Text

Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures EPP-001 Re Activation & Implementation of Emergency Plan & EPP-004 Re out-of-plant Radiological Survey.Revised Table of Contents Encl
	ML20041A317
Person / Time
Site:	Summer
Issue date:	01/19/1982
From:	; SOUTH CAROLINA ELECTRIC & GAS CO.
To:	;
Shared Package
ML20041A313	List: ML20041A312; ML20041A316; ML20041A317;
References
	PROC-820119-01, NUDOCS 8202190420
	Download: ML20041A317 (150)
	v • d • e

Dergency Plan Procedures Instruction Sheet The followirg instructional information and checklist is beirg furnished to help insert the Iroper Revision or change into the Emergency Plan Procedures.

Discard the old sheets and insert the new sheets as listed below. Keep these instructicn sheets in the front of the Emergency Plan Procedures to serve as a record of revisions or changes.

Remove Insert Table of Cbntents Table of Cbntents EPP-001 EPP-001 EPP-004 EPP-004 EPP-010 EPP-010 EPP-012 EPP-012 EPP-018 (Change #1)

EPP-019 EPP-019 EPP-021 EPP-022 l

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PDR ADOCK 05000395 F

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PROCEDURE TRANSMITTAL FORM Sheet of I.

DATE: //

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PROC. # d' M6/ Y REV. Il d

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PERMANENT?

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NEW PROCEDURE?

REVISION?

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11.

ACTION:

(NOTE:

Details or the change to be provided on Sheet 2)

Review New Procedure Review Revision

/ Review Change REASON FOR ACTION:

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111.

WILL t ill d KE V J b 10N / Cri ANG E/ N EW PROCEDURE?

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. v Result in a violatian of Technical Specifications?

I Result in significant increased personnel radiation exposure?

,h Represent an unreviewed safety question?

A Result in reduction of the mardin of safety to the public, environment or plant personnel?

X Violate the provisions established in the FSAR concerning operation and accident analysis?

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IV.

REQUIRED REVIEW AND COMME 41 RLSOLUTION:

Due Date:

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REVIEWED BY (AP)

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COMMENTS VIA TELECON,DATE/ TIME

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FINAL APPROVAL:

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Green - Q A Copy L

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Page of CHANGE / COMMENT FORM DATE:

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PAGE 2 REVISION O 5/22/81

()

4.1.1 The Manager, Nuclear Operations / Education and Training is responsible for coordinating the training of all Virgil: C.

Summer Nuclear Station personnel.

4.1.2 The Manager, Nuclear Operations / Education and Training may delegate the training responsibilities to those personnel qualified to teach a specific cubject.

4.1.3 Lesson plans should be provided for each instructor's program and the designated instructor will be responsible for identifying and ccrrecting weak areas within his part of the training program.

4.1.4 All on-site and off-site Virgil C. Summer Nuclear Station staff listed in the Training Groups and Associated Training Requirements (Attachment I) shall be required to attend, on an annual basis, a training session covering a review of the Emergency Plan and Emergency Plan Procedures.

4.1.5 All non-essential personnel, including contract people, shall receive Emergency Plan training, on an annual basis, as part of the General Employee Training Program, AP-1101.

()

4.1.6 All off-site emergency organizations listed shall be invited, on an annual basis, to attend an Emergency Plan and Emergency Plan Procedure Training Program per the requirements of Attachment I.

4.1.7 Tests may be administered to, attendees as deemed applicable by the instructor.

These test may be written or oral tests.

A minimum grade of 70% shall be considered.a satisfactory performance.

4.2 Emergency Plan Drill and Exercise Development 4.2.1 The Emergency Coordinator is responsible for the planning, scheduling and coordination of all emergency planning related drills and exercises, with assistance provided by other groups and individuals, such as the Nuclear Training Coordinator.

4.2.2 All drills and exercises are approved by the Station Manager, with the exception of the Annual Radiation Emergency Drill which shall be approved by the General Manager Nuclear Operations.

1 4.2.3 The following is the sequence of events for the development and implementation of drills and exercises:

A.

Determine the type of drill to be held and the date and time that it will occur.

!$ESb2Epek0r Oo"$be ob0urbhncN"ob the"emOhge$ chb""

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1/19/82 VIRGIL C. SUMMER NUCLEAR STATION

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NUCLEAR OPERATIONS PROCEDURES EMERGENCY PLAN PROCEDURES TABLE OF CONTENTS PROCEDURE DATE NUMBER PROCEDURE TITLE REVISION ISSUED EPP-001 Activation and Implementation of Emergency Plan 1

1/19/82 EPP-002 Communication and Notification 0

12/1/81 EPP-003 In-Plant Radiological Surveying 0

12/1/81 EPP-004 Out-of-Plant Radiological Surveying 1

1/19/82 EP P-005 Offsite Dose Calculations 1

1/19/82 EPP-006 Emergency Reactor Coolant Sampling 0

12/1/81 EPP-007 Environmental Monitoring 0

12/1/61

(~} EPP-008 On-Site Assembly 0

12/1/81 V

EPP-009 On-site Medical 0

12/1/61 EPP-010 Personnel / Vehicle Decontamination 1

1/19/82 EPP-011 Personnel Search and Rescue 0

12/1/81 EPP-012 Onsite Personnel Accountability & Evacuation 1 1/19/82 EPP-013 Fire Emergency 0

12/1/81 EPP-014 Toxic Releara 0

12/1/81 EP P-015 Natural Emergency (Earthquake, Tornado) 0 12/1/81 EPP-016 Emergency Facilities Activation & Evacuation 0 12/1/81 EPP-017 Post-Recovery and Re-Entry 0

12/1/81 EPP-018 Emergency Training and Drills 0

12/1/81 EPP-019 Emergency Equipment Checklist 1

1/19/82 EPP-020 Emergency Personnel Exposure Control 0

12/1/81

-]* Safety Related Procedure s_,

SOUTH CAROLINA ELECTRIC AND GAS COMPANY VIRGIL C. SUMMER NUCLEAR STATION NUCLEAR OPERATIONS MUCLEA'R 03ERATONS COPY N0......N Z E EMERGENCY PLAN PROCEDURE EPP-001 ACTIVATION AND IMPLEMENTATION OF EMERGENCY PLAN REVISION 1 JANUARY 7, 1982 NON-SAFETY RELATED O

Reviewed by:

U 15

/ f 9%

Ohl11NATOR (ofthis revision)

/ Dite

/ l' PL--

QUALtFIED E E EWER

' Date Approved:

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63 PL

' MAN AGER /

(date Date Issued: JAN.1 91982

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Form AP-101-2, (1/80) g DAW CHAIRMAN d

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EPP-001 PAGE 11 REVISION 1 1/7/82

,,(/

TABLE OF CONTENTS Page List of Effective Pages i

1.0 PURPOSE 1

2.0 REFERENCES

1 3.0 CONDITIONS AND PREREQUISITES 1

4.0 PROCEDURES 1

4.1 CLASSIFICATION OF EVENT 1

4.2 1MPLEMENTATION OF EMERGENCY PLAd 1

4.3 UNUSUAL EVENT 1

4.4 ALERT 2

4.5 SITE EMERGENCY 4

4.6 GENERAL EMERGENCY 6

(~h

\\ ATTACHMENTS Attachment I Emergency Action Level Summaries Attachment II Immediate Actions Summary

(~)h

r Mc ukr-NUMBCR PROCEDURE TITLE REVISION ISSUED hPP-021 Activation of the Early Warnint; Siren System (EWSS) 0 1/19/82 EPP-022 Verification of Communications Operability 0

1/19/82O G'

1 l

l l

l EPP-001 PAGE i REVISIOfl 1 1/7/82 LIST OF EFFECTIVE PAGES h

PAGE REVISIOII i

1 11 1

1 1

2 1

3 1

4 1

5 1

6 1

7 1

6 1

9 1

10 1

ATTACHMENTS Attachment I Pages 1 thru 13 1

Attachment II 1

O O

EPP-001 REVISION 1 1/7/82 1.0 PURPOSE O

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 Plan."

2.2 NUREG-0654, Criter'ia for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants.

3.0 CONDITIONS AND PREREQUISITES 3.1 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 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 g

implementation of the Emergency Plan; whereas a large release W

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.

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

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 exceeded.

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.

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 plan condition.

O PAGE 1 of 10

EPP-001 REVISION 1 1/7/82

/~'T 4.2 The Shift Supervisor shall:

'vl 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 tnis procedure.

Unusual Event (Section 4.3) or Alert (Secticn 4.4) or Site Emergency (Section 4.5) or General Emergency (Section 4.6) 4.3 Unusual Event 4.3.1 Immediate Actions:

(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 to all plant personnel over the plant paging system.

ATTENTION ALL PERSONDEL:

THE STATION IS IN AN UNUSUAL EVENT CONDITION.

THE INITIATING EVENT IS NOTE:

[ REPEAT ANNOUNCEMENT].

B.

Notify the Security Shif t 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.

E.

Ensure that the Emergency Log is established and maintained, fG PAGE 2 of 10

EPP-001 HEVISION 1 1/7/82 F.

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

lll NOTE:

Consideration should be given to access routes taken.

4.3.2 Follow-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 Summary, 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 to all plant llI personnel over the plant paging system.

ATTENTION ALL PERSONNEL:

THE STATION IS IN AN ALERT CONDITION.

THE INITIATING EVENT IS ALL EMERGENCY RESPONSE PERSONNEL REPO'r'T TO THEIR STATIONS.

B.

If necessary, sound the Radiation Emergency Alarm.

NOTE:

[ Repeat the Alarm and Announcement].

C.

Notify the Security Shift Leader to implement appropriate security measures.

D.

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

O PAGE 3 of 10

EPP-001 REVISION 1 1/7/62 r3 E.

Ensure that the Initial Notifications are completed

(_)

per EPP-002.

F.

Ensure that the Emergency Log is established and maintained.

G.

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

NOTE:

Conaideration should be given to access routes taken.

H.

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

I.

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.

A) k-C.

If the radiation emergency alarm is initiated, all Personnel in the Radiation 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 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 conditions not

(~S covered by procedures.

%)

PAGE 4 of 10

EPP-001 REVISION 1 1/7/82 F.

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

4.4.4 Final Actions:

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 emergency or down-grade of the emergency classification.

B.

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

4.5 Site Emergency 4.5.1 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 g

following:

W 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 STATIONS.

ALL NON-ESSENTIAL PERSONNEL EVACUATE THE SITE PROCEED TO B.

Sound the Radiation Emergency Alarm.

NOTE:

[ Repeat the alarm and announcement]

O PAGE 5 or 10

EPP-001 REVISION 1 1/7/82

(~s C.

Notify the Security Shift Leader to implement appropriate security measures.

D.

Notify the Fairfield Pump Storage Facility of site evacuation.

E.

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

F.

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

G.

Ensure that the Emergency Log is established and maintained.

H.

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

NOTE:

Consideration should be given to access routes taken.

I.

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

J.

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):

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.

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.

4.5.3 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.

O) m PAGE 6 of 10

EPP-001 REVISION 1 1/7/82 C.

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

D.

Make assignments to h'is 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).

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, g

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 down-grade of the emergency classification.

B.

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

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 accomi lish or cause to be accomplished the following:

A.

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

O PAGE 7 of 10

EPP-001 REVISION 1 1/7/82 q(_-

ATTENTION ALL PERSONNEL:

THE STATION IS IN A GENERAL EMEEGENCY CONDITION, THE INITIATING 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.

NOTE:

[ Repeat the Alarm and Announcement].

C.

Notify the Security Shift Leader to implement appropriate security measures.

D.

Notify the Fairfield rump Storage Facility of Site Evacuation.

E.

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

(\\')

F.

Notify local authorities of the VCS recommendations regarding activation of the Early Warning System (EWS).

G.

Upon direction by local authorities, request the Shift Supervisor to activate the Early Warning System.

H.

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

I.

Ensure that the Emergency Log is established and maintained.

J.

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

NOTE:

Consideration should be given to access routes taken.

K.

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

L.

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

O Y_)

PAGE 8 of 10

EPP-001 REVISION 1 1/7/82 4.6.2 Immediate Actions (All other personnel):

O A.

Emergency Response Personnel report to their designated stations.

D.

Non-essenti-1 personnel evacuate the site, proceed to their privame residence or offsite holding area as designated by the ED, await further instructions.

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.

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 llI 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, Alert, 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 cown-grading of the General Emergency condition, the ED shall ensure that offsite authorities are:

O PAGE 9 of 10

s EPP-001 REVISION.1 j

1/7/82 l g 1.

Notified verbally by normal emer6ency l

communications.

j 4

l 2.

Provided with a written summary within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months of i

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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1 9

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O PAGE 10 of 10

WEROEtCY ACTION LEVELS SLNMARY EPP-001, ATTACW EMT I PAGE 1 of 13, REVIStGN 1 SITE GENERAL SYSTEM ltav0LVED UNUSUAL EVENT ALERT EMERGENCY EtzfRGENCY HEACTOR INI T I AT i t0 COtol T ION INITIATitG CONDITION INITIATit6 CO*OITION INITIATING CONDITICN COOLANT EXCEEDING TECHNICAL SPECIFICATION RAPID FAILURE OF SEVERAL STEMt KNOWN LOSS-OF-COOLANT ACCICENT SM ALL Am LARGE LOCAs WITH t AttlHE SYSTEM FH IM ARY TO SECONDARY m PRIMNtY GENERATOR TUBES (e.g., SEVERAL (LOCA) GREATER THAN CHARGING PUYP CC t'CCS TO PERFORM LEAutNG TO SYSTEM LEAF RATES HUNDRED GPM PRIMARY-TO-SECONDARY CAPACITY.

SEVEoE cme DEGRADATION OR MELT.

LE AX RATE).

ULTIMATE FAILURE OF RE ACIm Detection Method:

Detection Method:

BUILDING POSSIBLE FOR *WLTDOWN Pr imary to seconjary leak rate Detection Method:

' Pressurizer low pressure reac+e:

SEQUEPCES.

gr eater than 1 gra total for score tr!p; ag than 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or greater than 500 Pressur i zcr low pressure al arm anc Pressur i zgr low pres Ara safety Cetection Method:

gpd ter steam generator as reactor tr ip; g inject wn shna6, og iden tl f led by daily RCS leakage Pressur i zer low level alarm; aj High Reactor Pullding pressure, Saf ety injection sf gnal with evaluation; g RM-A9, G19A, Gl98, G19C high and reacto-trip; and Frimary sys tem teak rate greater alarm; g High Reactor Buttding mump level

1) Statts la9ps a nd !cate saf ety than those specified in Technical Stea-i genorator water level g

injection end Rm pJnps not Speci f icat ion 3.4.6.2 as identi fied rapidly increasing in one or more High Peactor Buf f ding humidity; runninj: or by dally FCS leakage eval uat ion, steam generator (s), falling in the g

2) Flow Indicefors f or Saf ety others; g RM-A2 high alarm injection Systeri read zero; g

1) > 0 pressure boundary leakage RM-L3, fN-L7, FN-L10 high al arms; RT-5, RMG-7, R*1G-13, high al arm; 1nd RM-A2 high alarm;

2) > 1 gpm unidentifled for rore and than 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Possible lifting of steam INITIATING CONDITION

3) > 10 9pm ident if lod RCS t eakago generator IHV's and/or safety RAPID FAILURE OF SEVERAL STEAM f or nor e 1han 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months s.

vaivos.

GENERA;CR TUBES (SEVERAL HUNDRED

4) > 30 gpm control lod leakage GPM PRIMARY-TO-SECONDARY LEAX tNITIATING CONDITION RATE) WITH LOSS OF OFFSITE PCWER.

SMALL INA AND INITIALLY SUCCESSFUL br s. ) _

psig or more than 4 (2235 + 20 INITIATING COtolTION ECCS. SUBSEQUENT FAILLHE OF REACTOR COOLANT LE/XAGE RATE Detoction Method:

HEACTOR BUILDING HEAT REMOYAL EXCEEDS 50 GPM.

SYSTEMS OVER SEVERAL HOURS COULD INITIATING CONOtTION Pressurizor low pressure alarm and LEAD TO CORE MELT AtO POSSIBLE Auto NAL REACIOR COOLANT TEMP.

Detection Method:

reactor trip, or pressur i zer level FAttlRE OF THE REACTOR BUILDING.

Ato/OH FRES$URE OR ABNORMAL F0EL rapidly decreasing g TLMPERATtFE THAT WOULD INDICATE A

1) Excessive Reactor Make-up to Pr ess ur i zer low-level alarm; aQ Detection Method:

LOSS OF SUBCOOLim MARGIN OR the Volume Control Tank RM-A9, G19A, G199, G19C high alarm; Pressur izer low pressure reactor g OVERfHESSURIZATION.

2) STP-114.2 ag Undervol tage alarms on IDA and trip; and l

Detection Method:

109 buses, and Pressurizor low pressure safety

1) Reactor Coolant Tavg greater Steam Generator water tevel injection signal ag than 590*F; or rapidly increasing in one or more

1) Rtit flow indicators show zero

2) RCS pressure greater than 2310 steam generators, falling In the flow after shift to RHR is psig; or other s; and attempted and for greater than 2

3) RCS pressure less than 1765 RM-L3, FN-L7, FN-L10 high alarm; br. Subsequently and, RCS psig; and coru exit imperature and tnrporature rising, greator than 620*F as Indicated by

2) Reactor Building spray and a valid incore thormocouple.

Possible f if ting of steam genera-Reactor Building c!r handling

4) Coro subcooling monitor less for PRV's and/or saf ety valves.

system fall to f unct ion.

than 50*F.

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h EMERGEtCY ACTIOJ LEVELS StfetARY EPP-001, ATTACINEhi'l PAGE 2 of 13, REVISION 1 SYSTLM SITE GENERAL INYOLVED UNUSUAL EVENT ALERT EMERGENCY EMERGENCY STLAM INITIATitsi CONDITION INITIATING CONDITION INITIATING CONDITION SYSTEM RAPID SECONDARY SYSTEM MAJOR STEAM LINE BREAK (e.g.,

MAJOR STEN 4 LINE BREAK WITH DEPR ESSUR IZ AT ION.

CREATER THAN 6 IN. EQUIVALENT GREATER THAN 50GPM DIAMETER) WITH A SIGNIFICANT PRIMARY-TO-SECONDARY LEAKAGE AND Detection Method:

PRluARY-TO-SECOtOAPY LEAK RATE.

INDICATION OF FUEL DAMAGE.

Increased steam flow; M Detection Method:

Detection Method:

Reduced RCS temperature and pressure; and Rapidly decreasing reactor Rapidly decreasing reactor Observation of break or steam dump, coolant Tavg pressur izer Coolant Tavg

relief or safety valve pressure, and pressurizer level; pressurizer pressure and inadvertently opened.

g RH-L3, R4-L7, R4-L10 high pressurizer level alarms; and

1) Steam line differential

1) Steam line differential pressure safety injection pressure, safety injection signal; g High Reactor signal; eM Building pressure alarm; High Reactor Building and RM-A2 high alarm for pressure alarm and RM-A2 higt rupture In Reactor Building alarm M

-OR-FaIIed Fue! Monitor A1 arm for

2) High steam flow and Lo-Lo rupture in Reactor Building T,yg or low steam og_

pressure safety injection

2) High steam flow and Lo-Lo signal for rupturo downstrear Tavg or low steam pressure of MStV's.

safety injection signal M RM-A9, G19A, Gl98, G190 high alarm a d Failed Fuel Monitor INITIATING COtJOITION high alarm RAPID GROSS FAILURE OF ONE STEAM GENERATOR TUBE WITH LOSS OF OFFSITE POWER.

Detection Method:

Pressurizer low pressure alarm and reactor trip; a d Pressurizer low leval alarm; a d RM-A9, Gl9A, Gl90, Gl9C high l

alarm a d Pl esst -izer low pres-I sure safety injection signal; ag Undervoltago alarms on 10A and IDB busos; M tei-L3, RM-L7, RM-L10 high alarms

04ERGENCY ACTION LEVELS

SUMMARY

EPP-001 ATTACtN et7 i 0

PAGE 3 of 13, REv f SIGN !

SYSTEn SITE GENERAL ltevot VED UNUSU AL EVENT ALERT EMERGENCY EMERCENCY RADIOLOGICAL INITIATING CONDITION SUSTAINED HIGt RADI ATION LEVELS G; INITIATING CONDITION INITIATING CONDITION E F FLtE NT S GASEOUS EF FLUENT INSTANTANEOUS HIQi AIRBOPNE CONTAMINATION WHICH RADI ATION MONITORS DETECT LEVELS EFFLUENT MONITORS DETECT LEVELS RELEASE RATE TECHNICAL INDICATES A SEVERE DEm ADATION IN CORRESPONDING TO CREATER THAN 50 CORRESPONDING TO 1-REM /HR WHOLE BODY SPECIFICATION LIMITS EXCEEDED FOR 1 THE CONTROL OF RADIOACTIVE MREM /HR WHOLE BODY FP 0.5 HP. m OR 5-REM /HR THYRolD AT THE HR.

(APPENDIX B TABLE II, COLtJ4N 1 MATERIALS (e.g.,

INCREASE OF GREATER THAN 500 MREM /tR WHO.E EXCLUSION AREA BOUNDARY UNDER ACTUAL 10CFR20)

FACTOR OF 1000 IN DIRECT RADI AT10h BODY FOR 2 MIN. (OR FfvE TIME %

METEOROLOGICAL CONDITIONS.

READINGS).

THESE LEVELS TO THE THYRotD) AT Detection Method:

THE EXCLUSION AREA BOUNDARY FOR Detection Method:

Detection Method:

ADVERSE METEOROLOGY (PASQUILL F Anjt of the following gaseous STABILITY, IM/SEC WIND VELOCITY).

1) Radiation Monitor levels exceed of f l ueret moni tors in valid alarm

1) Unexpected RMG readings as those specified for Site Emergency; mode for more than I hr.:

follows:

Detection Method:

and_

a) RMG 2-4, 6-13, 16: greater

2) Calculation on Dose Assessment R4-A3 fc4-A9 than 2.5 R/hr Any of the following valid Forms ind icates lovels exceeding la4-A4 RM-A10 b) RMG 7, 17A, 1 78, 18 greater atmospheric radiation monitor 1-rem /hr whole body or 5-rom /hr R4-A13 than 100 R/hr readings:

thyroid at the exclusion area Rr4-A 14 c) RMG-1 : greater than 1 R/hr

1) RM-A3, RM-A4, RM-A9, RM-A10, boundary using radiation monitor (due to radloactivity releases to RM-A13, RM-A14 readi ngs and readings and effluent stream flow the environment)

2) Unexpected plant area Iodine or analysis shows equivalent 1-131 rates (measured or assumed) for particulate airborne concontrattor release rate greater than 1.14 actual meteorological conditions; greater than 1000 MPC.

Cl/hr for 0.5 hr or greater thar or measured in-si tu.

(as per 10CFR20 Appendix B, Table 11.4 CI/hr for 2 minutes, l)

2) RM-A3, RM-A4, Rft-A9, Rm-A10, RM-A13, RM-A14 readings and analysis shows equivalent Xe-133 release rate greator than 409 Cl/hr for 0.5 hr or greater than 4890 CI/hr for 2 minutes (CONTINUE ON NEXT PAGE)

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b D4ERGENCY ETbf LEVELS

SUMMARY

EPP-001, ATTACFNER1 PAGE 4 of 13, REVISION 1 1

SYSTEM SITE GENERAL INVOLVED UNUSUAL EVENT ALERT EMERGENCY EMERGENCY R ADIOLOGICAL INITIATING CONDITION INITI ATitG COrolTION INITI AL C0tolTION EFFLUENTS.

LIQUID EFFLUENT COrCENTRATIONS RADIOLOGICAL EFFLUENT RELEASE RATE DOSE RATES LISTED BELOW ARE (CON'T)

TECi1NICAL SPECIFICATIONS LIMITS EXCEEDING 10 TIMES TECINICAL FROJECTED BASED ON GAMMA RADIATION EXCEEDED t0R 15 MIN.

(APPEtoix B SPECIFICATION INSTANTANEOUS MONITOR (RMG) READitGS AND/OR TABLE 11 COLUMN 2 10CFR20).

LIMITS.

OTHER PLANT PARAMETERS OR ARE.

l Detection Method:

MEASURED AT THE EXCLUSION AREA i

Any of the following valid liquid Detection Method:

BOUNDARY.

{

effluent monitor readings for longer than 15 min. which are Any of the following valid Detection Method:

greater than:

radiation monitor readings for longer than 15 minutes

1) Reactor Building leak rate RM-L5: high alarm setpoint results in calculated dose RM-L9: established in a) 10 times alarm setpoint for rate at exclusion area discharge permit; and boundary greater than 50 Isolation valve falls to PN-A3 RM-A9 RM-A13 mrem /hr whole body for 0.5 hr; l

close;

. FN-A4 RM-A10 RM-A14 or or 500 mrem /hr whole body for 2 HM-L3: while steam generator b).RM-L5 10 times alarm min.

RM-L7: blowdown 15 FN-L9 setpoints established IN-LI O: directed to the nuclear in discharge permit and 2).. Rad iation Monitoring Teams blowdown system

. Isolation. valve falls measures dose rates greater and Isolation valves fall to close g than 50 mrem /hr for 0.5 hr or 1

to close (due to greator than 500 mrom/hr for 2 radioactivity releases to FN-L3 10 times alarm min. (beta + gamma) at the the environmont).

FN-L7, setpoints while stem exclusion area boundary; g generator blowdown Is.

directed to the nuclear 3) Radiation Monitoring Teams blowdown system and measure thyroid dose rates isolation valves fall (equivalent 1-131 i

to close (due to concentrations) greater than:

i radioactivity reloases i

to the environment).

a) 250 mrem /hr (1.3x10-7 Cl/cc for 0.5 hr; or

.b) 2500 mrem /hr-(1.3x1D 3

I Ci/cc) for 2 min at the exclusion area boundary.

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EMERGEtCY ACTION LEVELS

SUMMARY

EPP-001 ATTACit4ENT I 0

PAGE 5 of 13, PEVISION 1 SYSitM SITE GENERAL INVOLVfD UNUSUAL FVENT ALERT EMERGENCY EMERGENCY FULL INITIATitG CONDITION INITIATING CONUITION INITIATING CONDITION INITIAllNG CONDITION DAMAGE FUEL DAMAGE INDICATION.

POSS10LL FUEL DAMAGE.

DEGHADED CORE WITH POSSIBLE LOSS LOSS Ci TWO OF THREE FISSION OF C00LABLE CE04ETRY.

PRODUCT BARRIER WITH POTENTI AL Detection Method:

Detection Method:

LOSS OF THE THIRD BARRIER (e.g.,

Doso equivalont 1-131 activity Detection Method:

LOSS OF FUEL INTFCRITY A'O concentration greator than limit ir

1) Primary coolant samplo PRIMARY COOLANT BOUNDARY APO HIGH Figure 3.4-1 of Technical Indicatos equivalent 1-131 Val la readings on incore POTENTIAL FOR RADl0ACTivlTY Specifications; concentration greater than thermocouples above 700*F, a d RELEASE FR04 CONTAltt>ENT) g 300 Cl/cc; T

nd T hot cold rapidly divering ( T rapidly Detection Method:

Gross f allM fuol detector alarm; or and Laboratory analysis which

2) Gross failed fuel detector increasing) or no T across core; indicates an increase in failed alarm and laboratory analysis and f ailed Fuel hbnitor of f scale

1) LOCf as identified in Site 6

fuol of 0.1 perco<it in 30 minutes.

which Indicates an increase Weatorthan 10 cpm)

Emergency; and Containment in toiled fuel of 1 percent ir status panel Indicatos 30 min or a total failed fuel incomplete isolation:

of 5 percent.

INITI ATit6 CONDITION

-or-MAJOR DAMAGE TO MORE THAP 1..E SPENT FUEL ASSEMBLY IN REACTOR

2) LOCA as Idontiflod in Site INITIATING CONDITION BUILDING Ort FUEL HANDLING BUILDINC Emerg on ey; ad FUEL HANDLING ACCIDENT WITH LEADING TO CLAD RUPTLEE (e.g.,

RM-A2 high al arm; and RELEASE OF RADIOACTIVITY TO LARGE OBJECT DAMAGES FUEL OR WATE0 RMG-7 and/or RMG-18 reading 4

REACTOR OR FUEL HANDLING BUILDING.

LOSS BELOW FUEL LEVEL).

greator than 10 R/hr; g Reactor Building pressure Detection Mothod:

Dotection Method:

greater than 30 pstg ;or at least 2 min.

Obsorvation of dernage to spent Observations of major damage to fuel assembly; a d more than one spent fuel assembly

3) Breach of containment intogrity (Reactor Building) or

1) RM-A2 high alarm and/or Spont fuol pool water below fuel and Indicated cladding rupture; RMG-17A, 170 high alarm af ter level a d accident in Reactor Building;

-or-

1) RM-A2 and/or RMG-17A, 173 higt

2) RMJ 6 high alarm; y alarm for accident in Reactor

4) Cose rato outsido Fuol RMG-8 high alarm; Building Handling Dullding indicates after accident in Fuel

2) RM-A6 and/or RMG-8 high alarm 100% Gap release from spent Hand ling Build ing.

for accident in Fuel Handling fuel:

Building

-and or-

5) kbre than gap activity released O

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EMERGEtCY ACTlw LEVELS

SUMMARY

EPP-001, ATTACm Eh /.

PAGE 6 of 13, REVISION 1 SYSTEM SITE GENERAL INVOI.VED UNUSUAL EVENT ALERT Et1ERGENCY EMERGENCY STATION INITIATING CONDITION INITIATING CONDITION

-lNITIATING CONDITION INITIATING CONDITION POWER TOTAL LOSS OF OFFSITE POWER OR LOS$

LOSS OF OFFSITE POWER AND LOSS Of LOSS OF OFFSITE F0WER AND LOSS Of FAILtRE & WFSITE APO ONSITE -

OF 04 SITE A-C POWER CAPABILITY ALL ONSITE A-C POWER FOR A PERIOC

'ONSITE A-C POWER FOR MORE THAN'15 POWER ALONG WITH TOTAL LOSS OF GREATER THAN 5 MINUTES MIN.

EMERGENCY FEEDWATER MAKELP CAPABILITY FOR SEVERAL HOURS..

Detection Mothod:

Detection Method:

COULD LEAD TO EVENTUAL CORE Mr.LT AND POSSIBLE FAlltRE OF THE -

Undervoltage alarms on IDA a d IDB Undervoltage alarms on IDA and

1) Undervoltage alarms on 1DA REACTOR BUILDING.

buses; ESF power supply A and/or B 108 busos, ESF PWR Supply A 100 buses; g failure Alarm, and/or B Fallure Alarms

2). ESF Power Supply A/B failure Detection Method:

alarm Undervoltage alarms on IDA and IDB.

[

. buses for greater than 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and Steam delven Emergency Feedwater INITIATING CONDITION LOSS OF ALL ONSITE D-C POWER FOR INITI ATIPG CONDITION pump falls to start.-

[

A PERIOD CREATER THAN 5 MINUTES.

LOSS OF ALL VITAL ONSITE D-C POWER Fm MORE THAN 15 MIN.

Detection Method:

D-C bus undervoltage alarms (all a_nd,ESF Povor Supply A/B D-C bus undervoltage alarms on buses);

n all buses; ESF PWR Supply A failure alarm.

and/or D Failure Alarm

+

INITI ATING COtolTION LOSS OF FUNCTIONS NEEDED F01 PLANT HOT SHUTDOWN.

1 Detection Method:

Inability to establish charging pump Injections; g inability to establish energency feedwater flow; or Inab_Illty to establish l-service water flow; and Inability to establish componont cooling water flow.

a

EMERGEtCY ACTION LEVELS StfotARY EPP-001, ATTAC*ENT l PAGE 7 of 13, REVISION 1 SYSTEM SITE GENERAL INVOLVED UNUSUAL EVENT ALERT EMERGENCY EMERGENCY E tGI NE ERED INITIATING CONDITION INITIATit0 CoralTION INITIATit6 CONDITION INillATING CONCITION S AF EGUARDS LCCS INI T I ATLD (C0t tCIDENT WITH ALL ANNUNCI ATOR ALARMS LOST.

ALL ANNUNCIATORS Ato PLANT TRANS IENT INITIATED BY LOSS OF POSITIVE Fit 0 LNG THAT INITI ATION IS C0!PUTER LOST FOR MORE THAN 15 FEEDWATER AND C0fGENSATE SYSTEMS TOT SPUR IOUS ).

Datoction Method:

MINUTES APO PLANT TRANSIENT (PRitCIPAL HEAT REMOVAL SYSTEM)

INITIATED OR IN PR0 MESS.

FOLLOWED BY FAILURE OF ENERGE'CY Detection Muthod:

Observation by operator.

FEEDWATER SYSTEM FOR EXTENDED Detection Method:

PERIOD. CORE MELTING PCSSIBLE IN Safety injection Signal veri fled by SEVERAL HOURS. ULTIMATE FAILURE red undan t Indication.

Observation of event.

OF REASTOR BUILDING POSSIBLE IF INITIATING C0tolTION CORE MELTS.

EVACUATION OF CONTROL ROOM ANTICIPATED OR RE(PJiRED WITH INITIATING CONDITION Detection Method:

INITIATING CONDITION CONTROL OF SHUTDOWN SYSTEM EVACUATION OF CONTROL ROOM AND F AILLI<E OF A fkESSURtZER OR STEAM ESTABLISHED FROM LOCAL STATIONS.

CONTROL OF SHUTDOWN SYSTEMS NOT Reactor trip on low feodwater GENERATOR SAFETY OR REllEF VALVE TC ESTABLISHED FR04 LOCAL STATl3NS flow; and, RESEAT (EXCEEDit0 NORMAL WEEPAGE).

IN 15 tilN.

Docreasing wide-rango steam Detection Method:

generator levels toward of f-scale Detoction Method:

low on all steam generators; ag Detection foothod:

Prossur Izur or steam generator I) Emergency f eedwater flow sa f ety or rol let valve opens and indicators indicate zero flow then f alls to resot as indicated Same as initiating event.

2 mi'n. after required; or by:

Same as initiating condition.

2) Status lamps Indicate

1) Pressurizer relief valvo unergency feedwater pumps not position light indicates open; running 2 min. after required; or Emergency Feodwater cannot be Wessurizer safety valve restored within 30 min, position indicator reads grooter than 1 porcont or valid dCou s t l Cal monitor lndl Cation.

2) Visual and/or aud ible Indication at vont stacks of opun stoan generator safoty or rollef valvo; or Excoss foodwater flow to and stean f low from affected generatcr.

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V EMERGEtCY ACTL/ LEVELS

SUMMARY

EPP-001, ATTACHMEr. M PAGE 8 of 13, REVISION 1 SYSTEM SITE GENERAL l tNOLVE D UNUSUAL EVENT ALERT EMERGENCY EMERGENCY EtCINEERED INITIATING CONDITION INITIATING COtDITION INITIATING CONDITION S AFEQUARDS LOSS OF ENGINEERED SAFETY FEATURE REACTOR COOLANT PUMP LOCKED ROT 0fi TRANSIENT REQUIRING OPERATION OF (CON'T)

FUNCTION REQUIRING TECHNICAL WITH FUEL DAMAGE.

SHUTDOWN SYSTEMS WITH FAILLEE TO SPECIF ICATION SHUTDOWN. (TECHNI-TRIP WHICH RESULTS IN CORE DAMAGE CAL SPEClf ICATIONS 3.3.2)

Detection Hethod:

OR ADDITIONAL FAILURE OF CORE Reactor coolant pump auto trip COOLING Ato MAKEUP SYSTEMS WHICH Detection Method:

alarm; and COULD LEAD TO CORE MELT.

1) Eng inoered Saf ety features Reactor trip on low Activation Systan found inop-coolant flow; g Detection Method:

erable Reactor coolant pump phase over current rolay actuatlon; and Roactor remains critical af ter INITIATING COtolTION RML-1 Alarm.

attempted trip ag INDICATIONS OF RADI ATION MONITOR-ING IHCCESS AND EFFLUENT PARA-

1) RML-1 alarm, o METERS WHICH REQUIRE PLANT SHUT-DOWN OR INITIATING CONDITION

2) Flow Indicators on safety LOSS OF VITAL ASSESSMENT 01 LOSS OF ALL FUNCTIONS NEEDED FOR injection system and RtR systems CU1MUNICATION EQUIPMENT SUCd PLANT COLD SHUTDOWN.

show zero flow with safety THAT THE SAFE OPERATION OF THE Injection initiated, o PLANT IS EFFECTED.

Detection Method:

3) Status iIghts show safety Detection Method 1) Loss of Rm system not functional and injection system and RHR punps Radiat on Monitoring System 2)

Inability to sustain natural or not running with safety Loss of motoorological equipment forced circulation.

Injection initiated.

3) Significant loss of conmun ica-tion capability offsite INITIATING COtolTION F AILURE OF THE REACTOR PROTECT 10t.

SYSTEM TO INITI ATE AND C04PLETE /

TRIP WHICH BRINGS THE REACTOR SlECR 1 T IC AL.

Detection Method:

Reactor ranalns critical af ter trip Initiation.

EMERCEiCY ACTION LEVELS StFMARY EPP-001, ATTACmFNT I PAGE 9 of 13 REYlSICN 1 SYSTEM SITE GENERAL I f r/OL V E D UNUSUAL EVENT ALERT EMERGENCY EMERGENCY f IRE I N I T I AT I NG CGti)l T ION INITIATING CONDITION INITIATING CONDITION FIRE LASTING MORE THAN 15 MINS.

F IRE POTENT I ALLY AF FECTING FIRE AFFECTING REDUNDANT SAFETY SAFETY SYSTEMS.

TRAINS OR FUNCTIONS.

DetactIon Mothod:

Detection Method:

Obtervation or tiro detection dev ice al arm w i t h con f i rm ing Observation of firo that could Observation of major fire that observation Ind icat ing a f ire aff et safety systems.

defeats redundant safety system lasting more than 15 min.

trains or functions.

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id EMERGEtCY ACTik_.jVELS S'J4 MARY EPP-001, ATTACtffEk,/

PAGE 10 of 13, REVISION 1 SYSTEM SITE GEf4ERAL INYOLVED UNUSUAL EVENT ALERT EMERGENCY EMERGENCY SECtEITY INITI ATING CONDITION INITIATING CONDITION INITIATING CON 0lTION INITIATING CONDITION SECtRITY TtHEAT 01 ATTEMPTED ENTR)

ONGOING SEVERE SECURITY THREAT SECURITY TtHEAT INVOLVING SECURITY THREAT RESULTING IN LOSS OR ATTEMPTED SABOTAGE.

IMMINENT LOSS OF PHYSICAL CONTROt CF PHYSICAL CONTROL OF THE Detection Method:

OF THE PLANT.

FACILITY.

Detection Method:

Secur ity safeguards contingency event which results in Detection Method:

Detection Method:

1) Roport to the Control Room by adversaries commandeer ing an

observer, area of the plant, but not Physical attack on the Plant Physical attack on the Plant has control of shutdown capability.

Involving immlnont occupanc'; of resulted in occupation of the

2) Alarm of Integrated Fire and control room and auxit lary control room and the auxillary Secur ity Panel, shutdown panels, shutdown panels by unauthorized personnel.

l

EMERGENCY ACT ION LEVELS SLEMARY EPP-001. ATTACtNENT I PAGE 11 of 13 R P, lS 10% 1 0

SITE GENERAL SYSTEM INVOLVED UNUSUAL EVENT ALERT EHERCENCY EMERGE NCY F4ATURAL INITIATit0 CONDITION INITIATitO CONDITION INfTIATING CONDITION PHE rf/4E TON P4ATINAL EVENTS SEVERE NATURAL EVENT NEAR SITE.

SEVERE NATURAL PHENOMENON BEING EXPERIEtCED OR FROJECTED WITH PLANT POT IN COLD SHUTDOWN.

a.

EARTHQUAKE b.

TCHNADO ON SITE a.

EARTHQUAKE GREATER THAN THE c.

HlNRICANE NEAR SITE (OBE) LEVEL a.

EARTHQUAKE GREATER THAN SSE i

b.

TORMADO STRIKING F ACILITY LEVELS.

l c.

HURRICANE WINDS GtEATER THAN b.

WINDS IN EXCESS OF 100 ftPH OF Detectlon Method:

75 MPH SITE.

Detection Method:

a.

Solsmic Recording System Start ind ic at ion.

a) Solsmic Rosponse Spectrtri b.

Observation of event.

Trouble Anrunciator Reactor Building Foundation l

c.

Observation of ovont.

b) Observation of event Seismic Switch (SSE) c) Motocrological MonitoiIng l

System Data or Woathor Burau Metoorological Monitoring System Report.

Data.

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d D4ERGENCY ACL) LEVELS Slf4 MARY EPP-001, ATTACtf4 Erd PAGE 12 of 13, REVISION 1 SYS FEM SITE GENERAL INVOLVED UNUSUAL EVENT ALERT EMERGENCY EMERGEtCY INITIATitG CONDITION MAttlADE INITIATING CONDITION INITIATING COtO! TION PHENOMENON OTHER HAZARDS BEING EXPERIEtCED OTHER HAZ ARDS BEING EXPERIENCED OF OTHER HAZARDS BEING EXPERIErCED OR PROJECTED WITH PLANT NOT IN FH0JECTED WHICH HAVE THE POTENTIAL OR PROJECTED WHICH HAVE A COLD SHUTDOWN:

FOR ENDAtOERING THE FACILITY SIGNIFICANT POTENTIAL FOR AFFECTING PLANT SAFETY.

a.

AIRCRAFT CRASH INTO VITAL a.

ONSITE AIRCRAFT CRASH.

a.

AIRCRAFT CRASH ON FACILITY.

STRUCTURES.

b.

ONSITE TRAIN DERAILMENT.

b.

MISSILE IMPACTS ON FACILITY b.

MISSILE OR EXPLOSION IMPACT c.

ONSITE EXPLOSION (EXCLUDING WITH RESULTANT MAJOR DAMAGE.

ON FACILITY RENDERING SEVERE PLANNED ACTIVITIES).

c.

KNOWN EXPLOSION AT FACILITY DAMAGE TO SHUTDOWN EQUIR4ENT d.

NEAR OR ONSITE T0XIC m RESULTING IN MAJOR DAMAGE TO c.

ENTRY OF T0XIC OR FLAMMABLE FLAMMABLE GAS RELE ASE OF A PLANT STRUCTURES m GASES INTO VITAL AREAS WHiCH MAGNITUDE THAT THREATENS EQUIPMENT.

INVOLVE A SIGNIFICANT PERSot:4E L.

d.

ENTRY INTO FACILITY ENVIRONS DEGRADATION OF PLANT e.

TURBINE GENERATOR ROTATING OF T0XIC OR FLAT-t4ABLE GASES SAFETY.

COMPONENT FAILURE CAUSING IN COrCENTRATION WHICH EXCEEE RAPID PLANT SHUTDOWN.

THE LIMITS OF FLAMMA0lLITY OF Detection Method:

T0XICITY.

Detection Method:

e.

TURBINE GENERATOR FAILURE a) Aircraft crash causing CAUSING CASING PENETRATION.

damago or fire in:

a.

Observation of event.

1) Reactor Building; s b.

Observation of event.

Detection Method:

2) Control Room; o c.

Obsorvation of explosion or

3) Auxiliary Building; o warning 'r un of f site.

a) Observation of aircraft crast

4) Fuel Handling Building;or d.

Obsorvatita of release or into Pl ant structures.

5) Turbine Building; o warning from of f si to, b) Observation of missile

6) Intako Structures e.

Turbino trip and observation impacts on Plant structures b) Loss of functions needed for of turbine mal f unction or or components.

hot shutdown. (seo page 6 of

failure, c) Observation of damage by this Attachment) explosion, d) Observation or warning from c) Entry of toxic or flammable outside the Pl ant; detection gases into:

of gases (using portable

1) Control room; or instrumentation) which exist

2) Cable spreading rooms; or in concentrations which

3) Reactor Building; o excood the Iimits of

4) SwI tchgear room: o flammability or toxicity.

5) Sa fo shutdown panols; or e) Turbine trip and observation

6) Emergency diesel of penetration of casing, generator rooms; as detected by portablo in-strumentation M which ren-ders a train of a safety-related system inoperablo.

EMERGEtCY ACTION LEUELS StimNtY EPP-001, ATTACif4ENT I PAGE 13 of 13, REVIS10M 1 SYSTO4 SITE GENERAL l ttvCLV E D UNt!SUAL EVENT ALERT EMERGENCY EMERGENCY OTHER INITIATito COtOITION INITIATING COtolTION I NI TI AT i tC C0tOIT ION LOSS OF Q)NTAltNENT INTEGRITY OTHER PLANT C0tOITIONS EXIST THAL OTHER PLANT CONDITIONS EXIST THA1 REQUIRING TECHNICAL SPECiF1 CAT 10N WARRANT ACTlVATION OF TECHNICAL WARRANT ACTIVATION OF EMERGEPCY SHUIDOh!J (TECHNICAL SPECIF ICATION SUPPORT CENTER AND EMEPGEtCY FACILITIES NO RADI ATION 3.6.1.1)

OPERATIONS FACILITY.

MONITORING TE AMS AND A PRECAUT tONARY PUGLIC WARN lPC.

Detection Method:

1) Any automatic containment Detection Method:

Isolation valve found to bo As determined by Emergency inoperable or Director.

As determined by Emorgency

2) Reactor Building air lock Director.

inoperable or

3) Penetration (s) fall leak test (as specified in Technical SpectfIcations)

INITIATlto COtolTlON THAf1SPORTAT 10N OF OVEREXPOSED AND/OR CONTAMINATED, INJURED INDIVIOUAL FRCH SITE TO il0 SPITAL.

Datuct Ion Method:

Samo as init iat ing condition.

INITI AT itG COtO! TION OTHER PLANT COtolTIONS EXIST RLQUIRING ODIER THAN NORMAL PLANT SilUTIXMN ANI) REQUIR ING ltCREASED AWAREtJLSS Ort THE PART OF STATE OF F ICI ALS.

Detection Method:

As dutormined by Emergency Director.

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n EPP-001 ATTACHMENT II PAGE 1 of 1 REVISION 1 IMMEDIATE ACTION

SUMMARY

UNUSUAL IMMEDIATE ACTIONS EVENT ALERT SITE GENERAL 1.

ANNOUllCEMENT TO PLANT PERSONNEL 2.

SOUND RADIATION ALARM 3

NOTIFY SECURITY SHIFT LEADER 4.

110TIFY FAIHFIELD PUMP STORAGE FACILITY 5

EtJSURE Of1-SHIFT PERSONNEL RESPONSE NOTIFY LOCAL AUTH OF 6.

EAHLY WARNIf1G SYSTEM RECOMMEND 7.

ACTIVATE EWS IF REQUIRED U.

INITIAL NOTIFICATIONS PER EPP-002 9

EMERGENCY LOG ESTABLISHED 10.

OFF SITE EMERGENCY SERVICES, IF REQUIRED ACTIVATE TSC/OSC OR NOTIFY EMERGENCY 11.

RESPONSE PERSOtJNEL 12.

110TIFY OFF-SITE EMERGENCY COORDINATOR Ef1SURE TSC/OSC ARE ACTIVITED Oh EMERGENCY 13 RESPONSE PERS0!JNEL NOTIFIED ENSURE EOF IS ACTIVATED OH EMERGENCY I4.

RESPO!1SE PERS0!If1EL NOTIFIED l

DETERMlf4E IF SITE EVACU ATIO!1 IS REQUIRED 15

( IllCLU DIl4G FAlHFIELD PUMP STORAGE FACILITY)

SOUTH CAROLINA ELECTRIC AND GAS COMPANY VIRGIL C. SUMMER NUCLEAR STATION NUCLEAR OPERATIONS YE!Ai0?i?OONS COPY No...... M,7. E...........

EMERGENCY PLAN PROCEDURE EPP-004 OUT-OF-PLANT RADIOLOGICAL SURVEYING REVISION 1 JANUARY 6, 1982 NON-SAFETY RELATED Reviewed by:

J

/ 7 72 ORIGINATOR (bf this revision)

/ D6te h=-

e I

QUALIFIED REVIEWER Date Approved:

Ann //bx lh 9

P MATTAGE

[Date l

REV EWD BY 3SRC Date Issued:.tn 1 a 10A2

/

C)

CHAIRMAN _

- -_._ DUE Form AP-101-2, (1/80) l

x EPP-004 PAGE 1 REVISION 1 1/6/82 LIST OF EFFECTIVE PAGES PAGE REVISION 1

1 11 1

1 1

2 1

3 1

ATTACHMENTS Attachment I 1 1 1

Attachment III 1

Attachment IV 1

9

(

6

c EPP-004 PAGE 11 REVISION 1 1/6/62

(])

TABLE OF CONTENTS Page List of Effective Pages i

1.0 PURPOSE 1

2.0 REFERENCES

1 30 CONDITIONS AND PREREQUISITES 1

4.0 PROCEDURES 2

ATTACHMENTS Attachment I Survey Record Attachment II -

Approximation of Air Sample Iodine and Particulate Concentration with RM-14 and HP-210 Attachment III - Iodine Graph Attachment IV - Particulate Graph O

I i

O k

s EPP-004 REVISION 1 1/6/82,

1.0 PURPOSE O

1.1 To provide guidanc, 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-303, " Airborne Activity Sampling Techniques and Procedures".

2.4 EPP-007, " Environmental Monitoring".

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 EOF.

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.

O 32 The Out-of-Plant Monitoring Director should proceed to the 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.

3.4 Coordinate with TSC/ EOF to determine travel routes which minimize plume exposure.

35 Minimize exposure while taking surveys, (e.g.,

10 min. air samples).

Coordinate surveys with TSC/ EOF to prevent unnecessary exposure.

36 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.

O PAGE 1 0F 3

e EPP-004 REVISION 1 1/6/82 38 Limit the use of protective clothing, as radiological conditions

(_3j warrant, to minimize public concern.

39 Retain all samples and sample data for re-evaluation.

3 10 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 reco rd s.

4.0 PROCEDURE 4.1 Out-of-Plant Monitoring Director (guidelines) 4.1.1 Dispatch out-of-plant survey teams as needed.

4.1.2 Establish and maintain communications with Out-of-Plant surveyors and EOF when activated.

4.1 3 Frequently monitor meteorological and effluent conditions, keeping surveyors updated.

4.1.4 Identify sampling locations and routes, using priorities listed below as guidelines:

(O_)

4.1.4.1 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.

l 4.2 Out-of-Plant Surveyors

('T RJ PAGE 2 0F 3

5 EPP-004 REV13 ION 1 1/6/82 4.2.1 Obtain emergency kits from Service Building Annex and a

radios from Health Fhysics Lab or TSC.

Check seals and W

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 Source check instruments in kit with the source supplied in the kit for response radiation.

4.2 3 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 kit.

4.2 5 Establish communication with TSC and/or EOF.

4.2.6 Obtain current pertinent data from TSC/ EOF (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 applicable HPP's.

Ensure instruments are source checked for response after each use.

NOTE:

TSC/ EOF and surveyors should collaborate to determine k

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.

4.2 9 Record sample and survey data on Attachment I.

4.2.10 Contain, label and retain samples 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.

NOTE:

Take precautions to minimize exposure to environmental TLD's during transportation either to or from sampling station.

O PAGE 3 0F 3

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s EPP-004 ATTACHMENT I PAGE 2 OF 2 REVISION 1 SURVEY INSTRUMENT INFORMATION lll INSTRUMENT NUMBER 1 INSTRUMENT NUMBER 2 INST. TYPE INST. TYPE SERIAL NUMBER SERIAL NUMBER CALIB. DATE CALIB. DATE SOURCE CHECK SOURCE CHECK (INIT)

(INIT)

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)

NOTES:

1.

Instrument number on front sheet should be 1 thru 4 from above information.

O REMARKS:

l l

O

r EPP-004 ATTACHMENT II PAGE 1 0F 1 REVISION 1

()

APPROXIMATION OF AIR SAMPLE IODINE AND PARTICULATE CONCENTRATIONS 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.

Determine volume of air sampled in liters or ft3 as indicated on instrument.

3 Use graph (Attachment III) to approximate iodine concentration.

Recommended allowable background is < 100 cpm.

4.

Use graph (Attachment IV) to approximate gross particulate concentration.

Recommended a3

Able background is < 100 cpm.

Bases 1.

Recommended allowable background is 100 cpm.

Attachment lII 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.

3 Attachment IV is derived using 10% detection efficiency and a 99%

filter collection efficiency.

~

EPP-004

, ATTACHMENT III l

I REVISION 1 m

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SOUTH CAROLINA ELECTRIC AND GAS COMPANY VIRGIL C. SUISTER NUCLEAR STATION NUCLEAR OPERATIONS N UC_ EAR 0 3 ElA" 0 MS CO PY N 0.......M'7. 6...........

EMERGENCY PLAN PROCEDURE EPP-005 0FFSITE DOSE CALCULATIONS REVISION 1 JANUARY 7, 1982 O

NON-SAFETY RELATED Reviewed by:

/!FF2 RI 'IN ATOR (of this revision)

'Dhte

/> J. N A =

Ibbu QUALIFEED R!f/IEWER Date i

Approved:

9st&a PL,Qp MANAGER t/e/e2 Date a u Issued: M 1 M82 EV EWE 3 3Y PSRC A. GA.A~

//f/fz

/

Form AP-101-2 (1/80)

O CHAIRMAN DATE o

l

EPP-005 PAGE i REVISION 1 1/7/82 LIST OF EFFECTIVE PAGES Page Revision i

1 11 1

111 1

1 1

2 1

3 1

4 1

5 1

ATTACHMENTS I

1 II 1

III 1

IV 1

'l 1

VI 1

VII 1

VIII 1

IX 1

h X

1 XI 1

XII 1

XIII 1

XIV 1

1 0

EPP-005 Page 11 Revision 1 1/7/82 6

TABLE OF CONTENTS gm

(_)

Pace List of Effective Pages i

s Flow Chart 111 1.0 PURPOSE 1

2.0 REFERENCES

1 30 CONDITIONS AND PREREQUISITES 1

4.0 PROCEDURE 1

50 BASES 4

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:

Off-Site Dose Calculation Using High Range Monitors

(/3 ATTACHMENT IV - Sample Fo rm:

Activity Release Status N.

ATTACHMENT V - Sample Form:

Projected Offsite Doses ATTACHMENT VI - Sample Fo rm:

Out of Plant Monitoring Dispatch & Data Form ATTACHMENT VII - Sample Form:

Dose Off-Site (Dose Rate) Calculation from Environmental Monitoring ATTACRMENT VIII - Dose-Concentration Conversion ATTACHMENT IX - Delta T Atmospheric Stability Classification ATTACHMENT X - Sigma Theta Atmospheric Stability Classification ATTACHMENT XI - Meterological Sector Definition ATTACHMENT XII - Correction Factor for High Range Monitors A2TACHMENT XIII - Protective Action Guides (PAGS)

ATTCHMENT XIV - Pasquill-Turner Method for Determining Atmospheric Stability.

(~)

'w s s

EPP-005 3 y PACE 111 aEnSzos 1 1/7/82 Select go,7,g,g Method M * "",

Method 4.0 Drives 3,g o

Manual I

Mathed 4.2 IX at or c9 Sac's up Stability Stability Dy I

4.2.1 4.2.2 II Location 4.3 Case Calculation s.4 u

i.a

.,.. ~,

u.

~

- "!";**3

\\

ntz

.4.2 Compare XIII PAG's Accountant 11c';

7

.4..

g i

I Report Etachment 7

4.4.5 d

h 9

Off-Site l

VIII

{ Mon ring {

i f

\\

lMcnitsetng l

/

l Pref ections

. 5.2 i

EPP-005 REVISION 1 1/7/82 1.0 PURPOSE 1.1 To provide methods for estimating wholebody and child thyroid dose rates due to abnormal releases of radioactive materials to the environment.

1.2 To provide a method of comparing the integrated wholebody and child thyroid doses of the EPA Protective Action Guides (PAG's).

2.0 REFERENCES

2.1

" Virgil C.

Summer Nuclear Station Radiation Emergency Plan".

2.2 American Society of Mechanical Engineers, " Recommended Guide for the Prediction of the Dispersion of Airborne Effluents", May 1968.

23 Dames and Moore, " Data Reduction Procedure for Virgil C. Summer Nuclear Station", September 1974.

2.4 Slade, D.

H.,

(ed.), " Meteorology and Atomic Energy - 1968",

TID-24190, Division of Technical Information, USAEC (1968).

25 Tu rner, D.

B.,

"A Diffusion Model for an Urban Area", Journal of

(^3 Applied Meteorology, February 1964.

V 2.6 U. S. Nuclear Regulatory Commission, Proposed Revision 1 to Regulatory Guide 1.23, " Meteorological Programs in Support of Nuclear Power Plants",, September 1980.

27 NUREG-0654/ FEMA-REP-1, " Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and 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 Technology, Inc.

30 CONDITIONS AND PREREQUISITES 31 None 4.0 PROCEDURE

(

NOTE:

This procedure delineates two (2) methods by which l

offsite doses may be calculated (i.e.,

computer l

calculation and manual calculation).

Either method, or a l

combination of both methods, may be used since the same l

results can be obtained.

()

l PAGE 10F 5

EPP-005 REVISION 1 1/7/82 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 TSC 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 cf plant monitoring teams.

Proceed to step 4.5 4.2 Manual Method 4.2.1 Stability Class Determination If the primary 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.

is preferred.

A.

Differential Temperature (AT) 61-10 meters and 40-10 meters Method.

1.

Obtain A T information from the Control Room 3

instrumentation.

W NOTE:

Priority should be given to the 61-10 meter information with the back up being the 40-10 meters.

2.

If the Control Room instrumentation is inoperable, personnel may be dispatched to the meteorological tower to obtain T information directly from the met tower instrumentation.

3 Determine the Pasquill Category by using Attachment IX and select appropriate overlay.

4.

Proceed to Step 4.3 for determination of plume location and X/q values.

B.

Sigma Theta Method 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 .

O PAGE 2 0F 5

EPP-005 REVISION 1 1/7/82 2.

Wind range is determined by the difference between 73

(_)

the highest and lowest values measured.

If the wind direction chart shows one or two spikes, these should be ignored in determining the wind range.

If more than two spikes, these must be considered in determining wind range.

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 Pasquill Category by using Attachment X and select appropriate overlay.

4.2.2 Backup meteorological data can be obtained from two sources, the' site 2 tower and/or the National Weather Service (NWS).

A.

Dispatch personnel to site 2 tower and use data from local strip charts for windspeed and direction.

Use method B of step 4.2.1 to obtain stability class.

Data from site 2 is preferred over NWS data.

Radio communication should be established for the duration of the incident.

Dosimetry is required for personnel at site 2.

r-(_)3 B.

If primary tower data is not available call the NWS (Phone:

794-2593) 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 XIV " Turner's algorithm" to obtain stability class.

43 Location of the Effluent Plume 4 3.1 After determination of appropriate overlay in Section 4.2 place overlay to the center of the base map.

432 Orient 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 and th6 direction to which the wind is blowing (e.g. wind is b:.owing from 270 to 90 ).

4 3 3. The conversion from wind direction measured in degrees to wind direction in sectors is presented in (3

Attachment XI.

(/

PAGE 3 0F 5

EPP-005 REVISION 1 1/7/82 4.4 Manual Doce Calculation O

4.4.1 Complete Part 2 of Attachment I.

4.4.2 Complete Attachment II if radiation monitor RM-A3 is on scale.

Compare results with the PAGS (Attachment XVI).

4.'43 If RM-A3 is offscale or if there is a steam release complete Attachment III.

Compare results with the PAGS

( Attachment XVI).

NOTE:

Attachment XII, will be necessary for completing Attachment III.

.4.4.4 Complete Attachnent IV to maintain curie accountability.

Total activity of iodine, noble gas, particulates, and tritium must be kept current. (Hourly updates if possible) 4.4 5 Transfer all applicable results to Attachment V for transmittal and documentation purposes.

4.5 Environmental Monitoring 451 As soon as practical, dispatch monitoring teams to the effected meteorological sectors.

Attachment VI, should be used to record location and results.

NOTE:

Dose projections based on source terms should be lh verified as soon as possible by supportive measurements.

Based on these measurements, a reassessment of the PAG's should be taken.

4.5 2 Attachment VII can be used to project doses based on environmental samples.

These can then be compared with source term projections.

5.0 BASES This section is included to provide a brief explanation of the sources of constants and graphs used in the procedures and associated alcachments.

4 3 1-B 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 strait line gaussion plume model as described in Reg.

Guide 1.145 O

PAGE 4 0F 5

EPP-005 REVISION 1 1/7/82 4

II-B The Iodine to noble gas activity ratio of 0 3,

()

until measured, is a conservative estimate from

~

actualratiocouldbe10gwouldsuggestthatthe Ref. 2.7 page D-59 TMI-or less.

A fast and accurate measurement of the actual ratio is important to avoid unnecessary evacuation orders based'on the Iodine PAGS.

III-B Same comment as II-B VIII-B The curves follow the methodology and assumption of Ref. 2./.

The noble gas curve comes from EQ.

2 9, the Iodine curve from EQ. 2.13 XIV-B This description of the Pasquill-Turner method was I

supplied by Dames and Moore.

The calculation of the solar *sititude was ootained from the Alabama Power Company Farley Station EDCM.- It was verified by comparision with selected values from the Smithsonian Meteorological Tables.

XIII-B Taken from Ref. 2.7 The particulate concentrations 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 ..

4 l.

i

(

l l ()

PAGE 5 0F 5

EPP-005 ATTACHMEllT I PAGE 1 0F 1 REVISIO!! l O

METEOROLOGY AIID SOURCE TERM REPORT FORM Mindspeed mph (10 meter prefered)

Time Direction degrees (10 meter prefered)

Delta T degrees (61-10) or (40_10)

(Circle One)

Sigma Theta degrees Stability Class (Use Delta T and Attachment IX or Sigma Theta and Attachment X or Turners Algorithm and Attachment XIV)

Part 2:

Source Term RMA3 CPM (net)

Flow Rate g

RM-A13 R/hr Time RM_G19 R/hr O

EPP-005 ATTACHMENT II PAGE 1 0F 2 REVISION 1 (3(-)

EMERGENCY OFF-SITE DOSE CALCULATION USING STACK MONITOR SOURCE TERM Time of Trip Current Time Time after Trip RM-A3 Noble Gas Reading CPM (A) m3 min.

(B)

Flow rate:

CFM x 0.028 =

/

Release Rate: (A)x(B)x(3 3x10-10)

C1/sec (C)

=

(C) x 3600 =

C1/hr (use in EPP-001)

Wind Speed:

MPH x 0.45 =

m/sec (D)

(X/Q)u from isopleth for 1 mile m-2 (E1) sec/m3 (F)

X/Q: (El)+(D)

=

Noble gas dose to concentration conversion from Attachment VIII X2=

rem /2hr (G)

C1/m3

/~T

( JHOLE BODY DOSE (2 hrs): (F) x (C) x (G)

=

rem 2 hr. (H)

Iodine to noble gas activity ratio (use 0 3 unless measured)

(I)

Iodine dose to concentration conversion from Attachment VIII rem /2hr C1/m3 (J)

/"N N,l

EPP-005 ATTACHMENT II PAGE 2 OF 2 REVISION 1 EMERGENCY OFF-SITE DOSE CALCULATION USING STACK MONITOR SOURCE TERM Time of Trip Current Time Time after Trip Iodine to noble gas dose ration (I) x (J) + (G)

(K) 1 CHILD THYROID DOSE:

(K) x (H) =

l 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 (ES)

(E5)/(El)

(L5) 10 miles (E10

( E10) /( E1)

(L10)

DOSE 2 miles (L2) x ( H) rem x (K)

=

rem 5 miles (L5) x (H) rem x (K)

=

rem 10 miles (L10) x (H) rem x (K)

=

rem WHOLE BODY CHILD THYROID g

(2 Hour)

W O

~

EPP-005-ATTACHMENT III PAGE 1 0F 2 REVISION 1 Lo OFF-SITE DOSE CALCULATION i

USING-HIGH RANGE MONITORS Time of Trip Current Time Time after Trip RM-A13 RM-Gl9 Dose Rate mr/hr mr/hr (A1)

Flow Rate CFM lb/hr

-(A2)

Calibration.6.67x10-5 (to be supplied)

(B1)

Correction factor from Attachment XII (B2)

Release Rate (A1)X(A2)x(B1)/(B2)

Ci/sec (C)

(C) x 3600 =

C1/hr(use in EPP-001)

Wind Speed:

MPH x 0.45 =

m/sec (D)

(X/Q)u from isopleth for 1 mile m-2 (El) sec/m3 (y)

Q: (E1)+(D)

=

Noble gas dose to concentration conversion from Attachment VIII X2=

rem /2hr (G) 4 C1/m)

WHOLE BODY DOSE (2 hr.):

(F) x (C) x (G) =

rem 2hr (H)

I Iodine to noble gas activity ratio (use 0 3 unless measured)

(I)

Iodine dose to concentration conversion from Attachment VIII rem /2hr (J) ci/m3 f

A i

' O

EPP-005 ATTACHMENT III PAGE 2 0F 2 REVISION 1 0FF-SITE DOSE CALCULATION USING HIGH RANGE MONITORS Time of Trip Current Time Time after Trip Iodine to noble gas dose ration (I) x (J) + (G)

(K)

CHILD THYROID DOSE:

(K) x (H)

=

at 1 mine (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)/(El)

(L2) 5 miles (ES)

( ES)/( El)

(L5) 10 miles (E10

( E10 )/( E1)

. L10)

(

DOSE 2 miles (L2) x (H) rem x (K)

=

rem 5 miles (L5) x (H) rem x (K)

=

rem 10 miles (L10) x (H) rem x (K)

=

rem WHOLE BODY CHILD THYROID g

(2 Hour)

W 9

EPP-005 ATTACHMENT IV PAGE 1 0F 1 REVISION 1 O

ACTIVITY RELEASE STATUS Time:

Elapsed time since last' release calculation see (A1) he (A2)

Noble Oas Average release rate since last calculation C1/sec (B1)***

Activity-released since last calculation (A x B1) 01 (C1)

Previous total of noble gas released C1 (D1)

Total activity released (C1 + D1)

C1 CURRENT DOSE ELAPSED TIME CURRENT OLD TOTAL TOTAL DISTANCE RATE (rem /hr)

(A2)

DOSE DOSE DOSE 1 mile X

=

+

=

. rem 2

X

+

=

rem

=

5 X

=

+

=

rem 10 X

=

+

=

rem O

Iodine Average celease rate since last calculation C1/sec (B2)

Activity released since last calculation (Al X B2) 01 (C2)

Previous total of Iodine released C1 (D2)

Total activity released (C2 + D2)

C1 CURRENT DOSE ELAPSED TIME CURRENT OLD TOTAL TOTAL

. DISTANCE RATE (rem /hr)

(A2)

DOSE DOSE DOSE 1 mile X

=

+

=

rem 2

X

=

+

=

rem 5

X.

=

+

=

rem 10 X

=

+

=

rem

- - B1 x 3600 =

C1/hr, This figure is to be used for Determining Emergency Action Levels in EPP-001 Attachment I.

O

EPP-005 ATTACHMENT V PAGE 1 0F 1 REVISION 1

- PROJECTED OFFSITE DOSES **

METER 0 LOGICAL DATA Time:

WS:

mph WD:

to Class:

T SAMPLE DATA Sample Concentrations (

C1/ml)

Source Date Time Number Iodine NG Part.

H-3 MONITOR READING Iodine to NG Grab Time Since Inst.

Gross BKDG.

Net Sample Result Ratio Accident Start hr min TWO HOUR DOSE PROJECTION IN REM Whole body ( REM /2hr. )

Child Thyroid (REM /2hr.)

llh 1 mi.

2 mi.

5 mi.

10 mi.

1 mi.

2 mi.

5 mi.

10 mi.

ACTIVITY RELEASE STATUS AS OF (TIME):

Release Rate (Ci/sec)

Total Released (C1)

Noble Gas Iodine Particulate Tritium CURRENT TOTAL DOSE Whole body (rem)

Child Thyroid (rem) 1 mi 2 mi 5 mi 10 mi 1 mi 2 mi 5 mi 10 mi e

r-a 14 k.,.

A a

a x EPP-005 ATTACHMENT VI PAGE 1 OF 1 REVISION 1 (O/

OUT OF PLANT MONITORING DISPATCH AND DATA FORM-Dispatch Unit Time Location.

Miles Degrees Comments:

4 4

Report Location Confirmation YES/NO Time Rad Level R per hour (A)

Air Sample Volume cubic ft. x 28320 =

cm3 Particulate-net epm C1/cm3(a)_

Particulate Concentration

=

Iodine net cpm (c)

C1/cm3 (C)

Iodine Concentration

=

Iodine dose to concentration conversion rem /2hr from Attachment VIII C1/m3

- (D) 2 hr. child thyroid dose (C) x (D) rem (E)-

2hr NOTE:

Compare (A), (B), and (E) to PAGS (Attachment XIII)

U

EPP-005 ATTACHMENT VII PAGE 1 0F 1 REVISION 1 O

OFF-SITE DOSE (DOSB RATE) CALCULATION PROM ENVIRONMENTAL MONITORING Sample Time Rad level Check One:

Location Iodine Measured Dose cem (A)

(Dose Rate) mr/hr xj at location from isopleth (B)

Q O

(A) + (B)

(C)

=

x5 from isopleth at 1 mile (D1)

Q 2 miles (D2) 5 miles (D5) 10 miles (D10)

Dose (Dose Rate) at 1 mile (C) x (D1)

=

(C) x (D2) 2 miles

=

rem (C) x (D5) 5 miles (mr/hr)

=

10 miles (C) x (D10)

=

0

e 4

ta e

g 4

o m

9 u

a

(

m m

a m

e d

a.O r

ga ga l ; i, a jl i

j i

6 a

gie

1

0-i 6 a a g.

~..,, g m

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... D _ %N,.

s O

d U

! 4 w

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! w l

~

1 i

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..i... _ _ _. _ _..

lp

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.,I _. _..A

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.... _...... _... _......... ~

....r...

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9...

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-...... - _..... i _.h -

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e

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EPP-005 ATTACHMENT IX PAGE 1 of 1 REVISION 1 ATMOSPHERIC STABILITY CLASSIFICATION llh Temperature Differential (o T)

Stability Pasquill T in F

Classification Categories 61-10 m 40-10 m Extremely Unstable A

1-1.75 1-1.03 Moderately Unstable B

-1.74 to

-1 56

-1.02 to -0 92 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 Sllghtly Stable E

-0.45 to 1 37

-0.26 to 0.80 Moderately Stable F

1 38 to 3.67 0.81 to 2.16 Extremely Stable G

>3.67

>2.16 O

O

i EPP-005 ATTACHMENT X PAGE 1 of 1 REVISION 1

,r's

(,)

ATMCSPHERIC STABILITY CLASSIFICATION Sigma Theta (c0)

Stability Pasquill (degrees)*

_QJassification Categories Extremely Unstable A

>22.4 Moderately Unstable B

22.4 to 17 5 Slightly Unstable C

17.4 to 12 5 Neutral D

12.4 to 7 5 Slightly Stable E

7.4 to 3.8 Moderately Stable F

3.7 to 2.1 Extremely Stable G

<2.1 (J~1 s,

Standard deviation of horischtal wind direction fluctuation over a period of 15 minutes to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

(Wind Range divided by 6)

Ref. USHRC Reg. Guide 1.23, Rev.

1, Sept. 1980.

1 Pi U

EPP-005 ATTACHMENT XI PAGE 1 of 1 REVIS71N 1 METEOROLOGICAL SECTOR DEFINITION llh Wind Central Direction Value Limits of Sector Sector (degrees) 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 E

90.0 78.75 <

1 101.25 ESE 112 5 101.25 <

1 123 75 SE 135 0 123 75 <

1 146.25 SSE 157 5 146.25 <

1 168.75 S

180.0 168.75 <

1 191.25 SSW 202 5 191.25 <

1 213 75 SW 225 0 213 75 <

1 236.25 WSW 247 5 236.25 <

1 258.75 llI W

270.0 258.75 <

1 281.25 WNW 292 5 281.25 <

1 303 75 NW 315 0 303 75 <

1 326.25 NNW 337 5 326.25 <

1 348.75 N

360.0 348.75 <

1 11.25 CALM Wind speed less than 0.75 mph MISSING Unreliable data O

(5 X 5)._. _- FIE a u *d 3

e. -

.=*==.-a.=

.e------

.e-.

._A

^ MMM W-S.6 h 6 4-w.* M h..

6 h h-I

.... -..... - - ~.

.,.... +. -

.h u

i w

A m-l

_w m---e**6 me.u-4 mm.

. uni.,e.--

. + +.. = = * * <

M X

i

i ;

,y h.

D i

re

_.m _h3 _ g...

__ e-

_o

.. _.O i v e-p

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p_

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.s N...

. t.

Q

_ _ p_

H i

g _ _. _...

em.e_.h-e.e e 4e.ae.e--g.e u.s.

.m.>

> _ - =

w_. *. - -

+,-em

--e me

.e.-..

.ew 4

..-..g.*

e

.m.

W en.-

N e.-

--gus

.mus.ub.

--e

.w..

.e em p

-e--

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-4 he.

enwh m wmmne.g m

-O, M

MW

=

i i

i

( o.

q h

S i

I l !

/

(

EPP-005 ATTACHMENT XIII PAGE 1 of 1 REVISION 1 RECOMMENDED PROTECTIVE ACTIONS TO REDUCE WHOLEBODY AND THYROID DOSE FROM EXPOSURE TO A GASEOUS PLUME Projected Dose [ Rem) to (a) the Population Recommended Actions Comments (b)

Wholebody

<1 No planned protective actions.

Previously recommended protec-Thyroid

<5 State may issue an advisory to seek shelter tive actions may be reconsidered Particulate <l.5x10-7 and await further jnstruction.

or terminated.

ci/ml Monitor environmental radiation levels.

u Wholebody 1 to < 5 Seek shelter as a minimum.

If constraints exist, special Thyroid 5 to < 25 Consider evacuation.

Evacuate unless consideration should be given Pargiculate 1.5 to <7 5x constraints make it impractical.

for evacuation of children and ci Monitor environmental radiation levels pregant women.

10-u ml Control access.

_Wholebody 5 and above Conduct mandatory evacuation.

Seeking shelter would be an Tyroid 25 and above Monitor environmental radiation levels and alternative if evacuation were Particulate 7 5x10-7 adjust area for mandatory evacuation based not immediately possible yci and above on these levels.

ml Control access.

Projected Dose (Rem) to Emergency Team Workers Wholebody 25 Control exposure of emargency team members Although respirators and stable to these levels except for lifesaving lodine should be used where missions.

(Appropriate controls for emer-effective to control dose to gency workers, include time limitations, emergency team workers, thyroid respirators and stable iodine.)

dose may not be a limiting Wholebody 100 Control exposure of emergency team members factor for lifesaving missions.

performing lifesaving missions to this level.

(Control of time of exposure will be most effective.)

(aT These actions are recommended for planning purposes.

Protective action decisions at the time of the incident must take existing conditions into consideration.

(b) At the time of the incident, officials may implement low-impact protective actions in keeping with the principle of maintaining radiation exposures as low as reasonably achievable.

O O

O

EPP-005 ATTACEMENT XIV PAGE 1 OF 3 REVISION 1 O

The Pasquill-Turner Method for Determining Atmospheric Stability If both the primary and secondary AT sensors are inoperative and sigma 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. Determination of stability class as a function of wind speed and net radiation is given in Table 1; In this system, insolation is estimated by solar altitude and modified for existing conditions of total cloud cover and cloud ceiling height. At night estimates of outgoing radiation are made by considering cloud cover. The net radiation index 'i's 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 < 5/10, use' the net radiation index cor" esponding to r

the insolation class number.

c) If cloud cover >5/10, modify the insolation class number by the following i

steps:

1) If ceiling < 7000 feet, subtract 2

11) If ceiling > 7000 feet, but < 16,000 feet, subtract 1 111) Il total cloud cover is 10/10 and ceiling is >7000 feet, subtract 1 (compare to 1 above) iv) If total cloud cover is not 10/10 and ceiling is > 16,000, assume modified class number equal to insolation class number v) If = edified insolation class number is less than 1, let it equal I vi) Use the net radiation index corresponding to the modified insolation class number

()

Thus, it can be seen from Table I that instability occurs with high positive net radiation and low wind speeds, stability with negative net radiation and light winds, and neutral conditions with cloudy skies or high wind speeds.

l l

I L

EPP-005 ATTACHMENT XIV h

PAGE 2 0F 3 REVISION 1 Calculation of Solar Altitude a = arcsin [ sin 6 sinQ + cos ((H-12 ) 180*) cos 6 cos))

12 where $ = station latitude 1 34.3*

H = hour o f. day (24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months clock) 6 = arctan ( -tan (23.S*) cos (360* (N+10)))

30a where N = number of days fr.o.m the beginning of the year O-i

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0 EPP-005 ATTACHMENT XIV PAGE 3 0F 3 REVISION 1 TABLE 1 STABILITY CLASS AS A FUNCTION OF NET RADIATION AND WIND SPEED Wind Speed

Net Radiation Index M

(knots) 4 3

2 1

0

-1

-2 o,l.15 0, 1 A

A B

C D

F G

1, 3.45 2, 3 A

B B

C D

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st.6,5.75 4, 5 A

B C

D D

E F

6.7 6

B B

C D

D' E

F F.05 7

B B

C D

D D

E

7. 1 10.35 8, 9 B

C C

D D

D E

11.5 10 C

C D,

D b

D E

11 65 11 C

C D

D D

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D D

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+ Table I was developed for wind speed in knots. To convert from knots to meters per second, multiply rcughly by

.5, accurately by.51444.

1 TABLE 2 INSOLATION AS A FUNCTION OF SOLAR ALTITUDE j

Insolation Jolar Altitude (a)

Insolation Class Number 60* < a Strong 4

35 * < a < 60*

Moderate 3

15 * < a < 35 '

Slight 2

a < 15

Weak 1

1

- See Page 2 of this attachment O

SOUTH CAROLINA ELECTRIC AND GAS COMPANY Os VIRGIL C. SUMMER NUCLEAR STATION NUCLEAR OPERATIONS TJC_ EAR 0?RA"0XS COPY No... ' /~57F

~ ~ ' * * * * * ' * * * * * * * '

EMERGENCY PLAN PROCEDURE EPP-010 PERSONNEL / VEHICLE DECONTAMINATION REVISION 1 JANUARY 6, 1982 NON-SAFETY RELATED O

Reviewed by:

/f 9.

ORIGINATOR ' Tor this revision)

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EPP-010 PAGE 1 REVISION 1 1/6/82 O

LIST OF EFFECTIVE PAGES PAGE REVISION 1

1 11 1

1 1

2 1

3 1

ATTACHMENTS Attachment I 1

Attachment II 1

O l

O

EPP-010 i

PAGE 11 REVISION 1 1/6/82 TABLE OF CONTENTS PAGE List Of Effective Pages i

1.0

_P.U..RPOSE 1

2.0 REFERENCE 1

30 CONDITIONS AND PREREQUISITES 1

4.0 PROCEDURES 2

i ATTACHMENTS t

Attachment I Attachment II i

4 4

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EPP-010 REVISION 1 1/6/82 h

1.0 PURPOSE To provide instructions for the decontamination of personnel and vehicles during emergency conditions.

29 REFERENCES 2.1

" Virgil C. Summer Nuclear Station Radiation Emergency Plan."

2.2 HPP-405, " Personnel Decontamination".

23 EPP-012, "Onsite Personnel Accountability and Evacuation.".

2.4 EPP-009, "on-Site Medical".

25 NUREO-0654, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants.

30 CONDITIONS AND PREREQUISITES 31 All injuries occurring within the Radiation Control Area will be considered contaminated until monitored and cleared by Health Physics.

g 32 Potentially contaminated personnel / vehicles will be monitored and decontaminated on-site unless evacuation to an off-site area is required.

When evacuated to off-site holding areas, monitoring and decontamination of personnel / vehicles will be performed at locations designated by Health Physics.

3 2.1 For offsite/ Security Annex Monitoring and decontamination.

3 2.1.1 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.

3 2.1.2 Source check instruments in kit with the source supplied in the kit for response to radiation.

33 All decontamination shall be supervised by Health Physics personnel.

34 All personnel and vehicles found to be contaminated will be g

reported to the Radiological Assessment Supervisor.

PAGE 1 0F 3

EPP-010 REVISION 1 1/6/82

()

4.0 PROCEDURE 4.1 Personnel Decontamination 4.1.1 The following Radiation / contamination limits shall be utilized:

a.

All personnel shall be limited to non-detectable loose surface contamination of less than 100 cpm above background at 1/2 inch using a pancake GM tube (HP-210 probe), with an efficiency greater than or equal to 10% and background less than or equal to 400 c pm.

4.1.2 All personnel who have or are suspected of having internal contamination shall have a whole body count at the earliest possible time.'

4.1 3 During emergency conditions, it may become necessary to evacuate contaminated or potentially contaminated personnel.

These individuals should be monitored and decontaminated at the designated off-site holding area, if that is their destination.

These personnel should be dressed in paper coveralls with a yellow and magenta arm band.

()

4.1.4 Personnel decontamination perfobmed inside the plant will be accomplished in the decontamination facilities described in HPP-405 " Personnel Decontamination".

4.1 5 Personnel decontamination to be performed outside the Protected Area may be accomplished by direct HP coverage in the Q.A./ Security Building (whenever possible).

All waste generated, both solid and liquid, shall be collected for subsequent disposal.

Precautions to minimize waste should be used whenever pocsible.

4.1.6 If personnel decontamination is performed at the offsite holding area, decontamination supplies located in the Q.A./ Security Building should be utilized.

4.1 7 Complete Attachment I for all contaminated personnel.

4.1.8 Bioassays will be administered, based upon levels of skin contamination, at the discretion of the Radiological Assessment Supervisor.

4.2 Vehicle Decontamination.

qb PAGE 2 0F 3 1

/

EPP-010 REVISION 1 1/6/82 4.2.1 Vehicle monitoring should be performed by Health Physics personnel using the appropriate equipment stored in the emergency kits.

4.2.2 The following limits will be used for unconditional l

release of vehicles during offsite evacuation:

4.2.2.1 Less than 1000 DPM/100 cm2 Beta / Gamma, smearable contamination.

4.2.2.2, Less than 100 cpm at 1/2" using a pancake GM l

Tube (HP-210 probe).

l 4.2.3 All vehicles found to be contaminated in excess of the above limits should be decontaminated using the following guidelines.

NOTE:

Don appropriate protective clothing prior.to decontamination attempts.

4.2 3.1 Rope and post an area accordingly.

4.2 3 2 Lay out plastic in the roped area and place the l

vehicle upon the plastic.

i g

4.2.3 3 Using the decon supplies in the off-site monitoring kits, decon the vehicle using decon i

roam and towels or disposable rags.

l l-4.2 3 4 Ensure that all contaminated towels and rags are placed in the radioactive trash bags provided in l

the Emergency Kit.

NOTE:

If, af ter several decon attempts, the contamination levels still do not meet the criteria listed in section 4.2.2, contact the Director of Health Physics or Health Physics Supervisor for further instructions in decontamination techniques.

4.2 3 5 complete Attachment II for all contaminated vehicles.

k PAGE 3 0F 3 1

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EPP-010 ATTACHMENT I PAGE 2 of 2 REVISION 1 PERSONNEL CONTAMINATION REPORT NAME OF PERSONS (S) INVOLVED:

DATE:

TIME:

RWP/SRWP NO.:

LOCATION OF INCIDENT:

SUSPECTED OR KNOWN CAUSE:

WERE CORRECT HEALTH PHYSICS PRACTICES BEING FOLLOWED?

YES NO PORTION OF BODY CONTAMINATED:

INITIAL READINGS:

Fixed:

DPM ggg READINGS AFTER DECONTAMINATION:

Fixed DPM PERSONNEL INJURY INVOLVED:

YES NO ACTION TAKEN FOR DECONTAMINATION:

MEDICAL ACTION TAKEN:

BODY BURDEN ANALYSIS PERFORMED:

YES NO RESULTS OF BODY BURDEN ANALYSIS / EXPOSURE ASSIGNED:

CORRECTIVE ACTION TAKEN TO PREVENT REOCCURRENCE:

/

ggg INDIVIDUAL'S SUPEItVISOR DATE HEALTH PHYSICS SUPERVISOR DATE

?

e r.PP-010 Attachr. ant II Pace 1 of 2 Revision 1 2

VEHICLE P.ONITORINC INSTRUCTIONS VIHICLE SURVEY FOPJi NOTE: k2se this' form for contaminated vehicles only.

Owner's Name License No.

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Indicate vehicles needing decontamination.

Survey Survey License State Results License State Results O

Instrumentation Used Survey Completed by Date Reviewed by Date O

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SOUTH CAROLINA ELECTRIC AND GAS COMPANY VIRGIL C. SUMMER NUCLEAR STATION NUCLEAR OPERATIONS NUClAR 0?ETATONS COPY No........,g7. 5...........

EMERGENCY PLAN PROCEDURE EPP-012 ONSITE PERSONNEL ACCOUNTABILITY AND EVACUATION REVISION 1 JANUARY 6, 1982 NON-SAFETY RELATED O'

/

Reviewed by:

1 f 72-ORIGINATOR (of this revision)

/ Dhte

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' QUALIFIED RFBIEWER Date Approved:

h /M, i6 Z P Q MANAGER /

Date REV W ] BY 3SRC Date Issued: JAN.1 91982

'D y I

U2-f h-ON Form AP-101-2, (1/80)

CHAIRMAN DATE

EPP-012 PAGE i REVISION 1 1/6/82 LIST OF EFFECTIVE PAGES Page Revision i

1 11 1

1 1

2 1

3 1

4 1

5 1

6 1

7 1

ATTACHMENTS g

Attachment I 1

Attachment II 1

l 1

1 l

l l

O

EPP-012 PAGE 11 REVISION 1 1/6/82 O

TABLE OF CONTENTS i

l M

List of Effective Pages i

1.0 PURPOSE 1

2.0 REFERENCES

1 30 CONDITIONS AND PREREQUISITES 1

4.0 PROCEDURES 2

ATTACHMENTS Attachment I - Evacuation Routes Attachment II - On-Site Assembly Verification Checklist O

4 l

l l

1 l

EPP-012 REVISION 1 1/6/82 1.0 PURPOSE 1.1 To describe the actions to be taken in the event that the evacuation of personnel, either in a speci:.'ic area of the plant or the entire plant, is required.

2.0 REFERENCES

2.1

" Virgil C. Summer Nuclear Station Radiation Emergency Plan" 2.2 EPP-008, "On-Site Assembly Verification" 23 EPP-OlC, " Personnel / Vehicle Decontamination" 2.4 EPP-Oll, " Personnel Search and Rescue" 25 SPP-ll4, " Security Responsibilities During Emergencies".

2.6 SPP-405, " Security Force Responsibilities for Emergencies During Construction" 27 NUREG-0654, Criteria for Preparation & Evaluation of Radiological Emergency Response Plans & Preparedness in Support of Nuclear Power Plants h

30 CONDITIONS AND PREREQUISITES 31 A specific area within the plant will be evacuated under the following conditions:

a.

Confirmed report of a significant radioactive spill in a work area.

b.

Confirmed report of an unexpecte<1 increase in the level of radiation or airborne activity in a work area.

c.

One or more area radiation monitors in a single building reach their alert setpoint.

d.

Or as designated by the Shift Supervisor / Emergency Director.

32 All non-essential personnel will be evacuated from the plant site under the following conditions:

O PAGE 1 OP 7 L

EPP-012 REVISION 1 1/6/82 a.

Site Emergency b.

General Emergency c.

As directed by the Shift Supervisor / Emergency Director 33 Sounding of the Reactor Building Evacuation Alarm will be cause to evacuate the Reactor Building.

The Reactor Building 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.

34 Evacuation signs have been placed throughout the plant.

Red signs have been placed in the Radiation Control Area and direct personnel to the 412' elevation for personnel decontamination procedures implementation if applicable.

Green signs have been placed throughout the rest of the plant and direct personnel out of the Protected Area by the way of the Guard House.

35 Personnel who are found to be contaminated during evacuation, and decontamination cannot be completed expeditiously, 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 Specific Area within the Plant.

4.1.1.a When personnel become aware that the conditions outlined in Section 3 1 exist in their area or an announcement of the plant paging system instructs them to evacuate the area they are in, they shall immediately proceed to a location j

away from the affected area.

l 4.1.1.b The personnel shall remain together as a group l

and contact the control room for accountability.

The Shift Supervisor will be notified of the names of any individuals thought to still be in this area.

(

l PAGE 2 OF 7 l

+

EPP-012 REVISION 1 1/6/82 4.1.1.c The area will be searched for poss'.ble remaining g

personnel.

Results will be reported to the Shift Supervisor.

4.1.1.d Upon direction by announcement eve:* the plant paging system and Fairfield Pamp Storage by phone 345-5830, microwave 8-3644; or Control Room on back shift, 8-3639, personnel will proceed to their assembly areas or predetermined duty station.

All contractor and visitor personnel not permanently assigned to a specific Summer Nuclear Station group, will proceed or be escorted through the guard house

.to the Q.A. Security Building.

They will remain there until further instructions are received.

NOTE:

"Onsite Assembly Verification" EPP-008 may be initiated at the discretion of the Shift Supervisor /ED.

4.1.2 Personnel who have evacuated from the affected area shall remain in the location evacuated to 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 from the Reactor Building.

4.2.1 Upon sounding of the Reactor Building Evacuation Alarm, all personnel will evacuate the Reactor Building and will go to the access control point located at the 412' elevation of the Control Building following red arrows.

NOTE:

Follow normal H.P. procedures upon exit of the "RCZ".

4.2.2 Following area evacuation, the Shift Supervisor will l

notify the Emergency Director of the circumstances that l

caused the sounding of the Reactor Building Evacuation l

Alarm.

4.2 3 Personnel who have evacuated the Reactor Building will be monitored for loose surface contamination, as necessary.

l Decontamination procedures will be instituted, as l

required, per EPP-010.

Radiation exposure will be l

determined and evaluated by the reading of pocket dosimeters and TLD's, if necessary.

l l

41) l l

PAGE 3 0F 7

EPP-012 REVISION 1 1/6/82 NOTE:

Sections 4 3 and 4.4 or 4 5 are to be performed g-)s simultaneously.

(,

43 Personnel accountability when evacuation of non-essential personnel from the site is required.

4.3 1 Af ter notification that 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.

4 3 1.b All non-essential personnel shall exit the plant thru the guard house, using normal exiting routine.

4 3 1.c Personnel working in the Radiation 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 manner:

4 3 2.a The Shift Supervisor, Operations Support Center rs Supervisor and Technical Support Center

(_)

Supervisor shall account for the personnel in their respective areas and report to the guard house those personnel present per Attachment II.

4 3.2.b Security personnel in the guard house will verify by badge count that all personnel other than the essential have left the station.

4 3 2.c Security will report any suspected missing personnel to the ED/SS.

4 3 2.d Suspected missing personnel shall be paged from the guardhouse.

" Attention, the following personnel report your location to Security, (Names

,) for accountability (Repeat this message) 4.3 2.e If af ter 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.

OV PAGE 4 0F 7

EPP-012

~

REVISION 1 1/6/82 4 3 2.f At the direction of the ED/SS EPP-Oll,

" Personnel Search and Rescue" shall be implemented.

4.4 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.

" All Non-Essential Personnel Evacuate the station.

Proceed to your private residence and await further instructions".

REPEAT THE ABOVE INSTRUCTION.

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 4.5 Evacuation of Non-Essential Personnel to Offsite Holding Areas (See Attachment I area map).

(At the discretion of the E.D./SS this should include personnel at Fairfield Pumped Storatge Facility).

451 The Emergency Director / Shift Supervisor shall determine which holding Area to evacuate to based on a review of prevailing wind data.

452 The Emergency Director /Shif t 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

" All Non-Essential Personnel Evacuate to Parr Steam Plant and await further instructions".

O PAGE 5 0F 7 i

EPP-012 REVISION 1 1/6/82 Repeat the above instruction.

O 4.5.2.b For the north holding area "All Non-Essential Personnel Evacuate to the Monticello Reservoir Recreational Facility and await further instructions".

Repeat the above instruction.

4.6 General guidance for conduct of evacuation.

4.6.1 Non-essential personnel will proceed through the Guard House, leave their security badges, be checked for contamination and further proceed to the off-site holding area or private residence by vehicles.

(Unless otherwise directed in a drill).

Personnel proceeding to an offsite holding area must keep their TLD and dosimeter unless otherwise directed by HP or Security.

4.6.2 The Security Shift Leader will ensure all non-essential personnel have exited the Guard House and all essential personnel have been accounted for within 30 minutes or will report the situation to the Shift Supervisor or Emergency Director who will initiate EPP-Oll, " Personnel Search and Rescue".

()

4.6 3 The Emergency Director will ensure notification of the personnel at the Fairfield Pumped Storage Facility (Phone

345-5830, 8-3644,.or 8-3639) is performed and they are instructed to take the same actions as other non-essential personnel.

4.6.4 The Emergency director will ensure that a member (s) from-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.

4.6 5 In the event of evacuation to an offsite holding area, a senior supervisor shall be assigned by the E.D. or S.S.

to maintain communications with the site and establish control at the offsite holding area if activated.

4.6.6 The Emergency Director will ensure that a person (s) qualified in personnel monitoring and' decontamination is sent to the designated off-site holding area.

O PAGE 6 0F 7

EPP-012 REVISION 1 1/6/82 4.6.6.1 The person responsible for monitoring will obtain an offsite holding area radiation lhh 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.

l 4.6.7 The Emergency Director will ensure that the Fairfield County Emergency Services Dispatcher is notified to assist in decontamination of vehicles and personnel as necessary.

4.6.8 Personnel evacuating from inside the RCA should frisk with EM-14 or portal monitor on 412' elevation control building.

Personnel evacuating the alte should monitor at the guard house using the portal monitor or RM-14.

Any Alarm Conditions on portal monitors or obvioua,

increase in count route on.RM-14 should be reported to H.P.

O 1

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EPP-012 ATTACHMENT II PAGE 1 0F 1 REVISION 1 lll ON-SITE ASSEMBLY VERIFICATION CHECKLIST DATE TIME LOCATION:

(PHONE EXT.

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TYPE AND REMARKS-AND/

BADGE UNACCOUNTED ESSENTIAL-OR LAST KNOWN NUMBER NAME PRESENT FOR LOCATION WORK LOCATION O

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SOUTH CAROLINA ELECTRIC AND GAS COMPANY O

VIRGIL C. SUMMER NUCLEAR STATION NUCLEAR OPERATIONS NUC. EAR OPECA"ONS COPY NO...... X 2 E..........

EMERGENCY PLAN PROCEDURE EPP-019 EMERGENCY EQUIPMENT CHECKLIST REVISION 1 JANUARY 6, 1982 A

NON-SAFETY RELATED Reviewed by:

ShamOM

/- 7 4 1 ORIGINATQR (of this revision)

Date

h. hh=

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QUALIFIED REVIfdER Date Approved:

W0erwffs1 tlelea PLAN ()lANAGER

/W Datfe Daw Issued: JAN. 1 H 82 REV EWED BY PSRC O 4 p 4j ily/gu Eoem iP-101-2 <1 80)

CHAIRMAN

._./ _...

DATE

EPP-019 PAGE 1 REVISION 1 1/6/82 LIST OF EFFECTIVE PAGES llh PAGE REVISION 1

1 11 1

1 1

2 1

ATTACHMENTS Attachment I - Pages 1 and 2 1

Attachment II - Pages 1 through 6 1

Attachment III - Pages 1 through 5 1

Attachment III.1 1

Attachment III.2 1

Attachment III.3 1

O Attachment III.4 - Pages 1 through 6 1

Attac hment III.5 1

Attachment III.6 - Pages 1 through 4 1

Attachment III.7 - Pages 1 through 3 1

Attachment III.8 - Pages 1 through 4 1

0

EPP-019 PAGE 11 REVISION 1 1/6/82

()

TABLE OF CONTENTS Page List of Effective Pages i

1.0 PURPOSE 1

2.0 REFERENCES

1 30 CONDITIONS AND PREREQUISITES 2

4.0 PROCEDURE 2

ATTACHMENTS ATTACHMENT I

- Control Room Emergency Equipment Checklist 1

ATTACHMENT II

- Technical Support Center Emergency Equipment Checklist ATTACHMENT III - Radiation Emergency Kit Surveillance Requirements

(_)ATTACHMENTIII.1-ControlRoomRadiationEmergencyKitEquipment Checklist ATTACHMENT III.2 - Operations Support Center Radiation Emergency Equipment Kit Checklist i

ATTACHMENT III.3 - First Aid (412' Control Bldg) Ambulance Radiation Emergency Kit Emergency Checklist ATTACHMENT III.4 - Security Annex Radiation Emergency Kit Equipment Checklist ATTACHMENT III.5 - Aux. Bldg. (436') & Fuel Handling Building (463')

Radiation Emergency Kit Equipment Checklist ATTACHMENT III.6 - T.S.C. Radiation Emergency Kit Equipment Checklist ATTACHMENT III.7 - Richland Memorial Hospital Radiation Emergency Kit-Equipment Checklist ATTACHMENT III.8 - E.O.F. Radiation Emergency Kit Equipment Checklist O

EPP-019 REVISION 1 1/6/82 1.0 PURPOSE O

1.1 This procedure establishes the actions to be taken to ensure the operational readiness of emergency equipment and supplies.

2.0 REFERENCES

AND GLOSSARY 2.1 References 2.1.1

" Virgil C. Summer Nuclear Station Radiation Emergency Plan" 2.1.2 AP-301.1, " Document Control Procedure" 2.1 3 NUREG-0654, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants 2.2 Glossary 2.2.1 Abbreviations The following abbreviations appear in the attachments to this procedure:

A.

AP

- Administrative Procedures B.

BRH - Bureau of Radiological Health C.

CHP - Chemistry Procedures D.

CR

- Control Room E.

DHEC-Department of Health and Environmental Control F.

E0A - Emergency Operations Area G.

EOC - Emergency Operations Center H.

EOF - Emergency Operations Facility I.

EOP - Emergency Operating Procedures J.

EPP - Emergency Plan Procedures K.

FHP - Fuel Handling Procedure O

PAGE 1 0F 2

EPP-019 REVISION 1 1/6/82 L.

PPP - Fire Protection Procedure O

M.

FSAR-Final Safety Analysis Report N.

GOP - General Operating Procedures 0.

HPP - Health Physics Procedure P.

LLEA-Local Law Enforcement Agency Q.

OSC - Operations Support Center R.

SCEPD-South Carolina Emergency Preparedness Division S.

SOP - Systems Operating Procedures T.

TSC - Technical Support Center U.

SCBA - Self Contained Breathing Apparatus l

t 30 CONDITIONS AND PREREQUISITES 31 None 4.0 PROCEDURE rs

%) 4.1 Surveillance of emergency equipment'shall be in accordance with the requirements specified in the attachments to this procedure.

4.2 The Emergency Coordinator shall assure that surveillance of the equipment and supplies is accomplished within the specified frequencies.

43 All discrepancies detected during surveillance activities shall be corrected within fourteen (14) days.

Those not corrected within (14) days will be brought to the attention of the Plant Manager by the Emergency Coodinator.

4.4 Upon successful completion of each surveillance requirement, acceptable results will be documentated by signing and dating in the spaces provided.

Forward completed Emergency Equipment Checklists to the Emergency Coordinator.

45 All drawings and procedures shall be controlled in accordance with AP-301.1, " Document Control Procedure".

4.6 All completed equipment checklists will be retained as permanent plant records and maintained in accordance with AP-301.2.

O PAGE 2 0F 2

p f)'

EPPP;9 ATTlivr1 MENT I s-s-

PAGE 1 of 2 REVISION 1

' CONTROL ROOM EMERGENCY EQUIPMENT CHECKLIST RESPONSIBLE SURVEILLANCE QUANTITY FREQUENCY SUPERVISOR EQUIPMENT DESCRIPTION REQUIREMENT REQUIRED SIGNATURE DATE Quarterly Operations Emergency Plan and Graphics, Overlays and.

Inventory 1 set Procedures Maps Inventory 1 set Drawings of facility and plant site Inventory 1 set First Aid Kit Inventory 1

Flashlights and batter-les Inventory 6

Portable radio Inventory and verify operability 4

Short wave transmitter Inventory and verify operability 1

Telephone Inventory and verify operability 1

1 EMERGENCY COORDINATOR Date m-

EPP-019 ATTACHMENT I PAGE 2 of 2 REVISION 1 CONTROL ROOM EMERGENCY EQUIPMENT CRECKLIST (Continued)

RESPONSIBLE SURVEILLANCE QUANTITY FREQUENCY SUPERVISOR EQUIPMENT DESC7IPTION REQUIREMENT REQUIRED SIGNATURE DATE Semi-Operations Flasnlight batteries Replace with new 12 annual batteries.

Portable radio battery Recharge or replace with fully charged battery.

N/A EMERGENCY COORDINATOR Date O

O O

'N, EPP 1

ATTA.. MENT II PAGE 1 of 6 REVISION 1 TECHNICAL SUPPORT EMERGENCY EQUIPMENT CHECKLIST RESPONSIBLE SURVEILLANCE QUANTITY FREQUENCY SUPERVISOR EQUIPMENT DESCRIPTION REQUIREMENT REQUIRED SIGNATURE DATE Quarterly Tech Support Safety parameter Verify operability display system of software 1

Computer TSC computer and TSC Verify operability displays of software 1

Tech Support Aperture card reader-Inventory and printer verify operability 1

Tech Support Copying machine Inventory and verify operability 1

Tech Support Graphs, Overlays, Maps Inventory 1 set Tech Support Log Book Inventory 1

EMERGENCY COORDINATOR Date

EPP-019 ATTACHMENT II PAGE 2 of 6 REVISION 1 TECHNICAL SUPPORT CENTER EMERGENCY EQUIPMENT CHECKLIST (Continued)

RESPONSIBLE SURVEILLANGE QUANTITY FREQUENCY SUPERVISOR EQUIPMENT DESCRIPTION REQUIREMENT REQUIRED SIONATURE DATE Quarterly Tech Support Plant Procedures Audit (cont'd.)

1-GOP 2-SOP 1 set en 3-EOP 4-EPP 5-HPP 6-FPP 7-FHP 8-CHP 9-AP Tech Support Drawings of facility and systems to the component level Audit 1 set Tech Support FSAR including the Environmental Report Audit 1 set Tech Support VCS Technical Specifi-cations lit 1

Tech Support Mitigating core damage manual Audit 1

Tech Support Precautions, Limitations and Setpoints Documents Audit 1

Tech Support State Radiological Emergency Response Plan Audit 1

EMERGENCY COORDINATOR Date O

O O

(]

EPP('S s'

\\s ATTL_. MENT II LPAGE 3 or 6 REVISION l' s

TECHNICAL SUPPORT EMERGENCY T.QUIPMENT CHECKLIST (Continued)

RESPONSIBLE SURVEILLANCE QUANTITY FREQUENCY SUPERVISOR EQUIPMENT DESCRIPTION REQUIREMENT REQUIRED SIGNATURE DATE Quarterly Tech Support County Radiological Audit (cont'd.)

Emergency Response Plan 1 - Fairfield County 1

2 - Newberry County 1

3 - Lexington County 1

4 - Richland County 1

Tech Support Title 10, Code or Federal Regulations Audit 1

Tech Support V.

C. Summer Station i

Radiological Emergency Plan Inventory 1

Emergency Potassium Iodine Inventory and Coordinator Pills check expiration date 100 (min)

EMERGENCY COORDINATOR Date

EPP-019 ATTACHMEUT II PAGE 4 of 6 REVISION 1 TECHNICAL SUPPORT EMERGENCY EQUIPMENT CHECKLIST (Continued)

RESPONSIBLE SUR'v EILLANCE QUANTITY FREQUENCY SUPERVISOR EQUIPMENT DESCRIPTION REQUIREMENT REQUIRED SIGNATURE DATE Inventory and Quarterly Emergency 6 - Plant page verify operability 1

(Cont'd.)

Coordinator Technical Support Area 1 - dedicated lines to the four Inventory and l

counties verify operability 1 ea i

2 - dedicated line to Inventory and DHEC-BRH verify operability 1

3 - dedicated line to Inventory and State EOC-SCEPD verify operability 1

4 - four telephone Inventory and lines verify operability 4

5 - telecopier Inventory and 1

verify operability 6 - plant page Inventory and 1

verify operability 7 - intercom (Tech Inventory and l

Support Area to verify operability CR, TSC and OSC) 1 l

Dose Assessment Area 1 - one telephone Inventory and line verify operability 1

2 - radio (plant)

Inventory and verify operability 1

l 3 - intercom (dose Inventory and ansessment area verify operability 1

to TSC, HP Lab, and Plant Moni-toring teams areas) 4 - Plant page Inventory and verify operability 1

EMERGENCY COORDINATOR Date O

O O

(~N EPPg9 EJ

'\\

ATTAvaMENT II PAGE 5 of 6 REVISION 1 TECHNICAL SUPPORT EMERGENCY EQUIPMENT CHECKLIST (Continued)

RESPONSIBLE SURVEILLANCE QUANTITY FREQUENCY SUPERVISOR EQUIPMENT DESCRIPTION REQUIREMENT REQUIRED SlGNATURE DATE Quarterly Emergency Communications (cont'd)

(Cont'd.)

Coordinator NRC Area 1 - Three telephone Inventory and lines verify operability 3

2 - Plant page Inventory and verify operability 1

Plant status display area 1 - Three telephone Inventory and lines verify operability 3

2 - Plant page Inventory and verify operability 1

3 - Intercom (this Inventory and area to CR, TSC verify operability 1

and OSC)

Monitoring Teams area 1 - One telephone Inventory and line verify operability 1

2 - Plant page Inventory and verify operability 1

3 - Radio (plant)

Inventory and verify operability 1

4 - Intercom Inventory and verify operability 1

EMERGENCY COORDINATOR Date

EPP-019 ATTACHMENT II PAGE 6 of 6 REVISION 1 TECHNICAL SUPPORT EMERGENCY EQUIPMENT CHECKLIST (Continued)

RESPONSIBLE SURVEILLANCE QUANTITY FREQUENCY SUPERVISOR EQUIPMENT DESCRIPTION REQUIREMENT REQUIRED SIGNATURE DATE Quarterly Emergency Communications (cont'd)

(Cont'd.)

Coordinator NSSS Area 1 - one telephone Inventory and line verify operability 1

2 - dedicated line to Inventory and Westinghouse verify operability 1

(Pittsburgh, Pa.)

3 - plant page Inventory and verify operability 1

A/E Area 1 - one telephone Inventory anC line verify operability 1

2 - dedicated line Inventory and to Gilbert Assoc.

verify operability 1

(Reading, Pa.)

3 - plant page Inventory and verify operability 1

l EMERGENCY COORDINATOR Date O

O O

EPP-019 ATTACHMENT III PAGE 1 0F 5 REVISION 0 I

I Radiation Emergency Kit Surveillance Requirements Health Physics is responsible for performing the inventory and surveillance of the radiation emergency kits listed in Attachments III.1 through III.8.

The required frequency of inventories is monthly.

Any equipment removed from these kits for the purposes of repairs, functional checks or calibration will be replaced with equivalent equipment during absence.

The following Surveillance Requirements are used during inventories to ensure that all equipment is functional.

These reouirements are coded and used to verify completion of each kit surveillance.

Any discrepancies found during the performance of inventories should be noted in the comments sections of the attached Check Lists.

The person (s) performing surveillance will ensure that each item on each check list meets or exceeds the Surveillance Requirements specified and the latest approved attachments to' this procedure are used prior to signing off each item.

Completed Check Lists will be forwarded to the Emergency Coordinator for retention and review.

Surveillance Requirements I

I Code A.

Check procedures, maps or forms listed as emergency equipment to ensure that the latest approved / issued revision is in place.

Replace as necescary.

B.

Ensure that the Hospital Survey Packet contains a minimum of:

1 - roll of rad. ribbon or approx. 100' of rad. rope 10 - 3 pocket radiation signs the inserts 100 - smears in envelopes 2 ea. - Pencil, pens, grease pencils 8 - Rad. Material labels for waste containers 10 - Blank survey maps 10 - Survey Forms (HPP-302 Att. I) 1 pr. - scissors 10 - Survey Forms (EPP-010 Att.I)

O

EPP-019 ATTACHMENT III PAGE 2 0F 5 REVISION 1

()

Code Surveillance Requirements These items may be placed in one packet, several packets or individually stored.

Ensure items listed are present prior to signoff.

C.

Ensure that equipment in " packets"/ poly bags are sealed and/or taped and labeled with the date the " packet" was sealed.

" Packets" which should be replaced due to shelf life estimates require the label to also contain the due date for replacement.

Ensure these packets are replaced no later than the month following the due date.

" Packets" with broken seals require itemized inventory inspection, and resealing prior to sign-off.

D.

Ensure individual items with estimated shelf life are labeled with the date the item was placed 11. the kit and the due date.

Replacement requirements are the same as " packets" in Surveillance Requirement C.

E.

Ensure batteries are replaced with good fresh ones or functionally tested biannually.

Ensure that batteries are stored in a manner to prevent electrical shorting (i.e. insulate terminals).

Do not leave batteries stored in instruments / equip-ment that is not designed for battery storage, bgs F.

Operability of portable survey instruments is verified during calibration on a quarterly basis in accordance with HPP-611 Calibration of Station Survey Instruments.

Verify that calibration is current during inventory.

If calibration is past due, remove the instrument af ter replacement with equivalent instrumentation.

If the calibration is due prior to the next scheduled inventory, record the due date in the comments section.

G.

Perform or ensure that the mcnthly inspection of respiratory equipment has been performed in accordance with HPP-603 Decontamination, Inspection, Maintenance, and Storage of Respiratory Equipment, prior to sign-off.

I

EPP-019 ATTACHMENT III PAGE 3 OF 5 REVISION 1 Surveillance Requirements Code H.

Ensure this tool kit packet contains a minimum of:

1 allen wrench, 4 hasps, 4 nails and 1 screwdriver / nut drive act.

I.

These items require a physical inventory and a visual inspection of condition prior to sign-off.

J.

Ensure this posting / survey ' packet' contains a minimum of:

50 - particulate air filters 2 et. - pencil, pens, grease pencils 4 - 3 pocket radiation signs with insects 50 - smears in envelopes 1 pr. - tweezers 20 - environmental envelopes 1 roll - radiation ribbon or 100 ft. of Rad rope (approx.)

1 - Record Logbook 1 - scratch pad 10 - planchets 2 - vegetation bags 1 - clipboard 10 - Labeled Air Sample Bags These items may be placed in one packet, several packets or individually stored.

Ensure items listed are present in each kit prior to sign-off.

l I

K.

Place visitor TLD's in a plastic bag and label bag with date of TLD changeout.

TLD's are to be changed monthly in conjunction with normal monthly TLD changeout.

L.

Inventory, check calibration date(s), re-zero if >20% of full scale or off scale.

M.

Inventory and functionally check charger at each battery replacement by zeroing a pocket dosimeter.

N.

First Aid Kits - Ensure each kit contains the following cotton, gauze bandage, elastic bandage, bandaids, and sponge.

O

EPP-019 ATTACHMENT III PAGE 4 0F S REVISION 1 Code O

Surveillance Requirements O.

Ensure the protective clothing ' packets' contains a minimum of the following items:

coveralls (cloth or paper) 1 pair head cover or hood 1

1 pair cloth golves (liners) 1 pair. -

rubber or work gloves (heavy) disposable gloves (light) 1 pair 1 pair disposable shoe covers 1 pair rubber shoe covers

1 box disposable gloves

This item is not included in the packet ensure it is present prior to sign off.

These ' packets' will be opened and inspected at the specified shelf life frequency.

All items will be inspected for signs of deterioration and replaced as necessary.

P.

Verify operability at 6 month intervals when batteries are replaced.

Do not store batteries in calculator or flashlight.

()

Q.

Ensure the radiation emergency monitoring kit battery " packet" contains a minimum of:

2 sets of batteries for the calculator 2 sets of batteries for the flashlight j

2 sets of batteries for each portable survey instrument l

2 ea. - 1 amp slow blow fuses for the air sampler R.

Replace the RM-14 in the kit each month with a calibrated j

instrument with a fully charged battery.

Source check the instrument prior to sign-aff.

S.

Ensure the Decon Kit includes a minimum of:

100 - Smears and envelopes 4 cans - Radeon foam (or equivalent) - Check for expiration 2 rolls - Paper towels 1 - Scratch pad 4

g

EPP-019 ATTACHMENT III PAGE 5 0F 5 REVISION 1 l

I Surveillance Requirements Code 4 - 3 pocket radiation signs with inserts 2 each - Pens, Pencils, Grease Pencils 1 - Roll of Rad ribbon 2 - Poly sheets (approx. 20' x 50')

3 - Poly bags (approx. 18" x 36")

These items may be placed in one " packet", several packets, or individually stored.

Ensure all items are present in each kit.

T.

Ensure the Off-Site Holding Area Protective Clothing ' Packets' include a minimum of:

20 pairs - Paper coveralls 20 pairs - Disposable shoe covers 20

- Paper head covers 2 rolls

- Masking tape 50 pairs - Disposable gloves (Surgeon)

These items may be placed in one " packet", several " packets", or individually stored.

Ensure all items are present in each kit.

Z.

Run Hewlett Packard 1000 Computer Program to read meteorological data and obtain a listing of latest met tower values to verify proper operation of met tower to Hewlett Packard 1000 data link l

I as outlined by EARS Program Software Package.

U.

Ensure the survey ' packet' contains a minimum of 1 - roll of Radiation Ribbon 4 - 3 pocket Radiation Signs with inserts 50 - Smears and Envelopes 2 ca - pencils, pens, grease pencils 5 pr - Disposable gloves O

EPP-019 ATTACHMENT III.1 PAGE 1 0F 1 REVISION 1 CONTROL ROOM RAOIATION EMERGENCY KIT EQUIPMENT CHECK LIST DATE PERFORMED:

ITEM EQUIPMENT

' SURVEIL.

MIN.

PERFORMED BY SIIELF DESCRIPTION REQMT.

QTY.

SIGNATURE COMMENTS LIFE 1

Self Contained Breathing 0

6 N/A Apparatus 2

SCBA Space Bottles G

6 N/A 3

Respirators (Full Face)

G 6

N/A 4

Space filter cartridges D

12 4 yr.

for full face respirators II.P. REVIEWER DATE EM ERG. COORDINATOR DATE O

O O

1

(~d.

f)

ATTACHMENT III.2

')

EPP-019 P

\\

'~s PAGE 1 0F 1 REVISION 1 OPERATIONS SUPPORT CENTER RADIATION EMERGENCY KIT EMERGENCY CHECK LIST DATE PERFORMED:

ITEM EQUIPM ENT SURVElb.

MIN.

PERFORMED BY SHELF DESCRIPTION REQMT.

QTY.

SIGNATURE COMMENTS LIFE 1

Protective clothing C,0 10 2 yr.

" packets" 2

Respirators (Full Face)

G 5

N/A 3

Space filter cartridges D

10 4 yr.

for full face respirators 4

5 rolls of Tape " packet" C

1 2 yr.

5 Flashlight P

5 N/A 6

Battery " Packet" for 5 C,E 1

6 mo.

Flashlights 7

GM Survey Meter (E-400/

F 1

N/A E-530) or equivalent 8

1 set of batteries for C,E 1

6 mo.

survey instrument 9

Vamp Area Monitor (or equiv.)

F 1

N/A 10 Cs-137 Check Source I

1 N/A 11 SCBA G

2 N/A 12 Telephone 1

Inventory & Verify Oper-N/A ability H.P. HEVIEWER DATE EMERG. COORDINATOR DATE

EPP-019 ATTACHMENT III.3 PAGE 1 0F 1 REVISION 1 FIRST AID ROOM (412' CONTROL BUILDING)

AMBULANCE RADIATION EMERGENCY KIT EQUIPMENT CHECKLIST DATE PERFORMED:

ITEM EQUIPMENT SURVEIL.

MIN.

PERFORMED BY SHELF DESCRIPTION REQMT.

QTY.

SIGNATURE COMMENTS LIFE 1

Protective Clothing C,0 4

2 yr.

Packets (Disposable) 2 Poly bags (appr.18"x36")

I 5

N/A 3

Poly bags (appr.12"x25")

I 5

N/A 4

Poly bags (appr.12"x12")

I 5

N/A 5

Poly bags (appr. 3"x6")

I 10 N/A 6

Absorbent Material I

1 N/A (36' x 20" approx.)

7 Patient Contamination A

5 N/A Forms, EPP-010 Att. I 8

Radiation Tape (roll)

I 1

N/A 9

Survey " Packet" C, U 1

N/A 10 l RM-14/HP-210 Probe (or equivalent)

F, R 1

N/A H.P.

REVIEWER DATE EMERG. COORDINATOR DATE O

O O

()

ATTACHMENT III.( )

4 PAGE 1 0F 6 REVISION 1-SECURITY ANNEX' RADIATION EMERGENCY KIT EQUIPMENT CHECK LIST DATE PERFORMED:

ITEM EQUIPMENT SURVEIL.

MIN.

PERFORMED BY SilELF DESCRIPTION REQMT.

QTY.

SIGNATURE COMMENTS LIFE 1

Radiation Emergency /Moni-2

Per listed items N/A toring Kits (Each kit to contain the following items.)

a) Posting / Survey Packet C,J l

N/A b) Poly sheets (approx.

I 2

N/A 20' x 50')

c) 2 roll masking tape C

1 2 yr.

" packet" d) Tool Kit " packet" C,H 1

N/A e) First Aid Kit N

1 N/A f) Bottles (1 liter)

I 3

N/A 137 g) Cs Check I

1 N/A Source

1) AgZ Filters (Plant D

10 4 yr.

j) AgZ Filters ( Environ-D 5

4 yr.

mental) k) Calculator P

1 N/A H.P. REVIEWER DATE EMERG. COORDINATOR DATE

EPP-019 ATTACHMENT III.4 PAGE 2 0F 6 REVISION 1 SECURITY ANNEX RADIATION EMERGENCY KIT EQUIPMENT CHECK LIST DATE PERFORMED:

ITEM EQUIPMENT SURVEIL.

MIN.

PERFORMED BY SHELF DESCRIPTION REQMT.

QTY.

SIGNATURE COMMENTS LIFE (1 Cont)l) Watch 1

- Verify Operability N/A tn ) Environmental Key (s)

I 1 set N/A n) Map of 10 mi. EPZ/

A 1

N/A Sampling Stations o) Disposable gloves I

5 pr.

N/A p) Roll of paper towels I

1 N/A g) Flashlight P

1 N/A c) Battery " Packet" C,

E, Q l

6 mo.

s) E-400/E-530 (or equiva-F 1

N/A lent) t) PIC-6A (or equivalent)

F 1

N/A u) RM-14/HP-210 probe (or F,

R 1

N/A equivalent) v) 12V Air Sampler (or F

1 N/A equivalent) w/ cables w) Low Range Dosimeter L

2 N/A (0-500 mr) x) High Range Dosimeter L

2 N/A (0-lR) y) Whole Body TLD K

2 N/A H.P. REVIEWER DATE EMERG. COORDINATOR DATE O

O O

~

(~)%

(D EPP-019 f

ATTACHMENTIII.4~)

s A/

PAGE 3 0F 6 REVISION 1 SECURITY ANNEX RADIATION EMERGENCY KIT EQUIPMENT CHECK LIST DATE PERFORMED:

1 TEM EQUIPMENT SURVEIL.

MIN.

PERFORMED BY SHELF DESCRIPTION REQMT.

QTY.

SIGNATURE COMMENTS LIFE (1 Cont) Z) Procedures / Forms A

1 ea N/A

1) EPP-004 Out of Plant N/A Radiological Surveying A

1 N/A

2) EPP-007 Environmental Monitoring A

1 N/A l

3) EPP-010 Personnel /Ve-hicle Decontamination A

1 N/A

4) EPP-020 Emergency Per-N/A sonnel Exposure Con-trol A

1 N/A l

5) Out of Plant Survey /

N/A I Sample record (EPP'004 Att. I)

A 10 N/A

6) Personnel Contamina-tion Report (EPP-010 Att. 1)

A 10 N/A

7) HPP-301 Operation or N/A Station Portable Survey Instruments A

1 N/A

8) HPP-302 Radiation and Contamination Survey Techniques A

1 N/A H.P. REVIEWER DATE EMERG. COORDINATOR DATE

r-EPP-019 ATTACllMENT III.4 PAGE 4 0F 6 REVISION 1 SECURITY ANNEX RADIATION EMERGENCY KIT EQUIPMENT CHECK LIST DATE PERFORMED:

ITEM EQUIPMENT SURVEIL.

MIN.

PERFORMED BY SilELF DESCRIPTION REQMT.

QTY.

SIGNATURE COMMENTS LIFE (1 Cont) 9) HPP-303 Airborne Activity Sampling Techniques & Procedure A

1 N/A

10) HPP-304 operation of the EIC Personnel Radiation Monitor Model RM-14 A

1 N/A H.P. REVIEWER DATE EMERG. COORDINATOR DATE e

G O

EPP-019 ATTACHMENT III.4 PAGE 5 0F 6 REVISION 1 SECURITY ANNEX RADIATION EMERGENCY KIT EQUIPMENT CHECK LIST DATE PERFORMED:

ITEM EQUIPMENT SURVElb.

MIN.

PERFORMED BY SHELF DESCRIPTION REQMT.

QTY.

SIGNATURE COMMENTS LIFE 2

Off-Site Holding Area Kit 2

Per listed items N/A

( Each kit to contain the following items.)

a) Decon Kit " Packet" C,S 1

N/A b) Protective Clothing C,T 1

2 yr.

" Packet" c) First Aid Kit N

1 N/A d) Check Source (Cs-137)

I 1

N/A e) E-400/E-530 (or equiva-F 1

N/A lent) f) 2 Sets of batteries for C,E 1

6 mo.

survey instrument

(" packet")

g) RM-14/HP-210 probe (or F,R 1

N/A equ' valent) h) Irrigation bottles I

2 N/A (500 ml)

H.P. REVIEWER DATE EMERG. COORDINATOR DATE

EPP-019 ATTACifMENT III.4 PAGE 6 0F 6 REVISION 1 SECURITY ANNEX RADIATION EMERGENCY KlT EQUIPMENT CHECK LIST DATE PERFORMED:

ITEN EQUIPMENT SURVEIL.

f1IN.

PERFORMED BY SiiELP DESCRIPTION REQMT.

QTY.

SIGNATURE COMMENTS LIFE h) Procedures / Forms A

1 ea N/A 2 (Cont) 1) EPP-010 Personnel /

N/A Vehicle Decontamination A

1 l

2) Personnel Contamination Report (EPP-010 Att. I)

A 20 N/A

3) Vehicle Survey Record (EPP-010 Att. II)

A 20 N/A

4) HPP-301 operation of Station Portable Sur-vey Instruments A

1 N/A

5) HPP-302 Radiation and Contamination Survey Techniques A

1 N/A

6) Survey Record (HPP-302 Att. I)

A 20 N/A

7) HPP-304 operation or EIC Personnel Rad.

Mon. Model RM-14 A

1 N/A

8) HPP-405 Personnel Decontamination A

1 N/A H.P.

REVIEWER EATE EMERG. COORDINATOR DATE O

O O

/"N)

EPP-019 rs, s

)

(s ATTACHMENT III.I, /

PAGE 1 0F 1 REVISION 1 AUXILIARY BUILDING (436') & FUEL HANDLING BUILDING (463')

RADIATION EMERGENCY KIT EQUIPMENT CHECK LIST DATE PERFORMED:

ITEM EQUIPMENT SURVEIL.

MIN.

PERFORMED BY SHELP DESCRIPTION REQMT.

QTY.

SIGNATURE COMMENTS LIFE 1

Aux. & FHB Kits I*

2

Ensure both Kits are inventoried Each kit will contain the following:

1.1 Protective Clothing C,0 10 2 yr.

" Packets" 1.2 Respirators ( Full Face)

G 5

N/A 13 Space filter cartridges D

10 4 yr.

for full face respirators 1.4 5 roll - masking tape C

1 2 yr.

" packet" H.P. IlEVIEWER DATE EMERG. COORDINATOR DATE

EPP-019 ATTACHMENT III.6 PAGE 1 OF 4 REVISION 1 T.S.C.

RADIATION EMERGENCY KIT EQUIPMENT CHECK LIST DATE PERFORMED:

ITEM EQUIPMENT SURVEIL.

MIN.

PERFORMED BY SHELF DESCRIPTION REQMT.

QTY.

SIGNATURE COMMENTS LIFE 1

S.C.B.A.

G 8

N/A 2

S.C.B.A.

Spare Bottles G

8 N/A 3

Respirators (Full Face)

G 8

N/A 4

Spare filter cartridges D

16 4 yr.

for full face respirators 5

Radiological and meteoro-Z l

N/A logical data computer 6

Whole Body TLD's K

25 N/A 7

Extremity TLD Holders I

15 N/A (for ankle or wrist) 8 High Range Dosimeter L

25 N/A (0-5R) 9 Low Range Dosmeter L

25 N/A (0-500mr) 10 Dosimeter charger with 2 D,M,E 1

6 mo.

"D" cell batteries batt.

attached ll PIC-6A (or Equivalent)

F 1

N/A 12 E-400/E-530 (or F

1 N/A (Equivalent)

H.P. REVIEWER DATE EMERG. COORDINATOR DATE O

O O

()T EPP-019

(~l ATTACHMENT III.6' '

s PAGE 2 0F 4 REVISION 1 T.S.C. RADIATION EMERGENCY KIT EQUIPMENT CHECK LIST DATE PERFORMED:

ITEM EQUIPMENT SURVEIL.

MIN.

PERFORMED BY SHELF DESCRIPTION REQMT.

QTY.

SIGNATURE COMMENTS LIFE 13 Portable P&I Air Samplers FR 2

Ensure P&I adaptor is N/A present 14 2 sets of batteries for C,E 1

6 mo.

high range survey instru-ment and 2 sets of bat-teries for low range survey instrument in a

" packet" 15 First Aid Kits N

2 N/A 16 Flashlights P

10 N/A 17 Battery " Packet" for 10 C,E.

1 6 mo.

Flashlights 18 5 rolls of Tape " Packet" C

1 2 yr.

19 Protective Clothing C,0 25 2 yr.

" Packet" 20 Survey ' packets' U

2 N/A 21 Alarming Dosimeter F

2 N/A 22 Plastic P.C. Set D

10 2 yr.

23 Particulate air filters I

10 N/A 24 AgZ Filters (Plant)

D 10 4 yr.

H.P.

HEVIEWER DATE EMERG. COORDINATOR DATE

EPP-019 ATTACHMENT III.6 PAGE 3 0F 4 REVISION 1 T.S.C.

RADIATION EMERGENCY KIT EQUIPMENT CHECK LIST DATE PERFORMED:

1 TEM EQUIPM ENT SURVElb.

MIN.

PERFORMED BY SHELP DESCRIPTION REQMT.

QTY.

SIGNATURE COMMENTS LIFE 25 Air Sample Results Log (HPP-404 Att. II)

A 20 N/A 26 Personnel Contamination Report (HPP-405 Att. 7)

A 20 N/A 27 Perimeter Survey (HPP-410 Att. V)

A 20 N/A 28 Rad Work Permit (AP-702 Att. I)

A 10 N/A 29 (S)RWP Signature Att (AP-702 Att. III)

A 10 N/A 30 Self Read. Dos. Card (AP-703 Att. I)

A 50 N/A 31 Auth. {Co Excead Exp.

Limits A

10 N/A 32 Resp. Issue Log (AP-705 Att. I)

A 10 N/A 33 Air. Rad Area Entry Log (AP-706 Att. I)

A 10 N/A 34 Cs-137 Check source I

1 N/A 35 Survey Record (HPP-302 Att. I)

A 50 N/A H.P. REVIEWER DATE EMERO. COORDINATOR

.DATE O

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EPP-019 ATTACllMENT III.7 PAGE 1 OF 3 REVISION 1 RICHLAND MEMORIAL HOSPITAL RADIATION EMERGENCY KIT EQUIPMENT CliECKLIST DATE PERFORMED:

ITEM EQUIPMENT SURVEIL.

MIN.

PERFORMED BY SIIELP DESCRIPTION REQMT.

QTY.

SIGNATURE COMMENTS LIFE 1

E400/E530 (or equivalent)

F 1

N/A 2

Pic-6A (or equivalent)

F 1

N/A 3

Dosimeter charger with 2 "D"

cell batteries attached D,M,E 1

6 months (Battery) 4 Low Range Dosimeter (0-500 MR)

L 6

N/A 5

High Range Dosimeter (0-lR)

L 2

N/A 6

Respirators (Full Face)

G 6

N/A 7

Spare Full Face Filter Cartridges D

12 4 year 8

IIospital survey Packet A,C,B 1

N/A 9

Disposable Shoe Covers I

25 pr.

N/A 10 Waste Containers (Liquid) with lids I

2 N/A 11 Waste Containers ( Solid) with lids I

2 N/A H.P. REVIEWER DATE EMERG. COORDINATOR DATE O

O O

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(~')

EPP-019

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ATTACHMENT III.7'-

PAGE 2 0F 3 REVISION 1 RICHLAND MEMORIAL HOSPITAL RADIATION EMERGENCY KIT EQUIPMENT CHECKLIST DATE PERFORMED:

i 1 TEM EQUIPMENT SURVEIL.

MIN.

PERFORMED BY SHELF DESCRIPTION REQMT.

QTY.

SIGNATURE COMMENTS LIFE 12 Decon Solution D,

I 5 gal.

As Labled 13 Movable Shield 1" steel with 4" Lead glass window I

1 N/A 14 Lead Container Approx.

6"x8" I

1 N/A 15 Decontamination Tabletop I

1 N/A 16 Portmble Cart I

1 N/A 17 Blotter Paper I

1 roll N/A 18 5 rolls of tape " Packet" C

2 2 years 19 Herculite approx.

~

10'x100' I

1 N/A 20 Polyethylene I

1 roll N/A 21 Poly Bags approx (38"x63") (yellow, labled)

I 10 N/A 22 Protective clothing

" packets" (Disposable)

C,0 10 2 year 23 Cs-137 Check Source I

1 N/A H.P. REVIEWER DATE EMERG. COORDINATOR DATE

EPP-019 ATTACHMENT III.7 PAGE 3 OF 3 REVISION 1 RICHLAND MEMORIAL HOSPITAL RADIATION EMERGENCY KIT EQUIPMENT CHECKLIST DATE PERFORMED:

ITEM EQUIPMENT SURVEIL.

MIN.

PERFORMED BY SHELF DESCRIPTION REQMT.

QTY.

SIGNATURE COMMENTS LIFE 24 Battery ' packet' to contain two complete sets of batteries for instruments (Item #1 & 2)

C,E 1

6 months H.P. REVIEWER DATE EMERG. COORDINATOR DATE t

O O

O

p p

EPP-019 (G

ATTACHMENT III.fid PAGE 1 0F 4 REVISION 1 E.O.F. RADIATION EMERGE!!OY KIT EQUIPMENT CHECK LIST DATE PERFORMED:

ITEM EQUIPMENT SURVEIL.

MIN.

PERFORMED BY SHELP DESCRIPTION REQMT.

QTY.

SIGNATURE COMMENTS LIFE 1

Radiation Emergency /Moni-2

Per listed items N/A toring Kits (Each kit to contain the following items.)

a) Posting / Survey Packet C,J l

N/A b) Poly sheets (approx.

I 2

N/A 20' x 50')

c) 2 roll masking tape C

1 2 yr.

" packet" d) Tool Kit " packet" C,H 1

N/A e) First Aid Kit N

1 N/A f) Bottles (1 liter)

I 3

N/A l37 g) Ca Check I

1 N/A Source

1) AgZ Filters (Plant D

10 4 yr.

j) AgZ Filters ( Environ-D 5

4 yr.

mental) k) Calculator P

1 N/A H.P. REVIEWER DATE EMERG. COORDINATOR DATE

EPP-019 ATTACHMENT III.8 PAGE 2 0F 4 REVISION 1 E.O.P.

RADIATION EMERGENCY KIT EQUIPMENT CHECK LIST DATE PERFORMED:

ITEM EQUIPMENT SURVEIL.

MIN.

PERFORMED BY SHELF

//

DESCRIPTION REOMT.

QTY.

SIGNATURE COMMENTS LIFE (1 Cont)l) Watch 1

- Verify Operability N/A m) Envitonmental Key (s)

I L set N/A n) Map of 10 mi. EPZ/

A 1

N/A Sampling Stations o) Disposable gloves I

5 pr.

2 yr.

p) Roll of paper towels I

1 N/A q) Flashlight P

1 N/A c) Battery " Packet" C, E, Q l

6 mo.

s) E-400/E-530 (or equiva-F 1

N/A lent) t) PIC-6A (or equivalent)

F 1

N/A u) RM-14/HP-210 probe (or F, R 1

N/A equivalent) v) 12V Air Sampler (or F

1 N/A equivalent) w/ cables w) Low Range Dosimeter L

2 N/A (0-500 me) x) High Range Dosimeter L

2 N/A (0-lR) y) Whole Body TLD K

2 N/A H.P. REVIEWER DATE EMERG. COORDINATOR DATE i

O O

O

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EPP-019

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ATTACHMENTIII.6-)

(_/

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PAGE 3 0F 4 REVISION 1 E.O.F. RADIATION EMERGENCY KIT Ef3IPMENT CHECK LIST DATE PERFORMED:

ITEM EQUIPMENT SURVEIL.

~ MIN.

PERFORMED BY SilELP DESCRIPTION REQMT.

QTY.

SIGNATURE COMMENTS LIFE (1 Cont) Z) Procedu res/ Fo rms A

1 ea N/A

1) EPP-004 Out of Plant N/A Radiological Surveying A

1 N/A

2) EPP-007 Environmental Monitoring A

1 N/A

3) EPP-010 Personnel /Ve-hicle Decontamination A

1 iUA

4) EPP-020 Emergency Per-N/A sonnel Exposure Con-trol A

1 N/A

5) Out of Plant Survey /

N/A Sample record (EPP-004 Att. I)

A 10 N/A

6) Personnel Contamina-tion Report (EPP-010 Att. I)

A 10 N/A

7) HPP-301 Operation of N/A Station Portable Survey Instruments A

1 N/A

8) HPP-302 Radiation and Contamination Survey Techniques A

1 N/A H.P. REVIEWEE DATE EMERG. COORDINATOR DATE a

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SOUTH CAROLINA ELECTRIC AND GAS COMPANY VIRGIL C. SUMMER NUCLEAR STATION NUCLEAR OPERATIONS NUCiEAR 0?iRAT OXS COPY No....... g 7p...........

EMERGENCY PLAN PROCEDURE EPP-021 ACTIVATION OF THE EARLY WARNING SIREN SYSTEM (EWSS)

REVISION 0 SEPTEMBER 10, 1981 NON-SAFETY RELATED O

Reviewed by:

/ 7 f)

ORIGINATOR (5T this revision)

/ Ddte l

l QUALIFIED RENTIEWER Date Approved:

WhmA nlsls2 P

MANAGER Da'Je l

l Date Issued: JAN.19 M82 REV EWED 3Y PSRC

~

f g

Form AP-101-2, (1/80)

CHAIRMAN _. _

MM

EPP-021 PAGE i REVISION 0 9/10/81 h

LIST OF EFFECTIVE PAGES Revision P_ age a

1 0

11 0

1 0

2 0

3 0

ATTACHMENTS Attachment I O

Attachment II O

Attachment III O

O O

EPP-021 PAGE 11 REVISION O 9/10/81 TABLE OF CONTENTS Page List of Effective Pages i

1.0 PURPOSE 1

2.0 REFERENCES

1 3.9 CONDITIONS AND PREREQUISITES 1

4.0 PROCEDURES 1

ATTACHMENTS Recommendation for Activation of the EWSS Attachment I Message for the Evacuation of the Recreational Attachment II Facilities on Monticello Reservoir.

O Attachment III -

Authorization List O

~

EPP-021 REVISION O 9/10/81 1.0 PURPOSE O

1.1 To provide guidance for the activation of the Early Warning Siren System.

(EWSS)

2.0 REFERENCES

2.1

" Virgil C. Summer Nuclear Station Radiation Emergency Plan".

2.2

( A.C. A) Alerting Communicators of America Operations Manual.

2.3 EMP-170.003, " Electrical Maintenance Procedure", Warning Siren Maintenance.

2.4 Plectron Remote Control Head (Siren Interface) Model No. G8 Operations Manual.

2.5 EPP-001, " Activation and Implementation of Emergency Plan" 2.6 EPP-002, " Communication and Notification".

2.7 EPP-005, "Offsite Dose Calculations".

3.0 CONDITIONS AND PREREQUISITES 3.1 A release of radioactive materials from the plant has commenced lll or has increased to levels which will subject portions of the Emergency Planning Zones to doses equal to or exceeding levels established by the Environmental Protection Agency that recommend certain public actions as per Reference 2.7.; or, as a precautionary measure as deemed necessary by the Interim Emergency Director / Emergency Director.

3.2 The I.E.D/E.D. shall ensure that actions in Reference 2.1, 2.5, 2.6, and 2.7 are being or will be carried out.

l 4.0 PROCEDURES 4.1 The communicator, under direction of the IED/ED, shall refer to Att. III and determine the applicable county official who may authorize activation of the EWSS.

4.2 The communicator shall complete sections 1 and 2 of Att.

I.

4.3 The communicator shall contact the applicable county by the dedicated phone line for that county; or, if unavailable, by regular land line (Refer to Reference 2.6 for phone numbers).

O PAGE 1 0F 3

EPP-021 REVISION 0 9/10/81

({}4.4 The communicator shall read sections 1 and 2 of Att. I to the person contacted.

4.5 When authorization to activate the EWSS is granted by an appropriate county official as per Att. III, the communicator shall complete section 3 of Att. I.

4.6 The communicator shall sign the Att. I and return the Attachment to the Emergency Director.

4.7 The ED shall sign the Att. I and direct an individual to activate the EWSS.

4.8 The designated individual should obtain the EWSS key from the Shift Supervisor's security key box and insert the key into the slot on the EWSS panel in the Control Room and turn key to the right to power the EWSS panel.

4.9 Push the appropriate button:

4.9.1 Fairfield County eirens will be activated by pushing buttons numbered 1, 3, and 5_.

4.9.2 Newberry County sirens will be activated by pushing the buttons numbered 4 and 6.

(',j 4 9.3 Lexington County sirens will be activated by pushing the T

button numbered 7.

4.9.4 Richland County sirens will be activated by pushing the button numbered 8.

NOTE:

The activated sirens will sound for three(3) minutes each time the button (s) is pushed.

If a wrong button is pushed, the button numbered 10 will cancel the signal if pushed within one(1) second of the wrong push.

4.10 To activate the speaker systems and tne flashing red lights at the two recreational facilities on Monticello Reservoir, the designated individual should:

4.10.1 Wait until a three minute cycle of the sirens has ended.

4.10.2 Announce over the operations radio frequency:

Attention all personnel.

Do not use your radios until otherwise instructed.

Do not, I repeat, Do not use your radios until otherwise instructed.

(_3 f

)

PAGE 2 OF 3

EPP-021 REVISION 0 9/10/81 4.10.3 Push button numbered 9 on the EWSS panel and hold down.

O h.10.4 Key the microphone on the Control Room base radio to activate the speaker system.

4.10.5 Read the message on Att. II over the speaker system, if applicable.

4.11 To deactivate speaker system, let up on the microphone key and button numbered 9 on the EWSS panel.

4.12 Announce over the operations radio that all personnel are now cleared to use their radios.

4.13 If not during daylight hours, request Security to shoot flares over Monticello Reservoir.

O I!I PAGE 3 0F 3

EPP-021 ATTACHMENT I PAGE 1 0F 1 REVISION O Date Time

{)

RECOMMENDATION FOR ACTIVATION OF THE EWSS 1.

This is Name Title 2.

An event is in progcess at the V. C. Summer Nuclear Station that warrants the recommendation by the Emergency Director to activate Name Title the Early Warning Siren System in County.

We request that County Official From Att. III Title authorize the activation of the Early Warning Siren System for his/her county.

This is an urgent matter that requires a decision within the next (15) fifteen minutes.

3.

County official authorizing activation of EWSS Name (ensure this person is listed in Att. IV)

Title County O

Authorization given Date Time Communicator

/

Date Time Emergency Director

/

Date Time NOTE:

Use Reference 2.6 for land line telephone numbers if dedicated lines fail.

O

EPP-021 ATTACHMENT II PAGE 1 0F 1 REVISION 0 Message for the Evacuation of the Recreational Facilities on Monticello Reservoir.

l.E.D./E.D. Signature Date Time Attention all personnel.

Attention all personnel.

This is the V. C. Summer Nuclear Station.

An event i

is in progress at the plant that requires evacuation of the Monticello Reservoir Recreational Areas.

You are requested to leave the lake area.

Turn on your radio or television to an Emergency Broadcasting Station for more information.

Drive safely.

Don't panic.

You are not in any immediate danger.

O Repeat message.

Communicator's Signature Date Time 0

EPP-021 ATTACHMENT III PAGE 1 0F 1 REVISION 0 V("%

AUTHORIZATION LIST (County Officials with Approval Power to activate the EWSS).

FAIRFIELD COUNTY R. B.

(Bud) Cooper, Chairman, County Council Donald P.

(Rusty) Reed, County Administrator George Douglas, Director, Disaster Preparedness In the event that the aforementioned agency parties are not available, the utility is authorized to act as Fairfield County's agent in the activation of the EWSS.

NEWBERRY COUNTY Thomas E.

(Tommy) Longshore, Jr. Public Safety Director David C. Waldrop, Jr., Public Safety Department Deputy Director E. F. Lominack, Jr., County Administrator L. L. Henderson, Sheriff RICHLAND COUNTY O

\\_/ Hugh K. Boyd, Jr., Director Joyce F. Goodwin, Administrative Assistant LEXINGTON COUNTY (Uncer signature of Charles A. Whitehead, Director - Public Safety Department).

The aforementioned has delegated that two telecommunications operators are on duty 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months per day in the Central Communication Center in the County Emergency Operations Center.

These operators are authorized to render the county's decision based on the Company's estimate of the situation, emergency classification and recommendations.

NOTE:

Use Reference 2.6 for land line telephone numbers if dedicated lines fail.

I SOUTH CAROLINA ELECTRIC AND GAS COMPANY VIRGIL C. SUMMER NUCLEAR STATION NUCLEAR OPERATIONS OC EAR 0?E7K 0YS CO PY No....... /.5.. 7..f........

EMERGENCY PLAN PROCEDURE EPP-022 VERIFICATION OF COMMUNICATIONS OPERABILITY REVISION 0 SEPTEMBER 11, 1981 NON-SAFETY RELATED O

Reviewed by:

/ V 2? -

A ORIGINATOR (of this revision)

/ Dg,s l

k QUALIFIED REVIEWER

' Date Approved:

MOwxv4 i/e/s2_

Date PLg MANAGER /vy

{[hfC,)

b D

Date Issued: JAN.1 91909 Form AP-101-2, (1/80) p O

= " "

9, e

EPP-022 PAGE i REVISION 0 9/11/81 h

LIST OF EFFECTIVE PAGES h

Revision 1

0 11 0

1 0

2 0

ATTACHMENTS Attachment I, Pages 1 through 3 0

O l

I l

l 9

l l

l t

EPP-022 PAGE 11 REVISION O 9/11/81 O

TABLE OF CONTENTS M

List of Effective Pages i

1.0 PURPOSE 1

2.0 REFERENCES

1 3.0 CONDITIONS AND PREREQUISITES 1

I 4.0 PROCEDURES 2

ATTACHMENTS ~~

Attachment I - Verification of Communications Operability O

I O

EPP-022 REVISION 0 9/11/81 1.0 PURPOSE

.O 1.1 To provide guidance for verifying that communications designated for use during an emergency are functional.

1.

2 To provide for a method to document the tests of the emergency communication equipment.

2.0 REFERENCES

2.1 Virgil C.

Summer Nuclear Station Radiation Emergency Plan.

2.2 NUREO - 0654/ FEMA REP-1, Criteria for Preparation and Evacuation of Radiological Emergency Response plans and Preparedness in support of Nuclear Power Plants.

23 EPP-001, " Activation and Implementation of Emergency Plan" 2.4 EPP-002, " Communication and Notification" 2.5 EPP-021, " Activation of the Early Warning Siren System" 2.6 CEP-007, "(EOF) Equipment and Supply Inventory, Procedure" 3.0 CONDITIONS AND PREREQUISITES 3.1 The required frequency for verification cormunications operability is as follows:

A.

Communications with state and counties within a 10 mile plume exposure (EPZ) Emergency Planning Zone, will be tested monthly.

B.

Communications with Federal and State Agencies within the 50 mile Ingestion (EPZ) Emergency Planning Zone, will be tested quarterly.

C.

Communications between Summer Station, State, County emergency operations centers and Radiation Monitoring Team (s) will be tested annually.

D.

Telephone numbers referenced in EPP-002, Communication and Notification will be updated quarterly.

3.2 The Emergency Coordinator is responsible for the conduct of all communications tests addressed in this procedure and the documentation thereof.

O PAGE 1 0F 2

EPP-022 REVISION 0 9/11/81 3

If a substantial loss of off-site communications is identified, 03 refer to reference 2.3.

4.0 PROCEDURES 4.1 The Emergency Coordinator or his designee shall test each mode of communication as per Attachment I on a frequency as specified in Section 3.1 of this procedure.

4.2 The person performing the test should sign the appropriate space on the Attachment I if the communication link is operable.

4.3 The person performing the test should write "00S" (out-of-service) in the appropriate space on the Attachment I if the communication link is inoperable and contact the applicable maintenance group for repair.

4.4 Where applicable, the person performing the test should require all off-site persons contacted to return the call within two minutes to verify the proper person / agency has been reached.

45 Completed checklists should be filed in the Emergency Coordinator's office.

4.6 Any equipment found inoperable shall be reported to the Shift Supervisor.

)

4.7 When the equipment has been repaired, the Emergency Coordinator or his designee shall test the equipment and document the test in his files.

PAGE 2 0F 2

EPP-022 ATTACHMENT I PAGE 1 0F 3 REVISION 0 VERIFICATION OF COMMUNICATIONS OPERABILITY lll Monthly Communications Test Date Signature of Verification Dedicated Lines 1.

State Emergency Operations Center 2.

State Forward Emergency Operations Center 3

Fairfield County 4.

Newberry County 5

Richland County 6.

Lexington County 7.

BRH-DHEC 6.

NRC 9.

Westinghouse

10. Gilbert Other 1.

Plant Alarms a.

Fire Alarms b.

Reactor Building Evacuation c.

Radiation Emergency Alarm 2.

Data Display System O

EPP-022 ATTACHMENT I PAGE 2 OF 3 REVISION 0

()

VERIFICATION OF COMMUNICATIONS OPERABILITY Quarterly Communications Test Date Signature of Verification 1.

Vital Personnel Phones A.

Station Manager B.

Supervisor of Nuclear Information C.

General Manager, Nuclear Operations D.

Emergency Planning Coordinator 2.

Verify telephone numbers in EPP-002 3

Nuclear Operations Radio System 4.

Telecopiers e

A.

TSC

(~)

v B.

EOF 5

Gai-tronics System 6.

Other paging systems 7. LLEA Network 8.

Health Physics Network Phones i

i

I EPP-022 ATTACHMENT I PAGE 3 0F 3 REVISION 0 VERIFICATION OF COMMUNICATIONS OPERABILITY gg)

Annual Communications Test Date Signature of Verification 1..

S. C. Fo rward E. O.C.

2.

Fairfield E.O.C.

3.

Newberry E.O.C.

4.

Richland E.O.C.

5.

Lexington E.O.C.

6.

Off-Site Radiation Monitoring Radios 7.

Environmental Monitoring Radios O

O L.

ML20041A317

Text

2.0 REFERENCES

2.0 REFERENCES

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

2.0 REFERENCES

2.0 REFERENCES

2.0 REFERENCES

2.0 REFERENCES

2.0 REFERENCES

2.0 REFERENCES

2.0 REFERENCES

2.0 REFERENCES

2.0 REFERENCES

2.0 REFERENCES

2.0 REFERENCES

2.0 REFERENCES

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