ML20078H786

Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures 1055 Re Maintaining Emergency preparedness,1004.1 Re Unusual Event & 1004.2 Re Alert

ML20078H786
Person / Time
Site:	Crane
Issue date:	09/26/1983
From:	Hukill H, Nelson M, Toole R GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20078H784	List: ML20078H786
References
0027B, 27B, PROC-830926-01, NUDOCS 8310170007
Download: ML20078H786 (93)

Text

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1055 Revision 2 09/26/83 IMPORTANT TO SAFETY 33 NON-ENVIR0tNENTAL IMPACT RELATED N

TFiEE MILE ISLAND NUCLEAR STATION

~ UNIT NO.1 ADMINISTRATIVE PROCEDURE 1055 MAINTAINING EMERGENCY PREPAREDNESS Table of Ef fective Pages Page Revision Page Revision Page Revision Page @ vision 1.0 1

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1055 Revision 1 THREE MILE ISLAND NUCLEAR STATION

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UNIT NO.1 ADMINISTRATIVE PROCEDURE 1055 MAINTAINING EMERGENCY PREPAREDNESS Table of Contents Section Page 1.0 GENERAL 3.0 1.1 Purpose 3.

1.2 Scope

.0 1.3 References 3.0 2.0 RESPONSIBILITIES V

3.0 2.1 Manager, Plant T MI-1 3.0 D

2.2 Fire Brigade Coordinator 4.0 2.3

Manager, y

tal Controls TM 4.0 2.4

Manager, ustrial Safety a 4.0 2.5 Manager,. QA Methods Progr s

5.0 2.6 Plant Engineering Dir

.T

-1 5.0 2.7 Director, Systems e

g 5.0 2.8 Operations and a nance Director, TMI-5.0 2.9 Manager, Ra o i

l Controls, TM 6.0 2.10 Manager, P intenance. TMI 1 6.0 2.11 Manager, Plant Administration TMI-1 6.0 2.12 Emergency Preparedness Manager 7.0 l

2.13 Manager, Plant Operations, TMI-1 7.0 2.14 Manager, TMI Information Management 8.0 l

1.0

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m n-w w

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l 1055 Revision 1 i

Table of Contents (cont'd)

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Section Page 3.0 REQUIREM5NTS 8.0 3.1 Emergency Preparedness Drills 8.0 3.2 Emergency Preparedness Training 8.0 3.3 Emergency Preparedness Equipment 3.4 Emergency Preparedness Facilities 9.0 3.5 Scheduling and Tracking Emergency Preparedn 10.0 Requirements 3.6 Emergency Prepar s Documents Con o 12.0 List of Enclosvees 1.

Emergency Co er (ECC) 13.0 2.

Technical Supp Center (TSC) 15.0

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3.

Operations Support Center (OSC) 17.0 4.

Near-site Emergency Opera i cility (NEOF) 19.0 5.

Annex Near-site Emerg Op ations Facilit F{

21.0 6.

Environmental Asse[sy t ' mmand Center (

23.0 r~

n 7.

Parsippany TecMc qunctions Center (P 24.0 8.

Emergency Facil t' nventory Sheet 25.0

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1055 Revision 1

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1.0 GENERAL 1.1 Purpose This procedure delineates the requirements for maintaining emergency preparedness in TMI Unit 1.

1.2 Scope This procedure applies to all phases of maintaining le y

preparedness in TMI Unit 1.

1.3 References 1.3.1 Emergen an, TMI Unit i 1.3.2 Emer e lan Implementing nt for TMI Unit 1 1.3.3 A 10, Administration th('On-site and Off-site l

e ncy Duty Roste 1.3.4 1051, Emerge n

g Drills

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1.3.5 AP 1052, Eme e ning Training 1.3.6 AP 1053, i rge y Equipment Readfhss Gheck List r. rotection Progna:.P}Y 6

1.3.7 AP 103 an N ~N 2.0 RESPONSIBILITIES 2.1 The Mana

,no Training, TMI-sysponsible for the folicw-v Nv ing:

y 2.1.1 Schedule training for all emergency response personnel on the Emergency Plan and Implementing Document.

2.1.2 Schedule all site personnel to receive basic familiari-zation with the TMI Emergency Plan.

2.1.3 Coordinate emergency training for all Off-site support agencies in accordance with reference 1.3.5 and 1.3.7.

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3.0

l 1055 Revision 2 2.1.4 Ensure that all fomal Emergency P1&n Training is properly documented.

2.I.5 Forward results of training and documentation to Emergency Preparedness Manager as requested.

2.1.6 Assistance to the Emergency Preparedness Depa 'nent by providing drill observers.

2.2 The Fire Brigade Training Coordinator is respons' r the planning, scheduling and conduct of Quarterly gade Drills in accordance with erence 1.3.7.

2. 3. The Manager, Env o al Controls TR responsible to:

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2.3.1 Pr ssistance to th Emegncy Preparedness an in conductin n Emergency Exercises in oniance with r n

1.3.4.

2.3.2 Ensure that the ro mental Assessr ommand Center lable and in readh,ess as per section is maintai s

3.4.6.

g 2.4 The Manager. In'Eys g.'

A~ M 1 Safety and Heekh responsible to:

M 2.4.1 Prov' ssistance to the 'Emen}ency Preparedness

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V NMbo er in conducting the medical Emergency Drill in accordance with reference 1.3.4.

2.4.2 Ensure that first aid and medical equipment required I

for use in emergencies are available ano in reaainess.

2.4.3 The Site Supervisor-Safety and Health is designated the responsibility to carry out these duties in the absence 1

1 of the Manager, Industrial Safety and health.

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4. 0

I 1055 Revision 1 2.5 The Manager, QA Methods Program, Audits is responsible for

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auditing, at least on an annual basis, the TMI Emergency Plan and Implementing Document to verify compliance with the Operational Quality Assurance Plan, the Fire Protection Plan, internal rules and procedures, federal regulations, and operating lice e provisions.

2.6 The Plant Engineering Director, TMI-1 is respons sure that the Technical Support Center is maintain le and in readiness as per se on 3.4.2.

2.6.1 Provid a nce to the Em eparedness

\\oncy De y supplying d ill servers and scenario s

ce as request 2.7 The Dire Systems Engine @ g responsible to ensure that

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the Parsippany Technical Center is ma ed available and in readiness as p fon 3.4.7.

A 2.8 The Operations and/Ra nce Director _lMP-1 responsible to

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\\ w maintain the ONfteMmergency Organ 6n4uty Roster current N

V

'v in accordanc 7 '

eference 1.3.3.

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2.8.1 FY n de assistance to the Emergency Preparedness l

Department by supplying drill observers and scenario

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assistance as requested.

l 2.9 The Manager, Radiological Controls, TMI-1 is responsible to:

2.9.1 Provide assistance to the Emergency Preparedness Manager in conducting the following as per refer-ence 1.3.4.

a.

Radiation Emergency Exercise

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1055 Revision 2 b.

Radiological Controls Drill c.

Radiological Monitoring Drill

2. 9.2.

Ensure that radiological controls ememency equipment is maintained in accorcance with reference 1.3.6.

2.9.3 Ensure that the Operations Support Center and the Radiological Assessment Coordinators area e CC are maintained available and in readin p

sections 3.4.3 and 3.4.1 respective 2.9.4 Provide stance to the Emerg Pr redness Depart e upplying dril bser.rs and scenario a

e as requested.

'2.10 The Mana#,

Maintenance sible to:

2. 10.1 ovide assistanc

.ergency Preparedness Manager in cond epair and Dama C ntrol Drills in accorda reference 1.3.4.

2.1D.2 En sure.

ge control equ equired for use V ~

iness.

gies is availabl d g read in 2.11 The Site Em rgeac;gPreparedness Managerps responsible to:

y xe 2.11.1 a, schedule and coordinliT[all Emergency Plan j

s related drills and exen:ises.

2.11.2 Maintain the near-site Ememency Operations Facility in readiness as per section 3.4.4.

2.11.3 Maintain the Annex Near-Site Emergency Operations Facility in readiness as per section 3.4.5.

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1055 Revision 2 2.11.4 Review the Emergency Plan training lesson plans and examinations for technical accuracy, and provide

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technical support of applicable training activities.

2.11.5 Audit Emergency Preparedness records and documents at l

least ennually and submit results to the fol i ng:

a.

Nanager, Emergency Preparedness b.

Operations and Maintenance Direc

-1 c.

Vice President, TMI Unit 1 2.11.6 Maintai rent the following-l Item Tracking s sg a.

Ac b

i 1 Scenario fil f-site Emerge ization Duty Roster Emergency P e.

Emerg enc P redness Task Sch i

System f.

Emerg cy i n Implementing cm,ept 2.12 The Manager, P1a Goe ions, THI-1 i ns e to:

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Pr[w aspistance to th gency Preparedness l

2.12.1 Mn conducting alth s and exercises in v

v an ance with reference 1.3.4.

2.12.2 Ensure that the Emersency Control Center is maintained l

available and in readiness as per section 3.4.1.

2.12.3 Provide assistance to the Emergency Preparedness l

Manager in the performance of emergency communications tests as required by EPD-S0001 Emergency Comunications Operability Test Procedure.

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1055 Revision 2 2.13 - The Manager, TMI Infonnation Management is responsible to:

l 2.13.1 Provide controlled copies of procedures and the Emer-l gency Plan to facility coordinators as required in sub section 3.4.

2.13.2 Maintain current, up-to-day drawings and tech ical l

manuals at emergency facilities as require su section 3.4

3. 0 REQUIRDENTS 3.1 Emergency Prepare Drills 3.1.1 Drill s n:ises will b duct d following the e

D g

s of reference 3.4 3.1.2 r1 enarios will ed for each drill and proved in acco e

' h reference 1.3.4.

A file of these scenarios i maintained by e Site l

Emergency ness Manager.

3.1.3 Orill all be retaineLo at<1 east one year

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wit ergency Prepared s gpt. then forwarded to e

A g5r4ycontrols for pepnen, storage.

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3.2 Emergency Pregaredness Training 3.2.1 Training on the Eraergency P1an and its implementation shall be scheduled for all personnel at TMI Uni.t 1 as per reference 1.3.5.

3.2.2 Documentation of fonnal training provided shall be maintained by the training department.

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q 1055 Revision 1 3.3 Emergency Equipment, Preparedness

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3.3.1 Inventories, inspections and operability checks shall

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be performed on Emergen;y Preparedness Equipment in accordance with reference 1.3.6.

3.3.2 Emergency kit / locker key control shall be mai ined by the Radiological Controls Department with 1

s J

maintained in the Emergency Control Ce r.

3.4 Emergency Response Facilities

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NOTE:

Tne i s identified below their designee

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shall ry the facili i ainst the a

enclosure (s) a Q quarterly and.

ch drill or e ench ffecting those es. These iny t ies shall be documented I

losure 8 and he Emergency Prepared _

ess Department.

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3.4.1 The Emergency Co enter (ECb) sh maintained by

,,the Manager 1

Operations TMI-set the require _

ments o nc e 1, Part A.

,dttilogical Assess.

'N tor (RAC) areaAlQ~e maintained by the ms 1

Mani

,. adiological Conth MI.1 to meet the re_

\\h qtnganents of Enclosure 1, Part 3.

3.4.2, The Technical Support Center (TSC) shall be maintained by the Plant Engineering Director, TMI.1 to meet the re.

quirements of Enclosure 2.

3.4.3 The Operations Support Center (OSC) shall be maintained by the Manager, Radiological Controls to meet the re.

quirements of Enclosure 3.

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1055 Revision 2 3.4.4 The Near-site Emergency Operations Facility (NEOF) shall be maintained by the Emergency Preparedness Manager, to meet the requirements of Enclosure 4.

3.4.5 The Annex Hear-site Emergency Operations Facility ( AEOF) shall be maintained by the Emergency Prepared ess Mana-ger, to meet the requirements of Enclosu 3.4.6 The Environmental Assessment Command C) shall be maintained by the Manager, Envi Controls TM1 to meet requirements of Enc re 3.4.7 The P Technical Fu onshnter (PTFC) shall be m

by the Direct r, ems Engineering to meet th uirements of E 1 7.

3.5 Trackin rgency Prepared irements The Action Itc g Sy, stem is d ed to list l

3.5.1 Emergency dness discrepanc s mments from to assign resg y for their whatev o

r t

and to follow Mh to completion.

a Action item Tra (ystem shall be main-l tained by the Emergency Preparedness Manager.

l b.

Action items are detemined from drill critiques, l

4 audits or inventories, are assigned tracking j

numbers, persons responsible for their resolution, and listed on a schedule. The status of these l

items are maintained in the Emergency Preparedness office.

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1055 Revision 2 c.

Computer Printouts, with response fonns, will be forwarded weekly to all persons assigned responsibility until the item is reported complete or a resolution i s made. The Action Item Computer System will then be updated.

d.

All responses are to be documented o a e ency Preparedness Ation Item Report-e responses are filed in the Eme eparedness off e.

R n of action i.

sha be reflected on De Ation Item Sch dule ness Document t

3.6 Emergene r

3.6.1 file of drill s r

shall be maintained by the Energency Prepa anager The f for drill scenarios that delineate refefence 1.3.4.

3.6.2 Onergen Lists shall be t inad current and W

C-ava o security site rsonnel by the Emernesf Preparedness Mhnagen or his designee.

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(gsite Emergency urganization Duty roster shall be 3.6.3 maintained current and available by the Emergency Preparedness Manager.

3.6.4 The Emergency P1an will be controlled and revisec in acconfance with regulatory requirements and GPUNC policies.

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1055 Revision 2 3.6.5 Emergency Plan Implementing Procedures (EPIP's) will be controlled and revised to reflect the latest version of the Emergency Plan. Revisions which may impact upon

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the Radiological Controls Department will have the review of the Radiological Controls Departmen. All attempts will be made to resolve the comme ts n unresolved coments will be escalated r. anage-g

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1055 Revision 1

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ENCLOSURE ONE (Page 1 of 2)

A.

Emergency Control Center (ECC) l 1.

Located in the Unit 1 Control Room and adjacent Shift Super-visor's Office.

2.

In addition to nonnal communications, the fc11owing 11 of emergency communications shall be provided:

a.

Operational Line in Shift Supervisor's Offi b.

Radiological Lines in Control Room and c.

NRC Emergene ification System (

Control Room and Shift Sup v o 's Office.

y d.

Health ysi Network (HPN)

Shi Supervisor's Office.

e.

E me al Assessment AC area.

f.

Nati 1 Warning Syst i WA line in Cont 1 Room.

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g.

Emergency Director' Dialer in Shift isor's Office.

h.

Emergency D or s Hot-line in Cgitro Room.

1.

Radio Comu ons.

c n

3.

Shall pro gffcientworkarea he following personnel:

l a.

Emergene/ Director b.

Emergency Comunicator c.

Operations Coordinator d.

Radiological Assessment Coordinator e.

Radiological Assessment Engineers h

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1055 Revision 1 ENCLOSURE ONE (Page 2 of 2) 4.

Equipment will be maintained in the Emergency Locker in accor-dance with reference 1.3.6.

5.

In addition to documents normally in the Control Room, controlled l

copies of the Emergency Plan and Implementing Document shall be provided.

6.

Operating Materials shall be provided to include limited v

to, the following:

a.

Status Boards 1.

Emerge tor / operation coor ator D

b.

Emerge c ors log book c.

Pho i

g d.

Of supplies Log sheet holders,1 s

e.

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B.

Radiological Assessment Co r (RAC) area 1.

Located in the Un rol Room 2.

Operating Mat shall be provided t Mde, but not limited i

to, the fo w

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a.

Statu ds b.

REMP maps Appropriate logs and procedures c.

d.

Calculation system (i.e., TRS-801 l

e.

Office supplies l

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1055 Revision 1

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ENCLOSURE TWO (Page 1 of 2)

Technical Support Center (TSC) 1.

Located in the Control Tower Building, 322' elevation, beneath the Control Room.

2.

In addition to nomal communications, the following lines of rgency communications shall be provided:

a.

Operational Line b.

NRC Emergency Notification System c.

Parsippany/TMI Li d.

B and W Exten line 9

3.

In addition to th ncy equipment ire by AP 1053, the follow-ing operatin rials shall be pro.d a.

4 desks, ables,10 chai

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b.

Continuous Air Monito c.

Area Radiation Monit d.

Whiteboard with Q rs and erasers e.

Emergency P IPs f.

Unit 1 F (W

g.

Unit 1 TechnMal Specifications h.

Select Vendor Manuals Diesel Generator, Reload Report, Physics Test Manual, CRDM l

Manual, Bailey ICS/NNI, RPS, and ESAS Manuals, Reactor Coolant Pump Manual i.

Engineering Handbooks (Electrical, Mechanical, Industrial Power) i j.

Procedure Index k.

Operating Procedures (1100 Series)

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1055 Revision 1

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ENCLOSURE TWO (Page 2 of 2)

Technical Support Center (TSC) 1.

Seiect Survellance Procedures (ESAS, RPS', ICS, and NNI) m.

Emergency Procedures (1202 Series) n.

Abnonnal Operating Procedures (1203 Series)

• o.

Select Plant or System Drawings Series 001, 002, 012, 014, 015, 206, 208,

, 303, 304, and 660

• p.

Instrument List (

1 thru SS 308_24 q.

Telecopier C

D r.

CRT Termina wit rinter s.

Phone g

t.

General ce Supplies l

-- 55 ;-- 5;;;i g;-~~ n ;ii;7i ;;;;-

h--- iB5i5- ;

j Audits o ngs will be cond d documented I... __________ _

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1055 Revision 1

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ENCLOSURE THREE (Page 1 of 2)

Operations Support Center (OSC) 1.

Located in the area of the Radiological Access Control Point on the 306' elevation of the Auxiliary Building.

2.

In addition to normal comunications, the following lines of rgency comunications shall be provided:

a.

Operational Line.

b.

Radiological Line.

c.

NRC Emergency Not tion System.

d.

Radiological C t Auto-Dialer.

9 3.

Shall provide suf work areas or d-areas as required for the j

following per 1.

a.

Operation upport Center ina r.

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b.

Emergency Maintenance r

or.

c.

Radiological Control

( nator.

d.

Chemistry Coordi F

e.

Industrial Sat %t d Health Represe63td 4.

Emergency equipme N 1 be maintained i h mergency Locker in accor-w dance with reference 1.3.6.

5.

Operating materials shall be provided to include, but not limited to, the following:

a.

Status board b.

Emergency log book c.

Phone listing

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4 1055 Revision 1

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ENCLOSURE THREE (Page 2 of 2)

Operations Support Center (OSC) d.

Office Supplies e.

Log sheet holders, log sheets f.

Emergency Plan and Emergency Plan Implementing Docume g.

Radio, base station O

O P

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- - - - - - -. -. -. _,.,, = _

1055 Revision 1 ENCLOSURE FOUR (Page 1 of 2)

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Near-Site Emergency Operations Facility (NEOF) 1.

Located in the Training Center.

2.

In addition to normal communications, the following lines of emergency comunications shall be provided:

a.

Operational Line b.

Radiological Line c.

NRC Emergency Notification System Line d.

NRC Health Physic work Line e.

Environmental A n Line D

f.

Parsippany g.

Emerge r's Hot-Line h.

Radio e ication with e nm al and radiol gical field

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assessment teams.

i.

Conventional telepho 3.

In addition to emerge ent required p.

ference 1.3.6, operat-ing materials shall ided to includeWt t limited to the l

WN following:

7 (V

i v

N\\ -

One extenshn cord a.

s b.

One set of Unit 1 FSARs c.

One set of Unit 2 FSARs d.

Three four-drawer file cabinets e.

Nine folding tables f.

Two 6'-two door lockers g.

Fifty chairs h.

Two clocks

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1 1055 Revision 1 ENCLOSURE FOUR (Page 2 of 2)

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Near-Site Emergency Operations Facility (NEOF) 1.

Three space dividers J.

Six lamps (battery powered) k.

Phone stands 1.

Twenty-four clipboards m.

Seven comunications logs and writing materials n.

Twelve flashlights and batteries o.

Eleven plant and ity status boards p.

One set of Unit it 2 Operatin

+ edures D

q.

Emergency P Emergency Plan pie nting Document l

r.

INP0 M greement Han l

s.

TMI Evac on Time Estima

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t.

CRT with printer and an uter teminal u.

Radio 20.0

1055 Revision 1

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ENCLOSURE FIVE (Page 1 of 2)

Annex Near-Site Emergency Operation Facility (AECF) 1.

Located in the office complex at Crawford Station.

2.

In addition to normal communications, the following lines of emergency t

communications shall be provided:

a.

Operational Line b.

Radiological Line c.

Conventional Telephone 3.

Shall provide sufficien k areas or standby a as required for the l

following personnel:

9 a.

Group Leade R

Con Support b.

Rad Co or ersonnel c.

Group teacer - Maintenance rt

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d.

Maintenance Support Per nn e.

Maintenance and Cons ct Manager f.

Group Leader - S pity upport 9

SecuritySupy nnel h.

Personnel Aonit ing Coordinator d

I V

V

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f.

Radiological'Ontrols Manpower Superintendent 4.

Shall provide areas for the following functions:

a.

Badge issue b.

Training c.

TLD issue d.

Whole Body counting facility, k

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1055 Revision 1 ENCLOSURE FIVE (Page 2 of 2)

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Annex Near-Site Emergency Operation Facility (AEOF) 5.

Equipment shall be provided in an Emergency Locker in accordance with reference 1.3.6.

6.

Operating materials shall be provided to include, but not li ted to, the following:

a.

Three tables b.

Eight chairs c.

Phone cabinet

d.

• Log book D

e.

INPO Manual reement Handboo f.

Activa g.

2 log sh holders

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h.

Three status boards (Rad t

operational, g i.

Blackboard, chalk a r

j.

Clock

./

k.

Area map (

i list 1.

Tech. dr m.

Writing ma als (pens, markers, etc.)

n.

Radio Emergency Plan and Emergency Plan Implementing Documents o.

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1055 Revision 1

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ENCLOSURE SIX (Page 1 of 1)

Environmental Assessment Comand Center (EACC) 1.

Located in the Environmental Control Building at the Olmsted (Harrisburg International) Airport.

2.

In addition to normal operation communications, the followin ines of communication shall be provided:

a.

Environmental Assessment Line (1) dedicated line to RAC (2) dedicated 11 EOF b.

Conventional Tel c.

Radio commu s to field ass men eams 3.

Shall provid 1

t work areas ollowing personnel:

l a.

Environm 1 Assessment na (L

b.

Environmental Assessment 4.

A status board shall be pr to the Environmest%1 Assessment Coordi-

\\f nator.

5.

In addition to equi ^

mally utiliz k)facilityaGeli

/

detector shall d.

In addition to do\\cupents nomally in the Environmental Control Building, 6.

controlled copies of the Emergency Plan and Implementing Document shall be provided.

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1055 Revision 1 ENCLOSURE SEVEN (Page 1 of 1)

_[

Parsippany Technical Functions Center (PTFC) 1.

Located at the GPU Nuclear offices in Parsippany, New Jersey 2.

In addition to nonnal communications, the following lines of emergency communications shall be provided:

a.

Parsippany/B and W Line b.

Parsippany/TMI Line c.

Conventional Telephone 3.

Shall provide sufficien k areas for the fo g personnel:

a.

Group Leader - T ca Support D

b.

Technical S o

taff 4.

To provide th st

-to-date plant ng parameters, a CRT with printer and p1 computer tenni il e installed t operate on a

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not-to-i nte rf ere-wi th-op e rati o ns is.

5.

The PTFC Staff shall have cess to entire de n cal Library and l

shall be provided with tr ed copies of t erge'ncy Plan and

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Implementing Docu 5.

Additional docu; en+

supplies speci

1. Tech Functions Precadure EP-033, "Operatio f the Parsippany Tech. Functions Center" : hall be available.

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1055 Revision 1

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ENCLOSURE EIGHT (Page 1 of 1)

Facility Inventory Sheet, QTR/YR Emergency Facility Date No Deficiencies check Deficiencies Found:

(List below)

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Signed Dept. Head or designee Send to:

Emergency Preparedness Dept.

Trailer 67 TMI-1 k

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1 004.1 Revision 10 09/26/83

!!f 0RTANT TO SAFETY NON-ENVIRONMENTAL ItFACT RELATED THREE MILE ISLAND NUCLEAR STATION UNIT NO.1 EMERGENCY PLAN IMPLEMENTING PROCEDURE 1004.1 UNUSUAL EVENT i.

Table of Effective Pages Page Revision Page Revision Page Revision Page ion 1.0 8

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Qnar Date

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v[ ignature J Signature Date Document ID: 0023W

1004.1 Revision 8 THREE MILE ISLAND NUCLEAR STATION

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UNIT NO.1 EMERGENCY PLAN IMPLEMENTING PROCEDURE 1004.1 UNUSUAL EVENT

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1.0 PURPOSE

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The purpose of this procedure is to define the conditions that shall be regarded as an Unusual Event for Three Mile Island Nuclear St n

(Unit 1) angt to:

a.

Ensure necessary actions are taken to protect th ea and safety of the public, b.

Ensure necessary a are taken to not. y

. Nuclear management and offsite e n

esponseorganizajiy c.

Mobilize the r

iate portions D e wnergency response organi-zation tiate appropriate r

actions.

The Emergency DiNtor is respons' mplementingtpsprocedure.

(

NOTE:

The Emerg rector is vested pt ain author. :

l ity and re bility that may n

'ber elegated to fication of an emergen\\

a sub ni Included are:Q A.

C.

B. f4 ng and directi rffg,,a, event.

c,y l notifications to :

No e agencies.

V oving and direc,t ng n'fomation releases to fx e media.

(

NDK Kpproving and, if posirt5le, personally conveying N appropriate Protective Action Reccmmendations to :

the Bureau of Radiation Protection.

E.

Directing on_ site evacuation at the Alert or lower level emergency classification based on l

potential hazard to non. essential personnel.

F.

Authorizing emergency workers to exceed 10 CFR 20 :

Radiation Exposure Limits.

G.

Approving and directing deviation from establish. :

ed operating procedures, emergency operating pro. :

cedures, normal equipment operating limits or technical specifications during attempts to con. :

trol the emergency.

(NOTE:

It is imperative that the Emergency Director consult to the ful-i lest extent practicable with the Parsippany Tech- :

8 nical Functions Center in arrivir,1 at a decision :

to deviate from prescribed procedures.)

(

t 1.0 n

v e

---n.-,

-,-e, w

~

1004.1 Revision 8 When the designated Emergency Support Director (ESD) arrives at the site

(,

and declares himself to be ready to assume that role, he will assume overall r~esponsibility for management of the response to the accident and 1

recovery, operations. With activation of the ESD function, the ESD specifically will assume decision authority for It. ems C and D

owever, decision authority for Items A, B, E, F and G will be retai he V

Emergency Director (ED). Decisions on all of the list ac ns nonnally will result from close and continuous consultation he ESD and the ED and it is the res bility of the ED t e the ESD is provided with the necess information to a g timely and

\\

appropriate decisi the special caAof e ent classification, the ESD shall reta

)he erogative to o e ED if, in the judgement of the ESD, un nty or other cM ions exist tofthe extent g\\he warranting cla'ssification of a vel of emerge n that

(

v classificed by the ED.

2.0 ATTACHMENTS, Lkhsu Dvent Notifica%n 2.1 ency Status Rep'nONU c~

2.2 Attachment v

2.3 Attachment I M Checklist for Notification of Significant Events Made in Accordance with 10 CFR 50.72.

(

2.0

1004.1

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Revision 8 3.0 EMERGENCY ACTION LEVELS

(

3.1 Radiological Controls and Containment Integrity INITIATING CONDITION INDICATION 3.1.1 Radiological effluent technical As indicated by a valid Alert specification limits being alarm on RM-L7 or a high alarm approached.

on RM-A-5 low range 3.1.2 Valid, unarticipated ALERT alarms Any two or more di ic on any two or more area and/or monitor ALERT e

process radiation monitors at the received in Room same time.

simultaneaus 3.1.3 Valid Reactor Building Evacuation Receipt lid Reactor Alarm.

Buildi vac tion Alarm.

3.1.4 Loss of containme t rity As cate by a loss of the requiring shut _

echnical abi W meet any one of the specificatio con ' ons of Technical Specif-1 ti n Limiting Condition for tion 3.6.

3.1.5 Reactor c nt total activi s indicated b either:

> SO uCi/mi ut < 3850 uCi/

a.

Reactor c ant activity and/or Dose Equivalent Io as dete by sample

(

> 4uCi/ml but <300 uCi/

and analy Q Tndicating possible f age.

b.

RM-L Q~x 104 cpm bu <

0 cpm.

1 x 103 cpm j

c.

RE1\\

>5 tut c.S x 10 epm.

3.1.6 TransportatioIL,,

con-e by the Shift Super-taminated or<

ally con-

[

og taminated personnel

('

' rem site t site medical facility.

3.2 Security 3.2.1 Security threat or attempted Shift Supervisor's judgment,

. entry or attempted sabotage based on advice of tb Security of the site (0wner Controlled Duty Sergeant.

Area).

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3.0

1004.1 Revision 8 INITIATING CONDITION INDICATION

(

3.3 General Plant Status 3.3.1 Ottfer plant conditions are in Whenever plant conditions progress or have occurred which warrant it, as judged by the may indicate a potential Shift Supervisor / Emergency degradation of the level of Director.

safety of the plant.

NOTE:

In exercisin judgment a aeed for decla

..-.:u al

Event, ty conce fety status of the length of '

uncertainty sts nd the pros-s for early resolu-tio f ambiguities N.e.ld be considered; u

, uncertainty about the level of safety of the plant extending beyond a reasonable time period is a sufficient basis f declaring an Unusual vent.

(

3.4 Pressure, Temperature ve ory Control 3.4.1 Exceeding primary s nf4s k As indt'h d any one of the ca on.

followwh eqnfirmed Reactor rate technical sp\\

Cool'antheit Rates:

I i

I a q ibiry pressure Boundary c N except OTSG tubes) Leak

('4te > 0 GPfi.

1. x b.

nidentified reactor N

coolant leakage > 1 gpm and

< b0 GPM measureo by Daily Leak Rate Test.

c.

Total Reactor Coolant Leakage > 10 GPM and < 50 i

GPM measiired by Daily Leak j

Rate Test.

d.

Primary to Secondary Reac-tor Coolant Leakage > 1 GPM and < 50 GPM total tErough the steam generator tubes 1'

for BOTH generators mea-sureo oy the Daily Leak Rate Test and validated as a primary to secondary leak.

(

4.0

1004.1 Revision 8 INITIATING CONDITION INDICATION 3.4.2 Abnormal coolant temperature Operation with subcooling less and/or pressure.

than 30* or greater than 100*

and substained.

1 3.4.3 Faflure of a safety or relief Failure of the following to valve in a safety related system close:

to close following reduction of a.

Pressurizer Safe I

applicable pressure.

Valve (s), Power rated Relief Valve (

SG safety val ndicat-ed by th cal valve monitor 1 ow measur-4 ing eq b.

OTS ric Relief Va s)

Decay Heat S t elief valve.

3.4.4 A reactor trip s

y As (mfi ed by reactor trip either:

caus by a validated low-flow a.

Any reac c gr ant pump ip e by a total loss of fail

ater, b.

Tot s of ability to feed 3.4.5 Reactor trip followed by a Reactor trip m (F-1-1)

(

unplanned automatic ECC followed by Q).ction Flow initiation.

alarm (F N

3.5 Electrical Power 3.5.1 A sustained lo offfsite power A,sQn'dijaTed by a reactor trip j

resulting inAe tbr trip.

gassedbylossofpower.

\\

tA

//

3.5.2 A loss of On-sites AC power sAbi<rdicated by a loss of the capabilityNehul'fing in a tech-fatTity to meet any of the nical specifitation snutacwn.

conaitions of Technical Specif-ication Limiting Condition for Operation 3.7.2.

3.6 Instrumentation and Actuation Systems 3.6.1 Indications or alarms on process As indicated by a loss of or effluent parameters not indications, assessment or functional in control room to an communications capability extent requiring plant shutdown requiring plant shutdown or other significant loss of, by Technical Specification or primary and backup assessment as determined by the Shift or comunication capability.

Supervisor when assessment or off-site notification capabili-i ties are hampered.

i

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5.0

1004.1 Revision 8 INITIATING CONDITION INDICATION

(

3.6.2 Loss of engineered safety As indicated by a loss of the features or fire protection ability to meet any one of the system function requiring shut-conditions requiring shutdown down by technical specifications of Technical Specification (e.'g. because of mal function, Limiting Conditions of Opera-personnel error or procedural tion 3.3 or 3.18.

inadequacy).

3.7 Natural or Man-made Phenomena i

3.7.1 Natural phenomenon being exper-As indicated one of the i

ienced or projected beyond usual following:

levels.

a.

A vali n PRF-1-2 (>-

.01 old Seismic C

i on' indicating an j

ea th e.

~

b, ojected river stage

D" ft. at the River K(ar flood level).

er In-take Structure (50 y

l A projected river state

< 272 ft. at the River Water Inta e Structure (50 year low 1' el).

d.

High wi sting > 75 mph as indicate Wind Speed Reco @ (NDS-501) or l

Nation'a4lWiather Service l

s prd$e'otion of tornado or

'hur ' ne force winds.

3.7.2 Other hazard perienced ticated by any one of the or projected.

'folloying as judged by the S @ Supervisor, a.

Onsite aircraft crash outside the protected area fence and not impacting permanent plant structures.

b.

Train derailment within the Exclusion Area.

c.

Unanticipated explosion l

detected near or onsite.

d.

Near or onsite toxic or flamable gas or liquid release which could affect the habitability required for nonnal plant operability.

e.

Turbine rotating component failure causing a Reactor

(

trip.

j 6.0 l

1004.1 Revision 8 INITIATING CONDITION INDICATION

(

3.7.3 Fire in a permanent plant struc-Shift Supervisors judgement, ture which cannot be controlled based on advice of the fire by -the fire brigade within 10 brigade leader, min lutes of discovery.

3.7.4 Fire outside plant structures Shif t Supervisors judgement, requiring offsite firefighting based on request of e fire assistance to put the fire brigade leader for o te under control, firefighting assi ta 3.8 Reactivity Control 3.8.1 One Control Rod Stuck-Out, As indicat oss of the Stuck-In or Dropped, requiring ability any o.f the shutdown by Techni condi '

of chnical Specifications.

Speci c 1 s Limiting Co s f Operation 3.5.2.2 fo ntrol rod.

3.8.2 Unanticipate s'

ve reactivity d

rmined by the Shift insertio t

lly degrading visor or as indicated by the lev safety of the plan y one of the following:

a. An uncompensated operati ) reactivity chan esulting in a

(

vali 4feactor

\\

coplant putlet nipqroare alarm.

l

' unanticipated c.dfricali ty.

c inadvertent rod with-C

1. awal at power operations resulting in N

a reactor trip.

\\y

d. An inadvertant moderatcr dilution resulting in a valid high reactor coolant outlet temperature alarm and/or a Reactor trip.

These indications may be determined via instrumentation that will be installed or expanded as required by NUREG 0578 prior to restart.

(

7.0 i

1004.1 Revision 8 4.0 EMERGENCY ACTIONS Initials 4.1" Upon recognition that any of the action levels above have been t.

reached <or exceedcd, the Shift Supervisor shall assume the duties of Emergency Director. (The event should b sessed and declaied within ten (10) minutes of the occu e 4.2 Announce to the Control Room personnel that $w has assumed the uties of Emergency D cto The Emergency Director sh ically (appro, eve hour) consult with the lea n

of each area inv 1m in the emergency, ar.d disc s.

a.

atus of each are b.

Immediate actio.

aken by each g person

(

c.

Problem are d.

Recomendet course of act4; 4.3

Announce, announced, tne fo message over the public (dures system (merged)

N

.......------k......-..---...--....N v......----....---......--

l NOTE:

hpn on Whelen siren switch.

i l

" ATTENTION ALL PERSONNEL; ATTENTION ALL PERSONNEL: AN UNUSUAL l

l EVENT HAS BEEN DECLARED IN UNIT ONE. ALL MEMBERS OF THE I

ON. SHIFT EMERGENCY ORGANIZATION REPORT TO YOUR STATIONS. ALL l

OTHER PERSONNEL SHOULD CONTINUE WITH THEIR NORMAL DUTIES UNLESS FURTHER INSTRUCTI-0N IS GIVEN. Give a brief description l

l Of the event and repeat the announcement.)

(

h0TE$

Turn off5heken siren switch

(

l 80 l

1004.1 Revision 8 4.4 Assign a Comunicator to make notifications to persons and/or

(

~

' agencies per Attachment I,Section I.

4.57 Assign a Communications Assistant and direct him to perform all applicable steps of 1004.8.

4.6 Contact the Duty Section Superintendent and discus :

a.

Plant status b.

Which member's of the Duty Section are ui to augment the Onsite Emergency Organization.

4.7 Depending on rgency action le ch was reached or thattheapproprag rgency Operating exceeded.

s Procedu h

been implemen e 4.8 If I services (fire, a bu n, police) are required, direc he Connunicat t fy Dauphin Co y Emergency

(

Operations Center st the appropri Jistance.

Notify security t(

S Jtte) to begir,pr4p atJt3hs to expedite (Police / Fire Ambu _

entry of re gngemergencypers

.c lance). kevM should be ady' t

simetry Badge I s suanc,e.

NOTE:

If the Emergency Response personnel are required to respond outside the protected area affected by a radioactive plume, the Emergency Director or his designee will direct the issuance of TLD's from the North or South gate.

4.9 If the emergency involves radiological problems, direct the Radiological Assessment Coordinator to implement Radiological Controls During Emergencies (1004.9).

(

9.0 I

1004.1 Revision 8 4.10 If changes in onsite or offsite radiation levels are expected,

(

direct the Padiological Assessment Coordinator to:

a.

Dispatch offsite and/or onsite radiation monitoring teams in accordance with Emergency Plan Implementing Procedure 1004.10.

b.

Implement Onsite Offsite Dose Projections c

(1004.7).

4.11 If personnel / vehicles are, or are suspe t contamin-ated, have th initiate the Pers Vehicle Monitoring and Decontami on procedure (10 4 4.12 If addi esources or no ica\\1 ns are required, refer to ti Assistance a cation Procedure (1004.6).

4.13 Assig n individual t i

Attachment I Section I and give to the Radiolo ic sessment Coordi o transmit to the Bureau of Ra t1 Protection.

4.14 Direct the R o

al Assessment 1 ator to complete Attachmen tion II to trq. t the Bureau of Radia-tion o

n if a radioactfy ra dase has occurred or is

\\

D' oCCurrl 4.15 Stop all liquid and gaseous discharges that are in progress until an assessment of their impact is performed and specific approval is given to continue the release by the Emergency Director.

4.16 Verify that communications and documentation are maintained per procedure Connunications and Recordkeeping (1004.5).

(

10.0

s-1004.1 Revision 9 4.17 If applicable, direct the operations Coordinator to dispatch

(

Emergency Repair / Operations personnel to investigate the r identified problem area (s) in accordance with Emergency f Repair / Operations procedure 1004.21.

4.18 After 30 minutes from initial contact with PEMA, firm that BRP verification has been made. If no verifica o truct the Communicator to proceed to Attachment I on 1.2.(d).

4.19 If person (s) are injured or ill and are ologically controlled ar~

r are potentially c ina.ed, or if person (s) ha c ived radiatic sure greater than 25 REM; d r et e RAC to implem t Eihe gency Plan Implementing Pr ur 04.16, Contami uries/ Radiation Over-Expo 131 4.20 If personnel have be osed to 1 suf i

t to cause a thyroid dose of (<[ than or equal to*25 RAD, direct the' Nv/

RAC to imp 1 t

Thyroid Block roc,edure Emergency Plan V

Impleme bcedure 1004.35.

Based ugopessment of planttcondi,tions, either close out 4.21

\\

D' the U gaal Event or escalate to a higher class of emergency.

a.

If Recovery Phase criteria have been met (see Recovery Procedure 1004.24), but long tem recovery operations are not necessary, close out the Unusual Event by directing the Communicator to perform the notifications in Attachment I,Section II.

b.

If emergency action levels exceed those for an Unusual Event, escalate to a higher class, notify BRP on Radiological Line and make remaining notifi-11.0

1004.1 Revision 8 cations in accordance with the appropriate emergency procedure as specified in Step 5.1.

~

4.22 If necessary, due to potential contamination of normally t.

non-contaminated sumps and/or tanks, or the need to closely monitor liquid releases, initiate procedure 1004.1 Monitoring / Controlling Liquid Discharges For N ncon-taminated Systems.

5.0 FINAL CONDITIONS S.1 A higher cla rgency has been ed by the Emergency i

Director e

ting or exceedi y rgency action level of one th igher classes on f the following proce-du be ng implemented a.

rt (1004.2) b.

Site Emergenc 1

.)

{

c.

General Eme enc' (1004.4) 5.2 The Unusual h s been closed o ce no recovery N &

operation ^

uired, or N

nt can be shift a recovery mode by imple-5.3 The U

(

menting th procedure Recovery Operations (1C04.24).

5.4 At the close of the Emergency, ensure that all logs, check-lists, procedures and other documentation generated in the Control Room associated with the event are gathered and sent to the Emergency Preparedness Department for review and filing.

Date Signature of Person Responsiole for Implementing Procedure k

12.0

1004.1 Revision 8 ATTACHMENT I SECTION I INITIAL CONTACT INITIAL - The Connunicator shall notify the following agencies and f personnel, and update the Attachment I,Section II checklist for each notification.

1.

DAUPHIN COUNTY EERGENCY OPERATION CENTER (If this is a reclassification notification n tify BRP on the radiological line or 9-787-3720 th Item 3, Unaffected Con Rcom).

a.

Telepho : - 1 or 9-236-79

\\D b.

Me g

is at the Three Mile Island (name/ title Nuclear Station 1

111ng. We have eclared an

(

Unusual Even hours, and (bas pon (time)

Emergen i

+ r judgement, veq e of the follow-ing sta

$ts):

1.

ve not had a radioac.i've release D

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, but do not know if there will be detectable changes in offsite radiation levels. Ye will be keeping the Bureau of Radiation Protection (BRP) informed of the results of

(

our investigation, OR 13.C

1004.1 Revision 8 ATTACHMENT I SECTION I

(

INITIAL CONTACT INITIAL -

4.

We have had a radioactive release and expect to be able to detect changes in offsite radiat levels but they are expected to be less than e

i s calling for an alert.

We will b e 1 g the Bureau of Radiation Protection c.

Give a s non-technical descr no the emergency o

and any ally affected

- ation and areas.

\\

A

^

M M

cNT

~

~D

\\

PEN'SYLVANIA EME MANAGEMENT AGENC D 4PEMA) 2.

N (If this is c

ication noti tiq o to Item 3, Unaffecte klRoom).

I a.

T pW. PEMA Dedicated Linej(Use only during normal V

V w

ours 0800_1600 hrs., Monday - Friday) or 9-783-8150 i

(Use when the Dedicated Line is out of service or after normal work hours. A diverter forwards this after normal work hours call to the PEMA Duty Officer.)

NOTE:

If unable to contact, proceec to step 2.d.

(

14.0

__,,.w.-..m,-

,-c.

,9 y

y-

,,_gir,,

,.7.y

,-,,,..,,,,,,--,..y

-.y

,,e-

--nrve ve, T

= - - * - - - - -

1004.1 Revision 8 ATTACHMENT I SECTION I INITIAL CONTACT

~

b.

Message:

This is Three Mile Island Nuclear Station Unit 1 cal-ling. We have an emergency. Give me the Ope a ons Duty Officer. (When Duty Officer answers:)

This is at the Three and (name/ title)

Nuclear ion Unit 1 calling.

havMeclared an Unusual h rs.

request you (time) 9 co ct reau of Radiat Pr ction. Bureau of fa on Protection a should be made on tr.e 1M2iolgcical Line 48-69, 948-8071 944-0839.

(

(Based upon E.

ge Director judgem liver cne of the followi st dements):

1.

W n

had a radiod ease, OR 2.

had a radioact r

e, but do not expect situation to re %ffi detectable changes in offsite radiation levels, OR 3.

We have had a radioactive release, but do not know if there will be detectable changes in offsite radiation levels. We will be keeping the Bureau of Radiation Protection informed of the results of our investigation, OR

(

15.0

1004.1 Revision 8 ATTACHMENT I SECTION I INITIAL CONTACT

~

4.

We have had a radioactive release and expect to be able to detect changes in offsite radiation levels, but they will be less than the levels ca g for an Alert. We will be keeping the Burea' o ation Protection informed.

c.

Give a short non-technical descrip e emergency, and any tially affected po ns and areas:

bD m

(LM ~

n 'T L*

89 A

d.

If PEMA was u contacted, c Dauphin

(

County; ad i e t m that PEMA ca no ntacted and direct to notify PEMA, BSW Lancaster, York, Le Cumberland cog D

) des 4ggverification:

e.

Ex e t Bureau of Radiation Protection (BRP) contact after PEMA notification. If no BRP confirmation is received within 30 minutes, notify PEMA of the situation. If unable to contact PEMA (line busy), call Dauphin County and notify them that BRP has not verified initial con-tact. Request Dauphin County to contact PEMA and/or BRP.

I I

16.0 4

1 v-.-....

w..,

1004.1 Revision 8

~

ATTACHMENT I SECTION I INITIAL CONTACT INITIAL ~

3..

UNAFFECiED CONTROL R00M a.

Telephone: 8066, 8067, 8068 or inter Control oni Hot-Line b.

ESSAGE:

Give a brief description of Plant t Shift Super-visor.

4.

INSTITUTE OF AR POWER OPERAT 0 v

(Do not oti if this is a r ass

' cation notification.)

a.

le ne: 1-404-953 Contact TMI Site Operator assistance.

(

b.

MESSAGE:

This is k

at i ree

'le Island M y title)

Nucle

^ tion Unit 1 calling.

ave declared an Unarmrl ent at A

r.s. (Give a brief (timei VU

_. iption of the emergency.)

5.

' Notify the following personnel / agencies if the emergency situation is such that notification is deemed appropriate:

a.

Hershey Medical Center 9-534-8333 (Ask for Duty Nurse)

Notification to be performed per procedure 1004.16.

(

17.0

1004.1 Revision 8 ATTACHMENT I SECTION I INITIAL CONTACT INITIAL b.

Pennsylvania State Police 9-234-4051 MESSAGE:

This is at the Three Mile Isla ar (name/ title)

Station Unit 1 calling. We have dec r nusual Event at _

hours. We A had a

)

y)av ave not) radioa t release. Wereqir4 istance as follows:

(S e

assistance re ed c.

Adia on Management

'on Emerge

(

-1700) 73-1-2 -243-2990 (1700-0800) 73-41-5141

(

0 (0800-1700

-2,15-243-2950 MESSAGE-P, This %

aQ cee Mile Island Nuclear (name/ title)

T)

U MUnit 1 calling. W e declared an Unusual Event at hours.

(Give a brief description of the (time) emergency).

l

(

18.0

1004.1 Revision 8 ATTACHMENT I SECTION I

(

INITIAL CONTACT INITIAL We had a radioactive release. We require

~

(nave / nave not) the following assistance:

(State any assis required.)

d.

American Nuclear Insurers 74-1-203-6J - 0 r

%./

9-1-800-243-3172/3173 (after n working hours)

MESSAGE 9

Th at Three Mile Island (name/ ti tle) clear Station Unit ng. We have declared an (Give4rief Unusual Event at &

hours.

(

v descrip n

emergency).

a V

V 6.

NUCLEAR REGULATORY COMMISSION OFFICE Bethesda, MD.

(Communications with the NRC will be continuously maintained following contact.)

a.

Telephone: Emergency Notification System (ENS) (RED PHONE)

(If ENS Phone is inoperative, refer to Emergency Plan Implementing Procedure 1004.6, " Addition Assistance and Notification" for alternate methods).

(

19.0

1004.1 Revision 10 ATTACHMENT I SECTION 1 INITIAL CONTACT b.

MESSAGE:

....i._._.__._..._.....____.___.....__-__..._____......_..._......_..

' NOTE:

Complete this form (Adapted from NUREG-0845) before contacting the NRC (If this can be done wi out l

exceeding the one (1) hour notification ti.

i requirements obtain the infonnation fro.

i Shift Supervisor /Emen3ency Director.

t Request to speak to the Duty Off r

' Time of Contact Dug' yer's Name V

D T

/\\

at Three Mile ame Title i

land Nuclear Stati t 1.

We have declared a(n)

{

elect as approp y

GENERA

- GENT,Y (1004.4) 50.72 (NON EMERGENLYJ i

X UNUSUAL EVENT (1004.

TRA SRORTAT N ALERT (1004.2)

Pbc ECURITY, SAFEGUARJ5 n jR CATEbORY 0Th SITE AREA EME N 1004.3)

M AN aA Hourg on

>1 V me QNDate Pro $ide the statement selected by the Shift Supervisor / Emergency Director to the NRC Duty Otifcer.

1.

We have not had a radioactive release, OR 2.

We have had a radioactive release, but do not expect this situatior, to result in detectable changes in of fsite radiation levels, OR 20.0

~

1004.1 Revision 10 ATTACHMENT I SECTION I INITIAL CONTACT

~

3.

We have had a radioactive release, but do not know if there will be detectable changes in offsite radiation levels. We will be keeping th ureau of Radiation Protection infomed of the r u f our investigation, OR 4.

We have had a radioactive rel a xpect to be abl tect changes in e radiation levels will be less t ag levels calling for an bu We expect t e 1 v is to be less than 10

. em/hr (gama) than 50 MREM / hour child thyroid dose i

t.

We will b keeping the Bureau of R on Protection i i d.

c.

Give a shor chnical descrip emergency and potenti a

cted populatice 6 areas, if

' NO>

Y

^ x

.u<

EVENT TIME:

CAUSE:

21.0

1004.1 Revision 10 ATTACHMENT I SECTION I INITIAL CONTACT POWER PRIOR.T0 EVENT:

POWER NOW: t ANY SAFETY IWJECTION OR ECCS?

COOLING MODE:

ANY CONTAMINATI010 (QUANTIFY):

.O AnW ANY RELEASES: (QUANTIFY) A

~

\\vP V

_hV v

n N b

CONTAINMENT STATUS (IF APPLIC

.s 6Y n

ANY OTHER PROBLEMS:

A ssv s

N v

C)

O

.)

Qjn W

v PLANS:

DATE TIME OF COMPLETION COMPLETED BY NOTE:

If the NRC Duty Officer directs you to suspend continuous communications infonn The Officer a call back will be initiated if any significant changes occur'. Document with Duty Officer Name, Time and Date in the Emergency Director's Log.

22.0

1004.1 Revision 10 ATTACHMENT I SECTION II NOTIFICATION CHECKLIST i

TI!1E OF INITIAL NOTIFICATION TIME OF OR ESCALATION DE-ESCALATION OR CLOSE OUT

[m A

/

I :

SITE

GENERA USUAL:

SITE

GENERAL :

UN Q :

EVENT Alf;RV)' EMERGENCY : EMERGE ENT : ALERT : EMERGENCY : ENERGENCY :

AGENCY V g-

• [Vf:

Dauphin County VV

(f f.)

,PEMA

{\\ :

1 I:

M:

Unit 2 Control Room a

)

INP0

/ fs ::

/ ::

.y /) M.

(/

IIRC

O:

A

Hershey Medical Center ::

3 C)</! h k/[g-'j/)

I

State Police Rl4C

/)

41

.y

/-

ANI V:

\\)

pl

B and W

N/A

N/A

/

a

(/fvf L./

5 Affected Counties

N/A

il/A N/A j

• Optional 23.0 1

s E

1004.1 Revision 10 ATTACH!ENT I SECTION III SECONDARY CONTACT INITIAL -

The Comunicator shall nocify the following agencies and personnel and update the Attachment I,Section II cklist:

1.

Announce or have announced the following messag. v e

plant pa je after turning on whelen sirens "

i t ALL PERSONNEL, ATTENTION ALL PERSONNEL. The vent has been tenninat (Give a brief desc no the work and turn off whelen restrictions,1 a ny ) ". Repeat a a

siren s.

2.

Burdo diaton Protect' a.

ephone: Radio 1 a ne or 9-767-3720 b.

MESSAGE:

This is at the ThrM4fl Island Nuclear

'ngttl e)

Statio t 1.

We have clos -cab e Unusual Event a+

hours.

k l

Phaye notify PEMA, Dauphin, Lancaster, York, Lebanon and Cumberland counties.

3.

Unaffected Control Room a.

Telephone: 8066, 8067, 8068 b.

MESSAGE:

Notify Shift Supervisor / Foreman of close-out of the Unusual Evenc.

24.0

1004.1 Revision 10 ATTACHMENT I SECTION III SECONDARY CONTACT

~

INITIAL

4..

Nuclear Regulatory Commission Office - Bethesda, Md.

a. Telephone: Emergency Notification System (ENS) b.

MESSAGE:

This is at the i e Island ame/titl e)

Nucler Unit I.

We a clo d-out the Unusual Ev h _

hours.

(/ (time) 5.

If appl'

, notify the follo n sons and/or agencies of close-out o the Unusual E a.

Hershey Medic A Ce * : 9-534-8333 (a.,

Duty Hurse)

Per.nsylvanik Police:

9-23 5

b.

/] Y Radiat('oAAanage:nent Corcorati,on,

):

c.

NN N NN e

f.iergancies (OEg1) 73-1-215-243-2990

(

~

<'N N, (1700

) 73-1-215-841-5141 Office.

(CE00-1700) 73-1-215-243-2950 d.

American Nuclear Insurers: 74-1-203-677-7305 e.

Others: As directed by the Emergency Director.

DATE TIME COMPLETED BY 25.0

1004.1 Revision 10 ATTACHMENT II EMERGENCY STATUS REPORT

~

SECTION I Description of Emekency:

1.

A n%"

.hW nw 2.

Has the Reactor tripped Yes

/

No 3.

Did the Emergency Saf u Systems actuate s

/

No If so, which ones y

a.

High Pr Jection Yes i

b.

Low Pressuw Injection M

No c.

Core F1 cod No d.

4 psig Reactor Buildi Is ation Yes

/b e.

Reactor Building yai/

uuated Yes 4.

What is the status o e

ant a.

At power d<'

b.

Hot standby v c.

Hot Shutdown d.

Cooling down e.

Reactor Pressure psig f.

Reactor Temperature

_F 26.0

1004.1 Revision 10 ATTACHMENT II EMERGENCY STATtJS REPORT

~

SECTION I t.

5.

Is offsite pot.er available Yes

/

No 6.

Are both diesel generators operable Yes

/

No 7.

etave any personnel injuries occurred Yes

/

No What are the approximate radlation and/or contaminatio If so, is the injured person (s) contaminated Yes k '

/(

V mR/hr DPM/

7 8.

Are there exc r f ation levels n ntamination levelsu Yes

/

No If so, list below:

a.

Radiation Levels:

k b />

b.

Contamination Le DPM/1

\\(

\\

at location: _bV

_O Times \\

completed By Date v

v 27.0

1004.1 Revision 10 ATTACHMENT II EMERGENCY STATUS REPORT SECTION II Fifl out if a release has occurred or is occurring. Provide BRP all available infonnation for verification call.

1.

What i.s the approximate radioactive soun:e tenn disc e from the plant

( As detennined by the Projected Dose tion procedure L1004.7]).

a.

Noble gases M Ci/sec Ci/sec b.

Iodine v

D 2.

What is the a pro mate meteorolo a.

Wi ee mph b.

Wind ection c.

Stability Class Stabl Neutral

/

_e v

V bodydoserateanA ne concentration 3.

What is the projecte ho at the nearest o ye wnwind point

\\

b mR/hr a.

uCi/cc Q

b.

A c.

V (Location) 4.

Estimated duration of the release 2

If the release it. tenninated:

a.

Start time Stop Time Duration t

28.0

1004.1 Revision 10 ATTACHMENT II EMERGENCY STATUS REPORT

~

SECTION II b.

If the release is still in progress:

Start time Estimated duration (hrs / min / sec)

O 4._.....+Ah....

o 4

o@

4 v

4 O

s 0

29.0

1004.2 Revision 11 09/26/83 IMPORTANT TO SAFETY NON-ENVIR0l#4El4TAL IMPACT RELATED THREE MILE ISLAND NUCLEAR STATION -

UNIT NO.1 EMERGE!LY PLAN IMPLEMENTING PROCEDURE 1004.2 ALERT Table of Effective Pages Page Revision Page Revision Page Revision Page M ision 1.0 9

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/

fcm

')lD 6 l?3 Date1gnature & -/0l$ - Signature Date Document ID: 0024W -- -~

1004.2 . Revision 9 THREE MILE ISLAND NUCLEAR STATION UNIT NO '1 EMERGENCY PLAN IMPLEMENTING PROCEDURE 1004.2 ALERT

1. 0 PU RPO SE -

The purp'ose of this procedure is to define the conditions that shall be reganied as an Alert for Three Mile Island Nuclear Station (U t I) and to: a. Ensure necessary actions are taken to protect th h nd safety of the public. b. Ensure necessary a ns are taken to not PU-clear management and offsite eme sponse organizDns. \\ c. Mobilize th riate portions th mergency response organi. zation n appropriate action s. The Emergency tor is respons implementing this procedure. ( [0TE$ hh Emer D tor is ested wi aknYut[- ority an sibility that mafgot (e delegated Included arp;AV/ to a sub C}$s ion of an emet A. K raving and directing %agegevent.f$ciyl notifications B. F N site agencies. \\N I Cb ;ov l nfYmation releases to ing and direg( s media. x (NO.\\ Approving and, if pb@ e, personally conveying : i l M* appropriate Protective Action Recc::r.endations to the Bureau of Radiation Protection. l E. Directing onsite evacuation at the Alert or lower level emergency 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, normal equipment operating limits or : technical specifications during attempts to control the emergency. (Note: It is imperative : that the Emergency Director consult to-the fullest extent practicable with tne Parsippany Technical Functions Center in arriving at a decision to deviate from prescribed procedures). ( 1.0 I -.--,,,..,,,._.,_..-..-,,~.--e r r - te-e e-. m v e. wa-er-

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 assume overall responsibility for management of the response to the accident and recovery' operations. 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 ret ne_ b the Emergency Director (ED). Decisions on all of the list normally will result from close and continuous consultation e ESD and the ED and it is the res ibility of the ED t e ure he ESD is provided with the nece onnation to a e at timely and appropriate decisi n the special c ue o vent classification, the ESD shall retaMth rogative to oyerr\\ht he ED if, in the judgment of the ESD, u inty or other e m ions exist to the extent warranting classification of a h vel of emerge han that

( v m classified by the ED. 2.0 ATTACHMENTS 2.1 Attachment I, Notifications \\ 2.2 Attachment t - rgency Status Rehrt h D 2.3 Attachment LTL, Checklist for Notification of Significant Events Made In Accordance with 10 CFR 50.72. 2.0 . _ _. ~ ~. -.. _ _.

1004.2 Revision 9 6 3.0 EMERGENCY ACTION LEVELS ( 3.1 Radiological Controls and Containment Integrity Initiating Condition Indication 3.1.1 Rddiological effluent activity As indicated by any of the exceed the Environmental technical following validated by sample specification instantaneous limits. and analysis: x 104 a. RM-A8 (gas) - t< cpm (Hig a 1.0 x 10 b. RM-A9 s 4.5 x 104 cpm 1 ) but <3.0 c. 5 0 x 106 cpm.* d. iodine) increase >- O cpm / min but < x 10 cpn/ min.* 9 (iodine) increase > O .5 x 103 cpm / min but < - x 104 cpm / min.* Offsite Radiological Monitoring Team reports > 10 mR/hr gamma) but <50-mR/hr at y offsite locat (

g. 'Off te R logical Mo ri Team reports Obse' alent I-131 dingt at any offsite esation of >50 mR/hr QD 2 x 10-8 Ci/cc) to

<2$0 mR/hr (<1.6 x 10-7 ,Ci/cc). i 3 \\ RM-L7 >1.0 x 10 cpm v g (hign Tiarm).

i. 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 l of radioactive materials. and/or process radiation monitors (RMA, RML or RfG monitors) at the same time. These indications may be determined via instrumentation that will be installed or expanded as required by NUREG 0578 prior to restart. ( 3.0 ,-m,

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 ha 'ncreased by a factor 1 above normal. 3.1. 3 Fuel damage accident with release An acciden occ while ~ of radioactivity to the contain-handlin el during ment or fuel building. refuel ile moving obje ov the spent fuel po h causes any one of e fol ing: alid High alarm on 9 -A2. b. A valid High alam on RM-A4. A valid High alarm on RM-A8. ~ d. A valid igh alarm on RM-A13. ( e. A val 1 alarm on RM-47. f. A Ita m g igh alarm on itNGAf s g vai,id increase by a M tr of 100 of atmos-hdric activity as determined by sample and analysis. 3.1.4 Reactor Cootadt pump failure at As indicated by both of the power leaaing to fuel damage. following: a. Receipt of a valid RCP tiotor Overload alarm and decreasing ficw in the affected loop, and b. Reactor Coolant specific activity as detemined by sample and analysis is >50 uCi/ml but <3850 FCi/ml. 4 CPM but (RML1 Low >6 x 10 <1 x 106 CFM and/or RML1 High >l x 103 CPM but >2 x 100 CFM). ( 4.0

1004.2 Revision 9 Initiating Condition Indication ( 3.1.5 Reactor Building pressure Reactor trip and ECCS -->4.0 psig, but <30 psig. initiated due to high Reactor Bui.lding pressure. 3.1.6 Reactor cool < ant 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/mi but <1430 uCi/mi and analysis. Tndicating fuel cladding failure. b. RM-L1 Low c e High) c. RM-L1 Hi cpm but <1 3.1.7 Secondary system activity As indi ample and >1.0 uCi/ml (I-131 equivalent). analy s. 3.2 Security 3.2.1 Security of ity (Protected Mupervisor's judgement Area) is t d y unauthorized bi on information from the entry of t (0wner Controll Du Security Sergeant. Area).

3. 3 Genera nt Status 3.3.1 Other plant conditions a Whenever conditions I

progress or have occur warrant i udged by the may involve an'actu t tial Shift Su ervi / Emergency substantial degrada i n the Dir level of safety t nt. NOT exercising the Jtidgement as to the / \\ Deed for declarina an V lert, uncertainty A concerning safety gx status of the plant, the length of tiiae the uncertainty exists, l the prospects for l early resolution of l ambiguities, and the potential for substan-i tial degradation of the level of safety of l l the plant should be considered; i.e., uncertainty as to the existence of substan-L tial degradation of the level of safety of the plant extending beyond a reasonable time period is a ( sufficient basis for declaring an Alert. 5.0 l

1 l 1 1004.2 Revision 9 1 Initiating Condition Indication ( 3.4 Pressure, Temperature and Inventory Control 3.4.1 Primary coolant leak rate of As indicated by increased greater than 50 gpm. makeup flow in excess of ~ letdown flow by 50 gpm or l makeup tank level decreasing at approximately 2 inches per minute or greater. 3.4.2 Primary to Secondary leakage: As indicated a. Total primary to secondary a. Valid a a on RM-A5 leak rate >50 gpm. High Ra conjunction with nk level de e approximately nche minute or s. b. Total primar ondary b eak ate determined by leak rate 'g nd <50 gpm \\ y leak rate test or AND los fUstte power. \\ eup tank level M ecrease up to 2 inches / minutes with previous indication of tube leakage (RM-A5 Low Range in igh Alarm) in conjun o with an I indica ' lure of off, site pow r, c. Total primary to cou ry leak c. LaakNrate2determinedby rate >l gpm amjP <. In AND dahy' leak rate test or a steam lineQice'ak. Qgp tank level d 4rease up to 2 iFxhes/ minute with a f . rapid unanticipated ah N

• ' decrease in steam A

pressure or activation of the Steam Line Rupture Detection System (SLRDS) 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 t,ank Low Range in High Alarm) Decause this is diff-: in conjunction with con-cult to see thi 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 >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 indicat reactor cident with a loss of both Diesel trip cau s of power Generators for less than 15 and t a s on both minutes. Dies en ors neither of whi gizes the ID or IE 4 kV bu s. 3.5.2 Loss of all power for AI tery Voltmeters read less than 1 es. ze and there is no light or ntrol power available. 3.6 Instrum tion and Actuati s a 3.6.1 Most or all annunciators As judged b he Shift Super-I ~ which may involve an visor. potential substantia p tion of the level o of N the plant. r actor protection Anyx sFittor trip setpoint Failure of thg{qeMd complete 3.6.2 systemtoipit C3'e4ngwxceeded with no rod a trip whe rer.:U. red. f inl)mit lignts. <N N 3.6.3 CompleteTols any function M indicated by a total loss needed for Mant 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 Removal Pumps, Reactor Coolant Pumps, etc. ) coincident with total loss of ability to feed OTSG's. 7.0 m. ,w ~-g e ,s,,e ,.-,m ,t. -9 m -w-+-e, e--- - - ~p., .,p-.y

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 ( e >302 River Wa ~'be, at the feet but <3 ~ e Struc-ture. c. Projec e ri r stage <271 the River 7 r a e Structure, d. tor do striking a ty. urrn ane vinds >75 mph \\W ndicated on the Wind peed Recorder. 3.7.2 Other h d ng experienced indicated by any one of t e following: a. Aircraft crash or other missile gpact within the protected rea or onto I any pehnme plant str y ure. " b. Howex;r,$sion damage to an ermanent plant /) su uc,ure. ReTesse of toxic or f?ammable gasses into the 'blant which, in the N\\ judgement of the Shift \\ Supervisor, affects the safe operation of the pl:1t. d. Turbine failure resulting in casing penetration. e. Any fire in a permanent plant structure whicn 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 [ ,, - - -, +., e w-,- e g<

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. ificatior. Limiting Condition for Operation 3.5.2.2 for more than one co 1 rod. 3.8.2 Control Rod Ejection. As indicated tor Trip due to n tron flux in coincid ce i h loss of coolant c ns. 4.0 EMERGENCY ACTIONS V Initials any of the above I lon levels hTve been 4.1 Upon recog h reached d, the Shift Su v or/ Duty Section Superin ent assume the d e the Emergency Director. (The event should be assessed ared within 10.i utes of its occurrence.) 4.2 Announce to Contr@jR rsonnel that b has assumed the du' e[* (~7 Emergency Director ( (name) Emergency Director. shallpericfc approx. every gnsult with the lead personnel c' area involved in th Wemergency, and discuss: a. Status of 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. " ATTENTION ALL PERSONNEL; ATTENTION ALL PERSONNEL: AN A RT HAS BEEN DECLARED IN UNIT 1. ALL MEMBERS OF THE ONSITE E R ORGANIZATION REPORT TO YOUR STATIONS. ALL OTHER E AWAIT FURTHER INSTRUCTIONS." (If emergency is radia nted add: "There will be No S ng, Drinking, or Ea n unt further notice.") (Give b description of. eve t and repeat the D announcement). 4.4 If emerg 1 diation-orient t that the Radiation Emergency. rm be sounded. ~ ___........______ m._______._____ ( on switch after aTaTEbs been NOTE: Turn off Wh s sounded. Q 4-4.5 Assign a Comunica Jto make notificatic sons and/or agencies per t I, Section I. ( / 4.6 Assign a C tions Assistant ami, et him to perform all N applicable st ps of 1004.8. 4.7 Contact the Duty Section Superintendent and discuss: l a. Plant status b. Which members of the Duty Section are required to augment the Onsite/Offsite Emergency Organization. 4.8 Depending on the emergency ac. tion level which was reached or l 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. Not1fy Security (N/S Galte) to begin preparations to expedite entry of responding emergency personnel (Police / Fire / Ambulance). Security hould be advised to implement procedure 1004.19 Emergency Sec i imetry Badge Issuance. NOTE: If the Emergency Response perso.1 required to respan side the protected k af cted by a radio lume the Emersen hctor or his desi direct the i A ce of TLD's from the N o uth gate. \\Q 4.10 If the nvolves radio roblems, direct the Radiolo Assessment Coo t o implement Radiological ( Controls During Emergencie .9). 4.11 If changes in onsite ite radiation levMs are expected, QV/ direct the Radio 19<$c essment Coord ogte. a. Di spatc and/or onsite r ti monitoring teams in D) accordancewh EPIP's 1004.1Q hM b. Implements 0nsite Offsite Cose Projections procedure (10C'.7). v 4.12 If personnel /vehicies are, or are suspected to be contaminated, l j 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). l l 4.14 If additional resources or notifications are required, refer to Additional Assistance and Notifications procedure (1004.6). l 11.0

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 Di/ect the Radiological Assessment Coordinator to complete Attact"aent II, Section II to transmit to the Bureau of, ia-tion Protection if a radioactive release has occurred or i o r ing. 4.17 Stop all liquid and gaseous discharges that are i e s until an assessment of their impact is performed and e ' approval is given to continue t elease by the Emer Dir ctor. 4.18 Verify that commu s and documen n ar maintained per D procedure Co ons and Record epi (1004.5). 4.19 If appli et the Operat dinator to dispatch Emergenc air / Operations on to investigate the identified problem area (s) in acccrda e Emergency Rep ' / Operations g procedure 1004.21. alcontactwitLh,e 4.20 After 30 minutes firm that BRP verification h made. If no ve cu n, instruct the ccnraunicator ~ eed to Attachme hetion 1.2 (d). <N \\Y \\ 4.21 Instruct thi Ndlological Assessment Ct6rdinator to provide ongoing dose estimates for actual releases to the Bureau of Radiation P rotection. 4.22 Evaluate dote projections and estimates and if necessary, reccamenc protective actions to the BRP consistent with the guidelines in Attachment I, Section IV. 12.0 ---wmy-

1004.2 Revision 10 4.23 If personnel are injured or ill and are in a radiologically controlled area or are potentially contaminated, er if person (s) haiTe mceived radiation exposure greater than 25 REM; direct the rah to implement Emergency P1an :mplementing Procedure 1004.16, Contaminated Injuries / Radiation Over-exposure. 1 31 4.24 If person (s) have been exposed to 1 sufficient to a thyroid dose of greater than or equal to 25 RAD, e RAC to implement the Thyroid Blocking Procedure Eme n Implementing Proce 1004.35. 4.25 Basea upon assess, plant conditi ither close out the D Al ert, e sca e a higher class emgency or downgrade to a lower cl s. a. If very Phase crit h been met (see Recovery Procedure 1004.24), b ong term mcovery ions are not ( necessary, clos u e Alert by perfo.rh(ng he notifications in Attachne ion III. V b. If Reco Qe cri teri a have bebn met, but Alert emergnh on levels are noponpr being exceeded, de-e s te to an Unusual EventY notifying 3RP on the Radiological Line and perform the remaining notifications in accordance with the Unusual Event orocedure (1004.1). c. If emergency action levels exceed those for an Alert, escalate to a higher class, notify BRP on the Radiological Line and make the mmaining notifications in accordance with the appropriate emergency procedure as specified in Step 5.1. ( 13.0

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), Moriitoring/Co6 trolling Liquid Discharges. 5.0 FINAL CONDITIONS - 5.1 A higher class of emergency has been declared by the r n Director after meeting or exceeding an emergency 1 el of one of the higher classes and one of the follo e-dures is being implemented. a. Site Emergen .3) D b. General cy (1004.4) 5.2 A lower c s rgency has b ' red by the Emergency Director nusual Event p du 1004.01) is being implemented. b 5.3 The Alert has been closed o t i e no recovery ons are g required. a recovery mo,h mplementing the 5.4 The Alert can be s te procedure Reco ations (1004.24 %a,t all logs, check-lists, th 6.5 At the close f' Emergency, ensura v procedures andsother dccumentation generated in the Control Rocm V associated with the event are gathered and sent to the Emergency Preparedness Department for review and filing. Date . Signatiire of Person Responsible for Implementing Procedure 14.0

l 1004.2 Revision 9 ATTACHMENT I / Section I Initial Contact The Cornunicatfor 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 reclassi11 cation notification, f 'se BRP via Radiological line o 787-3720 then unaff d Co trol Room) go to Itan 3. 9 Telepho@1 or 9-236-797( a. 1. f ntact, activa County radio system. b. MES. This is at the Thre 1 Island g Nuclear Station t alling. We hav_e b@edanAlert Y at yburs. ( tim (Based hooe-Emergency Directo nent, deliver one of the Nd \\ folicwta, statements): v 1. We 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 ~s-v -r---- y --,m-w ,,w g -y.,, ,e,,

1004.2 Revision 9 ATTACHMENT I ( .Section I Initial Contact Initial 3. We have had a radioactive release, but do not ow if there will be a detectable change in offsit r ion levels. We will be keeping the Bureau a ion Protection informed of the results o estigation, OR 4. We have a a adioactive rel and expect to be able to changes in offs er ation levels, but they e ted to be les e levels calling for a e Emergency. W 11 keeping the B reau of Radia-tion Protection i e. { c. Give a short non c 1 al description he ergency and the extent o e oactive relea Agfie affected m\\$ populatio ea. CO'; W v 2. Pennsylvania Emergency Management Agency (PEMA) (If this is a reclassification notification, go to Item 3, Un-affected Control Room.) 16.0 -, - + --u, ~

1004.2 Revision 9 ATTACHMENT I ( Section I ~ Initial Contact t. Initial a. Telephone: PEMA Dedicated Line (Use only during NQRt@' ark hours 0800_1600 hrs. Monday-Friday) or 9_783_815 ( hen the dedicated line is out of service or aft no 1 work hours. A diverter forwards this after no K hours call to the PEMA D icer). NOTE: If 1 o contact, proce step 2.d. b. MES This Three Mile Isl r Station Uni i calling. We ( have an emergency. Gi e the Operations fficer. (When Duty Offic an rs:) This is [ at t rae M'ile Island ' ~ 't.me/ T i tl e ; Unit 1 calling % ve declared an Alert Nuclear i \\ V at b hours. V (tiep) We request you contact Bureau of Radiation Protection. Bureau of Radiation Protection callback should be made on the Radio _ logical Line or 948 8069, 948_8071 or 944-0839. (Based upon Emergency Director judgment, deliver one of the following statements): 1. We have not had a radioactive release, OR 17.0

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 f site radiation levels, OR 3. We have had a radioactive release, know if there w e detectable chang of ite radiation levels 1 be keeping ureau of Radiation Pr c informed of th res ts of our investigation, R 4. have had a radi i elease and ex ct to be able to datect change site radiatio s but they will be les the levels calliabf ite Emer-gency. w keeping the eau Radiation Prot ~ nformed. k n c. Give a sho n-technical desc n of the emergency, and b any potegially affected populations and areas: I 18.0 ,y ,,n.w-.

1004.2 Refision 11 ATTACHMENT I Section I ~ Initial Contact Initial d. If PEMA is unable to be contacted, contact Dauphin unty; advise them that PEMA c,annot be contacted and di c to notify PEMA, BRP, and Lancaster, York, Leban umberland counties. e. Message verifigg4n: Expect Bureau ological Pro (BRP) contact after PEMA no on. If no BRP fi tion is received within 30 e, otify PEF % of tion. If unable to ~ conta EMA (line busy 11 phin County a d notify them that BRP has not verif initial contact. st Dauphin County to contac E nd/or BRP. 3. Unaffected Control / com TeleQ h6, 8C67, 8068 hhontrol Rocm Hot Line. a. b. Emergency Organi . Staffing is reauested bu'(knplementation of the Unit 2 Emergency Plan is not required. (Give a brief description of plant status to the Shift Supervisor / Foreman.) 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 i ca-tion.) a. Telephone: 1-404-953-0904 or t e TMI Site I Oper r for assistance v b. M Th' \\ (t bree Mile Island (name/ title V clear Station Unit c 1 We have declared an ert at Give a brief cription of (time) ( the emerge j A bv AM <N ~ l 5. a the following pers / agencies if the emergency \\/ situation is such that notification is deemed appropriate. i a. Hershey Medical Center 9-534-8333 (ask for Duty Nurse) Notification to be performed per procedure 1004.15. l l f 20.0

100402 Revision 9 ATTACHMENT I Section I Initial Contact Initial b. Pennsylvania State Police 9-234-4051 MESSAGE: This is at r _ Mile (name/ title) Island Nuclear Station Unit g. We have de n Alert at We (t'. (have/have not) D a radioactive r leas, e require assistance as lows: (State stance required.) Radiation Manageme t orporation (RMC) v y-Emerg 800-1700) 73- -243-2990 (1700-0800) 41-5141 (0800-17 5-243-2950 N at the Three Mile ( name/ tr+.Qp ' v Island Nuclear Station Unit I calling. We have declared an Alert at hours. (Give a brief (time) description of the emergency). We (nave /have not) had a radioactive release. I 21.0

1004.2 Revision 9 ATTACHENT I / Section I Initial Contact ~ ~ Initial d. American Nuclear Insurers 74-1-203-677-73 5 or 9-1-800-243 /3 3 (after n ng hours) Message: This is /> Three Mile (name/ti t1 e) I lear Station tic ling. We have d an Alert a x hours (Give a brief imM description of e ency). k ad a radioact e release. We m (have/ W) ( n@ ^ oW <N V W M v[J ON ~ = i \\ 22.0

1004.2 Revision 11 ATTACH!ENT I Section I Initial Contact ~ Initial ( 4. Nuclear Regulatory Commission (NRC) - Bethesda, MD. (Continuous comunications with the NRC will be main in llow-ing contact.) a. Telephone: NRC Emegency Notification S r. S) (RED PHONE) (If ENS Phone nopertative, refer erg ncy Plan Impl e-menting Pro e 04.6, " Additi Assistance Notifica- \\v ti o n", r ernate methods). \\ b. MES " E: NOTE: Complete tnis pted from i4URE - 45) before contacting the f this can be ithout ex-ceeding th hour notificati require-ment) ob infonnation fro he t Super. visor / Director. .. _ _ _ _........ _ _ ~ 1 Request toQs to the Duty Off g \\ l C R ) Duty *Qf i& s Name Time E'tntac 4 Thi s i s / at Three Mile Island Hame Titl e Nuclear Station, Unit 1. We have declared a(n) (select as l l j appropriate): i 50.72 (Non Emegency) General Emergency (1004.4) Unusual Event (100.4.1) Transportation x Al ert (1004.2) Physical Security; Safeguards Site Area Emergency (1004.3) Other Category l } 23.0

v 1004.2 Revision 11 ATTACHENT I Section I Initial Contact Initial at hours on Provide the stateme selected Time Date by the Shift Supervisor / Emergency Director to uty Officer. I 1. We have not had a radioactive rel OR 2. We radioactive re piq;s t do not expect this I si to result in d t tab e changes in offsite iation level s. 3. We have had di ive release but o know if there will tectable cha o te radiation levels will be keeping the, Bar.gu of Radiation Pr;2.c t. n nfomed of th hu of our investigation. 4. t yp had a radioactive se and expect to be able l to detect changes in offsite radiation levels but they will be less than the levels calling for a Site Emer-sncy. We expect the levels to be <50 mrem /hr (gamma) and child thyroid dose commitment to be <250 MREM /hr. We will be keeping the Bureau of Radiation Protection inf omed. 24.0

1004.2 Revision 11 ATTACHMENT I Section I ~ Initial Contact c. Give a short non-technical description of the emergency, the extent of the radioactive release, if any, and the tentially affected populations and areas, if appropriate. A AD EVENT TIME: Q h CAUSE: nT (tN ~ AW A% POWER PRIOR TO T: M PCWER NOW: ANY SAFETY INJECTION OR ECC bA \\ b, -s\\d COOLING MODE: ANY CONTAMINATION? (QUAN Y x v v ~ ANY RELEASES: (0UANTIFY): 25.0

1004.2 Revtsion 11 ATTACH!ENT I Section I ~ Initial Contact CONTADNENT STATUS (IF APPLICABLE): /\\ ANY OTHER PROBLEMS: A AU PLANS: C x M \\Vp/ DATE TIME OF L ON A \\\\ COMPLETED BY NOT E. If' the NRC Duty Of rects you to suspend con-inuous comuni n fonn the offi er a call back : will be initi ny significant nges occur. Document with icer. name, ti d date in the Emerg i tors Log. ________________A__ V p& Q l e l 26.0 l 1 I.

4 1004.2 Revision 11 ATTACHKNT I SECTION 11 iluTIFICATION LitELKLIST TlHE OF INITIAL NOTIFICATION TIME OF OR ESLALAT10il DE-ESCALATION OR CLOSE OUT a SITE

GE

UNUSUAL:

SITE

GENERAL :

Ul4 USUAL:hERT :

EHERGENCY : L :: EVENT : ALERT : EMERGENCY : EMERGEl4CY : EVEllT J, j AGElK.Y ( g..(::b

Dauphin County

//l l A Vg V

/

PEMA

/.. 4 (f @ MV

Unit 2 Control Room

{\\ : i l: -Na

IllP0

)

NRC 7A ::

.V /) M: / :: (/

liershey Medical Center ::

• C,*

(/

_T: Vf: d

State Police

• :\\>

/: 3 V : :, RMC V

• :(j

) A :: / A:

ANI b

B and W

ll/A : ll/A :

V: \\) - p

S Af fected Counties

N/A : ll/A :

N/A f_ A iff I

• Optional 27.0

1004.2 Revision 11 ATTACHMENT I Section III Secondary Contact Initial The Communicator shall notify the following agencies and pers nel and update the Attachment 1, Section 11 checklist for each noti ic io. I 1. Announce or have announced the following message ov p ant page ATTENTION after turning on whelen sirens " ATTENTION ALL PE t ALL PERSONNEL. The has besn tenninat (bi a brief de-scription of the wob ictions, if a Re eat message and 9 turn off whele s. 2. Burehu of Bei Protection a. Teleph Radiological L' orQ787-3720 b. MESSAGE: This is ha he Three Mile Is and N clear Station (name/t v Unit 1. We hive % sed out the Al at\\\\ hours and ,1 (time) initiated ecovery operations. Please notify PEMA, Dauuhin, Lancaster, York, Lebanon and Cumoerland counties. 3. Unaffected Control Room a. Telephone:8066, 8067, 8066 b. Message: Notify Shift Supervisor / Foreman of Close out of the Al ert. 4. Nuclear Reculatory Commission bffice - Bethesda, Md. a. Telephone: Emergency Notification System (ENS) (RED PHONE) 28.0

1004.2 Revision 11 ATTACHENT I Section III Secondary Contact Initial b. MESSAGE: This is _ at the Three Mile I N lear (name/titl e) Station Unit 1. We have closed out the hours and initiat ry operations 5. If applicabl 'f the following per and/or agencies of close ou f ert: a. rshey Medical Cep%r: 534-8333 (ask for DJty Nurse) b. P nnsylvania St e: 9-234-4051 Radiation Mb Corporation (RNC): c. ias (0800-1700 5-243-2990 1 '15-841-5141 ( 1 70 4 Office ( CfD 170 ) 73-1-215-243-2950 d. ic n Nuclear Insurers 203-677-7305 V e. Others - as directed by the Emen;ency Director. DATE TIME OF COMPLETION COMPLETED BY .w 29.0

1004.2 Revision 11 ALERT ATTACHMENT I SECTION IV PROTECTIVE ACTION RECOMMENDATION GUIDELINES THESE RECOMMENDATIONS MAY BE DEllVERED ONLY BY THE EMERGENCY DIRECTOR 1. Consideration shall be given to sheltering if: a. Release time is expected to be short (Puf f r 2 hours) and b, Evacuation cou ot be well underway ior W expected plume arrival due warning time igh w d speeds, and/or foul we 2. Consideration s 1 iven to evacuatio a. Ar se is expected t c ith projected doses approach-ing or exceeding: 1 Rem Whole nd or 5 Rem C id v asa b. Releas ti-expected to b ong ( >2 hours) and c. Evacuation can be well underway prior to plume arrival for above release, based upon wind speed and travel conditions. 30.0

1004.2 Revision 11 ATTACHMENT II EMERGENCY STATUS REPORT Section I ~ 1. Description of emergency: A o 2. Has the Reactor tripped Yes/No 4 -3. Did the Emergency Safegu Systems actuate Y o If so, which ones,, a. High Pr u njection YesXHb b. Low sswInjection /No c. Core od Yes/No d. 4 PSIG Reactor Buildi o tion Yes/No 4. What is the status ft --- J a. At power I b. Hot Sta i c. Hot Sh wn d. Cooling Down e. Reactor Pressure psig f. Reactor temperature

• F 31.0

10 04.2 Revision 11 ATTACHMENT II EMERGENCY STATUS REPORT Section I 5. Is offsNe power available Yes/No 6. Are both diesel generators operable Yes/No 7. Have any personnel injuries occurred Yes/No If so, is tha injured person (s) contaminate k/ a. U 1. What are the approximate radiation ntamination level s /hr 2 D o DPM/100 cm \\ 8. Are these excet91v ation levels ntamination Levels ~ Yes/No a. If so, List below: 1. Radiation Whole Body) A 2. Contami d io els DPM/ <W e--? at 1 tg ) m DATE TIME COMPLETED BY O l 32.0 ,---r. ..,_,.,_.,-,__y. ..m.

1004.2 Re'tision 11 ATTACHMENT II EMERGENCY STATUS REPORT Section II Fill out if a' release has (is) ocurring. Provide BRP all available infoma-tion for verification cali. 1. What is the approximate radioactive soun:e tem discharge r the plant ( As detennined by the Projected Dose Calculatio re (1004.7 ). ) a. Noble gases n Ci/sec v b. Iodine b 1/sec 2. What is the approx orology a. Wind spe h b. Wind dir on c. Stability Class-Stable /Ne table 3. What is the projected whole ose rate and iod conc trition at the nearest offsite dow n t v a. A.. b. /cc Iodine c. (Location) v 4. Estimated duration of the release a. If the release is teminated: Start time Stop time Duration b. If the release is still in progress: Start Time Estimated duration (hrs / min /sec) 33.0

10 04.2 Revision 11 ATTACliMEllT II EMERGEtiCY STATUS REPORT Section 11 Baked on projected dose rates, iodine concentration and duration or 5. a. estimated-duration (if still in progress) of the releas will the lower limits of the EPA Protective Action Guides be ce ce (i.e., 1 Rem Whole Body, 5 Rem Child Thyroid. Yes/flo b. If yes, estimate t o exceeding PAG: hbGrs m Date Time Completed Q Completed By v 34.0

1004.3 Revision 11 09/26/83 IW ORTANT TO SAFETY NON-ENVIRONMENTAL IMPACT RELATEL THREE MILE ISLANO NUCLEAR STATION UNIT NO.1 EMERGENCY PLAN IMPLEMENTING PROCEOURE 1004.3 SITE EMERGENCY Table of Effective P' ages Page Revision Page Revision Page Revision Page _ ision 1.0 9 31.0 9 v 2.0 9 32.0 9 3.0 9 33.0 9 4.0 9 34.0 9 5.0 9 35.0 9 6.0 9 36.0 7.0 9 8.0 9 9.0 9 Q 10.0 9 11.0 10 12.0 9 13.0 9 14.0 9 15.0 9 16.0 9 17.0 9 18.0 9 19.0 11 20.0 9 21.0 9 22.0 9 23.0 9 24.0 9 25.0 9 25.0 9 27.0 9 28.0 9 29.0 9 30.0 9 Y hW:_ 9b6l0 Date ./ gigriature 0 -/)A-Date Signature Document ID: 0025W c

1004.3 Revision 11 ATTACHMENT I SECTION I INITIAL CONTACT ~~ INITIAL 3. Unaffected Control Room a. Telephone: 8066, 8067, 8068 or inter Control Room tline. b. MESSAGE: Emergency organization staffing is reg s ut implementation of the Unit 2 Emergency Plan required. (Give a brief description of plant status Shift ~ Supervisor /Fo .) 4. Institute of Nucle ower Operations D v (Do not noti i t is is a reclas icah n notification). a. Tel -404-953-0904 ct the TMI Site operator for a stance by dial 0" b. MESSAGE: This is A at Three M Island Nuclear (nay tle) Station Unj .alling. 'ie have de'cbW.a Site Emergency a brief description of hourg at a v the emergpncy). 19.0 -. - _ _ -.}}