ML20073K792

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Public Version of Rev 3 to Procedures Manual 83-1,including Procedures EP I-0 Re Accident Classification Guide & EP I-1 Re Notification of Unusual/Significant Event
ML20073K792
Person / Time
Site: Salem  PSEG icon.png
Issue date: 01/20/1983
From:
Public Service Enterprise Group
To:
Shared Package
ML18087A855 List:
References
PROC-830120, NUDOCS 8304200471
Download: ML20073K792 (46)
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Text

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,, . EP I-0 ACCIDENT CLASSIFICATION GUIDE

_'N EP I-0 ,

PURPOSE The purpose of this procedure is to describe the Accident Classi- .

fication System and to delineate those actions necessary to '

properly identify an accident class by initiating conditions and associated observable plant parameters. Detailed emergency responses or " Action Stateme'nts" for each class of emergency are found in~ Procedure's EP I-1, EP I-2, EP I-3 and EP I-4. .

DESCRIPTION - ACCIDENT CLASSIFICATION GUIDE The Clas~sification G,uide is separated into four (4) basic modules.

They are:

1) RADIOLOGICAL - An actual release of radioactive material, abnormal radiation level, or indicated failure of a fission product boundary.

4

2) OPERATIONAL - Any- plant conditions, equipment failure or combination of the two (2) which could result in a ,

radiological incident.

3)' FIRE / NATURAL / SECURITY - Any fire, natural phenomena, or security event affecting the operability of structures or ,

equipment which could lead to a radiological incident.

1

4) MISCELLANEOUS - Any event not addressed in the Radiological, Operational, or Fire / Natural / Security modules which could lead to a radiological incident or require off-site

, notification.

i 8304200471 830415 PDR ADOCK 0500027 F Page 1 of 4. Rev. 3

e, #_

EP I-O' Each basic module is broken down into major event categories as submodules, illustrated on the " Accident Classification  !

Flowchart" ( Attachment No.1 of this procedure) . Each submodule is then further divided. The specific indicating conditions comprise the lef t hand column of'each page in the Classification Guide. The middle column in the Guide lists the observable plant-parameters of " Emergency Action Levels" (EAL's), the recognition of which requires entry into the appropriate accident classification (listed by Emergency Procedure) required for specific initiating conditions. ,

DESCRIPTION - ACCIDENT CLASSIFICATION FLOWCHART The Accident Classification Flowchart (Attachment No. 1 of this procedure) is a tool designed t6 assist the Senior Shift Supervisor / Shift ~ Technical Advisor /EDO in selecting the ,

appropriate portion of'the Accident Classification Guide when certain combinations of plant can'ditions may d.ictate selection of, or escalation to, a higher order of emergency classification.

US'E OF THE ACCIDENT CLASSIFICATION SYSTEM ThemechanismsbywhichEmergencyProceduresEPI-1throughEP I-4 are initially implemented are as follows:

1) An event occurs which causes initiation of a Plant Emergency Instruction which in turn refers to a specific part within the Accident Classification Guide.
2) Plant parameters which reach an EAL for an accident class in the Accident Classification Guide are observed by plant operators.

Page 2 of 4

+- .

e EP I-0 Upon recognition of conditions which require implementation of the Emergency Plan, the Control' Operators will notify the Senior Shift Superviso'r/ Shift Supervisor.

In the event that plant conditions degrade or additional abnormal plant conditions arise, the Senior shift Supervisor / Shift, Super-visor /EDO/STA may find additional assessment guidance by use of the Accident Classification Flowchart (although the Flowchart is not intended to replace the Accident Classification Guide) . The Flowchart can indicate, for certain combinations of plant conditions, which basic module in the guide contains the Initiating Conditions, EAL's, and applicable Emergency Procedure for the conditions present.

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Page 3 of 4 Rev. 3

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_ EP I-0 Prepared By: b.A.Aurge Reviewed By: k -N / cM 3 Departmen[ Head Date

' Reviewed By:_ /

Nuclear Emergency Planning Engineer -Date.

Reviewed By: ,4 Ab 4, [ /"2d -N '

Station Qdallty Agstff2gce Review Date (if required see EP VI-2)

SORC Meeting No.: b 3"OS E .

Date

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Approved By: /k / W //ob /d General Manager - Salem Operati.ons Date '

I npproved By: / g Manager - Nuclear Site Protection Date .

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~l ACCIDENT CLASSIFICATIOel GUIDE i .

EADlogsOGICALs An actual Selease of Radioactive material, abnormal radiation levele JDr indicated f ailure of a flee!On product boundary.

I INITI ATIssG CONDIT!oss SMsaG5ssCY ACTIost LEVELS ACCID 8st? CLASS e

3. Cassous effluent instantaneous release rate Technical specif1- A. Any of the following valid process monitor readings for longer than og

! cations limite exceeded for 1 hr. ( Appendia B Technical  ! br. which are, greater thans (se I-1)

[ fpecifscation 2,3.3).

, la-41Cs 4.355 cpm

. I D-4 5B s 8.354 cpm 23-41Cs 4.955 cpm . ,

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, 2D-418: 8.3E4 cpu j/ -

a confionation by grab sample and laboratory analysis sha!! be'made so,'

. soon as poselble. /

2. sustained !! quid release (greater than 15 min.) of radiological . A. Any of the following valid Bus process monitor readings for longer A .

l ef fluente greater than 10 times Technical specification instan- than 15 min, which are greater thans (sp !-2)

taseous !!alte and wh8ch le not immedittely controllable. I l l l 1p-41Cs 4.386 cpm or high off-scale lT4

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1R-41Bs 8.5E5 cpm 2R-41Cs 4.956 cpm or high off-scale h e

2p-41ss 0.385 cpm -

  • 3. Come rate at the minimum esclueton area equivalent to 500 ma/hr - A, Any of the following valid pasa process monitor readisig for longer than SAs M W.S. or 2500 mp/hr to the thyroid for 2 minutes. two minutes which are greater thans

.(EP I-3) .

18-4tCe 2.957 cpm

i. A. Based upon Gaseous Ef fluent Monitors and alte specific 5% worst la-elas 5. 086 . c pe, case meteorology.

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l j IB-43s 5.0E0 mR/hr t

29-41Cs 3. 4 E1 c pm ' .29-41Bs 5.8E6 cpm

! 8. Based upon containment radiation levels, design baste, leak 3.' valid radiation monitor reading as fo!! owes SAE rate and ette specific 58 worst case meteorology. (EP I-3) 1p-21s off-scale or, 2p-21: 3.1E5 mm/hr, i C. Emaed upon dose rate survey C. 3) Field team measures whol'e body dose rates greater than 54 mrom/hr SAs

! for 0.5 or areater t' en 500 mrom/hr for 2 min. at the usa. (Er I-3)

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2) Field team measures Thyroid dose rates (equivalent 3-131 concentrations) greater thans 250 mrom/hr (1.0E-7 uC1/cc) for 0.5 hr or 2500 mrom/hr (1.0E-6 uCl/cc) for 3 min. at the

, .A. .

i' D. Projected W.S./ Thyroid does using actual meteorology. D. As' indicated by dose calculation procedure EP IV-Ill, !!2, or !!3. .SAE (EP I-3)

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ACCIDENT CLASSIFICATIoel culpE pADIoLOGICALs An actual Delease of Radioactive material, abnormal radiation levels or indicated (silure of a fleelon product bounder /. .

INITIATING CONDITION ENERGENCY ACTION LEVELS ACCIDENT CLASS -

a 4. como rate at the minimum exclusion area equivalent to ap/hr  ;

W.a. or Sa/hr to the thyroid. ,

l A. sesed upon Gaseous Effluent Monitors and site specific St A. Any of the following valid mediation Monitor read $nge se followes GE worst came meteorology. (EP I-4) 1R-41Cs off-scale or ,15-418s off-scale or .

IB-43s 10mp/hr or . I 2p-41Ce off-scale or~~ '

8. Based upon contaipment radiation levels, design basis leak B. Valid Radiation Monitor reading as fo!!ows: GE rate and site specific 54 worst case meteorology. . . lEP I-4) t .

IR-21s off-scale c,r i 23-21s 7.5E5 mp/hr.

C. baeed upon dose rate survey. C. Pield survey team measures 1 3/hr. W.B. at the MEA or $ 3/hr Thyroid GE $

11-131 concentration of 2.05-6 uct/cc). (EP 3-4) ,

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D. Projected N.B./ Thyroid dose using actual meteorology.

D. As indicated by dose calculat!'on procedure EP IV-111, !!2, or !!3. GE (El I-4) -

5. asdiation levels or airborne contamination which indicate A. Increase in measured or calculated dose rates imp /hrt either insta!!ed A i e sovsre degradation in the control of radioactive materials or portable monitoring equipment by a factor of 1000 (EP I-2)  !

which results in an increase in measure or calculated dose rate imp /hr) by a factor of 1000 times, on

' 3. Unit 1 verification based on increase of analog strip chart reading over a 20 minute p4riod, on C. Unit 2 verification based on radiation monitoring computer trend.  ;

' 6. Liquid effluent concentration specification limite exceed for A. Any of the following valid radiation monitoring readings for longer than ut I 15 min. 15 minlutes which are greater thans (EP I-1) la-les 1.ps4 cpm or i 2a-18s 4.08E4 cpm][nd

3. Isolation valve fa!!s to close.

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talsA, e, C, os alarm and blowdown to 12 sGa tank in progrees or 2aleA, a, C, o, alarm and biowdown to 22 sGa tanh in progr... or

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  • l ..A ACCscEwT Ca.Assyr Cation c'u Ds ,

' aADIOLOGICAI.s An actual selease of Radioactive material, abnormal radiation levels or lad lcated fa!!ure of a fleelon product boundary.

j INIT}& TING CONDITIOg SMBaCENCY ACTI000 LEVEI.s ACCIDENT'CI. Ass .;

11. (continued) .

os Loss of 2 or 3 rianton product barriers with a potential loss of 3. toes of Primary coolant Inventory (sp 3 4) 3:4 barrier, (e.g., loss of primary coolant boundary, clad 1. Primary coolant leakage exceeds makeup capacity, low pressuriser level, fa!!ure and high potential for loss of containment). pressuriser level decreasing and Charging Pumpe' flow at maximum. /

i on l E al valid containment presure greater ,than 4.0 pois. ,

AND WAccumulator(s) discharge (while in mode 1, 2, or 3). *I' on .

1- . E Inadequate sub-cooling, as indicated by P-250 strip chart recorder or manual calculation and the plant in modes 1, 2, or 3.

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  • f E The following radiation monitor readings: l f

I al 1(2)a31 indicating 20s/hr or greater.

AND o ET Any 2 of 4 of the tottowing nois chann.a. of f-aca14 .

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/ al 2 of outContainment of 5 Fan Call 6

Unit Drainage preneure gregter Alarme than 4.0Mpele, tuate,/3 (2 Tor ipdication b) Containmen; sump' level greater than 31'3". There la indication

, of an in-containment steam line break.

C. Containment ratture (Actual or Likely)

1. Containment N3 concentration greater than 4%.
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  • 7' Indication of Containment pressure greater than (1 pelg and ,

increasing. (2/4) ,

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, E Either of the fo!!owings i

l a) There are lose than 5 Fan Co!! units available, with no 1 containment spray train capability, or b) There are less than 3 ran call units available, with only -

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W Indication of Containment' pressure greater than 23.5 psig and increasing. (2/4) l.:*

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ACCIDENT CLASSIFICATION GUIDS .

aioloLoGICALs An actual pelease of Radios,ctive material, abnormal radiation levels or indicated failure of a flesion product boundary.

INITIATING CONDITION ENEDGENCY ACTION LEVELS ACCIDENT CLASS -

$ 11. (Continued) . .

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Loss of 2 or 3 fission product barriers with a potential loss of OR -(se 3-4) 3rd barrier, (e.g., lose of primary coolant boundagy, clad .

failure and high potential for loss of containment). 4..Unisolatable steam line break outside containment with indications of a primary to secondary leak. ,

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l ---- 5. Containment penetration isolation valve (s) or hatch failure se determined by 500/S88 lVisual observation or high airborne activities around penetrat'lon or hatches).

12. Exceeding primary to secondary leak rate Technical Specifibetion. A. Primary to secondary leakage exceeding either of the fo!!owings us or primary system leak rate Technical Specification (EP I-1),

. 1) I gpm total leakage through all steam generators, or

2) 500 gallons' per day through any one steam generatoT om u E! neector coolant system leakage exceeding any of the fo11owing D ~

'3 -

Il No pressure boundary. leakage, 'or P 2) I gpa Unidentified Leakage, or ~

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3) 10 gpa dentified Laakage,, or * .'
4) 40 gpa ntrolled Leakage witE SCS at Normal Operating Prosaure
  • b 13. rs!!ure of a pressuriser Safety or pe!!st Valve to Deseat A. Pressuriser pressure less than 2200 pelg with POPS not armed oj; pg l 32 B. Pressurize,r pres,sure less than 375 peig with POPS armed. I"' I-II h pellet / safety valve ta!! pipe high temperature indication or .

D. Pressuriser Relief Tank level increasing.

14. espid gross fa!!ure of one Steam Generator tube with lose of A. Deactor Trip and Safety injection initiates on decreasing Pressuriser A offsite power. Pressure. (EP I-2) .

I Valid Radiation Monttor Alarme are received on channele 315 or DISA, .

n, C, or p.

AND .

E7'Pressuriser pressure (after inittal decrease) recovers to a pressure greater than secondary (main steam) pressure and (if required) steam line atmospheric discharges to control steam presurs.

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AhD II~Of fette pouer toes la indicated by Overhead Annunciator or meters on pane! SP6 or indication of the Control Console.

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ACCIDENT CLASSIFICATION GUIDE .

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. a*DIOtoGICALs An actual pelease of padioactive material, abnormal radiation levels or indicated failure of a fission product boundary.

INITIATING CONDITION ENEDGENCY ACTION LEVELS ACCIDENT CIASS

15. Espid failure of Steam Generator tubes (e.g., several hundred A. Reactor Trip and Safety injection initiate on decreasing Pressuriser UE gga primary to secondary leak rate). . Pressure.' (gP 3.lg

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3. Valid padiation Nonitor Alarms are received on Channels BIS or s!6A, .

3, C, or D.

1 AND CPressuriser Pressure f alle to recover to a pressure greater than

, Steam Generator Pressure.

I i 16. Steam !!ne break with significant (e'g., greater than 10 gym)

. A. Steam Line Isolation and Safety Injection initiated on High Steam

  • A I i primary to secondary leak rate. Line Flow with either Low Tavg or Low Steam Pressure and valid

( EP I-2) sediation Monitoring Alarme on Cnannels 815 or pl9A, B, C, or D.

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, C Safety Injection initiated on Steam Line High Differential Prosaure l

'O and valid Radiation leonitor Alarms on B15 or pl9A, B, C, or D.

On

, Q 17. Primary coolant leak rate greater than 50 gpe. A. In accordance with Tectmical Specification Section 3.4.6.2 Unit I or A ,

O 3.4.7.2 Unit 2 and one charging pump is unable to maintain pressuriser (EP I-2) 4 18. Known thee of Coolant Accident greater tbn makeup' pump A. Low pressuriser level with level decreasing and Charging Pumpe' flow SAE  !

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'M 19. 1!$id fa!!ure of Steam Generator tubes (several hundred gym A. Beactor Trip and Safety injection initiate on decreaalog Pressuriser SAE m leakage) with loss of of f ette power. Pressure, (BP I-3)

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s. valid Radiation leonitor Alarms are received on channeta 315 or 319A, 8 e, C, or D.

AND CPressuriser Pressure f alle to recover to a pressure greater than Steam .

Generator Pressure.

AND

. COf f site power loss le indicated by Overhead Annunciators and/or meters l 1

1 on Panet RP6 and on control console.

20. Etsaa Line break with greater than 50 gpm primary to secondary l

j leakage and indication of fuel damage. A. Steam Line* Isolation and Safety Injection initiated on High Steam Line SAE ,

i Plow with either Low Tavg or 1.ow Steam Pressure or, r (SP I-3)

5. Safety injection initiated on Steam Line High Differential Pressure.

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ACCIDENT CLASSIFICATION GUIDE .

aADIOLOGICALs An actual pelease of Radioactive material, abnormal radiation levels or indicated f ailure of a fission proddct boundary.

INITIATING CONDITION ENERGENCY ACTION LEVELS ACCIDENT CLASS

23. steam Line break with greater than 50 gpa primary to secondary AND I

leakage and indication of fuel damage (cont.). E!~ Valid padiation Nonitor Alarms on Channels BI5 or BISA, B, C, or D.

AND 57~ unit I letdown monitor 18314 in high alarm (off-scatel . .

Unit 2 letdown monitor 2831A in high alarm (off-acale)

AND '

E!~ Laboratory analysis which indicates an increase in f a!!ad fuel of 1 percent in 30 m8n. or a total fa!!ad fuel rate of 5 percent, fyr i Il Primary coolant sample indicates 3-131 concentration greatar than 300 uCl/cc.

21. Io.m of Containment Integrity resulting in a unit shutdown by A. In accordance with Technical specification section 3.6.1. UE Technical Specifications. ( EP I-l y . , ,
22. rust damage accident with release of radioactivity to contain. A. A valid alarm on the following Radiation Monitor A O ment or fuel handling building. *

(EP I-2) e 1) 1(2)p5s Alarm or 1 25 1(2)R9: Alarm 2GF 0 3) 1(2)R29s Alarm ~~~

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  • TT~la41as Alarm or *

) 51 3R41Cs Alare ~~

g 2E o B, 2 of the 4 conteinment pH4 poqltor il l(2)R2s Alarm ,

21 1(2)p7s Alarm 31 1(2)p10As Alarm

4) 1( 2) ains: Alarm
  • AND TT l(2) pals la/hr .

AND E!~ Verify fuel handling problem where damage to fuel May have occurred.

23. Ma jor damage to spent fue! In containment or fuel handling A. A valid alarm on the fo!!owing Radiation Nonitor SAS
  • building (e.g., object damages fuel or water lose below f uel (EP l-3) -

Itvell. Il !!2)p5s Alarm or

2) 1(2199: Alarm or
3) 1(2)p29s Alarm ~~

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E 2 of the 4 Containment pHS Monitor

\ Il 1(2)R2s Alarm

2) 1(2181: Alarm
  • 3T 1(2lR10As Alarm *
4) 1(2)pl0Ms Alarm . .

AND TT~llanaals !s/hr AND d 27 Confirmed fuel damage or loss of water level to below fuel level. q mn tt It F1 wC

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ACCIDENT CLASSIFICATION GUIDE

  • t OptcATIONALs Any abnormal plant conditions, equipment fattures, or combin'ation of the two which could result in a radiological incident. .

INITIATING CONDITION EMERGENCY ACTION LEVELS ACCIDOWT CLASS

- 1. Minual or automatic actuation of emergency core cooling systems A. Any limit in Technical Specification Table 3.3-3 and 3.3-4 exceeded or og with a discharge to the weseet. sanual initiation has been sade or (gp 3 3)

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B. Logic lights for any single or concidence initiation !!L on SP-4, defeguarde Statue Display.

AND \ .

C7~sst systsu Actuation is verified by control console indicatlod (flow, i valve positions, tank levels, etc.) for any of the following's I ,

1) safety injection
2) steam I.I ne teoTatton -)*
3) Containment spray .

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2. uncontrolled rapid ee.undary depresemurisation (Steam or A. gigh steam Flow or og feedwater line rupture). (Ep I-1)
3. Abnormal increase in feedwater flow to one or two atoom generatore 93 Any of the fo!!owings -

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  1. 8 '

!) Low steam generator pressure

2) Low T (average) ,

j , 3) peduced SCS pressure

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O 3. Failuse of a steam' Generator Safety or Atmospheric Belle'[ A, Visual and/or audible indica't1on at the vent stacks of the open valv's US pg valve to ressat, after pressure teetored to desired level. .(EP I-1) 03 /

i 45 II sacees feedwater! flow or gteseflow for the affected generator, f

4. Lose of Engineered safety Feature function requiring shutdown A, In accordance with Technical Specification Section 3.5 3 - UE by Technical spectitcation (because of malfunction, personnel (EP*I-))

stror or procedural inadequacy). * *

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1 ACCIDENT CLASSIFICATION GUIDE I f ortalTIONALs Any abnormal plant conditions, agulpment f ailures, or combination of the two which could result in a radiological incident, ki INITIATING CONDITIost ENEDGENCY ACTION LEVELS ACCIDSNT CLASS ;

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5. An event which requires initiation of unit shutdown to comply A. In accordance with Technical Specificatione. Use with Technical Specification Limiting conditions for Operation. ,(sp 3-1)

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6. Complete loss of any function needed for plant cold shutdown. A. Fallure of the pHB eystem to attain or maintain the primary system A I temperature has than 300*F. (gP I-2)- i g . .

. 3. Entry into Action Statement a. of Technical Specification 3.5.3 (Emergency Core Cooling System). -

7. Complete loss of any function needed for plant hot shutdown. A. Loss of Main and Aust11ary Feedwater. SAs (EP I-3)

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a. Imes of Steam pump system and all Steam Generator Power operated

, pollef Valves and Safety valves.

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S. Total loss of of f site power or toes of onette AC power capability.

A. Shutdown required in accordance with Technical Specification Section-3.8.1.1.a.

US (EP I-3)

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) 8 e B. Indication of the loss of 500 EV, 13 KV anJ 4 av group buses on the

!g control console, ap06 electrical display and lit overhead annunciatore (Section J and 5).

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c. seactor Trip on *soas of 4 sv croup muses * (overhead annunciator
  • F-26).

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p. Shutdown required in accordance with Technical Specification Section 3.8.1.1.b. f E

j 3, Indication of loss of 4 Ev vital muses on the control console and on -  ;.

overhead annunciatore (J-17, la, 19) with inability to energise those buses from the emergency diesel.a. .'

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orsaATIONALs Any abnormal plant conditione, equipment failures, or comb'ination of the two which could result in a radiological incident, INITIATING CONDITION . EMEDGENCY ACTION LEVELS . ACCIDENT CLASS ,

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3. Loss of offette power and loss of all onette AC power. A. Indication ci tha loss of 500 EV, 13 EV,'and 4 58 Group Buses on the A control console, RP-( electrical display and !!t overhead annunciatore (EP I-2)

( Sect ion J and 5 ) .

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3. Indication of loss of 4 EV Vital Buses on the ccntrol consolo and on the
  • overhead annuncletore (J-17, te,13) with inability to enereise those buses from the emergency diesels.
10. Loss of of fiste power and loss of a!! onette AC power for more A. Indication of the loss of 500 EV, 13 EV and 4 EV Group Buses on the SAE t han 15 minutes. control console, BP-5 electrical display and !!t overhead annunciatore (Er I-3)

(Section J and El for greater than 15 minutes.

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, - 3. Indication of loss of 4 EV Vital Duses on the control console and on 1

' overhead annunciatore (J-17, 18 ,.19) with inab!!!ty to energine those a

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buses from the emergency diesels for greater than 15 minates.

  • A. Loss of 500 EV, 13 EV and 4 EV Group Buses, Vital tuses ll l
11. Failure of of fette and onette power along with total lose of GE Auxillary Feedwater System capabi!!ty for several hours and (EP I-4) la projected core melt and f a!!ure of containment. AND e; 3. Inability to energise 4 EV vital Dueos from emergency diesel generatore h for greater than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

85E l C. Flow indication for Ausillary Feedwater system shove no flow for greater

, than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />,

12. Loss of a!! onelte DC power. A. Receipt of a!! the following valid overhead annunciator alarmes A A23, A38, A39, A46 and A47 (EPI-2)-
13. Lore of all onette DC power for more than 15 minutes. A. Deceipt of a!! of the following valid overhead annunciator alarmes

(EP I-3)

A23, All, A39, A46 and A47.

M j B. Inability to restore onette DC power within 15 minutte of the occurrence.

  • 14. Loss of all overhead annunciator alarme for more than 15 minutes A. As stated. A

, due to an unknown cause. (EP 1"3I

15. Loss of all overhead annunciator alarme for more than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and A. As stated. 888
a planed transient initiated or in progress. IEP I"3I

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ACCIDeast C1.aSStrICATION GUIDE OrtBATIONALs Any abnormal plant conditione, equipment failures, of Combination of the two which could reedtt in a radiological incident.

INITIATING CONDITION SNEDGENCY ACTIOef LEVELS ACCIDSelf CLASS ~ '

16. Failure of the Deactor Protection System to initiate and complete A. Deceipt of peactar Protection Logic input (see Technical Specification . A e trip which brings the reactor subcritical. Table 2.2-1) as displayed on panel RP-4. . (EP l-2)

AND e

3. Not a!! pod Bottom lights lit or Nuclear Instrumentation indicates reactor not subcritical.
17. Failure of the Beactor Protection System to automatically, or A. Deceipt of Reactor Protection 1.ogic (see Technical Specification SAR throuuh control operation action, manually initiate and complete Table 2.2-1) as on panel pr-4. (sP I-3).

e toip which brings and maintains the reactor subcritical.

! SEE .

+

3. All pod Bottom !!ghts not !!t or Nuclear Instrumentation indicates reactor not subcritical.

AND . .

f C. No boration capab!!!tles.

1 .

) IB. Evacuation of Control Doom anticipated or required with contro!" A. As Stated. 'A-of shutdown systema established from local stations. ~(EP I-2)

IS. Evacuation of Control Doom and control of shutdown systema not A. As Stated . SAE 3 estab!!ahed from local stations la 15 minutes. (BP I-3) e

23. Transient initiated by loss of Feedwater and Condensate Systems A.Deactortripon{owfeedwaterflows followed by failure of Auxiliary reedwater Systems for entended period and core melting poselble in several hours. AND
9. Decreasing wide-range steam generatoreg toward off-scale low on all steam generatoreg A!!D
c. 1) Aust!!ary feedwater flow indicators indicate seco flow 2 minutes after requireds g ,
2) Control Console indication of turbine and motor driven Auxiliary Feedwater pumpe indicates pumps not running 2 minutes af ter requireds i f $!!D
  • ir-
p. Ausiliary Feedwater cannot be restored within 30 minutes.
21. Transient requiring operation of shutdown systems with fa!!ure A. Beactor remains critical or returns to criticality af ter trip. CE I to scram which resulte incore damage or addstional failure of (EP I-43 core cooling and makeup systems (which could lead to core ment). AND .

C l) Flow indicators on safety injection systems and pWR systems show-sero flow with safety injection initiated or

2) Status lights show aafety injection systems and Deta pumps not running with safety injection initiated.

D I WM

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ACCIDENT CLASSIFICATION GUIDS .

Fic"/N ATUR A!/SECUkIT1 s Any fire, natural phenomena, or security event effecting the operab!!!ty of structures or equipment tahich could leak to a radiological incident. ,

INITIATING CONDITION BMEDGENCY ACTION LEVELS ACCIDEst? CLASS .

1. Fire lasting greater than 10 minutes that af fects plant opera- A. Observation of a fire lasting greater than 10 minutes that affects us tion (e.g., causes a reduction in power or a modo changel, plant operation. (sP I-1)
  • S.E -
3. Fire alarm received and confirming observation of a fire lasting greater than 10 minutes that af fects plant operation.
2. Fire potentia!!y affecting safety systems. A. Observations of a fire in one of the follouing areas potentially A affecting a safety systems (EP I-2)
1) Containment or~ .

I 2) Control Doom g *

3) pelay poem o_r, di Protection Backs or
5) Aust!!ary Buildin~g g J 6) Service Water Structure g e il Penetration Areas or -

1 8) Fuel Hand!!ng SuildIng 8 . _. .

Op

3. Observation of a fire that, in the judgment of th9 Senior shift

) Suervisor/rDO, could affect a safety system.

g

,3 3. Fire comprosteing the function of safety systems. A. Observation of h fire in one of the folloulag areas that has affected SAE a safety eyetens (EP I-3)

1) Ct tainment or

, 2) Control Boom 7r

! 3) Relay Roos o f *

4) Protection packs or

i il Penetration Areas or 81 Fuel Handling BullilTag SE B. Observation of a fire than, in judgment of the Senior Shif t supervisor /

EDO has affected a safety system.

j 4. Security Incident A. Substantiated Security Threat, attempted entry or A. Implementation of Security Procedures, section 5.3, event (51, (6) or (St. UE 1 attempted sabotage. (EP I-Il 4

b. Ongoing Security Compromise. 3. Oggoing security event, security Procedure, section 5.3, events (5), (6), 'A or (8). (EP I-2)

. e j d tD 9

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', 1 t-l ACCIDENT CLASSIFICATION GUIDS ,

FIRE /NATUDAL/SECupITYs Any fire, natural phenomena, or security event af fecting the operabil$ty of structures or equipment which could leak to a radiological incident. ,

INITIATING CONDITION EMEDGENCY ACTION LEVELS ACCIDENT CLASS

, 4. Security Incident (continued)

'C Ongoing Security compromise involving imminent loss of C. Ongoing Security event which may result in lose of phyelcal control of SAE l

physical control of the plant. .the plant (phyelcal attack w!Lh occupancy of the control Doom, hot (BP I-31 shutdown panel or vital areaal, security Proceduree, section 5.3, events (6) or (8). ,

D. Ongoing Security compromise r'esulting in the loss of physical D. Ongolog Security event which resulta in loss of physical control of the GE control of the plant. plant (physical attack with occupancy of the Control poon, hot shutdown (EP I-4) panel or other vital areas of the plant), Security procedures, section 5.3,

. events (6) or (8).

i '

5. Natural phenomena being emperienced or projected beyond usual evente. ,

A. Any earthquake felt in-plant or detected on station seismic instrumentation, A. Sethnic monitori q lastrumentation is activated (0,03g), se indicated by UE l 43

. DD all of the followsngs (EP I-1)

  • a W3 f8  !) seismic Monitor Alarm (overhead annunciator b43) actuatea $n Unit No. I control soon and b3 2) observation that'setemic monitoring is recording and O * '

' I* 3) verification of setemic distubance by call $ng the National Earthquake Information conter at (303) 234-3994.

l

0. Unusual flood or low water levels. 9. Tide level record r indicates 97.[ ft. (PSE6G DATUN) for flood, or $3.1 ft. UE  !

! (PSE6G DATUM) for low water. (EP I-1) I'

. e  !

C. Any tornado on site. , C. Tornado funnel observed within the minimum esclueton area. UB' D. Any hurricane or unusual wind conditione.

' . (EP l-1)

  • D. sustained winde in excess of to sph, as indicated by any *of the following U8 j Noteorological Instrumentations (8F I-1)
1) Nominal Elev. 33 ft. channel for wind speed or *
2) Nominal Elev. 150 ft. channel for wind speed or
3) Nominal slev. 300 ft. channel for wind speed ~~
6. Severe natural phenomena being emperienced or projected.

A. Earthquake greater than 033 levels. ), Seismic Monitoring Equipment (strip-chart) indlated (8.1g) or greater A and verification of a solemic disturbance by calling the Natural (EP I-2) i tarthquake information conter at (303) 234-3994, B. Flood or low water near design levels. 9. Tid's level recorder indicates 99.0 ft. (PSE&G DATUM) for floods, or *A

  • 81.0 ft. (PSt4G DAyDM) for low water. (EP I-2)

! C. Any tornado striking fact!!ty. C. Tornado funnel observed within'the Security Boundary. '

A

{*

!EP I-2) ,

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, 4

  • N i *
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, , ACCIDENT CLASSIFICATION GUIDE F133/ NATURAL /SECURITYs Any fire, natural phenomena, or security event af fecting the operab!!ity of attuctures or equipment which could leak to a radiological incident.

INITIATING CONDITIGd ENERGENCY ACTION LEVELS ACCIDENT CLASS-

6. Severe natural phenomena being esperienced or projected.

Icontinued)

! o. Any hurricane or unusual wind conditions. D. Sustained winds of 95 mph, as indicated by any of the following' A' Noteorological Instrumentations (EP l-3) 11 Elev. 33 f t. channel for wind speed or

2) Elev. 150 f t. channel for wind speed cr
3) Elev. 300 f t. channel for wind speed ~~

] 7. Severe natural phenomena being experienced or projected that- ,

. comptomises the functions of safety systone.

4 A. Earthquake greater than DDE levels. A. Setemic Monitoring Equipment (strip-chart) indicatee (0.2g) or SAE greater and verification of a Setemic Disturbance by calling the (EP I-3) pational Eart hquake Information conter at (303) 234-3994.

  • 13 '

De

5. Tide level recorder indicates 100.5 ft. (PSE6G DATUM) for flood, SAE or 74.4 f t. (PSE6G DATUN) for low water. (EP I-3) to C. Any tornado on ette ef fecting safety structures. C. Tornado funnel on site impacting the followings SAs g (EP I-3) o 1) Turbine building or

' rg 2) service Building or

3) Auxiliary Su!! dig or- .

La 4) Containment pu!! ding or '- *

5) Service Water Intake Efructure or~~"
6) RWST or PWST or AFWST or
7) Fuel Handling Building ~~

, D. Any hurricane or unusual wind conditione. D. Sustained winde in excess of 100 mph as indicated by !be followls.g SAE poteorological Instrumentations * (EP I-3) i i  !) Elevation 33 f t. wind speed or

l. - 2) Elevation 150 ft. wind speed [Br >

3). Elevation 300 ft. wind speed

+

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ACCIDENT Cl.ASSIFICATION GUIDE mISCt! LANtDUS s Any event not addressed in the radiological, operational, Or. fire /ascurity module which could lead to radiologlCal Incident or require offiste notificatlon.

INITIATING CONDITION ENEpGENCV ACTION LEVEE.S

, ACCIDENT CLASS

1. Aircraft crash Occurrings --

. A. Near site ut A. Aircraft crash one of the 500within the minimum EV transmission exclualon area or a crash effecting /,

lines. (EP I-1)

/

3. On Site . B. Aircraft crash within the security boundary. / A C. Onsite affecting plant structures lEP I-2) 1 C. Aircraft crash causing damage or fire ins / SAR 1

( EP I-3),

t , il Turbine muilding or N l

4 21 Service Building or

3) Auxiliary su!! ding ~or

, . 4) Containment Sullding ol *

5) service Water Intake Structure or~

GI BWST or PWST or AFWST or

7) Fuel Handling building ~

t 'O g 2. Onette Tomic Flammable Gasees -

lC@ A. A release which threatene onette personnel.

A. Observation of a release or warning f rom off elte.

~

' UE (EP I-1)-

3. A release which enters vital areas. 5. Observation or measurment of gases which exceed flammability or A O toulcity 1 vels 9 after entering the Control poom g Aus!!!ary Du!! ding , (EP I-2) ventilation system, m -

g C. A release uhich enters vital areas compromising the f' unctions C, Detonetton or cqabustion of 4 flammable gas $n one of the areas actually SAE' of safety systems. affecting a safety system. (EP I-3) ,

1) Containment g
2) Control poon or
3) b lay poon or ~ ' *
4) Protection Facks or -
5) Auxiliary su!! ding g
6) Penetration Areas or
7) service Water IntaFe Structure or~
8) Fuel Hand!!ng Building
3. Turbine generator failure causing an outer casing penetration. A. Turbine trip and observation of penetrations througli the outer caelag. 'uB
4. Missile impact onsite resulting in structural damage. (EP I-1)

A. Observation of an impact causing severe structural damage to a building A within the security boundary, IBF I-2) tJ f m .ed -

4 -N.

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ACCIDENT Cl.ASSIFICATIDIS CUIDE g!!CELLANEOUSs Any event not addressed in the radiological, operat!Onel, or fire / security module which Could lead to radtplogical incident or require offiste notification.

e INITIATING CONDITION EMEEGENCY ACTION LEVELS ACCIDEst? CLASS

5. Missile impact onsite resulting in damage to a vital structure. A. Observation of an impact causing structural damage to the followlege SAE (EP I-3) j 1) Turbine Building or
2) Service Du!! ding or
3) Auxiliary Buildin~g or
4) Containment Building g
5) Service water Intake Structure or~ .

El BWST or PWST or AFWST or~ .

7) Fuel Hand!!ng Building ,
6. Emplosion within'the security boundary excluding planned activities.

A. An emplosion which affects plant operations (e.g., causes A. Observation of an emplosion or its consequences, UE .

a reduction in power or mode). IEP I-1) 80 h. An emplosion which potentia!!y affects a safety system. R. An emplosion in one of the following areas potentially affecting a &

De safety system. (EP I-2)

! (O .

i O Il contalonent or

  • 2) Control poom or M 3) islay poom g~ ,
4) Protection Backs or  ?

' O 5) Ausillary sullding or

6) Penetration Areas oF
  • ta 71 service Watef inta E Structure C. An explosion compromising the functions of safety systems. C, An emplosion in one of the follouing areas that has affected a safety SAE system. (EP I-3)
1) Containment or
2) Control poom or *
3) pelay poon or~

i .

4) Protection lacks or *
5) Auxiliary Buildin~g g .

i

6) Penetration Areas or h,s .W 7) Service Water Inta E Structure or~~
4) ruel Hand!!ng pullding
7. Other Plant conditions exist that warrant increased awareness on A, As judged by the Senior shift Supervisor /EDO, UE the part of State and local of fette authorities. (EP 3-13

\ .

3. Other Plant conditions estet that warrant precautionary A. As judged by the Senior Shif t Supervisor /EDO. A activation of Technical Support Center. IEP I-2) e i

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I ACCIDENT CLASSIPICATION GulDs - ,

gISCELLANEOUSs Any event not addressed in the radiological, operational, or fire / security module which could lead to radiological thcident or require offlete notification. .

INITIATING CONDITION *

- BNERGENCY ACTION LEVELS ACCIDENT CLASS

9. Other Plant conditions estet that warrant precautionary A. As judged by the Senior Shif t Supervisor /EDO. SAs

operations Pacility and/or notification to the general puh!!c.

10. Any serioust ninjured and contaminated person requiring'off-site A. As judged by the Senior Shift Supervisor /EDO. us medical treatment and off-site decontamination. (gP I.1)

II. Any of the following iteme which require notification l'n ,

accordance with letters of agreement. ,

A. Any unit startup or a unit trip (planned / unplanned) from A. As judged by the Senior Shift Supervisor /EDO. UE .

greater than 20% turbine power. (EP I-1) *

s. Any event requiring a press release be prepared. B.!As judged by the Public Affaire Nanager - Nuclear /Daalgnee us (EP I-1)
c. Unusually large fish kills, large movement of equips'nt e or
  • C. As judged by the Senior shif t Supervisor /EDO. UE gy personnel which could slanificantly affect local traffic (EP I-il Di P*""*'"' -
  • 10

'g D. Significant increase in noise levels stream release on site p. As judged by the Senior Shif t Supervisor /EDO, UE alarm or strena which might be heard off-site. (EP I-1) 06

5. Durating caused by a regulatory action. E. As stated. DE O (sr ;-1) th

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EP I ( , EMERGENC

Y. PROCEDURE

EP I-l

, NOTIFICATION OF UNUSUAL EVENT /SIGNIFICANT EVENT ACTION STATEMENTS - SECTION I'- EMERGENCY COORDINATOR Initials l

. The Senior shif t Supervisor shall:

l.. Determine classification of the event to be an Un, usual ,

Event as defined by EP I-0; cg a Significant Event as defined by Attachment 4 of, this procedure.

.EP I-0 Part , No. .

and/or Significant Event No.

2. Assume the responsibilities of the Emergency Coordinator.

(see page 4 for responsibilities)

~

3. Fill in data on the Initial Contact Message-Form (Figure
8) - Attachment 2 to this procedure. .
4. Direct that the Station Status Check List-(Figure 9) -

Attachment 3 to this' procedure be completed (to' the .

. extent possible at this time) and,given to the Des.ignated' Communicator.

l l

5. Direct the Designated Communicator to make notifications of Attachment 1 to this procedure within the time limits listed and maintain communications with the NRC Operations '

Center when directed to do so by the NRC duty off'icer.

6. Direct the communicator to respond to calls from State or local officials by providing the information on the Station Statu's Check List or Press Release received from

> the Public Affairs Manager - Nuclear and have the name and

affiliation of the person calling recorded on the Station Status Checklist.

1 of 13 Rev. 3

. s EP I-11 ACTION STATEMENTS *

7. Direct the Communica' tor to ref r Yequests for information from other agencies to the Public Affairs -Manager -
Nuclear.
8. Refer to EP I-7, " Station Fire," to conduct fire fighting actions. If.outside assistance is required, have the Salem Fire Di'spatcher called. Give the location,; type of fire, and where vehicles will be met by. Security personnel to communicator. .
9. If this is a security event, coordinate with the Security

' Lieutenant to implement the Contingency Plan and Procedures.

10. Transfer the Emergency Coordinator responsibilities to the Emergency Duty Officer, when available.

" 11. Forward all completed forms to the Senior Operating Supervisor. Attach any other completed EP's'or attach-ments used.

ACTION STATEMENTS M SECTION II'- COM'UNICATO'R M . .

The Designated Communicator shall:

1. When directed by the Senior Shift Supervisor /EDO;use the

. data provided on the Initial Contact Message Form to .

notify persons listed on the Communications Log within the time limits specified on Attachment 1. -

2. Upon receipt of a phone call from the New Jersey Bureau of Radiation Protection (BRP) or Delaware Division of Emergency Planning and Operations (DEPO) do the following:

^

a) Provide the Station Status Checklist (Figure 9) -

Attachment 2 to this procedure - at current level of completion. ,

2 of 13 Rev. 3

~

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?

EP I-l

3. When d.irected'by the Senior Shift Supervisor /EDO cbntact the Salem Fire Dispatcher and provide the following message':

a) This is the Communicator at Salem Generating Station. This is a nctification of a fire.

b) We request fire 1 company support.-

c) The type of fire is .

d) The lo' cation of the fire is .

'e) The fire truck (s) will be met at and directed to- the location of the- fire by our-

~

~ security force. .

Notify security (ext. o5 locatidn where fire truck (s) should be met and type of fire.

~

ACTION LEVEL '

,Whenever an action level listed in EP I-0 as an Unusual Event has been reache,d, notification of an Unusua.l' Event will. be made to.

offsite authorities and'de'signated personne'1.-within the time 1 1

limits listed in Attachment 1.

1 i Whenever an action level described as a Significant Event

( Attachment 4 ) is reached, notification of a Significant Event will be made to offsite authorities and designated personnel l ,

within the time limits listed in Attachment,1.

NOTE -

Notification shall be reperformed for additional events, as de. fined in EP I-0 or Attachment 4 to this procedure.

An Event which satisfies both the definition of an Unusual Event and a S'ignificant Event shall be classified as an Unusual Event.

3oh13 Rev. 3 1 . . _ , . .- - . - - _ _ .

EP I-l

~

~

LIMITS ON AUTHORITY The person acting as the Emergency Coordinator (Senior Shif t Supervisor, Eme'rgency Duty Of ficer, ' or Emergency Response Manager) has the authority and responsibility to immediately and unilaterally initiate any emergency action including the decision to notify and provide protective action recommendations to authorities responsible for implementing off site emergency measures.

ATTACHMENTS Attachment 1 - Communications Log (Figure 7)

Attachment 2 - Initial Contact Message Form (Figure 8 ) ,

Attachment 3 - Station Status Checklist (Figure 9)

Attachment 4 - Significant Event Classification l .

e.

l I

i l 4 of 13 Rev. 3 i

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, . r - .

x EP I-l

, Signature Page Prepared By: C. rBirrge

_ )

Reviewed By: -

W /hlh!I-Departmen ead Date Reviewed By: /L 2----

/ Nuclear Emergency Planning Engineer' Date

/!6 !S 3 Reviewed By: A-Station Quality Assurance Review ' Date (if required see EP VI-2)

. I 1

SORC Meeting Number: D -03 l 11 33 Date' Approved By: . 4[ / // '/!

General Managdr - Salem Operations Date Approved By:

/

?

)

Manager - Nuclear Site Protection Date I

l- . . .

5 o f 13 Rev. 3

s TIME REQUIRED FOR ') -

LIMIT EVENT CLASS ' PERSON TO BE PERSON DATE/ , CONTACTED IN .

, . CONTACTED CONTACTED TIME BY ,

(HINUTES) UE/SE A SAE CE e

15 YES YES YES YES Primary: [EDO(Contactnae) .

. L. Pry . , Office: Ca r Beeper llome J. Cueller . Office: Car: NA; '-

.. .. Beeper: Homes i e e e o I * ,

15 YES YES YES YES Secondary: TSS (Contact One)'

L. Hiller Office: Car N., . -

Beeper

  • llome , \ n -

N,\

  • L. Catalfomo Office: Car - NA;- o Beeper: . 1[ome : ' x $>

cH cn ,y o$ 15\ YES YES YES YES NEW JERSEY m

  • NN

'* Q Primary: .' f ,

OS

[oq Secondary: -

yy OZ 15 YES YES YES YES DELAWARE j 5d" Primary p Secondary: o -

  • O 15 NO NO NO YE3 Salem County Primary: (Direct Line)

Secondary :'i- 'N. .

15 NO NO NO YES Cumberland County Primary: (Direct Line)

I Secondary: 'N '

15 NO NO NO YES New Castle Chunty .

I

  • Primary: (Direct Line) .k-
  • Secondary:7'~~~ ' ' - ~ .

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$ 'ji g 15 NO NO NO YES Kent County .

< 1 Primary: (Direct Line) {-

  • ~~'

Secondary: ' -- so

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D, 15 NO NO NO YES U. S. Coast Guard * .

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A oererer rerer L C n t : ;

NT C cecece (i pi pi p ecece gi pi p t s i

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rt 4 s P cl i i l S D e ran umo reo u pi nan omo Tan mo anr moo C R ou NS nl . .A . V b . cic con cic Cic Cic R . .

ea1 1 J(R( u . . ere eHU ere SPS Are LPS R re NPS NLB CS PR W SPS S S S S S S S

'S S E E E E E E E E E C Y Y Y Y Y Y Y Y S S S S S S R E S S E OS A E E E E E E E S Y Y Y Y Y Y Y . Y FS A S S S DL S S S S S E E E E E E E EC A E .

Y Y Y , Y Y R Y . Y Y I T UN QE E S S S EV S S S S E E O E O E E RE / E N Y N Y Y Y E Y ' ' Y U

)

S T E EI T 0 0 0 0 MMNU 0 0 0 0 I I I N 3 3 3 6 6 6 6 6

TL I H  ;'

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I TIME { HEQUIRED FOR 1.IMIT. EVENT CLASS . PERSON TO BE -

PERSON -DATE/ CONTACTED ,

IN -

CONTACTED ,

, CONTACTED TIME ' BY (HINUTES) UE/SE A SAE GE -

90 YES YES YES YES New Jersey DOF ,

Primary: ,

Secondary: See Addendum 1 . ,

. C 90 YES YES YES YES New Jersey BPU Primary:

Se const a- " -

90 NO YES YES YES American Nuclear Insurers Primary:

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. o I_1 Attachment 2' ATTACHMENT 2

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INITIAL CONTACT MESSAGE FORM JIRECTIONS FOR COMMUNICATOR Upon completion of the below prepared message the Emergency Coordinator or the Designated Communicator shall make the* required notifications using Attachment I to this procedure.

NOTE: In the event.of a test, drill or exercise, preface and complete each message with the phrase'"THIS IS A DRILL, THIS IS A DRILL".

SECTION I (Provide to all)

THIS IS ,

(NAME) (TITLE)

SALEM NUCLEAR GENERATING STATION, UNIT NO.

THIS IS A NOTIFICATION OF:

a SIGNIFICANT EVENT -

an UNUSUAL EVENT a SITE AREA EMERGENCT an ALERT a GENERAL EMERGENCT lHIS EVENT OCCURRED AT ON (TIME - 24 HOUR CLOCK) (DATE) .

[ THERE IS NO RELEASE IN PROGRESS.

[ WE HAVE A. NORMAL RELEASE IN PROGRESS.

~

[ WE HAVE AN UNCONTROLLED RE. EASE IN PROGRESS. ,

SECTION II (Provide to New Jersey and Delaware Only)

NO PROTECTIVE ACTIONS ARE RECOMMENDED AT THIS TLME WE RECOMMEND SHELTERING

~

FOR THE FOLLOWING SECTOR (S) /

(Distance-Miles)

WE RECOMMEND EVACUATION FOR THE FOLLOWING SECTOR (S)

/

(Distance-Miles)

SECTION III (Provide to PSE&G personnel only)

DESCRIPTION OF EVENT Use back of sheet if necessary.

(Figure 8) 9 of 13

w e

. . EP I-l Attachm3nt-3 ATTACHMENT 3 STATION STATUS CHECK LIST

- Salem Generating Station Unit No.

Transmitted By_:,Name ,

Position:

l. Date and Time of Incident: Date Time (24 hr clock) 2.' Accident Classification: b ) Significant Event b) Unusual Event b Alert b Site Area Emergency b General Emergency
3. Cause of Incident:

Primary Initiating Condition used for declaration of incident EPI-0 Part , Number and/or -

Significant Event No. ,

Descriptio,,n of the incident i

4. ' Status of Reactor: b) Tripped b) At Power b ) Hot Shutdown E5) Cold Shutdown
5. Pressurizer Pressure psig , Core Exit TC 'F

'6. Is offsite power available? b) YES 'b) NO -

7. Are two or more diesel generators operable? b) YES b) NO
13. ~Did the emergency safeguards system activate? b)' ~YES b I NO

~

.9. Has the containment been isolated?(5) YES b) NO

10. Other pertinent information l

l (Figure 9) 10 of 13 Rev. 3 l

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EP I-l Attachment 3 1

Station Status Checklist - Radiological Information - -

11. Gaseo'us Release: b YES b NO. -

)

(A) Release Terminated: b yrs bNO (B) Anticipated or Known Duration of- Release Hours (C). Type of Release: .b GROUND b ELEVATED

-(D) Wind Speed: MPH Wind Direction: (Toward)_

_'~~ ' Divide by 2 to get M/Sec ' (From)

Delta Temp: (Compass Points)

(E) Stability Class: b Unstable b Neutral b S.eable (F) Release Rate' Iodine Ci/Se c.

(G) Release Rate Noble Gas: Ci/Sec.

12. Liquid Release: b YES b NO (A) Release Terminated: b YES b NO (B) Anticipated or Known Duration af Release Hours

- (C) Estimated Concentration .. pico Curies / Liter

('

(D) Release Rate Liters / Hour

13. Projected Off-site Dose Rates (As Soon As' Data Is Available):

Adult -

Distance- (miles) Whole. Body -(mrem /hr) . Child Thyroid (mrem /hr)'

14. 15 minute updates to' States: ~

Time Initials State of New Jersey State of Delaware ..

i b Others ~

Name

~

. Agency .

Name s

Agency (Figure 9) 11 of 13 Rev. 3

. . ~

.. .c.

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  • - EP I-l Attachment 4 ATTACHMENT ~4 SIGNIFICANT EVENT CLASSIFICATION .

DIRECTIONS The Emergency Coordinator shall review the initiating conditions listed below to-determine.if significant event notification is required.

Notification shall be made as indicated in Attachment 1 to this procedure.

-SIGNIFICANT EVENT INITIATING CONDITIONS

1. Any event r.equiring initiating any As evaluated by the section(s) of the Station Emergency Emergency Coordinator Plan Procedures, except for EP I-5, for injuries requiring less than 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> hospital stay. _ -
2. Any accidental, unplanne~d, or uncontrolled As evaluated by the radioactive release. (Normal or expected Emergency Coordinator releases from maintenance or other opera- and the Radiation tional activities are not included.) Protection Engineer.

~

3. Any serious personnel radioactive contam- .As evaluated'by the ination requiring extensive onsite'decon- Emergency Coordinator tamination or outside assistance. and the Radiation Protection Engineer.
4. Any event that results in the plant not Aa. evaluated by the being in a controlled.or expected con- Emergency Coordinator.

dition (Mode 1-6).

'5.-Union strikes affecting the availability As evaluated by the

. of operating personnel or the security Emergency Coordinator, personnel.

6. Any serious or fatal injury occurring on As evaluated by~the

- site and requiring off-site medical Emergency coord'inator.

, assistance (hospital stay greater than - -

48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />).

7. Any event involving nuclear material which As evaluated by thE has or may have: Emergency Coordinator and the Radiation a) Exposure of the whole body to 25 rems Protection Engineer or more; exposure of the skin of the whole body of 150 rems.or more; or exposure of the feet, ankles, hands or _.

forearms to 375 rems or more.

l s

_ 12 o f ' 13__ _ . _ _ _ _ _ __ Re_v. _1_

'EP I-l s . . Attachment 4 ATTACHMENT 4 SIGNIFICANT EVENT CLASSIFICATION b) The release of radioactive material in concentrations which, if averaged over a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, would exceed 5,000 times the limits specified for such materials in Appendix B, Table II of 10CFR20.

c) A loss of one working week or more of the operation of any facilities affected.

d) Damage to property in excess of $200,000.

8. Any event involving nuclear material which As evaluated by the has or may have: Emergency Coordinator and the Radiation

, , Protection Engineer.

a) Exposure of the whole body to 5 rems or more; exposure of the skin of the whole body to 30 rems or more; or exposure of' the feet, ankles, hands, or forearms to 75 rems or more.

b) The release of. radioactive material in concentrations which, if averaged over a peri.od of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, would exceed 500 times the limits specified for such materials in Appendix B, Table II of 10CFR20.

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TIME REQUIRED FOR '

LIMIT EVENT CLASS - PERSON TO BE l PERSON. DATE/ CONTACTED +

IN ' CONTACTED CONTACTED TIME BY. J (HINUTES) UE/SE A SAE CE ,

'~-

i 15 YES YES YES YES Primary: -

EDO (Contact One)f

  • 1 L. Fry ,

Office:' Ca r t .

Beeper llome '

, J. Cueller Office: Car Beeper: lione 15 YES YES YES YES Secondary: TSS (Contact One) ,

a L. Miller Office: Ca r t -

Beeper llome L. Catalfomo Office:- Cars ' NA.

{ Beepers,.  ; lione r ,

n 15 YES YES YES YES NEW JERSEY -

O.

y Primary:- (Direct Line) .g ,

g Secondary: x _ z ro . , 'n

,g 15 YES YES YES YES DELAWARE Primary:

~$

(NAWAS)' , H .

'O m Secondary: 0;  ;. , O

w .

1 s 15 NO NO NO YES Salem County, &

I Primary: (Direct Line) 8 Secondary:

15 NO NO NO YES Cumberland. County.

Primary: (Dire'ct Line) .

Secondary: .

15 NO NO NO YES New Castle County * '

i j Primary: (Direct Line) i Secondary - ..

4: m to .

W 'O 15 NO NO NO YES Kent County , ,j,.

, Primary: (Direct Line) .

et  :

Secondary: #

,> a 15 NO NO NO YES U. S. Coast anard i ' .;,; Primary: ', '

ji~ .

~

TIME REQUIRED FOR . , {

LIMIT EVENT CLASS - ' PERSON TO BE PERSON DA E/ CONTACTED

  • CONTACTED- CONTACTED TI) BY*

IN ~

(HINUTES) UE/SE A SAE CE .

30 YES YES YES YES Ceneral. Manager - .

Salem Operations (Contact One) . .

11.. Midura Office:- .

. Beepers. Ilone I

'J,. Driscoll Office:  : .

(Asst. CM)' . Beeper: , llome: ,

. R. A. Uderitz Office: Car:

(VP - Nuclear) Beeper: -N/Al lione [ .

~

YES YES YES Public Affairs Manager-Noc1' ear (Contact One) /

30 YES R. Silverio. Offices Cart,NAt ,

Q Beeper: lione r - ,

, _c W. Denman Offices _  ; Car -NA': / d j ,

Beeper NA: lione_: j ,

Z 0

, .o -

ljj 30 NO YES YES YES Security'-Site (Shift Lieutenant) k -

o' Primary: ,y Secondary: . z-9 us

'o

  • F

' rw 60 YES YES YES YES Security-llope Creek llope Creek Project b iw i I Union Security ,-

60 NO YES YES YES Second Sun yisitor's Center Primary: ,

Secondary . - <

I I 60 I YES'- YES YES LAC Township .

i

' YEf

Primary: (Direct Line) -
  • Secondary: ,

60 YES YES YES YES NRC ,

l ,

Primary: . (ENS) ,.

's tg Secondary:

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or - o

'~ _ _ _

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60 YES YES YE$ YES NRC Resident (Contact One). '-~

' L. Norrholm - Officer; Home 4 .

b. Summer -e Office:' one s ; f.

. - _ - _ _ _ f__ i

- ~

TIME REQUIRED FOR LlHIT EVENT CLASS. PERSON TO BE ,

PERSON DATE/ CONTACTED ,

IN . CONTACTED CONTACTED TIME BY , . .

(MINUTES) UE/SE A SAE CE , e 90 YES YES YES YES New Jersey DOR .

Primary: ,, .p' .

Secondary: See AadEndum 1 90 YES YES YES YES New Jersey BPU Primary:

Secondary: .

90 NO YES YES YES American Nuclear Insurers

  • Primary: ,

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INITIAL CONTACT MESSAGE FORM -

n IIRECTIONS FOR COMMUNICATOR Upon completion of the below prepared message the Emergency Coordinator or the Designatad Communicator shall make the required notifications using Attachment 1 to this procedure. \s NOTE: In the event of a test, drill or exercise, preface and complete each message with the phrase "THIS IS A DRILL, THIS IS A DRILL"..

  • SECTION I (Provide to all)

THIS IS ,

(NAME) (TITLE)

SALEM NUCLEAR GENERATING STATION, UNIT NO.

THISISANOTIFICATI5NOF:

a SIGNIFICANT EVENT.

a SITE AREA EMERGENCY

] an UNUSUAL EVENT an ALERT

] a GENERAL EMERGENCY

'HIS EVENT OCCURRED AT ON (TIME ,24 HOUR CLOCK) (DATE)

O razar Is no artrisz In PaoGazss-

.~ E W HAVE A N,0RMAL R$ LEASE IN PROGRESS. -

WE HAVE AN UNCONTROLLED RELEASE IN PROGRESS.

SECTION II (Provide to'New Jersey and Delaware Only)

NO PROTECTIVE ACTIONS ARE RECOMMENDED AT THIS TIME WE RECOMMEND SHELTERING FOR THE FOLLOWING SECTOR (S) /

(Distance-Miles)

] WE RECOMMEND EVACUATION FOR THE FOLLOWING SECTOR (S) /

, (Distance-Miles)

SECTION III (Provide to PSE&G personnel only)

DESCRIPTION OF EVENT Use back of sheet if necessary.

t Page 1 of 1 l .

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,' . E P.. , -

Figuro 9 STATION STATUS CHECK LIST w

.~ Salem Generating Station Unit No.

Transmitted By: Name Position:

1. Date and Time of Incident: Date Time (24 hr clock)
2. Accident Classification: b Significant'Even't b ' Unusual Event Alert b Site Area Emergency. O General Emergency
3. Cause of Incident:

Primary Initiating Condition used for declaration of incident EPI-0 Part , Number and/or

, Significant Event No. .

Description _of the. incident

4. Status of Reactor: b Tripped b At Power b Hot Shutdown U -Cold shutdown
5. Pressurizer Pressure psig Core Exit TC 'F
6. Is offsite power available? b YES O NO
7. Are two or more diesel generatiors operable? - YES O NO .
8. Did the emergency safeguards system ac'tivate? O YES U NO ' '
9. Has the containment been isolated? b YES b NO -
10. Other pertinent information 7-i _

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Page 1 of 2 Rev. 3 l

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. EP' w Figure 9-Station Status Checklist - Radiolo'gical Information-b NO

11. Gaseous'; Release:: b YES  ;

(A) Release Terminated: O YES bNO'

  • - (B). Anticipated or Known Duration'of Release Hours (C) Type of Release: b . GROUND ELEVATED-(D) Wind Speed: MPH Wind' Direction: (Toward)
  • Divide by 2 to.get M/Sec (From)

Delta Temp: (Compass Points-)

(E) Stability Class:

Unstable b Neutral' Stable (F) Release Rate Iodine Ci/Sec. .

(G) Release Rate, Noble Gas: Ci/Sec.

12. Liquid Release: b- YES O NO

'(A) Release Terminated: b YE3 b NO (B) Anticipated or- Known Duration of Release Hours

.(C). Estimated Concentration pico Curies / Liter i

). -

(D) Relea.se Rate Liters / Hour

13. Projected Off-site Dose Ra'tes (As Soon As Data It Available):

. . Adult Distance (miles). Whole Body (mrem /hr) Child Thyroid. (mrem /hr)

14. 15 minute updates .to States: Time Initials C State of New Jersey State of Delaware ..

1 Others Name Agency

.. Name Agency Page'2 of 2 Rev. 3

4- ,

-6 No. 101

.U.S. NRC, Dir. of NRR

+

  • Washington, D.C. 20555 Mr. S. A. Varga , Chief, Ope r. .

.m, Reactors BR#1, Div. of Licensing SALEM GENERATING STATION EMERGENCY PLAN EMERGENCY PLAN PROCEDURES INDEX JANUARY 20, 1983 SECTION I - ON-SITE PROCEDURES -

RE7. MO.

EP I-0 Accident Classification Guide . . . . . . . . . . . . . . . . . . . . ~ . . - 3 Part 1 Radiological

  • Part 2 Operational Part 3 Fire / Natural / Security Part 4 Miscellaneous Flow Chart . . . . . . . . . . . ...................'.- 0 EP I-1 Notification of Unusual Event /Significant Event . ............ I EP I-2 Alert . . . . . . . . . . . . . . . . . .

................. 2 EP,I-3 Site Area Emergency . .. . . . . . . . . ................. 2

, EP I-4 General Emergency . . . . . . . '. . . . . . . . . . . . . . . . . . . . . 2 EP I-5 Personnel Emergency . .

.....~._e . . ................

1 EP I-6 Radioactive Spill . . . . . . . . . . . . . . . . . . . . . . . . . . . . - 1 EP l-7 Station. Fire .. . . .. . . . . . . . . ............,.... 1

'/

EP I-8 Personnel Accountability . . . . . . . . . . . . . . . . . . . . . . . . .. 1

-s EP I-9 Search and Rescue Operations . . . . . . ................ *1 EP I-10 Conducting an Inventory of Emergency Equipment- ............. 1 EP I-11 Communications Equipment . . . . . . . . ................

i 1

l EP I-12 Site Evacuation . ..... '

. .....s ................. 1

'luP. I-13 Post Ac'cident ' Low Pressure . Injection Monihoring . . . .......... '

,1 i EP'I-14 Initiation of Recovery Operations'. . . . . . . . . . ..........

1 EP I-15' Stable. Iodine Thyroid Blocking ' . . . .~,.a. .....s.. '

. .... . . . . . I lup I-16 Recall of Evacuated Site Personnel . . . ................ 1 EP I-17 Radiation Protection - Emergency Action . ................ 1 EP I-18 Operations Support Center Activation . . ................ 1 EP I-19 Activation / Evacuation of the Technical Support Centar . ......... 1 SECTION II - OFF-SITE PROCEDURES -

EP II-l Emergency Response Manager Preparation to Assume Responsibilities . . . . 1 EP II-2 Site Support Manager Preparation to Assume Responsibilities . ...... 1 EP II-3 Radiological Support Manager Preparation to Assume Responsibilities . .. 1 l EP II-4 Notification of Corporate Energency Response Personnel ......... 1 l EP II-5 Emergency Paging of Corporate Emergency Response Personnel ....... 1 EP II-6 Off-Site Administrative Support . . . . . .........,....... 'l l EP II-7 Testing of Emergency Procecurs.EP II-4 . ................ 0 l

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l SECTION III - SECURITY EMERGENCY PROCEDURES REV. NO.

  • I

. i

- EP, III-l Opening of the Technical Support Center . . . . . . . . . . . . . . . . . 1 EP III-2 Opening of the Emergency operations ' Facility

. . . . . . ... . . ... .. ,2 EP III-3 Personnel Accountability .. . ........ . . . . . . . . . . ... 1 EP III-4 Site Evacuation - Security Support. ....... . .'. . . . . . ... 1

~

EP III-5 Emergency yehicle Support . . . ....... . . . . . . . . . . . ... 1 SECTICN TV - RADIATICN PROTECTICN/CREMISTRY EMERGENCY PROCEDURES i

EP IV-101 TSC Initial Response . .. . . . . ... . . . . . . . . . . . . . ... 1 EP IV-102 Control Room Initial Response . ... ..... . . . . . . . . . . . ... 1 EP IV-103 Control Point Initial Response .......... . . . . . . . . ... 1

, EP IV-104 TSC Evacuation . . . . . ... . . ....... . . . . . . . . . . ... 1 EP IV-105 Control Point and Equipment Evacuat' ion ..... . . . . . . . . . ... 1 EP IV-106 ALARA Task Review and Emergency Exposure Authorisstion . . . . . . ... l' EP IV-107 Radia tion Monitor a Evalu' tion ' . . . . . . . . . . . . . . . . . . . . . . 1 EP IV-108 Protective Action Recommendations . . . . . . . . . . . . . . . . . . . .

~

1 EP IV-109 Plume Tracking by Helicopter . . ..... . . . . . . . . . . . . ... 1 v

EP IV-Il0A Field Monitoring by TSC . . . .. .. . . . .. . . - . . . . . . . . . ... 2 -

EP IV-1108 Field Mcnitoring by ECF .. . . . ... . . . . .. . . . . . . . . . ... '

O EP IV-111 Effluent Dose' Calculations . . .. . . ..... . . . . . . . . . ... 2 EP IV-ll2 Emergency operations Facility - Radiological Assessment .

. . . . . ... O i

EP IV-ll3 Computerized Dose Calculations .. . . . . . . . . . . . . . . . . . ... 2 EP IV-114 Computerized Dose Calculations on Programmable Calculator . . . . . . . . 0 EP IV-115 ' Personnel and' Vehicle' Survey. . . . . . . . ... . ... . .'. . .'. . . . . ' 'l EP IV-ll6 Fire Brigade Escort . . .. . .. . . . . . . . . . . . .. . . . . . . . ,. . . 1 EP IV-ll7 Re-Entry Team Radiation Protection ....... . . . . . . . . . . . .. ... ,1 EP IV-118 High' Activity Sampl'aiAnalysis'. . . . .. . . . . . . . . . . . . . . . . . ' 2' EP IV-119 Per'sonnel Decontamination . . . . . . . ... . . . . . . . . . . . ... 1 EP IV-120 Equipment Decontamination . . . .. . . . . . . . . . . . . . . . . ... I w

EP IV-121 Containment Atmosphere Remote Sampling .. . . . . . . . . .. . . ... . 1 EP IV-122 Emergency Staffing Guide . . ............ . . . . . . . ... 1 EP IV-201 Radiation Protection Senior Supervisor Response . . . . . . . . . . ... 1 EP IV-202 Chemistry Senior Supervisor Response ... . . . . . . . . . . . . ... 1 EP IV-203 Administrative Assistant Response . . . . . . . . . . . . . . . . . . . .

. 1 EP IV-204 Short Term Environmental Response . ..... . . . . . . . . . . . ..'. 1 EP IV-205 riatorial and Instruments Supervisor Response . . . . . . . . . . . ... 1 EP IV-206 Dosimetry-Counting Room Supervisor Response . . . . . . . . . . . . ... 1 EP IV-207 Rad Was te Supervisor Res ponse . . . . . . . . . . . . . . . . . . . . . . 1 EP IV-208 Dose Assessment - ALARA Supervisor Response . . . . . . . . . . . . . . - . 1 EP IV-209 In-Plant Supervisor Response . .. . . .. . . . . . . . . . . . . ...

1 EP IV-210 Procedures-Training Supervisor. Response . . . . . . . . . . . . . . . . . 1 ~

_/ EP IV-211 Radiation Protection Communications Guide . . . . . . . . . . . . . ... 1 EP IV-212 Radiation Protection Emergency Inventory Control . . . . . . . . . ... 1 EP IV-301 Interim Post Accident Primary Coolant Sampling . . . . . . . . . . ... 2 EP IV-302 Emergency Sampling Procedure for the Plant Vent . . . . . . . . . . ... 1

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SECTION V - ENGINEERING DEPARTMENT EMERCENCY PROCEDURES . REV. NO.

rP V-1 Notification of Engineering and Construction Department . ... . . . . . . 0 EP V-2 ' Corporate Engineering Support Manager Response (CHERC) ......... O EP V-3 Site Engineering Support Manager Response (EOF) ............. O EP V64 Corporate Engineering Team Leader Respon'se (CHERC) ......,..... O EP i-5 Corporate " Quality Assurance Department' Response (CHERC) ......... O

^

C' EP Ved j/ Site Quality Assurance Department Response (EOF) - ............

EP V-7 Site Engineering Team Leader' Response (TSC) .....~.......... O EP V-8 Methods Department & Engineering Department Divisional Representatives Response (CHERC) . . . . . . . . . . . . . . . . . . . . . . . . . . ~ . 0 SECTION VI - PLAN ADMINISTRATION EP VI-l Revision and Approval o,f Plans and Procedures .'. . . . . . . . . . . . . 1 EP VI-2 Distribution of Plans and Procedures .................. O EP VI-3 Review of Plans and Procedures ...............,...... 0 EP VI-4 Procedures Format . . . . . . . . . .' . . . . . . . . . . . . . . . . . .. O EP VI-5 Conduct of Drills and Exercises . . . . . . . . . ............. 1 I

'. SECTION VII - PUBLIC INFORMATION EP VII-1 Public Information Notification . .................... 0 EP VII-2 General Manager. - Information Services Response . ............ 0 EP VII-3 . Public Information' Manager Response . . . ............~.....

O.

EP VII-4 Public Information Technical Liaison Response . . . . . . . . . . . . . . 0 EP VII-5 Pub.lic Information T.echnical Assistant Response . ....

O "EP VII-6 Internal Information . .......................... O EP VII-7 Me d i a Re l a t ion s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 0 EP VII-8 Emergency News Center Activation /Pulbic Information Coordinator Response .. . . . . ......................... 0 ADDENDUM Addendum 1 Master Phone List . . ......................... 3 Addendum 2 Supplemental _ Station Status Checklist . . . . . . ... . . . . . . . .~. 1 FIGURES Figure 1 EDO Checklist . . . . . ......................... 1 Figure 2 Communications / EOF Manning Board .................... 1 Figure 3 Operational Status Board ........................ C

.- Figure 4 Post Accident RMS Assessment Data . ................... 1 Figure 5 Area / Process RMS Data . ......................... O Figure 6 Offsite Cose Summary . ......................... 0

. 3 of 3 _

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,' No.'101 U.S. NRC, Dir. of NRR

. Washing t'on', - D. C. 20555 -

Mr. S. A. Varga, Chief, Oper. e Reactors BR#1, Div. of Licensing.

SALEN GENERATING STATION EMERGENCY PLAN .

  • JANUARY 20, 1983 SECTION I - ON-SITE PROCEDURES RE7. NO.

EP I-0 Accident Classif,1 cation Guide . . . . . . . . . . . . . . . . . . . . . . 3 Part.1 Radiological Part 2 Operational

, Part 3 Fire / Natural / Security Part 4 Miscellaneous

  • Flow Chart ...............................

O EP I-l Notification of Unusual Event /Significant Event . ............ 3 EP I-2 Alert .

2 EP I-3 Site Area Emergency . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 EP I-4 Ge ne ra l Em'e rgen cy . . .* . . . . . . . . . . . . . . . . . . . . . . . . . 2 EP I-5 Personnel'Eme'rgency . . . . . . . . . . .~. . . . . . . . . . . . . . . . 1 EP I-6 Radioactive Spill . . . . . . . . . .'. . . . . , . . . . . .,. . . . . . 1 EP I-7 Station Fire ~.

............................... 1 EP I-8 Personnel Accountability . .

...................... . 1 EP I-9 Search and Rescue Op*erations ...................... 1 EP I-10 Conducting an Inventory of Emergency Equipment ............. 1 -

EP I-ll Communications Equipment _ . .

....................... 1 EP I-12 Site Evacuation . . . . ..............-........... 1

. EP I-13 Post Accident Low Pressure Injection Monitoring . . . .......... '

1 EP I-14. Initiation of Recove ry Cpera tions .. . -. . . . . . '. . . . . . . . . . . . 1 EP I-15 Stable Zodine Thyroid Blocking . . . . . . . . . . . . ..... ... . . . . 'l EP I-16 Recall of' Evacuated'S'ite Personnel' . . . . . ... . . . . . . . . . . . . 1 EP I-17 Radiation Protection - Emergency Action . ................ 1 EP I*18 Operations. Support Center Activation .................. 1 EP I-19

~

Activation / Evacuation of the Technical Support Center . . . . . . . ... . 1 SECTION II - CFF-SITE PROCEDURES -

EP II-l Emergency Response Manager Preparation to Assume Responsibilities . . . ., 1 EP II-2 Site Support Manager Preparation to Assume Responsibilities . ...... 1 EP II-3 Radiological Support Manager Preparation to Assume Responsibilities . . . 1 EP II-4 Notification of Corporate Emergency Response Personnel ......... 1 EP II-5 Emergency Paging of Corporate Emergency Response Personnel ....... 1 EP II-6 Off-Site Administrative Support . . . .................. 1 EP II-7 Testing of Emergency Procecure EP II-4,,. ................ 0 2r . -

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- EP, III-1 Opening of the Technical Support Center ., . . . . . . . . . . . .. . . . . 1

)

)

EP III-2 Opening of the meergency Operations Facility . . . . . . . . . . . . . ..

2 EP III-3 Personnel' Accountability . . . . . . . . . ... . . . . . . . . . . . . .-

1 EP III-4 Site Evacuation - Security support .................... 'l EP III-5 Emerg'ency yehicle Support . ..................~..... 1 SECTION IV - RADIATION PROTECTION /CMEMISTRY EMERGENCY PROCEDURES EP IV-101 TSC Initial Response ..........................

1 EP IV-102 control Room Initial Response . . . . . . . . . . . . . . . . . . . . . . 1 EP IV-103 Control Point Initial Response ..................... 1 EP IV-104 TSC. Evacuation ............................. 1 EP IV-105 control Point and Equipment Evacuation ................. 1

' EP IV-106 ALARA Task Review and Emergency Exposure Authorization ......... 1 EP IV-107' Radiation' Monitor, Evaluation ......................

_1 EP IV-108 Protective Action Recommendations . . . . . . . . . . . . . . . . . . . . 2 .

EP IV-109 Plume Tracking by Relicopter ...~................... 1 EP IV-110A Field Monitoring,by TSC ......................... 2 EP IV-110B Field Monitoring by EOF . . . . . . . . . . . . . . . . . . . . . . . . . . O k EP IV-111 Effluent Dose Calculations ....................... 2 EP IV-112 Emergency Operations Facility - Radiological Assessment . . ',. . . .... 0 EP IV-113 Computerized Dose Calculations

...................... 2 EP IV-114 Computerized Dose Calculations on Programmable calculator . . . . . . . . 0 EP IV-115' Personnel and vehicle Survey '

. . . . ,. . . . . ,. . . . . . . . . . . . .- '1

. EP IV-116 Fire Brigade Escort . ' . .,................~........ 1 EP IV-117 Re-Entry Team Radiation Protection .................... 1 EP IV-118 High

  • Activity Sa mple An' alysis . . . . . . . . . . . . < . . . . . . . . . .

2 EP IV-119 Personnel Decontamination . . . . . . . . . . . . . . . . . . . . . . . . 1-

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  • EP IV-120 Equipment Decontamination . . . . . . . . . ... . . . . . .' ....... I EP IV-121 Containment Atmosphere Remott sampling ................. . 1 EP IV-122 Emergency Staffing Guide ........................

1 EP IV-201 Radiation Protection Senior Supervisor Response . . . . . . ....... 1 EP IV-202 Chemistry Senior Supervisor Response .................. 1 EP IV-203 Administrative Assistant Response . . . . . . . . . . . . . . . . . . . . '1 EP IV-204 Short Term . Environmental Response . . . . . . . . . . . . . . . . . . . '.~

' 1 EP IV-205 Material and Instruments Supervisor Response ..............

  • I  !

EP IV-206 Dosimetry-Counting Room Supervisor Response . . . . . . . . . ...... 1 EP IV-207 Rad Wa s te Supervisor Response . . . . . . . . . . . . . . . . . . . . . . 1 EP IV-208 Dose Assessment - ALARA Supervisor Response . . . . ., . . . . . . . . . . 1 EP IV-209 In-Plant Supervisor Response ...................... 1 a EP IV-210 Procedures-Training Supervisor Response . . . . ............. 1

.; EP IV-211 Radiation Protection Communications Guide . . . . . . . ......... 1 EP IV-212 Radiation Protection Emergency Inventory Control ............ 1 EP IV-301 Interim Post Accident Primary Coolant Sampling ............. 2 EP IV-302 cmergency Sampling Procedure for the Plant Vent . ............ 1 2 of 3 2 . _ _ _ _ . . --_ _ _ _ _ _ ._ R_ev.. _ . 5 . .- _._

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t.... ....

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. 1

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i REY. NO. I OCEDURES~ - I SECTION V - ENGINEERING DEFAR7NENT tment EMERCENCY

. . . . . . . . . PR 0

  • l 0 1

~

Notification of Engineering and Construction Depar . . . . ' . . . . .

EP*V-1 (CHERC) . . 0 l i

EP V-2 Corporate Engineering Support Manager Response . .......... O i

Site Engineering Support Manager Response ) (EOP)

......,..... 0 . '{

EP V-3

)

Corporate Engineering Team Leader Response C ERC) (CRERC . ........ O EP V-4 Corporate' Quality Assurance Department Response (H s

. I EP V-S 0.

Site Ouality Assurance Department Response ........ (EOF) 4 . . . . .

EP V-A i ional Pepresentatives Site Engineering Team Leader Response (TSC) i 0 EP V-7 .

EP V-8 Methods Department & Engineering Department D v s.................

Response (CNERC)

SECTION VI - PLAN ADMINISTRATION __ ........ 1

  • O Revision and Approval of Plans and....... Procedures........... ......

-EP VI-I O EP VI-2 Distribution'of Plans and Procedures...............,...... 0 EP VI-3 EP VI-4 Review of Plans and Procedures Format .

Procedures........~..........-........ 1

[

  • EP VI-5 conduct of Drills and Exercises . . . . . . . . . . . . . . . . . .

SECTION VII - PUBLIC INFORMATIO_N .......J. 0 O

Public Information Notification .i. .'. . . . . . . . . . Response . . . . . . . . . . . . O.

EP VII-l EP VII-2 General Manager - Information Serv ces .

C EP VII-3 . Public Information Manager Response . . . .. . . Response . ... . . . . .'... 0-. . . .

EP VII-4 'Public Information Technical LiaisonPublic . .- . . . . . Informatio O

  • 0 EP VII-5 . ' ' . . . . ...

EP VII-6 Internal Information'. . . . . . . . . . . . . . . ... . ..

EP VII-7 Media Relations . . . . . . . . . . . . .". tion . . .Coordinator

.... 0 Emergency News Center'Act'ivation/Pulbic Informa EP VII-8 Response ...............

ADDENDUM _ 3 1

Addendum 1 Master Phone List ~ .

Addendum 2 Supplem' ental Station Status Checklist 1

~

_FICURES-

. 1 Figure 1 EDO Checklist .

... . . . .............. O Figure 2 Communications / EOF Manning Board........................ I Figure 3 Operational Status Board ..............

Figure 4 Post Accident RMS As sessment Data . . . . . .

......... O 0

Figure 5 Area / Process RMS Data . . . . . . . . . . . . . . . . ..........

Figure 6 Offsite Dose Summary ReV. 5 ..-

3 of 3 _ _' = ~ - _ . - " - - - - - - - - . _ , _ , , _ _ _

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