, equipment,' and vehicles 'at a reception /decon-
~
'tamination center.)
~
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E Demonstrate a bility,to determine appropriate measures for controlled
-18.
recovery isn'd reentry. (Actions in this area include close out of reception / congregate care / decontamination facilities, public y.. , information releases,(including measures to be taken upon reentry), decision' making nt EOC's, .and pickup /close out of access control / traffic. control points. .Hore dcLails will be provided in the
~
scenario.) y, LC. 2Brownst6cn Township- . s+ . -
- 1. Demonstrate thel ability to fully staff facilities and maintain staffing-around the clock (staffing will be with a shift change or double staffing in some positions as identified in the exercise saanual).
_ :2. Demonutrate the ability to_ make decisions and .to coordinate cmcrgency Jactivities'. (command and control functions at/between EOC's). 32 . Demonstrate the adequacy of. facilities and displays to support J caergency . operations (Brownstown Township EOC and ancillary facilitics).
- 14. - Demonstrate . the. ability to communicate with all appropriate
- ' _ locations, organizations . (using appropriate communications channels
--as primary and secondary systems).
, Demonstrate ability to alert ' the public within the.10 mile EPZ SS.
and disseminate an initial instructional message within 15 minutes. (Contact with'EBS wl11 be made by;the EOC with an initial message that this is a test.- l Sirens'w111 not be sounded.) 6.. Demonstrate ability' to formulate appropriate instructions to the
- c public-in a timely fashion. (Via the JPIC and simulated EBS contact.)
'71 . Demonstrate the. organizational ability .necessary to manage an orderly ' evacuation of all or part of the plume EPZ (with a demonstration offa. limited number of persons).
28h . Demonstrate the. organizational ability necessary to ~ deal with. 3 g' '
' impediments to evacuation,such' as inclement weather or traffic obstructions (via nimulated message play)..
- 9. : .D' e monstrate the organizationalf ability necessary s to control access
~
- .to an evacuated area (with a demonstration of limited manned
~
control points using' police and/or Department of Public Works-personnel.and vehicles).
- 10. . Demonstrate the organizational ability and resciarces noccanary to 4 -
' ef fect:an orderly evacuation ~ of mobility-impaired individuals -
Lwithin the plume-EPZ (with a limited demonstration).
- l 11b -Demonstrate ability to continuous 1y ' monitor and control- caergency
= worke r exposure. .
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'12.. Demonstrate the_ ability to supply and administer KI once.the decision has been made to do so.
21 3 . Demonstrate ability..to brief the media in a clear, accurate, and
; timely manner at the JPIC.
14.1 Demonstrate ability to provide. advance- coordination of information Jreleased (at the EOC's and JPIC).
- 15. . Demonstrate adequacy of procedures for registration and radiological l
. monitoring of evacuees (using a limited number of persons and Ksimulating-use of' actual decontamination).
~
_~
> 16.1 Demonstrate adequate equipment and procedures for decontumination
~of caergency workers, equipment, and vehicles.
- 17. ' Demonstrate ability to determine appropriate measures for controlled recovery and reentry. . (Actions in this area include close out of reception / congregate care / decontamination facilities, public information releasca (including measures to be taken upon reentry),
decisjon making' at EOC's,;and pickup /close out of access control / traffic control points. More details will be provided in the
~
' scenario.)
D. . Monroc-- Coun ty , {1. : Demonstrate the ability'to fully staff facilities and maintain staffing around. the clock (staf fing will be with u.shif t' change
~
. or double staffing in soma positions as identified in the exercise
- manual).
, 12. De'monstrate the ability to make' decisions and to coordinate caer8ency b, - 7 activities-(command and control functions at/between EOC's).
- 3 .' - Demonstrate:the adequacy of' facilities and displays to support
' emergency operations (Monroe County EOC and ancillary facilitics).
M--- ' .m-_' N: Demonstrate 'the abilityTsio communicate with:all appropriate
~
anfprimaryland secondary sysLems).
- 5. Demonstirate ability 'to . alert the public within the' 10 mile EPZ and disseminate :an initial instructional, message' within 15 minutes.
. (Contact with EBS will be made by _ the County. EOC with. an initial
~
k inessage that this.is'a-test. Sirens will not he-sounded.) 6._ . Demonstrate ability to formulate appropriate Instructions to the
. Lpublic_in_a: timely. fashion..;(Via the JFIC and simulated EBS contact).
LDemonstrate the organizational ability necessary'to manage an-
~
7 .' 4
' orderly' evacuation of;all' or part of the ' plume EPZ (with a demonstration
% of a limited evacuation). k i 1
~
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. THIS IS A DRILL
, CHRONOLOGY OF EVENTS FERMI 1 TIME- EVENT E0810 'Off gas 17:mR/hr. MSL 6000,mR/hr. Rx 1v1 = 200.
.!Rx;P =,90014. RCIC = 100'gpm. Torus = 77*F.
. Torus lvl = normal. SRV status = all valves operable.
X- . N . .. . .
- Initiatinglevent =' manual scram.- Hi rad alarm in Rx bldg and iO817J Lower lvl: aux bldg. 0ffsite fire assist. requested. No E B
- offsite release. < Stability Class C based on .084 AT*C at
~
50 M. Wind. speed 1.5 mph. Wind dir.Lfrom 178 to 358*.
~
. Downwind 'secto'r . RAB. Precip.<= none.
c5 , 0843: ' Gen.1. Emergency at 0834. Basis = major.sta leak outside
< primary containment, without isolation, and potential loss
;2 , . of;fuelEcladding.
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'0851 EOF has been activated. .
).0850' ~ EOF Mgr - W. Gens . 313/586'-5765. Evac recommendation 5 mi.' radius. -10 mi. RAB sectors. Evac schools, institutions, and rec areas in 10'mi. radius. Shelter all others in 10 mi.
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telephone numbers of the Headquarters Incident L Response Personnel.
- b. Ask to;be informed of any changes in Headquarters it E INIT.
staffing. Give the RCTM your telephone number and y 3/) TIME name. -
- 4. ' Collect and fill in necessary information on the Incident (7)f INIT.
"Information' Board. T'#() TIME
- a. Items 1 through 7 - information is obtained from ENS mF INIT.
message forms and interfa'ce with the Base Team Manager f*VO-TIME p and Emergency Preparedness Manager.
- b. ' Items 8 through 11 -'information is obtained from ENS )y)F INIT.
mest, age-forms,. interface with the Emergency Prepared r v/5 TIME ness Manager and requests to outgoing ENS communicator. for information.
- c. Item 12 .information is obtained through direct YhF INIT.
interface with State Liaison Manager. or use of message C43 TIME forms. Ed. Item 13 and 14_- information is obtained through }nf --INIT. direct interface with Protective Measures manager or 9td) TIME
-use-of message forms. -
1 S '. Assure that' Chronology of Events status board plotter is ty)F INIT.
= assigned. (o.'69 TIME-k-
t .
- a. If the Chronology of Events board is not manned, INIT. l request the Reactor Safety Manager to assign an TIME l individual to plot incoming information from the ENS l Communicator.
- 6. Assure that 10 and 50 mile radius EPZ maps are posted in nif INIT.
the IRC. 6'qfA TIME
- a. Maps are filed alphabetically in the map cabinet ThF INIT.
located in the "think tank." 4 <Lf/) TIME.
- b. Post the 1-10 mile EPZ map in the IRC on the map }YM: INIT.
hanger located on the left hand side of the Base Team g#s/} TIME Manager.
- c. Post-the.other 1-10 mile EPZ map in the IPC on the l))f INIT.
east wall in the Protective measure area. p 45?l TIME
- d. Por , the 1-50 mile EPZ map on the south wall next to ThF INIT.
the Base Team / Site Team assignment boards. (#tff/) TIME
- 7. . Assure that messengers are ava e k pS ple every two Thf INIT.
hours) to transmit messages from both the HPN Communicator f56 TIME and ENS Communicator to the Chronology of Events Plotter, and among other IRC positions. Check Emergency Assignment i Chart and the Administrative Support Manager for available
, personnel.
-8. Assure that the Chronology of Events status board is (7)F INIT.
transcribed and copies are distributed to all IRC 7:03 M TIME positions. L a'. Administrative support personnel available for this_ M f INIT. function are found on the Emergency Assignment Chart. 74r TIME Rotate personnel each half hour _for typing. If initial activation is lengthy, rotate messengers and
- typists for; relief.
'b. Assign messengers to Xerox and distribute the trans W 'INIT.
cribed information. ft/C TIME
-9. Notify _ switchboard of persons assigned to base Team M INIT.
- Management. positions. KA TIME (10. NotLify Headquarters Response Coordinator Team Member No.1 iv)F INIT.
E(9-1-1-202-951-0550) and inform them of personnel assigned (146 TIME Base Team / Site Team positions. Fax this information to the r
--Headquarters Incident Response Center (Table 1 and 2). ,
- 11. - Periodically,. send a messenger _to the Switchboard Operator INIT.
l to collect _any incoming messages-(i.e., media inquiries) ~ TIME which need to be distributed to IRC personnel.. t: 2
, . ;- 'n ".. l
- 12. Maintain a log of all ENS messages. agg: INIT.
TIME L13. Answer all busy / don't answer IRC calls and take messages P41f INIT. or transfer calls as necessary (consider assigning a staff /o TIME member to answer these calls if you become too busy).
- 14. Generally oversee all Administrative Support functions hqir INIT.
needed during activation. 87;30 TIME INIT.
~
- 15. Every half hour check with all Base Team Managers to ensure their needs are being met such as: Chronology of TIME event forms, administrative needs.
TASKS (Expanded Activation)
- 1. Support' Site Team requests. INIT.
TASKS (De-Activation Mode)
- 1. Return IRC to normal state of preparedness. INIT.
TIME
- 2. Compile records 1at end of activation in preparation for INIT.
reports and critiques. TIME t. a ;
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. BASE TEAM MANAGER-K 4%z" Dub :
Protective Meas. Mgr. Safeguards Mgr. HP r Emer . Prep..Mgr. FSL Mgr. Pub.- Aff. Mgr. , 0 ({ , fr)mM . . W. P.,[h (O. h 0A TYl*S b k-t 4-i . IRC Controller. Comununicat rp (WSe4+h)m.Foda,Plotters /,- 4 Rx Safety Mgr. . Admin.. Support Mgr. P. fA ?- g ;y, f f. g, %g p* Messengers S. h 9 w
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- 4 SITE TEAM MANAGER
. Cr. .
Safeg ards Emerg. Resp Coord.
-HP Coord .
Coord. afety"Coord. Prot. Meas. Coord. d -EOF P. A. Coord. - Rx M Go -EOFc TSC TSC L'Coord. -EOF d c7~ Mo.****- = EOF /JPIC
'H EOF Rx.; Safety; Spec. .TSC
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-( --
(Base' Team Manaaer) - Checklist IBASE TEAM PROCEDURES
- Personnel-Qualified: Regional Administrator, Deputy Regional Administrator and All Divis* ion Directors
; TASKS-(Standby and Initial Activation Mode) '
I. IAssign team managers for the following areas if the primary A%$ INIT.
. primary individuals are not available: Emergency Prepared 7e4JIME
& ness,~ Administrative Support," Protective Measures, Public
~~ Affairs,' Incident Response' Center Controller, Reactor Safety,
, ; Safeguards, Health Physics', Communicator 2, and Federal / State
= Liaison.
,P
- 2. Ensure that communications are established and maintained
' with the licensee via the Emergency Notification System
$$k INIT. t 75M TlifE and the Health Physics Network. Ensure that communications
-'are established with Headquarters ET, and analysis and Support W iMekccl
. Groups(~ i.e. . Reactor Safety and Protective Measures Analysis) g,
' Periodically brief1these groups on status of incident and
~
response activities. 3._ . ; Remind all Base Team members to complete their checklists. 'A4h INIT.A Periodically request verbal. status reports from each Base to2- TIME gTeasmember.
~
i! - 4; Ensure Resident Inspector (s) are notified.and dispatched sad INIT. 2 to'thelControl Room and Technical Support Center. M TIME
- 5. Ensure proper Federal and . State agencies lare notified of M INIT.
t the-incident.: (See Section III of the Supplement)~. 7M TIME . 6.- ; Support Site 1 Team needs:. A. l 1-: ensure Site Team has money'for food,. lodging, and 1
*~
INIT.
, transportation.
/ TIME
-)
y'
.-! ensure Site Team transportation has'been established. INIT; f,U)d4,~'
TIME Nc T4*'*' -
~ -; ensure SitejTeam is equipped with necessary radiological INIT.
^
v u.J,
-protection,-monitoring, and communication equipment. TIME 1
- P ' -
' ensure' team'is equipped with necessary site information. :INIT. MM TIME V - - ~ -
3 "ensu q unfettered site.accessLand escort to emergency INIT.
,) (facilitias-is established.
TIME .
.uyd I- Rev. 1,;02/84 y .. -- --
3- }
ex-f.:
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7.- Inform ET of' Site Team' departure and ETA. 8L68(INIT. 73 / TIME
> 8. . If you are in the Standby Mode, establish communications GT/./ ~ INIT.
Luntil-the-arrival of the Site Team with the licensee's-
~
?! d TIE y.
_ -Corporate management group. ~This' includes contacting the
. Corporate Emergency Director when he/she becomes operational.
; Inform them of NRC's' energency response activities -including Site' Team ETA'.~
9.- Review and approve.all press releases from the region'and jf INIT.T _ . assure that'they have been approved by HQ.
'7:vuTIME
. 30. ' Ensure 24 hour per day assignments are made for staffing INIT.
7the Base Team and prepare shift change for Site Team. TIE
~ Consider obtaining necessary staffing from .other NRC
. Regions. ' Assign the Emergency Preparedness Manager to Jcontact HQ to obtain.other Regional support.
-11.'. Maintain'a record of related activities. 4NINIT.F TIME s - i12.' - Establish and" staff the "think' tank" for technical % INIT.
research and consultation.' Consider staff members from Too TIME all. divisions;: TASKS ~(Expanded Activation)
^
- 1. -Coordinate with the Director'of Site Operations'and support N Y INIT.
;DSO needs. TIME-(2 Establish or maintain' counterpart communications with. _ INIT.
~
isenior licensee-management, Site Team and Director, ET, yc 0 TIME
, Jindependent ofithe ENS.or HP Networks, through'the Headquarters Duty Officer (202/951-0550).-
f3.1 -- Arrange. for Site Team ~ augmentation. ' Normal extent lof duty INIT.4 i cshould not exceed two weeks. PA TIME
~ ~
t 4.7 LArrange with HQ-to provide additional manpower support fros' 59'INIT. other regions. ' TIME-I ' [5.: ) Provide:forthe'24hourperdayoperationoftheBaseTeam ~INIT.A'
- through,' shift. scheduling. #> TIME-4 ? Approve periodic updates regarding NRC response and assure [ INIT.#
they are transmitted to: appropriate Federal and State SMME l agen'cie's . [ Monitor onsite andtoffsite' developments and provide any
~
NIT. N
- 17. . ; additional l technical expertise needed by the Site Team.
' TIME
'8. l Staff and maintain the "think. tank" as necessary. 6 d7 INIT.
y; ed TIME
..~
'2 Rev. 1, 02/84
- g. , 3' - - - . .
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~
- 9'. - Provide for staff' support of the Base Team Operation as 8UIWk INIT.
- follows: Incident Response Center Controller, Public 97 ts TIME
. Affairs Manager, Protective Measures Manager, Reactor Safety Manager,-Administrative Support Manager, Safeguards *
' Manager, and Emergency Preparedness Manager.
- 10. Maintain a record of related activities. WSdk.INIT.
t:4 m IME TASKS (Deactivation)'
- 1. Monitor licensee activities regarding repair and recovery INIT.
operations. Keep the Regional Administrator and HQ advised TIME of these activities. 2.. Collect all records on incident response and prepare a INIT.
-critique;of emergency procedures. TIME t -
s 4 Rev. 1, 02/84
~
3
~
(-: -. _
1 ,
-(Administrative S'upport Manaser)
~ BASE TEAN PROCEDURES v -
TASKS (Initial A'etivation Mode) The' Administrator Support Manager will: . 1.: Report to.the Incident Response Center (IRC) as soon as INIT. citsis= activated. y- /-dTIE
. attW tRetrievetheRIIICalloutListsh,BandC)fromthe
;2. INIT.
c . equipment: storage. cabinet in the Think Tank. Ask the 41/vTIE Incident Response Center Controller for' assistance if necessary. L 3. - Coordinate the movement of the. Site Team o the sity,' INIT.
- - . including arrangements for trapportatio)n, lodging,- I TIE clerical support,' travel advances, and necessary supplies ^
- m 'and equipment:(see Section III of the RIII Emergency.
! Response Implementing Procedures). '4 -
INIT. 1a. For.the;following sites,~ consider' ground trans
- :portation/ helicopters-as your first alternatives: TIE
.- iD. C.. Cook.
- .. Dres' den C , .-
I I.aSalle
'~
. . , ; Palisades
.- -Zion-
- b. For'all~ remaining site's, use fixed wing aircrait as- INIT.
%' '/ ';20 TIE
-the.first priority. Friester-Aviation should be the primary charter company' used,:with the remainder of -
companies-listed on p. III-38 of the RIII Emergency iResponse. Implementing Procedures serving as backups.
- c.- -Provide for. ground. transportation between the.IRC and INIT.
.g l sir transportation facilities. Arrange for-ground- lJ . TIE transportation between-the airport and~the site.
. ~~
b - . " Arrange:for police escorts if necessary.
' d .' ~ Provide' travel' advances'and TR's-as needed. Contact ~ INIT.
LtravelTsection personnel for-advance and TR issuance. [d TIE 7, p (Ifjthe incident occurs'during'off-hours,- TR's and-advance money,will-be available. through the Regional :
~
. Administrator,' Deputy Regional Administrator,,or
- Assistant to the' Administrator. .
INIT.
;0btain.the.-appropriste IRC Site Book'(located in the
~
, ie.-
? book shelves in the:IRC Think Tank area). ' Consult . TIE 4the Travel section- for information on transportation, police agencies,land-hotel / motel aecommodations.
3: 3;-
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- i 4'. Confer with the-Incident; Response Center Controller INIT.
.regarding equipment needs for the IRC. gg TIME l5.. ' Provide clerical support.to the Base Team. Provide INIT.
/ _ _ messengers for:long= term operations of the IRC. j # TIME
~ Coordinate with IRC~ Controller and/or. Emergency Response
~ Manager.:
~
I6. . Coordinatefwith the Safeguards Manager to provide all INIT.
" ~
;information needed-for access authorization for Site Team TIME
. members.
. ~ 7 '. Provide ecessary administrative information to backup INIT.
' region. Coordinate travel,' lodging, access information, TIME Land nec sary supplies and equjpment for backup region i
t personnel'. -- J W )
- _ . .~
- 18. (Maintain a record-of related activities. INIT.
TIME O (TASKS.(Expanded Activation Mode).
~
M ' la ' TheLAdministrative-Support Ma' nager will: y , J l l. ) Monitor and-continue-to provide for the. administrative INIT.
;needs of-the: Site. Team and" Base Team as: identified in _y./d TIME
- 'i-1
~~
- iinitial activation. Provide for transporting replacements Jfor Site. Team members.
2.: ! Assist HQ on' administrative requirements for HQ personnel. f INIT.
~
-traveling to the. site'. TIME' 7
~
/3. ; Provide = administrative.needs, as~ requested, by!the-Base INIT.
q : = Team Manager.; , TIME [e3= 4. TMaintain 'a record of.related? activities. INIT.
~
TIME.
- TASKS?
(' Deactivation Mode)I
- fThe.' Administrative Support Manager will:
, ; {1 '.' ' 1 Provide foritransportingthe Site. Team back to the Region. '
NIT. TIME
^
T2 0 IProvide~for theLdisassembly and' retrieval of'all supplies.-
~
l[ s - INIT.
' 4 and materials -provided ;for -Site l Team use. TIME
{' , e r 3 . '- ICollect all? records on incident response. -Prepare.a4 ' - ' INIT. o ,
, critique,of2 emergency response procedures.'- TIME i ' j,
,I p --
~*
r4 m . 2. Rev. I, 06/84 c, ._ . w^
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~
, [(Site Team Leader) '
' SITE TEAM PROCEDURES- .
-Personne1' Qualified: . Regional Administrator, Deputy Regional Administrator, and Division Directors
-TASKS'(Initial Activation Mode)'
- The-Sit'e Team Leader will:
^
-1.- Evaluate incident classification with assistance from the 6/J)INIT.
Emergency Response Coordinator.. @ IME
- 2. iEstablish communication with ET in Headquarters (i.e., MA INIT.
-l delegate.this to a qualified. communicator). TIE 3.2 3 Appoint a Regional Base TeamfManager if the Deputy Regional /M1 INIT.
.' Administrator'is-unavailable. -
TIE De'signateLan-. initial Site Team for the-following areas: - j4; d@ INIT s c -- TIE
, J
- Pub 1'ic ' Affairs L
- Reactor Safety' Assessment.
ns , O* Protective Measures' Assessment
+
. q* Safeguards 1 Assessment-
,
- Emergency Preparedness
< ,
- Health-Physics-
~ 1* Federal / State ~ Liaison.
g . 4
)(List'of; qualified staff'is prov'ided,iniAttachme't.IO)-
3 - a
~5.; Ensure that these emergency.-response: functions"have INIT.
' adequate' support staff.
TIE
,- ..6L . Dispatch the'Hobile Lab to-the site for nuclear power g INIT T
, [i .
reactor incidents., The' Mobile Lab ~ will 'be dispatched to
)the' licensee's-Emergency. Operation's Facility.
. n.7 TIE y E1rg- Co* / 'O N.? (Assess:the overalliresponse'to;the incident. 43MINIT.
~ -TIE
..j
- , :8. 'Brief.the Site Team prior to being dispatched to.the 61 A INIT. tJ. 3 ik-L. 9 scene. TIE %
"a + .m ~
- 9. ' l Cal 1$the)NRC0C upon arriYa1 at the'destinatiion airport or. ~ M ~ INIT.
M .w hen-in the. vicinity-of the site to' determine4 1f access to TIE , c the site;is riecommended, .and to : confer with the Director.1 jregarding incident: status.
& , Yk .
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,10. For nuclear power reactor incidents,' initially report to MA INIT.
- the-licensee's TSC and'obtain a briefing from the Senior TIME
, 'ResidentiInspector and licensee management. Ensure that a ,
. Resident' Inspector is available in the Control Room at all times.1
~
/11.:. Report t'o th'e licensee's EOF for a-Site Area or General h/A INIT.
Emergency, establish communications, and obtain a briefing TIME from Senior licensee management and the Regional Base Team. k- = Report to the TSC for Alert emergencies or lower. ,
*~ :12. ' Call'the Director of the Executive Team to advise him of f INIT.
your status regarding: knowledge.of the incident and Site TIMEg Team staffing. -If appointed DSO, ask the Director what
- authorities'are delegated to the DSO.
113. ' Maintain a record'of'related activities. @ INIT. TIME ,L' iTASKS:(Expanded Activation Mode); t+
% ~(Acting as' Regional Administrator)
~
.The: Site Team I.eader will:.
b ;1.C iEstablish or maintainicounterpart communications, through (A,d INIT. W ,_ the. Headquarters Duty ~0fficer (202/951-0550),' with senior TIME
. licensee management',- EOF Director), Base Team-and HQ,
~
independent of the ?- or HP Networks. _ /2. (Support the-DSO. @ INIT.
,, TIME >
.INIT.
~
- 3.- ,lSchedu1e perio'dic briefing with' the Senior Resident : *
- Inspector.
- TIME n.
^
"r ,
g k INIT.%
- 4. lAssess overall licensee emergency response'to mitigate:thei
*M : consequences'of theLaccident. -
, atti TIME-P ..
'5.n Identify;anyLlogistical'supportineedsLof the' Site Team and L-INIT.
c m, report these needs to the Deputy. Director at Headquarters ^ [~M_ TIME ( and the: Regional Base Team. , m x l6.:. censure Headquarters'and the Regional Base Team-are-Mb-INIT.4
.' ; periodically. updated'of NRC(site operations?
sin TIME:
+ ;7; lMaintainarecord$frelatedactivikims.? 09 INIT.- -/* i _.
TIME
- h(AckingasDirector'ofISit'e' Operations)-
~
g The' fo11owing; tasks must bsTaccomplis'hed by the Regional AdministratorE Hif he.is; appointed the. Director of Site Operations (DS0) in addition'to /S; the; expanded' activation tasks. identified above: z- 4
~
I'
'2 Rev. 1, 02/84 l > .2 _ _
gm % $:2 i - ci '
- j. .
q 4 _
'1 7 fSupervise:the activities of all NRC personnel at the site. IM INIT.
~ Request.the Base Team to arrange support from other regions TIME
-and HQ as'necessary. .
'.[ E2.. LAdvise'the licensee as appropriate. . Issue orders if (M' INIT.
~
necessary (these will be. carried out-only.'if given the TIME authority by;the NRC Director). h 3.; ' Evaluate staff anal'ysis (Site Team and Headquarters M INIT.
'assessmentiteams)~of licensee actions. a / ^ TIME
- ~
L41 :If given the authority by the.NRC Director, decide on NRC INIT.
. recommendation of protective measures for the public and TIME iinform ET. Coordinate NRC recommendations with the licensee.
4, {52- 'If. given authority by- the -Director,imake appropriate INIT.
- recommendations to key state and local a~gencies.(i.e, TIME
= Governor's Office and County Cowission or County Sheriff).
Coordinate this information with the licensee. 3 . n i ' ds
,6.
Inform IIMA of protective measures recommeadations through~
~
, INIT.
, - the State EOC or EOF. ,
TIME
.. . 7- .
La. Coordinate all guidance and recomunendationsgiven to >
- the ^ State l with- the SFO except .where :isuminent pe'ril to
- the'public. health and safety exists and time:does~not
~
. l permit a coordinated recommendation.
/
Eb. > If 's Senior FEMA Official (SFO) is designated and face-ito-face communication _is-not possible, the DSO will
~
[ establish alseparate management communications link ' x_
;with the SFO.- '
~
s - s - 3 Q ~ 'fi TN LEeep the; Headquarters Deputiy Director l(i.e.', Ef0) advised : INIT. . y ~ J' g : of participation by other Federal' agencles iand refer dis TIME / l agreements.to.the-Director (Chairman,iNR.C)lfor resolution. , e . . . 7.. > DINIT.
,,9p];f f f , ? 8!; i(Deputy Relay Director Lthe ~need through:the for additionalisupport Regional Base Team. toi the HeadquartersTIME -
ws ( 9. s ^ Review press releases.for_ accuracy.and hold press ' INIT.
- conferences _as necessary. ' Major press : conferences should TIME 4 f; ~.
, cbe.' held-jointly with the state,;-local government, the 4icensee, f"T ,
- and ;other' federal ' agencies. -
s 10'.i(Referia11'politicalinquirestotheHQDirectorfor? INIT. o E k-
'. s -resolution.--
V , s TIME n a, p J. . k ,
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( [ , en 3 Rev. 1,'02/84
~ .
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I 4 s - TASKS (Deactivation Mode) a a The Site Team Leader /DSO will: 3 m
- 1. Determine the need for continued Site Team operation. INIT. 3 TIME
- 2. Prepare for disbanding the Site Team. INIT. j TIME 7
+
- 3. Haka assignments for long term monitoring of recovery INIT. ;
operations. TIME ,
- 4. Coordinate the regional evaluation of incident response INIT.
3 e activities. TIME -' a d E, L_ E L i n 9 1
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=
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IRC MESSAGE FORM 4
. ,. ..(Far Ralcying Meccag2s Within tha IRC)
- TT0f^ Od O k' i DATE/ TIME:
lF ON;; Administrative I
SUBJECT:
m n
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, iBASE TEAM PROCEDURES]
- TASES'(Initia1LActivation Mode).
o ThkEmeisencylPreparednessManagerwill:
.1; , 7 Report t'otthe-IRC whec activated.- ff$kINIT.
(f 40 TIME 2.- LEnsure;that the following. personnel.have been paged or l[ b NIT. 1
; 7. . : phoned and directed to immediately report to the IRC: # 4 5 TIME ^ ~
E T
- a. : Eme'rgency Preparedness Section Chief ibA f rgency Preparedness'and Operational Support Branch Chief b w j . ..
c.. 1 Independent Measurements & Environmental Protection Section
- 8 LChief
.' ' { d.; e'deral/ State Iiaison Officer --
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/f.; rgencyIPreparedness Coordinator
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. M h NIT.
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73.' 9s' J : support needed to facilitate Base Team operations and Site TIME
" \ Team' staffing.
4.- Monitor ~:themobilization'andstaffingofIthieIncident d k INIT.; pf ~
- iResponse Center. . Assure that all identified positions are. TIME
< - : properly filled.; Assist.the Base Team Manager '
in'providing W y4 f; ~ , , backup support;for sustained' operations. E T5.- IObtain':the'IR'C copy.'of the lppropriate' facilities Site Book 'INIT. for. reference purposes. The Site Books'are located in'the' TIME
. Think Tank portion ~of the IRC. Q f g Q ,lI ,
6.1 1 Assist the.IRC' Controller in. obtaining incident: ,fil)DINIT. p- lin'g::;ation. g- TIME W. V . . . E_ 27.V fEnsure-that adequate. administrative preparations are made INIT. r x ' 4
.for.the timely. deployment of the G gional Site Team, ,
TIME 1 < , , zincluding transportation arrangements; travel advances,
- i lodging ' accommoda tions , ~' etc.~
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pp j; - 6 y ;.. ;q ~ q, , 18.1 : Ensureithat'the'IRC Controller obtains names and phone . $_ b NIT.
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' numbers -for HQ Emergency Response Personnel Status Board. TIME
'Obtain emergency' response organization names and phone
~
enumbers from the licensee. Obtain all information on the eIncident Information Status Board and give this information to:the IRC Controller. 9.- ' Keep.the Regional Administrator and Base Team Manager d h INIT. '
' appraised oflall findings. TIME
;10. l-Monitor periodic' plant status updates and make appropriate b M NIT.
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- _- .through~the' Base Team Manager regarding NRC incident
; response' activities.
[ 11.. Monitor-liaison' activities with off site agencies. Assure j[k.INIT.
~
'periodicicontacts are being made. TIME :
TASKS 1(Expanded Activation Mode) TDuring this mode the-focus.of activity will shift from the Base Team ' 10 peration to the Site-Team operation. The Base Team may retain one Lperson~.to. coordinate the emergency preparedness function. If so,.the
-Emergency Preparedness Manager will: _
g 1.- Support: the activities of the Emergency Preparedness and INIT.
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Operations Support Site Team members. ' Provide for sup- TIME 1 plementing personnel and relieving primary Site Team g' members as required. U [2.T l Monitor the activities of Emergency.. Preparedness Site Team- INIT. members.. TIME' % ;m . , .
~3. L Maintain records 1 of ~ all findings.. .INIT.-
4 TIME iTASKS (Deactivation Mode):
-The Emergency' Preparedness Manager will:
Lt. -Assemble all records of the' incident and prepare an INIT.
~ emergency preparedness' critique'of' incident operations. TIME O[
1
+' 2.X Monitor reentry a'nd recovery activitle's, and provide- INIT.
guidance lon reentry guidelines'for the evacuated TIME population, 'if. applicable.- r t- ,'O
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' - FERMI
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L TIME: , EVENT s L1040; :Rx-'P = 80; Rx 1v1 = 230 Drywell: P = 0.5~
- T-= 100*F Rad ivl = 5000 R/hr
. Torus: ~ P = 0.5.-
Lvl =. normal T = 71*F
- 0ff gas: 17 mR/hr
,MSL Rad: '1.3E+4 mR/hr
.RCIC in standby -
~
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- SRV's operable.
- 1110- Region-III participation.in this drill is complete.
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, CHRONOLOGY OF EVENTS
- 3. - - . F. ERMI Q - TIME- ' : EVENT:
1 Rx lvl = 230. 1 0950 'Rx'P =:170. L. Drywell: - P = 0.5 T =-100'F.
~ '
. Rad Iv1 = 4800 R/hr
~ - : Torus: , P = 0.5
- Iv1 = Normal-T = 79*F.
-;0ff gas 17 mR/hr MJ
,y - :-MSL Rad SE + 04 mR/hr.
RCIC.in standby. SBGTS: DIV'II-in operation' DIV.I - standby
- Noble gas = 1.7 E-01 pC/CC
- a. -10051 All parameters the same.
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o , [ CHRONOLOGY OF EVENTS FERMI 4 f ETIME -: .EVENTJ
'0918 Off gas 17 mR/hr.. MSL. Rad = 5.8E + 05 mR/hr.
~
- Rx Iv1 =-200 in. Rx P = 230.' RCIC = 100 gpm.
~
Torus temp = 79*. -Torus Ivl = Normal. SRV's operable. 70932; Rx P =:160'
~Rx LVL = 200 Drywell: _..P.=.0.5
~
T'= 100*F
-C RAD LVL = 4000 R/HR
; . Torus:. P.= 0.5:-
~ LVL: = Normal
~
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, :58GTS>?DIVIinOgration..DIVII.isstandbySBGTS RAD LVL = 8.2E+01-1AssessingPlacingkVIIBSGTSonatthistime.
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~~
Have'taken containment atmos. particulate and noble-gas sample
- ' analysis, results available.in 2 hours.
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; EVENTl
}. TIME i ^ 1- 0851 ~ EOF has-been activated.
.).0850 f-EOF- Mgr-- W.E Gens 313/586-5765. Evac recommendation Evac schools, institutions,
;5'ai;: radius. '10 mi. RAB sectors.
-and rec areas in'10 mi radius. Shelter all others in T10 mi.
L-0902 ~ off gas;= same...MSL Rad = 4.5 E + 5 mR/hr. Rx P = 325.
-:RCIC = 100 gpm. Torus temp. = 77'F. Torus ivl = normal.
- y. :SRV's operable.
0912 Rx P = 230.. Rx-Iv1 = 200 stable.
. Drywell:-; ~ P = 0.57 psig. .
T = 101*F. Rad 1v1 = 2500 R/hr-
-: Torus P = 0.5 psig... -
Secondary Containment: -'S8GTS rad level = 5.52 E + 03 h
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. CHRONOLOGY OF EVENTS FERMI
- ) TIME _
--EVENT
'0810: :;0ff gas 17 mR/hr. MSL 6000 mR/hr. Rx lvl = 200.
-Rx P.= 900 4. RCIC = 100 gpm. Torus = 77*F.
. Torus ivl = normal. SRV status = all valves operable.
0817I- -Initiating event =-manual scram. Hi rad alarm in Rx b1dg and Lower Iv1 aux b1dg. Offsite fire assist requested. No offsite release. Stability Class C- based on .084 AT*C at
, , ;50 M. Wind speed 1.5 mph. Wind dir. from 178 to 358*.
. . ' Downwind sector RAB. Precip. =.none. Ge.1. Emergency at'0834. Basis = major.sta leak outside
-[0843 -
, primary containment, without isolation, and potential loss of fuel cladding.-
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THIS IS A DRILL i CHRONOLOGY OF EVENTS FERMI TIME EVENT' 0755i Off gas unchanged. Rx lvl 200 in - MSLTrad 600 mR/hr t. stable.- Rx P =.1010 4 confirmed. Rx Is subcritical, cannot
. scram 4 rods.
. 0757 Declared Site Area-Emergency. EOF not activated.
~
0805 TSC activat'ed. Manager = Bob Leonard 313/586-5730.
. State EOC activated. .
0804' . EOF:is being activated. All low pressure systems available. 2 RHR~.in-torus. cooling. 2 RHR in standby. ADS operable.
-RCIC;in operation. . 100 gpm, aligned from CTS, 100 psig discharge pressure. ' Suspect a drain line in steam tunnel
# :is-o;,en.. 1st and 2nd floor Rx.b1dg and steam tunnel + Hi Rad Steam leak detection in steam tunnel. Fire in HPCI room out.
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CHRONOLOGY OF EVENTS FERMI JTIME . EVENT'
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- 0704 cRX scram-fire lin HPCI room.
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- 0726 -Fire Brigade dispatched. RX is stable..
. . -0730, ;4 fods..not full-in,.1 rod at. position 02, 2' rods at 04, 1 rod ,4 ^atl42. All_4 in cluster power. Decreasing, IRM on range 1.
0734 Site Fax;No.'i313/586-5720, Site Team cleared for site access,
. ETA 0830-0900 CTS,. site security systems all manned.
* ~
' " : 0739 Scram signal:- suspect Hi MSL RaC MSIV isolate, primary contain-
.c oent isolated. HPCI fire = oil fire, undetermined cause. Off gas
-s...> Tand MSL isolated due to containment' isolation. MSL rad < 10 mR, Rxilv1!200-in t,LRx Press 1065~t.
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BEALTH FHYSICS EMERGENCY EQUIPMENT OFF-SITE RADI0thCICAL ENERGENCY TEAM KITS No. i QUANTITY QUANTITY
-ITEM REQUIRED AVAILABLE
- 1. . lastreetion Manual for obtaining ouvironmental samples and EF-210-1 Rev. -
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and 210-2 Rav. 1
- 2. Radeco 3809C Battery Powered Air Sampler 1 t..
- 1) Serial # b Cal. Due Date a) Extra Air Sampler Reads 2
'b) Particulate Filters Approx. 20 m.-
c) Silver Eeolite Cartridges 20 (
.d) Labels for Air Samples Approx. 50 t ,.-
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- 3. Dose Rate Meter (RO-2 or equivalent) 1 V ll
- 1) ' Serial # 8 Cel. Due Date r
- 6. -9 Voit Alkaline Batteries (spares) 3 e
- 7. 1 .
Ba8 for 30 V S. 4 TLD's (Personnel) . v
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, 9. TLD's for Environmental Monitoring 20 bd'
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e' i [ Federal / State Liaison Manager) BASE TEAM PROCEDURES
. TASKS (Initial:and Expanded Activation Modes)
NOTE: The task to be accomplished during the Initial and Expanded Activation Modes are essentially the same. The difference operationally is that under Initial Activation Base Team per-sonnel advise HQ through the Base Team Manager. Under Expanded Activation, Base Team personnel advise the Director of Site Operations (DS0) through the Base Team Manager. The position of the Federal / State Liaison Manager will be filled by the Regional State Liaison Officer or designated alternate. The Federal / State Liaison Manager will:
- 1. Report to the Region III Incident Response Center (IRC) b 1 NIT.
. upon activation.~ g( 4/57; TIME
- 2. Make initial notifications from the-IRC to the following INIT.
agencies: t>7V6ATIME
- a. State (s). Notify appropriate Emergency Services Agencies.
Ask specifically that both the State Radiological Health agency
-and the. State Liaison Officer are provided all information (see Section III).
. Federal agencies. Notify: (See Section III) mn0T (FAA. Coast Guard) for transportation events.
g g . { FEMA, EPA, HHS:FDA for facility events D UsDUU:05HA for worker injuries or deaths associated with events. g h. FEMA for security events.
- 3. Determine the present location and telephone number of INIT.
the Governor (s) of the State (s) involved and relay this D7// TIME information to the Federal / State Liaison Coordinator and the HQ Government Liaison Officer. Explain that the NRC may contact the Governor if necessary.
- 4. Request l'amediate notification of the designation of a ' INIT.
' Senior FEMA Official (SFO),~ including name, location and B R// TIME telephone number. Relay this information to the Federal State Liaison Coordinator Ihn8DIATELY upon receipt.
. 5 .- STANDBY: Initiate counterpart communications with the INIT.(S Headquarters Standby Team (Government Liaison Officer (57Vf TIME (GLO)), through the Headquarters Duty Officer (202/951-0550).
INITIAL ACTIVATION: Counterpart comununications will be initiated by the GLO. EXPANDED ACTIVATION: Maintain counterpart communications. 1 Rev. 1, 02/84
,L.e_
A:*
. 6. Request that for any significant contacts that the HQ INIT.
Federal / State Liaison representative initiates with State F75% TIME Officials, the FSL Manager is bridged on that call. . Maintain periodic contact with the agencies, identified in 2a and b, as appropriate, as well as with Office of State Programs (OSP) representatives (Page III-3). Brief agencies
;on the progression of incident events, and obtain reports on each agency's activities. .
INIT. MeM
- 7. Once.the Federal / State Liaison Coordinator arrives at either the EOF or the State EOC, notifications by the TIME Federal / State Liaison Manager of agencies identified in 2a will be discontinued. Notifications of agencies identified in 2b will be as directed by the Federal / State Liaison Coordinator.
SW INIT.
- S. Report status of various agencies' activities periodically to the Emergency Preparedness Manager and to the Base Team TIME
, Manager.
- 9. ' Respond to requests for NRC advice and assistance from NIT. N M State and local authorities. TIME 10.. Provide any necessary support and assistance to the b INIT. I Federal / State Liaison Coordinator who is either with the TIME Site Team or in the State Capitol Emergency Operations Center.
'11. .Obtain assistance for FSL coo'rdinator as requested through INIT.
OSP. 47(TIME
'12. Maintain a~ record of related activities, b INIT.
TIME TASKS (Deactivation Mode) 1.. Monitor reentry and recovery activities of state and local INIT. government and advise the Regional Administrator. TIME l-
- 2. Assemble all records of significant communications with INIT.
federal, state, and local agencies as well as with NRC TIME response officials. Based on these records prepare a critique of incident operations. 7 k' H 2 Rev. 1, 02/84 4
.) c L; _
w, + m
- S
~
- (Health Physics Manaaer) ,
. BASE TEAM-PROCEDURES-TASKS (Initial and Expanded Activation Modes)
~
4 NOTE: The tasks to.be~ accomplished during the Initial and Expanded Activation Modes are essentially the same. The difference Loperationally-is that'under Initial Activation base team personnel advise HQ through the Base Team Manager. Under
+ Expanded Activations they advise the Director of Site Opera-
^
~tions.(DS0). This function may be discontinued on the Base
. Team'during Expanded Activation.
- 1. -A Health Physics Manager is selected by the Base Team INIT.7gah<<J J -Manager.- TIME /
K
.2.-
^ ~
The Health Physics Manager initially reports to the IRC-
- INIT.
and coordinates'with'the licensee's Rad / Chem Supervisor Cr?4 TIME regarding:
- a. 'the-status of in plant surveys b.t ~t he status of monitored-releases cc. the status of rad. waste systems
,d.1 .the' status of-licensee personnel exposures
~
3.= Appoint a' Health Physics Communicator. Instruct the HPN O INIT. #
? Communicator to use the.IRC Message Form. . Caution the TIE
' Communicator to' press'hard and use a ball point pen when filling out'the IRC Message Form'.
~
- 42 .The Health Physics Manager will evaluate.the status of the JNIY.
~
~
Health / Physics Program including: 07If TIE a.- fl censee' data ~obtained in 2'a-d above. i ' b.1 = protective measures implemented for licensee.emergen y wechers , E' .; 5 '. - ; Coordinate recommendations for any additional Health A INIT.r g 7 Physics programs or protective measures that should be TIE implemented with the licensee..
- 6. ' Coordinate with the Protective Measures Manager in regard f ;INIT.
to protective measures for'energency workers and the TIE /3["'7 , general public.
~
'7.
JReview all licensee radiological data and obtain periodic INIT.
. , updates.' TIE 8'~. Evaluate the.need for. additional Health Physics staff to INIT.
. support the Site Team and monitor licensee activities-in TIE
^e
- -the following areas:
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[. 10Y 2 81983 Docket No. 50-341 The Detroit Edison Company ATTN: Mr. Donald A. Wells Manager, Quality Assurance -
-2000 Second Avenue Detroit, MI 48226 i 3
Gentlemen: W-
Subject:
Emergency Preparedness Appraisal To verify that applicants have attained an adequate state of onsite emergency -- preparedness as required by 10'CFR 50.47(a)(1), the NRC conducts special The
.preoperational appraisals of their emergency preparedness program.
-objectives of the appraisal are to evaluate the overall adequacy and effecti.eness of emergency preparedness and to identify areas of weakness that need to be strengthened.
During the'perio'd'of October 11-21, 1983, the NRC conducted a.special J appraisal of the state of onsite emergency preparedness at the Enrico Fermi 3 Areas examined during this appraisal are Atomic Power Plant-Unit No. 2. ; described in the enclosed report (50-341/83-24). Within these areas, the n appraisal team reviewed selected procedures and representative records,
. inspected emergency facilities and equipment, observed work practices, and 3 y
interviewed personnel. _ No significant deficiencies,' deviations, or noncompliances were identified as ] a result of this appr.aisal. _ The findings of'this appraisal indicate that several areas of your emergency These a preparedness program were not complete at the time of this appraisal. _- areas' among others include installation and calibration of certain equipment; = related procedural development and training; shift augmentation goals; and installation and testing of the Prompt Public Notification System. These - items are identified as Open Items and are listed in the enclosed Appendix A. The findings also indicate that there are several items in your emergency ;
. preparedness program which need improvement, and these items are listed in the -
enclosed Appendix B. These improvements are areas which we feel, based on
]
professional judgement, should be corrected. lYou are requested to submit a written statement within thirty days of the date Lof this letter, describing your planned actions for completing each of the items identified in Appendix A.and the.results of your consideration of each
-of the items in Appendix B. Some of the Open Items must be adequately -
These items have been specifically identified a ddressed prior to licensing. in Appendix A. m n IGkin y/ Ph? - s ;
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r . The Detroit' Edison Company 2 % 28 883
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I-In accordance' with 10 CFR 2.i90(a), a copy of this letter and the enclosures
> >;will be placed in the NRC.Public Document Room unless you notify this office, jby telephone, within ten days of the date of this letter and submit written "
= application to withhold information contained therein within thirty days of
'the date of this letter.- Such' application must be consistent with the re-
- quirements- of 2.790(b)(1). If we do not hear from you in this regard within f
M (the specified periods noted above.-a copy of this letter, the enclosures, and L ';your response.to this letter will be placed in the Public Document Room. : The responses. directed by thisLletter are not subject to the clearance k
. procedures'of the Office of hanagement and Budget,as required by the Paperwor
. Reduction Act'of 1980, PL 96-511.-
We will gladly. dis' cuss any questions you have concerning this inspection. a . Sincerely, . i[ - [r j C.J.{Paperi lo, Chief
.s ;
Emergency Preparedness and Radiological Safety Branch l
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Enclosures:
.'1. -l Appendix A,: Appraisal-Open Items- >
.l2.? Appendix B, Appraisal-
. Improvement Items
>3. -Inspection Report -
.No. 50-341/83-24(DRNSP)
F :- ~ cc w/encls:
.W.' ,
Jens, Vice President-Nuclear: c . Operations . LR..Lenart, Superintendent-Nuclear
. Production' u- LDMB/ Document. Control Desk (RIDS) 1 Resident Inspector, RIII' Ronald Callen, Michigan- .
s , Public Service Commission
- Marry E. Voigt, Esq.-
D.:Benent, FEMA,-Region V.
\
- D.-lMatthews, EPB, OIE:
- +,. 4 1o t s on/1d
'10/31/83 t ' '
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Y l 1 Appendix A - Open Items
- s
.:The following.is a list of Open Items identified in the area of emergency preparedness .which must be completed and re-examined prior to the fuel load, full power authorization, or in accordance with the schedules set forth in
.your NUREG-0737 correspondence.
l1. Satisfactorily demonstrate that shift augmentation can be consistently achieved within the goals specified in Table B-1 of NUREG-0654, Rev. 1; e.g., 30 to 60 minute response time with 11 persons in 30 minutes and 15 persons in 60 minutes. This must be completed prior to initial criticality. (Section-2.2) (341/83-24-01)
- 2. Complete installation, development of procedures, and training on the use
< of. Post-accident Primary Coolant Sampling System. This must be completed
' prior _ to. exceeding 5% power. (Sections 4.1.1.5, 5.4.2.4, and 5.4.2.5)
-(341/83-24-02)
'3. Complete installation, development of procedures, and training on the use
'of Post-accident Containment. Atmosphere Sampling System. This must be completed prior to exceeding 5% power. (Sections 4.1.1.6', 5.4.2.6, and t -
- 5.4.2.7) (341/83-24-03)
- 4. ' Complete installation, development of procedures, and training on the use of Post-accident Special Particulate, Iodine and Noble Gas (SPING) System.
This must?be completed prior.to fuel load.' (Sections 4.1.1.7, 5.4.2.8, y Jand 5.4.2.9)-(341/83-24-04) 5 .- Calibrate the analytical instrumentation in the Emergency Operations Facility (EOF) laboratory. This must be completed prior to exceeding 5%
-power. (Section 4.1.1.9) (341/83-24-05) t!
.[ . ,
- 6. Complete the Emergency Decontamination Facility. This must be completed prior to, fuel load. '(Section 4.1.2.3) (341/83-24-06)
. 7. Complete calibration of-containment high range monitors (ARMS) and all other process radiation monitors. This must be completed prior to fuel
. load. (Section' 4.2.1.2) (341/83-24-07).
J8.- Licensee.must develop a program for the surveillance, maintenance, and calibration of.the' meteorological measurement system. This must be completed prior to exceeding 5% power. (Section 4.2.1.4) (341/83-24-08)-
.9. - The Emergency Plan and Procedures must be revised to reflect 10 CFR 50
. Appendix E, IV.E.9.d requirements such that communication checks to the
-MRC Headquarters and Regional Office from the Control Room, TSC, and EOF-u will be conducted monthly. This must be completed prior to fuel load.
(Section 4.2.3) (341/83-24-09)
~
10.1 Develop procedures and complete training for the collection of liquid effluent' samples.. This must be completed prior to fuel load.
.(Sections 5.4.2.10 and 5 4.2.11) (341/83-24-10)
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, ~ Appendix A
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- 11. Maintain provisions with an;offsite. vendor to expand.the environmental
! monitoring program in the event _of an emergency to. collect and analyze water,~ milk,-soil, vegetation and air samples. This must be completed 7 prior to exceeding 5% power. (Section 5.4.2.12) (341/83-24-11)
.12. JImplement , security system.for accountability. This must be complete d Jprior to fuel load. (Section 5.4.3.3) (341/83-24-12)
- 13. Complete training lof appropriate offsite governmental support agencies, including a. review of Emergency Action Levels (EALs) and expected
' response and. site' access procedures for-local Michigan State Police m
personnel. .This must be completed prior to exceeding 5% power.
' -(Sections 6.1.1,.6.1.2, and 6.1.3) (341/83-24-13) 14~.1 Complete installation of non-radiological process monitors ,',arogen, Loxygen, chlorine).- This must be completed prior to fur sad.
.(Section'4.2.1.3) (341/8',-24-14)
$15.: Complete-: installation and testing of the Prompt Public Notification N . System tofensure Cuat physical means exist'.to alert the public of an
- ' emergency condition. This must be completed prior to exceeding 5% power.-
- (Section 6.2.2) (341/83-24-15)
~
c16. :EALsiwhich are general in nature should'be made more specific by including
- i. instrument readings' or. equipment status indicators which are used-to
~
' classify an emergency., For example, EALs involving high radiological:
~ effluent condition and the containment high range radiation monitor must
-includelspecific. radiation levels. This must be completed prior to
* . initial criticality. (Section -5.3) ~ - (341/83-24-16) n N
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. Appendix B - Improvement Items s
~ Based on the results of the NRC's appraisal.of the Enrico Fermi Atomic Power Plant l emergency preparedness program conducted October 11-21, 1983, the
~
following items should be considered for improvement:
~
U 1. - Develop. instruction' sheet'on how to energize the HVAC (heat, ventilation,
~ir a conditioning) System in the Technical Support Center (TSC) and attach it to the front of HVAC System; control panel. ^"
s (Section 4.1.1.2)
- 2. - = Revise Emergency Procedure-301-2, Section 5.5.1, relating to elevated tairborne radioactivity levels, to reflect. current practice.
(Section . 4 '.1.1.' 2)
- '3. - The alternate Operational Support Center.(OSC) should be equipped with fixed perma'nent emergency lighting. (Section 4.1.1.3)
~
!4 1 Acquire for the Emergency Operations Facility (EOF) decontamination f _ supplies and protective clothin'g. (Section 4.1.1.4)
I 5. s 1Developian: inventory _of supplies for the Alternate-EOF, include it in ye _ procedures,1and maintain a copy with the Alternate EOF supplies, s ~(Section 4.1.1.4)
- 6. tPosition the staged Personnel Monitoring Team. kits at the three offsite m "
fassemblyflocations.:1(Section 4.1.2.1)
-7._ InElude a copy of'the latest completed inventory list in each of the iemergency kits. (Section 4.2.1.1)_ .
Tall' equipment contained ~in the emergency supply kits should have
'8.; '
~ expiration dates where appropriate'and should be kept calibrated.
.(Section 4.2.1.1)
.o
- 29. 'lThe. applicant _is encouraged to work with other BWR owners toLdevelop
- Lemergency_ action-levels which_are symptomatic based similar to Emergency 10perating Procedures as opposed.to event' oriented emergency action levels
~
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'which are contained.in the. current emergency. plan implementing procedures.
* .(Sectionj5.2):
- 10. -Reviselthe Radiological Emergency Response ~ Preparedness (RERP) Procedures 1102-105 to reflect,the requirement of.10 CFR 50.72,_that State and. local:
- agencies,will be notified prior to notifying the NRC. (Section 5.4.1) f,
-11. :An appropriate type and number of hand-held calculators should be
~
provided to the individuals who_ implement manual dose assessment procedures.EP-540 and -541. (Section 5.4.2)-
' 512.s EMake a provision for incorporating field monitoring data into dose.
" projection, calculations. ;(Section 5.4.2) m ,
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I-R - 2P - Appendix B' 2 I13. Document :that the vendor's environmental monitoring program and the applicant's emergency environmental monitoring program will provide i
. comparable'results for all possible environmental media.
(Section 5.4'.2.12)1
- 14. LClearly' mark assembly / evacuation routes with conspicuously posted arrows, l signs, floor' markings,(colored lines), and/or other readily visible means.
.(Section 5.4.3.2)
! , 15; Any " dead spots" for HI-COM or radio. reception within the plant should be
'N sidentified and the system upgraded accordingly. (Section 5.4.3.2)
.16. :A' controlled copy'of.the, applicant's emergency plan should be provided to i tall:offsite support. agencies,-e.g., police, fire, ambulance, county EOC's, Rand. Brown'stown Township. (Sections.6.1.1, 6.1.2, and 6.1.3)
L17. Keys for the emergency lockers should be available, but on a controlled 4 basis. - (Section-7.2) 6 -18. Detector units for portable , radiation survey probes should be replaced as
' cpart of the: radiation monitoring ~ equipment at Seaway Hospital, Trenton, Michigan. (SectionL6.1.6)
- i ;19.f Revise Letter of Agreement with Frenchtown Fire Department (FFD) to
'*J specify who will'be in charge while.onsite, the FFD.(Chief) or the Fire.
"'_ Brigade Leader. . (Section 6.1.7) c
- 120 1: Resolve the status of the request.to change paragraph 4(c) of the Fixed
- < Facility- Emergency Response Voluntary - Assistance Agreement as requested
[by.1NPO-ina; Detroit.EdisonletterofMarch 11,-1981. (Section 6.1.7) 121. iProvide' training forfall acci ent d types- listed in'the RADOSE menu. c~!
- (Se6 tion.7.2)L'.
J22. ~Specify the individual'or organizational element responsible for 9, performing the tasks covered in.each emergency plan implementing
. procedure. ;(Section 5.1)'-
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,,'1
, . CONTENTS c
1 Page, E - II . 0 :- ADMINISTRATION OF EMERGENCY PLAN. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 4 32.0 cEMERGENCY' ORGANIZATION.'..................................................
> 2.1! 0n' 1 site Emergency Organization....................................... 4 5
[2.2[ Augment'ationoftheEmergencyOrganization.......................... 6
, 13.'OM: TRAINING:an[ RETRAINING..................................................
, I3.1[ProgramEstablishment......~......................................... 6 5 , .-' r* -
7 n: y3.2: Program Implementation..............................................
!4;0 eEMERGENCY FACILITIES ~AND EQUIPMENT....................................... 8 8
"4 ; 1 h Emergency Facilitiie s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
8
; ~ 4.1.1 JAs se s sment Facilitiies . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
. 3.:
' k 8 L _ 4.1.1.1- Control-' Room........................................
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f ' 2 4'.1.1".2 : ; Technical: Support Center (TSC) . . . . . . . . . . . . . . . . . . . . . . 9 9 ,, ,3 : 10 Ji ,
'_ [4.1.1.3: Operational Support Center (0SC)...................
' - 4.1.1.4 1 Emergency Operations Facility ' (E0F) . . . . . . . . . . . . . . . . . - 10
=421.1.5 Post iccident-CoolantiSampling and Analysis..;..'... 11
. ' ^
^
4.1.1.6LPost Accident I Containment Air Sampling and Analysis. 11 . Post' Accident Gas, Particulate,'and Iodine Effluent
, f 4.~ 1.1.7. '
12
? Sampling;and Analysis..............................
e _ i , 14.1.1.8 + Post: Accident Liquid Effluent Sampling and Analysis.12
,. x .
- 4.'1.1'. 9 E 0f f site Imboratory Facilitie's . . . . . . . . . . . . . . . . . . . . . . . 12 (N , '
Facilities..................................'......-13 D.#w <
~
7 4.1.2J Protective 13 ;
~- 14.1.2.1 Assembly, - Rea s sembly - Areas .~ . . . . . . . . . . . . . . . . . . . . . . . .
[ _' , x,. [ 1 ;4.1.2.2c Medical Treatment Facility.......................... 14' m , 14
, T4'.1.2.3 9 Decontamination Facilities.........................
' I I N4il .3 [ Expanded Support Facilities. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15 R. 1 15
. :4.114L News Ce6ter.................................................
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E 24.2 LEmergency Equipment...'.............................................. 15
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. '4. 2.1. iAs se s s me n t . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15
~
!4.2.1.1' Emergency Kits and Survey Instrumentation.......... 15 a.: . J 4.2.1.2 ' Area and Process Radiation Monitors. . . . . . . . . . . . . . . . 16
' ,gr
.4.2.1.3 Non-radiation Process Monitors..................... 17
=4.2.1.4.~ Meteorological Instrumentation..................... 17 t a.
' 4 . 2. 2 - Pro t ect ive . Equ ipment . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18
._4.2.2.1 -Respiratory Protection............................. 18 4.2.2.2 Protective Clothing................................ 18 19
. .g 4.2.3' Emergency. Communications....................................
4.2.41 Damage' Control / Corrective Action and Maintenance Equipment
.- an d - Sup p lie s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 19
- 4.2.5 : Reserve Emergency Supplies and Equipment. . . . . . . . . . . . . . . . . . . . 20
~
5-
. 4 . 2 . 6 L - Tran sp o rt a t io n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 0 20 5.0 . EMERGENCY IMPLEMENTIN
G. PROCEDURE
S.......................................
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~
4 L'Eg 5.11 Genera 1Mgak,ent ,,. and Forma t . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 20 p.
,1 . 552f Emergency,' Alarm, and Abnormal Occurrence' Procedures............... 21
- g" w 3 y 5. 3 JImpipmenting Ins tructions . . .'. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 22 4 25.4: Implementing Procedures............................................ .
24 24 x 5.4.1. Notifica't ions..............'................................. a~
-5.4.2eAssessment-Actions........................................... 25 v.
x
'5.4.2.11'Offsite Radiological Surveys....................... 26 i5.4.2.2 Onsite' Radiological. Surveys........................ 27 3
~,
Surveys....................... 27-c , 75.4'.2.3 :In-plant; Radiological
.. 15.4.2.4 : Post ' Ac'cident Primary Coolant Sampling. . . . . . . . . . . . . 28
~
'5.4.2.5 Post Accident Primary Coolant Analysis....,.........'28
~
4"4 Y 97:N _ Post Accident-Containment Air Sampling.............. 28
.5.4.2.6
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, 11
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'l 5.4'.2.7 -Post Accident Containment Air Analysis.............. 28
'f _ 5.4.2.8-cPost Accident Stack Effluent Sampling.............. 28 i 28 A ' 5.4.'2.9 Post Kccident Stack Effluent Analysis.............. m
-5.4.2.10 Liqui.d Effluent Sampling........................... 28
- .i ,5.4.2.11 Liquid Effluent' Analysis........................... 28-
~
5.4.2.12 Radiological Environmental Monitoring Program (REMP) 28 15.4.3 Protective' Actions.......................................... 29 T5 .4.3.1 Radiation Protection During Emergencies. . . . . . . . . . . . 29 5.4.3.2'- - Evacuation of Owner-controlled Area................ 30 5.4.3.3' Personnel-Accountability........................... 31
; ' 5.4.3.4 : Personnel Monitoring and Decontamination. . . . . . . . . . . 31
*! : 5. 4.3.5 Onsite Firs t Aid / Rescue . . . . . . . . . . . . . . . . . . . . . . . . . . . . 31 (5.4.4. Security During Emergencies . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 31
- u. -
J 5.~ 4. 5. Repair and Corrective Actions............................... 32 S
;5.4'.6' Recovery.................................................... 32 e
32
~
g- 5.4.7? Public Information..........................................
- 5. 4. 8 1 Fire Pro tection . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 3 t , , .
5.51 Supplemental-Procedures.............................................'33 . E5.5.1 " Inventory Operational Check, and Calibration of Emergency Equipment'and Supplies...................................... 33 P 33
. 5.5.2 Drills and Exercises.................................'.......
k A 5.5.3.-~ Review, Revision,_and Distribution of Emergency Plan
-and Procedures.............................................. 34'
~
34
$5.5.4' Audit....................'...................................
ed 34~
'6.0'. COORDINATION WITH OFPSITE GR0UPS.....~...................................
34'
?6.1EL0ffsit'e[ Agencies.......'............................................
'6.1'.1S Monroe: City-County office of Civil Preparedness'and. Monroe
' ' 1 County . Sherif f 's Depar tment . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 5 N
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' + - 35
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6.1.3 = Wayne- County, Michigan - Office of Emergency Preparedness. . . 36
, 6.1.4 Frenchtown Township Fire Department......................... 36
' '6.' 1. 5 EMTS Ambulance Service...................................... 37
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6.1.6 ? Seaway Hospital, Trenton, Michigan. . . . . . . . . . . . . . . . . . . . . . . . . . 37
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7 6 1.7 , Letters of Agreement................................. ...... 38 6.1.8 : Assistance from Contractors Vendors, and Other Utilities... 39 l 6.2 ~ General Public and Transient Populations . . . . . . . . . . . . . . . . . . . . . . . . . . . 39
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'6.2.1' .
Information 21stribution.................................... 39 c 6.2.2 Prompt Public l Notification System. . . . . . . . . . . . . . . . . . . . . . . . . . . 40 4 g' :v J6.32 qNews Media...... ................................................... 40
- 7.0 : DRILLS , EXERCISES , f and WAIK-THROUGHS. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 41
,.j7.1.-Drills and Exercises............................................... 41 L7.2d Walk-throughs of Emergency Response Personne1...................... 41' t
18.0 0 PERSONS. CONTACTED....................................................... 43 9.0.: EXIT INTERVIEW...........................................................'44 ANNEX A -LATTACHMENTS y; J ATTACHMENT 1 Staffing for. FERMI 2 Emergency Response Organization w ATTACHMENT l2 Nuclear _ Operations Organization -
. , , MATTACHMENT 3 Emergency Re'sponse Organization Functional Responsibilities b
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N , i U.S. NUCLEAR REGULATORY COMMISSIGN
, REGION III O Report No. 50-341/83-24
' Docket No. 50-341' License No. CPPR-87
- Licensee: -The' Detroit Edison. Company 2000 Second Avenue Detroit, MI: 48226 Facility Name: Enrico Fermi Atomic Power Plant-Unit 2 L ' Inspection At:- Fermi Site - Monroe, Michigan Inspection Conducted: 0ctober 11-21, 1983
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1/[2 f[N
, Inspectors. .-J. . Patterson- ~
Date Team Leader-
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Da'te Date-lApprovedBh , Chief ~/ IN# + Emergenc Preparedness Section Date b ll 2- f3
% . . P's riel o, Chief
. Emergency Preparedness'and. Da'te
. Radiological Safety Branch
. Inspection Summary
, . Inspection on October 11-21, 1983 (Report No. 50-341/83-24(DRriSP)).
Areas Inspected: Special. announced pre-operational appraisal of the state of: onsite emergency preparedness at the E rico Fermi. Atomic Power-Plant -Unit 2-
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1 involving.seven general areas:< Administration of the Emergency Preparedness J Program; Emergency Organization; Training; Emergency Facilities and Equipment;
-Procedures which Implement the' Emergency Plan; Coordination with ,0ffsite l Agencies;'and Exercises.and. Drills. The: inspection involved 522
_ inspector-hours;onsite by three:NRC inspectors and five' consultants.
-:Results:1- No items.of' noncompliance or deviations were identified, however several.open items.which must be completed before fuel load were identified. ~
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DETAILS
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a 4 , s1.0, ' Administration of Emergency' Plan
' 1.13 EResponsibility Assigned
, . Responsibilities'at-the_ Corporate level for emergency planning are
; assigned to-the;Vice-President, Nuclear Operations as the Emergency
- Officer. 'He.has,the overall management responsibility for the
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, Emergency. Response Organization-(ERO) :and for all assignments in the sj -
. ; organization. -At'the site,_the Superintendent-Nuclear Production as 2
, Emergency Director hasithe: prime ~ responsibility and authority for emergency response measures and implementation of the Radiological
' Emergency Response Preparedness (RERP) Plan until the Emergency LOperati6ns Facility.(EOF)'is activated.
'Th'e'RERP. Supervisor is. responsible.for developing and updating the RERP Plan and its implementing and administrative procedures. He
- . coordinates-the development and revision of the plan and procedures
-" withJother emergency response groups, support agencies and State and
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3._ :locallgovernments.-:He is also responsible'for ensuring that all ERO
? personnel complete required-training in emergency-preparedness as
- m - Jrequired by RERPfAdministrative Procedure-EPA-8. There is provision
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=foriinputiin the' form of recommended. corrections and any proposed irevisions'to the RERP Plan. This input is documented and reviewed R Eas described in RERP Administrative Procedure EPA-3. The RERP
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z Supervisor -reports to the Assistant Manager and Director of Nuclear 4 , Engineering,Lwhofreports'to the Manager of Nuclear Operations,'and jp -he in; turn to:the Vice President,-Nuclear Operations. -This.
.v; )Vice-President, as listed previously,' serves as the Emergency 1' -
' Officer.';:This chain-of-command is! separate from the reporting line fleadingito-the Superintendent-Nuclear Production, who is in charge '
Jof plant: operations. - 11.'2 L Authority!. 4'i .The[ Emergency. Officer,'VicePresident-NuclearOperations,hasthe.
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' overall" authority for bothLsite and corporate emergency response activities. ;This: authority is: defined'in~the planass well_as in the.
" implementing. procedures' yPersonnel assigned emergency functions are
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G Lgiven1the authority to perform assigned dutiesLas directed by the
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- > Emergency' Director,1 Nuclear ~ Shift Supervisor, or his alternate'as' M11sted:in.the RERP Implementing Procedures.-.Those with emergency
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l response' functions automatically. assume their emergency positions ' _n ,. 'lwhenever the RERP Plan is activated. .The RERP Supervisor has the.
<W?? a ? authority from.the ViceLPresident-Nuclear Operations to assume the
"- i . ; duty lof Emergency Planning Coordinator.which includes responsibility
- for: developing and updating'the emergency plan land Laplementing
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<l procedures, and for_ coordinating;the plan and procedures'with the
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4 i1.3 ' fCoordinationi (The RERP. Committee,is responsible for review of the RERP Plan and
* "- Implementing Procedures as well as other aspects of the RERP
- program.E This committee, which meets monthly, approves the plan and eprocedures and recommends approval by the On-Site Safety Review
* . Organization within Nuclear Production-Nuclear Operations. The
- committee reports to the Vice President-Nuclear Operations and is
- responsible foricoordinating all interdepartmental activities needed for the RERP program. This: committee function is described in Section" P of the RERP Plan and also -in the Emergency Plan Administra-ltive Procedure, EPA-1. The RERP Supervisor.is the Chairperson of this: committee. He is also' responsible for coordinating offsite and (onsite emergency planning activities.
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-1.4L LSelection and Qualification
, . Selection. criteria-for'those responsible for emergency planning are
' based on job experience, educational background and other qualifications determined by manag'ement as essential for the 1,
position. The inspector determined through interviews with J ' incumbents and review of training.and other personnel records that i ~ those-in the positions.do meet these criteria. Necessary training y ' is provided to emergency. planning personnel. ' Professional
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N development-training courses'are made available to the RERP
; Supervisor,.who has the prime responsibility for emergency ~
. planning.f These training courses consist of two to' three day
< workshops: conducted by the Institute of Nuclear Power Operations (INPO).; These courses are'also available to the Emergency Officer.
'.1S5 ) ,' Quality Assurance of Emergency Preparedness Program.
4 .The Nuclear-Safety Review Group (NSRG) is responsible for arranging for..an' independent' audit of the RERP Program on an annual basis.. This audit addresses all aspects of the RERP' Program, including both [ ,d4 :the plan and the procedures, training, equipment and the interfaces
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with the State and local' government agencies.' This' audit will be. _ 4 ; performed by.the Quality Assurance group.- The NSRG documents any
- ' recommended' corrections or proposed revisions to the plan. This
- + 'I, s procedure is described-in RERP Administrative Procedure EPA-3.
^ These results are forwarded to'the RERP Supervisor, who recommends i these corrective actions be carried out; ~ Final review and approval,-
jismadeby'theRERPCommitteeandtheVicePresident-Nuclear-10perations. Documentation of these reviews of the RERP' Program will'
@ be retained by the applicant for at least five years.
f ' I'An' audit. Subcommittee of the'NSRG will actually review the audit
@ [ findings which have been made-by_a Quality Assurance (QA) group that reports in a separate line of corporate structure to a'.Vice
President with'no emergency preparedness authority as required by-
,f :10 CFR 50.54(t). One of'the members of this' subcommittee isithe-
% Director of Quality Assurance. At the time of this appraisal no-
,g ( , formal independent audit'of the RERP Program has been conducted.
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- 1 LThe. inspector reviewed'the actions taken to correct the NRC findings ,
~ .from the February 1982 full scale exercise and found them to be l satisfactoryLwith 9 few open items remaining due primarily to j 4
L equipment' installation.' j
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' Based on the above' findings, this portion of. applicant's program is l 7 Lacceptable. ,
, % +2.0) LEmeraency Oraanization I y: :-221 ; ;Onsite Ormanization iig The onsite emergency: response. organization is staffed as illustrated
* :in Table B-1'of the RERP. Plan. A copy of this table is attached as ;
< ' Attachment 1. This table also includes the response time for Alert 11evel orchigher for the individual filling'.that position if that
. person is not on' ~ duty. An organization chart of the Nuclear
, Operations Organization (see; Attachment 2) is also-included to show
. the' functional levels and to detail the plant and technical support from Section B of the RERP Plan. ;An onsite emergency organization
%' chart listing functional responsibilities is included as-
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' Attachment-3. This chart: lists the functional position, alternate,
' reporting function, emergencyLresponse location, and the emergency
,. ; responsibilities for each position.
The' Emergency Director who in normal operations is the Nuclear Shift
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Supervisor.is available onsite at all times. He has'the authority ,
'and responsibility to' initiate ~any emergency actions within the
.! provisions of the:RERP Plan. These functions are described in EP-110 as well.~as in the plan.
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* - 'The plan identifies the following key _ positions'of the onsite emergency organization:' Emergency Director of Control-Room (Nuclear EShift Supervisor); Emergency Director of TSC (Superintendent: Nuclear Production); Communicator.(Licensed Operator); Shift Technical'
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sAdvisor;'. Radiation Protection Advisor (General Supervisor-Health
~ Physics); Operations Support Coordinator (Maintenance Engineer);
Emergency Officer of EOF,(Vice President Nuclear Operations);. EOF R: Coordinator l(Manager, Wayne-Monroe Division); and Radiation
' Protection' Coordinator (Corporate Health Physicist). Other supporting positions in the TSC, OSC, and EOF were evaluated by the
; inspectors.and found to be~ adequate'in expertise and depth of'
- Jcoverage for emergency preparedness functions.
.Other emergency response positions: identified include support pers'ennel skilled in radiation safety, technical support, electrical and mechanical support, damage assessment:and repair, search'and irescue, administrative support,iand security / accountability. These
- lmsjor emergency tasks are assigned to: individuals' whose normal job
- function is similiar or related to accomplishing the. emergency responsibilities.
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w f CThe applicant's emergency plan specifies that the minimum shift
' staffing st all times will be 11. This includes four licensed
*- operators, four noglicensed operators, one Shift Technical Advisor, one Health. Physics / Rad-Chen Technician, and one Instrument and
> Control Technician.- ,
3
- :The REPR Supezvisor is responsible for determining the qualifications y ;of persons who function in the emergency response organization. The
' selection of personnel for emergency functions is a joint effort lbetween him and the manager or supervisor of the individual. The RERP; Supervisor may exercise veto _ power over a certain individual if
~he feels that person does not meet the-qualifications his department
, has' established. 'No other selection criteria are involved.
; Based on the above findings, this portion of the applicant's program (is acceptable. .
2,2 -Augmentation Ormanization
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- The Radiological. Emergency Response Preparedness (RERP) Plan
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' delineates in Section B, Table B-1,-The Emergency Response a- ~ Organization Staffing Plan. Table B Emergency Response
;0rganization' Functional Responsibilities-specifies by positilon/ title v : assignments and-functional responsibilities in the emergency cresponse organization. Corporate personnel are assigned to augment ein the areas 'of emergency. response coordination, foperational, accident assessment, radiological accident assessment, radiological'
"' environmental survey and monitoring (offsite RET), technical s
support, manpowe_r and logistical support,'and public information : including dispatching a licensee representative to the state EOC. Additional health physics support' personnel are available through n mutual aid agreements with four neighboring utility companies. , Those individuals designated ~to' augment the emergency organization. are assigned to' areas directly.related to their corporate position; and/or' ares' of expertise. Except for one key position, a minimum of - three qualified persons are available for each position. ' The one texception is' Emergency Operations' Liaison, where.there are only two
-persons available.
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.x .The' applicant has contracts with General Electric.and a private
_ consulting company to provide technical assistance to and
! augmentation of the. emergency organization if required. -Additional assistance is available for communications via a computer telecom-
- munications information exchange system under the administration of
< ,INPO. ;This information system-is identified by the trade name NOTEPAD. Only information approved by the Emergency Director will
- :be transmitted via' NOTEPAD. ,
aETo date, the applicant has not satisfactorily demonstrated that the.
-minimum augmentation specified.in NUREG-0654, Rev. 1, Table B-1, can.
.be. accomplished within the 30'and 60 minute goals. The two most 5
;recent' drills (both'were notification drills only, not involving actual travel to the. site) used estimates of departure and transit 4
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- times for persons contacted for mobilization. For'the September 21, A 1983, drill key personnel.such as the OSC Coordinator, TSC Nuclear Safety Advisor, TSC RAD Protection Advisor, = and the Meteorologist
* . required in excess of.60 minutes to arrive, with some non-key
^
personnel in those' areas estimating up to 2 hours to arrive. The September 13,-1983, drill showed similar times, i.e., in excess of
' one' hour for some: key personnel, and in excess of 2 hours for some non-key personnel. The: inspector's review determined that the
-system for augmentation notification is proceduralized and workable.
The following changes should be made to improve the shift augmentation concept:
- 1. Ths applicant should limit the number of staff required to respond within 30 minutes to 11.instead of 21 in keeping with
'NUREG-0654,~ Revision'1 guidance. .Thus, give a priority to fill
,/ En certain'energency positions by lowering the number of key 2f persons to be called. The inspector also suggested a change to
- 15 people required.for.a.60 minute response time.
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- 24. Clarify, through training, that the staff augmentation complement has 30 or 60 minutes to assume their function from
'the time the emergency is declared, not from their notification time.
4
- 3. ' Individual pagers.or some other means should be considered-for those people difficult.to reach. An evaluation of the call-in procedure should be made to assess.the various response times with the individual's. emergency position,-1.e., change the priority?of call-ins..
. Based on:the above findings, the following action must be taken to
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. achieve an acceptable program:- .
.: Satisfactorily demonstrate that shift augmentation can be consistently achieved within the goals specified in Table B-1 -
~t -of'NUREG 0654, Revision 1. -This must be completed prior to initial: criticality. :(341/83-24-01) f 3. 0 .- - Trainina/Retrainina
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- 3.1. :Prosram Establishment
?The applicant has a formally documented Emergency Plan
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c 1 Training / Retraining Program. The program is promulgated and
- specified in'sectionM'0" of'the RERP Plan, which is implemented in
-.the EP Procedures by EPA 8 . This section of the plan plus related 4 implementing procedures adequately' describe the training program as
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part of the-RERP, as required by 10 CFR Part 50, Appendix E, Section:IV.F. 1
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>% Qualification criteria-for the various functional area assignments are listed-in Emergency Plan Administrative Procedure EPA-8.
Training for the v9rious. emergency' assignments is specified in a training matrix of 20 modules (plus drills and exercises) against 65 1 categories of functional assignments. Within these 20 modules, all *
- functional areas of.the RERP Plan are addressed with the exception
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of meteorology;.however, three professional meteorologists are assigned _to Fermi'2 and are available on-call. _ General' employee training includes a section on Emergency Plan
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u cactions_and; requires an annual retraining session. Both initial and
' W _re-training are formally scheduled and include written
, ; examinations. Similar training and annual retraining is specified for licensee augmentation (corporate) personnel.
1~ - Formal' lesson-guides l are provided for each module of RERP training. m These guides state the training objectives, and are regularly +
> l upgraded as appropriate based on shortfalls or other deficiencies
. identified through~ drill / exercise. critiques, student / operator feedback, instructor, feedback, and the like.
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--Several instructors were interviewed and found to be well qualified and highly motivated. Training records were reviewed by the
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;; ; inspectors. The record' system is logical, practical, and thorough.
. A sampling revealed the system to contain the specified information
- 4- and in readily retrievable form. Included are class attendees (by -
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-name), class date, lesson title, instruct.or, exam grade and exam
. answer. sheet. Exam questions are also available by cross
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reference.
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Ms s -Training program's include both classroom and practical demon.stra-
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Y^ - ' x ltions,Eincludingusebythestudents'ofequipmentwhichmightbe. e o , used'during-an emergency.- -
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Changes to emergency organization procedures and equipment which foccur'in the period between. scheduled retraining sessions'are g - : promulgated using' mail-outs to affected personnel, who are' required-
/, ato' acknowledge by mailback that they have received and. reviewed the tchanges. Follow-up_is accomplished'(by training personnel) to g
,,J, assure full coverage and acknowledgement. 'All such interim emergency training provided by.maillis reviewed, summarized and J;' '
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-tested at the.next. annual retraining session.
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. Based'on the above findings, t.his portion of' the applicant's program
;is acceptable. .
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- 3 2. Proaram Implementation EA= review of training records supported the fact that training and examinations had been conducted'as scheduled and requir~ed. Records N>
were found to be accurate and-complete. . Examination scores and " - examination answer sheets were retained in the individual's training-s
- file.. The examinations themselves were filed' separately and were
# 'available for review.
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The manual [ training records system is supported by a computerized
. system entitled the " Personnel Training History System" (PTHS).
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, This system is not,yet-completely loaded with'back training data,
- but~such loading is proceeding at an orderly pace. The system
~- allows reasonably rapid retrieval'of' training information and data.
1WalkthroughLdiscussions were conducted with various persons having emergency response assignments (Ref. Section 7.2). These discussions substantiated the reported training and demonstrated that applicant personnel understood their emergency plan functional
^ assignments.
-Training is being provided for local services support organizations as.the EMTS Ambulance Service or Frenchtown Fire Department, who might be called to the site during an emergency.- Radiation Management Corporation 1(RMC) is training the EMTS Ambulance Service
- Land the Seaway Hospital. The Frenchtown Fire Department is being
-trained by the applicant.. Any entry to the applicant's protected area is controlled:by the Security Office, who provide any necessary escort: to .the specific. plant area. This helps eliminate the necessity _for. extensive training.in access procedures for these ofisite; support: agencies.
s - Formal training has not-yet been provided to the offsite_
. governmental agencies whose geographic boundaries are within the 10 imile EPZ, e.g., Monroe County, Wayne County and Brownstown Township.
.This ites is discussed in.Section 6.1 of this report. ' Training will
'be conducted by the licensee's RERP group or operations personnel
'where needed atleach of these agencies.
' Based on'the above-findings, this portion of the applicant's program
'is acceptable. ,
~4.0' Enernency Facilities and Equipment'
, 4.1 Emeraency Facilities. .
4
' Assessment Facilit'ies-4.1.1' -
'4.1 .1 " Control Room
- The inspecto'rs' reviewed Control. Room emergency preparedness. . . .The
-Control Room contained updated copies of the Emergency Plan and
, Implementing Procedures,y Emergency communication equipment consisted of.two. dedicated telephone lines to the TSC, one to the
- 0SC,; Michigan State Police, Monroe County Sheriff,.an NRC Emergency-
-Notification System (ENS) line and several additional dedicated.
E Llines, including one to the_ West-Sandwich Police Station in Ontario.
- Canada..'A. closed circuit television camera was also present in the
. Control Room and will be-used to provide access to data on the Control Room panels'in'the TSC. 1 Computer terminals are also Tavailable in the' Control Room. The Shift Technical Advisors have
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been trained to use them 'for emergency dose projections. [
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(.. ' Based!on the'above findings,.this portion of the applicant's program f Jis ' acceptable.
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4.1.1.2 ._ Technical Support Center (TSC)
;The' inspectors examined the Technical Support Center .. 3C) sad associated equipment and procedures. The equipment in place appears W -to be adequate with the exception of the Safety Parameter Display U ~ System (SPDS)'and the~inplant intercom system (HiCom) which have not Lyet been installed in the TSC. The TSC is approximately a five
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' minute' walk from the Control Room.
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- - :The TSC is equipped with de'dicated and. general commercial telephone
- lines, a microwave system and an antenna that can have a radio conrected when necessary to monitor offsite teams. Dedicated
- telephone lines include the NRC's FTS and ENSLfor the licensee portion of the TSC, the ENS and FTS for the NRC office and dedicated lines exist between the TSC and the Control Room, EOF, Monroe County Sheriff and Michigan State Police. The NRC office also contains
-four outside lires.
d
# .According:to applicaat pers.onnel, shielding of the TSC has been
. designed in'accordance with Item II.B.2 of NUREG-0737; i.e., limit n personnel exposures to 5 rem to the whole body over a 30-day period.
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-The TSC contains a HVAC system which upon activation of the TSC, is
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'the responsibility;of the Nuclear. Security Force to' insure it is-energized. -However, no procedures could be found.that instructed
< ; ;.6 (the Security Force on how to energize:the system. .The' Radiation
-Protection Advisor is responsible for monitoring the.TSC for.
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, airborne-contamination. . Although Emergency Procedure EP-310-2, Section-5.5.1,7 states that if' airborne radioactivity levels exceed
* .the limitsf of Health Physics Proceduri461.000.05,'all personnel will *
._ don respiratory equipment, the applic.nt ~has already determined not
'to do this,'and therefore maintains;only five respirators in the 1
- TSC.'
/The.TSC!is large enough to provide adequ' ate working space ~for a
- minimum of 2 25 personnel,z including working' space for five NRC-
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_ personnel. -Status boards for display-of data:in_the TSC were well-
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s3 : designed,,and.an; adjoining document room contained ~an adequate I ~ - - Jsupply'of current records, procedures, Technical Specifications and various schematics and drawings. Numerous copies of the Emergency _
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- H- ~ Plan and Procedures were-available..
-TAlthough all radio communication with offsite-field. monitoring teams <
is carried out'through=the EOF, one of_the OSC portable UHF radios icould be brought to the TSC;and used for.this purpose.. In addition, -{
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a' closed circuit television camera has been installed in~the: Control
; I -RoonLto provide viewing of'the panels from the TSC.' This'is currently'in the preoperational-testing stage.
? Based!on'the above findings, this portion of the applicant's program
, "is acceptable;;however, the following items-should be' considered for
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improvement: , 9 ,
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.TSC'should be developed and attached to the front of HVAC System control panel.
3
. '! Revise Emessency Procedure EP-301-2, Section 5.5.1 to reflect
- current. practice.
,e ?4;1.1.3 -Operational Support Center (OSC)
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!The Operational Support. Center (OSC) is a separate area adjacent to
's' the Control' Room.(third floor) at the north end of the Turbine Deck. : A sketch of the OSC area is listed in EP-302-1, Enclosure 1.
~The alternate OSC is an assembly area adjacent to the machine shop on the first1 floor of'the Turbine Building. The staffing and function.of the primary OSC is adequate as described. In addition, the. alternate'OSC wil1~be staffed with maintenance and health s
- physics' personnel'whenever the'0SC is activated. .Both the primary
- and alternate OSC are equipped with dedicated telephone lines to the Control Room and TSC with several additional inplant lines.
JJ* JEmergency kits in-the area of'the OSC and alternate OSC are
- installed and stocked. "In addition, 15 Scott Air Pacs are provided j)g 9
for respiratory protection. Inventory lists are available for the contents of each cf these kits. These. kits contain battery powered h'. u
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.,, portable emergency lighting, but no fixed emergency lighting was.
available for the alternate OSC. -The applicant has made adequate provision for_. evacuation of the OSC in the event of high radiation slevels. Based on-the-above findings, this portion of the applicant's program is= acceptable; howeverpthe following item should be considered for improvement: The alternate .0SC should be equipped with: fixed permanent . emergency lighting. - L4.1.1'.4 Emeraency-Operations Facility.(EOF) The~ primary. Emergency. Operations Facility (EOF) is located in the
- Nuclear Operations ~ Center (NOC),'about 6000 feet southwest of the 4 Fermi;2 Plant within the owner-controlled boundary 6 Anfalternate
. EOF.is located 22 miles northwest of the' Fermi 2 Plant at the
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Wayne-Monroe Division Headquarters. .The EOF contained sufficient space to provide all assigned personnel a' minimum of 75 square L feet. 'There was space for=a large number of news media in the cafeteria of.the'NOC; but_this is not expected'to'be used once-the Joint Public Information Center (JPIC) is activated.-
- Communications in the EOF include general business phones'and dedicated telephone lines to the Monroe County Sheriff . Michigan State Police, and TSC as well as ENS and FTS lines. Also available lare radio communications equipment for dispatching and control of offsite. radiological ~ monitoring teams.
p_ ~ 10
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; Equipment for radiological monitoring and protection included low
. ; and high range survey equipment, portable air sampler, personnel
=
m. 54, dosimetry and chec) sources. However, decontamination supplies, respirators and protective clothing were not available. In
~ addition, the micro-R meter (Ludlam-125) has not been calibrated.
Inventory lists of equipment were available, but were not kept with the supplies. o
~, Documentation in the-EOF included current copies of the Emergency Plan and Procedures, site and local maps, State of Michigan and Monroe County Emergency Plans, FSAR, plant layout drawings, schematics, and very good status boards.
- If the primary EOF becomes uninhabitable or inaccessible, the
' alternate EOF will be activated. Communication equipment and space at the alternate EOF is adequate to take over the functions of the primary EOF. However, there.is no inventory of the supplies maintained for the alternate EOF.
Based on the above findings, this portion of the applicant's program is acceptable; however, the following items should be considered for improvement:
, :. . Develop'an inventory of supplies for the alternate EOF, include it in the procedures, and maintain a copy with the alternate EOF supplies.
.. . ~ Acquire for the EOF decontamination supplies, and protective n- ^ clothing.-
; ?4.1.1.5 Post-Accident Coolant Samplina and Analysis
~
' 4'.1.1. 6 . LPost-Accident Containment Air Samplina and Analysis The inspector examined the applicant's post-accident sampling system and procedures. The post-accident. samples'for liquid are taken from .
the primary coolant via the jet pump or from the Torus. ' Gas / air samples are drawn from the drywell or suppression pool (Torus).
-The system was-obtained from General Electric and is similar to systems at several other plants. It provides for remotely-controlled flushing, sampling, dilutica of-samples and~
Jpost-sampling internal flushing.; Construction is very near completion, but a few items remain such as Installation of the 80 gallon demineralized water supply tank and gas bottle station and providing a power supply to the remote panel ai and sampler station. Also, the shielding blocks are onsite but not p installed. . J Because the system is not operable (not turned over to the utility by construction), it was not possible to determine if representative pressurizedLand unpressurized samples could be obtained and analyzed within.three hours per NUREG-0737 guidelines, 11 L
7,- i v. The procedures.for the sampling were recently issued as noted by
-the inspectors. 'Therefore, a hands-on walkthrough of a small volume liquid effluent saapple was made with the cognizant Systems Engineer. During the-walkthrough, the inspector and the Engineer
- ~ noted several areas where the procedure needed correction or could
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< . be improved, i.e. , ' steps out of order or needing clarification.
Also, several switches on the remote operating panel were noted which
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could be more clearly labeled. The cognizant engineer made note of these-items for procedure and system review when the system is accepted.'
- The' inspectors were informed that in some cases, separate chemistry analysis' procedures were being developed for post-accident samples.
- These incorporate changes in ALARA principles, time requirements,
- and direction for sampling.
Based on the above findings, this portion of the applicant's program is an Open Item which must be completed prior to exceeding 5% power. (341/83-24-02 and 341/83-24-03) 4.1.1.7 Post-Accident Gas and Particulate Effluent Samplina and Analysis Inspectors reviewed the methods for processing and monitoring c . gaseous-and particulate effluent from the plant. Each path for normal discharge.is monitored before entering the stacks. Monitoring is-done by Special Particulate, Iodine, and Noble Gas
. detectors (SPING-3) on the Radwaste-Building stacks, Turbine
. Building stacks and standby Gas Treatment System stacks. A SPING-4 monitors the Reactor Building stack. These SPINGs are installed,
.but have not been' calibrated or placed in. operation.
Based on;the above findings, this portion of the applicant's program is an open item which must be completed prior to fuel load. (341/83-24-04).~
~ m '4.1.1.8 Post-Accident Liquid Effluent Samplina and Analysis
-l Inspectors reviewed the facilities and plans for final radioactive
- effluent control during a postulated accident. Because of the relative capacities of holding systems and the Torus volume in Af .
addition to the isolation of Secondary Containment, there should be no discharge from these' sections of the plant. Further, radweste
~
.has additional capacity for holding coolant. See sections 4.1.1.5
" ' .~ , and 4.1.1.6 for primary coolant post-accident sampling.
'Basedon_theaboveikndings,thisportionoftheapplicant'sprogram t 1 . is' acceptable..
0 1.1.9' Offaite Laboratory Facilities . O Inspectors reviewed the utility's access to and' arrangements for offsite laboratory facilities. The applicant has provided a backup
' laboratory at the Emergency Operations Facility'(EOF). This F laboratory is equipped with analytical equipment for radiological and non-radiological analyses.
I 12
- f. > .', ,L
3? . l.? i y This equipment includes a multiplexed, high resolution, samaa spectrometer with'two shielded intrinsic Germanium (Ge) detectors, a gas chromatograp), and basic equipment for analytical chemistry.
-The gamma spectrometer system calibration is not complete.
v The inspectors.found_that RERP. Plan, Section C-1, refers to analyzing post-accident samples under contract with an outside contractor. Also, the Michigan Department of Health, Division of Radiological Health has a mobile laboratory capable of analyzing
-environmental samples, which would be readily available in an emergency.-
Based on the'above findings; this portion of the applicant's program
}is an Open Item pending calibration of the analytical instruments in the EOF-laboratory. This must be completed prior to exceeding 5%
> power. L(341/83-24-05) 4.1.2 Protective Facilities
~
4.1.2.1 -Assembly / Reassembly Areas
'The onsite assembly areas were observed and examined by the
. inspector. Various assembly areas are assigned to various
- s. categories of personnel.g The areas and categories' assigned are as
'follows:
.; .06C/TSC/ EOF.. All personnel assigned to these' stations are part-of the Emergency Response Organization.
The Alternate 0SC. .I & C Technicians and General Maintenance
^
. Journeymen.-
. General' Training and Orientation Center'(GTOC). All onsite employees not otherwise assigned. -
.- NOC Cafeteria. All personnel within and in the vicinity of the -
Nuclear Operations Center.
- c. Visitor's Center.. All visitors..and their escorts.(excluding
. , those at NOC).
, g" Fermi 1 Turbine Floor. All personnel within the Fermi 1 eomplex. .
- All areas are considered adequate with respect to accommodation-
- sisc, ventilation, supplies, portable lighting and communications.
W Respiratory protective equipment'and protective clothing are provided in most of-these areas.- i All assembly areas are located as specified in the plan and procedures, except that the Fermi 1 area does not appear in the-current plan revision. However,'this area does. appear on a notice which has been distributed to site personnel, and the inspector was advised it will be reflected in the next plan revision. 13 a , e_-_
d' , n, ?e- 1
.y ,-
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- Three offsite assembly areas have been-designated in the event of a
- site evacuation. All-three areas are at Detroit Edison facilities.
" ^
The primary offsitg. area is the Newport Service Center, located 6
. miles:SW of Fermi 2. Secondary areas are at the Monroe Power Plant
- and.the Trenton Channel Power-Plant, located 7 miles NW and 12 miles NNE respectively from Fermi ~2. The separation of these alternate areas allows a selection of the optimum alternate assembly area
! upwind from Fermi 2..
There are' currently no radiological emergency team kits in position
- st any of the offsite assembly points. However, kits are made up "c
- end, staged onsite, to be positioned at a later date.
Based on'the:above findings,'this portion of the applicant's program is acceptable; however, the following item should be considered for improvement:- t
. _ Position.the staged radiological emergency team kits.at the three offsite assembly locations.
,4 71.2.2' _ Medical Treatment Facilities The inspectors reviewed the. applicant's Medical Treatment Facility A.: located in the Office Service Building. A registered nurse is on-site five. days per week, during day shift working hours.
4 Additional ~first-aid training equivalent to Red Cross-Multi-Media-has been provided to all Fire Brigade, Damage Control, and maintenance personnel,c First-sid kits are located in various areas Lof-the plant.such as in the Fire Brigade Ready Room outside the
~
LOSC. In addition, the registered nurse will bring a medical kit when summoned for medical ~ treatment.- Stretcher lockers are _ distributed throughout the plant. Decontamination of injured _ personnel can be performed in the Medical Decontamination Facility located at Column M-16 in the Radwaste Building. lWhen warranted, contamination survey instrumentation 'will be provided by health physics personnel when summoned by telephone during a medical - accident. Communications equipment is available. The Registered Nurse has' custody of a supply of KI pills for distribution during an 4 - l emergency. .
-Based on these findings, this portion'of the applicant's program in acceptable.
4.1.2.3. Decontamination Facilities , 1Bealth Physics procedures' 63.000.21 and 66.000.10 were reviewed by the inspectors for compliance to good health physics practices. ~In addition, the. inspectors examined the Medical Decontamination VFacility located at Column 16 in the Radwaste Building.. At this present time, the decontamination' facility is not couplete. The anticipated' completion date is estimated within two months. Decontamination supplies will be stored in the decontamination facility along with Health Physics Survey instrumentation.. y
~ 14 Wo
1 g - f:e
- a. }
)
T ) l (Contaminated individuals would be treated according to standard
- : operating' procedures as followed by radiation safety methods. These supplies include p9tassium permanganate, other chemical solvents,
, ,- . soap, and protective clothing. . Liquid radioactive wastes will be R. ~ automatically routed _to Radwaste tanks and solid wastes will be appropriately; packaged for offsite shipment.
. Based on the above fin' dings," this portion of_the. applicant's program
^
is an open item which must be. completed prior to fuel load.
"(341/83-24-06) . 4~.1.3 ~ Expanded Support Facilities.
The applicant.has made provision'for corporate, vendor, and consultant staff augmentation _in the TSC and the EOF. Once an Lemergency has~been; terminated and recovery initiated, adequate
~
facilities ~existiin the' EOF which'could be utilized, depending on
.the magnitude-and scope of the recovery. Adequate communications equipment exist in these facilities.
1Basedonthe:abovefkndings,thisportion.oftheapplicant'sprogram
~
Lis ace'eptable. N 411.'4 ( : News Center
- :The inspectors examined the applicant's news center and discussed
% _ the applicant's provision for dealing with the press in the event of -
- an emergency. The news center or Joint Public Information Center t(JPIC) will-be located'at the Monroe County Community College.
t
' Communications _ equipment includes:54 general. commercial telephone
- textensions (25.for media personnel) and 13 extensions from onsite 1 emergency response l facilities. An additional 500 telephones could.
be installed.within 48 to:120 hours.. -
- The'JPIC has facilities for State and local personnel as well as
' licensee personnel. Provisions have been'made for copying, graphics,
^ '
V Lvisual' mids, public address system, security, food and obtaining-additional spa :e if necessary. Currently ~there are provisions to
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-handle up'to 500 people. An inventory is maintained ~of all the (supplies stored at'the'JPIC. ,
79 iBased on the'above-findings,.this portion-of-the. applicant's program
.~is acceptable.1 .
4 4.21 1Eneraeacy Equipment - B :4;2.1" Assessment- ,, Ll4. 2.1.1 :KitsLand Survey' Instruments ,
~
;The-inspectors examined emergency survey kits and survey instruments
_ dedicated to, emergency use. .The-contents of the kits and the survey instruments included in-the kits. varied from location to location
^ < '
- depending'on the intended'use of the equipment.. Kits used by
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=e..
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ik ?. : ioffsite' monitoring: teams included a battery powered air sampler, silver zeolite cartridges, radiation survey instrumentation, i- : particulate l filters, 0-200 mR pocket dosimeters, dosimeter chargers, si m and thermoluminescent-dosimeters (TLDs). lji
~
-Personnel protection equipment'and portable radiological assessment equipment dedicated to emergency use were located in kits in the vicinity of the EOF, TSC, and OSC. These included Friskers, pancake
, nG-M probes with count rate meters and full sets of protective
; clothing.~ The applicant also maintains survey instrument kits at
* ~
- cSeaway Hospital and at the.offsite assembly, locations. Emergency
*' 1 environmental instrumentation has the capability of detecting radioiodine concentrations in air of IE-07 uCi/cc and particulate concentration of at least IE-09 uCi/cc.
m JThe inspector observed'that all kits were complete with the 4
, ; - exception of the hospital _ emergency kit as indicated in 1Section 6.1.3. .All kits should contain an exact inventory list of T'
contents, so that the contents may be rapidly assessed before Lemergency use in the field.. None of the emergency kits contain a
~ '
copy of the latest completed inventory list. In addition, while portable survey-instruments did have calibration stickers affixed, 4-
<other instruments such as area monitors failed to have expiration
~
- dates attached or were not appropriately calibrated.
~ Based ~on the.above findings,.this portion of the' applicant's program
/'L 'is acceptable; ~ however, the following items should be considered for -
% M : improvement:
~.
~ ~
.- ' Inventory. lists of contents should be placed in each emergency
' kit .' -
~
/y < uAll' equipment contained in the emergency supply kits should - have_ expiration' dates where appropriate and should be kept M. calibrated. p 4.2.1.2' Area and Process Radiation Monitors y'# '. <- Containment High' Range Radiation Monitors'(CHRRM),are installed and
~
operable from 10-10s R/hr. EALs for containment' monitors.have been-
, developed.-
[ e m" gius ; Health PhysicsJpersonnel= interviewed by the inspector indicated that 4 ;none of the process radiation monitors had been calibrated.as of the m
, ;date'of this' appraisal, e.g., CHRRM, Standby Gas Treatment System
@ .(SGTS)~ monitor, liquid radwaste monitor, etc. The AMS-III air ~
d@LW 4 monitors in the EOF and TScialso were not. calibrated as of the date , Mk ,*, - .ofLthis appraisal. .The applicant's' Health Physics and RERP representatives are aware of the necessity to assure the proper
; calibration of appropriate monitors prior to start up/fhel loading.
M~ ' ; l ' ' The_same applicant personnel reported the Air Radiation Monitor p L(ARM)"in the fuel handling' area has been calibrated.- m 7.y g, i 16 ho w
w The calibration of this instrumentation is an open item which must
- be completed prior to fuel load. (341/83-24-07)
'4.2.1.3 <Non-Radiation Process Monitors The inspectors reviewed the alarms associated with non-radioactive process; monitors. Typical alarms include seismic, chlorine, offgas
- hydrogen, and division I and II H2/02 very high check combustibility.
~
7 :The seismicisystem is-installed, calibrated and approximately 85% completed with pre-operational testing. Chlorine gas is used in the circulating water treatment.-
-Previously, plans included a rail car for chlorine storage but the
' current plan is' for a reduced amount (five-1 ton cylinders). This is documented ~in the Plant Safety. Evaluation Report NUREG-0798,
-Section 6.4.2. The inspectors observed that the alarm for the
- -Chlorine monitor on the control-heating and ventilation system is
. located.in the. Control Room. This alarm has a trip associated with
~
.it-that places'the Control Room area ventilation into a
-recirculation mode. Further, there is an abnormal operating procedure l(20.000.26, Chlorine Leak) which contains the operator sc actions for the situation of a chlorine release. Installation of the plant chlorine monitors has not been completed.
Hydrogen and Oxygen, and some associated off-gas system monitors for e, . Hydrogen and temperatures were also selected for' review. Inspectors
!were informed that the divisions I and'II H /02 2 Very Hi Check Combustibility Systems were 95% installed.. Also, the monitoring systems' associated with~off-gas-- H2 detector, recombiner outlet
* , temperature,;and_ charcoal unit temperature were-installed and in
- _ preoperational: testing.
' Based on the above findings, the installation of the
' .non-radiological process. monitors (hydrogen, oxygen, and chlorine)
- 'is an.openl item which must be completed prior to fuel load.
.~ .(341/83-24-14)
~'
'4'.2. 41 iMeteoroloaical Instrumentation The inspectors reviewed the meteorological measurements program described in the Emergency Plan and Procedures. The meteorological system provides the basic parameters (i.e., wind speed, wind direction and an estimate of atmospheric stability) necessary to
~
perform the. dose assessment function. All the meteorological instrumentation meets the guidance described in Regulatory Guides 1.23 and 1.97.- The system consists of
' redundant instrumentation for the basic parameters with separate cabling supplying the power to each redundant set of instruments.
- Access to.the meteorological information is via-computer readout in the Control Room, TSC,-EOF and is accessible to the NRC. These 17
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I x 3. *3. . - - 7 -
. readouts provide =15-minute and hourly average values of the
- meteorological parameters'. The meteorological parameters can be
-accessed through tyo computer systems with backup data.available 7
through other local Detroit F.dison meteorological stations, the a Davis Besse. meteorological system, Weather Service International
-(WSI), and,the National Weather Service in Ann Arbor, Michigan. ~
Strip chart output of the meteorological parameters will be
~
available at the base of the main meteorological tower. The applicantiis currently working on a lake-breeze study. When Lthis11s. completed, the information will be incorporated into the feeteorological modeling/ dose assessment program. This is required
,to: adequately describe site meteorological conditions out to ten miles from the site, and is addressed in Supplement 1 of NUREG-0737.
-A further review of the. dose assessment and meteorological monitoring program will be conducted as part of the emergency response facility
. appraisal program which will be conducted after completion of all related Supplement 1 items.
Presently the applicant has no program for maintenance, calibration, iand surveillance of the meteorological instrumentation system. A
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t .
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c program of this nature is necessary to ensure the reliability and
- validity of the meteorological data.
Based on the above findings, the implementation of a program for maintenance, calibration, and surveillance of the meteorological system is an open item which must be completed prior to exceeding 5% -
' power. ;(341/83-24-08)'
.4.2.2 ' Protective Equipment u .4.2.2.1' -Respiratory Protection iThe inspectors' reviewed the availability of respiratory protection
' devices. The respiratory equipment currently reserved for emergency use at the plant includes 24 SCBA. packs, 20 MSA pressure demand-
- . units and thirty MSA purifying air respirators. Approximately 1400
- additional' respiratory protection units.have been ordered and will be integrated into the respiratory protection program.
n SCBA units.are refilled'at the Fermi 1 refilling station. The
~
backup refill station'is located'st the Frenchtown Township fire
, station..
- y .
Based'on the'above findings,"this' portion of the applicant's program ois acceptableL
~.4.2.2.2- Protective'Clothina The availability 'and quantity of protective clothing was reviewed
.for onsite'use.- There are currently approximately 2,000 sets of
- protective clothing being stored near the I,aundry Services on the 18
[ J h, ' - yy W- t
..i
.second floor of the Radwaste Building. 8,000 additional sets have been ordered ~and will be stored offsite until demand warrants replacement.
. Protective clothing for offsite needs are being stored in drums that
'can be transported to any offsite assembly site as required.
Based'on the above findings, this portion of the applicant's program
'is acceptable.
~4.2.33 Emeraency Cosumnications Equipment e
M The inspectors conducted a review of the onsite and offsite
- available-communications. All of the equipment identified in the plan was in place and operational with the exception of the NRC's ENS system and the pl.2nt intercom system (HiCom). The ENS is
< installed and operational through to Detroit, but the les beyond
, , Detroit _is not yet available. The~HiCom system is available at the c -Fermi 2 site,.but has yet to be installed in the TSC and EOF.
Emergency connunications resources include normal and dedicated
. telephone systems, microwave system, UHF and VHF radio systems and a W plant intercom system. -Each of these systems is used on a daily basis and act as a backup to each other. Monthly, quarterly, and
' annual testing of communication' equipment was acceptable with the exception of-the monthly checks to the NRC Headquarters and Regional Offices from the Control. Room, TSC, and EOF per 10 CFR 50 Appendix E, Section IV.E.9.d. Both the Plan and Procedures require the communication check to be made quarterly rather than monthly. A 24 hour / day capability exists to notify NRC, State and local
" i ~ authorities of.an emergency situation.
.p .
'The primary notification system within'the plant Protected Area will be an audible signal from the emergency alarm system.. This system has a different alare signal for Control Room evacuation, site evacuation, plant area evacuation, fire, and tornado. In high noise -
Lareas,' strobe lighting will be available to indicate to personnel that the alarm is activated. I Based'on.the above findings, the following' action must be taken to'
' achieve an ' acceptable program: -
.' .The Emergency Plan and Procedures must be revised to reflect
, 10 CFR 50 Appendix E, Section IV.E.9.d requirements in that communication checks to the NRC Headquarters and Regional Office shall be" conducted monthly. This must be completed
(
., . prior to fuel load. (341/33-24-09) e #
4.2.41 ~ Dassae' Control / Corrective Action and Maintenance Equipment and Supplies-The applicant maintains routine maintenance equipment and supplies at the Fermi 2. site. An additional emergency hit of. damage control equipment.is maintained:st the alternate OSC. The maintenance and
" b s .
Im' _ .
I j; ' :,.',
^
m . . ( .-
, inventory of this kit is routinely conducted and is the
! responsibility of the Maintenance Engineer.
Based on the'above fin' dings,.this portion of the applicant's program
-is acceptable.
4.2.5- . Reserve Emeraency Supplies and Equipment
;The applicant maintains an inventory of supplies, including
- protective clothing, respiratory protection equipment, dosimeters, radiation ~ detection equipment, comununications equipment, first aid supplies, and environmental monitoring supplies. These supplies are found at.various locations in the Fermi 2 plant and emergency response facilities._ Adequate quantities of emergency reserve supplies are maintained at minimum levels.
Based on the above findings, this portion of the licensee's program
.is acceptable.
4 4.2.6 Transportation The applicant has access to a complete fleet of Detroit Edison ,. vehicles if necessary, including four-wheel drive. Members of the
, offsite monitoring teams have their own company vehicles that are radio dispatched. Security has its own fleet of vehicles and the
- Fermi 2 Plant Stores and Transportation Department has additional d
vehicles.
- The EOF Coordinator has the authority to obtain any vehicle in the Wayne / Monroe Division of Detroit Edison and the Emergency Officer has the authority to obtain any Detroit Edison vehicle. Ambulance service is available from ENTS Ambulance Service. Detroit Edison also has access to airplane and helicopter service, and a helicopter -
landing pad is available at the site. *
< Based on the above findings,.this portion of the applicant's program is acceptable.
5.0 - Emeraency Implementina Procedures
-5.1 General Content and Format The procedures for implementing.the applicant's emergency plan (EPIPs) were reviewed. 1The procedures were arranged in the same general format with the following headingst (1) purpose, (2) references,.(3) entry conditions, (4) general information.
f F
,#(5) immediate actions, and (6) follow-up actions. Each procedure had a signature / approval page and,' where appropriate, check-off
?
^
lists were attached. ~The procedure format was in accordance with Administrative Procedure 12.000.07, "Frocedure Preparation, Review, Approval, Change, Revision,' cancellation, Control, and Distribution." I
, 20 6
_ m y:.. . 2-.
,,. s.,S i j '3 - .
Each EPIP is arranged in a logical step-by-step sequential fashion. Reference is made to other implementing procedures as well as other plant procedures (q.g., health physics) necessary to complete the required' actions initiated by the subject procedure. In addition to
.a reference section, the references appear in the body of the s , . procedure at the point where implementation of the other procedure i> is to be performed.- Nowever, not all procedures specified the individual ^or organizaticial element responsible for performing the
, stasks covered by the proc:dare. In general,'the procedures were
- found to provide necessary and adequate supporting information while not being overly descriptive to the point where the user is hindered in;the utilization of the procedures.
Based on the above findings, this portion of the applicant's program is acceptable; however, the following item should be considered for improveseat:-
.- lSpecify the individual or organizational element responsible for performing the tasks covered in each emergency plan implementing procedure.
- 5.2 Emeraency. Alarm and Abnormal Occurrence Procedures is The inspectors reviewed the applicant's Emergency Operating
-Procedures (EOPs), Abnormal Operating Procedures (AOPs), and Alarm Response Procedures (ARPs) and discussed the relationship of these
' procedures.to the Emergency Plan Implementing Procedures (EPIPs) with the Operations Supervisor.
The E0Ps are used to mitigate the consequences of a plant emergency-condition which is symptomatic of particular failure events and is identified through specific plant parameters regardless of the - particular initiating event which caused the emergency condition. The E0Ps were developed in conjuction with the BWR Owners Group and have been reviewed by the NRC. There are presently eight E0Ps as follows: c EOF 29.000.01. I.evel/ Pressure Control EOF 29.000.02 Cooldown EOF 29.000.03 Primary Containment Control E0F 29.000.04 Contiagency for RPV Flooding 50P 29.000.05 Contingency for I.evel Restoration EOF 29.000.06 Contingency for RPV Pressure Reduction EOF 29.000.07 Secondary Containment Control 30P 29.000.04 -
' Reactivity Control
.Inforestion and directions in the use of the Fermi 2 E0Ps, which must be throughly understood by plant licensed operators, are
, provided in Administrative Procedure 21.000.13. " Emergency Operating Procedure Guidelines." Section 3.5 of AP 21.000.13 states that plant' evolutions encountered or performed during the execution of the 30Ps asy place the plant in an event classification of the Radiological Emergency Plan, and that it is the responsibility of the Nuclear Shift Supervisor (Ng8) to recognize and classify these
- 4 21
l<' q . m - - 4 Levents'and to 'nitiate i any EPIP as necessary. In addition, Step 7
.under General Cautions of AP 21.000.13 states that the operator using'the E0P will, assure that the NSS is informed of any change in the plant status and that existing plant conditions may require
~
emergency; event _ classification in accordance with EPIP-101,
" Classification of. Emergencies." The possibility of developing emergency action levels-(EALs) which are symptomatic based similar to the E0Ps as opposed to the event oriented EALs in EPIP-101 (which a- :are generic throughout the industry for BWRs) was discussed with various-representatives of the applicant.
, 'AOPs are event oriented procedures which provide operating steps to mitigate the consequences.of a specific component of system
. failure. ~They address identified plant transients which may be expected during plant operation but are not of the magnitude of a design basis accident._ There are currently 38 AOPs at Fermi 2,
, three of which, as an example, are as follows:
A0P 20.000.02- Abnormal Release of Radiosctivity AOP 20.000.07 . Fuel. Cladding Failure 7 AOP~20.000.11- Loss.of Secondary Containment lutegrity Each AOP, either 'under inmediate operator actions or subsequent-
- operator actions, contains a step which requires the operator using the procedure to notify the NSS of the event, actions taken, and that it may be_ required to classify the event in accordance with EP-101, " Classification of Emergencies."
ARPs are to be followed upon actuation of specific alarms and/or annunciators and may be_ safety-related or non-safety-related '
' depending on which system or component is affected. The' Fermi 2 ARPs, of which there are approximately 1370,~are currently being
! ' revised. The revised version, where applicable, will' include a '
, statement similar'to that for AOPs listed above which refer the user to EP-101.
Based on the above findings,-this' portion of the applicant's program is acceptable; however, the following item should be considered for improvements
. -The applicant is encouraged to work with other BWR owners to
, develop emergency _ action levels which^are symptomatic based-
< similar to Emergency Operating Procedures as opposed to event
' oriented emergency action levels which are contained in the~
; current emergency plan implementing procedures.
- 5.3 Implementina Instructions Emergency Plan Implementing Procedure (EPIP) EP-101, Rey. 0,
" Classification of Emergencies" dated June 20, 1983 is the basic procedure used to classify an emergency and initiate the activiation
~,
of all subsequent emergency actions. EP-101 has ten sets of entry conditions'esch'of which consists of a-list of emergency conditions 22
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a.- ac , f . t and emergency action levels (EALs) which lead to the classification
- of 'an event into one of the four standard emergency classes. The
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#- . procedure includes,a brightly colored tab for each of the entry
- conditions, and the information is presented in a systematic and concise. manner which greatly facilitates the use of the procedure, as evidenced during the walk-throughs in the Control Room. ;
Procedure EP-101 is written for.use by the Nuclear Shift Supervisor and subsequent-individuals who may serve as the Emergency Director. The. procedure clearly specifies the authority and responsibilities
;of the. Emergency Director, including the three functions which may
-not be delegated to other members of the emergency organization, '
inamely'energency clossification, notification of offsite authorities Lincluding _the' recommendation of protective actions when appropriate,
.and authorization for emergency response personnel to_ exceed 10 CFR Part 20~ radiation limits.
;TheiEALs'in EP-101 are generally event oriented and have been Jdeveloped'in accordance with the guidance in NUREG-0654, ,
. Appendix 1. Plant. operations personnel were actively involved in ,
'the development of the EALs.. For the most part, the EALs are based on specific, observable indicators available to the Nuclear Shift Supervisor.in the Control Room who is responsible for the initial c classification of an emergency. However, some of the EALs,
'primarily for the entry conditions of " Degraded Safety Systems" and
" Reactor Control System Failures," are general in nature. For example, " inability of RHR systems to maintain the' reactor in cold
' shutdown," " inability to pressurize the reactor," and " main condenser cooling becomes inoperable" are listed-as EALs. These
-should3be more specific by including the instrument readings or
. equipment status indicators which'are used to classify an emergency. In. addition, some of the EAL conditions as described in
'the " Indication" column of the Emergency Classification Tables of
~
e, LEP-101 and Table. D-1 of the RERP plan do not list specific values, _
'for example radiation levels for the containment monitor and high radiological effluent conditions. The EALs must be completed and +
approved by the NRC.
- 'EP-101 leads to the implementation of other, more specific-l procedures. There is a separate implementing procedure for each of Ethe-four emergency classes, i.e., EP-102, Unusual Event; EP-103, Alert; EP-104,' Site Area Emergency; and EP-105, General Emergency.
-These procedures provide the step-by-step guidance.for the actions
+ ,to be taken under the direction of the Emergency Director following
- the l initial classification of an emergency. These actions include activation of the onsite emergency organization and facilities, notification.of offsite' authorities,. initiation of accident assessment and' plant corrective measures, and, at the General Emergency class, prompt. development of protective actinn .
-recommendations for State and County authorities.
Based on the above findings, the following action must be taken to achieve an acceptable program: .
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y , j _ . 'EALs which are general in nature should be made more specific by including instrument readings or equipment status indicators which'are.used to classify,an emergency. For example, EALs involving.the high radiological effluent condition and O' . containment high range-radiation monitor must include specific radiation levels. ?This must be completed prior to initial 4
-criticality. (341/83-24-16)
'5.4; 'Implementina Procedures
- 5'4.1
. ' Notifications i The applicant's RERP Procedures 102-105 and 290-293 delineate the notification-procedures to be;used during emergency situations. For each emergency class the sequence of notifications and augmentations have been outlined.-
The' initiation of augmenting onsite personnel is at the discretion of the Emergency Director, who is initially the Nuclear Shift Supervisor. This is-implemented by contacting the On-Call Plant Supervisor who notifies the Plant Superintendent, Emergency Officer,
- Secondary Alarm Station, Media Relations, and the Detroit Division
' ' Dispatch and Report Center per RERP Procedure 291. This is-R - c- idescribed further in Section 2.2 of this report. The Detroit -
Division Dispatch and Report Center makes further notifications to
. plant personnel as dictated by the On-Call Plant Supervisor.
;Not'fications i to1offsite authorities (e.g...Michigsn State Police, Monroe' County Sheriff, Sandwich West Police Station, NRC) areimade las specified after the declaration of any emergency class. Initial
- notifications are made by the Control Room with subsequent '
' notifications made by the TSC 'or EOF. The. transfer of these *
- a. ' notification responsibilities and the time constraints under which' L <
notifications will be made is outlined in RERP Procedure 290. The
. procedures also outline the responsibilitics'and means to notify' additional agencies'for support such as ambulance, hospital,-and -
fire. However, Procedures 102-105'do not specify that State and local officials will be notified before the NRC1as required by 10 CFR 50.72. l Planned messages are used for. notifications,-with a telephone number given to the agency receiving the message'to contact the site if-
"necessary.E A formal call-back procedure is otherwise not used for
- +
' notifications to the State and County, since these are made on dedicated ~ringdown telephones.
l Based on the above findings, this portion of the applicant's program. is acceptable; however, the following item should be considered for improvement: .
. Revise RERP Procedures 102-105 to reflect the requirements of 10.CFR 50.'72,.that State'and local agencies will be notified prior to' notifying the NRC.
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, e g- - i 5.4.2 [ Assessment-Actions (The insepetor reviewed the facilities, equipment, and procedures to-
~
' -be used for accident assessment after plant operation. The primary system is the Emergency Response .Information System (ERIS), which is ,
' currently' undergoing functional. testing and has not been delivered Lto the' applicant. According to an applicant representative, ERIS is u . scheduled to be fully functional by September, 1984.
ERIS will consist of two redundant computers which will serve to 1 operate the Safety Parameter Display System (SPDS), Meteorology Assessment,'and Dose. Assessment modules. Terminals (11 are planned) will be in the Control Room, TSC,-and EOF. The Dose Assessment module of ERIS will' fully automate (including input of ARM and PRM readouts) the current manual and semi-automatic dose calculational . methods described in the: discussion of procedures which follows. EP-540 Rev.'0, " Manual Offsite Radiological Dose Assessment Calculational Procedure - Airborne Release," provides methods for determining doses.and dose rates based on containment high range radiation monitor. readings, standby gas treatment system effluent monitor readings, and unmonitored releases through building vent stacks. The procedure contains flow charts, monitoring point o icharts,' tables, figures, and record forms necessary for completion of the designated assessments and distribution of information.to State organizations. However, no hand held g calculators.were ' supplied'or.available in the EOF, TSC, or Control
~ "
Room for'use in implementing this procedure. ,
/ A dose. calculation and assessment system using the Apple II computer has been developed and placed in~ service on an interim basis until-
' the ERIS becomes' functional. Hardware and software necessary for '
the operation of the~ interim Apple 11 system are available and ~
. operable in the TSC, EOF, and the Control Room for dose assessment-e l activities. Applicant personnel stated that the software is based -
- on the same technical basis at the ERIS Dose Assessment software.
The' Apple II users manual,."RADOSE-A Microcomputer Based offsite.
- Dose Assessment Package," has been prepared..and provides a method *
' for dose assessment personnel to use in the determination of offsite
' whole body-gamma and thyroid dose and dose rates resulting from airborne releases. The software package allows user control over-m
. source terms and dose parameters and is designed to automatically model'the following accident scenarios: LOCA,' Fuel Handling a ; Accident, Reactor Building Release, Radwaste Building Release and
- Turbine Building Release, s
Although copies of appropriate procedures were available at the dose assessment workstations in the TSC, EOF, and Control Room,' the
' -inspectors noted that' copies of certain procedures were not the 11atest version.
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Mf' EP-545, " Protective Action Guidelines Recommendations" (Approved
- 8/18/83) provides guidelines for determining protective action for i , 'the general public,to be recommended to State and local authorities for both projected whole body gamma dose and projected thyroid dose.- The PAGs for.the ingestion pathway have been established. . Table 5.1 of Enclosure 1 to this procedure provides i Jguidance for-protective action decisions in two categories:
'(1). projected potential.'or actual integrated dose pathway and
- (2) core,; reactor coolant, containment status pathway for rapidly Lescalating scenarios.. Use of the table leads to recommended protective. actions and provides a listing of considerations to be r ~made before making a final decision.
~ Key aspects.of accident assessment, including related equipment and
- Edecisional aids, appear to have been addressed adequately by the applicant except for a provision to incorporate field-generated
- radiological data in the dose assessment computer program.
.Providing for the input'of such data would establish a back up
" ' capability' in'the event that all effluent monitoring capability were
; lost add permit a correlation with dose projection data.
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< s (The licensee's procedure for dose assessment assumes a source term
'of release whose' isotopic composition contains a nuclide mix. This
- nuclide six is that present at reactor shutdown and is assumed to
' include'.100%' noble gases and 20% of the iodines as released to
, primary containment. No short-lived isotopes:(less than 3 minutes)
- are included.and no credit is taken for holdup'in the reactor 3
building.' .
~~ a a 6b - The inspectors contacted the Chief of the Nuclear Facilities and 7
- Environmental Monitoring Section of the Radiological Health Division
/
3of. Michigan Department of Health, and discussed the procedures.used' ' for' dose. calculations and assessment by the licensee.. The Michigan Department of. Health representative reported.they.use the same
~
~
; procedures -and assumptions for dose calculations and assessments and
'.there'are no apparent differences.
~
* " Based on'the above 7 findings this, portion of the applicant's program q :R i M is acceptable; however, the following items'should ba considered '
[ j; _ ~for. improvement: EAn~ appropriate type and number.of hand-held calculators should
~
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.be provided to the individuals.wholimplement manual dose ,
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jfassessmentprocedures:(EP-540and-541). my
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;. [MakeaprovisionIfor~incorporatingfieldmonitoringdata:into 4 ose d projection calculations.
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[5.4.2.1. Offsite' Radiologic'al Surveys- ~ . c s iThe inspector reviewed EP210-1:and-EP210-2 and-interviewed cognizant f _x LRadiological Emergency team members in order to evaluate the
' effectiveness of- the emergency environmental. monitoring program.
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L Team' members will be notified to report to an assembly point
~-
(Trenton Channel Power Station, Monroe Power Plant or Newport
. , . Warehouse) to be briefed, collect appropriate instrumentation and be dispatched to an offsite sampling point. Sampling locations are
. predetermined by grid-locations. The team will then collect samples as: directed by.the Radiological Emergency Team Coordinator. Samples
-will be transported to the Fermi site for analysis by Field Survey ,
Couriers; dispatched from the Newport Warehouse. Communications with the. Team ~ Coordinator will be by portable car radios or through i- commercial ~' telephone lines.' Ea'ch member of the team will receive a Thermoluminescent Dosimeter
.(TLD). and a Direct Reading Pocket Dosimeter, 0-200 mR scale, before Lbeing. dispatched into the field.
Offsite sampling procedures are listed in Appendix F of NT/R205
, Appendix G'of NT/R205 provides guidelines for the operation of radiation detection instrumentation including' precautions and
~ limitations... Radiation Survey-Data Forms are found in Appendix B of
.NT/R205.
i The' team members appeared to be very well trained and conscientious in performingLtheir duties. m. Based upon the above' findings, this portion of the applicant's '
, iprogram is acceptable.
'5.4.'2.2'SE L; - :5.4.2.3. ~0nsite-(Inplant and Out-of-Plant) Radiological Survey's LInspectors' examined the-procedures for activation of the Radiological Emergency Teams (RET) in the Radiological ~ Emergency LPreparedness. Plan (RERP). Procedures exist for activation' .
'(EP-201-1), . Functions : (EP201-2), 'and for variances from Radiological 1, ! Practice and Procedures'during an' emergency-(EP201-3). 'The:
g, procedure for RERP' training was also reviewedo
<Thefinspectors conducted a walkthrough with a Health Physics
. Technician where performance'of a survey.was observed. ; Appropriate.-
documentation of location, time, instrument used and background were-observed... Required performance items were observed in alltcases. Calculations.were made in the field and then checked'at the Health Physics ~1aboratory. 'An inplant survey was performed and'an
;out-of-plant-survey was walked through.: Smear, radiation readings,
.and air. sample techniques were performed, observed, and discussed.
x , Documentation. techniques and. counting. techniques were-also observed. m , Many_of the. aspects of performance'of these surveys were discussed (bp,the inspe.ctors with both the Health Physics Supervisor-and the c ' <
- Technician to assess actions.and techniques in the emergency .
situation. . Emergency health physics equipment lockers were located, 2; 1 inspected:and found to be. satisfactory by.the inspector. Both the
. dispatching and performance of.the.RETs were considered in the
- walkthroughs. 5(Reference Section 7.2)
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~5.4.2.4: Primary Coolant' Sam'elina 5.4.2.5.. Primary Coolant Sample Analysis 5.4.2.6 -Containment Air Samplinz
~
5.4.2.7' Containment Air Sample Analysis-5.4.2.8 = Stack Effluent Samplina
~
-5.4.2.9' Stack Effluent Samplina Analysis
- 5.5.2.10 Liquid Effluent Samplina-15.4.2.11 Liquid Effluent Samplina Analysis
. Procedures'for the sampling and analysis of primary' coolant, containment air, stack' effluent and liquid effluent are under development and review. 'These procedures will be completed upon
~
~ , installation'of the appropriate equipment, These areas are open s :- ' items pending completion of these procedures and training on their use.
35.4.2.12hRa'diological Environmental Monitorina Program (REMP)
'The applicant's REMP.is provided by a vendor with local representa- .
tive providing routine' sample collection. Based on the extent'of the' emergency, theTapplicant plans to conduct their own. T y jenvironmental~ monitoring program in lieu of using the vendor. For
- theimost-part,'the-applicantJwill' conduct environmental surveillance-
~
-as required:during an emergency event. -Calibration of the.
2 laboratory equipment'needed in the EOF to perform this analysis has
~
n not been completed. Correlation-or sample analysis splits between-the'_ applicant and the' vendor have not.been conducted;'therefore
~
1there is'no assurance.that applicant and vendor' analytical = procedures _will yield: comparable ~results.
. , s 1 Specific provisions ~for. collecting and analyzing' environmental-
_ parameters during an emergency ~ event are addressed ~as specified in. , Section 5.4.2.1.- . _ / Based en the above findings', this portion of the applicant's program Jis acceptable; however,- the following. item should be considered for fiaprovement: .
. ! Document-that the vendor's environmental monitoring program and
;the applicant's emergency environmental monitoring program will
~ '
~ provide comparable.results'for_all-possible environmental media. 1 s ip- >
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.The following open item must be completed:
l r0 . ' Maintain provisions with an offsite vendor to expand the environmental monitoring program in the event of an emergency
~ '
-to collect and analyze milk, soil, water, vegetation and air samples. This'must be completed prior to exceeding 5% power.
(341/83-24-11)
- 5.4.3 , Protective Action-L5.4.3.1' . Radiation Protection During Emeraencies Specific procedures'in .the RERP Procedures relating to radiation
- -protection during emergencies include the following:
EP-201 Onsite Radiological Emergency Team: Activation EP-201-2 Onsite Radiological Emergency Team: Functions
.EP-201-3 -Variances From Routine Radiological Practice and Procedures During and Emergency EP-401 . Reentry EP-402 -Recovery
- These' procedures supplement or augment routine Health Physics
. , - procedures for normal operation. The utility's philosophy regarding
- Radiological Controls / protective actions during emergencies is that I whenever possible routine health physics. procedures will be ffollowed. Specific changes or variations to these procedures are
? listed in the above procedures.
Inspectors noted,nfor! example,nthat EP-201 discusses authorization
- for~ exceeding administrative and regulatory. limits. In EP-201-3 it states that in~ procedure 69.000.11 the Emergency Director can authorize levels above 10 CFR 20 limits. '
Variations 'in requirements for prewritten radiological work permits (:RWP) or: the changing of the treatment of barriers was also .
. discussed in'EP-201-3.- ,
Inspectors found the: variations section to be carefully written with emphasis on controlled. actions'and reasonableness. Inspectors also reveiwedsthe Health. Physics procedures and the procedures for training. These; procedures . supported the RERP actions. in various 9, levels;of emergencies--always under' control ~of the senior staff
,' , Radiological Protection-Advisor'and Radiation Protection Coordinator. -
$Ia walkthroughs with all levels of Health Physics participants.for-the Emergency ~ Plan,'the' inspectors noted a good knowledge of the procedures and with only few exceptions, sound application of the '
7dAE ' procedures-in a sensible manner. - Based'on theTabove findings, this. portion'of the-applicant's program 31s acceptable.
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15.4.3.2 Evacuation of Owner Controlled Areas l Evacuation'of-specified areas, buildings, and/or the site is
-announced and directed by the Emergency Director. An ALERT or ,
- higher declaration-is accompanied by the evacuation alarm and a l HI-COM announcement which directs evacuation of all site personnel
'(other than those with operations or Emergency Response assignments) ,
, 1to designated assembly areas.
-Upon declaration cf a Site Area Emergency or General Emergency, or
*1 at any other time the Emergency Director determines.that conditions
-warrant evacuation of non-essential personnel, he will direct sevacuation of appropriate assembly areas. 1
-In traversing the various established routes to designated assembly
& points, the inspector observed that no lines, signs, or arrows were found. indicating the routes. -Interrogation revealed that lines had
# previously existed inplant, yellow for area evacuation routes and
' red for plant evacuation routes, but that the lines had been painted
.~out during recent general. area painting. Relining is reported
. planned but.-not yet scheduled.
.' Assembly: areas are adequately' defined as to location and use, and
-, : .the locations'are consistent with the Emergency Plan.
- The' Hi-Com system is available for personnel direction during
. emergencies. However, it was reported there exist " dead spots" for both HI-COM audibility and radio reception within the plant. A
~
, project is underwayfto identify problem areas and upgrade the system.
- -TheAssembly,Iccountability,'andEvacuationProcedure,EP-530,makes-
- Eappropriate reference to the Accountability Procedure, EP205-30.
'EP-530 also1 appropriately addresses personnel: monitoring and
-decontamination, although it does this through use/ assignment of the
-Personnel Monitoring Teams'(PMT) rather than by reference.to a
. ~
- :- procedure. -
[ ..('
' , EP-530, -section :5.3.2, estiablishes a five' sL:p procedure to provide
- verification to the Emergency Director by the Security Shift 4 ,,' '. Lieutenant;that'all noni ssential e personnel have'been evacuated and the area' verified to;be clear of non-essential personnel.
~
... Base'd'on the above findings,-this portion of the applicant's program w '
is acceptable; ,_however the following items should be considered
;,R .foriimprovement: -
.- Clearly mark' assembly / evacuation routes with conspicuously i s
- posted arrows,. signs, floor markings (colored lines), and/or
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.other]eadily.visiblemeans..
7 :.- :Any " dead spots" for.HI-COM or radio reception within the plant
.should be-identified and the system, upgraded accordingly.
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t. Q. 15.4.3.3 Personnel Accountability
- The inspectors reviewed the.. status of the equipment and procedures
~
). -for personnel, accountability during an emergency. Because the 9 systems for badge reading and control are only at the checkout 2 phase, it is not possible to' complete evaluation of the process of J- ' accountability. Procedures were approved and issued for
. accountability (EP 205.30), but assessment was not possible without the system in operation. The inspector noted that the system is scheduled for completion and complete checkout before the scheduled
,2 -exercise. This area is considered an open item which must be
'i completed prior to fuel load. (341/83-24-12)
. +..
' '524.3.4._ Personnel' Monitoring and Decontamination
~'
IThe inspectors reviewed EP 202-2 which addres'ses the monitoring of
;all personnel during.a' Plant Area, Protected Area, or Site Area g? l Evacuation. EP 502 specifies the contamination release levels.
Appropriate documentation record forms are provided for the
, disposition of evacuees. These forms will be forwarded to Nuclear 4
Security'and Health Physics for followup assessment. Based on the above findings, this portion of the applicant's program ;
;( sis acceptable.
5.'4.3i5 10nsite First Aid / Rescue
.5 The inspec' tors reviewed'EP204-2 and Health Physics Procedure c 69.000.10 which covers Damage Control and Rescue. Team Functions and
. Radiological /Hedical Emergencies. In addition, 61.000.05 and l 69.000.15 were reviewed.with respect to radiation exposure, fM . contamination and airborne' limits. These procedures describe the
' methods for receiving, recovering, and handling injured persons who
;may.also be contaminated.' Radiation protection guidance is also included.
!Basedonthe'above: findings,'thisportionoftheapplicant'sprogram- !
sis acceptable.-
-5.4 : Security Durina Emergencies-
- The inspectors reviewed the procedures related to security force
~ actions during. emergencies. These procedures,-EP205-1 through
'EP205-5; control the' actions of.the security force when the-RERP Plan
. x L is '~ activated. Procedure EP205-30 controls accountability. These
- procedures include-the actions.of the security force for situations during' activation of the RERP and include. contingency plans for
_ .-variations in the situation. Based on'the above. findings, this portion of'the applic' ant's program
~'
- "is.acheptable.
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4 k 5.'4.5 L Repair / Corrective Action Emergency' Procedures 203 and 204 provide for the activation and function of:the Fire Brigade'and the Damage Control and Rescue
. teams. Upon activation of the RERP Plan, assigned personnel for
+-these' teams will. assemble at the OSC or alternate OSC. Before teams are sent out, they are briefed on the status of the emergency,
- : radiological: conditions, exp s ure limits, stay times, required
-protective and emergency equipment, and personnel hazards such as fire,; smoke,fsteam or wreakage. All fire, damage control and rescue team efforts are coordinated with on-site radiological emergency personnel and. security personnel.
Based on the above findings, this portion of the applicant's program is acceptable, f5'.4.6' Recovery-
' 'Section M of.the Emergency Plan and Chapters Ill, 401, and 402 of
- the Emergency Procedures' describe the recovery organization and s Lthe criteria and procedures for re-entry and recovery operations. A
~
- complete recovery organization has been outlined in the procedures. >
' < The responsibility for declaring that the recovery phase may be ,
i entered rests with the Emergency 0fficer. Once~in the recovery
' phase,1the Emergency Officer becomes the. Recovery Manager and=
reports.to the Recovery Organization. .The Recovery Organization is responsible for developing and coordinating the recovery efforts and
. reports to the. Nuclear Safety Review Group. The Recovery Manager- !
- -has the' responsibility to notify offsite authorities in a timely. >
1
~ manner on the status of plantLeonditions.' He must'also ensure that ~
- plant. radiation levels are.at acceptable levels and. plant systems are -
' stable before allowing re-entry / recovery to commence.
' Based on the.above findings,Lthis portion of the applicant's program ,
~.is7 acceptable.
j 5.4.7 - Public Information Inspectors reviewed the procedures for all-aspects of public information control, checked ^the facilities and equipment,'and v <
. conducted walkthroughs with personnel involved in dissemination of
-information to the public and the media.
Section A.5 of the RERP Plan and the 600 series.of emergency
- ; procedures describe the' interface with.the public and the news media.
' ' " Procedures were found to beJcomprehensive. Inspectors: reviewed this control system 'in scenarios and as it was used in the FERMEX 82 c
. exercise. -The licensee demonstrated'a h}}