Text

Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures EPP-002 Re Communication & notification,EPP-003 Re in-plant Radiological Surveying & EPP-013 Re Fire Emergency
	ML20080M288
Person / Time
Site:	Summer
Issue date:	08/10/1983
From:	; SOUTH CAROLINA ELECTRIC & GAS CO.
To:	;
Shared Package
ML20080M272	List: ML20080M285; ML20080M288;
References
	PROC-830810-01, NUDOCS 8310030587
	Download: ML20080M288 (367)
	v • d • e

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c 8/10/83 VIRGIL C. SUMMER NUCLEAR STATION i NUCLEAR OPERATIONS PROCEDURES EMERGENCY PLAN PROCEDURES TABLE OF CONTENTS PROCEDURE DATE NUMBER PROCEDURE TITLE REVISION ISSUED _

EPP-001 Activation and Implementation of Emergency Plan 5 8/10/83 EPP-002 Communication and Notification 7 6/7/83 EPP-003 In-Plant Radiological Surveying 3 6/1/83 EPP-004 Out-of-Plant Radiological Surveying 4 5/25/83 EPP-005 Offsite Dose Calculations 4 5/25/83 .

EPP-007 Environmental Monitoring 1 7/27/82 EPP-009 on-Site Medical 2 7/27/82

. EPP-010 Personnel / Vehicle Decontamination 2 7/27/82 EPP-Oll Personnel Search and Rescue 2 7/27'/82 EPP-012 Onsite Personnel Accountability & Evacuation 4 5/25/83 EPP-013 Fire Emergency 3 5/25/83 EPP-014 Toxic Release 1 7/27/82 EPP-015 Natural Emergency (Earthquake, Tornado) 2 8/2/83 EPP-016 Emergency Facilities Activation & Evacuation 3 6/1/83 EPP-017 Post-Recovery and Re-Entry 3 5/25/83 EPP-018 Emergency Training and Drills 2 6/1/83 EPP-019 Emergency Equipment Checklist 4 6/1/83 EPP-020 Emergency Personnel Exposure Control 2 5/25/83

Safety Related Procedure

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- PROCEDURE DATE NDNBER PROCEDURE TITLE REVISION ISSUED EPP-021 Activation of the Early Warning Siren System (EWSS) 5 5/25/83 EPP-022 7erification of Communications Operability 2 5/25/83 G

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EMERGENCY PLAN PROCEDURE EPP-001 ACTIVATION AND IMPLEMENTATION OF ]!MERGENCY PLAN REVISION 4 MAY 17,1983 NON-SAFETY RELATED

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' Reviewed by:

& ln 2- C ORIGlWATOR (oY this revision) ~ /Dage

$41 ally sk/r3 DISCIF3rINE SUPERVISOR Jate i

Approved:

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FLANT MANAGER Date l

l Date Issued: ~

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EPP-001 3* -

PAGE i q REVISION 4 5/17/83 f LIST OF EFFECTIVE PAGES I PAGE REVISION i

4 11 4 1-4 {

2 4 '

, 3 4

'; 4 4

5 4 6 4 7 4 8 4 I

9 4

! /' 10 4 11 i.!; 4

( i: ATTACHMENTS Attachment I Pages 1 thru 13 4 Attachment II 4

, ,, Attachment III 4

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EPP-001 PAGE ti REVISION 4 5/17/83

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TABLE OF CONTENTS

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2.ECE '

q List of Effective Pa6es i~

1.0 PURPOSE 1

2.0 REFERENCES

1

, 30 CONDITIONS AND PREREQUISITES 1 4.0 PROCEDURES 2

.., 41 CLASSIFICATION OF EVENT 2 42 IMPLEMENTATION OF EMERGENCY PLAN 2 43 UNUSUAL EVENT 2 44 ALERT 3 45 SITE EMERGENCY 6 4.6 GENERAL EMERGENCY g

( ,' ATTACHMENTS i

i Attachment I Emergency Action Level Summaries l Attachment II General Emergency Protective Action Recommendations Attachment III Immediate Actions Summary 4

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EPP-001 l* .

REVISION 4 5/17/83 I

,{ 1.0 PURPOSE

' To define and implement the Emergency Action Levels (EAL's) that will initiate the Emergency Plan and to provide a means of classifying the emergency.

i 1

2.0 REFERENCES

l 2.1 " Virgil C. Summer Nuclear Station Radiation Energency Plan." ,

2.2 NUREG-0654, Criteria for Preparation and Evaluation of Radiological Energency Response Plans and Preparedness in Support of Nuclear Power Plants.

L

23 EPP-021, Activation of the Early Warning Siren System.

t 24 Policy Memorandum No. 25, Issuance, Control, and Usage of Radio Pagers.

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.i .

30 CONDITIONS AND PREREQUISITES 31 The Emergency Plan shall be initiated whenever an

" Initiating Condition" (as defined in Attachment I) has

( been reached or exceeded. y NOTE: The implementation of any specific emergency plan procedure (except this procedure) does not necessarily implement the Emergency Plan, but may do so at the discretion of the Emergency Director / Interim Energency Director. For example; a small chlorine leak would implement the toxic release procedure but not necessitate implementation of the Emergency Plan; whereas a large release with the potential for affecting

, the level of safety of the plant would implement the toxic release procedure and the Emergency Plan due to the declaration of an Unusual Event.

32 The "Initiatin'g Condition" shall be used to determine the applicable Emergency Action Level (EAL) per Attachment I.

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EPP-OO1 i REVISION 4 5/17/83

'~h 33 ~ The " Detection Methods" of Attachment I are to be used K only as an aid to determine if an " Initiating Condition"

.. has been reached or ' exceeded. Other detection methods,

not~1isted in Attachment I, say be used to determine if an "Inf.tiating Condition" exists. The existence of one or 4

r more of the detection methods could be but is not

, necessarily an indication- that an " Initiating Condition"-

9 =: exists.

34 Attachment II should be used by the IED/ED as an aid in determining what protective actions should be recommended to government officials:when a General Emergency is declared.

j

40. PROCEDURES y 4.1 Upon recognition of an . abnormal plant or site c'ondition j the observer shall notify the Shift Supervisor of the

j potential emergency plant condition.

42 .The Shift ~ Supervisor shall:

i

A. Evaluate the conditions and determine the' applicable Emergency Action Level (EAL) per the Emergency Action i

. . Level Summary, Attachment I.

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V B. Declare an EAL and implement the Emergency Plan per the applicable section of this procedure.

Unusual Event (Section 4 3)'

or Alert Section 4.4) 5 or Site Emergency Section 4 5) or General Emergency Section 4.6) 43 Unusual Event 4 3'1 . Immediate Actions: (Immediate Action Summary, See j Attachment III)

The Director Emergency) (IED shall Director (ED) or Interim accomplish Emergency or cause to be accomplished the following:

-. ~

A. Announce the emergsney condition to all plant personnel over the plant paging system.

ATTENTION ALL PERSONNEL:

THE STATION IS IN AN UNUSUAL EVENT CONDITION.

j THE INITIATING EVENT IS .

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N-NOTE: [ REPEAT ANNOUNCEMENTj.

B. Notify the Security Shift Leader to implement appropriate security measures.

C. Ensure that on-shift personnel have responded to their emergency response stations.

D. Ensure that the Initial Notifications are completed per EPP-002.

[

4 E. Ensure that the Emergency Log is established and maintained.

F. Request Offsite Emergency Services (Fire,

, Medical, LLEA, etc~.) if required per EPP-OO2, if necessary.

NOTE: - Consideration should be given to access routes taken.

i 432 Follow-Up Actions:

, The ED/IED shall continually assess the status of the Unusual Event per Attachment I .for possible

-(I "

escalation to a higher emergency classification or termination of emergency condition.

, 433 Final' Actions:

\-

When the emergency condition has cleared, close out

, the Unusual Event with a verbal summary to offsite authorities within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and close out of the Emergency Log.

44 Alert 4 4 1. Inmediate Actions (ED/IED): (Immediate Action a Summary, Attachment III)

The Director Emergency) (IED shall Director (ED) or Interim accomplish Emergency or cause to be accomplished the following:

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( ) A. Announce the emergency condition to all plant e

personnel over the plant paging system.

I j

a ATTENTION ALL PERSONNEL:

j THE STATION IS IN AN ALERT CONDITION. THE INITIATING EVENT IS ALL EMERCENCY RESPONSE PERSONNEL REPORT TO THEIR STATIONS.

B. If'necessary, sound the Radiation Emergency a

. Alarm.

C. Repeat the announcement.

4

.i NOTE: [ Repeat steps A, B

, for six minutes.] , and C every two minutes

- D. Nctify the Security Shift Leader to implement i appropriate security measures.

t

3. Ensure that on-shift personnel.have responded

(

to their emergency response stations.

x l',. F. During off-normal hours, call in emergency

-response personnel by activating the.SCE&G Radio Pager System as per-Policy Memorandum No.

t 25 G.. Ensure that the Initial Notifications are completed per EPP-002.

. H. Ensure that the Emergency Log is established and maintained.

I. Request Offsite Emergency Services (Fire, Medical, LLEA, etc.) if required per EPP-002.

NOTE: Consideration should be given to access routes taken.

I,

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PAGE 4 of 11

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~ EPP-001

~ . REVISION 4 5/17/83

. s I J. Ensure that TSC 1

EPP-016 and/or notification

/OSC are being of activated Emergencyper

Response Personnel.is initiated per EPP-002.

~ - ~ ~ ~ -

.-- K. Determine if.the site evacuation'is required.

.j (Inclading Fairfield Pump Storage Pacility) .

4 4 2- Immediate ' Actions ( All other personnel):

t A. Emergency Response Personnel report to their

- designated stations.

B. Non-essential personnel' continue assigned l duties suli avait further instructions.

C. If the radiation emergency alarm is initiated, 4 . all, Personnel in the Radiation Control Area 3 report to the Radiation Access Control Area on

! j the 412' level of the Control Building.

J 443 Pollow-up Actions d

j The ED/IED shall:

, i A. - Notify the Offsite Emergency Coordinator of-the

[ ,- , - emergency and. current plant conditions.

L' l E. Verify. that the TSC/OSC are manned and activated per EPP-016.

7 -! C. Ensure that updated follow-up notifications are made per EPP-002. .

1 D. Continue assessments and corrective actions to mitigate the' emergency condition and place the plant into a safe and controlled condition.-

E. Make assignments to his staff to mitigate:the emergency conditions per established Emergency Plan Procedures (EPP's) or as required for

0 conditions not covered by procedures.

1P. Continually assess the status. of the Alert condition per Attachment I for possible escalation to a higher emergency l

3 classification, down-grading'to an Unusual-Event, orfolose out of emergency condition.

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EPP-OO1 i

REVISION 4 1 5/17/83

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. ;,r ( 444 Final Actions:

4

1. A. When emergency conditions clear to allow for close out or down-grading of the Alert condition, the ED sball ensure that offsite

'i'

1 authorities are:

'l 1. ' Notified verbally .by normal emergency Ll: ; communications.

i

^

2. Provided with a written summary within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months of the close out of the emergency or

down-grade of the emergency.

., classification.

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B. Initiate EPP-017, Post-Recovery and Re-Entry as required.

I

45 Site. Emergency.

l 4.5.1 .Immediate Actions (ED/IED): (Immediate Action j Summary, see' Attachment III)

The Emergency)

Director (IED shall Director (ED) or Interim accomplish Emergency or cause to be i accomplished the following:

A. Announce the emergency condition and site evacuation to all plant personnel over the plant paging system.

3 ATTENTION ALL PERSONNEL:

i THE STATION IS IN A SITE EMERGENCY CONDITION. THE

!! INITIATING EVENT IS .

I ALL EMERGENCY RESPONSE PBRSONNEL REPORT TO THEIR l STATIONS.

ALL NON-ESSENTIAL PERSONNEL EVACUATE THE SITE PROCEED TO .

B. Sound the Radiation Emergency Alarm.

C. Repeat the announcement.

NOTE: (Repeat steps A, B, and C every two

+

minutes for six minutes.]

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PAGE 6 of 11

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^t e EPP-001 REVISION 4

,, /~~ 5/17/83 d -

D. Notify the' Security Shift Leader to implement ij appropriate security measures.

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E. Notify the Fairfield Pump Storage Facility of site evacuation.

I F.- Implement EPP-021.

"; -l1' G. During off-normal hours, call in Emergency Response Personnel by activating the SCE&G Radio Pager System as per Policy Memorandum No.

. 25 H. Ensure that on-shift personnel have responded to their emergency response stations. .

[

I. Ensure that the Initial Notifications are completed per EPP-002.

' : . -. J. Ensure that the Emergency Log is established

] I and maintained.

! E. Request Offsite Emergency Services (Fire, l Medical, LLEA, etc.) if required per EPP-002.

, i NOTE:-- Consideration should be 'given. to access

,A . . . -

j- routes taken.. '

t j' L. Notify the Offsite Emergency Coordinator of the emergency and current plant conditions.

. 3 M. Ensure that TSC I EPP-016 and/or n/OSC/E0F otificationare ofbeing Energency activated per

] Response. Personnel is initiated per EPP-002.

4 5.2. Immediate Actions ( All other personnel):

, A. Emergency Response Personnel report to their 4 -designated stations.

i:

B. Non-essential personnel evacuate the site, proceed to their private residence or offsite holding area as designated by the ED, and'avait

, further instructions.

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C. Personnel in the Radiation Control Area report to the Radiation Access Control Area on the 412' level of the Control Building, unless otherwise directed.

453 Follow-Up Actions A. Verify that the TSC/0SC/ EOF are manned and activated per 3PP-016.

B. Ensure that updated follow-up notifications are made per EPP-002.

C. Continue assessments and corrective actions to mitigate the emergency condition and place the plant into a safe and controlled condition.

D. Make assignments to his staff to mitigate the emergency conditions per established Emergency Plan Procedures (EPP's) or as required for conditions not covered by procedures.

E. Continually assess the status of the Site Emergency condition per Attachment I for possible escalation to a higher emergency classification, down-grading to an Unusual Event, or Alert, or close out of emergency condition.

F. Verify site evacuation is complete and all personnel are accounted for. (Including Fairfield Pump Storage Personnel).

454 Final Actions:

A. When emergency conditions clear to allow for close out or down-grading of the Site Emergency

! condition, the ED shall ensure that Sffsite l authorities are:

1. Notified verbally by normal emergency i communications.

l and 2. Provided with a written summary within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months of the close out of the emergency or I down-grade of the emergency i classification.

B. Initiate EPP-017, Post-Recovery and Re-Entry as required.

PAGE 8 of 11

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l. EPP-001 i REVISION 4 5/17/83

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j ( . 4.6 General Emergency-4.6.1 Immediate Actions (ED/IED): (Immediate Action Summary, see Attachment'II)

The Emergency Director (ED) or Interim Emergency Director (IED) ahall accomplish- or

! cause to be accomplished the following:

l fl A.- Announce the emergency condition and site j evacuation to all plant personnel over the plant paging system.

ATTENTION ALL PERSONNEL:

, THE STATION IS IN A GENERAL EMERGENCY-CONDITION. THE INTIATING EVENT IS .

ALL EMERGENCY RESPONSE PERSONNEL REPORT TO THEIR STATIONS.

. F

' ALL NON-ESSENTIAL PERSONNEL EVACUATE THE SITE.

l PROCEED TO .

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B. Sound the Radiation Emergency. Alarm.

C. Repeat the announcement.

.' NOTE: (Repeat steps A, B, and C every .two

,j minutes for six minutesj.

D. Notify the Security Shift ' Leader to implement i appropriate security measures.

E. Notify.-the Fairfilld Pump Storage Facility of

[ Site Evacuation.

i F. ' Refer to Attachment II for recommended protective' actions for offsite areas.

G. Implement EPP-021.

j'. H. During off-normal hours, call in Emergency Response Personnel by activating the SCE&G b Radio - Pager System as per Policy Memorandum No.

, 25 I. Ensure that on-shift personnel have responded 3

to their emergency response stations.

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PAGE 9 of 11

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EPP-001 ;

.L REVISION 4

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5/17/83 '

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J. Ensure that the Initial Notifications are l

' completed per EPP-002. '

! K. Ensure that the . Emergency Log is established

! and maintained.

.t

! L. Request offsite Emergency Services'(Fire,

.f Medical, LLEA, etc.) if required per EPP-002 NOTE: Consideration should -be given to access .

routes taken.

, M. Notify the Offsite Emergency Coordinator of the

,j emergency and current plant condition.

l

,j' N. Ensure that TSC/OSC/ EOF are being activated per EPP-016 and/or notification of Emergency Response Personnel is initiated per EPP-OO2.

4.6.2 .Immediate Actions ( All other personnel):

! A. Emergency Response Personnel report to their

designated stations.

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B. Non-essential personnel-evacuate the site,

~, proceed to their private residence or offsite

holding a as designated by the ED, avait further instructions.

C. Personnel in the Radiation Control Area report

.to the Radiation Access Control Area on the 1 412' level of the Control Building, unless

'i otherwise directed.

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PAGE 10 of 11

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REVISION 4

'l 5/17/83 1 hc 4.6 3 Follow-up Actions The ED/IED shall:

h- A. Verify that' the TSC/OSC/ EOF are manned and

] activated per EPP-016.

{ 3. Ensure th'at updated ' follow-up notifications are

_1 made per EPP-OO2.

-1 C. Continue aasessments and corrective actions to mitigate the emergency condition and place the plant into a safe and controlled condition.

[ D. Make assignments to his staff to mitigate the emergency conditions per established Emergency Plan Procedures-(EPP's) or as required for

, conditions not covered lyr procedures.

E. Continually assess the status of the General -

Emergency condition per Attachment I for

possible down-grading to an Unusual Event, I Alert, or Site Emergency, or close out of j emergency condition.

i

. F. Verify site evacuation is complete and all

~'

personnel are accounted for. (Including Fairfield Pmap Storage Personnel).

4.6.4 Final Actions:

A. When emergency conditions clear to allow for j{ close.out or down-grading of'the General Emergency. condition, the ED shall ensure that' offsite authorities are:

, 1. Notified verbally by normal emergency

! communications. ,

[

4- 2. Provided with a written summary _within 8 l hours of the close out of the. emergency or down-grade of the emergency classification.

B. Initiate EPP-017, Post-Recovery and Re-Entry as required.

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'h j;, EMERGENCY ACTION LEVELS StaemRY EPP-001, ATTAOSIENI I

f%GE I of 13, REVISION 4 3

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SYSTEM SITE GENERAL

! INVOLVED REACTOR UNUSUAL EVENT INITIATING C0pelTION INITIATING ColelTION ALERT ENERGEEY INITIATiss COISITION EIGRGEICY [

} iMITIATifG CONDis'8088 ,~ (

j^ 000LANI EMCEEDING TEDW11 CAL SPECIFICATION RAPID FAIListE OF SEVERAL STEAM 191DWN LOSS-OF-CO0t. ANT ACCIDENT SmLL AfD LARGE LOCAs WITH FAILGtE i

SYSTEM PRiemRY TO SEColenRY OR PRIMARY GENERATOR times te.g., SEVERAL (LOCA) GREATER THAN OmRGING Pt#F

.i, SYSTEM LEAK RATES HUNDRED GPM IRitmRY-TO-SEC00 GARY OF ECCS TO PERF0ltl LEADilG TO [

CAPACITY. SEVERE CORE DEGRAGRTION Gt DELT.;

} LEAK RATE). ULTilmTE FAILlatE Gr REACTOR 1

Detection Method: Detection Method:

BUILDING POSSIBLE FGt MLTDOWN Primary to secondary leek rate Detection Methods Pressurizer low pressure reactor SEQUEICES.

greater than I gpa total for more trip; and

, than 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or greater than 500 Pressurizer low pressure alarm en< Pressurizar low pressure safety Detection Method:

gpd per steam generator as l reactor trip; g injection signal, and

. Identified by dally RCS f eekage Pressurizar low level alarm; and, High Reactor Building pressure, Safety injection signol with

}, evaluations g RM-A9, Gl94, Gl98, or Gl9C valid (

_and, reactor trips edi [

!j; Primary system leek rate greater high alarms enjd, , high Reactor Building sump level 1) Status leaps indicate safety !

}, then those specified in Technical Steam generator water level g ; Injection and fHL pumps not [

!, , Specification 3.4.6.2 as identi tlec rapidly increasing in one or more High Reactor Building humidity; running: E ,

j by delly RCS leakage evaluation. steen generator (s), falling in the and, 2) Flow Indicators for Safety others; g RM-A2 high alarm injection System reed zero; 3d_ ,

'. 1) > 0 pressurs boundary leakage ste-L3, cr.itt-LIO volld high alarm RMG-5, It4G-7, steG-18, high alare;

}

2) > 1 gpm unidentified for more and -- .--------------- and itt-A2 high alors; j i l then 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Possible 11tting of steen INITIATING C000lTl0N

3) > 10 gpm Identified RCS leakage generator PRV's and/or safety [

l RAPID FAllistE OF SEVERAL STEAM for more than 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

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volves.

[

i GENEIMTOR TUBES (SEVERAL HUNDRED ----- ------------ i

4) > 33 gpm controlled leakage (at GPM MllMARY-TO-SEC0f0ARY LEAK INITIATING C0felTION [

! 2235 + 20 psig for more than 4 -----------------

RATE) NITH LOSS OF OFFSITE IUWER. SimLL LOCA ADO INITIALLY SUCCESSFUL '

hrs.) INIT1ATING C000lT10N t 5) > I gpm RCS pressure Isolation REACTOR COOLANI LEAlrAGE IMTE Detection Method ECCS. SUBSEQUENT FAILtftE OF REACTOR BulLDING lEAT REH0 VAL

[

valve per table 3.4-1 for EEEEDS 50 GPM. SYSTEMS OVER SEVERAL H01545 COULD jjl

__ _ Jlry,1,ey_ _th,an_4_ hour _sn _ _ _ ,, Pressurizer low pressure alarm and LEAD TO CORE ELT Als POSSIBLE

, ; INITIATipG C0 holt 10N Detection Methods reactor trip,3; pressurizer level FAIL 15tE OF THE REACTOR BUILDING.

, AB90RMAL REACTOR C00LANI TEfr. rapidly decreasing ud, i

} AND/0R PRES $15tE OR ABNORMAL FUEL 1) Excessive Reactor Make-up to Pressurizar low-level alarms ud, Detection Methods i

, TEIFERATtstE THAT NOULD llelCATE A the Volume Control Tank RM-A9, Gl9A, GI98, or Gl9C volld Pressurizer low pressure reactor 3 LOSS OF Stad)0 LING ISRGIN OR 2) Operational Lookage Test l OVERPRESSURIZATION. Procedure STP-ll4.002/

high alare; and, loss of IISKV and 230 KV ESF potential lights, and trip; ud_

Pressurizar low pressure safety

] l l

Detection Method Steen Generator water level Injection signal and j

'i l) Reactor Coolant Tavg greater rapidly Increasing in one or more 1) Rtet flow Indicators shoe zero - "

l 'j than 590*F; g stese generators, falling in the flow after shift to fHL is a

! 2) RCS pressure greater then 2310 others; and_ attempted and for greater then 2 I

} psig; or RM-L3, or ite-LIO valid high alarm; hr. subsequsntly and RCS j i 3) RCS pressure less than 1765 g temperature rislag, g 4 psig; and core eult temperature 2) Reactor Bullding sprey and

} greater than 620*F as Irdicated by Possible lif ting of eteen genere- Reactor Building air handling g a valid Incore thermocouple; g for PRV's and/or safety valves. system fell to function. M i 4) Inedequate Core Cooling Alarm, 9 l t

1 1 *

. J l'. @ U J .

l I

EMERGENCY ACTION LEVELS StDNARY EPP-001, ATTACFMENT 4 PAE 2 of 13, REVISION 4 SYSTEM .

SITE GEERAL INVOLVED l#AISlML EVENT ALERT EMERGENCY - EMRGEIOY STEAM INITIATING CONDITION INITIATING Q)>OITION INITIATING COSOITION SYSTEM RAPID SECONDARY SYSTEM MJOR STEAM LINE EREAK (e.g., mJm STEAM LINE IREAK WITH DEPRES$1RIZATION. ;

' GREATER THAN 6 IN. EQUlmLEN[ GREATER THAN 50GFW DIAMETER) WITH A SIGNIFICANT I PRimRY-TO-SECONDARY LEAfrAGE APO Detection Method: PRimRY-TO-SECOPMRY LEAK MTE. l>OICATION OF FLEL [REGE.

1 Rapid decrease in S/G pressures anc . Detection Method: Detection Method 4 . Reduced RCS temperature and l ji pressure; g Rapidly decreasing reactor Rapidly decreasing reactor 3

!0 Observation of treak or steam duop, coolant T,yg, pressurizar Coolant T,yg, l! relief or safety valve pressure, and pressurizer level; pressurizer gressure and Inadvertently opened, g RM-L3, or RM-LIO or IN-A9 j l pressurizar level; g i high alarms; g l

l 1) Steen line differential l) Steam line dif f erential l

) pressure, safety injaction pressure, safety injection signals g High Reactor signals g ,

Building pressure alarm; High Reactor Building and, d RM-A2 high alam for pressure alarm og valid rupture in f!eactor Building IN-A2 and IW-LI high alare 'i' I

'l -OR- g i

2) HIgh steam flow and Lo-Lo or T,yg or low steam 2) Highs 5amflowandLo-Lo pressure saf ety injection Tavg cr low steam pretture ;

signal for rupture downstrean safety injection signal and, '

of MSIV's. IW-A9, Gl9A, Gl98, or Gl9C or '

high alarm and,1W-LI valid 1 INITIATING COlelTION high alarm !

RAPID 20SS FAILIRE OF ONE STEAM '<

GENERATOR TlBE WITH LDSS OF 0FFSITE POWER. ,'

t Detection Methods a

Pressurizer low pressure alarm i

and reactor frIp; g Pressurizer low level alem; and, n j{ .

i; RM49, Gl9A, Gl98, or Gl9C valid i

high alarm and Pressurizer low pressure safety injection signal; (

g foss of Il5 KV and 230 KV ESF l Potential Lights; g -

RM-L3, cr IW-LIO valid high ,

alarms e

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i' EMERGEEY ACTION LEVELS Sl20MRY EPP-001, ATTAOSIENT I 6

PAGE 3 of 13, REVISIGt 4 '

SYSTEM SITE GEEl%L

! INVOLVED UNUSIRL EVENT ALERT [* ERGEEY EERGE8CY ,

RADIOLOGICAL INITIATING COISITION SUSTAINED HI9t IUDIATION LEVELS GI INITIAT10G C00elT10N INITIATING CONDITION EFFLUENIS GLSEOUS EFFLUENT INSTANIANEOUS HlR4 AIR 90RNE CONIAMINATION WHICH RADIATION MONITORS DETECT LEVELS EFFUENI NONITGtS (ETECT LEVELS

!l RELEASE RATE TECHNICAL llelCATES A SEVERE DEGMDATION IN CORRESPosellG TO etEATER THAN 50 CORRESPONDifG TG l-REM /tSt WOLE BODY I SPECIFICATION LIMITS EEEEDED FOR .1 THE CONIROL OF IMD10 ACTIVE MEM/Mt NHOLE BODY FOR 0.5 m. (R OR 5-REM /m THIROID AT TIE L l

m. (APPDelX S TABLE II, COLIA4N .1 8mTERIALS (e.g., INCREASE OF GREATER THAN 50015 TEN /m WOLE EELUSION AREA BOUpeARY IAOER ACTIML 10CF!t20) FACTOR OF 1000. IN DIRECT IMDIATIOP BODY FOR 2 MIN. (OR FIVE TIMES METEOROLOGICAL CopelTIONS.

i

, READINGS). THESE LEVELS TO THE THIR0lD) AT I- Detection Method: THE EXCLUSION AREA B00004RY FG4 Detection Method:

l Detection Method: ADVERSE METEOROLOGY (PASQUILL F j 1) RM-A3 (Ges) Increases > 1 X STABILITY, IN/SEC Nlte ELOCITV). ,

105 cpm above bkgd in any 8 I) Radiation Monitor levels owcoed i 3 1) Unexpected valid RMS readings those specified for Site Emergency; hour. ~or as follows: Detection Methods and I a) RMG 2-4, 8-13, or 16: greater M alculation on Dose Assessment-

'8

2) RM-A3 (todine) Increases > 8 X then 2.5 R/hr g Any of the following valid Forms Indicates levels exceeding 4

10 cpm above bkgd in any I b) RMG 7, l'JA , 17B, or 18 gaseous effluent monitor readings: 1-rem /hr whole body or 5- n/hr .

'i hour. or greater than 100 R/hr g thyrold at the esclusion area c) RMG-1: greater than i R/hr l) RM-Al3 (Ges) > 0.3 Mr/It above boundary using radiation monitor? 5

3) RM-A4 '(Ges) exceeds 4 times or - Skdg. for 2 min. 064 readings and ef fluent stroom flow i

the high alarm setpoint for 2) Unexpected plant area lodine or rates (measured or assumed) for 6 more the I hour. g particulate alrborne mncentratfor 2) RM-AI4 (Ges) > 2.2 mR/hr. above greater than 1000 MPC.

actualmeteorologicalconditionsj bkgd. For 0.5 hr. g > 22 mR/hr or measured in-situ.

I 4) Iti-A4 (lodine) In valid

high (as per 10CFR20 Appendix 8, Tabic above bhgd. for 2 min.

l. alarm for more than I hour. 1) l (CONTINUE ON EXT 1%GE) 4-

! I

- i i

S

.s

A valid high alarm will include ver3fication of radioactivity. concentrations In the sampilng media.

e f

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s, i} , ENGlGEN'Y ACTION LEVELS StaemRY

' EPP-001, ATTAQelENI 4:

fM 4 of 13, REVISION 4

,f SYSTEM _

. SITE GE1E m t.. 1;

., INWOLVFD UNUSUAL EVENT ALERT E8ERGEICY E8ERGEICY j;, RR010 LOGICAL : INIT IATim (XNSITION INITIAT116 CO@lTION . INITIAL C08DIT10N

[ ' EFFLUENTS Ligul0 EFFLUENI COEENTRATIONS ,

RADIOLOGICAL EFFLUENT RELEASE MTE DOSE M TES LISTED BEL 0lf ARF

" j. ICON'T ) TECHNICAL SPECIFICATIONS LIMITS OCEEDING 10 TIMES TECHNICAL ~ PROJECTED INSED ON Guem FADIATION 4

,jj. EEEEDED FOR 15 MIN. (APPElelX B SPECIFl(MTION INSTANIAIEOUS MONITOR (1919) READINGS AIS/0R f' lj. TABLE 11 COLlalN 210CFR20). LIMITS. '

j 8, Detection tiethods OTHER PLANI PARR81ETERS (R ARE . . . lt MEASLRED AT THE E)CLUSION AREA t Any of the following IIquid Detection Methods BOUWWlY. - *

} j* effluent monitors In e valid High.

' Alarm for longer then 15 min. and Any of the following # valid Detection Methods g

, isolation velve(s) fall to close radiation monitor readings for '

longer than 15 minutes 1) Reactor Building leek rate

}j, M -L5; or results in calculated dose 3'

m-L7; ~or ,;

a) 8tN-A3 (Gas) increases > 1 X - rate at exclusion arca *.

[ m -L9 106 cpm above bkgd. E boundr y greater the 50

{

l

'.; urem/hr whole body for 0.5 hr3 'i b) m-A3 (todine) Increases > 2 ) or !'

i- .

105 cpm above bkdg. g 500 mrea/hr whole body for 2 I l i min. i i c) RM-A4 (Ges) etceeds 40 times or '

j high alarm setpoint g 2) Radiation Monitoring Teams ~

' measures dose rates yeaf sr i d) RM-A4. (lodine) asiceeds 10 - than 50 aren/hr for 0.5 hr or j i!

\ times high alarm setpoint.

or greater then 500 aren/hr for 2 min. (beta + gamme) at-the

{j j *i j

' exclusion aree boundary; or , ;,

e) - RM-LS, M-L7, or M-L9 earceeds j 10 times high alarm setpoint . 3) Radletion Monitoring Teams i

and Isolation valves fall to measure thyrold dose rates -

l close. (equivalent 1-131-i .t l; J i concentrations) greater thans t

(

a) 250 mren/hr (1.3x10-7 - lI C1/cc for 0.5 hrs or 1 ll ,

b)-' 2500 aren/hr (1.3xtD '*

C1/oc) for 2 min at the , '!

1 } .- acclusloes area boundary.

l '

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A valid, high alarm will include verification of radioactivity concentration in the samplin0 media. '

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EMERGENCY ACTION LEVELS Stat 4ARY F

j .

EPP-0UI, ATTAOSIENT I PAGE 5 of 13, REVISION 4 I SYSTDI SITE GEERAL

, INVOLVED UNUSUAL EVENT ALERT EMERGENCY EMERGCICY 1

g FUEL INITIATING COBOITION INITIATING COMITION I

INITIATING CopelTION INitlATING COWITION

< , DAMAGE FtEL DAMAGE IIelCATION.

'I POSSIBLE FUEL DAMAGE. DE MADED CORE WITH POSSIBLE LOSS LOSS OF hfo & TlftEE FISSION , ,

} OF Q)0UBLE E00ETRY. - PRODUCT BARRIER WITH R)TENTIAL Detection Method: Detection Method:

1 ' LOSS OF THE THIRD GARRIER (e.g.,

Detection Method LOSS OF FUEL INTEGRITY AND M-Lt High alare; and Laboratory it4-LI High Alarms and Laboratory jj - {' !f' analysis which Indicates dose. analysis uhlch Indicates dose PRIMARY COOLANT BOU WARY AND Hiel 'j t i equivalent 3-131 activity POTENTIAL FOR RADIGACTIVITY equivalent 1-138 activity Wide Range Tht above 700*F, g RELEASE FROM CONTAllt4ENT j { concentration 1 3033Cl/ge. In the concentration 2 300)lCl/gm In the Thot and Tcold i ! primary coolant. Primary coolant, t

.; 1 rapidly diverging ( T rapidly Detection Methods i'l increasing) E no T across core; and Itt-Li offocale (greater than j , ,' 1) LOCA and Containment isolation E cpm) status lights Indicate 4 incomplete Isolation

i(

INITIATING C00mlT10N -

t

-or-j .

MAJOR DAMAGE TO M(RE THAN GE

)

I SPENT FUEL ASSEMBLY IN REACTOR 2) LOCA; and j

INITI ATING C0pelTION BUILDINS Ot FUEL OfueLING BUILDINE ftt-A2 high alare; and j

{

~

LEADING TO CLAD RUPTtRE (e.g., It4G-7 and/or 194G-18 reading '

FUEL HA89 LINS ACCIDENT WITH LARGE GlJECT DAMAGES FUEL 04 NATS greater it:an 10 4R/ hrs and

} f RELEASE OF RADIDACTIVITY TO j;' LOSS BELON FUEL LEVEL).- Reactor Building pressure REACTGt (R FUEL 1%) SLING BUILDING, j- l greater then 30 psig for.at Detection Methods least 2 ein.

ll Detection Methods or .

j, Observations of major damag'e to 3) Eeach of containment Observation of damage to spent more than oce spent fuel assembly Integrity (Reactor Bullding)

, fuel assembly; and or i' and Itt-LI of f-scale (> 106 Spent fuel pool water below fuel cpe)

{ 1) IDI-A2 high alors and/or level and _,

ft4G-17A, 118 high alarm after 4

accident in Reactor Bulldings I) Iti-A2 and/or It4G-17A, 178 higt '

- or alarm for accident in Reactor

2) E-A6 high alarm; g Building g j ft4G-8 high alare; 2) Iti-A6 and/or ft4G-8 high alare 4

Ii after accident in fuel for accident in Fuel Handling

. Handling Building. -

Building I' -l I 1 i

i 4 ..

i 4'

, , ,_ . . _ , . . . . . , . > a - - "' - -

?

1

} EMERGENCY ACTION LEVELS SL90mRY

b l

EPP-001, ATTADetENI 1 PAGE 6 of 13, REVISIG14 l

^

SYSTEM I,

' SITE . GEERAL l IDWOLVED UNUStML EVENT ALERT EleERGENCY EERGEEY

, STATION - INITIATING CONDITION INITIATl8G COBOITION INSTIATim ColelTION INITIATim CoselTION

I IUWER TOTAL LOSS OF OFFSITE POWER OR LOSS LOSS OF OFFSITE 19wER AND LOSS of LOSS OF OFFSITE R)WER A80 LOSS OF FAILLRE OF OFFSITE A80 ON ,

0F ONSITE A-C POWER CAPABIL15 ALL ONSITE A-C IUWER FGt N(RE -ONSITE A-C POWER FOR MWtE TMN 15 ~ POWER ALONG WITH TOTAL IDSS OF TMN 5 MINUIES MIN. EMERGEEY FEEDNATER mIIELP Detection Method: CAPA81LITY FOR SEVETML QlstS.

.; j ' Detection Method: Detection Method: . COULD LEAD TO EVENILML CWtE ELT l*

I: Loss of 115 KV and 230 KV ESF A80 POSSIBLE FAllistE OF TIE

!4 I) Loss of 115 KV and 230 KV ESF I) Loss of 115 KV and 230 MV Potential Lights REACTOR BUILDING. ',

Potential Lights ESF. Potential Lights and

and .and 2) A or 8 Trn. Blackout Seq.

' Detection Method: l

2) A or B Trn. Blackout Seq. Int. Alarm i

2) ' A or B Trn Blackout Seq. Int. Int. Alarm and i 3 I)' Loss of 115 %v and 230 KV ESF.

A lam and- 3) Both Diesel Generators *Pbtential Lights. -l l5 g 3) Both Diesel Generator Inoperable, and,

,I

,: t Inoperable - - - - - - - - - - - - - - - - - 2) A rr B Trn. Blackout Seq.' int.

ll 53 Both Diesel Generators --'-------------- INITIATips CopelTION Al' ara j Inoperable for> 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months INITIATIDG CoselTION LOSS OF ALL VITAL ONSITE D4 g .[i LOSS OF ALL ONSITE D{ POWER FOR POWER FOR MGtE TMN 15 MIN. 3) Both Diesel Generator,s j

j A PERIOD GREATER TMN 5 MINUTES. Detection Method Inoperable. '

' and i

Detection Method: 1) 0-C bus undervoltage alarms or 4) Steam driven Emergency

;i all buses; . Feedwater pump falls to start [,l l ,.

g j;; l) D-C bus undervoltage alarms 2) 480V ESF Channel A or B Loss and is inoperable for saveral hours.

l

?

'i on all buses; and of IE Alare 2*d l 2) 480 Y ESF Channel A or 8 Loss 3) DG A or B Loss of DC Alarm .

of DC Alarm and_ -----------------

i

' INITIATING Cole 1 TION I i' i

3) DG A or 8 Loss of DC Alarm LOSS OF FLSCTIONS DEEDED FOR

,, PIANI HDT SHUTDOWN.

j [

, Detection 14ethod j i !

{ j j 1) Inability to establish

g -

charglieg pump Injections anj ,

Inability to estabilsh I j ,

amargency Foodwater Flow. . i'.

E *'6 ;

' 2) RI5t System not functional c 4 l !

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EMERGEICT ACTION LEVELS SteemRY -

EPP-001, ATTADelElf I i ,i 19tGE 7 of 13, REVISION 4 .

SYSTEM S ITE . GEERAL lNVOLVED UNUStRL EVENI ALERT EERGEEY EERGEEY t IIElEERED INITIATilG ColDITION INITIATIIG COMITION INITIATim ColelTION INITIATils CopelTION i SAFEGLARDS ECCS INITIATED (COllCIDENT NITH ALL AISIUNCIATOR ALARMS LOST. ALL A100tmCIATORS Ale PLANT TRANSIENI INITIATED BY LOSS OF

{ , POSITIVE FINDING THAT INITIATION 15 COMPUTER LDST FOR MORE THAN 15 FEEDIIATER Ale ColeENSATE SYSTEMS

NDT SPURIOUS). . Detection Method: MINUTES ADO PLANI TRA16lENT (PRINCIPAL HEAT REM 0mL SYSTEMI INITIATED E IN FROGRESS. FOLLONED BY FAlltRE OF EMERGENCY Detection Method Observation by operator. FEE 00mTER SYSTEM Fm EXTEIWED -

,, Detection Method: PERIOD. cme ELTING FOSSIBLE IN j

Valid Safety injection Signal SEVERAL HDLRS. ULTilmTE FAILm E i

Observation of event. OF REACTm BUILDING FOSSIBLE IF . !

l INITIATING C00elT10N cme MELTS.

-- ~

EECLATION OF (X)NIROL ROOM -----------------

INITIATING C0lGITION ANIICIPATED (R RE@lRED WITH INITIATING COBOITION Detection Method: !

FAlttRE OF A IRESSLRlZER OR STEAM CONTROL OF SHUTDONN SYSTEM - EmCLATION OF CONTROL ROOM AfD

l. GENERATOR SAFETY OR RELIEF MLVE T( .l ESTA8LISHED FROM LDCAL STATIONS. CONTROL OF SHUIDONN SYSTEMS ICT Reactor trip on steem flow >

t t RESEAT (E)CEEDING ICRMAL NEEPAGEl.

iI .ESTA8LISHED FROM LDCAL STATIONS feedwater flows and .I IN 15 MIN. Decreasing wide-range steen '[

iI4- Detection MethM Detection Method generator levels toward of f-scale !'

,3 1ow on atI steen generators; [

! Pressurizer or steam generator Detection Method: g. t

,I safety or rollef valve, opens and II Emergency feedwater flow then falls to reset as Indicated Indicators . Indicate zero flow

i by: Same as initiating event.

I 2 min. ef ter requireds a or f

!' I) Valid open Inalcation of Same es initleting atmdition.

5-212 Status lamps Indicate Pressurizer rollet or safety energency foodwater pumps not valve position Indication t:

lights running 2 min. ef ter requireds {.

g M i ;

3) Emergency Feedwater cannot bo ;

g valid acoustical monitor Indication. restored .wlthin 30 min. . !{

!I or '

2) Visual ed/or andIble ,

t indication at vent stacks of '{i open steen generator safety or f

j relief valve; E

'I Excess feedwater flow to and J!

, 4 ,

steam flow from ef fected generator. I t,it q .

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? EMERGENCY ACTION LEVELS StMMRY EPP-001, ATTACiteENT l 4

' PAE 8 of 13, REVISION 4

+

SYSTEM SITE GENERAL INVOLVED UNU$tML EwENT ALERT EMERGENCY EERGEICY EIGINEERED INITIATING COWITION INITIATING COWITION INITIATING CON 0lTION SAFEQUARDS LOSS OF ENGINEERED SAFETY FEATtRE REACT (R COOLANT PUMP LDCMD ROTOF TRANSIENT etEQuiRING OPERATION OF

' ' (CON'T ) FUNCTION REQUIRING TECHNICAL WITH FUEL IW MGE. SHUTDOWN S1 STEMS WITH FAlLlRE TO 6 SPECIFICf. TION SHUTDOWN. (TECHNI-TRIP WHICH RESULTS IN CORE OUTAGE CAL SPECIFICATIONS 3.3.2) Detection Method: OR ADDITI0fAL FAILtRE OF WRE Reactor coolant pump acto trip ,

COOLING Am NLELP SYSTEMS WilCH

+

Detection Methods alarm; and COULO LEAD TO C(RE ELT.

,' I) Engineered Safety Features Reactor E p on low

i

) j Activation System found Inop- coolarit flow; g Detection Method:

} erable Reecfor cooIant pump phase aver l1 -----------------

current relay actuation; a_nd,

,n Reactor remains critical af ter 4

};

8 INITIATING CO60lTION valid RML-1 Alarm. attempted trip g

' IPolCATIONS OR ALARMS ON FROCESS l OR EFFLUENT PARAMETERS NOT FUNCTIONAL IN THE CONTROL ROOM TO -----------------

I) RML-1. alarm, g

,f AN EXTENT REQUIRING SHUT 00WN AS INITIATING CONDITION j PER TECHNICAL SPECIFICATIONSI OR,

2) Flow Indicators on safety LOSS OF ALL FUNCTIONS EEDED Fm injection system and IHL systems

; i, OTHER SIGNIFICANT LOSS OF PLANT COLD SHUTDOWN.

1 show zero flow with safety ASSESSNENT OR COMMUNICAT10N

, j CAPABI LIT Y. Detection Methods Injection Inltlated. E 3 ,

3) Status lights show safety i ; Detection Method 1) Loss of RtR system not functional and injection system and Rift pumps 1

j lJ Radiation Monitoring System; or 2)

Loss of all meteorological systems Inability to reject heat to the condenser.

not running with safety b Injection Initiated.

$' E.,

j 3) Significant loss of 1 6 commuplcation capability offsite. ----------------- '

i g INITIATING C0lelTION 7 FAILtRE OF THE REACTOR PROTECTIOP e

SYSTEM TO INITIATE AfD COMPLETE #

k TRIP WHICH BRINGS THE REACTOR

{. SLBCRIT ICAL.

-c.i Detection Method:

i Reactor remains criticai af ter trip initiation.

. s l

1 4:

h EMERGENCY ACTION LEVELS SL804ARY g

EPP-00ldATTAOetENTI- !

PAGE 9 of 13, REVISICAI 4 7' SYSTEM SITE GEERAL I INWOLVED UNUSUAL EVENT ALERT EMERENCY t I EMERGEEY FIRE INITIATING CONDITION INITIATING COWITION INITIATING CO W ITl0>4 '

>t FIRE LASTING MORE THAN 15 MINS. FIRE PDTENTIALLY AFFECTING FIRE MFECTING SAFETY TRAINS Gt l SAFETY SYSTEMS. FUNCTIONS. l Detection Method:

Detection Method Detection Method

v l Observation w fire detection device alarm with confirming Observation of fire that could Observation of mejor fire that I observatten Indicating a fire effect one or more safety defeats both trains of a safety lasting more than 15 min. systems. ;,

l system or function. .

2 l t i ..

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i-o ENERGENCY ACTION LEVELS SteemRY EPP-001, ATTAQ94ENT l' '

PAGE 10 of 13, HEVISION 4 -

SYSTEM lNVOLVED

, SITE GEleHL .

UNUSlRL EVENT ALERT l ENRGEICY . E8etGEEY '

SEctRITY INITIAT18G C00 GIT 10N INITIATipG C000lT10N

1. INITIATING C0lelTION INITIATIM3 CopolTION f

! . SECtRITY THREAT OR ATTEMPTED ENTR1 ' ONGOING SEVERE SECtRITY T)REAT SECLRITY TrREAT INWLVING SECIRITY TmeiAT RESULTlNG IN LOSS Ii .

OR ATTEDFTED SABOIAGE. l lWilNENT IDSS OF IHYSICAL CONTROL ' OF IHYSICAL Q)lffROL & T)E - 1

.l Detection Method W THE PLA N . FACILITY. -

Detection Method: Security.sefoguards contingency .

I event which results in Detection Metl od - Detection Nothod '

l) Report to the Control Room by . adversarles %deering en

'. ; Jobserver, _

Physical attack on the Plant eroe of the plant, but not or impacting shutdown capability, Phtsical attack on the Plant hos j involving launInent occupancy of resulted in occupation of the 21 Alarm of Integrated Fire and control room and auxillery i,l. . Security Penet. control room and the auxillery . '

. shutdown panels. shutdown panels by unauthorlaed '

! ~. ,

personnel.

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~I EMERGEEY ACTION LEVELS SiwaRY EPP-001, ATTA000ENI'I

[ ..

MGE 11 of 13, REVISION 4

<l +

SYSTEM.

l{ SITE GEERAL 6 INWOLVED IMfSUAL EVENT ALERT .

EMERGENCY EERGEICY "

MTtRAL L

, f INITIATING CONDITION INITIATING CopelTION INITIATING C000lTl0N

. PHEIONENON ,

,j NATLRAL EVENIS SEVERE ETLRAL EVENT EAR SITE. SEVERE 16TLRAL IHENONENON BEING EFERIENCED OR M0JECTED NITH

a. ' EARTHQUA E PLANI BOI IN COLD SHUTDOWN.

j - b. TORmDO ON SITE a.' EARTHQUAE REATER THAN THE U j c. HtRRICAE EAR SITE . (CBE) LEVEL a.. EARTHQUAE 9tEATER TMN SSE

, .j b. TORmDD STRIKING FACILITY ?

l

c. SYSTAINED HIRRICAE WINDS LE VELS.

b. SYSTAINED WINDS IN EEESS OF [

l Detection Method F GtEATER TMN 15 MfH 100 MPH ON SITE.

i .';

!}{

Detection Methods 3

a. Seismic Recording System Detection Methods i Start Indication. a) Jelsmic Response Spectrum ~ !!

I' b. Observation of orent. Trouble Annunciator l)

a. Reactor Building Foundation !!

c. Observation of event. b) Observation of event Selsmic Switch (SSE) -

, ! c) Meteorological Monitoring i

System Date or Weather Bureet b. Meteorological Monitoring Report. $

4 System Data.

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EMERGENCY ACTION LEELS StaemRY EPP-001. ATTADetENI 1

~ MGE 12 of 13, REVISION 4 l 1

SYSTEN SITE GEEmL .

.. INVOLVED UNUStML EVENT ALERT EERGEEY EtelGEICY ,

' INITIATits COISITION \'

impemDE INilIATING ColelTION - INITIATIIG Q)selTION

~

I -

PHENONEMON OTHER iMZARDS BElpG EFERIEEED I* OTHER mZAROS BEING EXPERIEEED G 'OTHER IMZARDS BEING EXPERIEEED OR M10JECTED WITH PLANI LOT. IN g PROJECTED WHICH mVE THE POTENTIAL OR PROJECTED WHICH imVE A COLD SHUIDONN: ,,

i*

FOR EPOANGERING THE FACILITY SIGNIFICANI FOTENIlAL FM a. AIRCRAFT CRASH INIO VITAL -

.I 3l

. AFFECTING PLANI SAFETY. STRUCTLRES.

a. ONSITE AIRCRAFT 01 ASH. a. AIRCm FT CM SH ON FACILITY. b. MISSILE m EFLOS10N IMPACT -

' b. ONSITE TRAIN CEmlLNENI. . b. . NISSILE INPACTS ON FACILITY ON FACILITY REICERING SEVERE !

c. ONSITE EXPLOSION (EXCLUDING WITK RESULTANI mJOR memGE. m M GE TO SHUIDOWN EQUIPNENT PLAlelED ACTIVITIES). c. MNOWil EFLOSION AT FACILITY c. ENIRY OF T0XIC OR FLApen8LE

,i d. NEAR m ONSITE T0XIC m RESULTING lN m JOR m8m0E TO GASES INIO VITAL AREAS WHICH ;

! FIAlemBLE ES RELEASE OF A PLANI STRUCTLRES m INVOLVE A SIGNIFICANT 1 i, MGNITUDE TmT THREATENS EQUIPNENT.

4 DEGRAMTION OF PLANI. !

PERSONNEL.- d. ENTRY INTO FACILITY ENVIRONS SAFETY. [

l'

e. TIE 18lNE GENERATCR ROTATING OF T0XIC m FLAM EBLE E SES' Detection Nothod: 1

.g COMP 0ENI FAlltRE CAUSING IN CO E ENTRATION WHICH EXCEEE

,; RAPID PLANI SHUTDOWN. THE LINITS OF FLApem81LITY G a) Aircraft crash causing

.jj Detection Nothod T0XICITY. dem:$e or fire in:

,e. TLPSINE GEERATOR FAILURE 1) Reactor Buildings or j m uSING G SING PENETRATION. 2) Control Room; g i a._ Observation of event.

' 3) Auxillary Building: E

b. Observation of event. F ection Nothod: 4) Fuel Handling Buildingsw.

c. Observation of explosion or j'

5) DG Sulldings or g warning from offsite, a) Observation of aircraf t crest 6) Intermediate Building :

d. Observation of release or into Piant structures. 7) SW Intake Structures warning from of fsite.. l b) Observation of missile *

e. . Turbtne trip and observation . Impacts on Plant structures b) Loss of functions needed for of turbine malfunction or .or components. hot situtdown. (see page 6 of falture. c) Observetlon of damage by. this Attachment) explosion.

d) Observation or warning from c) Entry of toxic or flammable j outside the Plants detection gases into:

of geses (using portable Il Control room; y, instrumentation) which exist j

2) Cable spreading rooms; or (

l in concentrations,yhich 3) Reactor ilullding; or j exceed the limits of

4) Switchgear rooms or -:

flammability or toxicity. 5) Safe shutdown panels; g !I e) Turbine trip and observation 61 Emergency diesel of penetration of cosing, ll generator rooms; as detected by. portable in- !,

strumentation anJ which ren-ders a train of a safety- 6 j

related system Inoperable.

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j. . ENERGENCY ACT10N LEVELS SIMERY - EfP-001, ATTACWEN I PAGE 13 of 13. REVISION 4' .

SYSTEN jlt INVOL VED ' UWSIML EVENT ALERT SITE EERGENCY GEEmL .

EDERGEEY -k!

,.! OTHER INITIATING C000lTl0N INITIATING COBOITION INITIATING COBOITION

h

a-

; t' LOSS OF CONTAlletENT INTEstlTY OTHER PLANT C0felTIONS EXIST TIR1 OTHER PLANT 0080lT10NS EXIST Tm1 "

'! ! REQUIRING TECHNICAL SPECIFICATION WGRANT ACTIMTION OF TECHNICAL NMRANT ACTIMTION OF 994GENCY SHUTf10NN ITECHNICAL SPECIFICATION ll 3.6.1.1)

SUPPORT CENTER Als PLACING FACILITIES Ale IMDIATION (

ENERGENCY OPERATIONS FACILITY NONITORING TEAMS AW A 'i PERSOfelEL ON STAM) BY .PRECAIK100mRY PlBLIC NARNING.

T Detection Methods *:

) II Any sufonetic confalnment Detection Method: Detection Method: '

Isolation volve found to be Inoperable g As determined by Emergency As determined by Emergency

2) Reactor Building air lock ll

Director. Director. ,

,i Inoperable g ,

3) Penetrationist fell leek test !

.' (as specti1ed in TechnIcel I SpectfIcetions) .[

I INITIATING C0felTION TIMNSPORTATION OF OVEREXPOSED Ale /DR CONTANilmTED, ' INJURED

?i llelVIDuAL FRON SITE TO HOSPITAL. I f Detection Mett Mr l Same es initiating condition.

j i

g INITIATilG CONDITION t OTHER PLANT CONDITIONS EXIST

i i

l- REQUIRING OTHER THAN lorumL PLAlf '

] SHUTDOWN ADO REQUIRING INCREASED I ANAREhESS ON THE PART OF STATE . -

OFFICIALS. f I

r l

Detectlon Methods i, As determined by Emergency *I 1

Director. ,

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. i l' EPP-001 l l 1

ATTAO#ENT 11 .

1 4 PAGE 1 0F I I[

; REVISION 4

.i !

GEIEAAL EERENCY PROTECTIVE ACIl0N REC 04EN0%TIONS hi C

l4 xxxxxxxxxxxxxx

x EPERAL x .

x EMElWENCY x '

x DECIARED x ;

xxx= ==wx ' (

i ';

i !! *

' RECI)ME.i D SHB.T ER ,

2 MILE RAD.US & 5 MILES -

l~ DQflefi t.*n a(1) (DNTI PUE 'i

, ASSESSMENT _ j!

j NO :i SUBSTNITI AL CDRE DAmGE PAG's (EPP-( 05 ATT. XI I) U i

' f YES IN PROGRESS OR PROJEGED7 ND PROJEGED TO BE EXCEH)ED1 l (AGUAL OR POTENTIAL FOR N j j 205 FUEL DAMAGE) a(2) N YES !!

i LARGE FISSION PRODLET i NO INVENTORY IN CONTAlle4ENTT YES

' RE(DMEND PROTEGIVE ,

'! (MORE 1rlAN GAP) AGIONS IN AC(Df0ANCE 'l i! WITH PAG's (EPP-005 ATT XII) ~

ml 1 1 l IMMINENI PROJEGE0 RE00seEND SHELTER [

j l CONTAll04ENT FAILIRE FOR AREAS THAT CAN8T B4MINENT PRDJEGED 'g l AND CORE DAMAGE OR YES BE EVACUATED SEFORE YES CONTAlletENT FAILLRE OR j i RELEASE UPDERWAY1 PLINE ARRIVAL (2-5 MILE ' RELEASE U80ElWAY7 e a

'; *(3) RADIUS). RE(DMEND e(3) {

EVACUAT10N OF 5-10 -

MILES DQfMWile. NO ..;

NO e (11(4)(5) i RE(DMIEND EVAGAATION j

! RE0000END EVACUATION OF 5 MILE RADIUS AND g i' 0F 2 MILE RADIUS AND 10 MILES DOWiefile 3 I 5 MILES DOWNWlM) 8(l) (4) !:

(l)(4) - .

l 5' i N j e (1) SITUATIONS REQUIRING URGENT ACIl0N BY GOVERNENT OFFICIALS (Based on Control Room Indicators, no dose projectlons required.)

e (2) Actual or Projected Release of 20$ gap fran core or loss of physical control of the plant to intruder 1s.

j # (3) Pufla release (release rate much greater than desigmod leak rate).

ilI a (4) For all evacuations, shelter the remainder of the 10-mile EPZ and promptly relocate the population af facted by any y cund contanInstion g

{ following plume passage.

i .. # (5) Concentrate on evacuation of areas near the plant '(s.g. may be time to evacuate the 2-mile radius and not the 5-mile radius). *,

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! 'i EPP-001 !

is ATTACHMENi III PAGE 1 of 1 REVISION 4 ,

i IMMEDIATE ACTION

SUMMARY

l .

l, 2 I i

UNUSUAL ! ;

', IMMEDIATE ACTIONS EVENT ALERT SITE GENERAL

, i. ANNOUNCEMENT TO PLANT PERSONNEL l 2. SOUND HADIATION EMERGENCY ALARM N/A I

3 NOTIFY 3ECURITY SHIFT LEADER

4. NOTIFY FAIRFIELD PUMP STORAGE FACILITY N/A N/A

5 ENSURE ON-SHIFT PERSONNEL RESPONSE

'j REFER TO ATTACHMENT II FOR ,

6. RECOMMENDED PROTECTIVE ACTIONS N/A N/A N/A NOTIFY LOCAL AUTH OF 1 7 EARLY WARNING SIREN SYSTEM RECOMMENDATION N/A N/A i, 8. ACTIVATE EWSS N/A N/A 9 INITIAL NOTIFICATIONS PER EPP-002

10. EMERGENCY LOG ESTABLISHED ,

12. OFF BITE EMERGENCY SERVICES, IF REQUIRED ACTIVATE TSC/030 OR NOTIFY EMERGENCY

, 12. RESPONSE PERSONNEL N/A 13 NOTIFY OFF-SITE EMERGENCY COORDINATOR N/A ENSURE TSC/OSC ARE ACTIVITED OR EMERGENCY 14 RESPONSE PERSONNEL NOTIFIED -

N/A ENSURE EOF IS ACTIVATED OR EMERGENCY -

I

_15 RESPONSE PERSONNEL NOTIFIED N/A N/A DETERMINE IF SITE EVACUATION IS REQUIRED

. 16. (INCLUDING FAIRFIELD PUMP STORAGE FACILITY) N/A ,

" e e

f .

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e o' SOUTH CAROLINA ELECTRIC AND GAS COMPANY VIRGIL C. SUMMER NUCLEAR STATION NUCLEAR OPERATIONS hh] O

{ g COPY No. . . . . . . . . . ./. 5. . 7. . . .. .. . .

EMERGENCY PLAN PROCEDURE EPP-001 ACTIVATION AND IMPLEMENTATION OF EMERGENCY PLAN REVISION 5 JULY 28, 1983 NON-SAFETY RELATED i) ..

\

Reviewed by:

13 OR(GINATOR7of this revision) ' Uate S Y DIS IFhlNE SUPERVISOR Date Approved:

hfba PLAN'I MANAGER

=-] P/ff94

'Dal e Date Issued:

l

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EPP-001 PAGE 1

.1 REVISION 5 m 7/28/83 LIST OF F.FFECTIVE PAGES

.PAGE REVISION 1 5 11 5 1 5 2 5.

3 5 4 5 5 5 6 5 7 5 8 5 9 5 10 5 11 5 ATTACHMENTS Attachment I Pages'1 thru 13 5

' Attachment II' 5 Attachment III _.

\ 5 4

1 a

d

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. . . . - - ~ . - - - _ - . __ -_ - _ . -. - - . .

EPP-001 PAGE 11 REVISION 5 (

'N 7/28/83 TABLE OF CONTENTS

. _ _ Pa$e List of Effective Pages 1 1.0 PURPOSE 1

2.0 REFERENCES

1 CONDITIONS AND PREREQUISITES 1

3. O 4.0 PROCEDURES 2 4.1 -CLASSIFICATION OF EVENT 2 4.2 IMPLEMENTATION OF EMERGENCY PLAN' 2 UNUSUAL EVENT 2 43 4.4 ALERT 3 6

45 SITE EMERGENCY 4.6 GENERAL EMERGENCY 9

\

ATTACHMENTS Attachment I Emergency Action Level Summaries Attachment II General Emergency Protective Action Recommendations Attachment III Immediate Actions Summary

~u . .-+%..

. .EPP-001 REVISION 5

-> 7/28/83 1.0 PURPOSE To define and implement the Emergency Action Levels (EAL's) that will initiate the Emergency Plan and to provide a means of ,

classifying the emergency.

2.0 REFERENCES

2.1 " Virgil C. Summer Nuclear . Station Radiation Emergency Plar.. "

2.2 NUREG-0654, Cri",eria for Precaration and Evaluation of Radiological Em2rgency Response- Plans and Preparedness in

. Support of Nuclear Power Plants.

23 EPP-021, Activation of the Early Warning Siren System.

2.4 Policy Memorandum No. 25, Is suance, Control, and Usage of Radio Pagers.

25 10CFR50 Applicability of License Conditions and Technical Specifications in an Emergency (7590-01) .

30 CONDITIONS AND PREREQUISITES -

31 The Emergency Plan shall be initiated whenever an

" Initiating Condition" (as defined in Attachment I) has been reached or exceeded.

NOTE: ~The implementation of any specific emergency. plan procedure (except this procedure) does not necessarily implement the Emergency Plan, but may do so at the discretion of the Emergency Director / Interim Emergency.

Director. For example; a small chlorine leak would

' implement the toxic release procedure but'not necessitate implementation of the Emergency Plan; whereas a large release with the potential for affecting the level of safety of the plant would implement the toxic release procedure and the Emergency Plan due to the declaration of Ln Unusual Event.

32 The " Initiating Condition" shall be used to determine the applicable Emergency Action Level (EAL) per Attachment I.

PAGE 1- of 11

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EPP-001 REVISION 5 7/28/63 33 The " Detection Methods" of Attachment I are to be used only as an aid to determine if an " Initiating Condition" has been reached or exceedad. Other detection methods, not listed in Attachment I, may be used to determine if an

" Initiating Condition" exists. The existence of one or more of the detection methods could be but is not necessarily an indication that an " Initiating Condition" exists.

34 Attachment II should be used by the IED/ED as an aid in determining what protective actions should be recommended to government officials when a General Emergency is declared.

35 The Duty Shift Supervisor must concur with any actions.

that depart from a license condition or technical specification in an emergency when such actions are immediately needed to protect the public health and safety. (Reference 2 5) 4.0 PROCEDURES 4.1 Upon recognition of an abnormal plant or site condition the observer shall notify the Shift Supervisor of the potential emergency plant condition.

4.2 The Shift Supervisor shall:

A. Evaluate the conditions and determine the applicable Emergency Action Level (EAL) per the Emergency Action Level Summary, Attachment I.

B. Declare an EAL and implement the Emergency Plan per the applicable section of this procedure.

Unusual Event' (Section 4 3) or Alert (Section 4.4) or Site Emergency (Section 4 5) or General Emergency (Section 4.0) 4.3 Unusual Event 4.3 1 Immediate Actions: (Immediate Action Summary, See Attachment III)~

The Emergency Director (ED) or Interim Emergency Director (IEL') shall accomplish or cause to be accomplished the following:

A. Announce the emergency condition to all plant personnel over the plant paging system.

ATTENTION ALL PERSONNEL:

THE STATION IS IN AN UNUSUAL EVENT CONDITION.

THE INITIATING EVENT IS .

PAGE 2 of 11

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EPP-001 REVISION 5

, *?s 7/28/83 NOTE: [ REPEAT ANNOUNCEMENT 3 B. Notify _ the Security Shif t Leader to implement appropriate security measures.

C. Ensurethaton-shifthersonnelhaveresponded ~

to their emergency response stations.

D.. Ensure that the Initial Notifications are completed-per.EPP-002.

E. Ensure that the Emergency. Log is established and maintained.

F. Request Offsite Emergency Services (Fire, Medical, LLEA, etc.) if required per EPP-002, if necessary.

NOTE: Consideration should be given to access routes taken.

432 Pollow-Up Actions :

The.ED/IED shall continually assess the status of

-- the Unusual' Event per Attachment I-for possible escalation to -a higher emergency classification or termination of emergency condition.

4.3 3 Final Actions:

When the emergency condition has cleared, close out the Unusual Event with a verbal summary to offsite authorities within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months :and close out of the Emergency Log.

4.4- Alert

, 4.4.1 Immediate Actions (ED/IED): (Immediate Action l

Summary, Attachment III) l The Emergency Director (ED) or Interim Emergency

Director (IED) shall accomplish or cause to be accomplished the following:

I I

w PAGE 3 of 11

_ . _ . . . _ _ . . . . . _ _ _ _ . _ . _ _ _ _ _ _ . _ . _ . . .~._. . - _ .

A EPP-001

~~

REVISION 5 7/28/83 A. Announce the emergency condition to all plant personnel over the plant paging system.

ATTENTION ALL PERSONNEL:

THE STATION IS IN AN ALERT CONDITION, THE INITIATING EVENT IS .

ALL EMERGENCY RESPONSE PERSONNEL REPORT TO THEIR STATIONS. -

B. If necessary, sound the Radiation Emergency Alarm. .

C. Repeat the announcement.

NOTE: [ Repeat steps A, B, and C every two minutes for six minutes.3 D. Notify the Security Shif t Leader to implement app'r opriate security measures.

NOTE: With concurrance from the Duty Shift I Supervisor, actions that depart from license !

conditions and Technical Specifications may be taken in an emergency when such actions are immediately needed to protect the public health and safety. Document in the Emergency Director's Log. Notify Plant Management and the NRC Operations Center as soon as possible.

E. Ensure that on-shift personnel have responded to their emergency response stations.

F. During off-normal hours, call in emergency response personnel by activating the SCE&G Radio Pager System as per Policy Memorandum No.

l 25.

G. Ensure that the Initial Notifications are completed per EPP-002.

H. Ensure that the Emergency Log is established and maintained.

I. Reques t Off site Emergency Services (Fire, Medical, LLEA, etc.) if required per EPP-002.

NOTE: Consideration should be given to access routes taken.

PAGE 4 of 11

l EPP-001 i REVISION 5 l 7/28/83 l J. Ensure that TSO/OSC are being activateo per I EPP-016 and/or notification of Emergency Response Personnel is initiated per EPP-002.

K. Determine if the site evacuation is required.

(Including Fairfield Pump Storage Facility) .

4.4.2 Immediate Actions ( All other personnel):

A. Emergency Response Personnel report to their designated stations.

B. Non-essential personnel continue assigned duties and await further instructions.

C. If the radiation emergency alarm is initiated, all Personnel in the Ra'diation Control Area report to the Radiation Access Control Area on the 412' level of the Control Building.

4.4 3 Follow-up Actions The ED/IED shall:

A. Notify the Offsite Emergency Coordinator of the emergency and current plant conditions.

B. Verify that the TSC/OSC are manned and activated per EPP-016.

C. Ensure that updated follow-up notifications are made per EPP-002.

D. Continue assessments and corrective actions to mitigate the emergency condition and flace the plant into a safe and controlled condition.

E. Make assignments to his staff to mitigate the emergency conditions per established Emergency Plan Procedures (EPP's) or as required for conditions not covered by procedures.

F. Continually assess the status of the Alert condition per Attachment I for possible escalation to a higher emergency classification, down-grading to an Unusual Event, or close out of emergency condition.

PAGE 5 of 11

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EPP-001 REVISION 5

'% 7/28/83 4.4.4 Final Actions:

.l A. When emergency conditions clear to allow-for close out or down-grading of the Alert condition, the ED shall ensure that offsite authorities are:

1. Notified . verbally by normal ~ emergency communications.

2. Provided with a written summary within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months of the close out of the'emercency or down-grade of the emergency classification.

B Initiate EPP-017, Post-Recovery and Re-Entry as required.

45 Site Emergency 451 Immediate Actions (ED/IED): (Immediate Action Summary, see Attachment III)

The Emergency Director (ED) or Int'erim ' Emergency Director (IED) shall accomplish or cause to be accomplished the;following:

A. Announce the emergency condition and site ~

-evacuation to all plant personnel over the plant paging system.

ATTENTION ALL PERSONNEL:

THE STATION IS IN A SITE EMERGENCY CONDITION. THE INITIATING EVENT IS .

ALL EMERGENCY RESPONSE PERSONNEL REPORT TO THEIR l

STATIONS.

ALL NON-ESSENTIAL PERSONNEL EVACUATE THE SITE PROCEED TO' ,

i B. Sound the Radiation Emergency Alarm.

C. Repeat the announcement.

NOTE: [ Repeat eteps A, B, and C every .two l minutes for six minutes.]

l PAGE 6 of 11

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EPP-001 REVISION 5 7/28/83 D. Notify the Security Shif t Leader to implement appropriate security measures.

~ ~

'E. Notify the Fairfield Pump Storage Facility of site evacuation.

-F. Implement EPP-021.

NOTE: With concurrance from the Duty Shift Supervisor, actions that depart from license conditions and Technical Specifications may be taken in an emergency when such actions are immediately.needed to protect the public health and safety. Document in the Emergency Director's Log. Notify Plant Management and the NRC Operations Center as soon as possible.

G. During off-normal hours, call in Emergency Response Personnel by activating the SCE&G Radio Pager System as per Policy Memorandum No.

25 H. Ensure that on-shift personnel have responded to their. emergency response stations.

I. Ensure that the Initial Notifications are completed per EPP-002.

J. Ensure that'the Emergency Log is established =

and maintained.

K. Request Offsite Emergency Services (Fire, Medical, LLEA, etc. ) if ' required per EPP-002.

NOTE: Consideration should be given to access routes taken.

L. Notify the Offsite Emergency Coordinator of the emergency and current plant conditions.

M. Ensure that TSC/OSC/ EOF are being activated per EPP-016 and/or notification of Emergency Response Personnel is initiated per EPP-002.

4.5 2 Immediate Actions (All other personnel):

g A. Emergency Response Personnel report to their designated stations.

B. Non-essential personnel evacuate the site, proceed to their private residence or offsite holding area as designated by the ED, and await further instructions.

PAGE 7 of 11

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EPP-001 REVISION 5 7/28/83

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C. Personnel in the Radiation Control Area report to the Radiation Access Control Area on the 412' level of the Control Building, unissa otherwise directed.

453 Follow-Up Actions A. Verify that the TSC/OSC/ EOF are manned and activated per EPP-016.

B. Ensure that 2pdated follow-up notifications are made per EPP-002.

C. Continue assessments and corrective actions to mitigate the emergency condition and place the plant into a safe and controlled condition.

D. Make assignments to his staff to mitigate the emergency conditions per established Emcagency Plan Procedures (EPP's) or as required for conditions not covered by procedures.

E. Continually assess the statue of the Site Emergency condition per Attachment I for possible escalation to a higher emergency classification, down-grading to an Unusual Event, or Alert, or close out of emergency condition.

F. Verify site evacuation is complete and all personnel are accounted for. (Including Fairfield Pump Storage Personnel).

4.5.4 Final Actions:

A. When emergency conditions clear to allow for close out or down-grading of the Site Emergency

> condition, the ED shall ensure that offsite authorities are:

1. Notified verbally by normal emergency communications.

and 2. Provided with a written swnmary within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months of the close out of the emergency or down-grade of the emergency classification.

B. Initiate EPP-017, Post-Recovery and Re-Entry as required.

PAGE 8 of 11

EPP-001 REVISION 5 7/28/83

N 4.6 General Emergency 4.6.1 Immediate Actions (ED/IED): (Immediate Action Summary, see Attachment II)

The Emergency Director (ED) or Interim '.

Emergency Director (IED) shall accomplish or cause to-be accomplished the following:

A. Announce the emergency condition and site evacuation to all plant personnel over the plant paging system.

ATTENTION ALL PERSONNEL:

THE STATION IS IN A GENERAL EMERGENCY CONDITION. THE INTIATING EVENT IS .

ALL EMERGENCY RESPONSE PERSONNEL REPORT TO THEIR STATIONS.

ALL NON-ESSENTIAL PERSONNEL EVACUATE THE SITE.

PROCEED TO .

B. Sound the Radiation Emergency Alarm.'

O. Repeat the announcement.

NOTE: [ Repeat steps A, B, and C every two minutes for six minutes].

D. Notify the Security Shif t Leader to implement appropriate security measures.

E. Notify the Fairfield Pump Storage Facility of Site Evacuation.

F. Refer to Attachment II for recommended protective actions for offsite areas.

G. Implement JPP 021.

NOTE: With concurransu --

the Duty Shif t Supervisor, action. ' depart from license conditions and Technica. attications may be taken in an emergency wn, mb actions are immediately needed to protes a public health and safety. Document in the Emergency Director's Log. Notify Planc Mana6ement and the NRC Operations Center as soon as possible.

PAGE 9 of 11

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EPP-001 REVISION-5 7/28/83 H.- During off-normal- hours, call in Emergency Response Personnel by activating the SCE&G Radio Pager System ~ as per Policy Memorandum No.

25 I. Ensure that on-shift' personnel have responded to their emergency response stations.

J. Ensure that the Initial Notifications are completed per EPP-002.

K. Ensure that the Emergency Log is established and maintained.

L. Request offsite Emergency Services (Fire, Medical, LLEA, etc. ) if required per EPP-002.

NOTE: Consideration should be given to access routes taken.

M. Notify the Offsite Emergency Coordinator of the emergency and current plant condition.

N. Ensure that TSC/OSC/ EOF are being activated per EPP-016 and/or notificatic 2 of Emergency Response Personnel is initiated per EPP-002.

. 4.6.2 Immediate Actions ( All other personnel) b A. Emergency Response Personnel report to-their designated stations.

B. Non-essential personnel evacuate the site, proceed to their private residence or offsite holding a as designated by the ED, await furthe r - ins tru ctions .

C. Personnel in the Radiation Control Area report to the Radiation Access Control Area on the

'412' level of th~e Control Building, unless otherwise directed.

1 3

1 PA'GE 10 of 11

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EPP-001 REVISION 5

/w 7/28/83 4.6 3 Follow-up Actions The-ED/IED shall:

A. Verify that the TSC/OSC/ EOF are manned and activated per EPP-016.

.B. Ensure that updated follow-up notifications are made per EPP-002.

C. Continue assessments and corrective actions to .

mitigate the emergency condition and place the

. plant into a safe and' controlled condition.

~

D. Make assignments to his staff to mitigate the emergency conditions per established Emergency Plan Procedures (EPP's) or as required for conditions.not covered by procedures.

E.- Continually assess .the status of the General' Emergency condition per Attachment I for

-possible down-grading to an Unusual Event, Aler t , or Site Emergency, or close out of emergency condition.

F. Verify ~ site evacuation is complete and all

. personnel are accounted for. (Including Fairfield Pump Storage Personnel).

4.6.4 Final Actions:

A. When emergency conditions clear to allow for close out or down-grading of the General ;

Emergency condition,-the ED shall ensure that offsite authorities are:

l 1. Notified-verbally by normal emergency communications.

2. Provided with a written summary within 8 t

hours of the close out of the emergency or

! down-grade of the emergency classification.

B. Initiate EPP-017,-Post-Recovery and Re-Entry as required. ,

l PAGE 11 of 11

EPP-001, ATTAQMENf a EMERGEICf N: TION LEVELS SM4ARY PAGE I of 13, REVISION 5 S1TE GENERAL SYSTD4 EMERGEICf EMERGEPCf ;

ALERT 1NV&VED UMJSUAL EVENT INITI ATitG C060lTION INITI ATitG C0pOITION INITIATING COtolTION lHITI ATi>G C0tolTION CEACT01 KNOWN LOSS-Of-CORANT ACCIDENT SMALL APO LARGE LOCAs WITH FAILURE EEEEDlNG TECHNICAL SPECIFICATION RAPlO FAILURE & SEVERAL STEAM C01 ANT (LOCA) GREATER THAN OiARGING FUMP OF ECCS TO PERF004 LEADING TO GENERAT01 10BES (e.g., SEVERAL SY STD4 PRIMARf TO SEC0tOARf 01 PRIMARf CAPAPITY. SEVERE C0th OEGRADATION 01 E LT.

SYSTEM LEAK RATES HutORED GPM PRIMARY-TO-SEC0tOARY i ULTIMATE FAILURE & REACT 0t LEAK RATE).

Detection Method: BUILDING POSSIBLE Fm MELTDOWN

< Detection Method: Pressurizer low pressure reactor SEQJEICES.

Primary to secondary leak rate Detection Method: I l trip; and grer.ter than I gpa total for more Detection Method: 0; t

' than 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or greater than 500 Pressurizar low pressure alarm anc Pressurizer low pressure safety '

reactor trip; and Irdection signal, a d I gpd per steam generator as High Reactor Building pressure, Safety Ird ection signal with ,

identified by dally RCS leakage Pressurizer low level alare; and ad reactor trip; a M evaluation; g RM-A9, Gl9A, Gl48, or Gl9C val id 1) Status lamps Indicate safety high alarm; and High Reactor Building sump level i Primary system leak rate greater ad ; Irdection and RHR oumps not than those specified in Technical Steam generator water level I l High Reactor Building humidity; running: E Specif ication 3.4.6.2 as identitlet rapidly increast rg in one or more ad 2) Flow Indicators for Safety

}

! by dally RCS leakage evaluation, steam generator (s), f alling in the injection System read zero; aM others; E d, RM-A2 high alarm

! RMG-5, I44G-7, R4G-18, high alarm; ,

i) > 0 pressure toundary leakage RM-L3, or RM-LIO valid high alarm

----------------- and RM-A2 high alarm; [

2) > l gpm unidentitled for more and !

Possible Bliting of steam INITIATilG C0tolTION '

than 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months RAPID FAILURE & SEVERAL STEAM

3) > 10 gpm identitled RCS leakage generator PRV's and/or safety ------------------

valves. GEERATot 10BES (SEVERAL HJ#0 RED ior more than 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . GPM PRIMARY-TO-SEC0tOARY LEAK INITIATlHG C0tolT10tv

4) > 33 gpo controlled leakage (at RATE) WITH LCSS 7 GFSITE POWER. SMALL LOCA APO INITIALLY SJCCESSFUL 2235 f,20 psig for more than 4 ECCS. SJBSEQJENT FAILURE &

- brs.) INITIATitG C0tolTION REACT 01 BulLDING EAT REM 0/AL ,

REACTOR CORANT LEAKAGE RATE Detection Method

5) >_ l gpm RCS pressure Isolation SYSTEMS OVER SEVERAL HQJRS C0JLD l valve per table 3.4-1 f or EXCEEDS 50 G'M.

Pressurizer low pressuro alarm and LEAD TO cme MELT Ato POSSIBLE

_ greater than 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . reactcr trip, og pressurizer level FAILURE & THE REACTG1 allLDING.

INITIATING CorolTION Detection Method:

rapidly decreasing a_nd, ABN0lMAL REACT 01 CORANT TEMP. Pressurizer low-level alarm; a d Detection Method:

APO/OR PRESSURE 01 ABNORMAL FUEL l) Ex:ess;cs Reactor Make-up to Pressurizer low pressure reactor the Volume Control Tank RM-A9, Gl9A, Gl98, or Gl9C valid TEMPERATURE THAT WQJLD llolCATE A high alare; and, loss of IISKV and trip; gd, LOSS & SU8C00 LING MARGIN 01 2) Operational Leakage Test Pressurizer low pressure safety j

Procedure STP-il4.002/ 230 KV ESF potential lights, and 1 OVERPRESSURIZATION.

Steam Generator water level . Irdection signal and I Detection Method: rapidly Ircreasing in one or more I) Rm flow Indicators show zero *

' 1) Reactor Coolant Tavg greater ,

flow af ter shif t to RM is than 590'F; or steam generators, falling in the others; and, attempted and for greater than 2

2) RCS pressure greater than 2310 RM-L3, or RM410 valid high alare; hr. subsequently gRCS psig; g temperature rising, and

3) RCS pressure less than i E5 g 2) Reactor Building spray and l

psig; and core exit temperature Possible lif ting of steam genera- Reactor Building air handling i greater than 620*F as Indicated by for PRV 8 s and/or sa f ety val ves. system fall to fur = tion.

a valid incore thermocouple; or

4) I nadequate Core Cooling Alarm.

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' i ENERGEEY ACTION LEVELS SD64ARY EPP-001,ATTACHMENTk' l PAGE 2 of 15, REVISION 5 I

SY STEM SITE GENERAL a

iNVQ.VED UNJSUAL EVENT ALERT EMERGEICf EMERGE EY STEAM INITl ATING cop 01 TION INITI ATilG C0foiT10N INITIATING CatelTION ,

SYSTEM RAPID SECOPOARf Sf STEM MAJE STEM LIE GREAK (e.g., MAJm STEAM LIE BREAK WITH j DEPRESSURl ZATION. GREATER MAN 6 IN. EQUlVALENT GREATER THAN 50GPM DIANETER) WITH A SIGNIFICANT PRIMARY-TO-SEC0f0ARY LEAKAGE AfD Detection Method: PRIMARf-TD-SEcop0ARY LEAK RATE. INDICATION & FUEL DAMAGE.

j Rapid decrease in S/G pressure; anc, Detectlon Method: Detection Method: ,

l Reduced RCS temperature and

]

pressure; g Rapidly de: reasing reactor Rapidly decremsing reactor !

l Observation of break or steam dump, coolant Tavg, pressurizer Coolant T a yg, relief or safety volve pressure, and pressurizer level; pressurizer pressure and Inadvertently opened. a d RM-L5, or RM-LIO or RM-A9 pressurizer level; and i high alarms; g j i

Il Steam line differential 1) Steam line differential !

pressure, safety Irdection pressure, safety Irdection l

, signal; MHigh Reactor signal; a d Buildirig crossure alarm; High Reactor Bullding l MRM-A2 high alarm for pressure alarm M valid rupture in Reactor Building M-A2 and RM-LI high alarm

-G- ~

and

2) High steam flow and Lo-Lo or

'j l Tavg or low steam 2) High steam flow and Lo Lo pressure safety Irdection Tavg or low steam pressure sig nal for rupture downstrean safety injection signal and of MSIV's. M-A9, Gl9A, Gl98, or Gl9C or

- - - - - -- --- high alarm and RM-LI valid f

INITI AT11C COP 0lTION high alare ~

RAPID CROSS FAILURE & G2 STEAM

, GElERATm TU8E WITH LOSS &

OFFSITE POWER.

-l Detection Methods f i

Pressurizer low pressure alarm )

and reactor trip; and -

Pressurizer low level alarm; a,ind RM-A9, Gl9A, GI98, or Gl9C valid high alarm a d Pressurizer low I pressure safety Ird ection signal; j and loss of 115 KV and 250 KV ESf j Potential Lights; g RM-t3, or RM4_l0 val id high .;

alarms j Jl _ _ _ ______ _ _ _ _ _ _ _ _ _ _ _

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ENERGECY ACTION LEVELS SM4ARY EPP-001, ATTACHMENT I

PAGE 3 of 13, REVISION 5 i

! SY ST84 SITE GENERAL INVa VED UMJSUAL EVENT ALERT EMERGEEY EMERGEET -

RADi&GilCAL INITI ATING C0mlT10N SUSTAllED HIGH RADIATION LEVELS G INITI ATipG COWITIOi4 INITIATim ColOITION i EFFLUENTS GASEQJS EFFLUENT INSTANTANEQJS HIGH AIRB0tNE COWAMINATl0N WHICH RADI ATION MONIT0tS DETECT LEVELS EFFLUENT MONIT0tS DETECT LEVELS .

RELEASE RATE TECHNICAL llOICATES A SEVERE DEGRADATION IN C04RESPopelm To stEATER THAN 50 CatRESPOM) LNG TO 1-REMAR WQ.E BGN SPECIFICATION LIMITS EEEEDED F04 1 THE CONTROL & RAD 10 ACTIVE MREN/HR WHOLE BGN F04 0.5 IR. 04 OR 5-REMAR THfR010 AT THE

, HR. (APPEIOlX B TABLE 11, C&UMN 1 MATERI ALS (e.g., IEREASE & GREATER THAN 500 MREMAR WQ.E E)CLUSION AREA SQJf0ARY USER ACTUAL i 10CFR20) FACT 04 & 1000 IN DIRECT RADIATies BGN F04 2 MIN. (Ot FlVE TIMES METE 04Q.0GICAL C0lolTIONS.

j READINGS). THESE LEVELS TO THE THYROID) AT

, Detection Method: THE ECLUSION AREA SQllOARY F04 Detection Method:

Detection Method: ADVERSE METE 0tG.0GY (PASSilLL F

1) RM-A3 (Ges) I rc reases > 1 X STA81LITY, IK/SEC WilO VELG;lTY). 1) Radiation Monitor levels owceed 105 cpm above bkgd in any I l) Unexpected valid RMG readings those specified for Site Emergency; hour. og as follows: Detectlon Method: M .

i ; a) RMG 2-4, : 8-13, or 16: g reater 2) Calculation on Dose Assessment ,

i

2) RM-A3 (lodine) Ircreases > 8 X than 2.5 R/hr or Any of the following valid Forms Indicates levels awceeding 104 cpm above bkgd in any I b) 144G 7, I h, I ll, or 18 gaseous ef fluent monitor readings: 1-res/hr whole body or 5-res/hr hour, or greater than 100 R/hr or thyrold at the esclusion area c) RMG-l: greater than i R/hr I) RM-Al3 (Ges) > 0.5 Mr/Hr above boundary using radiation monitor

3) RM-A4 (Gas) exceeds 4 times or Bkdg. for 2 min. 04 readirqls and ef fluent stream flow the high alarm setpoint for 2) Unexpected plant area lodine or rates (measured or assumed) for more the I hour, og particulate airborne concentratfor 2) RM-Al4 (Gas) > 2.2 mil /hr. above actual mateorological conditions; greater than 1000 MPC. bkgd. For 0.5 hr. or > 22 mR/hr or measured in-situ.

4) RM-A4 (todine) In valid

high (as per 10CFR20 Appendix B, Table above bkgd. for 2 min.

i alarm for more than I hour. 1)

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(CONTIMIE ON IEXT PAGE)

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A valid high a.larm will include verification of radioactivity concentrations in the sampling media.

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SYSTEM SITE GEERAL '

INV(1.VED UMJSUAL EVENT ALERT EMERGEfCY EMERGEPCf RADIOLOGICAL INITI AYING CO@lTION INITIATING C0mlTION INITIAL C0polT10N EFFLUENTS LIQUID EFFLUENT COPCENTRATIONS RAD 10LG31 CAL EFFLUEP'T RELEASE RATE DOSE RATES LISTED BELOW ARE (CON'T) TECHNICAL SPECIFICATIONS LIMITS EEEEDING 10 TIMES TECHNICAL PROJECTED BASED ON GM44A RADI ATION i EXCEEDED FOR 15 MIN. (APPEpolX B SPECIFICATION INSTANTAEQJS AONITm (RMG) READINGS A10/01

{

TABLE il CQ.UMN 2 10CFR20). L IM ITS. OTHER ftANT PARAMETERS Ol ARE ' i' Detection Method: MEASURED AT THE EELUSION AREA

{ Any of the following liquid Detect ion Methods B QJ t0ARY .

! effluent monitors in

valid High Alarm for longer than 15 min. g Any of the following

valid Detection Methods isolation valve (s) f all to close radiation monitor readings for lorger than 15 minutes l) Remtor Building leak rato l RM-L5; or results in calculated dose i l RM-L h E a) RM-A3 (Gas) Ircreases > 1 X rate at exclusion area l j RM-L9 106 cpm above bkgd. or boundary greater tha 50 t j arem/hr whole body for 0.5 hr; {

j b) RM-A3 (lodine) Increases > 2 ) or -

t, IOS cpm above bkdg. E ~500 mrea/hr sole body for 2 f min.

c) RM-A4 (Gas) exceeds 40 times or high alarm setpoint or ?) Radiation Monitoring Teams measures <bse rates greater l d) RM-A4 (lodine) exceeds

10 than 50 ares /hr for 0.5 hr or .;

! times high alarm setpoint. greater than 500 mres/hr for 2 j or, min. (beta + gamma) at the exclusion area boundary; g '

e) RM-LS, Fe4-L 7, or RM-L9 exceed !

10 times high alarm setpoint 3) Radiation Monitorirg Teams !

ag isolation valves fall to measure thyrold cbse rates close. (equivalont I-131 r concentrations) greater thans al 250 mres/hr (I.3x10-7 ,

CI/cc for 0.5 hr; or ,

b) 2500 arem/hr (1.3xl P CI/cc) for 2 min at the

, exclusion area boundary.

A valid high alarm will Ireluds verification of radioactivity concentration in the sampilig media.

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EMERGEICY ACTION LEVELS

SUMMARY

EPP-OOI, ATTACtNENT I PAGE 5 of 13, REVISION 5 SYSTEM SITE GEERAL INVCLVED UNJSUAL EVENT ALERT EMERGEICY EMERGEPCY FUEL INITI ATING COtolTION INITI ATING COOITION INITI ATING COtolTION INITI ATING C0tolTION DAMAGE FUEL 044 AGE IPOICATION. PESIBLE FUEL DAMAGE. DEGRADED cme WITH POSSIBLE LOSS LOSS & TWO & IlttEE FlSSION

& C00.ABLE EOlETRf. PRGUCT BARRIER WITH POTENTIAL Detection Method Detection Method: LOSS O' lilE THIRD BARRIER (e.g.,

j Detection Methods LOSS & FUEL INTEGll1Y Ato j RM-Li High alarra; a d Laboratory RM-Ll High Alarm; and Laboratory PRIMART COQ ANT BQJ)OARY AM) HlCH analysis which Indicates dose analysis which Indicatos dose POTENTI AL F01 RADIDACTivi1Y I equivalent 1-131 activity equivalent 1-131 activity Widt. Range That above 'JDO*F, and, RELEASE FR04 CONTAltNENT corcentration > 30 Cl/ge, in the con:entration > 300 Cl/gm in the Thot and Tcold primary coolant. primary coolant. rapidly diverging ( T rapidly Detection Method:

Itcreasing) or no T across core; and RM-Li of fscale (greater than 1) LGIA and Containment isolation W cpm) statuUlghts Indicate incomplete Isolation:

i _________________

! lNITI ATitG C0folT10N -or-

! MAJ01 DAMAGE TO MmE THAN ONE SPENT FUEL ASSEteLY IN REACT 01 2) LOCA; and,n BUILDING 01 FUEL hat 0 LING BUILDINE IN-A2 high alarm; and INITIATitG CotolTION LEADitG TO CLAD RIPTURE (e.g., RMG J and/or ING-18 reading FUEL HAPOLING ACCIDENT WITH LARGE GlJECT DAMAGES FUEL 04 WATEF greater than 104 R/hr; and RELEASE & RADIDACTIVITY TO LOSS BELOW FUEL LEVEL). Reactor Building pressure i REACT 01 01 FUEL HAf0 LING BUILDING. greater than 30 psig for at l Detection Method: least 2 min, j Detect ton Method: or_

Observations of major damage to 3) Breach of containment Observation of damage to spent more than one sy nt fuel assembly Integrity (Reactor Building) f uel assembly; and

~

or , and RM-LI of f-scale (> 106 Spent fuel pool water below fuel cpm) l) RM-A2 high alarm and/or level M RMG-l 'A, I b high alarm af ter a:c ident in Reactor Building; l) RM-A2 and/or RMG-1 'A, I B higt or alarm for accident in Reactor

2) PM-A6 high alarm; or, Buil ding o RMG-8 high al arm; 2) RM-A6 and/or RMG-8 high alarm af ter a:cident in Fuel- for a:cident in Fuel Handling Handling Bull ding. Bull ding O

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i f EMERGEMN ACTION LEVELS SJMMARf EPP-001, ATTACHMENT I

! PAGE 6 of 13, REVISION 5 I

! SITE GEERAL SY STEM INvQ.VED UNJSUAL EVENT ALERT EMERGEDCf EMERGEPCY

'f STATION INITIATite CopolTION INITIATING CotolTION INITIATING C0folT10N INITIATile COfOlT10N PNER TOTAL LOSS & GTSITE POWER m LOSS LOSS & EFSITE POWER APO LOSS O LOSS & EFSITE PGtER AIO LOSS G FAILURE & EFSITE AIO 061TE OF ONSITE A C PQfER CAPABILITY ALL ONSITE A-C POWER Fm MmE OrdlTE A-C POWER Fm MmE THAN I: POWER ALONG WITH TOIAL LOSS &

THAN 5 MINJTES M I N, EMERGEICY FEEDWATER MAKEUP f Detection Method: CAPABILITY Fm SEVERAL HQJRS. .

I Detection Method: Detectlon Method: CQJLD LEAD TO EVENTUAL cme MCLT l I) Loss of 115 KV and 230 KV ESF ADO POSSIBLE FAILURE & 1HE

1) Loss of 115 KV and 230 KV ESF I) Loss of 115 KV and 230 KV Potential Lights REACTm BulLDING.

Potential Lights ESF. Potential Lights g '

i I

and and 2) A or B Trn. Blackout Seq. Detection Method:

2) A or B Trn. Blackout Seq. Int. Alarm

, , 2) A or B Trn Blackout Seq. Int. Int. Alarm g 1) Loss of 115 KV and 230 KV ESF.

Alarm M 3) Both Diesel Generators Potential Lights.

! g 3) Both Diesel Generator inoperable, g i Inoperabl e ----------------

2) A or B Trn. Blackout Seq. I nt .

3) Both Diesel Generators ---------------- lHITIATite COBOlTION Alarm ;

inoperable for> l hour INITI ATING C0tolTION LOSS & ALL VITAL ONSITE D-C and i LOSS & ALL ONSITE D C POWER FQt PQdER Fm M(RE lHAN IS MIN. 3) Both Diesel Generators >

.; A PERIG) GREATER THAN 5 MINJTES. Detection Method: Inoperabl e.

I d Detection Method: 1) D-C bus undervoltage alarms or 4) Steam driven Emargency all buses; Feedwater pump falls to start ad and Is Inoperable for several

1) D-C bus undervoltage alarms 2) 480V ESF Channel A or B Loss hours.

on all buses; ag of DC Alarm d

a ri_

2) 480 V ESF Channel A or B Loss 3) DG A or B Loss of DC Alarm of DC Alarm and ----------------

INITIATile C0polTION *

3) DG A or B Loss of DC Alarm LOSS & fulCTIONS EEDED Fm

.- PLANI HOT SpilTDOWN.

Detection Method l) Inability to establish .

charging pump Injections ay ,

I Inability to establish emergency Feedwater flow.

E

2) Rift System not furctional

EMERGEN t ACTION LEVELS

SUMMARY

EPP-001, ATTACl44ENT 4 PAGE 7 of 13, REVISION 5 SYSTEM SITE GEERAL ,l lNWEVED UIUSUAL EVENT ALERT EMERGE EY EMERGEPCY EDGI EERED INITIATING C0polTION INITI ATipG COEITION INITI ATING COPOITION INITI ATi>G C0polT10N SAFEalARDS ECCS INITI ATED (COBElDENT WITH ALL ANNJDCIAT01 ALAft4S LOST. ALL ANeolOIATmS ADO PLANT TRAP 61ENT INITIATED Bf LOSS &

POSITIVE FINDING THAT INITIATION IS C04PUTER LOST F04 MmE THAN 15 FEE 0 WATER ADO COPOENSATE SYSTEMS NOT SPURIQJS). Detection Method: MINJTES ADO PLAl.T NtANSIENT (PRICIPAL HEAT REMOWAL SYSTEM) '

INITIATED Ot IN PROGRESS. FELOWED BY FAILURE & EMERGEEY Detection Method: Observation by operator. FEEDWATER SYSTEM F04 EXTEPOED Detectlon Method: PERIOD. CORE MELTING POSSIBLE IN g Valid Safety injection Signal SEVERAL HQJRS. ULTIMATE FAILURE

-- Observation of event, & REACTOt SUILDING POSSIBLE IF

. INITIATING C0polTION C0tE MELTS.

3 EVACUATION & CONIRE R004 ---------------- !

! lHlTIATING C0polTION ANTICIPATED Ot REQJIRED WITH INITIATING COEITION Detection Method: j i FAILURE & A PRESSURIZER Ot STEAM CONTHQ. & GUTDOWN SYSTEM EVA0JATION & CONTRQ. R004 APO GEERAT01 SAFETY 04 ftELIEF VALVE T(- ESTABLISHED FRO 4 LOCAL STATlDNS. CONTROL & SHJTDOWN SYSTEMS NOT Reactor trip on steam finu > l RESEAT (E)CEEDING N0HMAL WEEPAGE). ESTABLISHED FR04 LOCAL STATIONS f eedwater flow; and, n !

I N 15 M IN. Decreasing wide-range steen

! Detection Method: Detection Method: generator levels toward of f-scale l

low on all steam generators; Pressurizer or steam generator Detection Method: and +

safety or relief valve opens and 1) Emergency feedwater flow i 4 , then falls to reset as Indicated Indicators Indicate zero flow by: Same as initiating event. 2 min, after required; l

Il Valid open Indication of Same as initleting condition. Status lamps indicate 0 Pressurizer relief or safety emergency feedwater pumps not

,j' valve position Indication running 2 min. after required; l ights M

' l, o 3) Emergercy Feedwater cannot be or valid a:oustical monttor restored within 30 min.

I ndic at ion, j or l

2) Visual and/or audible i Indication at vent stacks of l open steam generator safety or ;

reflet valve; o Excess feedwater flow to and -

, steam flow from af facted ger.arator.

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EMERGEEf ACTION LEVELS SJMMARf EPP-001, ATTACtNENT I.

PAGE 8 of 13, REVISION 5 i

( SYSTEM SITE E EPAL INWG.VED UMISUAL EVENT ALERT EMERGEEY f En4ERGEEY

- ti:SIEERED INITIATING C0mlil0N INITI ATim CopolTION -

lNITIATilG C0l@lTION r

SAFQ1ARDS LOSS & ENGINEERED SAFETY FEATURE . REACTGt C0Q. ANT FUDP LG:KED ROTod TRANSIENT REQUIRING (PERATION & i l ICON'T) FUETION REQUIRING TECHNICAL WITH FUEL DAMAGE. SitJTDOWN SYSTEMS WITH FAILURE .TO

+

I SPECIFICATION SHJTDOWN. (TECHNI- TRIP WICH RESULTS IN CGtE DAMAGE -l CAL SPECIFICATIONS 3.3.2) Detection Method: 04 ADDITIONAL FAILURE F CGtE i Rea: tor coolant pump auto trip C0Q.im Ape MAKEUP SYSTEMS WICH Detection Method: alare; and CGALD LEAD TO C04E MELT.

I) Engineered Safety Features Rea: tor trip on low i Activation System found inop- cool ant flow; and Detection Method:

I ;

erable Reactor coolant pump phase over

! ----------------- {

INITIATING C0polT10N current rolay actuatlon; ~ and Reactor remains crItIcel after -

l val Id RML-l Alarm. attempted trip and j INDICATIONS Ot ALARMS ON PRG:ESS j tR EFFLUENT PARAMETERS NOT

'j I) RML-1 alarm, or s

? FUET100ML IN THE C ONTROL R004 TO ----------------

AN EXTENT HEQUIRIN[ OUTDQiN AS INITI ATING CobelTION 2) Flow Indicators on safety PER TECHNICAL SPEC.FICATIONS; G4, LOSS & ALL FUETIONS EEDED FGt injection system and Rift systems ,

OTHER SIGNIFICANT LOSS & PLANT CQ.D SHJTDOWN. show zero flow with safety '

ASSESSMENT G4 COMJNICATION lidection Initiated, or CAPA88LITY. Detectlon Methods -

I

3) Status _ lights show safety :

' Detection Method Il Loss of Rm system not functional and injection system and Rift pumps l Radiation Monitoring System; g 2) Inability to reject heat to the not running with safety i Loss of all meteorological systems condenser. IfQection Initiated.

Br,

3) Significant loss of communication capability of f site. - - - - - -----------

INITIAT16G CopelTION FAILURE & THE REACT 04 PROTECTiot SYSTEM TO INITIATE ADO C04PLETE / !

TRIP WHICH BRINGS lHE REACT 04 (

SU8 CRITICAL.

l Detection Method

\ '

Reactor remains critical af ter trip initiation.

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EMERGEEY ACTION LEVELS Sn44ARY EPP-001,- ATTAONENT I

i PAGE 9 of 13, REVISION 5 I

i SY STEM S1TE GEERAL i INWQ.VED _ UNJSUAl. EVENT ALERT EMERGEEY EMERGEEf flRE INITIATING CO@lTION INITlATilG COWITION INITI ATilG COIGITION FIRE LASTING MGtE THAN 15 NINS. FIRE POTENTIALLY AFFECTifG FIRE AFFECTipG SAFE 1Y TRAINS Gl SAFETT SYSTEMS, FU ET10NS.

Detection Method:

Detectlon Method: - Detection Method:

Observation or fire detection i device alarm with confirming Observation of fire that could Observation of major fire that t observation Indicating a fire affect one or more safety defeats both trains of a safety j lasting more than 15 min. systems. system o_r, function.

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i ENERGEICY ACTION LEVELS SJ844ARY EPP-001, ATTAC>WENT I PAGE 10 of 13, REVISION 5 SYSTEM SITE GENERAL ~

i -

INVQ.VED UMJSUAL EVENT ALERT EMERGEICY EMERGEK:Y j f SECURITY ' INITIATING CO@lTION INITIATING CO@lTION INITI ATipG COWITION ' lNITJATING COWITION SECURITY THREAT 04 ATTEMPTED EP8TRY ONGOING SEVERE SEEURITY THREAT SECURilY THtEAT INVQ.VING SECURITY TH4 EAT RESULTING IN L0sS Ot ATTEMPTED SABOTAGE. IMNIENT LOSS & MSICAL CONTR0L & MSICAL CONTRG. & THE 1 Detection Method: W INE PLANT. FACILITY. [.

Detection Method: Security safeguards contingency - ,

event whIch resutis In DetactIon Method: Detection Method: I l) Report to the Control Room by adversaries commandeering an i observer, area of the plant, but not Physical attack on the Plant Physical attack on the Plant has j g ,lopacting shutdown capabil ity. Involving laminent occupercy of resulted in a:cupation of the i 2) Alarm of integrated Fire and control room and auxillary ' control room and the auxillary I

Security Panel . shutdown panels. shutdown panels by unauthorized [

personnel . I f .

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, EMERGEPCf ACTION LEVELS SJNMARY EPP-00l* ATTActe4ENT I ~

PAGE 11 of 13, REVISION 5 ,

SYSTEM SITE GE ERAL , ,

iHW&VED .UNJSUAL EVENT ALERT EMERGE 80V EMERGESCY NAluRAL lN1TI AT1NG C0polTlON 1NITl ATING COpOIT1ON 1NITIAT19G C0pDITIGN

- PHE N04ENON NAlDRAL EVENTS SEVERE MIURAL EVENT EAR SITE. SEVERE mlDRAL PHENO 4ENON bel >G ,

EWERIEICED m PROJECTED WITH -[

a. EARTHQUAKE PLANT NDT IN cad SUTDOWN. i.

l b. T E NADO m SITE a. EARTHQJAKE mEATER THAN THE

c. tORRICAE EAR SITE (GE) LEVEL .

a. EARTHQJAKE'GtEATER THAN SSE

b. TENADO STRIKING FACILITY . LEVELS.

c. SYSTAIED ttJRRICAE Wlp0S b. ~ SYSTABED WINDS IN EM:ESS & ,

Detection Method: mEATER THAN B NPH 100 MPH ON SITE. }

Detection Method: }

l a. Selsmic Recording System .

Dete: tion Method: j j Start Indication. a) Seismic Response Spectrum j

( b. Observation of event. Trouble Annunciator a. Reactar Buildisg Foundation .

I c. Observation of event. b) Observation of event Selsmic Switch (SSE)

{ c) Meteorological Monitoring System Data or Weather Burea6 .b. Meteorological Monitoring Report. . System Deta. [

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, ENERGEPCf .*CTION LEVELS SJ844ARY EPP-001, ATTActe4ENT I PAGE 12 of 13, REVISION 5 SYSTEM SITE GEIERAL }'

l I!NQ.VED UNJSuAL EVENT ALERT EMERGE 8Cf EMERGEICf INITIATilG COIGITION MAf44ADE INITIATim ColOITION INITIATipG COWITION PHENO 4ENON OTHER HAZARDS BEllG EFERIEICED OTHER HAZARDS BElpG EFERIEICED O- OTHER HAZARDS BEING EWERIEfCED 04 PROJECTED WITH FLANT ICT IN PROJECTED WHICH HAVE THE POTENTIAL 04 FROJECTED WHICH HAVE A CG.D SitJTDOWN:

F04 EMANGERING THE FACILITY SIGNIFlCANT POTENTIAL F04 a. AIRCRAFT OtASH INTO VITA AFFECTING PLANT SAFETf. STRUCRlRES.

-; a. ONSITE AIRCRAFT CRASH. .a. AIRCRAFT CRASH ON FACILITY. b. MISSlLE 04 E#LOS10N 18 FACT

' i- b. De61TE TRAIN DERAILMENT. b. MISSILE IMPACTS 04 FACILITY ON FACILITY RE@ERING SEVERE

c. ONSITE EFLOSION (EELUDING WITH RESULTANT MAJ04 044 AGE. (W4 AGE TO SetlTDOWN E@lPMENT l

ftANNED ACTIVITIES). c. KNOWN EFLOS10N AT FACILITY c. ENTRf E T0XIC 04 FLA144ABLE

, d. EAR G4 ONSITE T0XIC 03 RESULTING IN MAJ04 DM4 AGE TO GASES INTO VITAL AREAS teilCH j FLAMMABLE GAS RELEASE & A PLANT STRUCIURES 04 INVQ.VE A SIGNIFICANT i i MAGNITUDE THAT TH4EATENS EW IPMENT. DEGRADATION 7 PLANT

, PERSONEL. .

d. ENTRY INTO FACILITY ENVIRONS _ SAFETY.

e. IURBINE GENERAT01 ROTATING & T0XIC Ot FLApe4ABLE GASES Detection Method:

C04PONENT FAILURE CAUSING IN C0fCENTRATION WHICH EEEEI' RAPID PLANT SHilTDOWN. THE LIMITS & FLAP 44 ABILITY G a) Aircraft crash causing TOKIC ITY. damage or fire In: ' "

Detection Method: e. IURBifE GEERAT04 FAILURE Il Reactor Building; E CAUSING CASING PEETRATION. 2) Control Room; g-

a. Observation of event. 3) Auxillery Buildirg; y

b. Otservation of event. Detection Method: 4) , Fuel Handling'Bullding;g ,

c. Observation of explosion or 5) DG Buildisg; og j1 warning from ofIsite. a) Observation of aircraf t crast 6) Intermediate Building

d. Observation of release or into Plant structures. 7) SW Intake Structures l warning from of f site, b) Observation of missile

e. Turbine trip and observation impacts on Plant strictures b) Loss of functions needed for of turbine malfun: tion or or components. hot shutdown. (see page 6 of j

{ failure. c) Observation of damage by explosion.

this Attachment) ,j

! t d) Observation or warning from c) Entry of toxic or flammable J i outside the Plant; detection gases into . ,

lj of gases (using portable 1) Control room; og j Instrumentation) which e41st 2) Cable spreading rooms; y,

, in concentrations,which 3) Rea: tor Building; ,og

, exceed the limits of 4) Switchgear rooes or flammability or toxicity. 5) Safe shutdown panel s; y_

. e) Turbine trip.and observation 6) Emergency diesel ,

of penetration of casing, generator rooms;

'l as detected by portable in-strumentation and which ren- j ders a train of a safety-related system inoperable.

+

T

1 EMERGEICY ACTION LEVELS SM4AW EPP-001, ATTACHMENT I ,

, PAGE 13 of 13, REVISION 5 SY STEM SITE ,

GEERAL lNvCLVED UPUSUAL EVENT ALERT EMERGEPCY EMERGEPCf OTHER INITIATING COtolTION INITI ATING C0foIT10N INITIATItG C0tolTION LOSS & CONTAltNENT INTEmlTY OTHER PLANT C0tolTIONS EXIST THAL OTHER PLANT COPOITIONS EXIST THAL RE(UIRING TECHNICAL SPECIFICATION WARRANT ACTIVATION & TECHNICAL WARRANT ACTIVATION & ENERGEfCY f

StuTDOWN (TECHNICAL SPECIFIC ATION SUPPmT CENTER AIO PLACING FACILITIES APO RADIATION 3.6.1.1) EMERGEtCY &ERATIONS FACILITY NONITGING TEAMS Ato A PERSONNEL 04 STAtO BY PRECAUT10teRY RJBLIC WARNING. ,

Detection Method: I l) Any automat Ic containment Detection Method: Detection Methods f Isolation valve found to be

inoperable E As determined by Emergency As de' armined by Emergercy l 2) Reactor Building air lock Director. Oirector.

l Inoperable g i

! 3) Penetration (s) tall leak test (as speelfled in Technical l

t Spec i f ications)

INITI ATING COPOITION ;

TRAtsPmTATION & OVEREXPOSED j AND/0R CONTAMINATED, INJJRED i INDIVIDUAL FRO 4 SITE TO HmPITAL.

4 Detectlon Method:

' Same as init latIng condit lon.

. =

INITIATING COtCITION OTHER PLANT C0tORTIONS EXIST REQtJ1 RING OTHER THAN HQ1 MAL PLANT StuTD(WN Ato REQJtRING ltCREASED AGEESS ON THE PART & STATE -

! &?lC8ALS.

4 Detectlon Method:

! As determined by Emergercy Direc tor.

EPP-001

=

)

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ATTACHMENT 51 i PAE l & I i REVISION 5 GEERAL EMERGEEf PROTECTIVE ACTION REC 094EIOATIONS i XXXXXXXXXXXXXX x GENERAL x x EMERGEPCf x x DECLARED x XXXXXXXXXXXXXX REC 04MEIO SHELTER 2 MILE RADIUS & 5 MILES

, 00WIMite *(l) COPRilOE

ASSESSMENT ,

! NO i

, SUBSTANTIAL cme DAMAGE PAG's (EPP-005 ATT. X11)

Y E1 IN PROGRESS m PROJECTED? NO PROJECTED TO BE EEEEDED (ACTUAL m POTENTI AL FOR 20$ FUEL DAMAGE) *(2) i Y ES LARGE FISSION PRQUCT NO INVENTOW IN CONTAltMENT 7 YES REC 044EPO PROTECTIVE (MmE THAN GAP) ACTIONS IN ACCGtDAPCE WITH PAG's (EPP-005 ATT Xil)

' REC 004Eto SHELTER lMHIENT PROJECTEI CONTAllNENT FAILURE FOR AREAS THAT CAN'T IMMIENT PROJECTED Ato CORE DAMAGE 04 YES BE EVACUATED BEFORE YES CONTAltNENT FAILURE m l RELEASE UtOERWAY 7 PLUME ARRIVAL (2-5 MILE RELEASE UiOERWAY ?

(3) 3A0luS). REC 044Eto ag33

. EVAQJATION & 5-10

MILES 00WNWitO. NO i NO e (I)(4)(5)

, REC 04MEro EiACUATION REC 004EPO EVACUATION OF 5 MILE RADIUS AIO

& 2 HILE RADIUS Ato 10 MILES DQOMite 5 MILES 00ftMite *(l) (4)

ag33g43 i l

(1) SITUATIONS REQJIRilG URGENT ACTION BY GOVERtNENT &FICIALS (Based on Control Room Indicators, no dose project *-'s required.)

(2) Actual or Projected Release of 20$ gap from core or loss of physical control of the plant to intruders. .

8 (3) "Put f" release (release rate much greater than designed leak rate).

e (4) For all evacuations, shelter the remainder of the 10-mile EPZ and.promptly relocate the population af fected by any ground contamination following plume passage.

< * (5) Concentrate on evacuation of areas near the plant (e.g. may be time to evacuate the 2-elle radius and not the 5-mile radius).

1

'I

..b EPP-001

. ATTACHMENT III i

PAGE 1 of 1 REVISION 5 IMMEDIATE ACTION

SUMMARY

UNUSUAL IMMEDIATE ACTIONS EVENT ALERT SITE GENERAL

1. ANNOUNCEMENT TO PLANT PERSONNEL

[. 2. SOUND RADIATION EMERGENCY ALARM N/A 3 NOTIFY SECURITY SHIFT LEADER I 4. NOTIFY FAIRFIELD PUMP STORAGE FACILITY N/A N/A 5 ENSURE ON-SHIFT PERSONNEL RESPONSE REFER TO ATTACHMENT II POR

6. RECOMMENDED PROTECTIVE ACTIONS N/A N/A N/A NOTIFY LOCAL AUTH OF 7 EARLY WARNING SIREN SYSTEM RECOMMENDATION N/A N/A :

i

8. ACTIVATE EWSS N/A N/A f _9 INITIAL NOTIFICATIONS PER EPP-002

10. EMERGENCY LOG ESTABLISHED

12. OFF SITE EMERGENCY SERVICES, IF REQUIRED l ACTIVATE TSC/OSC OR NOTIFY EMEROSNCY

12. RESPONSE PERSONNEL N/A ,

13 NOTIFY OFF-SITE EMERGENCY COORDINATOR N/A ENSURE TSC/OSC ARE ACTIVITED OR EMERGENCY ,

14. RESPONSE PERSONNEL NOTIFIED .

N/A

ENSURE EOF IS ACTIVATED OR EMERGENCY

. 15 RESPONSE PERSONNEL NOTIFIED N/A N/A DETERMINE IF SITE EVACUATION IS REQUIRED

16. (INCLUDING FAIRFIELD PUMP STORAGE FACILITY) N/A 9

. _ . _ . .a .. u. a-.- -.x-.,

-. . . . . ~ . , - - . . - - . - . . . - - . . . . . . . . . ~ . .

I A

I SOUTH CAROLINA ELECTRIC AND GAS COMPANY VIRGIL C. SUMMER NUCLEAR STATION NUCLEAR OPERATIONS MCLEAR- ann nom.,!jan,y EMERGENCY PLAN PROCEDURE COPY No.. . . . . . . . g*

EPP-002 COMMUNICATION AND NOTIFICATION REVISION 6 APRIL 26, 1983 NON-SAFETY RELATED

( ,

\

Reviewed by:

& 5 KT OR[GINATOW s (of this. revision) / Date

{ .E $

DISCIFLINE slJPERVISOR / Date .

s Approved: +

~

_ PLANT M AfDIE.R . -

$k/b Date' 3 ,,'

N O.

MAY 2 51983

~s n ( Date Issued:

4

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e EPP-002 PAGE i REVISION 6 4/26/83 LIST OF EFFECTIVE PAGES PAGES -

REVISION i 6

-11 6

- - 111 6 1- 6 .

2 6

.- 3 6 4 6 5 6 ATTACHMENTS Attachment I, Pages 1 & 2 6

.s Attachment II, Pagee 1 & 2 6 (l'--'

\

Attachment IIIA 6 Attachment IIIB 6 Attachment IIIC 6

- Attachment IIID, Pages 1 & 2 6 Attachment IVA, Pages 1 -

4 6 i

Attachment IVB, Pages 1 - 3 - 6 Attachment V, Pages 1 - 3 6 Attachment VIA 6 l'

Attachment VIB 6 Attachment VIC ,

6

! Attachment VII, Pages 1 & 2 6 Attachment VIII, Pages 1 - 4 6 l

l

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~ EPP-002 PAGE 11 REVISION 6

'~h 4/26/83 TABLE OF CONTENTS 4

PAGE List Of Effective Pages i 1.0 PURPOSE' 1 2.0 . REFERENCES 1 DEFINITIONS 1

, 30 f

4.0 PREREQUISITES 2 5.0 PROCEDURE 2 5.1 Initial Notifications 2 5.2 Notifications for Change of Energency Classification 2 5.3 Off-site anergency Services- 4 5.4 Follow-up Notifications 4

( ) g 55 Vital Personnel Notification 5 ATTACHMENTS Attachnent I - Warming Message: Nuclear Facility to State / Local Government Part I Attachment IIA - Warning Message: Nuclear Facility to State / Local Government Part II Ittachment IIIA- Initial hotification-Unusual Event Attachment IIIB- Initial Notification'- Alert Attachment IIIC- Initial Notification-Site Energency Attachment IIID- Initial Notification-General Energency Attachnent IVA - NRC One-Hour Notification Attachment IVB - ANI Eight-Hour Notification 2

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EPP-002 PAGE 111 REVISION 6 4/26/83 TABLE OF CONTENTS (Continued)

'Attachnent V - Off-Site Emergency Services Attachment VIA - Follow-up Notifications - Alert Attachment VIB - Follow-up Notifications - Site Emergency Attachment VIC - Follow-up Notifications - General Bnergency Attachment VII - TSC/OSC Emergency Telephone List Attachment VIII- Off-Site Energency Telephone List 9

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EPP-002 REVISION 6 ys 4/26/83

)

1.0 PURPOSE

- 1.1 The purpose of this procedure is to delineate the specific notification requirenents for each class of emergency and to provide a method for affecting these notifications.

2.0 REFERENCES

2.1 " Virgil C. Summer Nuclear Station Radiological Energency Plan" 2.2 NUREG-0654, " Criteria for Preparation and Evaluation of Radiological Energency Response Plans and Preparedness in Support of Nuclear Power Plants" 2 3 ' EPP-001,. "Activiation and Lnplementation of the Energency Plan" t

2.4 Voluntary Assistance Agreement (by and among Electric i

Utilities involved in Nuclear Generation) - Article 9 -

Transportation of Nuclear Materials; and Emergency Resources Manual, "INP0" Institute of Nuclear Power Operations.

2.5 Policy Memorandun No. 25 Issuance, Control, and Usage of Radio Pagers.

3.0 DEFINITIONS-AND ABBREVIATIONS 31 Definitions 3.1.1 Initial Notification - The transfer of .infonnation to designated organization (s)/ person (s) following

, change of plant status fran normal operations directly into any of the four energency classifications or upon escalation to a higher emergency classification. This transfer of information is required to begin within fif teen minutes after declaration of the applicable energency classification.

PAGE 1 0F 5

- ^ ..

" M*99*- h -

- ** -- 89 WS *'

EPP-002 REVISION 6

,- 4/26/83

)

, EXCEPTION: (1) The NRC, Bethesda, Maryland office and the Site Resident Inspector are to be notified within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of declaration of the event in accordance with Attachment IIA. 2) The knerican Nuclear Insurers (ANI) is to be notified within eight (8) hours of declaration of an Alert, Site Energency, or General Energency in accordance with Attachment IIB.

3 1.2 Follow-up Notification - The transfer of information to designated organization (s)/ person (s) updating the intitial notification. This transfer of information is required at 15 minute intervals following completion of initial or previous follow-up notifications.

l EXCEPTIONS: Pc11owing initial notification of the NRC,.an open communication line will be established and maintained to provide continuous updating to the NRC. Follow-up notifications are not. required for the Unusual Event classification.

32 Abbreviations

(. 3 2.1 TSC - Technical Support Center g 3.2.2 OSC - Operations support Center 3 2.3 EOF - Energency Operations Facility 3.2.4 ED - Energency Director 3.2.5 IED-Interim Emergency Director l 3 2.6 E.O.C-Energency Operations Center l 4.0 PREREQUISITES and' CONDITIONS 4.1 Unusual or abnonnal plant or site conditions exist which necessitate implementation of the Emergency Plan and the applicable Energency Classification has been declared.

5.0 PROCEDURE 5.1 Initial Notifications l

PAGE 2 0F 5 G

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EPP-002 l REVISION 6 i s. 4/26/83 I

5.1.1 Upon declaration of the appropriate energency ,

classification, the ED/IED will direct the canmunicator to haplement the appropriate notifications.

I NOTE: Refer to EPP-016 Attachnent II for l personnel, by title, who should be the j designated communicator.

5 1.2 The ED/IED will assure that the required information is available to effect prompt notification.

i 5.1.3 The camnunicator will, upon direction from the

,q ED/IED, implement the initial notifications. The t

infonnation in Attachment I is to be given to the I personnel / agencies as listed in Attachments III A, ,

III B, III C, or III D depending upon the

! classification of energency.

NOTE: Attachnents III, IV and V list alternates for various personnel. These notifications attempts are to be made in nunerical

' eequence as indicated and will be considered 8

complete upon successful notification of one

~~

of the listed.

5.2 Notifications for Change in Energency Classification .

NOTE: If classification change is made in the middle of a notifications sequence the cammunicator will

tenninate that notification sequence, and initiate the new notification for current status.

i 5.2.1 Upon escalation to a higher energency classification, the communicator will, upon direction fro , the ED; implement notifications per'

, the section of Attachment III which corresponds to

' the higher energency classification, and

-Attachments IVA and IVB.

5.2.2 When the unergency classification is downgraded, the communicator will, upon direction f rom the ED, bnplenent notifications per the section of Attachment VI which corresponds to the classification which.is being changed.

PAGE 3 OF 5

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f ,

' - EPP-002

, REVISION 6 g f3 4/26/83

.s 53 Off-site anergency Services 8

5.'3.1 Upon direction from the ED/IED, the cammunicator will Unplement the requested notification (s) per

! Attachment V.

.! 532 Upon direction from the ED/IED, the camnunicator j will contact other utilities for assistance using j the "INP0" Resource Guide, Reference 2.4.

NOTE: The Resource Guide is available in the i TSC and EOF.

i 1 5.4 Follow-up Notifications

! 5.4.1 Follow-up notifications are required for all energency classifications except Unusual Event.

. 5.4.2 The communicator will implement follow-up

! notifications. (The information in Attachnent I

and II is to be given to the personnel / agencies as

-listed in Attachments _VI A, VI B, or VI C depending

upon the energency classification.)

! 5.4.3. Follow-up notifications will be made by sthe site cannunicator(s) until the EOF is activated and assumes all off-site notification responsibilities.

Thereaf ter, the site camnunicator will transmit

a. applicable updated infonnation to the EOF as it j becomes available.

t l 5.4.4 Follow-up notifications to the Energency

, Preparedness Division and the counties shall be made by the TSC or EOF Communicator until such time l'j that the S.C. State. Forward EOC is -staffed and communications are established. When the S.C.

i , Forward E.O.C. is activiated, all camsunications, between the plant and state and county agencies i will go to the S.C._ Forward E.O.C. via the

'~

L dedicated phone line or established land line.

j NOTE: All transfers of notification responsibilities shall be documented.

i l'

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_PAGE 4 OF 5 L

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EPP-002

. REVISION: 6 4/26/83 i a

, 55 Vital Personnel Notification 5 5.1 The communicator will notify vital personnel as directed by the ED/IED per the Vital. Personnel Telephone Listing available in the Control Room and the TSC or by radio pager as per Policy Memorandum l No. 25

, 5.6 TSC/OSC/ EOF Communications 5.6.1 TSC-OSC - telephone list are provided in Attachment VII.

5.6.2 EOF - telephone list are provided in Attachment VIII.

i \

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EPP-002 ATTACHMENT I PAGE 1 0F 2

-, REVISION 6 WARNING ~ MESSAGE: NUCLEAR' FACILITY TO STATE / LOCAL GOVERNMENT Part I This is the Sumner Nuclear Station.

~

1.

2. My name is' This message (nunber ): Initial (a) Reports a real emergency. Follow-up (b) Is an exercise message. Time message given

4. My telechone number / extension is: ,

or 5 You may call back at the end of the message for verification.

6. The class of the emergency is: '(a) Notification of Unusual Event (b) Alert (c) Site Emergency (d) General anergency

7. This classification of emergency was declared at:

(a .m ./p .m . ) on (date).

8. The'intiating event causing the energency classification is: -

9 The energency condition: (a) Does not involve the release of radioactive materials fro the plant.

(b) Involves the potential for a release, but no release is occurring.

(c) Involves a release of radioactive material.

10. We recommend the following protective action:

(a) No protective action is recommended at this tbne.

(b) People living in zones remain indoors with the doors and windows closed.

EPP-002 ATTACHMENT I PAGE 2 0F 2

' /, _ , ' . REVISION 6 (c) People living in zones evacuate their homes and businesses.

(d) Pregnant women and children in zones remain indoors with the doors and windows closed.

(e) Pregnant women and children in zones 2

evacuate to the nearest reception center.

i (f) Other recommendations:

11. There will be:

, (a) A followup message j (b) No further communications

?

12. I repeat, this message:

i (a) Reports an actual emergency l (b) Is an exercise message

'13. Are there any questions?

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EPP-002 !

ATTACEMENT II PAGE 1 0F 2 REVISION 6 NARNING MESSAGE: NUCLEAR' FACILITY TO STATE / LOCAL GOVERNMENT Part II

1. The type of actual or projected release is:

(a) Airborne.

(b) Waterborne (c) Surface spill (d) Other

2. The source and description of the release is:

3 '(a) Release began /will begin at a .m . /p .m . ;

ttne since reactor trip is hours.

'(b) The estimated duration of tn'Te' lease is hours.

4. Dose projection base data:

Radiological release: curies, or curies /sec.

Windspeed: ' mph Wind direction: From Stability class: (A,B,C,D,E,F,ohG)

Release height: 'Ft.

Dose conversion factor: R/hr/01/m3 (whole body) )

s R/hr/C1/m3 (child thyroid Precipitation:

i l Temperature at the site: *F f

L 5 Dose projections:

' Dos e' C ommi tment

o .

Whole Body Child Thyroid

! Distance Rem / hour Ren/ hour of inhalation l Site boundary l

2 miles L 5 miles l 10 miles 1 1 l

l r 1 I

. . .- : :a.. -

_. - . :... . _. --..=...

EPP-002 ATTACHMENT II PAGE 2 0F 2 REVISION 6

..__._:______ WARNING' MESSAGE: NUCLEAR PACILITY'TO STATE / LOCAL GOVERNMENT Part II (cont.)

Projected Integrated Dose in Rem per Unit Time

l Distance' ' Whole Body' Child' Thyroid Si.te Boundary 2 miles 5 miles 10 miles

6. Field measurement of dose rate or contamination (if

. . available):'

7 Energency actions underway at the facility include:

-8. Onsite support needed from offsite organizations:

9 Plant Status:

(a) Reactor is: not tripped / tripped (b) Plant is at ~% power / hot shutdown / cold shutdown / '

.- cooling down (c) Prognosis is: stable / improving / degrading / unknown.

10. I repeat, this message:

8 (a) Reports an actual emergency.

, (b) Is an exercise message.

11. Do you have any questions?

i m

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EPP-002 ATIACHMENP IIIA PAGE 1 GP.1

'~' REVISION 6 g

UNUSUAL EVENP PAGER EASY PERSON AGENCY / PERSONNEL NUMBER NORMAL ACCESS SITE Nunnta TIME

1. Management Duty Supervisors (per Duty Roster)

1) Ollie Bradham

2) John Connelly -

3) Ken Woodward

4) Bruce W1111a=

5) Mel Browne

6) Mike Quinten !

\-

7) Vince Albert ,

2. 'S.C. Dept. cf Health & .

Environmental Control,. Bureau of Radiological Health 3.' 'NRC See Attachment IVA of EPP402 for NRC Initial Notification

4. Media ,Coord. (Mgr., Nuclear Info.)

Home Office

1) Becky McSwain

2) 1st Alt. - W. M. Lide, Jr.

5. Site Services Manager-Bob Stough I

6. Institute of Nuclear Power Operations (INFO)

7. American Nuclear Insurers (ANI) See Attachment IVB of EPP-002 for ANI Notification NCTfIFICATIONS COMPLEIE:

CALLER'S SIGNATJRE DNIE

Dedicated Line Also Exists.

_.,... . : ~_ . _ -.- -.- ;

--~'

E . 1 EPP-002 ATTACiMENT IIIB I PAGE 1 0F 1-REVISION 6

~'h INITIAL NOTIFICATION PAGER EASY P8 SON AGENCY /PESONNEL NUMBER NORMAL ACCESS SITE NOrmm TIME

1. Mana6ement Duty Supervisors (per D2ty Roster)

1) Ollie Bradham __

2) John Connelly

, 3) Ken Woodward ,

4) Bruce Wil11a=

5) Mel Browne

6) Mike Quinton - --

\

7) Vince Albert-NOIE: To contact additional Emrgency Response Personrel refer to Policy Memorandum No. 25 >

2. 'S.C. Dept. of Health &

Ehviremental Control, Bureau of Radiological Health s _

N/A

3. 'NRC See Attachnent IVA of EPP-002 for NRC

- Initial Notification i

4. Media Coord. (Mgr., Nuclear Info.)

Home Office

/

1) Becky McSwain

2) 1st Alt. - W. M. Lide, Jr. _

5. Site Services Manager-Bob Stough

6. ~ Institute of N2 clear Power Operations (INPO) k

7. Fairfield Pumped Storage Pacility'\

~ *8. American Nuclear Insurers (ANI) See ti:acfAeniIVB of EPP-002 for ANI Notification NOTIFICATIONS (DMPLEIE: _ _ , , , , , , m-

_ . . . _, .a vam .m -n-

Dedicated Lira Also Exists.

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EPP-002~

ATTACHMENT IIIC PAGE 1 0F 1

] INITIAL NOTIFICATION

" SITE EMERGENCY" NAME OF PAGER EASY PERSON AGENCY / PERSONNEL ' NUMBER ' NORMAL ACCESS SITE NOTIFIED TIME

'l. Management Duty Supervisors

. (per Duty Roster) .

t~

1) 'Ollie Bradham

2) John Connelly

3) Ken Woodward .

~4) Bruce Will11ams

5) Mel Browne

6) Mike Quinton. _ . _ _

7) Vince Albert

. NOTE:. To contact additional Emergency Response Personnel, refer to Policy Memorandum No. 25.

~ ~ ~

2. 'S.C. Dept.-of Health &

Environmental Control,

-Bureau of Radiological Health .

. 3. *NRC See Attachment IVA of EPP-002 for NRC <

Initial Notification Requirements

4. Media-Coord. (Mgr.,

Nuclear Info. ) Home Office

1) Becky McSwain 703

[

2) 'Ist Alt.~- W.M. Lide, Jr./

5. Site Services Manager -

-Bob Stough

6. Institute of Nuclear Power,-

LOperations (INPO)

7. .Fairfield Pumped Storage

'..- Facility ~

See Attachment IVB of EPP-002 for ANI American Nuclear Insurers Notification.

NOTIFICATIONS' COMPLETE:

4 cDedicated Line Also Exists.

^~ ~ :~& : :. , . . .- - :- : - .

EPP-002 ATTACHMENT IIID PAGE 1 0F 2 O REVISION 6 INITIAL NOTIFICATION

" GENERAL EMERGENCY" NAME OF PAGER EASY PERSON AGENCY / PERSONNEL NUMBER NORMAL ACCESS SITE NOTIFIED' TIME

-1. Management' Duty Supervisors '

(per Duty Roster) c

1) Ollie Bradham

2) John Connelly

. 3) Ken Woodward t

4) Bruce Williams

5) .Mel Browne

6) Mike Quinton

7) Vince Albert ,

NOTE: To. contact additional Emergency Response Personnel, refer to Policy Memorandum No. 25

2. 'S.C. Dept. of Health & .

Environmental Control, Bureau of Radiological i Health . .

3 -*NRC See Attachment IVA of EPP-002 for NRC Initial Notification Requirements

4. Media Coord. (Mgr. , Nuclear Info.) Home Office

1) Becky McSwain 703

2) ist Alt. -W.M.Lide,Jr{

-5 Site Services Manager -

Bob Stough

6. Fairfield Pumped Storage Facility

..

Emergency Preparedness

-- ' Division-

"i *

%t"nMfC*/'er* - .

Dedicated Line Also Exists.

~.~~^+~

^

^^

-- - - - - :. . . . . ..=.:.-.- . - - - - - - - .

EPP-002 ATTACHMENT IIID-PAGE 2-OF 2

N REVISION 6 INITIAL NOTIFICATION

" GENERAL EMERGENCY" NAME OF EASY PERSON AGENCY / PERSONNEL ~ NORMAL ACCESS SITE NOTIFIED TIME

'8.-#Fairfield County .

)[

9..'Newberry County 10..#Richland County

11. #Lexington County. .

12. Institute of Nuclear

- Power Operations (INPO) 13 American Nuclear Insurers See Attachment IVB of EPP-002 for ANI Notification.

\

NOTIFICATIONS COMPLETE:

Caller's Signature Date

Dedicated Line Also Exists.

v e

_ . , . . . . 2 .. ... _ =- - -. . - - -

' ' ~

. 5

1 EPP-002 ATTACHMENT IVA PAGE 1 0F 4

'~' REVISION'6 NRC ONE' HOUR NOTIFICATION The'NRC shall be notified within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of Declaration of an Faergency in accordance with Pages 2 through 4 of this attachment.

EASY PERSON NORMAL ACCESS CONTACTED

~ 1.- NRC - Bethesda, Md..

Dedicated Phone N/A a) Commercial telephone system to.NRC Operati'ons Center (Via Bethesda. Central Office). (202) 951-0550 b)-NRC-Atlanta, Ga. (404)'221-4503 018

-.-- 2. NRC - Resident _Inspec. tor _ _ . . . _ __ _ Yes No .

~

Jack Skolds 402T (N'.0. Ext)

Rome Phone NO.

-or 345-5683 748-5406

_- Beeper No.

CALLERS SIGNATURE DATE TIME t

~_ '

EPF-002 ATTACHMENT IVA PAGE 2 0F 14

REVISION 6 NRC ONE HOUR NOTIFICATION A. Identification: '

This is the Summec Nuclear Plant.

.My name is . . _ _ . _.

Our phone nunber is -

B. Event Classification:

We are now in a(n)

EVENT CLASSIFICATION

- which was declared at .

TIME C. DESCRIPTION:

What Happened:

f

, cause:

Consequences:

(

Actions:

Current Status:

D. . LICENSEE NOTIFICATIONS: (What notifications have been made. )

STATE (S)

LICENSEE MANAGEMENT' LOCAL OTHER NRC RESIDENT OTHER' E. . PRESS RELEASE: Has a press release been made or planned? Yes_ No_

9 U. , '

C

"

p7 _ h

. ~. - - - . . . . . - . . . - - - . _

.. .2.

EPP-002

, ATTACHMENT IVA PAGE 3 0F 4 f'T REVISION 6-4 NRC ONE HOUR NOTIFICATION Part II-Complete for all ALERT, SITE AREA, and GENERAL emergencies Licensee Actions:

Taken Planned Property Danage Radioactivity Released (or Increased' Release):

~ Liquid / Gas? Location / Source of Release Elevation Release Rate Duration. Stopped?

Release Monitored?- Amount of Release

% Tech. Specs.

Increased Radiation Levels ~in a~ Plant: Location (s)

Radiation level (s) Areas Evacuated Maximum site boundary dose rates = Location Integrated dose, Location Meteorology:

Wind Direction from Wind' Speed (Meter /sec or miles /hr)

T ( C or*F) Temperature (*C or *F)

Stability Class A B C D E F G \

Raining (Yes/No)

Projected Peak: Dose Rates Integrated Dose

, 2 mi (WB/I) (WB/I) 5 mi (WB/I) (WB/I) 10 mi (WB/I) (WB/I)

Sectors (WB/I) (WB/I)

Contanination (Surface): inplant' onsite offsite l

Reactor Operations:

Reactor System Status Power Level

', Pressure Temp Flow (pumps on) l Cooling Mode ECCS Operating / Operable i

L Containment Status Containment Isolated? 'Containnent Temp Containment Press Containment Radiation R/hr.-

Leak Rate R/hr.

Reactivity Control Control Rods Inserted ~ Status of Emer. Boration System u

5.

U -

_ . . _ _ . , . . _ _ _ _ _ . . . . .. .~ . . _

._ _.___ ~ _ _ _ _ _ , . _ . . _ . _ . . . _ . . . . . . _ _ _ _ _ . . _ _ _ _ . - _ . - - .._. .-

. 2 .;__. .._.;.... .2..m~... ; . _ _ _ . . . . _ _ _ .

1 EPP-002 ATTACHMENT IVA PAGE 4 0F 4

/] REVISION 6 INCIDENT NOTIFICATION INFORMATION ~

Part II f

Steam Plant Status: .

S/G Levels Equip. Failures Feedwater Source / Plow S/G Isolated?

1 Electrical'Dist. Status':

Normal Offsite Power Available?

Major Busses / Loads Lost D/G Running? '

Loaded?

Security / Safeguards:

Bomb Threat: Search Conducted?

Search Results Site Evacuated?

Extortion: Source (Phone, letter, etc.)?

Location of Letter Intrusion: Insider?' Outsider?'

Furthest Point of intrusion i , Fire arms related? Stolen / Missing Material?

2 Demonstration: -Size of Group Demands Violenca? Fire arms related?

Sabotage / Vandalism: Radiological? Arson Involved?

Stolen / Missing Material?'

)

l r

i

+

t

.~ . . , . _ . a .. _ . _ . _ _ _ _ _ . _, _ . _ . - _ _ _ _ _ . ,

7 EPP-002 ATTACHMENT IVB

'PAGE 1 0F 3 REVISION 6 ANI EIGHT HOUR NOTIFICATION ANI is to be~ notified'within eight (8) hours of the declaration of an Alert, Site Energency, or General Bngergency.in accordance with pages 2 and 3 of this attachment.

American Nuclear Insurers ( ANI) Phone No. (203)-677-7305 Eacy Access 019

,' Person Contacted Tim e _ _ Date Callers Signature

\

S

' .eem s -o+em -

e . . . - , , , ,. ,, ,._ _

EPP-002 ATTACHMENT IVB

' PAGE 2 0F 3

' 5, REVISION 6 ANI NOTIFICATION (1)

This is

.(Name) (Title)

(2a)- This is a drill (2b) This is NOT a drill (3) I am notifying you of an accident at the V. C. Sumner Nuclear

, Station which occurred at:

(Date) (Tima)

(4) This energency is classified as a .

, (5) Description of event:^

(6) Radiation Release Yes No.

(If yes, complete 6a through 6j)

(6a) Type of Actual Release or Type of Projected Release:

(6b) Esttnation of Duration of Public Inpact:

\

(6c) Release Rate: (6a) Noble Gas (6b)'

(6c) Release Height (6d) Meteorological Conditions: (6a) Wind Speed (mph)

(6b) Wind Direction (blowing to)

(6c) Stability Class j

(6d) Precipitation l (6e) Projected Dose At: Site Boundary 2 Miles 5 Miles 10 Miles (6f) Dose Rate--Whole Body (10A)* (10B) (100) (10D)

(6g) Integrate Whole Body Dose

( hour projection) (11A) (11B) (110)~ (llD)

(6h) Dose Rate--Thyroid (12A) (12B)' (120) (12D)

(61) Integrated Infant Thyroid i ( hour projection) (13A)~ (13B) (130) (13D)

(6j) Sectors Affected (14A)' (14B)~ (3 40)' (14D) l l

I

, , ,,, , - . , . , _ . . ,,,y. -. , , . , - , . _ p , - - - - - - .y. r.,--g_4,-..- r

EPP-002 ATTACHMENT IVB PAGE 3 0F 3 O REVISION 6 ANI NOTIFICATION

~ ' ' ' ~

(7) Injured Personnel Yes No.

(if yes, complete 7a through 7d)

(7a) Ntznber of injured personnel (7b) Is Is Not Radioactively Contaminated (7c) Injury

Description:

(7d) Requires Transportation to off-site Medical Facility Yes

No.

(8) Off-Site Energency Assistance / Actions Requested Yes No.

(If yes, complete 8a through Sc)

Yes/No Reason (8a) Law Enforcement i

I (8b) Fire Departments (8c) Hospital Facilities r (9) Public evacuation required Yes No Not at this time (9a) If "Yes" or "Not at this tizae", affected sectors 1

4e-- 4=m * * * = ,,

-D= aWNW -

4,, m e .w a% e h, a

EPP-002 ATfACHMEtif V PAGE 1 0F 3

.S - REVISION 6 OFF-6ITS DERGENCY SERVICES NAME OF PERSON AGENCY / PERSONNEL PHONE ? m m t.v TDE A. Canpany Physicians (Finner Clinic) ,

1) Carrol A. Pinner III M.D. - Pctnary 24 hrs.)

2) Harriet E. Pinner, M.D. - 2nd Alternate l B. Hospital Facilities .

1) Richland Menorial Hospital Give the following infonnation:

'Ihis is the Virgil C. Su::mer Nuclear Station.

'Ihis is a Drill 'Ihis is not a Drill We have contaninated/non-contaninated injured person being transported to your ,

facility.

2) Radiation Energency Assistance Center Training Site (Reacts) 24 houN l C. Ambulance Service la) Energency & dical Services - - - -

of Pairfield County f r

i lb) Alert MAST for standby f ir transportation. l

2) U.S. Amy MASP Operations or

!UIE: Alert Security of Energency Vehicle arrival as soon as request (s) for Off-Site Energency Services are canpleted.

\'

Ext; or\

\.

-;__ .J :n-

~

t. .

EPP-002 ATIACR4Dff V PAGE 2 0F 3 REVISION 6

)

- OFF-GIIE EMERGalCY SERVICES NAME OF

~

PERSON AGDICY/ PERSONNEL PHONE Nulmtu TD4E Give the following information for itens la and 2 above.

21s is a Drill his is not a Drill We have conta inated/non-contaninated injured person (s) requiring transportation to Richland Manorial Hospital. .(B e anbulance must enter the site via the main gate, using (denote route to be taken) or the helicopter should land at the primary landing pad (denote route to be taken)

D. NSSS Supplier /A.E.

Title Nane Office Hone HHL

1. Site Service Manager Bob Stough Notes: (1) 2e area code of the above phone rambers is (2) 'Ihe phone beeper nunber is '

2. _ Operating Plant Service John Miller Manager 1st Alternate 'Etm Sullivan 2nd Alternate Rich Paix 3 Service Response 'lbn Milto Manaser .

1st Alternate Bob Stokes 2nd Alternate John Miller

4. Ener5ency Response ha Anderson Director ,

5 Energency Response Ron Lehr Deputy Director

6. Bnergency News Mike Mangan'

< Comunications Note: Unless ind' rated otherwise, all phone nunbers are area code 412. Where an area code other than 412 is shown3 it applies to the office, hone, and HHL nunbers

2) GAI (Nonnal Working Ecurs)

/

[

EPP-002 ATTACE4ENT V PAGE 3 OF 3

' REVISION 6 OFF-SITE DIERGENCY SERVICES NAME OF PERSON PHONE Nurmer TIME AGENCY / PERSONNEL .- _

E. Fire Services

1) Fairfield Ccunty Fire Services Give the following information:

This is the Virgil C. Sutuner Nuclear -

Station.

ihis is a Drill 1his is not a Drill We request fire f15hting assistance at the Sunmer Nuclear Station. 'Ihe fire truck must enter via the main gate, using (denote route to be taken) .

Iocal Law Fnforcanent r' or F.

(off--normal hours) ,

G. National Wather Ser" rice (Backup to Load Dispatcher for weather infonnation).

I

1) Colunbial -

2) Greer -

CALLER'S SIGNATURE DATE d

g - ' T ;

m.:vb7s , N ~ . .

. -]

9/

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, f ( J- 0.- .s 4 4..4 arm, + L j ,q*t;,,& g4 d.3 r-s; ;- 4; f, EPP-002 2

' - '> 1 ATTACHMENT VIA

--d -

.f>- 33:p4,'1: ( d$ .'ij si/ ^ :3 ) ,

PAGE 1.0F 1 3 i

? . J' REVISION 6-Q,3-- '.

i _

w s, 3 .,.

1 1o# AT a, FOLLdWUP NOTIFICATION -

1 c! tt ,

A<

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1 ( I . ,r - .O 4<

ALERT

o. , : s.

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NAME OF

.i ~ O. . j' z y, PERSON 7qw J + ~ .

g , .

EASY TIME

-U

-ACCESS NOTIFIED Nyp N 4 GEN'CY/PEfiSOYNEff v . ,, g , w, ,n; NORMAL ^

h 1.3/S.C,k Dep'; of Eealthi k,", M. -

'4 '

X]V., \Bu/ eau c!." Radi61dgical.) h-Envirornental Control,', '

s

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+ Caller's Signature Date

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EPP-002 ATTACHMENT VIB '

PAGE 1 0F 1 *

"'- REVISION.6 FOLLOWUP NOTIFICATION SITE EMERGENCY NAME OF EASY CALLERS PERSON AGENCY / PERSONNEL NORMAL ACCESS SITE SIGNATURE NOTIFIED TIME 1.* S.C. Dept of Health'& N/A Environmental Control, Bureau of Radiological Health Notifications complete:

Caller's Signature Date NOTE: When the State Forward EOC is established the State BRH will move.

their operation to the State Forward EOC and communication will be via the State Forward E.O.C. Dedicated Phone Line.

Dedicated Line Also Exists.

~

\

f 5

q

7-EPP-002: j ATTACHMENT'VIC :

PAGE 1 0F 1 :

REVISION 6-O ,.

, a FOLLOWUP NOTIFICATION

' GENERAL EMERGENCY NAME OF EASY PERSON AGENCY / PERSONNEL NORMAL- ACCESS NOTIFIED TIME 1.S.C.LDept of Health & /.

Environmental-Control,

-Bureau of Radiological Health .2 _

The following notifications shall be.made by the TSC' or. EOF '

'Canmunicator until such tLne. that the S.C. State. forward EOC is ,

staffed. . . - .

j 2.5 Emergency' Preparedness. ,/

DivisionAdjutantGeneral'{.

Office ,

- 3.* Fa'irfield County 4.* Newberry County

. \

,.* Richland County 6.'* Lexington County.

Natifications canplete:

Caller's Signature Date NOTE: When the State Forward EOC is established the State BRH will move their: operation to the State. Forward EOC and communication will be~

via the State Forward E.O.C. Dedicated Phone Line.

Dedicated Line Also Exists. -

e 6_ .+ _- - , .--.---.4-,--...w. .. . _ .

^

EPP-002 ATTACHMENT VII PAGE 1 0F 2 REVISION 6 .

_s TSC/OSC' EMERGENCY ~ TELEPHONE' LIST l

I

{ Nuclear Regulatory Commission (NRC Area and E'.O. A)

Nuclear. Regulatory Commission-I j Nuclear Regulatory Commission TSC Display Room TSC Display Room I

f Dose Assessment Area ,

I i Technical-Support Engineers i

Technical Support Center Communicators Technical Support Engineers l _

i

' . Assistant Manager, Support Services-Vince_ Albert Security Supervisor-John Sefick Telecopier Phone to EOF

\

Radiation Monitoring Teams Data Logger Radiological Assessnent Supervisor-L. A. Blue Assistant Manager, Technical Support-M. Browne Emergency Director (

Energency Operations Area- General Use Westinghouse (NSSS)

GAI'(A/E) i OSC

\

OSC O

6 ne m ed pw *-' 6%

,,e,, , ,eg e p- e

EPP-002 TECHNICAL SUPPORT CENTER f REVISION 6 f f2

.R '

l nne .

. PIANT STATUS DISPLAY AREA .

~

. DOSE ASSESSMENT AREA.

"1 .

n

( j I EMERGENCY ATIONS

~ SHUT D-1 TECHNICAL SUPERVISOR

. SUPPORT AREA OFFICE iREi D-4 COMMUNICATIONS l #

AREA i- .

(Telecopier)

. 1 MONITORING NSSS A/E TEAMS 3 pag.g gggi AREA n-6

<. D-5 ,

= ' .

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-44 6 * *% e6aNai N*-MO O'O*T

,n ,w - - , w w -p --m-. - e -----g----< 4 .- ,,,-om-,om-, ---e4 -e,-- -g-- - p- - 4

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. EPP-002 ATTACHMENT VIII PAGE 1 0F 4 REVISION 6

!3 '

. Emergency Operations Facility Layout X

. m+ _

< ein- :, .:

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1 - COMMAND CENTER (Room 144) 9 - NRC AREA (Room 122)

. 2 - TECHNICAL SUPPORT AREA (Room 145) 10 - CONFERENCE ROOM (Room 3 - 0FFSITE RADIOLOGICAL MONITORING ARJA 143 (Room 145) 11 - COMMUNICATIONS AREA 4 - GENERAL SERVICES AREA (Room 138) (Room 140) 5 - CONSTRUCTION / REPAIR AREA (Room 138) 12 - REPRODUCTION AND 6 - MEDIA AREA (Room 141) RECORDS STORAGE AREA

~

7 - LOCAL GOVERNMENT AREA 13 - STROAGE AREA (Room 142) 8 - STATE GOVERNMENT AREA (Room 124)

s.

,, , ,,,, , y me N-d.bMa*'eG "*WN - '

, g. .- ,

-EPP-002 ATTACHMENT VIII; PAGE 2.0F 4

,n' ~ REVISION 6 a

0FF-SITE EMERGENCY TELEPHONE' LIST

' ' ~~ '

Emergency. Operations Facility

1. COMMAND CENTER

~

-EOF-Media Coordinator (R. McSwain)

EOF-Energency' Control Officer (0.W. Dixon)

EOF-Offsite Radiological Monitoring

.f Coordinator (B. Baehr)

EOF-Security Coordinator--(J. Harrison) 1

' ' EOF-General Services Coordinator .(J. Bailey)

EOF-Cons truction/ Repair . Coordinator - (J. Woods) d EOF-Technical Support Coordinator i

l' (M. Whitaker) 1 EOF-TSC/ EOF Dedicated Phone

2. TECHNICAL ~ SUPPORT' AREA

- EOF-Technical moport Engineers t

\ EOF-Technical'Suppore Engineers /Telecopier

3. OFFSITE RADIOLOGICAL MONITORING? AREA O EOF-Offsite Rad. Monitoring EOF-Offsite Rad. Monitoring

- EOF-Offiste Rad. Monitoring

(.

v

4. GENERAL' SERVICES' AREA T

EOF-General Services Personnel -

EOF-General Services Personnel EOF-General Services Telecopier 4, ,

=

d

-- . . . ~ .i . , _.- -.

, _ - ._. .- ,.,_.,- . _ . . . . . _ - . , , , . . . , . . _ .- , . . . . , , . . . . . , . . . , _ . . ~ . . . , . - , , . , _ - , , _ . .

. . , ..~. -- . . .

EPP-002.

ATTACHMENT VIII PAGE 3 0F 4 REVISION 6

. R

- OFF-SITE EMERGENCY TELEPHONE LIST Snergency Operations-Facility

5. CONSTRUCTION / REPAIR ~ AREA

^

i EOF-Construction Personnel

-] '

t EOF-Construction Personnel i

6. MEDIA AREA

/

EOF-Company Media Personnel EOS-Company Media Personnel EOF-Company Media Personnel

+

7. LOCAL GOVERNMENT AREA I EOF-Local Goveranent Officials EOF-Local Government Officials EOF-Local Government Officials t .

8. STATE GOVERNMENT' AREA EOF-State Government Offici'als EOF-State Governnent Officials

9. NRC AREA EOF-NRC Officials l

EOF-NRC Officials EOF-NRC Officials

. EOF-NRC Officials t.

1 l

.-q

a EPP-002

'~

ATTACHMENT VIII

. PAGE 4 0F 4 l

REVISION 6

- 0FF-SITE' EMERGENCY TELEPHONE LIST Emergency Operations Facility e

10. COMMUNICATIONS AREA I' _ EOF-Emergency Communicator 11., SECURITY ~ CONTROL POINTS EOF-Hallway Area i

! EOF-North Entrance I

t 0

e e

ee<e ..m on e e w- .ee e e se e4 O *"* M M * * **r 4 e.. . y e w s , e m.e,,.,g .-.. as -me*=4

. = = = * * * - * * * ** * * * * * * * -"**""# '

, - ___y____._

1 s

. . l

~ \

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^

1 l

N SOUTH CAROLINA ELECTRIC AND GAS COMPANY I

( )

VIRGIL C. SUMMER NUCLEAR STATION l NUCLEAR OPERATIONS l

EMERGENCY PLAN PROCEDURE ,

e i

EPP-002 COMMUNICATION AND NOTIFICATION -

REVISION 7 JUNE 1, 1983 NON-SAFETY RELATED

~

, NJC_MR 01 ERAT ONS COPY No. . . . . ./. 5.2. . . . . . . . . . . . . . .

Reviewed by:

'. /1 13

'OR3GINATOR W f this revision) / Dhte h 0 DISCIPLINE SUPERVISOR / Date

(_ Approved:

PLANU MANAGER

$/Wh Date -

Date Issued:

P e

-e s ea- - ee.e e e wp.,e% . g a g a w- m e- -ament wen = -

Mh +-e _mg,e t -.- r ---

,e-.-9 --.mm--p,. - - - - - - ---ew- - - - ,- , .>=.--.c--, ,. e- --.,we i- - ' .>?-e sw4m ,w+w +p= r, _m_ _.__ _

. - - ~

^

'EPP-002

- PAGE 1 REVISION 7

6/1/83 i

'A LIST OF EPPECTIVE PAGES PAGES REVISION s 1 7 11 ,

7 111 7 1 7 2- 7 3

3 7 4 7 5 7 ATTACHMENTS Attachment I, Pages 1 & 2 7 f~ Attachment II, Pages 1 & 2 ._ 7 Attachment IIIA 7

. Attachment IIIB 7 Attachment IIIC 7 Attachment IIID, Pages 1 & 2 7

' Attachment IVA , Pages 1 - 4 7

Attachment IVB, Pages 1 - 3 7 l -Attacherev V, Pages 1 - 3 7 N

Attachment VIA 7 l

Attachment VIB 7 Attachment VIC 7 Attachment VII, Pages 1 & 2 7 Attachment VIII, Pages i - 4 7 j

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EPP-002 PAGE 11 REVISION 7 7 6/1/83

._ TABLE 0F CONTENTS ',

PAGE List Of Effective Pages i 1.0 PURPOSE 1

~

2.0 REFERENCES

, 1 30 DEFINITIONS 1 4.0 PREREQUISITES 2 -

50 PROCEDURE 2 51 Initial Notifications 2 52 Notifications for Change.of Emergency Classification- 2 53 off-site Emergency Services 4

( '

\, a 5.4 Follow-up Notifications -

\ 4 55 Vital Personnel Notification ' 5 ATTACHMENTS Attachment I - Warming Message: Nuclear Facility to State / Local Government Part I

-Attachment IIA - Warning Message: Nuclear Facility to State / Local Government Part II Attachment IIIA- Initial Notification-Unusual Event

j. Attachment IIIB- Initial Notification - Alert Attachment IIIC- Initial Notification-Site Emergency i Attachment IIID- Initial Notification-General Emergency l

i Attachment IVA - NRC One-Hour Notification Attachment IVB - ANI Eight-Hour Notification i

i I

i i

l EPP-002 PAGE 111-REVISION 7 6/1/83 TABLE OF CONTENTS (Continued) t Attachment V - Off-Site Emergency Services ,

l Attachment VIA - Follow-up Notifications - Alert 1 Attachment VIB - Follow-up Notifications - Site Emergency Attachment VIC - Follow-up Notifications - General Emergency Attachment VII - TSC/OSO Emergency Telephone. List .

Attachment VIII- Off-Site Emergency Telephone List

\

4 l

l l

l -- . .. . . , . _ _ . . . . _ . -- --. . - -

l - - - - _ -_ _ - _ - - __

- EPP-002 REVISION 7 6/1/83 1.0 PURPOSE 1.1 The purpose of this procedure is to delineate the specific' notification requirements for each class of emergency and to provide a method for affecting these notifications.

2.0 REFERENCES

2.1 " Virgil C. Summer Nuclear Station Radiological Energency Plan" 2.2 NUREG-0654, " Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants" ,

23 EPP-001, "Activiation and Implementation of the Energency Plan" 2.4 Voluntary Assistance Agreement (by and among Electric Utilities involved in Nuclear Generation) - Article 9 -

Transportation of Nuclear Materials; and Emergency Resources Manual, "INPO" Institute of Nuclear Power

,- Operations. g 25 Policy Memorandum No. 25 Issuance, Control, and Usage of Radio Pagers.

, 30 DEFINITIONS AND ABBREVIATIONS

\

l 31 Definitions i

3 1.1 Initial Notification - The transfer of information to designated organization (s)/ person (s) following change of plant status from normal operations directly into any of the four emergency classifications or upon escalation to a higher emergency classification. This transfer of information is required to begin within fif teen minutes after declaration of the applicable emergency classifi. cation.

l l

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EPP-002 REVISION 7 6/1/83

(~x t

~

EXCEPTION: (1) The NRC, Bethesda, Maryland office i i and the Site Resident Inspector are to be notified within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of declaration of the event D1 accordance with Attachment IIA. 2) The American Nuclear Insurers -(ANI) is to be notified within eight (8) hours of declaration of an Alert, Site j Emergency, or General Emergency-in- accordance with Attachment IIB.

3 1.2 Follow-up Notification - The' transfer of information Jo designated organization (s)/ person (s) updating the intitial notification. This transfer of information is required at 15 minute intervals .

following completion of initial or previous follow-up notifications.

EXCEPTIONS: Following initial notification of the NRC, an open communication line will be established and maintained to provide continuous updating to the NRC. Follow-up notifications are not required for the Unusual' Event classification.

3.2 Abbreviations

. 3 2.1 TSC - Technical Support Center i 3 2.2 OSC - Operations Support Center 3.2 3 EOF - Emergency Operations Facility 4 3 2.4 ED - Emergency Director 325 IED-Interim Emergency Director 3 2.6 E.O.C-Emergency Operations Center 4.0 PREREQUISITES and CONDITIONS 4.1 Unusual or abnormal plant or site conditions exist which necessitate implementation of the Emergency Plan and the applicable Emergency Classification has been declared.

50 PROCEDURE 51 Initial Notifications

\

PAGE 2 0F 5

n= .=w= . .. . . - - - .- . . . _ . - . . . , .

.EPP-002 REVISION 7 6/1/83 p

5 1.1 Upon declaration of the appropriate emergency classification, the ED/IED will direct the c anmunicator to implement -the appropriate notifications.

NOTE:

' - ~ ~

Refer to EPP-016 Attachment II for personnel, by title, who should-be the designated communicator.

5 1.2 1Due ED/IED will assure that the required information is available to effect prompt notification. ,

5 1.3 The communicator will, upon direction from the '

ED/IED, implement the initial notifications. The information in Attachment I is to be given to the personnel / agencies as listed in Attachments III A, III B, III C, or III D depending upon the classification of emergency.

NOTE: ' Attachments III, IV and V list alternates for various personnel. These notifications attempts are to be made in numerical sequence as f.ndicated and will-be considered complete upon successful notification of one of the listed.

52 Notifications for Change in Emergency J1assification NOTE: If classification change is made in the middle of a notifications sequence the communicator will terminate that notification sequence, and initiate the new notification for current status.

5 2.1_ Upon escalation to a higher emergency classification, the communicator will, upon direction from the ED, implement notifications per

- the section of Attachment III which corresponds to the higher emergency classification, and -

Attachments IVA and IVB.

5.2.2 When the emergency classification is downgraded, the communicator will, upon direction f rom the ED, implement notifications per the section of Attachment VI which corresponds to the classification which is being changed.

b PAGE 3 0F 5 u--e . e- ., ~~. ..

~. . - - , .-__ _._. . , - _ . _-. .__

EPP-002 REVISION 7 6/1/83 1

- C.

53 Off-site. Emergency Services

- 531 Upon direction from the ED/IED, the communicator will' implement the requested notification (s) per. '

~ Attachment ~V.

532 Upon direction from the ED/IED, the communicator will contact other utilities for assistance using the "INPO" Resource Guide, Reference 2.4.

NOTE: The Resource Guide is available in the TSC and EOF. .

5.4 Follow-up Notifications 5.4.1 Pollow-up notifications are required for all-emergency classifications except Unusual Event.

5.4.2 -The communicator will implement follow-up notifications. (The information in Attachment I and II is to.be given to the personnel / agencies as listed in Attachments VI A, VI B, or VI C depending upon the emergency classification.)

5.4 3 Follow-up notifications will be made by the site communicator (s) until-the EOF is activated and

- ~

assumes all off-site notification responsibilities.

Thereafter, the site communicator will transmit applicable updated information to the EOF as it becomes available.

5.4.4 Follow-up notifications to the Emergency Preparedness Division and the counties shall be made by the TSC or EOF Communicator until such time that the S.C. State. Forward EOC is staffed r.nd communications are established. When the S.C.

l Forward E.O.C. is activiated, all communications,

.: between the plant and state and county agencies will go to the S.C. Forward E.O.C. via the j ,

dedicated phone line or established land line.

l l NOTE: All transfers of notification responsibilities shall be documented.

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EPP-002 REVISION 7 l 6/1/83 b.- -

55 Vital Personnel Notification 551 The communicator will notify vital personnel as directed by the ED/IED per the Vital Personnel Telephone Listing available in the Control Room and the TSC or by radio pager as per Policy Memorandum No. 25 5.6 TSC/OSC/ EOF Communications 5 6.1 TSC-OSc - telephone list are provided in Attachment VII.

4 5.6.2 EOF - telephone list are provided in Attachment VIII.

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PAGE 5 0F 5

EPP-002-.

ATTACHMENT I PAGE 1.0F.2-REVISION 7 o

.b $ARNING MESSAGE: NUCLEAR FACILITY-TO STATE / LOCAL GOVERNMENT Part I -

1. This is-the Summer Nuclear Station.

2. My name is Edis message'(number ): : Initial (a)~ Reports a real emergency. Follow-up (b) Is.an-exercise message.- Time message given

~

4. - Me *al anhone number / extension is: ,.

. or N._

5 You may call back at the end of the message for verification.

6. The class of the emergency is: (a) Notification of Unusual Event (b) Alert (c) Site Emergency (d) General Emergency

^

7 This classification of emergency was declared.at:-

(a.m./p.m.~) on (date).

8. The intiating event causing the emergency classification

1s:

~

6 9 The emergency condition: (a) Does not involve the

' release of radioactive materials from the plant.

(b) Involves the potential for a release, but no release is occurring.

(c) Involves a release of

i. ,

radioactive material.

10. We recommend the following protective action:

_(a) No protective action is recommended at this i' time.

. (b) People-living in zones remain indoors with the doors and windows closed.

7 EPP-002 ATTACHMENT I PAGE 2 0F 2 7_, REVISION 7 i

(c) People living in zo'nes evacuate their homes and businesses.

(d) Pregnant women and children in zones remain indoors with the doors and windows closed.

(e) Pregnant women and chil'dren in zorias evacuate to the nearest reception center.

(f) Other recommendations:

11. There will be:

(a) A followup message .

l (b) No further communicatione

12. I repeat, this message:

(a) Reports an actual emergency (b) Is an exercise message

13. Are there any questions?

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EPP-002 ATTACHMENT II PAGE 1 OF 2 REVISION 7 0i s WARNING MESSAGE: NUCLEAR FACILITY TO STATE / LOCAL GOVERNMENT Part II -

1. The type of actual or projected release'is:

(a). Airborne (b) Waterborne. -

(c) Surface spill (d) Other

2. The source and description'of the release is:

3 (a) Release began /will begin at a.m./p.m.; -

time since. reactor trip is. houn .

(b) The estimated duration of the release is hours.

4. . Dose projection base data:

4 Radiological release: curies, or curies /sec.

Windspeed: mph

.- Wind direction: From

\

Stability class: (A,B,C,D,E,F, or G)

Release height: Pt.

Dose conversion factor: _R/hr/01/m3 (whole body) )' -

R/hr/01/m3 (child thyroid Precipitation:

Temperature at the site: 'F 5 Dose projections:

Dose Commitment

Whole Body Child Thyroid i

Distance Rem / hour Rem / hour of inhalation Site boundary 2 miles 5 miles 10 miles

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EPP-002 ATTACHMENT II PAGE 2 0F 2 REVISION 7

[' WARNING MESSAGE: NUCLEAR FACILITY TO STATE / LOCAL GOVERNMENT Part II (cont.) .

' Pro.fected Integrated Dose in Rem per Unit Time' Distance Whole Body Child Thyroid Site Boundary -

2 miles 5 miles-

_ 10 miles l

6. Field measurement of dose rate or contamination (if -

available):

7 Emergency actions underway at the facility include:

8. Onsite support needed from offsite organizations:

9 .- Plant Status:

(a) Reactor is: not tripped / tripped

[.~- (b) Plant is at 5 power / hot shutdown / cold shutdown /

cooling down

( c) Prognosis is: stable / improving / degrading / unknown.

10. I repeat, this message:

(a) Reports an actual emergency.

(b) Is an exercise message.

11. Do you have any questions?

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EPP-002~

A'lTAC11MBiT IIIA PAGE 1 0F 1

--, , REVISION 7

' INITIAL N01'IFICATION UNUSUAL EVENP PAGER EASY PERSON AGENCY / PERSONNEL NUMBER NORMAL ACCESS - SI'IE . Nurmw TIME

1. Management Duty Supervisors (per Duty Boster)

1) 0111e Bradham

. 2) John Connelly .

. 3) Ken Woodward

4) Bruce W1111mr=

5) Mel Browne ,

W

6) Mike Quinton l

\

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7) Vince Albert L

_. 'S.C. Dept. of Health &

\ s N

Ehviromental Control, Bureau \

of Radiological Health \-

--3. Energ. Preparedness Division . \

4. 'NRC .See Attachnent IVA of EPP-002 for 100 Initial Notification

5. Media Coord. (Mgr., Nuclear Info.)

Ecme Office r;

1) Becky McSwain \

\

2) ist Alt. - W. M. Lide, Jr. \

6. Site Services Manager-Bob Stough

7. Institute of Nuclear Power Operations (INPO) *

'N~- .. - . - - _ .

8. American Nuclear Insurers (ANI) See Attachmnt IVB of EPP-002 for ANI Notificaticn

' NOTIFICATIONS COMPLEIE:

CALLER'S SIGNATURE DATE

' Dedicated Line Also Exists.

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EPP-002-

.lNITIAL NOTIFICATICN A'FPACINENE IIIB PAGE 1 OF 1 ALERP REVISICN 7 O

PAGER NUMBER NORMAL EASY ACCESS SITE PERSON Nunnt.v TIME AGENCY / PERSONNEL,

~ -

1. Managenent Duty Supervisors (per Duty Bester) ___

2) John Connelly ,__

3) Ken Woodward

4) Brum Williams

5) Mel Browne .

6) Mike Quintm

7) Vince Albert NOIE: 'Ib cmtact additional Energency Respanse Personnel refer to Policy Memorandum No. 25 . .

2. 'S.C. Dept. of Health &

Ehviremental Cmtrol, Bureau of Radiological Health

3. Energ. Preparedness Division a

4. *NBC - See ittachnent IVA of EPP402 for NBC Initial Notification

5. Media Coord.-(Mgr., Nuclear Info.)

Home Office 7 .- _._.

1) Becky McSwain .

2) 1st Alt. - W. M. Lide, Jr. ___

6. Site Services Manager-Ibb Stou6h

7. Institute of Nuclear Power Operations (INFO)

\

8. Fairfield Pumped Storage Facility

9. American Nuclear Insurers (ANI)' See Atta$ kent IVB of EPP-002 for ANI No'.,iricatim

'NCTIFICATICNS CmPLEIE:

CALLER'S SIGNATURE DATE

Dedicated Line Also Exists.

~

EPP-002-ATTACHMENT IIIC

- INITIAL NOTIFICATION PAGE 1 0F 1

. REVISION 7

" SITE EMERGENCY" NAME OF

/- PAGER EASY PERSON r AbudCY/ PERSONNEL- NUMBER NORMAL ACCESS SITE NOTIFIED TIM 3

1. Management Duty Supervisors (per: Duty Roster) . . . -

1) Ollie Bradham

2) John Connelly

3) Ken Woodward

4) Bruce W11111ams

5) Mel Browne .

6) Mike Quinton

7) Vince Albert ~! g NOTE: To contact additio'na$ Emergency Response Personnel, refer to -

Policy Memorandum-No. 25

2. 'S.C. Dept. of Health &

Environmental Control, .\

. Bureau of Radiological i

. Health k N/A

- 3. - Emerg. Preparedness Division \( ___

N/A l

~4. #NRC See Attachment IVA of EPP-002 for NRC

Initial Notification Requirements

~

5. Media Coord. (Mgr.,

Nuclear Info.) ,

Home Office

1) Becky McSwain \. .

1

2) lat Alt. - W.M. Lide, Jr.

6. - Site Services Manager -

Bob Stough 7 Institute of Nuclear Power Operations-(INPO)

8. Fairfield Pumped Storage f Facility L. . _ _ _ _ - - _

- 9. - American Nuclear - Insurers See Attachment IVB of EPP-002 for ANI Notification.

NOTIFICATIONS COMPLETE:

Galler's signature Date

' Dedicated Line Also Exists.

- r

EPP-002 ATTACliMENT IIID PAGE 1 0F 2 REVISION 7 INITIAL NOTIFICATION

" GENERAL EMERGENCY" .

NAME OF PAGER EASY PERSON AGENCY / PERSONNEL NUMBER NORMAL ACCESS SITE NOTIFIED TIME

1. Management Duty Supervisors (per Duty Roster) _

1) Ollie Bradham .

2) John Connelly

3) Ken Woodward

4) Bruce Williams _

5) Mel Browne

6) Mike Quinton

'7) Vince Albert _

NOTE: To contact additional Emergency Response Personnel, refer to Policy Memorandum No. 25. -

~ ~ ~ ~

2. 'S.C. Dept. of Health & T' ~

Environmental Control, Bureau of Radiological Health ,

3 'NRC See Attachment IVA of EPP-002 for NRC Initial Notification Requirements

4. -Media Coord. (Mgr. , Nuclear Info.) Home Office

1) Becky McSwain '

2) -1st Alt. - W.M. Lide, Jrl 5 Site Services Manager -

Bob Stough

6. Fairfield Pumped Storage Pacility

,. ' Emergency Preparedness Division-gtankOG neral's Office i

" - - ~ ' ~

eDedicated'Line Also Exists.

t

. EPP-002 ATTACHMENT IIID i PAGE 2 0F 2

. . REVISION 7 INITIAL NOTIFICATION

" GENERAL EMERGENCY" NAME OF EASY PERSON AGENCY / PERSONNEL NORMAL ACCESS SITE NOTIFIED TIME N/A

8. 'Fairfield County

[

9..*Newberry County N/A

10. *Richland County- N/A -

11. 'Lexington County N/A-

12. - Institute of Nuclear-Power Operations (INPO) N/A 13 American Nuclear Insurers See Attachment IVB of EPP-002 for ANI - ~

' Notification.

\

NOTIFICATIONS COMPLETE:

Caller's Signature Date 0 Dedicated Line Also Exists.

eaa a e ape +ee a ope N * "*M-e aw7+ usse w ae - e emm.e

EPP-002 ATTACHMENT IVA PAGE 1 0F 4

.gss. .

REVISION 7

,g NRC ONE HOUR-NOTIFICATION The NRC shall be notified within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of Declaration of an Energency in accordance with Pages.2 through 4 of this attachment.

EASY PERSON 1 NORMAL ACCESS CONTACTED

1. NRC - Bethesda, Md. Dedicated Phone N/A a) Commercial telephone system to NRC Operations Center (Via BethesdaCentralOffice).[

b)NRC-Atlanta,Ga.k

2. NRC - Resident Inspector Yes No . _ _

Jack Skolds C' N.O. Ext)

\ Home Phone NO.

or i '.

5eeper Ko.

CALLERS SIGNATURE DATE TIME f

I

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3 1 4 q EPP-002

') 6? ATTACHMENT IVA 4 -

- PAGE 2 OF 4 fN -

REVISION 7

'. 1 '

NRC ONE HOUR ~

NOTIFICATION g:l '

i A. Identif1 cation:

This is the Summer Nuclear Plant.

My name is .

Our phone number in-x y'4 ._ _

B.. Event Classification: ,

,3- We are now in a(n)

EVENT CLASSIFICATION

which was declared at ,

TIME C. DESCRIPTION: -- -- -- -

What Happene'd:

. Cause:

t Consequences:

Actions: __

Current Status:__

f s D. . LICENSEE NOTIFICATIONS: (What notifications have been made.)

STATE (S). LICENSEE MANAGEMENT I- LOCAL OTHER NRC RESIDENT OTHER-E. PRESS RELEASE: Has a press release been made or planned? Yes No ye*

4 s ,q u - . . . .. .. . - . . . - - . . . . - . -- .s m

EPP-002 ATTACHMENT IVA PAGE 3 0F 4 REVISION 7 NRC ONE HOUR NOTIFICATION isrt II-Complete for all ALERT, SITE AREA, and GENERAL emergencies l Licensee Actions: .

Taken Planned -

Property Damage Radioactivity Released (or Increased Release):

Liquid / Gas? Location / Source of Release Elevation ,

Release Rate Duration Stopped?

Release Monitored? Amount of Release 5 Tech. Specs. .

Increased Radiation Levels in a Plant: Location (s)

Radiation level (s) Areas Evacuated Maximum site boundary dose rates Location Integrated dose Location Meteorology:

l Wind Direction from Wind Speed (Meter /sec or miles /hr)

T (*C or*F) Temperature (*C or 'P)

Stability Class A B-C D E F G Raining (Yes/No)

Projected Peak: Dose Rates Integrated Dose 2 mi (WB/I) (WB/I) 1 5 mi (WB/I) (WB/I) l 10 mi (WB/I) (WB/I) l Sectors (WB/I) (WB/I) l l Contamination (Surface): inplant onsite offsite

! Reactor Operations:

l Reactor System Status Power Level Pressure Temp Flow (pumps on)

Cooling Mode ECCS Operating / Operable _,

Containment Status Containment Icolated? Containment Temp Containment Press Conte.inment Radiation R/hr.

Leak Rate R/hr.

Reactivitr Control Control Rods Inserted Status of Ener. Boration System

..---._ -__ _-..__-~_ _ ..,,-_ .___ .- , ~.

._ __- . - - ___ _,_..-._---_._. . . . - . . _ ~ .

. . _ . . ~

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^

.____._...m__.

. EPP-002 i

-ATTACHMENT IVA PAGE 4'0F 4 n REVISION 7 i'

INCIDENT NOTIFICATION INFORMATION l . . Part II Steam Plant Status:

S/G Levels _ Eq.uip. Failures Feedwater Source / Flow S/G Isolated?

Electrical Dist. Status: -

Normal Offsite Power Available?

Major Busses / Loads Los t .

D/G Running? _ Loaded?

Security / Safeguards:

Bomb Threat: Search Conducted?

Search'Results Site Evacuated?

Extortion: Source (Phone, letter, etc.)?.

Location of Letter Intrusion: Insider? Outsider?

Furthest Point of intrusion

. Fire arms related? Stolen / Missing Material?

Demonstration: Size of Group Demanda Violence? Fire arms related?

Sabotaae/ Vandalism: Radiological? Arson Involved?

Stolen / Missing Material?

7 t

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2 . -. _ _:::::._ _ _ - ..

EPP-002 ATTACHMENT IVB PAGE 1 0F 3 REVI,SION 7 g

ANI EIGHT HOUR NOTIFICATION ANI is to be notified within eight (8) hours of the declaration of an Alert, Site Emergency, or General Emgergency in accordance with pages 2 and 3 of this attachment.

American Nuclear Insurers ( ANI) Phone No. .

Easy Acceau

. Person Contacted Time Date Callers Signature b

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. EPP-002 ATTACHMENT IVB PAGE 2 0F 3

-,, , REVISION 7 ANI NOTIFICATION i

(1) This is !

(Name) (Title) !

(2a) This is a drill !

l (2b) This is NOT'a drill (3) I am notifying you of an accident at the V. C. Summer Nuclear Stacion which occurred at:

(Date) (Time)

(4) This emergency is classified as a _ .

(5) Description of event:

(6) Radiation Release Yes No.

(If yes, complete 6a through 6j)

(6a) Type of Actual Release or Type of Projected Release:

(6b) Estimation of Duration of Public Impact:

(6c) Release Rate: (6a) Noble Gas (6b)

(6c) Release Height (6d) Meteorological Conditions: (6a) Wind Speed (mph)

(6b) Wind Direction (blowing to)

(6c) Stability Class (6d) Precipitation (6e) Projected Dose At: Site Boundary 2 Miles 5 Miles 10 Miles (6f) Dose Rate--Whole Body (10A) (10B) (100) (10D)

(6g) Integrate Whole Body Dose

(' hour projection) (11A) (11B) (110) (11D)

(6h) Dose Rate--Thyroid (12A) (12B) (120) (12D)

(61) Integrated Infant Thyroid

( hour projection) (13A) (13B) (130) (13D)

(6j) Sectors Affected (14A) (14B) (140) (14D) l l

l l

.-. ,, . - , - - , . . , - - . , - - ~ , . . , - _ . . - , - - . . . , . . . - , , , , . - . , , . , - , , , , , , . , - , - , ,,--,-, -,m

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~ - -

. _ _ . _ _ . _,. _. . . -.., . .. m . __ m _

i EPP-002 ATTACHMENT IVB PAGE 3 0F 3

-. . , REVISION 7 i ANI NOTIFICATION (7) Injured Personnel Yes No.

(if yes, complete 7a through 7d) ,

(7a) Number of injured personnel (7b) Is Is Not Radioactively Contaminated (7c) Injury

Description:

(7d) Requires Transportation to off-site Medical Facility -

Yes No.

b (8) Off-Site Emergency Assistance / Actions Requested Yes No.

(If yes, complete 8a through Sc)

Yes/No Reason (8a) Law Enforcement (8b) Fire Departments s (8c) Hospital Facilities (9) Public evacuation required Yes No Not at this time (9a) If "Yes" or "Not at this time", affected sectors 1

' ~~

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EPP-002

~

ATTACINENE V PAGE 1 0F 3 REVISION 7

?-

OFF-61TE EMERGENCY SERVICES NAME OF PERSON AGENCY / PERSONNEL PHONE Nura;2v TIME A. Company Physicians (Pinner Clinic)

1) Carrol A. Pinner III M.D. - Primary f (24 hrs.~)

2) Harriet E. Pinner, M.D. - 2nd' Alternate B. Hospital Pacilities .

1) Richland Memorial Hospital Give the following information:

' Ibis is the Virgil C. Amur Nuclear Station.

'Ihis is a Drill 'Ihis is not a Drill We have contaminated /nonentaminated injured person being transported to your '

facility.

2) Radiation Ebergency Assistance

\~

Center Training Site (Reacts) 24 hour-C. Ambulance Service r~ ,

la) Emergency Medical Services of Fairfield County Ib) . Alert MAST for standby ,

transportation.

N

-2) U.S. Arw MASf Operatials (

NOIE: Alert Security of Emergency Vehicle arrivb. as soon as request (s) for Off-Site Ebergency Services are coupleted.

Ext or '.

9 9

I e

"~ ' .

m_ w me w m o w. wd - .-

EPP-002 ATfACHMENT V PAGE 2 OF 3 REVISION 7 0FF-SITE D4ERGENCY SERVICES NAME OF PERSON AGENCY /PERSONNZL PHONE PUmitD_ TDE Give the following infonnation for items la and 2 above.

This is a Drill This is not a Drill We have contaminated /non-contaminated

' injured person (s)' requiring transportation to Richland Memorial Hospital. (1he anbulance nust enter the site via the main gate, using .

(denote route to be taken) or the helicopter should land at the primary larxiing pad (denote route to be taken)

D. NSSS Sipplier/A.E.

Title- Name Office Home HHL

1. Site Service Manager Bob Stough .

Notes: (1) The area code of the above phone numbers is ' ' ' ' ,

(2) The phone beeper nunber is ' I

2. Operating Plant Service Jolst Miller Manager 1st Alternate Tim Sullivan

.2nd Alternate Rich Faix 3 Service Response 'Ibn Milto Manager lat Alternate Bob Stokes l 2nd- Alteernte John Miller i

. 4. Energency Response Tom Anderson Director .

~

5. Bnergency Response Ron Lehr Deputy Director

6. Snergency News Mike Mangan Ccrmunications _ _ - -

. Note: Unless indicated otherwise, all phone numbers are area code 412. Where an area code other than 412 is shown, it applies to the office, hone, and HHL rumbers

2) GAI '

~

(Normal .

Workin6 Hours) ri. '

/

O

t EPP-002 i ATTACHMENP V PAGE 3 OF 3 REVISION 7 p,

OFF-SI'IE EMERGENCY SERVICES ,

NM45 0F PERSON AGENCY /PERSCNNEL PHONE NOPIFIED TDE

~

E. Fire Services

1) Fairfield County Fire Services Give the folicwing infon::ation:

'Ihis is the Virgil C. Surmer Nuclear .

Station. . .

'Ihis is a Drill This is not a Drill-We request fire fi 6hting assistance ,

at the Su::mer Nuclear Station. The fire-tnick nist enter via the main gate, using (denote route to be taken) ,e I

- F. Local Law Enforcement or (aff--normal hours) L >

G. National Weather Service (Backup to Load Dispatcher for weather informaticrl).

,'~~

1) Columbia - /

/ .-

%O" t

9

EPP-002 ATTACHMENT VIA PAGE 1 0F 1 REVISION 7

,r' FOLLO,WUP NOTIFICATION

~

ALERT NAME OF EASY PERSON AGENCY / PERSONNEL NORMAL ACCESS NOTIFIED TIME 1.* S.C. Dept of Health &

Environmental Control,-

Burea'u of Radiological Health Notifications conplete: .

Caller's Signature Date

Dedicated Line Also Exists.

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EPP-002 ATTACHMENT VIB

-PAGE 1 0F 1 REVISION 7

\ ~ , FOLLOWUP NOTIFICATION SITE EMERGENCY- -

NAME OF EASY CALLERS PERSON AGENCY / PERSONNEL NORMAL ACCESS SITE SIGNATURE NOTIFIED TIME - -

1.0 S.C. Dept of Health &\. .'

Environmental Control, \

Bureau of Radiological \ .,

Health Notifications complete:

Caller's Signature Date NOTE: When the State Forward EOC is established the State BRH will move their operation to the State Forward EOC and communication will be via the State Forward E.O.C. Dedicated Phone.Line.

Ded,1cated - Line Also Exists.

m l

4 0

l l

l L _. . . ._ . _ _ _ _ _._ - ._ .___ . _

- EPP-002 ATTACHMENT VIC

. PAGE 1 OF 1 REVISION 7

7. ~

(

FOLLOWUP NOTIFICATION ,

^

G,ENERAL EMERGENCY

^

NAME OF EASY PERSON AGENCY / PERSONNEL NORMAL ACCESS -- -NOTIFIED TIME 1.0 S.C. Dept of Health & '

/

Environmental Control, Bureau of Radiological /

Health .-

The following notifications shall be made by the TSC or EOF

~

Communicator until such time that the S.C. State forward EOC is .

staffed.

p -

~~ ___

2.0 Emergency Preparedness Division Adjutant General's Office - - - --

- 3.0 Fairfield County 4.5 Newberry County l \

5. .dichland County [.

6.0 Lexington County. ,

Notifications complete:

Caller's Signature Date NOTE: When the State Forward EOC is established the State BRH will move their operation to the State Forward E00 and communication will be via the State Forward E.O.C. Dedicated Phone Line.

Dedicated Line Also Exists. ,

A e

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EPP-002 ATTACHMENT VII PAGE 1 OF 2 e

REVISION 7 I~' TSC/OSC EMERGENCY TELEPHONE LIST Nuclear Regulatory Commission (NRC Area and E.O. A) f~

Nuclear Regulatory Commission f.

Nuclear Regulatory Commission I

TSC Display Room i TSC Display Room Dose Assessment Area ,

l Technical Support Engineers Technical Support Center Communicators Technical Support Engineers Assistant Manager, Support Services-Vince Albert Security Supervisor-John Sefick Telecopier Phone to EOF .,

t

Radiation Monitoring Teams Data Logger Radiological Assessment Supervisor-L.A. Blue

! Assistant Manager, Technical Support-M. Browne

! Emergency Director l

Emergency Operations Area- General Use l

Westinghouse (NSSS) ,

GAI (A/E)

OSC.

OSC

\

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__

. EPP-002

~

TECHNICAL SUPPORT CENTER PAGE 2 of 2 REVISION $ ,

/*a

~

NRC.._

PLANT STATUS DISPLAY AREA _

- < . DOSE ASSESSMENT AREA _

~

,n /

l

/ EMERGENCY .S$IFT .

f D-1 OPERATIONS SUPERVISOR.

TECHNICAL D-2 SUPPORT AREA D-3 On .i.CE AREA l

D-4 '

I .

f ,

i COMMUNICATIONS AREA [

'(Telecopier) -

< 1 .

MONITORING NSSs A/E

- TEAMS AREA AREA AREA D-6

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EPP-002 i ATTACHMZNT VIII PAGE 1 OF 4 REVISION 7 g.

t Emergency Operations Facility -

Layout a

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2. d M.-Gl. *# sIE.NI$ I 1 D " " "' % d i 1 - COMMAND CENTER (Room 144) 9 - NRC AREA (Room 122) .

2 - TECHNICAL SUPPORT AREA (Room 145) 10 - CONFERENCE ROOM (Room 3 - OFFSITE RADIOLOGICAL MONITORING AREA 143 (Room 145) 11 - COMMUNICATIONS AREA 4 - GENERAL SERVICES AREA (Room 138) (Room 140) 5 - CONSTRUCTION / REPAIR AREA (Room 138) 12 - REPRODUCTION AND 6 - MEDIA AREA (Room 141) RECORDS STORAGE AREA 7 - LOCAL GOVERNMENT AREA 13 - STROAGE AREA

. (Room 142) N 8 - STATE GOVERNMENT AREA (Room 124)

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EPP-002 ATTACHMENT VIII PAGE 2 0F 4 REVISION 7 r" OFF-SITE EMERGENCY TELEPHONE LIST Emergency Operations Facility

1. COMMAND CENTER

[ EOF-Media Coordinator (R. McSwain)

EOF-Emergency Control Officer (0.W. Dixon)

, e EOF-Offsite Radiological Monitoring Coordinator (B. Baehr)

/ EOF-Security Coordinator (J. Harrison) f .

EOF-General Services Coordinator (J. Bailey)

EOF-Construction / Repair Coordinator (J. Woods)

EOF-Technical Support Coordinator (M. Whitaker)

EOF-TSC/ EOF Dedicated Phone

2. TECHNICAL SUPPORT AREA EOF-Te chnical Support Engineers EOF-Technical Support Engineers /Telecopier

(

3. OFFSITE RADIOLOGICAL MONITORING AREA EOF-Offsite Rad. Monitoring EOF-Offsite Rad. Monitoring

)

EOF-Offiste Rad. Monitseing

(

l

. 4. GENERAL SERVICES AREA EOF-General Services Personnel EOF-General Services Personnel EOF-General Services Telecopier y --

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EPP-002

. ATTACHMENT VIII PAGE 3 of 4 REVISION 7

~m,. OFF-SITE EMERGENCY TELEPHONE LIST Emergency Operations Facility .

5.. CONSTRUCTION / REPAIR AREA i

EOF-Construction Personnel EOF-Construction Personnel

6. MEDIA AREA EOF-Company Media Personnel EOF-Company Media Personnel -

EOF-Company Media personnel 7.; LOCAL GOVERNMENT AREA EOF-Local Government Officials f . EOF-Local Government Officials EOF-Local Government Officials

8. STATE GOVERNMENT AREA ,

EOF-State Government Officials EOF-State Government Officials 9 NRC AREA EOF-NRC Officials EOF-NRC Officials EOF-NRC Officials EOF-NRC Officials L

e e

O G

7 Y M - -

- ' EPP-002

. ATTACHMENT VIII PAGE 4 OP 4 REVISION 7 OFF-SITE EMERGENCY TELEPHONE LIST Emerg*ency Operations Facility.

10. COMMUNICATIONS AREA EOF-Emergency Communicator

- 11. , SECURITY CONTROL POINTS EOF-Hallway Area EOF-North Entrance . .

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COPY No....d-] ~ ~ "*""""

SAP-139 ATTAOiMENT IV

'. PROCEDURE DEVELOPMENT FORM - A PAGE 10F 3

1. DATE: [/I/83-

/

PROC. # [ 8 M - d C 1_ REY. # NN7 CHG. # /

REVISION 0 TITLE: b m/m u.n n'c a.bb a d Nok'M* ah, PE'44ANENT7 ><. RESTRICTED FROM TO SAFETY RELATED7 , - -

NEW PROC 7 REV1SlON7 "'. S ",:CT Q G4ANGE7 =>c Yes No N ~

11. DESCR IPTION: (See Section 6.3.4)

S t.Jist jfffe.c.A N % A h Sh a $a.A ).< i h av m.e & em-- .r- d*A r E LhW-- Nek - No. 1r 3- s'/

Ill. WILL THIS REVISICN/CHAPGE/NEW PROCEDt.RE7 Yes No

1. Represent a change to proadures as descri bed in the FSM7 (50.5 revlow) 1

2. Represent i test or experiment not described in the FSM7 (50.59 revi ew)

3. Requi res a -hange to Technical Spect fications? (50.5 revi ew) 4 Result in slJnl ficant inc eased personnel radiation exposure? (ALARA review)

StNMARY JUSTlFICAll0N (List FSM References) (attach additional pages as requi red):

g

$~k Q vn s~~~~ A *f ]~d [ 4 lr No.fiaa Afo. t 3- 34

.w/JM ( (Orl ai n'Efor)

Ve aA t-(Evaluated by Ol'YEToll ne Supervi sor) 6/ss

/ Dete)

NOTE: If the answer to any of the above questi ons i s "YES" - See Secti on 6.3.3 of procedure.

IV. A. REQUIRED REVIEW Ato COMMENT 8. COMMENTS vl A TELECDN COMMENTS i

^

t SAP ' OTHER Date / Time Person Contacted YES NO

. ) Op ()4 (R (d) /

( (;O oos. / _ _ , , , , , ,

( QQ K, % /o /

() S () /

()

(

( ) CA

()

/

((

() Telecon Ort gi nator PEV1 EWERS CCN@iTS RE!DLVED: 'k (01 sci pil no Suoervi ser (Oste)

V. FINAL QA REVIEW ( As applicable, ref er to section IV.A)

VI 1. PSRC REVIEW Conctrrence Date A. Reviowed by:

VI. FINAL APPROYAL: /

PSRC CHAIRMAN Dat e A. Responsible Individual Cementsa Yes No Approval /Concurrones 'Date B. PSRC Cements Resolwds B. PSRC Roview Requi red: Yes No /

ASSISTANT MANAGER Date PD f~ rn/f. ,

PSRC CHAIRMAN Date i

N.

JUN 2 81983

, +m4es .m e ee-e .mm..*=h*** * " * *'M*

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- - EPP-002

' ATTACHMENT IVA PAGE 2 0F 4 REVISION 7 CHANGE 1 NRC ONE HOUR NOTIFICATION

~'

A. Identification:

TIME 0F. NOTIFICATION This is' the Summer Nuclear Plant in Region II.

My name.is- .

. Our phone number is' B. Event Classification:

We are now in a(n)

EVENT CLASSIFICATION

i which was declared at .

- TIME

) C. REACTOR EVENT:

I

Power prior to event . Power at time of report .

e Trip? Initiating Signal SI or ECCS? Initiating Signal _

g ESF actuation?

D. EVENT DESCRIPTION AND CAUSE t

k Radioactive releases? (Quantify)

. f, .

i Other major problems l E. PLANT ACTIONS / PRESS RELEASES?

I

.i

-l F. NOTIFICATIONS?

I j STATE PLANT MGMT.

,'l i ..

LOCALS OTHER NRC RESIDENT OTHER

,O SOUTH, CAROLINA ELECTRIC AND GAS COMPANY VIRGIL C. SUMMER NUCLEAR STATION NUCLEAR OPERATIONS t

NtCIA'R OPERATION .

CDP 1 No 67 * * '"'"

EMERGENCY PLAN PROCEDURE EPP-003 IN-PLANT RADIOLOGICAL SURVEYING REVISION 3 APRIL 26, 1983 NON-SAFETY RELATED s

\

/

Reviewed by:

T' #/5'/B

' Uate OR{GINATOR Iof this revision) et ,V. S-3 DISCIPLINE SUPERVISOR Date Approved: .

A $ Nlft PLANT MANAGER Date

'") Date Issued::JUN O 11993

{

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& GNB3 DAM

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c' ,

EPP-003 PAGE i

-REVISION 3

-[ ,- 4/26/83 -

s . LIST OF EFFECTIVE PAGES' PAGE ,

REVISION 1 3 11 3 1 3 F 2 3 3 3 .

4 3 5 3 ATTACHMENTS ATTACHMENT I 3 ATTACHMENT II 3-i ATTACHMENT III 3

( -\

/

ATTACHMENT IV 3 ATTACHMENT V 3 P

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EPP-003 PAGE 11 REVISION 3 l n '

4/26/83 .

TABLE OF CONTENTS PAGE .

List of Effective Pages 1 1.0 PURPOSE ,

1 1

2.0 REFERENCES

1 3 0- CONDITIONS AND PREREQUISITES 4.0 PROCEDURE - 2 ATTACHMENTS Attachnent I - Survey Record Attachnent II - Approximation of Air Sample Iodine and Particulate Concentrations with RM-14 and HP-210.

Attachnent III - Estimate of Iodine Concentration with RM-14 and HP-210 Attachnent IV Estimate of Particulate Concentration' with RM-14 and

, N HP-210 Attachnent V'- RCA Access Routes

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c EPP-003 REVISION 3 4/26/83 O '

~-

1.0 PURPOSE 1.1- Provide. guidance for the direction and Unplementation of-Radiological Surveys inside the plant.in the event of an- .

I emergency. This procedure 4 shall be Dnplemented upon the decision of the Radiological Assesanent Supervisor or his designee when there is an actual or potential degradation in the control of radioactive materials warranting the protective actions set forth in this-procedure.

2.0 REFERENCES

2.1 " Virgil C. Summer Nuclear Station Radiation Energency ,

Plan".

4 E 2.2 HPP-151. "Use of Radiation Work Permit (RWP) and Standing j ,

Radiation Work Permit (SRWP)".

23 HPP-401, "Is sue, Te rmination, and Use of RWP's".

2.4 HPP-153. "A&ninistrative Exposure Limits".

25 EPP-019, "Energency Equipnent Checklist".

I.

. 2.6 HPP-302, " Radiation and Contanination Survey Technique \

6" sa 2.7 HPP-810, " Sampling. of Radioactive Gases and Liquida".

2.8 HPP-303, " Airborne' Activity Sampling Techniques and

. Procedures". ,

30 CONDITIONS AND PREREQUISITES

! 31 In-Plant surveys will be' directed from the TSC, Control

.;. Room, or HP Lab.

- 32 The In-Plant Monitoring Director should report to the TSC Limmediately af ter notificat' ion or upon Protected Area-Evacuation. .

! 33 In-Plant monitoring personnel should report to the H.P. Lab or as directed by the In-Plant Monitoring Director bmnediately upon' notification or upon Protected Area s

Evacuation.

~

34 . Standing RWP's are not applicable for: entries into areas F with severe or unknown exposure potential.

35 Entries into areas where a severe or unknown potential for radiation exposure exists should be limited to:

- : v-PAGE 1 0F 5 _

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EPP-003

' REVISION 3 4/26/83 s 1.0 PURPOSE 1.1 Provide guidance for the direction and unplementation of Radiological. Surveys inside the plant in the event of an ,

I emergency. This procedure shall be implemented upon the decision of the Radiological Assessnent Supervisor or.his designee when there is an actual or potential degradation.

in the control?of radioactive materials warranting the protective actions set forth in this procedure.

2.0 REFERENCES

, 2.1 " Virgil C. Sunmer Nuclear Station . Radiation Energency '

i Plan".

2.2 HPP-151. "Use of Radiation Work Pennit (RWP) and Standing Radiation Work Permit (SRWP)".

23 HPP-401, " Issue, Termination, and Use of RWP's".

2.4 HPP-153. "A&ninistrative Exposure LLnits".

2.5 EPP-019, " Emergency Equipnent Checklist".

2.6 HPP-302, " Radiation and Contanination Survey Techniques" \

s -

2.7 HPP-810, " Sampling of Radioactive Gases and Liquids".

2.8 HPP-303, " Airborne Activity Sampling Techniques and

. Procedures". ,

' ~

e 3.0 CONDITIONS AND PREREQUISITES

~

31 In-Plant surveys will be' directed from the TSC, Control Room, or HP Lab.

3 2 'The In-Plant Monitoring Director should report to the TSC hmnediately af ter notificat~1on or upon Protected Area Evacuation. .

33 In-Plant monitoring personnel should report to the H.P. Lab or as directed by the In-Plant Monitoring Director immediately upon notification or upon Protected Area Evacuation.

3.4 Standing RWP's are not applicable for entries into areas with severe or unknown exposure potential.

_ 35 Entries into areas where a severe or unknown potential for radiation exposure exists should be limited to:

s_- ,

PAGE 1 0F 5 -

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EPP-003

- REVISION 3 4/26/83

,f3

-' 3 5.1 Operation of valves and components essential to the

safe operation of the plant. ,

3 5.2 Repair activities essential to the safe operation of the plant. ,

d 353 Obtaining information necessary for propec evaluation-

> of existing conditions.

4 3 5.4 Rescue attempts to preserve human life. ,

3.6 Areas with severe or suspected severe radiological conditions will be entered using the " buddy system", with a two man back-up team dressed for entry, (with the exception ,

of donning SCBA), in stand-by. -

' NOTE: A minimtan of one back-up team, in stand-by, is sufficient for multiple teen entries. All personnel who are considered back-up (not actually performing an activity)-should renain in an area of low radiation levels where practicle to keep their exposures ALARA.

' 3.7 Protective requirements for entering areas where high levels of radioactive contanination are suspected are as follows:

3 7.1 Minimum . dress requirements:

Cloth overalls 2 pr. disposable plastic shoe covers i Cloth hood 1 pr. rubber boots Plastic suit 2 pr. rubber gloves Cloth gloves Extrenity Dosimetry (as applicable)

TLD and dosimeter High range dostneter NOTE: Backup tesna should not don the plastic suit until ready for entry into the affected area.

3 7.2 Additional protective requirements are as follows:

M

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- PAGE 2 OF 5

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l .

EPP-003 REVISION 3 4/26/83 i O. Protective Requirenents

] ,

^

Condition'

Noble gas concentrations . TLD placed under protective.

suspected > 1 x 10-3 clothing.

uci/ml Eye protection if fuel danage has occurred or suspected.

Iodine concentrations- SCBA

suspected > 10 x MPC Lapel Air Sampler H3' concentrations SCBA.

suspected > 10 x MPC. .

Plastic Suit Particulate concentrations Particulate mask or SCBA suspected > 10 x MPC . (SCBA required if > 50 x MPD suspected). Lapel Air Sampler -

Standing water > 1" Waders suspected Extrenity dostnetry Protective requirements may be altered at the discretion of In-Plant Monitoring Director or the Radiological Assessment Supervisor as survey and sample data are available.

38 Continuously monitor radiation levels as surveys are j perfo rmed. Assure prompt notification of the Radiological Assessment Supervisor of any areas where general area.-

radiation levels exceed 1 Ren/hr. At'least one person in each entry party should wear an alarming audible dostneter, if_high radiation levels are expected.

39 Maintain exposure ALARA - Coordinate all-efforts with TSC to prevent unnecessary-exposure.

310 AgZe cartridges must be installed in radiation moniuors RM-A3 and RM-A4 as soon as possible. 0ther radiation monitors affected should have AgZe cartridges installed'as-

! time and conditions permit.

L l 3 11 AgZe iodine filter cartridges should be used for air l sampling when noble gas concentrations are suspected greater I' than 1 x 10-3 pci/ml.

'3 12 Reference 2.6 should be referred to for survey techniques and considerations.

313 Reference 2.7 and 2.8 should tur referred to for sampling techniques and considerations.

l

~.

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PAGE 3 0F 5

4 l

- . . . . . . . - . _ _ , m . . . . . . . _,..___,.a. ___ _ _ _ _ _ _ _ . _ . . , , _ _ , _ _ , . _ _ _ . _ , , _ .

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4. -.=. - ..-.a.. . = . ...

h' EPP-003 REVISION 3

,,s 4/26/83

(' '- : 4.0 PROCEDURE' In-Plant Monitoring Directo'r (guidelines)-

. 4.1

~

4.1.1 ' Activate In-plant survey teams as needed.

4.1.2 Monitor readings from the radiation monitoring system and maintain display drawings and data logs current

$ '4.1.3 Establish and maintain communications with in-plant surveyors.

'4.1.4 Identify and coordinate survey and asupling locations

- and routes taken, with.the Energency Director, '

t - Radiological- Assessment Supervisor, and in-plant surveyors, to minimize exposure.

t NOTE: Attachnent V of this procedure may be used to evaluate and -determine access routes to vital areas under post-accident conditions.

4.1 5 Coordinate issuance of Radiation Work Permits as-specified-in References 2.2 and 2.3.

NOTE: If tLne does not permit- the generation of RWP's to be ,

used initially, ensure the following is entered in

. .the logbook: .date, ttne, work perfonned, ~1ocation, originator /departnent, known radiological-conditions,

. ~

approvals and actual doses received after the job is completed.

4.2 In-Plant Surveyors 4.2.1 Don high range. personal doshneter.

4.2.2 Evaluate the situation (using current data from TSC) and prepare equipnent'needed for Entry. Don L

protective clothing and respiratory protection, as required.

i l

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i PAGE 4 0F 5 l

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u EPP-003 REVISION ~3-

,1 ~ 4/26/83

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'R- NOTE: .A teletector, or equivalent,.should be used 4

'when entering areas of. unknown exposure -

. potential. .I f there is a potential'for'high.

level beta exposure, an instrument calibrated df' for beta measurements -(eg. RO-2) shall be 4

used. Check all:instrunents for response to radiation prior _to use.

gj'g M;

I

% 4.2 3 ; Prior to entry, determine amount of allowable-

. . exposure. Adjust 'setpoint on' alarming Dosimeter accordingly.

I

4.2.4 Perform surveys, as directed from TSC,=per-HPP-302,

^

" Radiation and Contamination ? Survey Techniques) ,

NOTE: TSC.and surveyors should collaborate to-

~ l ' J.' 9 ~1 determine appropriate post accident efforts

" (eg.' type sampling, sample locations, routes, etc. ), to ensure maximun ' data obtained with a 1

" minimum Lof manpower / man Rem expended.

, 7

s. . . , ,

j- ~e Record sample data on Attachnent I.

u .4 ). 2 . 5 e q. i ^;' i l'. 2.6 Relay survey results to TSC by the GAI-Tronics page l or best means available.- -

n ( -

.4.2.7 Transport samples . and smears to count room for - !

' *' analysis.

- ;- 4.2.8.: Perform analysis - of air samples 'at the 412' elevation -[

in the Control Building unless excessive-background

,; is present.

. t. t If excessive background is present, send

^

I

7 4.2.8.1 p .,y samples'to-the Environmental Lab for'

' . Analysis. If results are needed quickly, l

i analyze samples using RM-14 and HP-210 probe s

as instructed by Attachments II and III.

W 4.2.9 Retain and file e.11 survey records in the TSC and/or

~

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submit the records through the Emergency Coordinator 4R . f5./D to)the Docunents Section for retention in the Plant

' : .a dj' '

't J/ .Histery. Files.

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EPP-003 ATTACBENT I PAGE 1 of 1 m

l- REVISION 3 N .

SURVEY RECORD-TYPE OF SURVEY RADICIDGICAIJ j SMEAR M DATE TIME SURVEY BY INST. TYPE INST.

REVIEWED BY SERIAL NO. EFFY.

BUILDING DATE CALIB BKG'D REMARKS COUNTED BY ,

RAnIOLnGICAL Mr/hr BETA SMEAR ALPHA Itan Equipnent or Total Count Gross Net DPM No Location Distance Ganma Beta Neutron Counta Tine cAn cAn 100 ant i

I l

EPP-003

' ATTACHMENT II PAGE 1 0F 1

-/ '

REVISION 3 s-ATT4CHMENT-II .

APPROXIMATION OF AIR SAMPLE IODINE AND PARTICULATE. if CONCENTRATION WITH RM-14 and HP-210 .

Instructions

1. Obtain contact' reading (not 1") on front of iodine filter-cartridge once it is placed in poly bag. Particulate filters cannot be placed in poly bag until after a count rate is .

obtained.

. 2. Detennine .volune of . air sampled in liters or f t3 as indicated on instrument.

3 Use graph (Attachnent III) to approxLnate iodine concentration or perform computation at the bottom of the graph. ' Recommended allowable bsckground is <100 cpm.

4. Use graph ( Attachnent IV) to approximate gross particulate concentration or perform computation at the bottom of the graph. -

Recommended allowable background is < 100 cpm.

\

Bases

1. 'Attachnent III is derived'using .37% detection efficiency with an I-131 stand.rd and a 90% filter collection efficiency.

4

2. Attachnent III does not compensate for noble gas interference.

l This method is limited for counting AgZe filters or charcoal filters used in the absence of noble gas atmospheres.

t i ,

3 Attachment IV is derived using 10% detection efficiency and a 99%

i filter collection efficiency.

4. Calculations at the bottom of Attachment III and IV are based on the constants stated above in steps 1 and 3 The only variablesc

' are the actual volumes of the samples.

I L a.) To determine volume in cu.f t. , multiply run-time in minutes i

by flow rate in cu.ft. (20 cfm x 10 min. = 200 cu. f t) .

b.) To determine volume in liters, multiply run-time in minutes l

by flow rate in liters per minute (201/ min x 10 min. = 200 l liters) f .-

L' ,

l' .

,s -mv e vw = w ~ v-,e .- - .m r , en- e swea e v- ~ * - ,--,e-- -

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5 ESTIMATE OF 100lHE CONCENTRATION WITil RM-14 AND HP-210 U r u per l$$1$ter 10-6 , ,,,,,jo-5

) 10

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(11ters 7 E). ~

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46 7520 '

)'

ESTIMATE OF PARTICULATE CONCENTRATION WITH RM-14 AND HP-210 -l Approximate Gross Particulate Concentration in pc/mi -

[

a Ip-7 * '

30-6 * *$ * > =

0-5 '

-9

2 * * * * * !!

I 0-10. .{0 , , , ?- *l l! l!!

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ATTACMENT IV {f 1

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. . . a. . . .=:, . :--. .. . :- : ^ ' .- .:-. - - -

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- EPP-003 ATTACHMENT V PAGE 1 0F 8 REVISION 3 POST ACCIDENT RCA ACCESS ROUTES This Attachment provides access routes to specific areas within the Radiation Control Area of the plant. These access routes are the most direct routh starting at the HP. access control area located on the 412' elevtion of the Control Building. The routes described here are to be used as a guide in deterning actual routes to be taken under energency conditions.

EPP-011 " Personnel Search and Rescue", requires routes to be planned and approved by the Shift Supervisor and Health Physics prior to entering the Radiation Control Area during energencies. ,

r Existing and expected radiological' conditions will be considered in

detenning the actual routes taken-to ensure that entry team exposures are maintained ALARA.

Whenever access routes beginning on the 412' elevation of the Control

. Building are not-practical,-entries-into affected areas of the plant fom other elevations or outside ground level access points should be considered and utilized if practical.

\

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c, . . _ . . . _ _ _ . . . _ _ . _ . . . _ . _ . . _ ..a _ - __ _ . _ _ . . _ _ _ . _ . , _ _ . _ _. . . -

7 EPP-003 ATTACHMENT V

,, PAGE 2 0F 8

'N -

REVISION 3

. ELEV. AREA ROOM' ' ROUTE 4

l'

~

374' A - RHR/ Spray Pump Rms. & Cooling Units 74-16&l7 388' B ~ Charging /S.I. Pump Rus. 88-23&24 3 to A/8 to B&C C - Charging /S.I. Pump "C" Auxiliaries 88-13NE 7 Local Control Panel-D - S.F. Pit Hx.88-13N 9

^

412' F - S.F. Pit' Cooling Punpa & Local 12-18 6 Control Panels t-G - Eng. Safety -Feature Motor Control 12-28 4 Center .

H - Waste Processing . System Control Panel 12-15 5

.400' I -' Charging /S.I. Pump Cooling Units 00-02 10 Eng. Safety Feature Substation Bus 63-01 14 463' J and Motor Control Center

)

K-H2 Recomb. Control & Power Supply 63 13 Panels.

L-H2. Recomb. Control & Power Supply ~63-09 11 Panels , .

('"")

2" s** is!";";r"" *

"'-""*"" * "- 63-H 7

' M2- Reactor ' Bldg. Atmos. Sample Collect- 63-17 13 Pt.'& H 2; Gas Analyzer N - TSC '

O - Control . Room ,

412' P - Sample Room 15

'(CB),

Q - Radio Ch em . Ro om . 15

.R - Count Room 15 S - Nuclear Blowdown '14A 436' (AB) 14A T - Pressurizer Heater Controls _ ,

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.A SOUTH CAROLINA ELECTRIC AND GAS COMPANY s

VIRGIL C. SUMMER NUCLEAR STATION NUCLEAR OPERATIONS .

. NJC3R OPMATONS.

C0PY No............. b 1 .

d EMERGENCY" PLAN PROCEDURE

[TPdO4 4 g.

OUT-OF-PLANT RADIOLOGICAL SURVEYING REVISION 4 MAY 17,1983 NON-SAFETY RELATED (s._.- )

\

Reviewed by:

I!/7!93

' Da1f e -

ORIG (INATOR (5I this revision) fd CLlb./

DISCIP.LINE SUPERVISOR Sft7/83

' Date i

l Approved:

PLANT MANAGER

/)n$ . W N 21

'D at e l ppy '2 ; 190'3

Date Issued

f I

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. . . a -- - -. .. _ . . _ _ _ _ _ , __ , _

..o EPP-004

'. .PAGE i-REVISION 4 5/17/83 r .-

S LIST dP EFFECTIVE PAGES' PAGE- REVISION

-i. 4 i' -

11- 4 1 4 2 4 3 .

4 .

. e. .

.4 4

I .

- ATTACHMENTS Attachment I 4

. Attachment II 4 Attachment III 4

,4 ' - Attachment IV 4

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E'PP-004 PAGE 11 REVISION 4 5/17/83 G ' ' " ~

TABLE OF CONTENTS List of Effective Pages i 1.0 PURPOSE 1

2.0 REFERENCES

1 30 CONDITIONS AND PREREQUISITES 1 4.0 PROCEDURES 2

.s. .

c,.. . . .. , i: ATTACHMENTS

~

Survey Record Attachment I -

Attachment II - Approximation of Air Sample Iodine and Particulate- Concentration with RM-14 and HP-210 Attachment III - Iodine Graph Attachment IV - Particulate Graph

~1

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9 4

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EPP-004

, REVISION 4 5/17/83

, p. 1.0 PURPOSE 1.1 To ' provide guidance for ' the direction and implementation of radiological surveys outside the plant in the event of an emergency. ,

2.0 REFERENCES

2.1 " Virgil C. Summer Nuclear -Station Radiation Emergency Plan. "

2.2 EPP-005, "Offsite Dose _ Calculations"'

23 HPP-302, " Radiation and Contamination Survey Tachniques" 24 HPP-303, " Airborne Activity Sampling Techniques and Procedures".

~

25 EPP-007, " Environmental Tionitoring" .

30 CONDITIONS AND PREREQUISITES 31 Out-of-Plant survey activities will initially be directed from the TSC. When practical, direction of areas outside a 1 mile radius will be transferred from the plant, to the EO F . - The EOF is responsible for ensuring the TSC/

Out-of-plant -Monitoring Director is continuously informed of monitoring results from outside the 1 mile radius.

The Out-of-Plant Monitoring Director should proceed to the'

~

32 TSC immediately after; notification, or upon protected area evacuation.

33 Out-of-Plant monitoring personnel should be trained on meteorological effects on plume dispersion and projected exposures to the public.

l 34 Coordinate ^with TSC/EOP to determine travel routes which minimize plume exposure.

fC

'4 35 Minimize exposure yhile taking surveys, (e.g., to min. air

[ samples). Coordinate surveys'with TSC/ EOF to prevent unnecessary exposure.

i l

PAGE 1 0F 4 a---- .. . - - . w,.e.w.-.. , . . . ...w.. g. .y -wg , y, . . + - -

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EPP-004

, REVISION 4 5/17/83 rN 3.6 As time / conditions permit, surveyors should initiate spot radiation and/or contamination surveys, to expedite data collection; (e.g., if in the parking lot, conditions may allow surveyor to monitor vehicles in . immediate area) . .

37 AgZe- iodine filter cartridges should be used for air sampling when noble gas concentrations are suspected.

38 Smears of horizontal surfaces should be taken (ie; -

automobiles; equipment etc.) to provide data on environmental-conditions.

39 Limit the use of protective clothing, as radiological conditions warrant, to minimize public concern.

3 10 Retain all samples and sample data. for re-evaluation.

3 11 ' Monitoring results shall be maintained by the TSC and EOF.

All monitoring results from outside the 1 mile radius should be maintained by the EOF and stored with environmental program data for subsequent report preparation. Monitoring results within the 1 mile radius should be maintained by the TSC and stored with plant records. ,

3 11.1. All survey and sample results obtained from outside the 1 mile radius will be documented and maintained by the EOF. This is the central location for sample / survey results outside of the 1 mile radius.

3 11.2 ' All surveys and samples obtained within the 1 mile

~

radius will be documented and maintained by the TSC.

NOTE: All samples will be retained for laboratory analysis

. and stored at the locations specified above for possible future analysis and evaluation. Do not dispose of any samples without approval of the Radiological Assessment Supervisor.

40 PROCEDURE 41 Oit-of-Plant Monitoring Director (guidelines) 4.1.1 Dispatch out-of-plant survey teams as needed. .

l 4.1. 2 Establish and maintain communications with Out-of-Plant surveyors and EOF when activated.

i

?

I 1 PACE 2 0F 4 l

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. 2. 2 :.:.

EPP-004 REVISION 4 5/17/83

(~ 4.1 3 , F,requently monitor meteorological and effluent conditions, keeping surveyors updated so that routes can be chosen to. keep surveyors' exposures ALARA. ,

. 4.1.4 Identify sampling locations and routes, using priorities listed below as guidelines: ,

~

4141 Residential areas within projected plume.

4.1.4.2 Centerline . plume concentrations.

4.1.4 3 Identify plume edges.

4.1.5 Maintain current status of out-of-plant maps in TSC.

4 1.6 Maintain dialogue with.the In-Plant Monitoring Director to coordinate post accident efforts.

4.1.7 Determine the-need for further environmental sampling (e.g., grass, water and soil).

4 1.8 Transfer control of survey effort (outside'one mile exclusion. area) to EOF when practical. .

NOTE: TSC will continue to maintain overall control of out-of-plant monitoring, within the 1-mile exclusion area. s

\

42 Out-of-Plant Surveyors -

4 2.1 Obtain emergency kits from Service Building Annex and radios from Health Physics Lab or TSC. Check seals-and inspection on Emergency Kits.

NOTE: If seals' are broken or inspection date is not current on emergency kits, perform a quick. check to ensure emergency kits are adequate for field use.

4 2.2 Check instruments in kit with the source supplied for response to radiation.

T 423 Obtain vehicle from Security or the E.D. for off-site transportation.

4.2.4 If not already wearing personal dosimetry, don TLD and self-reading dosimeter contained in emergency 4

kit. Place control TLD's in shielded container. [

8 PAGE 3 0F 4

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.;~. ~-.; .-

v- . . - - .

,.-. .. ,. 7 EPP-004 REVISION 4 5/17/83 f7; 425 Establish communication with TSC and/or EOF.

~

If

.- radios are not operable, use the nearest telephone

'for communication.

~

4.2.6- Obtain current pertinent data from TSC/E0F (estimated release rates of: particulate, iodine and noble-gases; wind- direction; projected plume area; etc.)

4 2 7 . Perform surveys, as directed from TSC/ EOF, per References 2 3, 2.4, and/or 2.5. ' Ensure instruments are source checked for response' after each use.' -

NOTE: .TSC/ EOF and.. surveyors should collaborate to determine appropriate : post accident--efforts -(e.g. , type .

sampling, sample locations, etc.) to ensure maximum data obtained with a minimum of manpower /manRem

expended.

4 2.8 Analyze samples in accordance with applicable HPP's using available equipment. . Approximate air sample iodine and particulate concentration :in accordance with Attachment II.

14.2.9 Record sample and' survey data'on Attachment I.

NOTE: Ensure that smear results 'and locatiogs of contamination levels > 1000 dpm/100cm are recorded-

.in Attachment I. \

4.2.10 Contain, label and retain samplea for' subsequent analysis in the laboratory.

4.2.11 Collect and replace TLD's and particulate and iodine-filters at Environmental Stations when requested by the TSC/ EOF as per Reference -2 5

! NOTE: Take precautions to minimize exposure to environmental TLD's during transportation either to or from sampling station.

r .

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PAGE 4 0F 4 l

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2PP-004 i- ATTACHMENT I

> PAGE 2 0F 2 -

REVISION 4'

\ .. SURVEY- INSTRUMENT INFORMATION INSTRUMENT NUMBER 1 INSTRUMENT .VUMBER 2

' INST. TYPE INST. TYPE SERIAL NUMBER SERIAL NUMBER CALIB. DATE CALIB.-DATE SOURCE-CHECK SOURCE CHECK (INIT) (INIT)

EFFICIENCY (IF REQUIRED) -EFFICIENCY (IF REQUIRED)

INSTRUMENT NUMBER 3 INSTRUMENT NUMBER 4 INST. TYPE' INST. TYPE '

SERIAL NUMBER SERIAL NUMBER CALIB. DATE CALIB. DATE SOURCE CHECK SOURCE CHECK (INIT) .(INIT)

EFFICIENCY (IF REQUIRED) EFFICIENCY (IF REQUIRED)

NOTES: 1. Instrument number. on front sheet should- be 1 thru 4 from above information.

\

REMARKS:

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._ y EPP-004 ATTACHMENT II

.PAGE 1 0F 1 7'S REVISION 4 l T-'

APPROXIMATION OF AIR SAMPLE IODINE AND PARTICULATE CONCENTRATIONS

' WITE RM-14 L AND EP-210 Instructions !

s-

~

- 1. Obtain contact reading (not 1".) on front of iodine . filter cartridge once it is placed in poly bad. Particulate filters cannot be placed in poly bag until after a count rate is obtained.

2. Determine vo.lume of air sampled in liters'or ft3 as indicated on instrument. ,

3 Use graph (Attachment III) to ' approximate iodine '

concentration or perform computation at the bottom of.the graph. : Recommended allowable background is < 100 cpm.

4 Use graph ( Attachment IV) to approximate gross particulate concentration or perform computation at the bottom of. the graph. Recommended allowable background is < 100 cpm.

~

Bases

1. Recommended allowable background is 100 cpm. Attachment III .

is derived :using .37% detection efficiency with an I-131 standard and a 90% filter collection efficiency. ,

2. Attachment III .does" not compensate for noble gas interference. This method is limited for counting AgZe filters or charcoal filters used in the absence of noble gas atmospheres. i 3 Attachment IV is derived using 10% detection efficiency and a l 99% filter collection efficiency. ;

4 Calculations at the bottom.of Attachments III and IV are based on the constants stated above in s'teps 1.and 4 The only variables are the actual volumeu of the samples.

a.)- To determine volume in cu.ft., multiply run-time in minutes by flow rate in cu.ft. (20cfm x 10 min = 200 cu.

ft).

g b.) To determine volume in liters, multiply run-time in

. minutes by flow rate in liters per minute L

(20 1/ min x 10 min.= 200 liters) .

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. s v.

t, SOUTH CAROLINA ELECTRIC AND GAS COMPANY VIRGIL C. SUMMER NUCLEAR STATION .

NUCLEAR OPERATIONS NUC1hR OPERATIONS COPY 1,'o.. . . . . . .

, . . .... .l.5 'f. . a .

EMERGENCY PLAN PROCEDURE EPP-005 0FFSITE DOSE CALCULATIONS REVISION 4 APRIL 28,1983

\

NON-SAFETY RELATED is Am .</f L3 ORIGENATOR.Tbf this revision) ' Date ,

V.A dA2 DISCIPLINE SUPERVISOR

$/n Date i

Approved:

d PLAN'] MANAGER

.flklQ DEte MAY 2 51983 Date Is' sued:

.a

- . ~ ~ . - . ~ . - -

e. -.-

_;__~._ _---~~

- ' ~

.n._ ~:,.-...m,. . ;" 'e=.>'-- --

'7

. .~~u-- ~a . . . . .~ s... . .n.

- - EPP-005 PAGE 1 REVISION 4

/ 4/28/83 LIST OF EFFECTIVE PAGES P, age, Revision 4

1 4 11 4

.111: 4 1

4 2 4 3 4

-4 4

.5 4 -

~6 4 7 4 e

ATTACHMENTS I .

. 4 II, Pages 1 and 2 4 III, Pages 1 and 2 4 IV 4 V 4 VI 4-VII \ '

4

' 4 VIII IX 4 X

4 XI 4 XII- 4 XIII, Pages 1 through 3 4 XIV- 4 XV ~4 XVI 4 XVII '4

. 'XVIII, Pages~1 through 4' 4 L

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. EPP-005

. Page.11 Revision 4 4/28/83-m TABLE OF' CONTENTS 1 ,' ~

P_a_ge, List of: Effective Pages- i .

~ '

- Flow Chart iii 1.0 PURPOSE 1 i

2.0 ' REFERENCES -.

30 ' CONDITIONS AND PREREQUISITES 2 -

4.0 PROCEDURE 2 50 BASES 5 .

ATTACHMENTS

~

ATTACHMENT I- - Sample form: Meteorology and Source Term Report Form ATTACHMENT =II - Sample Form: Emergency Off-Site' Dose Calculation Using Stack Monitor Source Term .

- ATTACHMENT III- Sample Form: .0ff-Site Dose Calculation Using High-Range Monitors ATTACHMENT IV - Sample Formi Activity Release Status

- ATTACHMENT V - Sample Form: Out of Plant-Monitoring-Dispatch & Data Form:

ATTACHMENT VI - Sample Form: Dose Off-Site (Dose Rate)

Calculation from Environmental Monitoring ATTACHMENT VII -Dose-Concentration Conversion ATTACHMENT VIII-Delta T Atmospheric Stability Classification i

ATTACHMENT II - Sigma Theta Atmospheric Stability '

Classification-

. ATTACHMENT I - Meterological Sector Definition ATTACHMENT II - Correction Factor for High Range Monitors ATTACHMENT III -Protective Action Guides (PAGS).

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EPP-005

-l . Paga 11 Revision 4

-(, b' ~ !

4/28/83 e - .

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TABLE OF CONTENTS (cont) 3 '/.i' List of Effective Pages ,

ATTCHMENT XIII- Pa' squill-Turner Method for Deter' mining Atmospheric Stability.

.'t-r ATTACHMENT XIV ' Volume-Pressure Steam Curve I[c,>

s.

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3-

. .' f. , , I ATTACHMENT XV - Containment Leakage Source Term -

T ATTACHMENT XVI- Calibration Constant (pre HPP-906 implementation)

/ / ' J ATTACHMENT XVII - Calibration Constant (post HPP-906 ,

J.- ! implementation). .

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ATTACHMENT XVIII - Projected Whole Body and Thyroid Exposure Rate at 1 Mile r.

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EPP-005 REVISION 4 p 4/28/83

, , . 1.0 PURPOSE l 1.1 To provide methods for estimating wholebody and child thyroid dose rates due to abnormal released of radioactive materials to the environment.

1.2 To prov[de a method of c.omparing the int grated wholebody and child thyroid doses to the EPA Protective Action !

Guides' -(PAG 's ) .

2.0~ REFERENCES 2.1 " Virgil C. Summer Nuclear Station Radiation Emergency l Plan".

2.2 American Society of Mhc'hasical Engineers, " Recommended Guide for the Prediction of the Dispersion of Airborne Effluents", May 1968.

2.3 Dames and Moore, " Data Reduction Procedure for Virgil C.

Summer Nuclear Station", September 1974.

2.4 (ed.), " Meteorology and Atomic Energy -

Slade, 1968", TID-2 D. H.4190, Division of Technical Information, USAEC (1968).

. i 25 Turner, D. B. , " A Diffusion Model for an Urban Area",

Journal of Applied Meteorology, February 1964.

2.6 U. S. Nuclear Regulatory Commission, Proposed Revisicn 1 to Pegulatory Guide 1.23, " Meteorological Programs in l

Support of Nuclear Power Plants", September 1980.

2.7 NUREG-0654/PEMA-REP-1, " Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and j

f Preparedness in Support of Nuclear Power Plants", December 1980.

2.8 Emergency Assessment and Response Systems, (EARS 1,000 and EARS 9845). Technical Manual. Applied Physics y Technology, Inc.

29 EPA-520/1-75-001 (Revised June 1980) " Manual of Protective Action Guides and protective actions for Nuclear Plants." ,

2.10 EPP-002 Communication and Notification.

1 A

PAGE 1 0F 7 6

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EPP-005 REVISION 4

/' 4/28/83

, 2.11 Virgil C. Summer Nuclear Station Final Safety Analysis Report, Chapter 15,. Sections 15 3 and 15.4.

o- 2.12 EPP-906 Preplanned Alternate Method for Monitoring Post Accident Parameters as required by Technical g Specifications . ..

30 CONDITIONS AND PREREQUISITES 31 None d

' 4.0 PROCEDURE -

NOTE [CL,This procedure delineates two (2) methods by which offsite doses may be calculated (i.e. , computer calculation and manual calculation). Either method, or a combination of both methods, may be used since comparable results can be obtained.

4'.1 Overlay Selection 4.1.1 If the computer is not available proceed to step 4.2 to initiate manual calculations.

\

4.1.2 Use the HP9845C in the Technical Support Center to run the menu driven real-time dose projection system. The program is started by following guidance derived through Reference 2.8.

4.1.3 Complete step 4 3 so that the manual method map is available for use in case of computer failure. The map is also useful in dispatching out of plint monitoring teams. Proceed to step 4.5 4.2 Manual Method 4.2.1 Stability Class Determination i

If the meteorological tower is inoperable proceed to step 4.2.2 otherwise, complete Part 1 of Attachment I to obtain meteorology and source term data from control room instrumentation. Method A.

(below) is preferred.

PAGE 2 0F 7

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EPP-005 REVISION 4 4/28/83

. ( m.

A. Differential Temperature ( a T) 61-10 meters and !

40-10 meters Method.

l. Obtain A T information from the Control

< Room instrumentation.

NOTE: Priority should be given to the 61-10 meter

> > information with the back -up being the 40-10 meters, i

2. If the Control-Room instrumentation is e inoperable, personnel with a portable radio may be dispatched'to the met'eorological

'- tower to obtain AT information directly -

from the met tower instrumentation. Keys E7 ." 3. 9 to towers are available in the Emergency e . Planning Key Box-located in the Emergency Operations Area of the T.S.C.

3. Determine the Pasquill Category.by using Attachment VIII and. select e.ppropriate X/Q overlay found near .the plotting map.

4. Proceed to Step 4.3 for determination of plume location and X/Q values. g -

i j

B. Sigma Theta Method r .

1. Review the wind direction chart located in Control Room and determine wind range for a period of 15 minutes to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

2. Wind range is determined by the difference between the highest and lowest values measured. If the wind direction chart

- shows one or two spikes, these should be

. ,i- ignored in determining the wind range. - If

-more than two spikes, these must be considered in determining wind range.

L 3 If the wind range is larger than 180 degrees, use 180* as the wind range value..

4. Divide the wind range by six (6).

5. Determine the Pa, squill Category by using Attachment IX- and select appropriate

- overlay.

4.2.2 Backup met'eorological data can be obtained from l the National Weather Service (NWS).

3 PAGE 3 0F 7

_ . . . . . , _ . . _ _ . . ._ __. _ _ . - - . m .m

- .. . .. - . ~ - . - . -- - . . .. . .. . . . . . - -. . .

EPP-005 REVISION 4 ;

,,_s 4/28/83 A. If noteorological tower' data is not available call the NWS (see ref. 2.10 for phone number) and obtain windspeed, wind direction, % cloud

. cover and ceiling height. Also, obtain current forecast and note any fronts that may cause a rapid shift in wind speed or direction.

Complete Attachment IIII " Turner's algorithm" to obtain st, ability class.

4 3- Location of the Effluent Plume 431 After determination of appropriate overlay in Section 4 2 place overlay tu the center of the base i map. .

432 Orient the centerline of the overlay along the direction the wind is blowing. -

NOTE: Wind directions are given as directions from which the wind is blowing; affected directions are 180*

from the wind direction. When communicating wind direction, specify the direction from which_the wind is blowing (e.g. wind is blowing from 270*)

433 The conversion from wind direction measured in degrees to wind direction in sectors is presented '

in Attachment I.

44 Manual Dose Calculation 4 .'4 .1 Complete Part 2 of Attachment I.

A. To perform a quick estimate of the projected offsite radiation exposure, complete Attachment XVIII as per the instructions on the back of the form.

4 4.2 Complete Attachment II if radiation monitor RM-A3 (Gas) or RM-A4 (Gas) is on scale. Compare results with the PAGS (Attachment III).

4.4 3 If RM-A3 (Gas) or RM-A4 (Gas) is offscale or if there is a steam release complete Attachment III..

Compare, results with the PAGS (Attachment III).

NOTE: Attachments VII, II and IIV, will be necessary for completing Attachment III.

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w EPP-005 REVISION 4 4/28/83 4.4.4 Complete Attachment XV if either . radiation ~ monitor RM-07 or .RM-G18 are on scale. Compare results with PAG's (Attachment XII).

4.4.5 If the radiation monitors on the effluent path are offscale or inoperable and HPP-906 has not been implemented, follow the assumptions used in Ref. 2.11

. for estimating effluent release rates. .

4.4.6 complete Attachment IV to maintain curie accountability. Total activity of iodine, noble ga,s, particulates, and tritium must be kept current. (Hourly updates if possible) 4.4.7 Transfer all applicable results to EPP-002 Attachment II for transmittal and documentation purposes.

4.5 Environmental Monitoring 451 As soon as practical, dispatch monitoring teams to '

the affected meteorological sectors. Attachment V, should be used to record location and results.

Dose projections based on source terms should be

() NOTE:

-x verified.as soon as possible by supportive measurements. Based on these measurements, a reassessment of the PAG's shoul'd be taken.

4.5.2 Attachment VI can be used to project doses based on environmental samples. These can then be compared with source term projections.

50 BASES 4- 51 This section is included to provide a brief explanation of the sources of constants and graphs used in the procedures 4 and associated attachments.

A. Step 4 3 1 - Until a full class A model is developed, subsequent to the completion by Dames and Moore.of a detailed study of the Summer Station Meteorology, the (X/Q) overlays will be based on a straight line gaussion plume model as described in Reg. Guide

. 1.145 l.

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-s ,

4/28/83 B. Attachment II,Section I - The Iodine to noble gas I activity ratio of 0 3, until measured, is a conservative estimate from Ref. 2 9 page D-59 WI-2 -

would suggest that the actual ratio ' could be 10-3 I or less. A fast and accurate measurement of the actual ratio is important to avoid unnecessary ,

evacuation orders. based on the Iodine PAGS.

The calibration constants 3 3x10 -10 and 3.8 x 10 -10 are based on the manufacturer's calibration and various unit conversions as follows:

3 3X10-10 =1 min x 106 ml x 10-6 ci i voi/ml EU sec mI d ci 50x100 CPM 3 8X10-10 = 1 min x 106 mg ci X 1 uci/ml m x 10-6

[ EV sec uci 44x100 CPM

c. Attachment III,-Section I - Same comment as B.

The calibration constants 4.0 x 10-5, 9 5 x 10-5 and 8 5 x lo-* are based on the manufacturer's calibration and various conversion as follows:

4.0 X 10-5 = 0.028 m3 x 106 ml X 10-6 -ci x l' min x 1 ci/ml ftS mI y ci E6 see ll.7-mr/hr 95 x 10 0.028 m3 x 106 ml x 10-6 ci x 1 min x 1 ci/ml ft5 m3 yIEI 50 sec 4789 me/hr.

8.5 x 10-4 = 0.028 m3 x 106m1 x 10 .6 ci x 1 hr x 1 ci/ml ft3 " mT- poi 3600 sec 9 13x10-7 mr/b D. Attachment VII - The curves follow the methodol'ogy and assumption of Ref. 2.9 The noble gas curve comes

< from EQ. 2 9, the Iodine curve from EQ. 2.13

. E. Attachment-XIII-This description of the Pasquill-Turner method was supplied by Dames and. Moore. The calculation of-the solar altitude was obtained from the Alabama Power Company Farley Station EDcM. It was verified by comparision with selected values from the Smithsonian Meteorological

. Tables.

G PAGE 6 0F 7

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EPP-005~

REVISION 4 *

. ~m 4/28/83

~

.P. " Attachment III - Protective actions are taken from Ref.

2: .9 The particulate concentration,-7 5 x 10-7 Ci/ml, .

would-lead to an exposure of 2000 MPC Hours in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . That is, it is analogous to a whole body exposure of 5 REM.- Other concentrations are related by ratio to the specified whole body exposure found in.Ref 2 9 G. " Attachment IIV is a plot of standard steam table' data

~for saturated steam.

H. Attachment II is a plot of the ratio of DOSE to concentration for mixed fission noble gas to that for 133 Ie as a function of time after trip.

I. Attachment.IV - the conservative leak rate of 2 56 ft.3/Ain is based on the Tech. Spec. allowable limit (Section 3 6.1.2) of 0.2% by weight of containment air per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months at 47 1 psig ;

which is the. pressure expected with a steam line break.

(1.84E6 ft. 3)x(0.002) x (1 hr.) = 2 56 ft.3/ min.

(24 hrs.) (60 min.)

J. Attachment IVI is a plot of calibration constant versus time

. post-accident for RM-G7 and RM-G18. Data is based on a report

[ by GAI on RM-G7 and PM-G18 calibration. The calibration constants were derived as follows: ,

(i uCi/ml) x (1 hr.) x (1E-6 C1) x (1E6ml) x (0.028_m3)

(Cr ar/hr) (3600 sec) (uC1) (m3) ( Pt . 2 )

=7.78E-6 = calibration constant Cr where CF = conversion factor derived from data-supplied by GAI.

K. Attachment XVII is a plot of calibration constant versus time

. post-accident for a RM-16/RD-17A monitoring system outside the Reactor Building air lock when HPP-906 has been implemented for either RM-G7.or RM-G18. . Data and derivations are as in J' above.

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EPP-00'S

. ATTACHMENT I

., PACE 10F 1 REVISION 4 METEOROLOGY AND SOURCE TERM . ,

REPORT FORM l Windspeed mph (10 meter preferred) Time Direction degrees (10 meter preferred)

Delta T degrees (61-10) or (40-10) (Ch.rcle One,

, 61-10 is preferred)

Stability Class (Use Delta T and Att'achment VIII or Sigma Theta and Attachment.IX or Turners Algorithm and Attachment XIII AT is preferred.

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ____________ _f___________

Part 2: Source Term RMA3 CPM (net) Pfow Rate RM-A4 CPM (net) Time RM-A13 mr/hr RM-A14 mr/hr RM-07 ~ mr/hr RM-018 mr/hr RM-019 mr/hr i

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. ATTACitENT II

,m PAGE 1 0F 2 aEvISim 4 -

I

( -

EMim0ENCY OFILSITE DOSE CAIEULATICN USING STACK MCNITOR SOURCE TIEM Time of Trip Current Time Thae after Trip .

191.-A3 (Gas) BM-A4 (Gas)

Count Rate CIM CPM (A)

Calibration 3.3 x 10-10 3.8 x 10-10 (A1)

Flow rate: CPM x 0.028 = m3/ min. (B)

Balease Rate (A) x (A1) x (B) i

,C_i, s (C)

(C) x 3600 = C1/hr (use in EPP-001)

Wind Speed: MPH x 0.45 =- m/sec (D)

^, (X/Q)u frca isopleth for 1 mile m-2 g (E1)

X/Q: (E1)+-(D) = sec/m3 (F)

Noble gas dose to concentration calversion from Attachnent VII x2= ren/2hr (G)

C1/m3

~

' DOLE BODY DOSE (2 hrs): (F) x (C) x (G) = run' 2 hr. (H)

Iodine to noble gas activity ratio (use (I) 1 0.3 unless measund)

Iodine ' dose to calcentration conversion fran Attachmerit VII rem /2hr

- C1/m3 (J)

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- ATTACitG!NT II n PAGE 2 CP 2 REVISICN 4 DERGENCY OFF-SI'IE DOSE CALCULATION USING STACK ION 1'IOR SOURCE 'IERM Tune of Trip Cur mnt Tune Tire after Trip Iodine'to noble gas dose ratio (I) x (J) + (G) (K)

CHILD 'IHYBOID IDSE: (K) x (H) =

at 1 mile (2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ), rem /2hr.

(X/Q)u at 2 miles *(E2) (E2)/(E1) (L2) 5 miles (E5) (ES)/(E1) (L5) 10 miles (E10 (E10)/(El) (L10)

Projected Integrated Dose in Rem per Unit Time 2 miles (L2) x (H) rem x (K) =

rum 5 miles (L5) x (H) can x (K) = rem rem x (K) = rem 10 miles (L10) x (H) M N ID (2 Hour)

(2 Hour)

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EPP-005

- ATI'ACBENf III e- PAGE 1 0F 2 REVISION 4 OFF-SITE DOSE CAICULATION USING HIGH RANGE lONI'10RS Time of Trip Current Time Time after Trip RM-A13 IM-A14 RM-Gl9 DOSE RAE mr/hr mr/hr mr/hr (A1)

FIDW RAE CFM CPM lb/hr (A2)

MASS /VOL 1 1 ft3/lb (A3)

(fran Att. XIV)

- Calibration 4.0 x 10-5 9.5 x 10-5 8.5 x 10-4 (B1)

Correction Factor flun Attadanent XI (B2)

Release Rate (Al) x (A2) x (A3) x (B1)/(B2) Cl. (C) s

) (C) x 3600 = C1/nr (use in EPP-001) \

Wind Speed: MPH x 0.45 = m/sec (D)

(X/Q)u frcm isopleth for 1 mile nr2 (El)

X/Q: (El)+(D) = sec/m3 (F)

Noble gas dose to concentration ccriversion

- frca Attachnent VII x2= rem /2hr (C)

C1/m3 WOIE BODY DOSE (2 hr.): (F) x (C) x (G) = rem (H) j 2hr l Iodine to noble gas activity ratio (use

l. 0.3 unless measured) (I)

Iodine dose to ccricentration mnversion feca Attachment VII rem /2hr (J) ci/m3

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EPP 005 ATTACHMENI III p~ . PAGE 2 0F 2 REVISION 4

(

OFF-SITE DOSE CAIfULATIN USING HIGH RANGE lONIIDRS Time of Trip . Current Time Time after Trip Iodine to noble gas dose ratio (I) x (J) 4. (G) (K)

CHILD SIYROID DOSE: (K) x (H) =

at 1 mile (2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ) rem /2hr.

(X/Q) Eat 2 miles -(E2) (E2)/(E1) (L2) 5 miles (ES) (ES)/(E1) (L5) 10 miles (E10 (E10)/(E1) (L10)

Projected Integrated Dose in Ren per Unit Time 2 miles (L2) x (H). rem x (K) = rem

( .

5 miles (L5) x (H) can x (K) = rem 10 miles (L10) x (H) rem x (K) = can

-'ERIZ'EDY CHIT'HD30ID (2 Hour) (2 Hour) e.

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EPP-005 ATTACIMENT IV

, PAGE 1 0F 1 REVISION 4-ACTIVIlY RELEdSE STATUS -

Time: '-

~_

Elapsed time since last release calculation sec (A1) hr (A2)

Noble Gas Average release rate since last calculation Ci/sec (B1)***

Activity released since last calculation (Alx B1) C1 (Cl)

Previous total of noble gas released C1 (D1)

Total activity released (C1 + D1) C1 CURRENT DOSE ELAPSED TIME CURRENT OLD IUfAL IUTAL

. DISTANCE RATE (rem /hr) (A2) DOSE DOSE DOSE .

1 mile X = + = rem 2 X = + = ran m 5 x = +- = rem

, 10- X = + \ = ran Iodine Average release rate since last calculation C1/sec (B2)

Activity released since last calculation (Al X B2), C1 (C2)

Previous total of Iodine released C1., (D2)

Total activity released (C2 + D2) C1 CURRENT DOSE ELAPSED TIME CURRENT OLD '1UIAL IUfAL '

DISTANCE RASE (rem /hr) (A2) DOSE DOSE DOSE 1 mile X = + = ren 2 X = + = can

. 5- X = + = rem 10 X = + = rem see B1 x 3600 = C1/hr, Shis figure is to be used for detecnining Bnergency Action Levels in EPP-001 Attachment I.

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4 DISPA'IG AND DATA Film Diiifiat'ch Unit Time Location Miles De6rees Comnents:

Report p,

\

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I4 cation Confirmation YES/NO Time Rad Imel R per hour (A)

Air Sanple Voltime cubic ft. x 28320 = an3 Particulate net epn _

y C1/cm3 (B)

~

Particulate Concentratial =

Iodine ,

net cpn(c)

) Iodine Concentration = VC1/an3 (C)

Iodine dose to ocncentration conversion renV2hr fran Attachment VII uC1/m3 (D) 2 hr. child thyroid dose (C) x (D) rem (E) 2hr NOIE: Coupare (A), (B), and (E) to PAGS (Attachment XII) 9

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f m PAGE 1 0F 1 REVISIOi 4 OFF-SI'IE 1)OSE CAIEULATION .

Pf0M ENVIBOOG!NTAL lONI'IORING

~~

Rad level

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Sample Time Check One:

Location Iodine 4

Measured Dose Rate rem / hour (A)

X/QE at location fran isopleth (B)

.i - .

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( A) +- (B) = (C)

(X/Q)E from isopleth at 1 mile (D1) 2 miles (D2) 5 miles (DS) 10 miles (D10) 1 Does Rate' at 1 mile = (C) x (D1) =

j 2 miles = (C) x (D2) = rem / hour l 5 miles = (C) x (D5) = -

10 miles = (C) x (D10) =

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- Real M na EPP-005 Dose-concentration convereton

, rem /iw Attachment VII 8 roen 2 hr

.! st /m3 Page 1 of 1 -

. , ,g f,3 Revision 4 -

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g. . . .

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7.__ e EPP-005 ATIACHMENE VIII PAGE 1 of 1

<. BEVISIGl 4

.A'INOSPHEBIC STABILITY CLASSIFICATION .

Tancerature Differential (a T) 6 Stability Pa= H 11 iin'F Classificattat -Categories 61-10 m l,*40-10m ;

Extranaly Unstable A 1-175 1-1.03 Moderately Unstable B -1.74 to -1.56 -1.02 to.-0 9,2 Slightly Unstable C -1.55 to -1.38 -0 91 to -0.81 Neutral D -1 37 to -0.46 -0.80 to -0.27 -

Slightly Stable E -0.45 to 1 37 -0.26 to 0.80 Moderately Stable F 138 to 3.67 0.81 to 2.16 Exteenely Stable 0 >3.67 >2.16 e

?,

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e o

e L .

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+.

O e

e g$6 ..A. . ee w es , % .eu. w % ,e -%, *.4- w w e- .=aww --=*ee-*e e a ame 9,

...:.... n.- . . .: _._. , _ . . . ,,_ . . . L , . _ n. _, , . :- , _ .

. . . . . .?.7_

EPP-005 A'ITAC}M!NP IX l 7 '- PA(E 1 of 1

- REVISICH 4

. A'DOSPHERIC STABILITY' CLASSIFICATION

. c.

. Sisma Theta.'-(ae )

Stability Pasquill l.g. (degrees)* t Classification Categories Extranely Unstable A >22.4 Moderately thstable B 22"4 to 17.5 Slightly Unstable C 17 4 to 12 5

=

t Neutral D' 12.4 to 7.5 Slightly Stable E 7.4 to 3.8 Moderately Stable P 3 7 to 2.1 Extranely Stable G <2.1 s

Standard deviation of horizontal wind direction flu'ctuation over a ~

period of 15 mirmtes to 1 bour. (Wind Range divided by.6) =

Ref. USNBC Reg. Guide 1.23, Rev.1, Sept.19do.

(

f

)

.-[ [^

,..h'

- - - - e'* *% e =.,e me, .eup e %4 . g , , _ , , ., , ,

. .- h w w .-. . _ . . . - . , _ ,

.. . . . - -. a ~ ,. .- , . . - . . . . . . , - - . . - . . . . . -

3,; ,

- - ~ -. - .

EPP-005 ATTACHMDff X PAGE 1 of 1

,G REVISION 4 g MEIDibHXIXIICAL SEC'IOR DEFINITION ,

ww Central-Direction if Value Limits of Sector Sector :- (degrees) t in Degrees NNE.

22.5 11.25 < 1 33.75 NE 45 0 33 75 < 1 56.25 ENE 67 5 56.25 < 1 78.75

' 90.0 78.75 < 1 101.25 E

ESE 112.5 101.25 < 1123.75 SE 135.0 123 75 < 1 146.25 SSE 157.5 146.25 < 1168.75

-S 180.0 168.75 < 1 191.25 SSW 202.5 191.25 < 1 213.75 SW 225.0 213 75 < 1236.25 .

Wsw 247 5 236.'25 < 1 258.75

~

W 270.0 258.75 < 1281.25 WNW 292.5 281.25 < 1303 75 f NW 315.0 303 75 < 1326.25

('

t NNW 337 5 326.25 < 1 348 75

! N 360.0 348 75 < 1 11.25 CAIM Wind speed less than >

0.75 uph MISSING Unrelinhle data l

l-l

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. ATTAQ MENP XII . .

PAGE 1 of 1 4

REVISION 4 ,

j.

i RE00 MENDED PROIECTIVE ACTIO4S TO RE00CE W10MBODY AND SEYHDID DOSE FIEN EXPOSIRE TO A GASEDUS PIADE Projected Dose (Rem) to (a) ;

! the Population Rectanended Actions Consnents i-

'+

! (b) b Wholebody <1 No planned protective actions. Previously reconsnended proteo- t h Thyroid <5 State may issue an advisory to seek shelter tive actions may be reconsiderec h Particulate <l.5x10-7 and await further instruction. or tenninated.

i- 01/ml Monitor environmental radiation levels.

f Wholebody 1 to < 5 Seek shelter as a mininnan. If constraints exist, special i Thyroid 5 to < 25 Consider evacuation. Evacuate unless consideration should be given

Particulate 15 to <7.5m constraints make it impractical. for evacuation of diildren and -

I i 10-7 901 Monitor environmental radiation levels pregnant women.

ml Control access.

1 Wholebody 5 and above Corxhict mandatory evacuation. Seeking shelter would be an '

Thyroid 25 and above Monitor environmental radiation levels and alternative if evacuation were j i Particulate 7 5x10-7 adjust area for mandatory evacuation based not immediately possible t

901 and above on these levels.

P ml Control access. . ,

j1 Projected Dose (Rem) to Bnergency Team Workers ji Wholebody 25 Control exposure of emergency team members Although mapirators and stable !L

!l to these levels except for lifesaving lodine should be used where !

] missions. (Appropriate controls for emer- effective to control' dose to , f

- gency workers, include time limitations, emergency team workers, thyroid i respirators and stable iodine.)

[ Wholebody 100 Control exposure of emergency team members dose may not be a limiting factor for lifesaving missions.

P i perfonning lifesavirs missions to this level. (Control of time of exposum will ,

3 be most effective.) F (a) These actions are reconsnended for planning purposes. Protective action decisions at the time of [

the incident naist take existing conditions into consideration. ! !

4 ,

I' (b) At the time of the incident, offici'als may implement low-impact protective actions in keeping with * !

3:

the principle of maintaining radiation exposures as low na reasonably adlievable. .

M .

i' ~

i t

i il.

a:i: _ _ _ _ _ _ _ _ _ _ _ _

.. . . . . ; -.. . .; _. . . . .. = :: ~ . :L. - _ L, ~ ~ . 7 ~ ~ ^ ^

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. EPP-005 -

ATTACHMENT XIII t n . ."PAGE 1 0F 3 REVISION 4 f~~~

~ ~

The Pasouill-Turner Method for Determining

Atmospheric Stability 1

If both the primary and secondary T-sensors are inoperative and signa theta is not available, the Pasquill-Turner method for

-defining Pasquill stability classes may be used. ' Before using this method, , contact -should be made with :the NWS. - This method is based on the principle that stability. near the ground is dependent primarily upon net radiation and wind speed. .

Determinati< ' of stability class as a function of wind speed and t net radiati,a is given in Table 1. In.this sytem, insolation is estimated by solar altitude and. modified for . existing ' conditions of total cloud cover and cloud ceiling height. At ni$ht estimates of outgoing radiation.are made by considering cloud

cover. The net radiation index is determined as follows:

1) If the total cloud cover is 10/10 and the ceiling is less .

than 7000 feet,. use net radiation index equal to O (whether -

day or night).

2) For nighttime (defined as the period from one hour before sunset to one hour after sunrise):

a) If total cloud cover < 4/10,- use net radiation index equal to ~2..

\

b) -If total cloud cover > 4/10, use net radiation index equal to -1. .

3) For daytime:

a) Determine .the insolation class number as a function of solar altitude from Table 2. .

. b) If cloud cover 15/10, use the net radiation index corresponding to the insolation class number. ;

c) If cloud cover > 5/10, modify the-insolation class number by the following steps: ,

. 1) If ceiling < 7000 feet, subtract 2

11) If ceiling 2,7000 feet, but <16,000 feet, subtract 1

111) If total cloud cover is 10/10 and ceiling is 2, 7000 ,

f eet , subtract 1 - (compare to 1 above) ,

w-J s +

SS ge 9

m s U+' "v..4 e. eA Y ' .- , , & f^p.

.' , , ; L 'Q K ':*" 'Y , _, _ *y - - ,~;,

^^ *

. , _ . - - - : . - _ . . _ , . _ . . _ _ _ _ _ . - _., n . . . . . . _ . _ _ . .

.. - . . . .. J. .

. EPP-005 ATTACHMENT XIII

~m PAGE 2 OF 3 4 REVISION 4 The Pasauill-Turner Method for Determining Atmospheric Stability iv) If total cloud cover is not 10/10 and ceiling is > ,

16,000, assume ' modified class number equal to insolation class number v)' It' modified insolation class number-is less than 1, let it equal 1 vi) Use the net radiation index. corresponding to the-

' modified insolation class number i Thus, it can be seen from Table 1 that instability occurs with high positive. net radiation and low wind speeds, stability with i negative net radiation and light winds, and neutral conditions with cloudy skies or high wind speeds. .

Calculation of Solar Altitude a = arcsin [ain osin$ + cos

((T H-12) 180') cos cos ]

where = station latitude = 34 3'

\

' H = hour of day. (24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months clock) 8 = arctan [ - tan (23 5*) cos (360* (N+10)]

365 where N _= number of days from the beginning of the year l

~W

, , . _ . + . _ . - =+ .w. e6,. . ..%

. . . . , _ _ . . _ . . . . , .,_ , _ . , . , , , . ,,,...,3 -

+w,

, . _, .,- m ,

.- . . . . . . _ . _ . . . . ..~._ ~ _ r, _ n . .m _ J.

. EPP-005 ATTACHMENT XIII

.-- ."'- PAGE 3 0F 3 REVISION 4 TABLE 1 ,

STABILITY CLASS AS A FUNCTION OP

NET RADIATION AND WIND SPEED Wind Speed

Net Radiation Index (MPH) (knots) 4 3 2 1 0 -1 -2 0, 1.15 0, 1 . A A B C D F G 2, 3 45 2, 3 A B B C D F. G 4.6, 5 75 4, 5 A B C D D E F 6.9 6 B B. C D D E F 8.05 7 B* B C D D D E 9.2, 10 35 8, 9 B C C D D D E 11.5 10 C C D D D D E 12.65 11 C C D D D D D

\

113.8 > 12 C D D D D D D

Table 1 was developed for wind speed in knots. To convert from knots 3

to meters per second, multiply roughly by .5, accurately by .51444.

TABLE 2 INSOLATION AS A FUNCTION OF SOLAR ALTITUDE

- Insolation 1

Solar Altitude (a) Insolation Class Number 60* < a Strong 4 35* < a 3,60a Moderate 3 15' < a f 35 S11sht 2

'~

a-5,15' Weak 1 s

- See Page 2 of this attachment. l

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. Attachment XV

. '. . Page'1 of 1

Revision 4 if

. :. t OFF3ITE DOSE CALCULATION USING CONTAINMENT LEAKAGE SOURCE TERM i

Time of trip:

Current time: Time after trip RM-G7 ,

RM-G18 Dose Rates ar/hr ar/hr (A1)

\

Flow Rate: 2.56 CFM 2.56 CFM -(A2)

Calibration: (from Attachment XVI or, if HPP-906 has been (B1) initiated, then Attachment XVII)

Release Rate (Al) x (A2) x (B1) = Ci/Sec - (C)

(Continue calculations following release rate derfvation in Attachment III) e e

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f. $. 6 ..

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_--- : y_ gg - -- =g- _ - 3_____3_----__.a.__-g

- - - - - __- -_ - - - -- . ._ 3 --_-. R st e. me 6.- , - ;;= >E u se a i e de V.6 - tu .g tw 4.== 4 - d.. s . J an . 25 l l . 3; , , i - 3., > > IA.I l l . . l I aman I r, . . . . . . . . , g g . . . . . , . . e 6 i .j i e i . e e i . i . . p .# . e . t . , e t . . . . . .

2. ! I K. ,2 f1 AI '

4 a . I,l . l 1E-8h i * ' O 10 . 50 100 TIME POST ACCIDENT (hrs) ....m. _, y + . . *. = * --.-%v. ,%e.=sim.,= - *~*ew ** - - - * * *- N ..- _ . _ . .. _-_ ._ _.._ _-. _ _ _ _ . - _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ ~ _ _ _ _ _ _ _ . . . _ _ _ _ _ _ _ . . . _ . . . _ _ . . - _ _ p . - - s . 3 REL aSE RATE A* pCi b "RdM/HR PROJECTED WHOLE BOI.n EXPOSURE . [ i.- . 3 RATE JNOBLE GAS? AT I MILE NOIBLE GAS RELEASE CFM 1Ig [, - - PREPARED BY: . CONCENTRATION 10 . - ~ i- - - DATE/ Tine : 4~ 4 REVIEWED BY:

Ci/Sec a. - .s i

'6' - -3 r ** . . TIME AFTER t 5Amn.Ed -3 10-- ac + 5 - 16 4- - SHUTDOWN De gg[ Mgg ., a- ~ ~2 -4 - .10 GENERAL C 10 2 .- q - HRS 10 10 - - - ~ EMERGENCY . -4 -sp s: - .g g, 3 - - ,.i _ ,, - - WIND 10 i ;

:' g M SITE ir>ENRGENCY z win. 2 SPEED syAgat Ty X - - - -

1 -3 - - 3,, .p Q- MPH = = -2 10 -- - . . site 4_ _ -10 . . -1 EuERGENCY (61-lOm) -2 - - -l 2 - 10 ir > so usu.

g 6 G s.6T 10 -

- s.l 10 - - / YvlND 1 ir > .in n. ~ ~ IO ,

I l

F- -i.se To 34T -3 -

10

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lb -2 E -o.45To s3T -4 - l 5 $M irNsE ~ C -10 to - - ~ 30 2- - . g+rs TE EuEns.

i. D -i.sr To-o44 . .

! ' - - - - i2 - -

-5 4- - - -

30 "'" '

J; . . . . ,4 -iss 10 ' ra lo . . - ., -- , A_.=. g 1 i -5 -3 C ' 20-4

g-6 .' - - - -

j :l g- - -10 e6 - - 4o-go y, _ _

-' - . - is s -

. . EuERGENCY 20 -T I l 8b I ~ ~

- - B -i T4 To-i 56 10 8

. -00 - -

~

as ElO - - ~

-4 -8 ! l 30

, -6

:-10 so - - 10--?

rawonasi.E B . . ,s

j 10 _

- - e A s-i.Ts uETEonot.oGv - .. s I; - - k 40 !W 6- - -5 Q h . . c5 -7 - - 3 h 4 go 2- - ,4 10 .,g-- 10 - - . . -2 2 . EPP-005 -- 80-6 I: ATTACHMENT XVIII - -4 ~ .3x105 ,j: l' PAGE 1 OF 4 - -6 - )f j REVISION 4 g,- -e , iI ; 3 . . . ... .~ ... _ _ . :. . . r AT I is E: I s ihal REM /2HR REL6ASE RATE. PROJECTp gy DOSE RATE @j ~~ CFM i - - :- g5 PREPARED BY : IODINE RELEASE - go i ' ] - , DATE/ TIME : CONCENTRATION - l REVIEWED BY I ' . Ci/Seo 2- - - -5 2 jeCIAnt l t, lo ~ : - -10 - r -s " - 10

GENERAL TIME AFTER EMERGENCY SHUTDOWN

[L Qgg -7 10 - - 2- !i l: :g }. ,H -6 _io _~ HRS. 2). N./ tt, - -, {- ;-10 - io - - : : , n = =- - -4

l

,,uo ge- -. .e n.gr .- - o

-i: sire c.c.o.

1- - - - w > 3o inn. v SPEED ' I' I -T go _ - s 95 - - STABILITY at. *p $ MPH

: -6

- - - - - "I - - i - -g 4o - - (61-lOsn) - -go -E - - 3o - e > 347 10 -- s l-g - - - E.g6 d - - is y 63 3o347 -3 .2 - .4 - l 10 - -8 i - ' i.o - .g.: - - -- uim => - . . 3, 10 -2 . E -o.4s io n.n -4 :. l - - eveur i-

-10 , go - - - -

i D -i.37 io-o.44 2- - - - g 4 w > inn. - - - - 4- - lod5 2 - -- - - s, -- . .. , - , s._::io io - - - . ,=.ca.r. > is - . ,. gs - - -s3 g c- --'ss To-'= j_ _; i ,, - - - , j e - 10 4 i. l B- 7 j

- - --'74 To-a.ss 30 -10 0 - -

- sire _- d 4 g8_ _ Q lb I)YMIN. ~ 4 - rmonAete 4-30 - - A - '7s ueTecnouxiv .: :.10, s- - . _- _g5 A C - . ,- n (A) .i - - - lo-I - - 4 : -- ~ -l "0"" - - EPP-005 -2 ~ _, ,,, g ATTACHMENT XVIII 4 [ - ~ IEY g-.- 10 -3 x105 ~ PAGE 3 0F 4 - -4 - ;; O5 REVISION 4 - -s .. . 7 -l - -e D 2 3 a - ~_______,_____M ___ ^ - -:. z_:.= . . . L. .. ._ ;_ _; _ . . _ . _ , _ , _ _ __ . _ _ . . . . _ .. a EPP-C05 l ATTACHMENT'XVIII . ,,. ' PAGE.4 OF 4 .O ' REVISION 4 N0h0 GRAM INSTRUCTIONS * . 1.0 , Determine each concentration of noble gas and lodine in the effluent. i iRecord values, pCI/m1, separately on the two nomograms. The following measurement methods should be used based on obtaining the most accurate ' results under the time restrictions present. ) 1.1 Use grab sample results whenever possible. Always verify nomogram results with computer cal.culations and grab sample results whenever practical . 1.2' Utilize RMS readings (Iow range) and correlation graphs - i In HPP-904.. 1.3 Utilize high range RMS channels to estimate the noble gas concentratloa. Assume the lodine concentration is 0.3 of the noble gas concentration unless grab semple results show otherwise. , 2.0 -Record the following information on each nomogram bas,ed en'r.ontrol room Indications.

3. .y 2.1 Time after shutdown in hours.

t

s. ~."

2.2 ot from 61-10m in F. A* 't U* $ ~ 2.3 Wind speed in MPH, preferably at 10 m. ',

1

- . e 2.4 Release rate in CFM. .

3.0 Using the numbered, scales, connect the following poines*:.- 3.1 A to li to obtain C (4). - l 3.2 1 to 2 to obtain 3 33 3 to C (4) to obtain 5 3.4 5 to 6 to obtain 7 . l 4.0 Obtain an independent review to assure scales are properly used. L 5.0 if the release concentration exc'eeds the range of the scale, the release . concentration can be divided by 1000 in order to utilize the nomogram. However, the result must be multiplied by 1000. 6.0 Results are accurate to within 30% of actual . calculations if the nomogram scales are properly used. We 9 ^W 4 e . ... . - . ~ . ~ . - , . - .... _ - . . . - ~ .. . -. 1 SAP-15 l ATTA0iMENT IV t PROCEDURE DEVELOPMENT FORM - A PAGE 1 0F 3 j REVISION O I. DATE: 4/20/83 . . PROC. p EPP-008 REY. # .4 i dig. # \ TITLE: On-Site Assembly hpf ' PEFNANENT7 A RESTRICTED FROM TO SAETY RELATED7 NEW PROC 7 REVIS10N7 X RESTRICTED CHANGE 7 Yes No X

11. DES 0tlPTION: (See Section 6.3.4)

To delete procedure in its entirety. Requirements now covered in EPP-012. -l l l. WILL THIS REvlSION/ CHANGE /NEW PROCEDtFE7 Yes No

1. Represent a change to procedtres as descri bed i n the FSM7 (50.5 revi ew) y

2. Represent a test or experiment not descri bed i n the FSNt? (50.5 revi ew) 1

3. Requi res a change to Techni cal Speci fications? (50.5 revi ew) x 4 Result i n signl ficant increased personnel radi ation exposure? (ALARA review) y SIMMARY JUSTIFICATION (List FSNt References) (attach additional pages as requi red):

Requirements now covered in EPP-012 zLMX( (Originator) V R. ale (Evaluated by Olscipline Supervisor) ustn Defe)' NOTE: I f the answer to any of the above questi ons I s "YES" - Seo Sectl on 6.3.3 of procedure. V. A. REQUIRED REVIEW NO COMMENT B. COMMENTS VI A TELECDN CO M NTS SAP OTHER Date / Time Person Contacted YES NO ( ) Ops () QR ( _T c9 Sup. / ( ) Mnt 6c) Oos. / __ ( ) TS () / __ () SS () / ( ) QA ( ) QA , / __ ( ) QC () / __ 6c ) K. Beale Telecon Origi nator REVIEWERS COMENTS RE!DLVED: # # $751f3 (Di' set'o li ne Supervi sor (Cate) V. FINAL QA REVIEW ( As applicable, refer to section IV.A) VI 1. PSRC REV1 EW Conctrren:o ' Ddte " A. Revi ewed by: VI. FINAL APPROVAL: / PSRC CHAIRMAN Date A. Responsible Individual fkuh Approval /Conctrrena [ h ] peg 'Date 7 B. PSRC Conments Resolwd B. PSRC Review Requi red: Yes NoY / ASSISTANT MANAGER Cate N JC _ EAR 0)~RA'g TTS / PSRC CHAIRMAN Date PnpY -- - . h...............O 7 g 2 51983 -.w., . . _ . . . . . . -. .. .. ,,-_ _ _ - _ -. _ . , r_.,,.. .- ~ .- .... - , - - . . . . . . . - . . . _ , . - .. Os SOUTH CAROLINA ELECTRIC.AND GAS COMPANY ( - - -- VIRGIL C. SUMMER NUCLEAR STATION . NUCLEAR OPERATIONS I ' ! r - ,. . .. wt.;LC.,,;q, . -- [*.. e ,'IN 7 f tjjyf W ilio..- _, Q _ EMERGENCY PLAN PROCEDURE ~ ' EPP-012-ONSITE PERSONNEL ACCOUNTABILITY AND EVACUATION REVISION 4 APRIL 28, 1983 NON-SAFETY'RELATED J. \ Reviewed by: }Y S Y* 13 OttIDINATOR tof this revision)- ' Date d9 GE r DISCIPLINE SUPERVISOR .rMb ' Date pproved: i NN/ PLANT MANAGER Bate' $ ' l Date Issued: MAY251983 . . :./ B == w emw*re+--w=e., %,wo .um4,. *%.. -%__ . . . . . .,%. , , , _ , . - - , _. .-,,_,,v.-. . , , . - - -.n, .-- _ -=. __ __ .._. _ 's + ~ - . EPP-012-PAGE.1- ' c,o .' ' REVISION' 4 l -_ t . . 4/28/83

7; .

~ LIST OF 1 EFFECTIVE ~:PAGES . s T P_aage, , Revision -1 - 4 - 11 4 . 1 4 2 . 4 3 4 . 4 4 5 4 -6. 4 7 -4 8 -4 q - {# - ATTACHMENTS ' Attachment I 4-e ( ,4 1 i 4 5 ^ _ , +.. .

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

l l EPP-012 PAGE il l -x = REVISION 4 - + 4/28/83 i - TABLE OF CONTENTS ^ . pg . List of Effective Pages i 1.0 PURPOSE 1

2.0 REFERENCES

1 30 CONDIl ONS AND PREREQUISITES 1 4.0 PROCEDURES 2 ATTACHMENTS Attachment I - Evacuation Routes 8

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EPP-012 REVISION 4 4/28/83 1.0 -PURPOSE 1.1 To describe the actions to be taken in t'he event that-evacuation of personnel, either in a specific area of the plant, the protected area or.the entire plant site,'is required. ' .

2.0 REFERENCES

2.1 " Virgil C. Summer ' Nuclear Station : Radiation ' Emergency Plan"

~

2.2 'EPP-002, " Communications and Notifications" - ,_

2 3' EPP-010, " Personnel / Vehicle Decontamination"

-24 EPP-011. " Personnel Search and Rescue" 25 SPP-114, " Security Responsibilities During Emergencies". ,

2.6 NUREG-0654,_ Criteria for Preparation & Evaluation of Radiological Emergency Response Plans & Preparedness in-Support of Nuclear Power Plants i_ 30 CONDITIONS AND PREREQUISITES \

31 Protected Area Evacuation may be? ordered b Director-(ED)/ Interim Emergency' Director.(yIED) the Emergency when conditions warrant such action.

i 32 When personnel are ordered to evacuate the Protected Area, they should have in their possession-the' personal ~ effects necessary to evacuate to an off-site holding area if so

, directed.

33 A specific area within the plant will be evacuated under the following conditions:

a. Confir'med~ report of a significant radioactive spill in

-;- a work area.

b. Confirmed report of an unexpected increase in the

, level of ra diation or a rib orne act vi ity in a. work area.

'W i O

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EPP-012 REVISION 4

,s 4/28/83

. ~

c., One or more area radiation monitors in a single buildi,ng reach their "Warh";setpoint. -

d . .- A fire in a work area.

e.. Or.as designated 1by the Shift-Supervisor / Emergency Director.

'3' 4 - All non-essential ' personnel will be evacuated from the b-plant site under the following . conditions:

a. - Site Emergency 4 General Emergency ,

c. As directed by the Shift Supervisor / Emergency Dire cto r 35 Sounding of the Reactor Building Evacuation Alarm will be l cause to evacuate .the Reactor Building. The Reac to r -

Eu11 ding Evacuation Alarm will sound:

a. Automatically - by source range (N-31 and N-32) nuclear instrumentation.

b. Manually .- by the reactor building evacuation button

\

located in the control room.

3. 6 ' Evacuation signs have been placed throughout the plant. l

~

Red ~ signs have been placed in the Radiation Control Area and direct personnel to the 412' elevation for personnel decontamination if applicable. Green si$ns have been placed throughout the-rest of the plant and direct

- pot sonnel out of the Protected Area by the way of the Guard House.

37 If decontamination cannot be done expeditiously, Personnel who are found to be contaminated during evacuation, should

]

be dressed in paper coveralls and marked with a yellow and magenta arm band.'

4.0 PROCEDURES 4.1 Evacuation.of Personnel from a. Spec'ific Area within the Plant.

- PAGE 2 0F 8

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EPP-012 REVISION 4'

,, 4/28/83

'4.1.1.a When personnel become aware that the conditions outlined in Section 31 exist in their area or if .

an annodncement on the plant paging system instructs them to evacuate the area they are in, they shall immediately proceed- to a location away

. 'from the affected area.

4.1.1.b Personnel shall remain toi; ether as a group and contact.the control room for accountability. The ,

Shift Supervisor will be notified of the names of any individuals thought to still be.in the affected area.

4.1,1.c The area may. be searched for possible remaining . .

personnel at the descretion of the Shift Supervisor /ED. Results will oe. reported to the Shift Supervisor /ED.

4.1.2 Personnel who have evacuated from the affected area shall remain at -th'e Access Control Assembly Area-until. monitored for loose surface contamination or-

~

directed otherwise by health physics personnel.

Personnel decontamination as per EPP-010,

" Personnel / Vehicle Decontamination" will be -

performed.as required.

.- 4.2 Evacuation of Personnel f rom the ' Reactor Build'ing.

4.2.1 Upon sounding of the Reactor Building Evacuation Alarm, allL personnel will evacuate 'to just outside the Personnel Access Hatch until otherwise instructed.

4.2.2 If the Reactor Building Evacuation Alarm- was not a spurious alarm, the SS/ED should announce over the PA System for all personnel evacuating the Reactor Building to proceed to. the Access Control Area for surveys and decontamination as necessary.

NOTE: Follow normal H.P. procedures upon exit of the "RCZ".

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EPP-012 REVISION 4

~

4/28/83 3

423 Pollowing' area evacuation, the Shift Supervisor

.- will notify the Emergency Director of the

. . circumstances that caused the sounding of 'the .

Reactor Building Evacuation Alarm.

L 4.2.4 Personnel who have evacuated the Reactor Building will be monitored for loose surface contamination.

- as necessary. Decontamination procedures will be instituted,-as required, per EPP-010. Radiation exposure will be determined and evaluated by the reading of pocket dosimeters and TLD's, if necessary.

~

NOTE: Sections 4 3 and 4.4 or_4 5 are to be performed simultaneously.

43 Personnel accountability when evacuation of non-essential personnel from the Protected Area or the site is ;

required.

431 After notification that a Protected Area or a site evacuation is required, the'following shall be performed.

4 3 1.a If not already on_ station, all. essential personnel shall report to their assigned duty stations. t 4 3 1.b All non-essential personnel shall exit the plant thru the guard house, or AAP (depending on their point of ingress) '

using normal exiting routine..

4 3 1.c Personnel working in the Padiation. Control Area shall proceed to the 412' elev. of the Control Building-for monitoring prior to proceeding to-either a or b above.

432 Accountability for all personnel shall be performed by security at the guard' house in the following-4 manner:

4 3 2.a The Shift Supervisor, Operations Support Center Supervisor and Technical Support Center Superviaor shall account for the personnel in their respective areas and u report to the Administrative Supervisor those personnel present. The Administrative Supervisor shall report those personnel to Security at the Guard House.

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EPP-012-l REVISION 4

.4/28/83

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I , 14 3 2.b _ Security personnel in the guard house and *

~

AAP will verify by badge _ count-that'all ,

. . personnel other.'than the_ essential have

left the_ station. The AAP will report any

.descrepancies to the guard house.

4 3 2.c . Security will report any suspected missing-personnel to the ED/SS. , ,

4.3 2.d ersonnel shall.be paged Suspected from-the guardhouse missing p/ Control Room /TSC. ,

_ Attention in the plant. Attention in the-plant The-following_ personnel' report your location to Security,-(Names , ,) Repeat this

fi message once per minute for three minutes.

4 3 2.e If after.. waiting for 5 minutes the suspected missing _ personnel have not reported to the guard house.the SS/E.D.

shall be notified. that these individuals cannot be accounted for. .

4 3 2.f At the. direction of the ED/SS EPP-011,

" Personnel Search and Rescue" shall be

- implemented.

N ,

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44 Evacuation of Non-Essential Personnel From the Site to their private Residence.

(At the_ discretion of the E.D./SS this should include personnel at Fairfield Pumped Storage' Facility).

'The Emergency. Director / Shift Supervisor shall instruct all non-essential personnel-to evacuate to their private-residences by making the following announcement on the

plant page. -

" Attention in the . plant. Attention in the plant" o - "All Non-Essential Personnel Evacuate the station.

Proceed to your private residence and await further instructions".

Sound the Radiation Emergency Alarm Repeat message.

^

REPEAT THE AB0VE INSTRUCTION EVERY TWO MINUTES FOR SIX-r -MINUTES.

t, 5 %

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EPP-012 REVISION 4 4/28/83 i

.s The Communicator should notify Fairfield Pumped Storage as per EPP-002. ,

45 Evacuation of Non-Essential Personnel to Offsite Holding '

Areas (See - Attachment I area . map) .

NOTE: Under,certain-conditions it may be necessary for ,

personnel to evacuate to' predesignated offsite holding areas i.e.

a. potential personnel contamination

b. need for additional personnel on short notice

c. radiation exposure considerations (At the discretion of the E.D./SS this should include personnel at Fairfield Pumped Storage Facility).

451 The Emergency Director / Shift Supervisor shall determine which holding Area to evacuate to based on a review of prevailing wind data. -

4 5.2 The Emergency Director / Shift Supervisor'shall instruct all non-essential personnel to evacuate to the desired Holding Area by making the following announcement. \

4 5 2.a For the south holding area

" Attention in the plant. Attention in the plant". "All Non-Essential Personnel Evacuate to the Nuclear Training Center and await further instructions.

Sound the Radiation Emergenc'y Alarm. Repeat message.

Repeat the above instruction every two minutes for six minutes.

4 5'.2.b For the north holding area Attention in the plant. Attention in the plant "All Non-Essential Personnel Evacuate to the Monticello Reservoir Recreational Facility and await further instructions".

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_ _ - _ _ _ _ _ __ - 2.___ e, .

. EPP-012 REVISION 4 4/28/83 Sound the Radiation Emergency Alarm. - Repeat message.- . .

Repeat.theLabove instr'uction every'two minutes for '

, six minutes.-

The. Communicator should notify Fairfield: Pumped .

Storage as_p_er EPP-002.

4.6 Evacuation ofi the- Protected Area. ,

, NOTE: Protected Area Evacuation should~be declared:when .

conditions' dictate the_need-for personnel accountability but not evacuation of the plant site.

4 6.1 The ED/SS-shall instruct all non-essential personnel to evacuate the Protected Area by making .

the 'following announcement::

. - i Attention in-the plant.- Attention in the plant. .

All non-essential personnel evacuate the Protected Area. Froceed to the areas outside the -

, ' Guard House.-or A'.A.P. and await further j instructions. \

Sound the Radiation Emergency Alarm - Repeat Message. ..

REPEAT THE ABOVE INSTRUCTION EVERE TWO MINUTES FOR SIX MINUTES.

l 47 General Guidance for conduct _of evacuation.

471 Non-essential-personnel will-proceed through the Guard House, or AAP (depending;on^their point of I.

ingress) leave their security badges, be checked for contamination and proceed to the off-site holding area or private residence by vehicles.

(Unless otherwise directed in a drill). Personnel t -

- proceeding to an offsite-holding area must keep their TLD and dosimeter unless otherwise directed by HP or Security.

4 4 5

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EPP-012 REVISION 4 4/28/83 4.7.2 The Security Shift Leader will ensure all .

non-essential personnel'have, exited the Guard House andfall essentiti personnel have been accounted for within about 30 minutep or will report the situation to the f Shif t -Supervisor or . Emergency Director who will initiate EPP-Oll, " Personnel Search and Rescue".

4.-7 3 The Emergency Director will ensure notification of - l the personnel at,tba Wai rfield Pumpe,d Storaze Facility- (Phone' . Ors. . As pe Jormed and they' are instructea to take the same

~

actions as other non-essentialpersonnel.

4.7.4 The Emergency director will ensure that a member (s) . l-f rom -the security force surveys the area within the exclusion area for persons. He will also ensure that members of radiation montoring teams that are sent out to do surveys are instructed to observe the area for personnel.

In the event of evacuation to an offsite holding l' 4.7.5 area, i senior supervisor shall be assigned by tne E.D. or S.S. to maintain communi~ cations with the site ~and establish control at the offsite holding

~ area if activated.

4.7.6 The Emergency Director will ensure that' a person (s) f.

qualified in personnel monitoring and decontamination is sent to the designated off-site holding area.

4.6.6.1 The person responsible for monitoring will obtain an offsite holding area radiation emergency kit from the security annex and proceed to the designated offsite holding area. This _ individual will ensure that all personnel / vehicles are monitored and decontaminated in accordance with EPP-010 Personnel / Vehicle Decontamination.

4.7 7 The Emergency. Director will ensure that the Fairfield County Emergency Services Dispatcher is

~

notified to assist in decontamination of vehicles and personnel as necessary.

4.7.8 Personnel evacuating f rom inside the RCA should -

frisk with RM-14 or portal monitor on 412' elevation control building. ~ Personnel evacuating the site should monitor at the guard house using the portal monitor or RM-14. Any Alarm Conditions .

on portal monitors or obvious increase in count rate on RM-14 should be reported to H.P.

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SOUTH CAROLINA ELECTRIC AND GAS COMPANY VIRGIL C. SUMMER NUCLEAR STATION NUCLEAR OPERATIONS

. KUCLEAR OPEgog3 COPY No.........

fg 7........

EMERGENCY PLAN PROCEDURE EPP-012 .

FIRE EMERGENCY .

, REVISION 3 APRIL 26, 1983 NON-SAFETY RELATED Reviewed by:

W .

' Date f3 ORIQNATOR C5f this revision)

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DISCIPLINE SUPERVISOR / Dhte b

i Approved:

ff Ash PLANT MANAEER

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'Dat%

Date Issued:

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EPP-013 PAGE i REVISION 3

,_. 4/26/83- -

LIST OF' EFFECTIVE PAGES .

PAGE -

REVISION 1 3 11 -

3 1 3 2 3 3 3 -

4 .

3 5 3 6 3

.7 3 8 3 9 s, 3 ATTACHMENTS Attactment I 3 1

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EPP-013 PAGE 11 .

REVISION 3

.., g 4/26/83 1

TABLE OF CONTENTS

_...._ -. PAGE List of Effective ~Pages i 1.' O PURPOSE '1

2.0 REFERENCES

1 3 0 -CONDITIONS AND~ PREREQUISITES 1 4.0 PROCEDURES 1 ATTACHMENTS Attachnent I

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EPP-013 REVISION 3 g_

4/26/83 1.0 PURPOSE To provide guidelines for the pranpt and e'fficient handling of a fire energency.

1

2.0 REFERENCES

2.1 " Virgil C. Sumner Nuclear ' Station Radiation Energency Plan" 2.2 " Virgil C. Summer Fire -Protection Program Plan" 4

2.3. AP-1401, . " Fire Protection Program" ,

2.4 " Fire, Preplans" 2.5 PPP-002, " Fire Report" 2.6 AP-1502, "NRC Report Preparation" 27 EPP-010, " Personnel / Vehicle Decontanination" 2.8 EPP-009, "Onsite Medical" 29 EPP-020,-"Bnergency Personnel Exposure Control" 2.10-NuReg 0654, Criteria for' Preparation & Evaluation of Radiological Energency Response Plans & Preparedness in-Support of Nuclear Power Plants 2.11 " Security. Safeguards Contingency Plan" 2.12 EPP-012 "On-Site Personnel Accountability and Evacuation".

3.0 CONDITIONS AND' PREREQUISITES 31 .This procedure is to be used whenever a potentially hazardous fire-has been discovered or the Energency Plan has been activated for a fire emergency.-Attachment I i provides a Flow diagram related to Lnplanentations of Procedure.

4.0 -PROCEDURE I

4.1 The individual at V. C. Sumner Nuclear Station discovering the fire shall:

+

0 PAGE 1 0F 9

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A EPP-013 REVISION 3

. 4/26/83 p

L 4 1-1 . Contact the control room by emergency number 3333 or plant Gai-tronics and report the fire by stating.the location, class and approximate size of the fire.

4 1.2 Unless undue-personal risk is apparent or doubt exists on' ability to properly use extinguishers, attempt-tocontrol~and/or extinguish th'e fire using fire extinguishers appropriate for the c1Saa of fire.

413 Remain in the vicinity at a safe distance until arrival of the-Fire Brigade and inform the Fire Brigade of the' circumstances.

4 2 The individual at the Fairfield Pumped: Storage Facility discovering the fire shall:

4 2.1 Contact the shift supervisor and/or control room by-Emergency Number-3333 or normal telephone, and report the. fire and the need for outside assistance.

The individual will also state the location and size

. of the fir.e.. ,

4 2.2 Unless undue personal risk is. apparent or doubt' exists on ability to properly use extinguishers, attempt to extinguish the fire using-fire

, extinguishers, and await the arrival of'outside assistance.

43 Persons within an area where fire occurs shall ensure 4 1 or 4 2 are accomplished, evacuate the immediate fire. area to the nearest safe distance-and comply with further authorized instructions as may be given- during the fire 4

emergency. If the fire is at the V. C. Summer Station -

within the radiation control area, persons will comply with health physics procedures for exit from such areas unless 1 conditions warrant immediate evacuation.

i 44 The Control Room Operator, upon receipt of a report of fire or fire alarm annunciation, shall:

l' .

l 441 Notify the Shift Supervisor or Control Room Foreman of the fire report or Integrated Fire and Security System Alarm.

l l

45 The Shift Supervisor / Control Room Foreman shall:

L 451 If the fire is at the Summer Station:

1 A. The following announcement shall be made over the plant paging system:

i PAGE 2 0F 9 V .

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EPP-013

l REVISION 3 '!

4/26/83 I

, 7s . l

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Attention all personnel, there is a (state ;

condition as'known) fire (or anoke) in (state ,

roan, elevation, and building). Personnel in the vicinity of. (state room , elevation'. and building).should leave this area.

OR Announce Protected Area evacuation as per Ref. 2.12.

B. The fire alann is sounded.

C. Repeat the message.

NOTE: Repeat steps A, B, & C above every two minutes for six minutes.

D. Notify the duty Security Shift Leader of the fire and ensure Security support and assistance has been initiated for the fira: response. -

E. If the fire occurs in any ventilation zone communicating with the Spent Fuel Pool 4

Ventilation Sub-systems,' Reactor Building Cooling 1

Units or the Control Room Normal and' Energency Air Handling System, refer to Technical Specification 4.9.llb, 4.6.3b or 4.7.6c respectively to ensure / verify operability of-the applicable HEPA filter bank.

F. Insure the plant is in aisafe condition -

commensurate with the real or potential consequences of the fire. ;

G. Provide general direction at the fire location and/or support to'the Fire Brigade Team Leader.

' ~

NOTE: Support to the fire brigade may include -

radiation monitoring,- first aid, evacuation, and assembling-additional Fire Brigade Teams, etc. Appropriate health physics and energency. plan procedures should be-used as warranted by the circunstances.

H. Detenmine the Energency Action Level (EAL) represented by the and advise the Emergency i Director of the EAL and corresponding Energency classification, e.g., unusual event, alert, site emergency, or general emergency.

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EPP-013 REVISION 3

, ~ ,

4/26/83 NOTE: The corresponding fire preplan identifiIes the safety related equignent which may be affected by the ~

fire.

- I. If~offsite assistance is required,.for example:

(a)- Safety Related Equipnent-is jeopardized (b) Fire is in excess of. Fire. Brigade.

Capabilities (c) Fire is located outside of pertneter fence Notify the Fairfield County Dispatcher. .

Phone: 635-5511 (Fairfield County Dispatcher)

Give the following infonnation:

This is Virgil C. Sanmer Station, (This is a drill This is not a drill .) We request fire fighting assistance at the Summer Nuclear

> Station. The fire trucks must assenble at the main l ~ gate, and await' further instructions from Security.

J. Upon extinguishing the fire, direct s necessary recovery to normal plant operation giving

- consideration to the following:

1. Need for fire watches as required by Technical Specifications while fire detection and suppression systems are out of' service.

2. Restoring fire detection and fire suppression systems to nonnal operational ~ alignnent in accordance with governing System Operating -

Procedures.

N'OTE: Maintenance may be required prior to resetting fire suppression systems. See 4.8.5.e of this procedure.

3 Initiating Licensee Event Report if required by AP-1502, NRC Report Preparation.

4.5 2 If the fire is at the Fairfield Punped Storage

. c Facility:

A. Notify offsite fire assistance as follows:

Phone 635-5511 Give the following information:

(Fairfield County Dispatcher) 4 PAGE 4 0F 9

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EPP-013 REVISION 3

.- - 4/26/83 This is Virgil C. Summer Nuclear Station, (this is a drill , this is not a drill . ) We request fire fighting assistance at the Fairfield Punp Storage

' Facility.

B. Notify duty security' shift leader of fire and ensure security support and assistance has been. initiated for_the fire. response.

L4. 6 The Emergency Director shall:

4.6.1 Activate provisions of the Energency Plan consistent with the Energency Classification of the fire. .

4.6.2

~

Ensure notification of-NRC I&E Regional Office is accanplished, if required.

4.7 The Fire Brigade shall:

4.7.1 Assemble at one of the two inplant fire stations or report directly to the announced fire scene dependent on the location of the fire, and watch station assignment.

A. Fire Brigade Leader: Respond-directly to the scene of the fire. g B. Fire Brigade Members: .

1. The Watchstander whose Watch-Station is closest to the reported fire shall respond directly to tne scene of the fire.

2. A11~ other on shift Fire Brigade Members will report to onelof the two assenbly points dependent upon the location of the fire.

D 4

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Assenbly Points Responding For all other Fire Location' Aux. Operator PB members

-Aux. b1dg., West Penetration, Auxiliary 412' Level ;

Druning Area, Building Control Bldg.

Hot Machine Shop, Puel Hdl. Aux. Operator Southeast Stairwell Bldg, Reactor Bldg. ,

Intermediate b1dg', ,

Inte rmediate 436' Level East Penetration Building. Turbine Bldg.

Diesel Generator bldg. Aux. Operator West End-Service water'& circulating water pump house, warehouse .

Turbine building, Service Turbine b1dg. 436' Level bldg. Transformer areas Aux. Operator Turbine Bldg.

Water Trenoment ' Plant West End Control bldg. Operator as 412' Level Control assigned building, Southeast Stairwell Outside of perimeter fence Aux. Operator 436' Level Turbine-As directed Bldg. West End By Fire Brigade 1 Leader 4.7.2 Those personnel reporting to the assembly area will don full fire protection and self-contained breathing apparatus, l

unless otherwise directed by the Fire Brigade Leader, or Control Room and standby. for further directions. A set of fire preplans shall be taken to the scene, if applicable, and when requested. -

4.h.3 Under the direction of the Fire' Brigade Leader extinguish the fire usi'ng the following guidelines.

A. Use the fire preplan ~ appropriate to the room for

' basic information on the fire hazards, room contents, l

and fire fighting techniques, if applicable.

5 B. Observe activation of autanatic suppression systems where installed.

Q "

C. If necessary, manually activate the autanatic -

suppression system.

l I PAGE 6 0F 9

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EPP-013 REVISION 3 4/26/83

,. D. Conduct fire -fighting in two person teams as *directed by the Fire Brigade Leader.

4.8 The Fire Brigade Leader shall:

4.8.1 Establish a Fire Fighting Command Post. - ,

4.8.2 Direct the fire fighting effort.

4.8.3 Advise the Shift Supervisor of the fire' conditions. This should be done upon arrival at the scene and at intervals

- during the fire emergency as appropriate to the >

circumstances.

4.8.4 Request from the Shif t Supervisor necessary support such as radiation monitoring, first aid, or offsite fire c ompanies . -

4.8.5 Coordinate support by offsite fire emnpanies appropriate to the circunstances.

i NOTE: The Fire Brigade Leader directs, in co-ordination -

with the Shift Supervisor, the activities of responding fire canpanies by direct communications with the Fire Chief. The Fire Brigade Leader ke'eps the Shift Supervisor apprised throughout the fire ,

energency, informs the responding Fire Chief of circunstances, and assigns firefighting objectives to the Fire Chief. Fire command of responding fire canpanies is provided by the Fire Chief in Charge subject to directions, restrictions and objectives assigned by the Shift Supervisor or Fire Brigade leader.

4.8.6 The Fire-Brigade Leader should ensure the following actions are taken upon. extinguishing the fire:

. A. Notify the Shif t Supervisor.

B.- Secure fire supprassion systems if a'ctivated by closing the supply valve (s).

l NOTE: _ Refer to " Fire Preplan" for valve location.

~1 C. Request-the Shift Supervisor to assign a Fire Watch if there is potential for reflash or.reignition.

e PAGE 7 0F 9

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EPP-013 REVISION 3 4/26/83 i

D. Direct Fire Bridgade members' activities with respect to restoring fire fighting equipment.

E. Initiate-necessary Maintenance Work Requests to restore housekeeping conditions and fire suppression systems. Maintenance Work Requests should be generated to replace. fusible links and/or recharge portable fire extinguishers, halon systems an'd CO2 systems, as necessary.

F.. Prepare a Fire Report in accordance with FPP-002,

" Fire Report".

4.9 The Fairfield County Fire "ervices shall: _

4.9.1 Report to the designated staging area located at the main gate next to the guard house. The chief in charge will report to Security.

492 Receive instructions from the Security Force which include current status of fire if known and location.to meet with the Fire Brigade Leader.

4.9 3 Receive personnel dostnetry equipment necessary for the ,

location of the fire.

, 4.9.4 Conduct fire. fighting in coordination with.the Fire Brigade Leader, and Shif t Supervisor.

4.10 The Security Force shall:

4.10.1 If the fire is at Sumner Station:

. A. Implement requirements of Security Safeguard -

Contingencies Plan.

B. When directed by the Fire Brigade Leader or Shif t Supervisor, admit responding offsite fire companies to the protected area.and perform the following:

i l 1. Ensure vehicle is not under duress, and that all l

responding personnel are members of the fire l

canpany.

l-

2. Distribute dosimetry devices assigned for this purpose it.necessary (see EPP-020).

S PAGE 8 0F 9

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EPP-013 REVISION 3 4 .

4/26/83

3. Escort the offsite fire companies within the protected area.

'4 . Escort the Fire Chief of.offsite f$ re companies to the Fire Brigade Leader.

5 Maintain the s'taging area for additional fire companies. The staging' area will be established so as not to interfere with ingress & egress from the station, but will be such that entry into the facility, if necessary, will not be Dnpaired.

i

6. Act as liaison between the Fire Brigade Leader and the staging area. ,

7. Prior to permitting offsite fire canpanies to exit the protected area, ensure that requirements of references 2.7 and 2.9 have been accomplished.

4.10.2 If the fire is located at the Fairfield Pumped Storage Pacility:

A. A& nit responding offsite' fire canpanies to the Fairfield Pumped Storage. Facility. ,

B. Provide security support as applicable during the 5

energency condition.

C. Establish a staging area for additional fire l companies. The staging area will be established so as not to interfere with evacuation routes, but will be 3

such that entry'into the facility, if necessary will j not be knpaired.

D. Act as Liaison between Pairfield Pumped Storage Personnel and the staging area. -

4.11 The Health Physics group shall:

A. Log persons, their assigned doshnetry-identification, ,

and vehicles, per reference 2.9, if necessary.

2- B. Collect dosimetry devices, if necessary.

C. Ensure radiation monitoring of persons and survey of vehicles .and equignent are performed before allowing exit from Protected Area if personnel or vehicles entered the Radiation Control Area.

3 9 g

PAGE 9 0F 9 -

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O SOUTH CAROLINA ELECTRIC AND GAS COMPANY l VIRGIL C SUMMER NUCLEAR STATION NUCLEAR OPERATIONS KCER CPERA"LdSS COPY No.

\S1 ~~~-

Emergency Plan Procedure EPP-015 NATURAL EMERGENCY (EARTHQUAKE, TORNADO)

REVISION 2 JULY 20, 1983 Non-Safety Related

(

Reviewed by:

A m_b ORIQNATORVf this revision) 7

' Ddte 13

$. sn/& >

DIS IFDRiE SUPERVISOR 7 b9 93

Datie Approved:

/ 4FL c s~ )/2. Wf%

PLAdT MANAGER Date '

Date Issued: AUG 02 S83

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-t EPP-015-PAGE 1

. REVISION 2 7/20/83

(. '

LIST OF SFFECTIVE PAGES Page Revision -

1 2 11 2

'l 2 2 2 ATTACHMENTS- .1 Attachment I, Pages 1 through 4 2 4

9 i-6 J O 6ewm *ew . -w -, **#-- ,

EPP-015 PAGE 11 REVISION 2

. -., 7/20/83

- TABLE OF CONTENTS fage List of Effective Pages i 1.0 PURPOSE 'l t-

2.0 REFERENCES

1 30 CONDITIONS AND PREREQUISITES 1 4.0 PROCEDURES 1

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. . _ . _ . _ . . . . . .. _.. _ . _ . . . _ _ . . . _ .1 EPP-015 REVISION.2 7/20/83

(.

',, 1.0 PURPOSE 1.1 To provide guidelines for initiating actions when either a tornado or earthquake threatens plant structures-or personnel.

2.0 REFERENCES

2.1 Virgil C. Summer Nuclear Station Radiation Emergency Plan. l 2.2 " Virgil C. Summer Nuclear Station Final Safety Analysis Repo rt , Chapter 3".

, 23 NUREG-0654, Criteria for Preparation & Evaluation of Radiological Emergency Response Plans & Preparedness in' Support of Nuclear. Power Plants.

2.4~ EPP-012, "Onsite Personnel Accountability and Evacuation.

25 EPP-002, " Communication and Notification".

30 CONDITIONS AND PREREQUISITES

< . 31 A tornado watch is declared by the National Weather i / Services when meteorological conditions in an area are such that the potential for.the formation of tornadoes exists.

32 A tornado warning is declared by the National Weather Services when (radar sighting, verified visual observation) a tornado has been sighted.

4.0 PROCEDURES 4.1 Tornadoes 4.1.1 When information is received, from either the load dispatcher or other reliable source, that.a tornado watch / warning is in effect for the area surrounding V.C. Summer Nuclear Station, the Shif t Supervisor shall perform the following:

a. Inform the Management Duty Supervisor.

b. Announce the watch / warning over the plant paging system directing personnel to seek shelter in a secure structure, if necessary and inform the guard house.

PAGE 1 0F 2

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EPP-015 REVISION 2 c

7/20/83 E' c.- Designate Shif t Personnel, or if the 0SC is -

activated,-.an Emergency Repair Team to ensure that all exterior doors to the plant structures

!are shut and secure (include non-protected buildings if time permits). 'Ihe Emergency -Repair Team should secure any ' equipment / materials in the ;

Protected Area that could become missiles in high winds and'put all heavy . equipment in a safe' condition (i.e., lowering crane. booms).

i'

d. An Emergen'cy ~ Repair Team should stand by in the event emergency assessment and corrective actions are required. The Emergency Repair Team should consist of the following:

l ~. ' Operations Personnel *

2. Health Physics Personnel 3 Maintenance Personnel 1

NOTE: Should a situation arise waich would require the i presence of an armed individual such as work being done on the physical security system, assistance from the Security-Force may be requested.

e. If evacuation of the site is required, follow the-

, -(

', procedure-outlined in'EPP-012, Onsite. Personnel,

- \ ' Accountability and Evacuation.

f. Upon cancellation of the watch / warning by the load dispatcher or the National Weather Service, make'the appropriate announcement.over the plant paging system and resume all normal activities. .

NOTE: Backup to. load dispatcher for weather _information is the National Weather Service' (Refer to EPP-002 for

' telephone number) 4.2 .. Earthquake

~4.2.1 In :the event of seismic disturbance, the Shif t .

Supervisor will initiate.the appropriate corrective actions for any-resulting damage.

~

4.2.2 Ifithe - seismic' instrumentation in the Control Room indicates that the . operating basis earthquake has been exceeded, the plant must be shutdown.

.4.2 3. 3T evacuation of the site is required, follow'the procedures outlined in EPP-012.

- 4.2.4 Bar any seismic -disturbance, complete Attachment I

, and forward to Assist 9nt Manager, Operations.

PAGE 2 0F 2

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EPP-015

, ATTACETIT I MAIN CONTROL BOARD ANNUNCIATOR PANEL PAGE 1 of 4 REVISION 2

( ., X - Indicates Annunciation RB FOUND SEIS. SWITCH OBE EXCEED (Panel 3-5)

SEIS RCDR SYS START / PWR LOSS (Panel 3-6)

SEIS RESPNS SPECTRUM ANNUN TRBL (Panel 4-6) t l.

k RB FOUND SEIS SWITCH OBE EXCEED SEIS RCDR SEIS RESPNS SYS START / SPECTRUM PWR T. CSS ANNUN TRBL l

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EPP-015 ATTACHMENT I PAGE 2 of 4 REVISION 2 g ., ANNUNCIATOR FRONT PANEL STATUS Response Spectrum Annunciator Model PSA 1575 (S/N 48)

X - Indicates Lamp is Lighted -

NORMAL

%SSE OBE. SSE OBE %SSE OBE {ni,wuroCV (Hz)

,- 2 2.5 E O 2.2 O O 4 !

t 5

6.4 8

10.1 12.7 16

] ] 20'.2 4

25.4 Yellow Red Yellow Red Yellow Red ~

NORTH / SOUTH VERTICAL EAST / WEST

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.. . . _ _ . - _ _ _ _ . . . _ _ _ _ _ ._ _ _ _ . _ _ . _._.._- a EPP-015 AITACHMENT I PAGE 3 of 4 REVISION 2

"' RELAY ROOM - INSTRUMENTATION PANEL CONTROL BUILDING - EIE/. 436 SEISMIC MONITORING SYSTEM XPN - 60 41 - EI Digital Cassette Playback

Playback ,,

MODEL DSP-1 Strip l Tape o '

Serial No. 108 aan IYa 1780B c3,,, e O O Controls e C ,

Pwr Select Cassette Cassette ;

Recorder Recorder '

IYR 1784 . IYR 1780A O. O AC/ON g ,

Event Alarm O Yen.

Batt/Vol.

8'# *

O Trigger Test O O O calib/Frea Test b Kev _

AC/ON O SEISMIC SWITCH POWER SUPPLY Q Event Alarm

Reset Batt./Vol. Serial No. 134 O O Test g DOCU E1TATION EVENT COUNTER READING (DSA-3) -

SEISMIC SWITCH EVENT ALARM (SP-1)

@ Indicates Yellow Lamp is Lighted

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. I EPP-015 i ATTACHMENT I PAGE 4 0F 4

^ REVISION 2 CONTROL ROOM OBSERVATIONS Date: Time:

' Earthquake Felt . [] Yes [] No Duration of Noticeable Motion - [] < 1 sec [] 1-4 sec

[] 5-10 sec [] > 10 see Estimated Duration (sec)

' Earthquake Heard - [] Yes [] No Description of Sound -

Direction of Sound / Motion (If Determinable):

Background Noise at Start of Earthquake: [] Quiet [] Moderate [] Loud i PLANT STATUS: [] Operational % Power Level !

[] Shutdown [] Reactor Trip Time OBSERVATIONS / PLANTS EFFECTS:

I I

u l

, Shif t Supervisor Date Time 1

=

- . . . - . _ . . . . . - . . . - - . . _ _ _ _ . . . _ ~ . _ _ . ..

f SOUTH CAROLINA ELECTRIC AND GAS COMPANY

- l VIRGIL C. SUMMER NUCLEAR STATION l 1

NUCLEAR OPERATIONS i NL C _ EAR O P ERA"'ONS

_ _'- COPY N o.. . . . . . . )$.]. . . .

EMERGENCY PLAN PROCEDURE ,

EPP-016 .

EMERGENCY FACILITIES ACTIVATION e, , ...

AND EVACUATION e

REVISION 3 APRIL 26, 1983 NON-SAFETY RELATED

/*

k. _, \

Reviewed by:

blRT DRlMINATORMor this revision) / pate ,

, iH ad.r -

DISC ~IPLINE SUPERVISOR s/da

' Date Approved: .

$YAA$

PLAST MAllAGER fl}Wy Dat6 , e --

.3N O i 1983 Date Issued-

~

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- - ._ . . . . - . . . . . . . . ... ~ .- -

l EPP-016 PAGE 1 I REVISION 3 i O '::

4/26/83 l

. . 1 LIST OF EFFECTIVE PAGES 1 f

PAGE REVISION .

i~ 3 g

11. .

3 l' 3 2 , 3 3 .

3 .

4' 4. , x-3 5 3 6 3 7 - 3 ATTACHMENTS Attachnent I 3' Attachnent II -

3

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EPP-016 PAGE 11 l

, ~s REVISION 3 l

4/26/83 TABLE OF CONTENTS List of Effective Pages - PAGE .

< 1.0 PURPOSE i i

2.0~ REFERENCES 1 30 DEFINITIONS AND ABBREVIATIONS 1 4.0 CONDITIONS AND PREREQUISITES 2 50 - PROCEDURE 3 .

ATTACHMENTS' " C ATTACHMENT I - Emergency Organization ATTACHMENT II - (On-Site Energency Organization Response)

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. EPP-016 REVISION 3 c s.

4/26/83

< - 1.0 PURPOSE .

The purpose of this procedure is to delineate the actions

~

1.1 necessary to activate and conditions for evacuation of, the Technical Support Center, Operations Support- Center, the Health Physics' Lab, the Baergency Operations Facility, and

' t}ie News Media' Area.

^

2.0 REFERENCES

2.1 " Virgil C. Sumner Nuclear Station Radiation Energency Plan" 2.2. NNREG 0654, " Criteria for Preparation &-Evaluation of ,

Radiological Energency Response Plans & Preparedness in

; Support of Nuclear Power Plants". . .

23 SPP-114 - Security Force Responsibilities During Emergencies 2.4 EPP-019 .Energency Equipnent Checklist 2.5 "CEMP" - Corporate Bu'ergency Management Plan

. 2.6 CEP-001 - Corporate Emergency Procedure - 001 CEP-007 - Corporate Energency. Procedure - 007

/ 2.7 30 DEFINITIONS AND ABBREVIATIONS 3.1 Definitions 3.1.1 Activation of Facility - A facility is activated when.

the facility is manned with the necessary personnel, prepared to provide its support function, as '

~ detennined by the Facility Leader.

32 Abbreviations 3.2.1 TSC-TechnicalSubportCenter .

'3.2.2 OSC - Operations Support Center .,

3.2 3 EOF - Energency Operations Facility 3 2.4 NMA - News Media Area L .

. PAGE 1 OF 7 9

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EPP-016 REVISION 3 4/26/83 .

'N c . 325 ED - Energency'D'irector .

3 2.6 IED - Interim muergency Director -

~

3 2.7 OEC - 0ffsite Baergency Coordinator 3 218 CR - Control Room ,

1 4.0 CONDITIONS AND PREREQUISITES 4.1 Plant conditions exist requiring haplementation of .the

'Energency Plan; and the conditions have been classified as an Alert, Site or General Bnergency.. . ,

~

4.2 Attachnent II is an aid to the ED/IED to identify personnel,

-by title, who are qualified to ' direct and/or perform-functions as per applicable Emergency. Plan Procedures (EPP).

4.2.1 In the section "Nonnal Assigned EPP Responsibility",

responsibility is delineated as follows: .

A. "X" - responsible for the initiation of action required by the procedure;

1. "X(1)" - first alternate for "X".\

2. "X(2)" - second alternate for "X".

B. "L" - responsibile for being.the leader of the team and/or activity described in the procedure; i

1. "L(1)" - first alternate for "L".

2. "L(2)" - second alternate for "L".

C. "M" - responsible for performing actions / assessment or being a member of the team described in the procedure.

NOTE: The ED/IED has overall responsibility for the initiation of and activities requir.ed in all EPP's.

4.3 'Each emergency facility is equipped per appropriate procedure.

-4.3.1- TSC/OSC/HP lab per EPP-019

/

s PAGE 2 0F 7

. .v ,

EPP-016

. REVISION 3 4/26/83 432 E0P/ News Media Area per CEP-OO7 ,

'4 4 At the discretion of the Interim Emergency Director, turnove of various responsibilities to the appropriate designated personnel can be accomplished as those persons respond to the emergency prior to the activation of the TSC/OSC. .

5.0 PROCEDURE 5 .1 Activation of Technical Support Center (TSC) 511 Upon declaration of an Alert, Site Emergency, or '

General Emergency the following essential personnel shall proceed to the TSC.

A. Emergency Director (ED)

B. TSC Communicator C.. ED Administrative Assistants (2)

D. Radiological Assessment Supervisor (1)

E. Out-of-Plant Monitoring Director.

P. In-plant. Monitoring Director G Personnel with:

1. Core Expertise

?. Mechanical Expertise 3 Electrical Expertise 5 1.2 Upon declaration of an Alert, Site Emergency, or General Emergency the following key personnel should proceed to the TSC.

~

A. Security Supervisor

~

B. Assistant Manager Support Services O. Assistant Manager Technical Support D. Assistant Manager Maintenance Services e

.%s PAGE 3 OP 7

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EPP-016 REVISION.3 4/26/83 e

u. E. Deputy Manager- -

'513 .. At the discretion of the Radiological Assessment-Supervisor, a radiological survey is performed to detennine the habitability of the TSC. If the .

radiation dose rate is greater than 100MR/hr. or the airborne radiation levels exceed 10CFR20 Ap'bendix B,.

Table 1 limits, the evacuation . requirements of S5ction 5.2 of this procedure shall be carried out.

5 1.4 A personnel accountability check shall be performed.

5 1.5 The Emergency Director (ED) shall receive an update on the energency condition from the Interim Energency ,

Director (IED).

5 1.6 Following the update of the ED, the IED shall officially turnover the Energency Director duties .and responsibilities to the ED along with the Energency Log.

5 1.7 The energency log shall be kept by the ED's logger following the official turnover.

,x 5.1.8 The TSC canmunicator shall report to the CR to

receive official turnover of the Energency

(

' ~ s' Notification Log from the interim communicator.

5.1.9 Upon the request of the ED, the TSC staff shall provide technical evaluations of the emergency condition and/or courses of action to be taken to minimize the effects of the energency condition.

5.2 Evacuation of the TSC If the airborne radiation levels exceed 100FR20, Appendix B, 1 Table 1 limits or the radiation levels exceed 100 MR/hr. in the i

. TSC, the following actions shall be taken.

5 2.1 The Bnergency Director (ED) shall designate the personnel required to stay in the TSC-and Control Room.

5 2.2 The renainder of the personnel shall proceed to the Energency Operations Facility (EOF).

5 2.3 If the EOF is or becomes uninhabitable, the ED shall designate the alternate assembly area.

4 O

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EPP-016 REVISION 3 4/26/83 u -5.3 Activation of the Operational Support Center (OSC) ..

+

531 Upon declaration of an Alert, Site Bnergency, or i General Snergency the following personnel, as a -

mintnum, shall proceed to the OSC. . '{-

A. Rad-Waste Opdrator (1)

B. Mechanical Maintenance (1)

C. I.& C Maintenance (1)

D. Electrical Maintenance (2)

E. Chemistry Specialist NOTE: All " lead" shift personnel shall report to the Control Room initially unless otherwise directed by the SS/ED. All 30/60 min. response personnel shall report to the OSC unless otherwise directed by the SS/ED.

~

5 3.2 The Operations Support Center Supervisor, upon being

! notified, should proceed to the OSC; along with other personnel as designated by the Bnergency Director.

5 3.3 At the discretion of the Radiological Assessment Supervisor, a radiation survey. shall be perfonned to detennine the habitability of ,the OSC. If the general area dose rate is greater than 100 mr/hr or airborne levels exceed 10CFR20, Appendix B, Table 1 limits , the OSC shall be evacuated in accordance with

, Section 5.4 of this procedure.

C 5.3.4 A personnel accountability chec.k - shall be perfonned.

5.3.5 When the OSC is manned the OSC Supervisor shall-

-report to the ED/IED that the OSC is, activated and prepared -to perfonn its support ' unction.

5 3.6. Upon the req'uest of the.ED/IED, the'OSC staff shall

- provide personnel to' man' fire brigade teams , search -

and rescue teams , first-aid teams , maintenance and

. , repair teams, and any other support desned necessary by the ED/IED.

5.4 Evacuation of-the OSC- .

If'the airborne radiation levels exceed 100FR20, Appendix B, Table 1 ltnits or the general area radiation-levels exceed 100 mr/hr in the OSC, the following actions will be taken:

PAGE 5 0F 7

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EPP-016 REVISION 3 4/26/83

.m l

i.

-1 5.4.1 The OSc will b.e transferred to a location designated .

by the ED/IED. The ED/IED will designate any personnel who must renain in the OSC.

55 Activation of the Health Physics Lab (HP Lab).

551 Upon declaration of an Alert, Site Energency, or General &nergency the following personnel shall peoceed to the HP Lab:

A. Inplant HP Support (2)

B. Offsite Survey Team (2)

Onsite Survey Team (1)

.t C.

552 At the discretion of the Radiological Assessnent Supervisor, a radiological survey is performed to detennine the habitability of the HP Lab. If tha general area radiation dose rate is greater than 100 mr/hr or airborne levels exceed 10CFR20, Appendix B, Table 1 limits the HP Lab shall be evacuated per Section 5.6 of this procedure.

5.5.3 A personnel accountability check shall be performed.

5.5.4 The Radiological Assessment Supervisor shall report to the ED/IED when the Radiological Monitoring temn(s) is/are ready to perform their support function.

5.5 5' Upon the request of the ED/IED, the Radiological Monitoring Group shall provide in-plant and I out-of-plant survey teams, personnel to accompany OSC support teams into the plant, and any other support desned necessary by the,ED/IED.

5.6 Evacuation of the.HP Lab:

i If the airborne cadiation levels exceed 10CPR20, Appendix B, I

Table 1 ltnits or -the general area radiation levels exceed 100 mr/hr. in the HP Lab, the following actions shall be taken.

5.6.1 The ED/ Radiological Assessment Supervisor shall designate the personnel required to stay in the HP Lab. ,

5.6.2 The remainder of the personnel shall proceed to the Technical Support Center (TSC).

g &

PAGE 6 0F 7

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4 EPP-016 REVISION 3 4/26/83

. . . ...s' '

i i >'

57 Activation of the Energency Operations Facility (EOF) - News .

Media Area (NMA), will be in accordance with "CEMP" and CEP-001.

5.8 Attachnent I provides general infonnation reg'arding the interface between the onsite and offsite energency '

organizations.

59 Attachnent II provides guidelines for the responsa of the oncite emergency organization; duty stations and basic responsibilities.

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EPP-016~ ,

ATPACIMENP I '

PAGE 1 (F 1 REVISICN 3 Bnergency !.

Control 0

' F Officer e

OFFSITE' .

1 EMEFOIDEN I.

EMB1GENCY _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ .___

i IECIMICAL CONIFIDL OPERATIONS EMSlGENCY SUPPORT CENIH1 ROOM SJPPORT Ca mut

, OPERATIONS FACILITY ASST. M R. RAD. ASSP. M R. OPERATIONS 4 : TECHNICAL AR9RR999fI OPER/.TIONS SUPPORT CENIH1 SUPPORT SUPERVISOR suler SUPERVISOR i

. TEEHNICAL CONsnt0CTION/

SU, N FDIE HlIGAIE 1, SUPPORT REPAIR PLAMP RAD COORDINATOR COORDINATOR SYSPEM AR9RR94ENI G M1ATORS FIRST AID

. & . & AR9ER965ff FERS0telEL & OPERATIONS STAFF STAFF PERSONNEL AUXILIARY OPERS. SUPPORT

. PEDIA SECURITY IDEHQ. REPAIR :

COORDINATOR COORDINATOR I 8

GENERAL OFFSITE RAD l

SERVICES MONFIORING *

1. COORDINATOR COORDINATOR EDF FEDI11AL, STATE

,, C019(JNICA100 IDCAL . FIGURE 5-5 OFFICIALS INPERFACE BETNEEN Oct. 1981 i!

ONSITY/0FFSI'IE ,

Hev. 5 EMERGENCY OPDtATIONS I

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l' ' SOUTH CAROLINA ELECTRIC AND OAS COMP,AN,Y VIRGIL C. SUMMER NUCLEAR STATION

. NUCLEAR OPERATIONS nCR 0? ERAT!0NS COPY No.. . . . . . . . . . . . ZIf. . . . . .

EMERGENCY PLAN PROCEDURE EPP-017 POST-RECOVERY AND RE-ENTRY REVISION 3 .

APRIL 26, 1983

- Non-Saf'ety Related Reviewed by:

%A a .Mkb

/ DAte ORIGINATOR tof this revision)

$2LilD DISCIPLINE SUPERVISOR Gdrs Date Approved: .

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Tat'e PLANT I4ANAGER Date Issued:

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4 EPP-017 PAGE 1 REVISION 3 4/26/83

. LIST OF EPPECTIVE PAGES _

~

P,a age _ .

Revision l 1 -3 11--

3

- 1 -3 2 3

. 3 3 .

4 3

. 5 3 6' 3 7 . 3 l ,

l ATTACHMENTS

' \

! -_/ Attactment I 3' i;

1* .

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. . . . . . . . . . _ . ac . ____. .._ . _ . . . _ _ _ _ _ ._1.-__.. .

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~EPP-017.

PAGE 11 REVISION-3

( ,

. . . 4/26/83 TABLE OF CONTENTS-P, a_ge, ,

. List'of Effective Pages i .

1.0 PURPOSE 1

2.0 REFERENCES

1

.3 0. CONDITIONS AND PREREQUISITES 1 4.0 PROCEDURE 2

ATTACHMENTS .

Attachnent I - Recovery Organization

\

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,1_

EPP-017 REVISION 3 4/26/83

'~

1.0 PURPOSE 1.1 To provide. guideline's for the following emergency actions:

1.1.1 Re-entry into affected areas of the plant.

1.1.2 Initial recovery operations to the establishment of the Long Term Recovery Organization.

2.0 REFERENCES

2.1 " Virgil C. Summer Nuclear Station Radiation Bnergency .

Plan". .

, 2.2 NUREG-0654, Criteria for Preparation & Evaluation of

-Radiological Snergency Response Plans- & Preparedness in Support of Nuclear Power Plants.

2.3 EPP-016.Bnergency Facilities Activation and Evacuation 2.4 EPP-020 Energency Personnel Exposure Control.

2.5 HPP-160 Control and Posting of Radiation Control' Zones.

\

3.0 CONDITIONS AND PREREQUISITES 3.1 Inmediate corrective and protective actions have established an effective control over the emergency condition.

3.2 Radiological conditions for affected-areas within the plant

- have 'been determined.

33 Plant personnel, who have completed the onsite radiation control and Safety Training Program and are eligible to receive energency dose rates as delineated in EPP-020, are

.available.- ,

34 Extended actions are necessary to return the plant-to its.

normal operating statu,s and the following recovery phase criteria have been met:

3.4.1 Radiation levels in all in-plant areas except waste processing systems are stable or decreasing with time.

3 4.2 Releases of radioactive materials to the environment from the plant are under control or have ceased.

3.4.3 . Any fire, tornado or similar energency condition is ,

controlled or has ceased.

PAGE 1 OP 7 .

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EPP-017 REVISION 3 4/26/83 3.5 All Post-Recovery and Re-entry activities will be carefully

, planned and reviewed prior to implementation of any such activities. i l

4.0 PROCEDURE ,

4.1 Planning of Re-entry Operations.

4.1.1 Review the following data prior to authorizing-re-entry by the energency teams:

A. Radiological surveillance data to determine plant areas potentially affected by high levels .

of radiation and contanination.

B. Current radiation exposure of emergency personnel who will participate in the re-entry operation.

C. Environmental conditions such as temperature, gases, snoke that. the re-entry teen will ,

encounter.

4.1.2 Preplan the activities of the Re-entry Teams taking the following items into account: s

s.

NOTE: Since it is not possible to anticipate, in advance, all the conditions that may be encountered in any energency situation, the recovery plan must be flexible enough to

- allow for any unanticipated occurrences and/or conditions encountered during the recovery operation.

1 A. Areas to be surveyed B. Anticipated radiation and contamination levels C. Adequacy of radiation survey instrumentation and equignent shall be reviewed. Additional

~

equipnent which may be needed to effect the recovery /re-entry will be made available by emergency operation facility.

J.

t **

PAGE 2 0F 7 s O

., . ~ . - . - . . . . - . _ . . . . . .

t EPP-017 REVISION 3 -

, 4/26/83 D. Shielding requirements and availability E. Protective clothing and equipuent required F. Access control procedures G. Decontemination requirements

. H. Communications I. Exposure control limits, personnel dosimetry requirements, and allowable exposures J. Route to-be followed ,

< 4.1.3 Designate a Re-entry Team which should consist of the following personnel:

A. Appropriate Technical / Operations / Maintenance Personnel - 3 (As per EPP-016 Att. II).

. B. Health Physics - 1 ,

NOTE: Ensure that each member 'of the temn has sufficient exposure reuaining to complete the re-entry procedures and not exceed the normal Virgil C. Sumner ' exposure Ibnits. (Re: Section 3.3) 4.2 Actions to be Accomplished During Initial Reentry.

4.2.1 Give the members of the emergency team the following l instructions:

A. Do not deviate from the planned route unless unanticipated conditions are encountere:.d.

B. If dose rates encountered during re-entry are significantly greater than anticipated, reentry personnel shall re' turn to a safe area and contact the anergency Director for further instructions.

4.2.2 Instruct the members of the Re-entry Team to assess the following items in the specified priority:

PAGE 3 0F.7 c e es o. * * * . .-,

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EPP-017

. REVISION 3 4/26/83

. A. Determination of initial required recovery operations including assessnent of equipnent danage.

B. Determination of real or potential hazards associated with the required recovery operation..

C. Without delaying the mission or causing unnecessary exposures, the Re-entry Team should monitor the dose rate along the route followed to obtain as much radiological information as -

i possible.

4.2.3 After reentry procedures have been completed, the Re-entry Team will:

A. Follow established selfenonitoring and personnel decontanination procedures, as necessary, under the supervision of the individual charged with health physics monitoring of the Re-entry Team.

B. ' Record and report to the Energency Director the radiological conditions and danage assessments in the emergency area.

C. If possible, areas of contaminationtshall be isolated and posted with appropriate warning' signs. These areas will be posted in accordance with ref. 2.5 - Portable shielding materia) should be used whenever practical.

43 Evaluation of Conditions 4.3.1 The ED/0EC will evaluate the radiological conditions and the danage assessment; report, and then determine:

A. The areas that have been arrected by the energency.

B. What must be done to restore the station to normal conditions.

C. Radiological controls to be instituted.

D. Personnel, equipment, and ttne required.

4.4 Recovery 4.4.1 During recovery operations, station supervisory personnel will take the action necessars to ensure that:

PAGE 4 0F 7

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EPP-017 REVISION 3 4/26/83 O t .A.

Recovery and clean ,up techniques are in accordance with good health physics practices i -

and procedures..

B. Personnel radiation exposure during the recovery stage-of the incident is closely controlled and docunented. Individual exposures shall be in accordance with administrative linits, where possible.

C. Recovery activities and repairs are properly documented and controlled.

D. Test programs to confirm fitness of equipnent '

for return to service are developed and

- executed.

4.4.2 Based upon the extent of the energency, long-term recovery operations may be required. The Bnergency Director will notify the Offsite Emergency Coordinator and make recannendations - as to the establishment of the Long Term Recovery Organization.

4.4.3 Recovery Organization (See Attachnent I)

(3s j A. The Offsite Energency Coordinator, with .

2 concurrence by the Energency Control Officer and

- Buergency Director will shif t 'f rom an anergency -

Organization to a Recovery Organization. When a Recovery Organization is implemented, 'the Of fsite Emergency Coordinator will inform appropriate offsite agencies.

B. The Recovery Organization will depend upon the nature of the accident and the situation after the accident. A general organization is shown in Attachment I. Specific organizational structure and staffing of the organization will be the responsibilty of the Energency Control Officer. He will' also determine the required scope and function of the recovery organization.

The Emergency Control Officer is the Vice President,_ Nuclear Operations.

C. The Recovery Manager, the General Manager,

- Nuclear Operations, will be responsible for recovery activities, including technical decisions and courses of action. He will-coordinate the functional activities of the various groups.

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EPP-017-

' REVISION 3 T,

4/26/83 !

D. The Technical Support Manager, Group Manager, Nuclear Engineering and Licencing, is responsible for recovery activities including analysis'and the developnent of. plans and proc?dures in direct support of Plant Operations personnel with the ,

objective of taking the plant to a safe shutdown

& condition in a manner which minimizes the effect on

-

ML20080M288

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