ML20076J358
| ML20076J358 | |
| Person / Time | |
|---|---|
| Site: | Three Mile Island  |
| Issue date: | 07/18/1983 |
| From: | Stange S GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20076J351 | List: |
| References | |
| 1004.2-01, 1004.2-1, NUDOCS 8309060625 | |
| Download: ML20076J358 (37) | |
Text
r 1004.2 Revision 9 07/18/83 IMPORTANT TO SAFETY NON-ENVIRONMENTAL IMPACT RELATED g4 THREE MILE ISLAND NUCLEAR STATION UNIT NO. 1 EMERGENCY PLAN IMPLEMENTING PROCEDURE 1004.2 ALERT Table of Effective Pages Page Revision Page Revision Page Revision ge Revision 1.0 9
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Signatfre Date
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Signature Date Document ID: 0024W 6
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1004.2 Revision 9 THREE MILE ISLAND NUCLEAR STATION UNIT NO.1 EMERGENCY PLAN IMPLEMENTING PROCEDURE 1004.2 ALERT
- 1. 0 PURPOSE The p'urpose of this procedure is to define the conditions that shall Le reganied as an Alert for Three Mile Island Nuclear Station (Unit I) and to:
a.
Ensure necessary actions are taken to protect th and safety of the public.
b.
Ensure necessary actions are taken to not
. uclear management and offsite eme response organiz c.
Mobilize the a fate portions o M ergency response organi-zation to it e appropriate e
actions.
The Emerge rh or is responsi e
mplementing this procedure.
x NOTE:
The Emerge r
or is vested i certain auth.
ority an res ibility that ma e delegated to a s diqat.
Included a o '{chtion cf an eme A.
Cl if ent.
B./ ayo Ap 9 and directing i ip notifications site agencies.
( roving and directin TT mation releases to
-."\\
media.
fpproving and, iflpos i le, personally conveying g
appropriate Protectiv Action Recomendations to :
the Bureau of Radi'atf'on Protection.
Directing onsite evacuation at the Alert or lower level errergency classification based on potential hazard to non. essential personnel.
F.
Authorizing emergency workers to exceed 10 CFR 20 :
Radiation Exposure Limits.
G.
Approving and directing deviation from estab-lished operating procedures, emergency operating :
procedures, nomal equipment operating limits or :
technical specifications during attcmpts to control the emergency.
(Note:
It is imperative :
that the Emergency Director consult to the fullest extent practicable with the Parsippany Technical Functions Center in arriving at a decision to deviate from prescribed procedures).
Q 1.0
1004.2 Revision 9 When the designated Emergency Support Director (ESD) arrives at the site and declares himself to be ready to assume that role, he will assuine overall responsibility for management of the response to the accident and recovery 39erctions. With activation of the ESD function, the ESD specifically will assume decision authority for Items C and D.
- However, decision authority for Items, A, B, E, F and G will be re hbythe Emergency Director (ED). Decisions on all of the li ns nomally will result from close and continuous consultatic the ESD and the ED and it is the res onsibility of the ED Se the ESD is provided with the ne nfomation to arri timely and appropriate dect _
the special cas ent classification, the ESD shall retai yrerogative to ov e the ED if, in the judgment of the ESD, ert ty or other co ions exist to the extent vel of emergeMy than that warranting cl ification of er7 classified by the ED.
Q 2.0 ATTACHMENTS 2.1 AttachmentI.[
rt Notifications AttachmentN,\\ergency Status a lib 2.2
^
2.3 Attachme Checklist for Notificetion of Significant Events Made In Accordance with 10 CFR 50.72.
i 2.0
1004.2 Revision 9 3.0 ' EMERGENCY ACTION LEVELS 3.1 Radiological Controls and Containment Integrity Initiating Condition Indication
~
3.1.1. Radiological effluent activity As indicated by any of the exceed the Environmental technical following validated by sample specification instantaneous limits. and analysis:
a.
RM-A8 (gas - 2.0 x 104 cpm (Hig but <
1.0 x 10 c b.
RM-A9 4.5 x 104 cpm larm) but <3.0 x
c.
.0 x 106 cpm.*
d.
M-iodine) increase >
x 102 cpn/ min but < -
x 10 cpm / min.*
M-A9 (igdine) increase >
.5 x 103 cpm / min but < -
1 x 104 cpm / min.*
Offsite Radiological Monitoring Team reports >
10 mR/hr (gamma) but <50-mR/hr t any offsite locat o.
g.
Off adiological nitor Team reports ivalent I-131 e
gs at any offsite 1 a ion of >50 mR/hr
.2 x 10-8uCi/cc) to N
'250 mR/hr (<1.6 x 10-7
}
uCi/cc).
RM-L7 >1.0 x 103 cpm (high alarm).
1.
RM-G8 > 6.0 x 103 mR/hr.
l 3.1.2 Radiation levels or radioactive As indicated by either:
contamination which indicate a a.
Valid, unanticipated high severe degradation in the control alarms on any two area of radioactive materials, and/or process radiation monitors (RMA, RML or RMG l
monitors) at the same time.
l These indications may be determined via instrumentation that will be installed or expanded as required by NUREG 0578 prior to restart.
l 3.0
1004.2 Revision 9 Initiating Condition Indication b.
Receipt of a validated report of airborne or waterborne contaminants as determined by sample and analysis or general radiation readings as determined by periodic survey to h ve increased by a facto 1000 above normal.
3.1. 3 Fuel damage accident with release An accid u
while of radioactivity to the contain-handling en fuel during ment or fuel building.
refue 11e moving obj t r the spent fuel p
whic causes any one of owing:
A alid High alarm on Q
M-A2.
O A valid High alarm on RM-A4.
/
c.
A valid High alarm on RM-A8.
d.
A valid High alarm on RM-Al e.
Av High alarm on RM-f.
ali igh alarm on v W d increase by a a tor of 100 of atmos-t heric activity as 0
analysis.
A determined by sample and 3.1.4 Reactor lant pump failure at As indicated by both of the power leadfng to fuel damage.
following:
a.
Receipt of a valid RCP l
Motor Overload alarm and I
decreasing flow in the i
affected loop, and b.
Reactor Coolant specific activity as determined by sample and analysis is
>50 uCi/ml but <3850 FCf/ml.
(RML1 Low >6 x 104 CPM but
<1 x 106 CFM and/or RML1 High >l x 103 CPM but >2 x l
10b CFM).
1 4.0
1004.2 Revision 9 Initiating Condition Indication 3.1.5 Reactor Building pressure Reactor trip and ECCS 1 0 psig, but <30 psig.
initiated due to high Reactor 4
Building pressure.
3.1.6 Reactor coolant total activity As indicated by either:
>3850 uCi/ml but <18,300 uCi/mi a.
Reactor coolant activity and/or Dose Equivalent Iodine-131 as determined by sample
>300 uCi/ml but <1430 pCf/ml and analysis.
Tndicating fuel cladding failure.
b.
RM-L1 Low fScageHigh) c.
RM-L1 Hi 10 cpm but <1 x 1 m.
3.1.7 Secondary system activity As indi ed - sample and 1 0 uCi/ml (I-131 equivalent).
analy s 1
3.2 Security 3.2.1 Security of hty (Protected Shif pervisor's judgement Area) is threa d by unauthorized %se on information from the entry of t6 t
Owner Controlled \\lf Security Sergeant.
Area).
- 3. 3 Gene g la Status 3.3.1 Other nt conditions Whenever ant conditions may involve an actua(o$
progress or have occur warrant i, as judged by the tial Shift sor/ Emergency substantial degrad ogo e
Dire tor.
level of safety o theglant.
NOT n xercising the gement as to the need for declaring an Alert, uncertainty
\\
concerning safety D
status of the plant,
(
the length of time the uncertainty exists, the prospects for early resolution of ambiguities, and the potential for substan-tial degradation of the level of safety of the plant should be considered; i.e.,
uncertainty as to the existence of substan-tial degradation of the level of safety of the plant extending beyond a reasonable time period is a sufficient basis for l
declaring an Alert.
l 5.0 l
1 004.2 Revision 9 Initiating Condition Indication 3.4 Pressure, Temperature and Inventory Control 3.4.1 Primary coolant leak rate of As indicated by increased 2 greater than 50 gpm.
makeup flow in excess of letdown flow by 50 gpm or makeup tank level decreasing at approximately 2 inches per minute or grea 3.4.2 Primary to Secondary leakage:
As indicated a.
Total primary to secondary a.
Yalid rm on RM-A5 leak rate >50 gpm.
High n conjunction wi h tank level d
f approximately s/ minute or ter.
b.
Total pri condary b
rate determined by leak rate m and <50 gpm N da ly leak rate test or AND lo o
site power.
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keup tank level decrease up to 2 inches / minutes with previous indication of tube leakage (RM-A5 Low Range n High Alarm) in conju fon with an ind failure of o fsite er.
c.
Total primary p sec,ndary leak c.
r e determined by rate >l gpm a M gpm AND a
eak rate test or a steam li r
e p tank level ease up to 2
(
ches/ minute with a A
rapid unanticipated decrease in steam pressure or activation of the Steam Line Rupture Detection System (SLCDS) or visual indication of a steam line break.
d.
Total primary to secondary leak d.
Leak rate determined by rate >l gpm and <50 gpm AND daily leak rate test or a loss of condensor, makeup tank level decrease up to 2 inches / minute with previous indication
- NOTE: 50 GPM = 1.67"/ min.
of tube leakage (RM-A5 on the makeup tank Low Range in High Alarm) because this is diff_:
in conjunction with con-cult to see the 2"/ :
densor vacuum <23 inches min. value is used.
Hg or less than 2 circu-lating water pumps oper_
ating.
6.0
~
1004.2 Revision 9 Initiating Condition Indication 3.4.3 Reactor Coolant System hot leg As read on Reactor Coolant temperature is y_620*F in either Outlet Temperature indication.
loop.
3.4.4 Non-isolable steam leak that As indicated by a Steam Line results in a rapid depressuri-Rupture System actuation zation of the steam system.
(<600 psig) on the affected 0TSG.
3.5 Electrical Power 3.5.1 Loss of all offsite power coin-As indic reactor cident with a loss of both Diesel trip ca loss of power Generators for less than 15 and t rms on both minutes.
Di tors neither of en izes the ID or IE ses.
3.5.2 Loss of al s
DC power for attery Voltmeters read less tha S
u es.
o and there is no light or ntrol power available.
//
3.6 Instru ntation and Actuati s
s 3.6.1 Most 811 annunciator As judged y the Shift Super-which may involve an att visor.
potential substanti 1 de a-s tion of the level a ety of the plant.
3.6.2 Failure of the ctor protection r ctor trip setpoint system to fnitiat' e and complete fqg exceeded with no rod n mit lights.
a trip wMrequWed.
3.6.3 Complet of any function s indicated by a total loss needed' ant cold shutdown.
of any of the following:
a.
Source and intemediate range nuclear instrument-ation.
b.
A loss of forced reactor coolant system flow (include Decay Heat I
Removal Pumps, Reactor Coolant Pumps, etc. )
coincident with total i
loss of ability to feed I
l OTSG's.
7.0
1004.2 Revision 9 Initiating Condition Indication 3.7 Natural or Man-Made Phenomena 3.7.1 Severe natural phenomenon being As indicated by any one of the.
. experienced.
following:
a.
Valid alarm on PRF 1-3,
" Operating Basis Earth-quake".
b.
Actual river stage >302 feet but <3 eet at the River Wa r t e Struc-ture.
c.
Proj r stage
<271 e
the River 7
e Structure.
d.
y nado striking cil y,
e, icane winds >75 mph N as indicated on the Wind
\\t?
eed Recorder.
3.7.2 Other hazar(s,sying experienced A indicated by any one of N_-
the following:
s a.
Aircraft crash or other missil impact within the prote d area or onto any nent plant struc b.
losion damage to a
anent plant r
ure.
He.ase of toxic or f
lammable gasses into the Ah lant which, in the
/
judgement of the Shift Supervisor, affects the safe operation of the plant.
d.
Turbine failure resulting in casing penetration.
e.
Any fire in a permanent plant structure which requires offsite firefighting capabilities.
3.7.3 Any fire jeopardizing the opera-As judged by the Shift Super-bility of any safety system, visor.
3.7.4 Evacuation of control room anti-Shif t Supervisor's judgement.
cipated or required with control of shutdown systems established from local stations within 15 minutes.
8.0 m a A r
~-m.
---.w--.
1004.2 Revision 9 Initiating Condition Indication
- 3. 8 Reactivity Control 3.8.1 More than one control rod Stuck-As indicated by a loss of the,
- Out, Stuck-In or Dropped requiring ability to meet any of the shutdown by Technical Specifica-conditions of Technical Spec-tions.
ification Limiting Condition for Operation 3.5.2.2 for more than one control rod.
3.8.2 Control Rod Ejection.
As indicated a tor Trip due t tron flux in coinci h loss of coolant ions.
4.0 EMERGENCY ACTIONS Initials 4.1 Upon recogn ti at any of the a ac ion levels have been reached ex ded, the Shift er or/ Duty Section Supe tenh t assume the d the Emergency Director.
(The event Mbuld be assesse de ared within 1 minutes of its occurrence.)
4.2 AnnouncetoControboom ersonnel that b />
has assumed the dut h Em rgency Direc rgency Director shallperi[c (approx, every (F lt with the lead personne Wch area involved hd/ emergency, and discuss:
a.
Stat f each area b.
Immediate actions to be taken by each lead person c.
Problem areas d.
Recomendations on course of action.
- 9. 0
1004.2 Revision 9 4.3 Announce, or have announced, the following message over the public address system (merged):
NOTE:
Turn on Whelen siren switch.
4
" ATTENTION ALL PERSONNEL; ATTENTION ALL PERSONNEL: AN ALERT HAS BEEN DECLARED IN UNIT 1.
ALL E MBERS OF THE ONSITE NCY ORGANIZATION REPORT TO YOUR STATIONS. ALL OTHE L AWAIT FURTHER INSTRUCTIONS." (If emergency is rad a ented add:
"There will be No Smoking, Drinking, or ng til further notice.") (Giv f description of the ent and repeat the announcemen 9
4.4 If emergenc adiation-orient ir et that the Radiation M
Emergen Alarm be sounded.
NOTE:
Turn off Whe iren switch afte a
has been sounded.
4.5 Assign a Comun o
make notifica o ersons and/or agencies p t g ent I, Section 4.6 Assign a,C ations Assistan rect him to perform all applicabi eps of 1004.8.
4.7 Contact the Duty Section Superintendent and discuss:
a.
Plant status b.
Which members of the Duty Section are required to augment the Onsite/0ffsite Emergency Organization.
4.6 Depending on the emergency action level which was reached or exceeded, ensure that the appropriate Emergency Operating Procedures have been implemented.
10.0
1004.2 Revision 9
'4.9 If local services (fire, ambulance, police) are required, direct the Communicator to notify Dauphin County Emergency Operations Center and request the appropriate assistance. Notify Security (N/S Gate) to begin preparations to expedite entry of responding emergency personnel (Police / Fire / Ambulance). Security should be advised to implement procedure 1004.19 Emergency Sec
/ Dosimetry Badge Issuance.
NOTE:
If the Emergency Response pers required to respond outside the protect r
ffected by a rad tive plume the Eme Di ctor or his Q
ill direct the i of TLD's from the d
N t o uth gate.
4.10 If th e involves radio o a problems, direct the Radio cal Assessment Coo n
to implement Radiological Contro uring Emerge
- 04. 9).
4.11 If changes in onsity o ite radiation leve e expected, direct the Radio.1 a
sessment Coor o:
a.
Di spatch ~of ite and/or onsite diati monitoring teams in accord wi th EPIP's 100.
b.
Im^
nsite Offsite Do Jmjections procedure (1004.7).
4.12 If personn / vehicles are, or are suspected to be contaminated, have the RAC initiate the Personnel / Vehicle Monitoring and Decontamination procedure (1004.20).
4.13 Activate the Technical Support Center, procedure (1004.28), and the Operations Support Center, procedure (1004.29).
4.14 If additional resources or notifications are required, refer to Additional Assistance and Notifications procedure (1004.6).
11.0
--...w
r 1004.2 Revision 9 4.15 Assign an individual to complete Attachment II,Section I and give it to the Radiological Assessment Coordinator to transmit to the
. Bureau of Radiation Protection.
4.16 [ Direct the Radiological Assessment Coordinator to complete Attachment II,Section II to transmit to the Bureau of Radia-tion Protection if a radioactive release has occurred or urring.
4.17 Stop all liouid and gaseous discharges that are ss until an assessmert of their impact is performed a d s ic approval is given to continue the release by the Emer c
rector.
4.18 Verify that c.
D ons and documentati re maintained per procedure C ui ions and Recordk pf
/
9 (1004.5).
4.19 If app ca rect the Operat on Cobrdinator to dispatch Emerge Repair / Operations p s 1 to investigate the identified problem \\ (s) in acco area th Emergency Re r/ Operations procedure 1004.21.
4.20 After 30 minutes tial contact wi confirm that BRP verification h n made. If no ve f n, instruct the communicat ceed to Attach ection 1.2 (d).
4.21 Instruct ~
ological Assessm
_$oordinatortoprovideongoing dose estima es for actual releases to the Bureau of Radiation Protection.
4.22 Evaluate dose projections and estimates and if necessary, recommend protective actions to the BRP consistent with the guidelines in l
Attachment I,Section IV.
l l
l t
12.0
1004.2 Revision 9 4.23 If personnel are injured or ill and are in a radiologically controlled area or are potentially contaminated, or if person (s) have received radiation exposure greater than 25 REM; direct the RAC to implement Emergency Plan Implementing Procedure 1004.16, Contaminated Injuries / Radiation Over-exposure.
131 4.24 If person (s) have been exposed to 1 sufficient to ea thyroid dose of greater than or equal to 10 RAD he RAC to implement the Thyroid Blocking Procedure Emerg an Implementing Procedure 1004.35.
4.25 Based upon asse f plant conditio s, her close out the Alert, esca t higher class of eme gency or down-grade to a lower cla V
a.
covery Phase criter' been met (see Recovery Proh' dure 1004.24),
g term recovery erations are not necessary, clos cut Alert by perform 1 t e notifications in Attachment ion III.
b.
If Recover, ase criteria have t ee met, but Alert emergeah tion levels are 10 e being exceeded, de-e\\ketoanUnusualE notify-ing BRP on the Radi feal Line and perform the remaining notifications in accordance with the Unusual Event procedure (1004.1).
c.
If emergency action levels exceed those for an Alert, escalate to a higher class, notify BRP on the Radiological Line and l
make the remaining notifica-tions in accordance with the appropriate emergency procedure as specified in Step 5.1.
l j.
1 l
13.0 l
l
a 1004.2 Revision 9 4.26 If necessary, due to potential contamination of normally non-contaminated sumps and/or tanks, or the need to closely monitor liquid releases, initiate procedure (1004.14),
. Monitoring / Controlling Liquid Discharges.
5.0 FINAL CONDITIONS -
5.1 A higher class of emergency has been declared by th ency Director after meeting or exceeding an emergenc level of one of the higher classes and one of the foi o 1 ce-dure; is being implemented, a.
Site Emer 04.3) b.
Gener cy (1004.4)
D 5.2 A lowe cl emergency hus b en ec ared by the Emergency Direct nd Unusual Event pr e (1004.01) is being implemented.
5.3 The Alert has been clos nce no recovery erations are required.
V 5.4 The Alert can b
-to a recovery plementing the procedureRecover[ Operations (1004.2 b.5 At the clou e Emergency, ens at all logs, check-lists, procedure ther documentatio eherated in the Control Room associate th the event are gathered and sent to the Emergency Preparedness Department for review and filing.
Date Signature of Person Responsible for Implementing Procedure l
14.0
1.
1004.2 Revision 9 ATTACHMENT I Section I Initial Contact The Comunicator shall notify the following agencies and personnel and update the Attachment I,Section II checklist for each notification.
Initial 1.
Dauphin County Emergency Operations Center (If this is a reclassification notification, f t
vise BRP via Radiological line or 9-787-3720 then unaff' ontrol Room) go to Item 3.
a.
Teleph e.
11 or 9-236-7976 D 1.
n ontact, activat p n County radio system, b.
GE:
Th is A
at the Thre ile Island (name/F
)
Nuclear Stati I calling. We h lared an Alert (time)V (Based-u mergency Direc.
ment, deliver one of the I
foil statements):
1.
W have not had a radioactive release OR 2.
We have had a radioactive release, but do not expect this situation to result in detectable changes in offsite radiation levels, OR 15.0
e 1004.2 Revision 9 ATTACHMENT I Section I Initial Contact Initial 3.
We have had a radioactive release, but do not know if there will be a detectable change in off i diation levels. We will be keeping the Bure fation Protection informed of the resul avestigation, OR 4.
We radioactive releas nd expect to be able changes in offs f ation levels, but they pected to be le a
he levels calling for a Site Emergency. W be keeping the Bureau of Radia-tion Protecti ed.
c.
Give a short n techMal descriptio of t emergency and the extent dioactive rel e affected populatio d area.
\\
n L\\
2.
Pennsylva Emergency Management Agency (PEMA)
(If this is a reclassification notification, go to Item 3, Un-affected Control Room.)
\\
l 16.0
1004.2 Revision 9 ATTACHMENT I Section I Initial Contact Initial a.
Telephone: PEMA Dedicated Line (Use only during NORMAL work hours 0800-1600 hrs. Monday-Friday) or 9 783-81 se when the dedicated line is out of service or af 1 work hours. A diverter forwards this after no 1
.rk hours call to the PEMA Duty Officer).
NbTh$
If n edocontac hdtostep2 pr
.................-- -y.~3........--.....--.......
b.
MESS T.
is Three Mile Islan N ar Station Unit 1 calling. We have an emergency.
e the Operations ty Officer.
(When Duty Offi r an s:)
This is 3
at ile Island
/ nameLF1%1e)
Nucle t
Unit 1 callin ave declared an Alert j
at N&
hours.
(M)
We reqYest you contact Bureau of Radiation Protection. Bureau of Radiation Protection callback should be made on the Radio.
l logical Line or 948-8069, 948-8071 or 944-0839. (Based upon i
Emergency Director judgment, deliver one of the following statements):
l 1.
We have not had a radioactive release, OR 1
l 17.0 l
l l
1004.2 Revision 9 ATTACHMENT I Section I Initial Contact 2.
We have had a radioactive release, but do not expect this situation to result in detectable changes in offsite radiation levels, OR 3.
We have had a radioactive release, t knov if there will be detectable chan i
site radiation leve ill be keepin the B au of Radiation P
t informed of the 1 s of our investigation, 4,
We have had a radioa release and expect to be able to detect cha fsite radiatio evels but they will be le(than e levels call ng fo Site Emer-gency be keeping th r
f Radiation Prot n informed.
c.
Give r-s non-technical ion of the emergency, and
.,.,,...... -.....r....
l 18.0
1004.2 Revision 9 ATTACHMENT I Section I Initial Contact Initial d.
If PEMA is unable to be contacted, contact Dauphin County; advise them that PEMA cannot be contacted and them to notify PEMA, BRP, and Lancaster, York, Leb Cumberland counties.
e.
Message verification:
Expect Bur o
adiological Protecti (BRP) contact after PEMA n(
"c on. If no BRP c f tion is received within 30, min notify PEMA of e ytuation. If unable to d
auphin County and notify them 4et PEMA (line bus )
that BRP has not v nitial contact.
equest Dauphin County to conta{PE nd/or BRP.
3.
Unaffected Control 1.,eg.eee..eee,,ee.e
, t.
Cont,0,.o m eot <,n..
b.
Ne age: Give a brief s 1 tion of plant status to f
Supervisor.
l l
19.0
1004.2 Revision 9 ATTACHMENT I Section I Initial Contact Initial 4.
Institute of Nuclear Power Operations (Do not notify if this is a reclassificati tifica-tion.)
a.
Telephone:
1-404-953-0904 or the TMI Site Operator for assistance b.
T i
Three Mile Island (name/ tit ) g
/ RtscMar Station Uni ing. We have declared an Alert at u
(Give a brief description of (tim the emerggy.)
A l
ctY M
n '0 5.'
the following p 06n 1/ agencies if the emergency l
tuation is such that notification is deemed appropriate.
a.
Hershey Medical Center 9-534-8333 (ask for Duty Nurse)
Notification to be perfonned per procedure 1004.16.
l 20.0
1004.2 Revision 9 ATTACHMENT I Section I Initial Contact Initial b.
Pennsylvania State Police 9-234-4051 MESSAGE:
This is at e Mile (name/ title)
Island Nuclear Station Unit We have d
red an Alert at hou We (tihre (have/have not)
We require assistance as radioactive rel ages llows:
(State asMstance required.)
/
~
c.
Radiation Man emeo_
orporation (RMC)
Eme i
800-1700) 73-215-243-2990 (1700-0800)
-841-5141 p
(, e (0800-17 0 215-243-2950 GE:
ts is
.O.
at the Three Mile
--/
(nam t<i tl Island Nuclear Stat n Unit I calling. We have declared an Alert at hours.
(Give a brief (time) description of the emergency). We (have/have not) l had a radioactive release.
i l
21.0
1004.2 Revision 9 ATTACHENT I Section !
Initial Contact Initial d.
American Nuclear Insurers 74-1-203-677-7305 or 9-1-800-2 3173 (after no ing hours)
Message:
This is Three Mile (name/ title)
@uclear Station Unit alling. We have red an Alert at hours (Give a brief (ye) description o ency).
We M
had a radioac ive release.
(hav 4e y t)
_G V
/8 N0 hN
$7
~
4Nv av s
g4 W
l l
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22.0
1004.2 Revision 9 ATTACHMENT I Section !
Initial Contact Initial 4.
Nuclear Regulatory Commission (NRC) - Bethesda, MD.
(Continuous connunications with the HRC will be main d follow-ing contact.)
a.
Telephone: NRC Emergency Notification S NS) (RED PHONE)
(If ENS Phone is inopertative, refer o gency Plan Imple-menting P 1004.6, "Additio a sistance Notifica-tion" rnate metheds).
O b.
MESS is at the Three Mile Island (name/ti e M
Nuclear Station Un ca ling. We hay c ared an Alert (time)
(Based u osv mergency Director
, use one of the followi a ements):
1.
We ave not had a radi
.ti)e release 2.
We have had a radioactive release but do not expect this situation to result in detectable changes in offsite radiation levels.
OR l
l 23.0 l
r 1004.2 i
Revision 3
~
ATTACHENT I s
Section I Initial Contact Initial 3.
We have had a radioactive release but do not know if there will be a detectable change in off t diation.
levels. We will be keeping the Burea atien Protection informed of the results u
nyestige: ion..
4.
We have had a radioactive rele.
xpect to be able to d nges in offsite a ion levels but thes e
ss than the leve aMing for a" Site Emer.
g We expect the e 1s'to be <50 mrem /hr (gamma) and child thyroid dose ent to be <250 MREM /hr.
~
We will be ke Bureau of Radi ion Protection informed. Q c.
(Give a short echnical descri o
he emergency, the
/
1 extent of s radioactive releas y, and the potentially ppropriate).
Df a affe ations and area N
y l
1 l
DATE TIME OF COMPLETION COMPLETED BY-l 1
NOTE:
After initial NRC notificaion is complete per l
Attachment I,Section I above; Refer to the NRC Notification Checklist, Attachment III. This i
I Checklist contains infonnation desired by the NRC l
and may be helpful in providing follow-up information.
l 24.0 1
4 e
1004.2 l
Revision 9 1
ATTACHMENT I i
SECTION II
. r.-
NOTIFICATION CHECKLIST TIME OF INITIAL NOTIFICATION TIME 0F OR ESCALATION DE-ESCALATION OR CLOSE OUT A
- ~
~
7:11NU5UXI.:.
TITE
- GESV:'UNITSITAl.:
5ITE
- GENERXE-~:
AGENCY
- EVENT ;/SLEI3I : EERGENCY :EMEBENCYgEVENT : ALERT : EMERGENCY : EMERGENCY _:
y / /l Nl -
b:
/
N
- Dauphin County f / ~
V [:
vp/h
- PEMA Y'
- (/ j Y i
- Unit 2 Control Room 6:
I:
\\)
/ [:
)
- INPO a
y:
- NRC
/5 ::
- ~
- M
- Hershey Medical Center ::
- O,:
=
((\\>s)J g y /.
/A V::,d :
- State Police V:
V
- K:
A-) A
../f
- RMC
(,
iy v
. __ [ ;_
- ANI p,
.:y-
- B and W
- N/A : N/A :
V:
Vy l/N
- 5 Affected Counties
- N/A : N/A :
N/A
,i vt-
- Optional 25.0
1 1004.2 Revision 9 ATTACHMENT I Section III Secondary Contact Initial The Consnunicator shall notify the following agencies and personnel and update the Attachment I,Section II checklist for each no tion.
1.
Announce or have announced the following message plant page after turning on whelen sirens " ATTENTION ALL N
, ATTENTION ALL PERSONNEL. 'The Alert has been tennina ve a brief de-scription of the htrictions, if any)'.
epeat message and turn off whel r
D 2.
Bureau of. R 1 Protection v
~
a.
Tete e: Radiological L
-787-3720 b.
MESSAG :
This is
&t e Three Mile Islan lear Station (name/ti Unit 1.
We hhv closed out the Aler hours and t
(time)
I initid overy operations. Wease notify PEMA, Dauphin, l
Lancaster, York, Lebanon and Cumberland counties.
3.
Unaf.'ected Control Room a.
Telephoca:8066, 8067, 8068 b.
Message: Notify Shift Superv t.,rik 7,5n of Close out of the Al ert.
4.
Nuclear Regulatory Commission Office - Bethesda, Md.
a.
Telephone: Emergency Notification System (ENS)
(RED PHONE) 26.0 l
1004.2 Revision 9 ATTACHMENT I Section III Secondary Contact Initial b.
ESSAGE:
This is at the Three Mile I d Nuclear (name/ title)
Station Unit 1.
We have closed out the hours (time) and initi very operations.
5.
If applicab
,n 1 y the following ns and/or agencies of close out o t Alert:
V Hershey Medical Ce er-9-534-8333 (ask for Duty Nurse) b.
Pennsylvania L a
e: S-234-405 c.
Radiation )(ana Corporation (
QAncies (0800-17 0%215-243-2990 (170 08 01 3-1-215-841-5141
\\
Office 800
- 0) 73-1-215-243-2950
- d. N can Nuclear Insur 4-1-203-677-7305 e.
ers - as directed by the Emergency Director.
DATE TIME OF COMPLETION COMPLETED BY 27.0
4 -
1004.2 Revision 9 ALERT ATTACHMENT I SECTION IV PROTECTIVE ACTION RECOMMENDATION GUIDELINES THESE. RECOMMENDATIONS MAY BE DELIVERED ONLY BY THE EMERGENCY DIRECTOR 1.
Consideration shall be given to sheltering if:
a.
Release time is expected to be short (Puf
<2 hours) and b
b.
Evacuation could not be well underw pr% to expected plume arrival rt warning time, hi wind speeds, and/or
\\D foul 2.
Consideratio s given to evacu i iY:
a.
(A lease is expected to with projected doses approach-ing or exceeding:
1RemWhoKB y d/or 5 Rem h froid p
nd b.
Relee is expected to'be g (>2 hours) and c.
Eva fon can be well underway prior to plume arrival for above release, based upon wind speed and travel conditions.
28.0
(
1004.2 Revision 9 ATTACHMENT II EMERGENCY STATUS REPORT Section I 1.
Descr.hption of emergency:
b E&v 2.
Has the Reactor tripped Yes/No 3.
Did the Emergency Safeguards Systems actuate Je If so, which o a.
High P essu njection h/No b.
Low R ss re Injection
/No c.
< tir Flood Yes/No d.
4 P3IG Reactor Buil o ation Yes/No e.
Reactor Buildin Spr ctuated Yes/No 4.
What is the status of th a.
At power b.
Hot c.
Ho own d.
Cool Down e.
Reactor Pressure psig l
f.
Reactor temperature
- F 29.0 l
l
1004.2 Revision 9 ATTACHMENT II EMERGENCY STATUS REPORT Section I 5.
Is of.fsite power available Yes/No 6.
Are both diesel generators operable Yes/No 7.
Have any personnel injuries occurred Yes/No a.
If so, is the injured person (s) contaminat No 1.
What are the approximate radiation a or ontamination levels A
mR/hr DPM/100 cr/
Q 8.
Are these excs,s diation levels a ontamination Levels Yes/N 8
a.
If so, List below:
1.
Radiation is hole Body) 2.
Contam n
}evels DPM at loc on:
~
4 Q
l DATE TIE COMPLETED BY 30.0
i 1004.2 Revision 9 ATTACHMENT II EMERGENCY STATUS REPORT Section II Fill out if a release has (is) ocurring. Provide BRP all avail ~able infonna-tion for verification call.
1.
What is the approximate radioactive source term discharge
. from the plant
( As determined by the Projected Dose Calculati o
ure (1004.7).)
a.
Noble gases Ci/sec k Ci/sec b.
Iodine m
2.
What is the appro 1 t teorology Q
a.
Wind s ed ph b.
Wind
^ tion c.
Stabili Class-Stable /
nstable 3.
What is the projected wholgbo se rate and fodin entration at the nearest offsite down int a.
16R/hr b.
t/cc Iodine i
c.
~
(Location) 4.
Estimated durat of the release a.
If the release is tenninated:
(
Start time Stop time i
Duration b.
If the release is still in progress:
j Start Time Estimated duration (hrs / min /sec) l l
l 31.0
a 1004.2 Revision 9 ATTACHENT II EMERGENCY STATUS REPORT Section II a
5.
a.
. Based on projected dose rates, f odine concentration and duration or estimated duration (if still in progress) of the release, will the lower limits of the EPA Protective Action Guides be ded (i.e.,
e 1 Rem Whole Body, 5 Rem Child Thyroid.
Yes/No b.
If yes, estimate time to exceeding PAG: />
ours
@g%m. Co,>ete l^4 e.te Co,>eted e, v
m%
g
(
l l
32.0
a 1004.2 Revision 9 ATTACHMENT III CHECKLIST FOR NOTIFICATION OF SIGNIFICANT EVENTS MADE IN ACCORDANCE WITH 10 CFR 50.72 A.
Identification:
Date Time Name of Person Making Report Licensee Facility Affected b
Applicable Part of 10 CFR 50.72 m
v B.
==
Description:==
Date of Event Time
/>
Description of What, pp{d.
C.
Consequences of E omplete dependin pe of event)
Injuries Fataliti
/
U Contaminatic/ personnel)
(property)
Overexposure nown/possible A
ential)
\\
Safety Hazard (describe btua %
Offsite Radiation Lev # v ANv el
\\ ~)
Integrated Dose Lo F od direction)
Meterology (wi d)
L Weather ConditioM (rain, clear, overcast, temperature)
Equipment / Property Damage D.
Cause of Event:
33.0
1004.2 Revision 9 ATTACHMENT III CHECKLIST FOR NOTIFICATION OF SIGNIFICANT EVENTS MADE IN ACCORDANCE WITH 10 CFR 50.72 E.
Licensee Actions:
Taken Planned Emergency Plan Activitated (Yes/No)
Classificati rgencyl f
Resident Inspector Notified (Yes/No)
Sta (Yes/No)
Press Releasa Plann
)
News Me ia terest (Yes/No)
L (ational F.
Current Status:
ete depending o e of event) 1.
Reac stems Status Power 1 Before Even Afte vent Pressure CN
- p. (t I
cold) hot RCS Flow (Yes/No Pumps On (
o Heat Sink: Con ser Steam te,--
mp Other ample Taken (Yes Activity Level S
l ECCS Ope' (Yes/No)
ECCS 0perable (Yes/No)
ESF Actuati n (Yes/No)
PZR or RX Level Possible Fuel Damage (Yes/No) l S/G Levels Feedwater Source / Flow Containment Pressure Safety Relief Valve Actuation (Yes/No) 1 See Emergency Action Levels, Appendix 1, NUREG-0654, Revision 1, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants.
34.0 1
1004.2 Revision 9 ATTACHMENT III CHECKLIST FOR NOTIFICATION OF SIGNIFICANT EVENTS MADE IN ACCORDANCE WITH 10 CFR 50.72 Containment Water Level Indication Equipment Failures Nonnal Offsite Power Availabe (Yes/No)
A Major Busses / Loads Lost Safeguards Busses Power Source
/)
_- y Loa s/No)
)
D/G Running (Y,
2.
Radioactivitf1htlbede 9
Liquid /Ga o ation/ Source g
v Release te N
Duration Stopped ( es/No)
A Release Mon red (Yes/No)
Amount of Release Tech S
. L1 s
Radiation Levels Are ed 3.
Security / Safeguards 2 Bomb Thre h Conducted f I7No Search Results Site Eva' es/No)
Intrusion:
Insider Outsider Point of Intrusion Extend of Intrusion Apparent Purpose Strike / Demonstrations:
Size of Group Purpose 2
See 10 CFR 73.71(c), effective April 6,1981.
l 35.0
)
- c..,.
1004.2 Revision 9 ATTACHMENT III CHECKLIST FOR HOTIFICATION OF SIGNIFICANT EVENTS MADE IN ACCORDANCE WITH 10 CFR 50.72 Sabatoge:
Radiological (Yes/No)
Arson (Yes/No)
Equipment / Property Extortion:
Source (phone, letter, etc.)
_b Location of Letter n
k Demands General: Firearms involved (Yes/No)
/>
ce (Yes/No)
Control of Fa mpromised or Thr (Yes/No)
Stolen / Mis rial Agencies d (FBI, State P 1 e,
ocal P311ce, etc.)
/6 g
o N>
Media Interest (presen pated)
A O
v 2x b3 36.0