Text

Revised Emergency Plan Procedures,Including Updated Index, Rev 12 to EPP-002 Re Communications & Notifications,Rev 8 to EPP-005 Re Offsite Dose Calculations & Rev 4 to EPP-009 Re Onsite Medical
	ML20116B119
Person / Time
Site:	Summer
Issue date:	04/08/1985
From:	Dixon O; SOUTH CAROLINA ELECTRIC & GAS CO.
To:	Grace J; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
	PROC-850408, NUDOCS 8504250033
	Download: ML20116B119 (135)
	v • d • e

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VIRGIL C. SUMMER NUCLEAR STATION NUCLEAR OPERATIONS PROCEDURES EMERGENCY PLAN PROCEDURES TABLE OF CONTENTO PROCEDURE DATE NUMBER PROCEDURE TITLE REVISION ISSUED EPP-001 Activation and Implementation of Emergency Plan 7 8/24/84' EPP-002 Communication and Notification 12 3/29/85 ~ EPP-003 In-Plant Radiological Surveying 4 7/24/84 EP.-004 Out-of-Plant Radiological Surveying 5 7/24/84 EPP-O'05 Offsite Dose Calculations 8 4/2/85 EPP-006 Transportation Accidents Involving Radioactive Material 0 2/7/85 [JT EPP-007' Environmental Monitoring 2 8/21/84 EPP-009 On-Site Medical 4 4/2/85 ~ EPP-010 Personnel / Vehicle Decontamination 4 7/24/84 EPP-011 Personnel Search and Rescue 3 7/24/84 EPP-012 Onsite Personnel Accountability. & Evacuation 5 7/24/84 EPP-013 Fire Emergen'cy 4 7/24/84 EPP-014 Toxic Release 2 7/24/84 i EPP-015 Natural Emergency (Earthquake, Tornado) 5 2/27/85 EPP-016 Emergency Facilities Activation & Evacuation 6 1'0/6/84 EPP-017 4 Post-Recovery and Re-Entry 5' 7/24/84 'EPP-018 Emergency Training and Drills 4 8/2/84 EPP-019 Er.ergency Equipment Checklist 6 3/30/85 EPP-020 Emergency Personnel Exposure Control 4 7/27/84 ' n(

Safety Related Procedure 8504250033 850408 th06 PDR ADOCK 05000395 y

F PDR g

i s PROCEDURE DATE NUMBER PROCEDURE TITLE REVISION ISSUED ' EPP-021 Activation of the Early Warning Siren. System (EWSS) 6 4/30/84 EPP-022 Verification of Communications Operability 5 11/15/84 4 h e e l l e h 1 L l f E G

1 SOUTH CAROLINA ELECTRIC AND GAS COMPANY VIRGIL C. SUMMER NUCLEAR STATION NUCLEAR OPERATIONS NUCl.El.2 C?ERATIONS COPY No..... 5 1 - ~ ~ ~- EMERGENCY PLAN PROCEDURE EPP-002 COMMUNICATION AND NOTIFICATIONS REVISION 12 JANUARY 23, 1985 SAFETY RELATED O ~ JJM DISCIP(INE SUP3iWISOR / DKte hYW W APPROVAL AUTHORITY Date MAR 2 9 togg ( DATE ISSUED RECORD OF CHANGES l CHANGQ TYPE DATE DATE CHANGE TYPE DATE DATE NO. CHANGE APPROVED CANCELLED NO. CHANGE APPROVED CANCELLED f e G e Aay -c--y ,5 yy--,7--w-w--- f wqg pu 9 yy,5g-.ye.--,9y-.y,m y-.y 9 p _gp,, ,,----g-y--p m4g-- -. 9w-- 9-w--~ -. --

EPP-002 PAGE i f-x REVISION 12 tj 1/23/85 TABLE OF' CONTENTS PAGE 1.0 PURPOSE 1,

2. 0 REFERENCES 1

3.0 DEFINITIONS 1 4.0 PREREQUISITES 2

5. 0 PROCEDURE 2

51 Initial Notifications 2 52 Notifications for Change of Emergency Classification 3

5. 3 Off-site Emergency Services 4

5. 4 Follow-up Notifications 4

(-~ s 5.5 Vital Personnel Notification 5

5. 6 TSC/OSC/ EOF Communications 5

ATTACHMENTS Attachment I - Warning Mescage: Nuclear Facility-to State / Local Government Part I Attachment IIA - Warning Message: Nucleat: Facility to State / Local Government Part II Attachment IIIA-Initial Notification-Notification of Unusual Event Attachment IIIB-Initial Notification - Alert Attachme,nt IIIC-Initial Notification-Site Area Emergency Attachment IIID-Initial Notification-General Emergency-Attachment IVA - NRC One-Hour Notification Attachment IVB - ANI Eight-Hour Notification S 9 1

EPP-002 PAGE 11 REVISION 12 1/23/85 TABLE OF CONTENTS (Continued) Attachment V - Off-Site Emergency Services Attachment VIA - Follow-up Notifications - Alert Attachment VIB - Follow-up Notifications - Site Area Emergency -Attachment VIC - Follow-up Notifications - General Emergency Attachment VII - TSC/OSC Emergency Telephone List Attachment VIII-Off-Site Emergency Telephone List O-O i-a l l- { ~ 1 l l l lO b L l L

) EPP-002 5 REVISION 12 , ~\\ 1/23/85 l.0 PURPOSE 1.1 The purpose of this procedure is to delineate the specific notification requirements for each class of emergency and to provide a method for affecting these notifications.

2.0 REFERENCES

2.1' " Virgil C. Summer Nuclear Station Radiological Emergency Plan"

2. 2 NUREG-0654, " Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants" 23 EPP-001, "Activiation and Implementation of the Emergency Plan"

2. 4 Voluntary Assistance Agreement (by and among Electri.c Utilities involved in Nuclear Generation) - Article 9 -

Transportation of Nuclear Materials;, and Emergency Resources Manual, "INP0" Institute of Nuclear Power. Operations. [~') 25 Station Directive No. 25 Issuance, Control, and Usage of \\/ Radio Pagers. m 30 DEFINITIONS AND ABBREVIATIONS 3.1 Definitions 3 1.1 Initial Notification - The transfer of information to designated organization (s)/ person (s) following change of plant status from normal operations directly into any of the four emergency classifications or upon escalation to a higher emergency classification. This transfer of information is required to begin within fifteen minutes after declaration of the applicable emergency classification. O PAGE 1 0F 5 V . _. ~ -, _, w = "r'~

EPP-002 REVISION 12 f 1/23/85 v' EXCEPTION: (1) The NRC, Bethesda, Maryland office and the Site Resident Inspector are to be notified within 1 hour of declaration of the event in accordance with Attachment IIA. 2) The American Nuclear Insurers (ANI) is to be notified within eight (8) hours of declaration of an Alert, Site Area Emergency, or General Emergency in accordance with Attachment IIB. 3 1.2 Follow-up Notification - The transfer of information to designated organization (s)/ person (s) updating the intitial notification. This transfer of infornation is required at 15 minute intervals following completion of initial or previous follow-up notifications. EXd5PTIONS: Following initial notification of the NRC, an cren communication line will be established and maintained to provide continuous updating to the NRC. Follow-up notifications are not required for the Notification of Unusual Event (N.U.E.) classification. 32 Abbreviations . *q-) 3 2.1 TSC - Technical Support Center 3 2.2 OSC - Operations Support Center 323 EOF - Emergency Operations Facility 3.2.4 ED - Emergency Director 325 IED-Interim Emergency Director ~ 3 2.6 E.'O.C-Emergency Operations Center 4.0 PREREQUISITES and CONDITIONS 4.1 Unusual or abnormal plant or site conditions exist.which necessitate implementation of the Emergency Plan and the applicable Emergency Classification has been declared. 50 PROCEDURE 5.1 Initial Notifications ("' (m-)/ PAGE 2 0F 5

EPP-002 REVISION 12 f-s 1/23/85 d 5.1.1 Upon declaration of the appropriate emergency classification, the ED/IED will direct the communicator to implement the appropriate notifications. NOTE: Refer to EPP-016 Attachment II for personnel, by title, who should be the designated communicator. 51.2 The ED/IED will assure that the required information is available to effect prompt notification. 513 The communicator will, upon direction from the ED/IED, implement the initial notifications. The information in Attachment I is to be given to the personnel / agencies as listed in Attachments III A, III B, III C, or III D depending upon the classification of emergency. NOTE: Attachments III, IV and V list alternates for various personnel. These notifications attempts are to be made in numerical sequence as indicated and will be considered g-'g complete upon successful notification of one ( j of the listed.

5. '2 Notifications for Change in Emergency Classification NOTE:

If classification change is made in the middle of a notifications sequence the communicator will terminate that notification sequence, and initiate the new notification for current status. 5 2.1 Upon escalation to a higher emergency classification, the communicator will, upon direction from the ED, implement notifications per the section of Attachment III which corresponds to the higher emergency classification, and Attachments IVA and IVB. 5 2.2 When the emergency classification is downgraded,- the communicator will, upon direction from the ED, implement notifications per the section of ~ Attachment VI which corresponds to the classification which is being changed. I b i,/ PAGE 3 0F 5 ~ +, ir .-e.- ,,-,-.r - - ~ - - r T

EPP-002 REVISION 12 1/23/85 53 Off-site Emergency Services 5.3 1 Upon direction from.the ED/IED, the communicator-will implement the requested notification (s) per Attachment V.

5 3.2 Upon direction from the ED/IED, the communicator J

will contact other utilities for assistance using ~ -the "INP0" Resource Guide, Reference 2.4. NOTE: The Resource Guide is available in the TSC and EOF. 5.4 Follow-up Notifications' 5.4.1 Follow-up notifications are required for all emergency classifications except N.U.E. 5 4.2 The communicator will implement follow-up notifications.. (The information in Attachment I and II.is to be given to the personnel / agencies as listed in Attachments VI A, VI B, or VI C depending upon the emergency classification. ) 5.4.3 Follow-up notifications will be made by.the site [- communicator (s) until the EOF is activated and s assumes all off-site notification responsibilities. Thereafter, the site communicator will transmit applicable updated information to the EOF as it becomes available. 5.4.4 Follow-up notifications to the Emergency Preparedness Division and the counties shall be made by the TSC or EOF Communicator until such time that the'S.C. State. Forward EOC is staffed and communications are established. "When the S.C. Forward E.O.C. is activiated, all communications, between the plant and state and county agencies will go to the S.C. Forward E.O.C. via the dedicated phone 11netor established land line. NOTE: All transfers of notification responsibilities shall be documented. () PAGE 4 0F 5

EPP-002 REVISION 12 1/23/85 0 55 Vital Personnel Notification'- 5 5.1 ~ The communicator will notify vital personnel as directed by the ED/IED per the Vital Personnel Telephone Listing available in the Control R'com and the USC or by radio pager as per Station Directive No. 25. 5.6 TSC/OSC/ EOF Communications 5.6.1 TSC-OSC - telephone list ' are provided in Attachment VII. 5 6.2 EOF - telephone list are provided in Attachment VIII. 4 6 t m 9 ,+

EPP-002 ATTACHMENT I PAGE 1 0F 2 .,e x REVISION 12 l) \\- WARNING MESSAGE: NUCLEAR FACILITY TO STATE / LOCAL GOVERNMENT Part I 1. This is the Summer Nuclear Station. 2. My name is This message (number ): Ini,tial (a) Reports a real emergency. Follow-up -( b ) Is an exercise message. Time message given 4. My telephone number / extension is: 345-5209 X-4227. l 5 You may call back at the end of the message for verification. 6. The class of the emergency isi (a) Notification of Unusual Event (b) Alert (c) Site Area Emergency (d) General Emergency 7 This classifica. tion of emergency was declared at: es 'f( ) (a.m./p.m.) on (date). 8. The intiating event causing the emergency classification is: 9 The emergency condition: (a) Does not involve the release of radioactive materials from the plant. (b) Involves the potential for a release, but no release is occurring. l (c) Involves a release of l radioactive material. l

10. We recommend the following protective action:

(a) No protective action is recommended at this time. (b) People living in zones remain indoors j with the doors and windows closed. I I I lg t ._,-._._.. _ _ ~ ___ _ __ _ __ _ _ _

EPP-002 ATTACHMEffr I PAGE 2 0F 2 REVISION 12 (c) People living in zones evacuate their homes and businesses. (d) Pregnant women and children in zones remain indoors with the doors and windows closed. (e) Pregnant women and children in *)nes evacuate to the nearest reception center.; (f) Other recommendations:

11. There will be:

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

12. I repeat, this message:

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

13. Are there any questions?

- - Informati.on for MEDIA COORDINATOR ONLY! ***

() 1. Plant Statu.s a. tripped / controlled shutdown, rate present pwr. level %/ continuing to operate at %/ operating at 100% power 2. RCS leakage? a. From b. To Where is leakage contained? c. ANSWER ANY OTHER QUESTIONS THE MEDIA COORDINATOR RAS. BUT ENSURE YOUR ANSWERS ARE CORRECT!! e

EPP-002-ATTACRMENT II PAGE 1 OF 2 REVISION 12 fy \\m-WARNING MESSAGE: NUCLEAR FACILITY TO STATE / LOCAL GOVERNMENT Part II 1. The type of actual or. projected release is: (a) Airborne (b) Waterborne (c) Surface spill (d) Other 2. The source and description of the release.is:

3. ~

(a) Release began /will begin at a.m./p.m.; time since reactor trip is hours. (b) The estimated duration of the release is hours. 4. Dose projection base data: Radiological release: curies, or curies /sec. Windspeed: mph Wind direction: From ^ ) Stability class: (A,B,C,D,E,F, or G)' This is a ground release. Dose conversion factor: R/hr/C1/m3 (whole body) (from EPP-005 Attachment VII) R/hr/C1/m3 (child thyroid) Precipitation: Temperature at the site:

F i

5 Dose projections: 'I

Dose Commitment

Whole Body Child Thyroid Distance Rem / hour

' Rem / hour of~ inhalation Site boundary ) 2 miles 5 miles 10 miles O e e = -~s .,,,w e .,e ,-n-,,-,,-,-,-,,,,-,,-,a.,-,.,,--,-.,.,w,-- -,m-.-- y a,e,,-

EPP-002 ATTACHMENT II PAGE 2 OF 2 /" REVISION 12 V) WARNING MESSAGE: NUCLEAR FACILITY TO STATE / LOCAL GOVERNMENT Part II (cont.)

Projected Integrated Dose in Rem oer Unit Time
Distance Whole Body Child Thyroid Site Boundary 2 miles 5 miles 10 miles

-6. Field measurement of dose rate or contamination (if available): 7 Emergency actions underway at the facility include: 8. Onsite support needed from offsite organizations: 9 Plant Status: (a) Reactor is: not tripped / tripped . ( ) (b) Plant is at % power / hot shutdown / cold shutdown / \\_/ cooling down (c) Prognosis is: stable / improving / degrading / unknown.

10. I repeat, this message:

(a) Reports an actual emergency. (b) Is an exercise message.

11. Do you have any. questions?

l l l l l

EPP-002 INITIAL NOTIFICATION ATTACHMDIT IIIA PAGE 1 0F 1 "VOTIFICATION OF UNUSUAL EVENT" RE7ISION 12 () PAG 3d PERSON AGENCY / PERSONNEL NUMBIR HOME SITE NOTIFIED TIE

1. Manarment Duty 'Supv.

(per Duty Roster) Ollie Bralham 603 798-1359 4040 John Connelly 613 798-W19 4257 Ken Woodward 663. 732-1614 4220 Bruce Williams 623 8-9-359-4044 4221 Mel Browne 633 732-0897 4140 Mike Quinton 643 8-9-356-1980 4044 Bob Croley 653 781-7069 4042 PAGER Home Office

2. Off-Site Energ. Coord.

D. A. Nauman 131 781-2164 743-3513 H. T. Babb 131 772-1964 743-3417 M. B. Whitaker 131 782-8623 748-3399 D. R. Moore 131 781-1293 748-3689

3. **S.C. Dept. of Health &

758-5531 Environmental Control, Buresa of Radiological Health N/A -)4.**Buerg.PreparednessDiv. 758-2826 N/A

5. *NRC See Attachment IVA of WP-002 for ITRC Initial Notification

6. Media Coord.

HOME OFFICE

1) Becle McS<ain-703 8-9-359-3510 73 M 933

2) Bill Lide 703 772-1830 748-3420

7. Site Services Mgr.-Bob Stough 256-9875 732-0693 345-5422 781-9128

8. Institute of Nuclear Power Operations (INPO) 404 953,0904 N/A 404 953-0922 -

9. herican Nuc. Ins. (ANI)

See Attachment IVB of EPP-002 for'ANI Notification EDTIFICATIONS COMPLEI'E: CALLER'S SIGtIAfJRS DAZE

Dedicated Line Also Exists.

n Dedicate 1 Line Also Exists (For Normal Working Hours only). .h ^ 4

r EPP-002 ATTAC3 MENT IIIB INITIAL NOTIFICATION PAGE 1 0F 1 RE7ISION 12 " ALERT" 7_. (*) PAGER PERSON AGE' ICY / PERSONNEL NUMBER HOME SITE TDTIPIID TDfE

1. Management Duty Supv.

(per Duty Rostec) Ollie Bradham 603 798-1359 4040 John Connelly 613 798-2719 4257 Ken Woodward 663 732-1614 4220 Bruce Williams 623 8-9-359-4044 4221 %1 Browne 633 732-0897 4141 Mike Quinton 643 8-9-356-1980 4044 Bob Croley 653 781-7069 4042 NOTE: To contact additional Emergency Response Personnel refer to Station Directive No. 25 (Pager System 256-455e; Group Call Numbers 133,100).

2. Off-Site Iber. Coord.

PAGER H04E OFFICE D. A. Nauman 131 781-2164 748-3513

4. T. Babb 131 772-1964 748-3411 M. B. Whitaker 131 782-8623 748-3399 D. R. Moore 131 781-1293 748-3683

3. **S.C. Dept. of Health &

758-5531 Errtironmental Control, Bureau of Radiological Health N/A ( v. **Emerg. Preparedness Div. 758-2826 N/A 4 -5. *NRC See Attachment IVA of EPP-002 for NRC Initial Notification

6. Media Coord.

Home Office 1 Becky McSvain 703 8-9-359-3510 733-6933 2 Bill Lide ' 703 772-1830 748-342u

7. Site Services Manager-Bob st 732-0693 345-5422 256-781-9129

8. Institute of Nuclear Power Operations (INPO) 404)953-0904 N/A i

404)953-0922

9. Fairfield Pumped Storage Facility 345-5830 N/A

10. American 'Tuclear Insurers (ANI)

See Attachment IVB of EPP-002 for A'TI Notification NOTIFICATIONS COMPLEl'E: vaLc.rt's swmunt vus " Dedicated Line Also Exists. " Dedicated Line Also Exists (For Nornal Working Hours Only). /s Q 2 o g

EPP-002 ATTACHMEtiT IIIC INITIAL NOTIFICATION PAGE 1 0F 1 RE7ISI0ti 12 /3 " SITE AREA E4ERGENCY" \\ \\ 'd NAME OF PAGER PERS0:1 AJE' ICY /PNSONNEL NIEBER HOG SITt NOTIFIED TI142

1. !4xrtgement Duty Supv.

(. per Duty Roster) Ollie Bradham 603 798-1359 4040 John Connelly 613 798-2719 4257 Ken Woodward 663 732-1614 4220 Bruce Williams 623 8-9-359-4044 4221 Mel Browne 633 732-0897 4141 Mike Quinton 643 '8-9-356-1980 4044 Bob Croley 653 781-7069 4042 NOTE: To contact additional kergency Response Personnel refer to Station Directive No. 25 (Pager System 256-4 558; Group Call Numbers 133,100,111).

2. Off-Site her. Coord.

PAGER H(NE OFFICE D. A. Nauman 131 781-2164 748-3513 H. T. Babb 131 772-1964 748-3411 M. B. Whitaker 131 782-8623 748-3399 D. R. Moore 131 781-1293 748-368v

3. ++S.C. Dept. of Health &

758-5531 Environmental Control, Bureau of Radiological Health N/A ( ) 4. **kerg Preparedness Division 758-2826 N/A

5. 'NRC See Attachment IVA of EPP-002 for NRC Initial Notification

6. Media Coord.

~ Home Office

1) Becky McSwain 703 8-9-359-3510 733-6933

2) Bill Lide 703 772-1830 748-342v

7. Site Services % g r-Bob Stough 732-0693 345-5422 256-9575 781-9129

8. Institute of Nuclear Power Operations (INPO)^

(404)953-0904 N/A (404)953-0922

9. Fairfield Pumped Storags Facility 345-5830'

~N/A

10. American Nuclear Insurers (ANI)

See Attachment IVB of EPP-002 for ANI Notification NOTIFICATIONS C0'4PLEI'E: a.u:x s suuruttb va tr., I

Dedicated Line Also Exists.
- Dedicate 1 Line Also Exists (For Nomal Working Hours Only).

o i -G

= EPP-002 ATTAGE4ENT IIID It(ITIAL NOTIFICATION PAGE 1 0F 2 i REVISION 12 " GENERAL EMERGEICY" 0 7b flA*4E OF PAGER PERS01 AGENCY /PERS0'NEL ?RMBER HOKE SITE NOTIFIED TIME

1. Management Duty Supv.

(per Duty Roster) Ollie Bradham 603 79 %1' 59 4040 3 John Connelly 613 798-2719 4237 Ken Woodward 663 732-1614 4220-Bruce Williams 623 8-9-359-4044 4221 Mel Browne 633 732-0897 4141 Mike Quinton 643 S-9-356-1980 4044 Bob Croley-653 781-7069 4042 NOTE: To contact additional Energency Response Personnel refer to Station Directive No. 25 (PagerSysten 256-4556; Group Call 133,111,100).

2. Off-Site Ener. Coord.

PAGER H04E OFFICS D. A. Nauran 131 781-2164 748-3513 H. T. Babb 131 772-1964 743-341/ M. B. ifnitaker 131 782 4 23 748-3399 D. R. Moore 131 781-1293 748-3683

3. **S.C. Dept. of Health &

758-5531 Envirornental Control, Bureau of Radiological Health N/A

4. *NRC See Attachment IVA of EPP-002 for NRC Initial Notification

5. Media Coord.

Home - Office 1 Becky McSwain 703 8-9-359-3510 773-6933 2 Bill Lide 703 772-1830 74B-342u

6. Site Services Manager-Bob St 732 4 93 345-5422 256-781-9128

7. Fairfield Pumped Storage Facility 345-5830 N/A

8. **Ernergency Preparedness Division-Adjutant General's Office 758-2826 N/A (State 200)

(Dedicated Line Alao Exists. " Dedicated Line Also Exists (For Norml Working Hours Only). O

EPP-002 ATTACHENT IIID INITIAL PUlTPICATION PAGE 2 0F 2 ILWISION 12 . /7 " GENERAL EERGENCY" NAME OF PERSON AGENCY / PERSONNEL NORMAL SITE FUTIFIED THE

9. *Fairfield County 5-635-5511 N/A

10. *Newberry County 66-276-4295 N/A

11. #Richland County 9-254-9296 N/A 12._ *Iaxington County 8-9-359-2521 N/A 13 Institute of Nuclear (404)953-0904 N/A Power Operations (INPO)

(404)953-0922

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

fDTIFICATION (XX4PLETE: caller's, signature uate C\\ V

Dedicated Line Also Exists.

e O G 6 [_

EPP-002 ATTACHMENT IVA PAGE 1 0F 4 [] REVISION 12 \\m/ NRC ONE HOUR NOTIFICATION 1 The NRC shall be notified within 1 hour of Declaration of an Emergency in accordance with Pages 2 through 4 of this attachment. s' PE'RSON NORMAL CONTACTED ^ 1. NRC - Bethesda, Md. Dedicated Phone a) Commercial telephone system to NRC Operations Center (Via Bethesda Central Office). (202) 951-0550 b) NRC-Atlanta, Ga. (404) 221-6068 After working (404)221-4503 hours 2. NRC - Resident Inspector Yes No Bill Hehl 4027 (N.O.-Ext) 772-6625 7.- or 345-5663 Home Phone No. ) 748-5406 Beeper No. CALLERS SIGNATURE DATE TIME e 9 = U ,-.my, ---e ..e - - - -, - = + - -- s-

EPP-002 ATTACHMENT IVA PAGE 2 0F 4 REVISION 12 ( ) NRC ONE HOUR NOTIFICATION A. Identification: TIME OF NOTIFICATION This is the Summer Nuclear Plant in Region II. My name is Our phone number 1s-(803)345-5209 l B. Event Classification: We are now in a(n) EVENT CLASSIFICATION which was declared at TIME C. REACTOR EVENT: Power prior to event Power at time of report Trip? Initiating Signal SI or ECCS? Initiating Signal ESF actuation? D. EVENT DESCRIPTION AND CAUSE Radioactive releases? (Quantify) Other major problems E. PLANT ACTIONS / PRESS RELEASES? F. NOTIFICATIONS? ETATE PLANT MGMT. LOCALS OTHER NRC RESIDENT OTHER

EPP-002 ATTACHMENT IVA g-O PAGE 3 0F 4 ( REVISION 12 NRC ONE HOUR NOTIFICATION Part II-Complete for all ALERT, SITE AREA, and GENERAL emergencies Licensee Actions: Taken Planned Property Damage Radioactivity Released - (or Increased Release): Liquid / Gas? Location / Source of Release Elevation ' Release Rate Duration Stopped? Release Monitored? Amount of Release % Tech. Specs. Increased Radiation Levels in a Planb: Location (s) Radiation level (s) Areas Evacuated Maximum site boundary dose rates Location Integrated dose Location Meteorology: Wind Direct $on from C~~' Wind Speed (Meter /sec or miles /hr) Temperature ( C or F) Stability Class A B C D E F G ' Raining (Yes/No) Projected Peak: Dose Rates Integrated Dose 2 mi (WB/I) (WB/I) 5 mi (WB/I) (WB/I) 10 mi (WB/I) (WB/I) Sectors-(WB/I) (WB/I) Contamination (Surface): inplant onsite offsite Reactor Operations: Reactor System Status Power Level Pressure Temp Flow (pumps on) Cooling Mode ECCS Operating / Operable Containment Status Containment Isolated? Containment Temp Containment Press Containment Radiation R/hr. Leak Rate Reactivity Control Control Rods. Inserted Status of Emer. Boration System CY s

EPP-C02 ATTACHMENT IVA PAGE 4 0F 4 -s REVISION 12 INCIDENT NOTIFICATION INFORMATION Part II Steam Plant Status: S/G Levels Equip. Failures Feedwater Source / Flow S/G Isolated? Electrical Dist. Status: Normal Offsite Power Available? Major Busses / Loads Lo D/G Running? Loaded? Security / Safeguards: Bomb Ihreat: Search Conducted? Search Results Site Evacuated? Extortion: Source (Phone, letter, etc.)? Location of Letter Intrusion: Insider? Outsider? Furthest Point of intrusion Fire arms related? Stolen / Missing Material? ) Demonstra$1on: Size of Group Demands Violence? Fire arms related? Sabotage / Vandalism: Radiological? Arson Involved? Stolen / Missing Material? i l O

EPP-002 ATTACHMENT IVB PAGE 1 0F 3 O REVISION 12 ANI EIGHT HOUR NOTIFICATION ANI'is to-be notified within eight (8) hours of'the declaration of an Alert, Site Area Emergency, or General Emgergency in accordance with pages 2 and 3 of this attachment. American Nuclear Insurers (ANI) Phone No. 1-800-243-3172 (203)-677-7305 Person Contacted Time Date Callers Signature 4 A O

EPP-002 ATTACHMENT IVB PAGE 2 OF 3 lG ) REVISION 12 ANI NOTIFICATION (1) This is (Name) (Ticle) (2a) .This is a drill (2b) This is NOT a drill (3) I am notifying you of an accident at the V. C. Summer Nuclear Station which occurred at: (Date) (Time) (4) This emergency is classified as a (5) Description of event: (6) Radiation Release Yes No. (If yes, complete 6a through 6j) (6a) Type of Actual Release or Type of Projected Release: (6b) Estimation of Duration of Public Impact: [ (6c) Release Rate: (6a) Noble Gas (6b) Iodine (6c) Release Height (6d) Meteorological Conditions: (6a) Wind Speed (mph) (6b) Wind Direction (blowing to) (6c) Stability Class (6d) Precipitation (6e) Projected Dose At: Site Boundary 2 Miles 5 Miles 10 Miles (6f) Dose Rate--Whole Body ('10A) (10B) (100) (10D) (6g) Integrate Whole Body Dose ( hour projection) (llA) (llB) .(110) (llD) l (6h) Dose Rate--Thyroid (12A) (12B) (12C) (12D) i (61) Integrated Infant Thyroid j ( hour projection) (13A) (138) (13C) (13D) (6j) Sectors Affected (14A) (14B) (14C) (14D) O V ~ l L

EPP-002 ATTACHMENT IVB PAGE 3 0F 3 [ \\ ) REVISION 12 \\-s i ANI NOTIFICATION (7) Injured Personnel Yes No. (if yes, complete 7a tnrough 7d) (7a) Number of injured personnel (7b) Is Is Not Radioactively Contaminated (7c) Injury

Description:

(7d)' Requires Transportation to off-site Medical Facility Yes No. (8) Off-Site Emergency Assistance / Actions Requested Yes ' No. (If yes, complete 8a through Sc) Yes/No Reason (8a) Law Enforcement (8b) Fire Departments O's .(8c) Hospital Facilities (9) Public evacuation required Yes No Not at this tim,e (9a) If "Yes" or "Not at this time", affected sectors l t- ~ (- 1 bi V

EPP-002 ATIACfEElr V PAGE 1 0F 3 -s [ ). REVISION 12 '-u 0FF-SITE EMERGEJCY SEVICES NA?E OF PERS0ti AGOICY/ PERSONNEL PHONE fDTIFIED TIME A.. Company Physicians (Pinner Clinic)

1) Carrol A. Pinner III M.D. - Primary 945-7475 (24 hrs.)

2) John H. Furguson - Alternate 945-7475

3) Harriet E. Pinner, M.D. - Alternate 945-7475 B.

Hospital Facilities

1) Richland Memorial Hospital 765-7561 Give the following information:

This is the Virgil C. Strume Nuclear Station. This is a Drill This is not a Drill p We have contaminated /non-contaminated Q injured person being transported to your facility. Extent of injuries, as known

2) Radiation Energency Assistance Center Training Site (Reacts)

(24 hour-(615)482-2441 Beeper 241 office #(615)576-3131 C. Ambulance Service

1) Energency Medical Services of Fairfield County 635-5511 or 635-4661 2)

U.S. Army MAST Operations 765-6235 (through Richland Memorial Hospital) NOTE: Alert Security of Energency Vehicle arrival as soon as request (s) for Off-Site Energency Services are completed. Ext. 4290 or 4291

EPP-002 ATTACHMENT V PAGE 2 0F 3 REVISION 12 'l ~ OFF-SITE E4ERGDICY SERVICES NAME OF PERSON AGDICY/ PERSONNEL PIONE NOTIFIED TIME ^ Give.the following infomation for itens la and 2 above. This is a Drill This is not a Drill We have contaninated/non-contaminated injumd person (s) requiring transportation to Richland Memorial Hospital. (The ambulance must enter the site via the main gate, using (denote route to be taken) or the helicopter should land at the~ primary landing pad (denote route to be taken) Exte.nt of injuries, as known D. NSSS Supplier /A.E.- Title Name Office Home HHL 1. Resident Customer Bob Stough 345-5422/732-0693/781-9123 l Service Manager Notes: (1) The area code of the above phone numbers is (803) (2) The phone beeper number is (803)-256-9875 .(s\\ V 2. Pittsburgh Customer Gary Percival 256-6387/373-3266 Service Manager 1st Alternate Ieslie Gibson (803)-345-5209/4236/(803)-772-8008 2nd Alternate-Jim Rea 256-6386/655-2980 3 Servic'e Response George Masche 256-6590/963-6938/963-0325 Manager i lat Alternate Bob Stokes 256-6409/325-1128/327-8214 1 2nd Alternate Joe Leblang 256-6390/325-1023/325-3998 4. Energency Response Tom Anderson 256-6155/327-8289/327-7221 l Director 5 Energency Response Ron Lehr 733-5516/373-1699/856-7613 l Deputy Director 6. Energency News Mike Mangan 373-4328/828-2543/828-0465 Connunications . Note:.Unless indicated otherwise, all phone numbers are area code 412. W1ere an area code other than 412 is shown, it applies to the office, home, and HHL numbers

2) GAI (Nomal (215) 775-2600 Working Hours)

O, , c-EPP-002 ATIACHENI V - _[Lh PAGE 3 0F 3 REVISION 12 w/ OFF-SITE DERGECl SERVICES NA E OF PERE N AGDICY/ PERSONNEL PHONE Nufins TIE -E. ' Fire Services 635-5511

1) Fairfield County Fire Services Give the following information:

'Ihis is the Virgil C. Sur:rner Nuclear Station. s This is a Drill. This is not a Drill We request fire fi hting assistance at the Suntner Nuclear Station. The fire truck must enter via the main gate, using (denote route to be taken) F. Local Law Enforcenent '35-5511o$ 1: 635-2931 p (off--normal hours) 635-4141 + National Weather Service (Ba'kup 'to Ioad Dispatcher for weather information). O. c

1) Colu:nbia 794-2593 or 796-4473 765-5501

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EPP-002 ATTACHMENT VIA PAGE 1 0F 1 FOLLOWUP NOTIFICATION ALERT NAME OF PERSON AGENCY / PERSONNEL NORMAL NOTIFIED TIME 1.* S.C. Dept of Health & 758-5531 Environmental Control, Bureau of Radiological Health Notifications complete: Caller's Signature Date ). Dedicated Line Also Exists (Normal Working Hours.ONLY). O f 9 i i I O ~ 4 w- -w a- ,.,w._,.<m,- 3 .,w,_.,m.,_ ,,,.-,,m7, .%._.,,.v.e- ..,,y.,,.y, ,m.,_., -7 ,s,,, w m.m,m ,,,m.-,,,,,.w..-

EPP-002 ATTACHMENT VIB PAGE 1 0F 1 ,~s ( ) REVISI.ON 12 %J FOLLOWUP NOTIFICATION SITE AREA EMERGENCY NAME OF PERSON AGENCY / PERSONNEL NORMAL NOTIFIED TIME f 1.* S.C. Dept of 'ealth & 758-5531 H Environmental Control, Bureau of Radiological Health Notifications complete: Caller's Signature Date NOTE: When the State Forward E00 is established the State BRH will move their operation to the State Forward E00 and communication will be via the State Forward E.O.C. Dedicated Phone Line.

Dedicated Line Also Exists (Normal Working Hours ONLY).

O \\m / P f

EPP-002 ATTACHMENT VIC PAGE 1 0F 1 [J] REVISION 12 N. FOLLOWUP NOTIFICATION GENERAL EMERGENCY NAME OF PERS0ti AGENCY / PERSONNEL NORMAL NOTIFIED TIME 1.**S.C. Dept of Health & 758-5531 Environmental Control, Bureau of Radiological i Health The following notifications shall be made by the TSC or EOF Communicator until such time that the S.C. State forward EOC is staffed. 2.** Emergency Preparedness 758-2826 Division Adjutant General's, j 0ffice 4 3.* Fairfield County 635-5511 4.* Newberry County 276-4295 _( ) Richland County 254-9296 6.* Lexington County 359-2521 Notifications complete: Caller's Signature Date NOTE: When the State Forward E00 is established the State BRH'will move their operation to the State Forward E00 and communication will be vis the State Forward E.O.C. Dedicated Phone Line.

Dedicated Line Also Exiats.
- Dedicated Line Also Exists (For Normal Working Hours Only).

t Pv -,r-., ,-> -~

EPP-002 ATTACHMENT VII PAGE 1 0F 2 _:p-REVISION 12 \\,/. TSC/OSC EMERGENCY. TELEPHONE LIST 4300 Nuclear Regulatory Commission'(NRC Area and E.O.A) 4301 Nuclear Regulatory Commission _(NRC Area and 3.0. A) 4302 Nuclear Regulatory Commission 4303 TSC Display Room 4299 TSC Display Room 4306 Dose Assessment Area -4307 Technical Support Engineers 4309 Technical Support Center Communicators 4309 Technical Support Engineers j ~ 4310 Administrative Supervisor - L. A. Blue Security Supervisor-John Sefick 4311 Telecopier Phone to EOF

/]

k/ 4312 Radiation Monitoring Teams s 4313 Data Logger 4314 -Radiological Assessment Supervisor - J. Cox 4315 Technical Support Supervisor - B. Croley 4316 Emergency Director - 4318 Maintenance Services - M. Quinton 4019 Operations Supervisor - K. Woodward 4319 Westinghouse (NSSS) 4320 GAI (A/E) 4351 OSC 4352 OSC t I a I N_) 4 + e e w- +t.,- 3-e,.,. +, - -,,, 7 yo.-, - -h.-.,,-4-- .m.,. e ,_g. y .m.- -,%_,,.,m,.. y.,-r-,,,___.,.m -.-19,

EPP-002 ATTACHMENT VII PAGE 2 of 2 REVISION 12 v TECHNICAL SUPPORT CENTER NRC 4300/4301 4302 8A DISPLAY iREA J 4303 4299 DOSE ASSESSMENT AREA 4306 4 L. 4307 4308 O 4309 4310 EMERGENCY OPERATIONS AREA TECHNICAL D[ SUPPORT A EA D-3 4300 4315 D-4 4301 4316 D-5 4313 4318 D]6 COMMUNICATIONS AREA (Telecopier) 4311 MONITORING NSSS A/E TEAMS AREA AREA AREA 4312 D-8 D-9 4319 4320 I O ,,_m. -r-.. --,--,,--.y ---..._...,.-----.._---,-y,---+w,, , =, -.,. -, -.,. r..

EPP-002 ATTACHMENT VIII PAGE 1 0F 4 m REVISION 12 k Emergency Operations Facility Layout 9 Stair way 8 N/ J N, Hallway ~/\\ 10 7 6 / 1 11 / N / h N 5 g / 3 12 i\\J ' '/ ll// // / / 13 14 / \\ /,/ [ /l / [/ j / / / / 1 - COMMAND CENTER (Room 144) 9 - NRC AREA (Room 122) 2 - TECHNICAL SUPPORT AREA (Room 145) 10 - CONFERENCE ROOM (Room 3 - 0FFSITE RADIOLOGICAL MONITORING AREA 143 (Room 145) 11 - COMMUNICATIONS AREA 4 - GENERAL SERVICES A'REA (Room 138) (Room 140) $ - CONSTRUCTION / REPAIR AREA (Room 138) 12 - REPRODUCTION AND 6 - MEDIA AREA (Room 141) RECORDS STORAGE AREA 7 - LOCAL GOVERNMENT AREA 13 - STR0 AGE AREA (Room 142) 8 - STATE GOVERNMENT AREA (Room 124) O gw,-

m

.,----t*--r-'+-+v--* - - - * " - - - - - - - - = = --d

EPP-002 ATTACHMENT VIII PAGE 2 0F 4 REVISION 12 ,_,b I (,j OFF-SITE EMERGENCY TELEPHONE LIST Emergency Operations Facility 1. COMMAND CENTER 5077 EOF-Media Coordinator (R. McSwain) 5078 EOF-Emergency Control Officer (0.W. Dixon) 5079-EOF-Offsite Radiological Monitoring Coordinator ( B. Baehr) 5080 EOF-Security Coordinator (J. Harrison) 5081 EOF-G~neral Services Coordinator (J. Bailey) e 5082 EOF-Construction / Repair Coordinator (J. Woods) 5083 EOF-Technical Support Coordinator (K. Nettles) 5053 NRC Representative ~

2. TECHNICAL SUPPORT AREA

/~'T 5075 EOF-Technical Support Engineers . N) 5076 EOF-Technical Support Engineers /Telecopier

3. OFFSITE RADIOLOGICAL MONITORING AREA 5067 EOF-Offsite Rad. Monitoring 5073 EOF-Offsite Rad. Monitoring 5074 EOF-Offiste Rad. Monitoring 4.- GENERAL SERVICES AREA 5017 EOF-General Services Telecopier 5018 EOF-General Servi.'as Personnel f

4 L) + t

1 EPP-002 ATTACHMENT VIII PAGE 3 of 4 REVISION 12 'O ( ( ) 0FF-SITE EMERGENCY TELEPHONE LIST Emergency Operations Facility 5 CONSTRUCTION / REPAIR AREA 5016 EOF-Construction Personnel 6. MEDIA AREA 5061 EOF-Company Media Personnel 5062: EOF-Company Media Personnel 5063 EOF-Oompany Media personnel 7 LOCAL GOVERNMEMT AREA 5064 EOF-Local Government Officials 5065 EOF-Local Government Officials 5066 EOF-Local Government Officials. 8. STATE GOVERNMENT AREA 5058 EOF-State Government Officials } 5059 EOF-State Government Officials 9 NRC AREA 5053 EOF-NRC Officials 5054 EOF-NRC Officials 50'55 EOF-NRC Officials 5056 EOF-NRC Officials r 't ( I s e I 9 L

EPP-002 ' ATTACHMENT VIII PAGE 4 0F 4 REVISION 12 OFF-SITE EMERGENCY TELEPHONE LIST Emergency Operations Facility ~ 10. COMMUtlICATIONS AREA 5051 EOF-Emergency Communicator

11. SECURITY CONTROL POINTS 5085 EOF-Hallway Area 5086 EOF-North Entrance 4

9 D 4 I' i I 1 h I 1 L....:.-_...,.~~.._. --8---

.I, SOUTH CAROLINA ELECTRIC AND GAS COMPANY p. VIRGIL C. SUMMER NUCLEAR STATION v NUCLEAR OPERATIONS ELCLEAR OPER!GONS CDP 1. No. -l 5~7 """"""' EMERGENCY PLAN PROCEDURE EPP-005 OFFSITE DOSE CALCULATIONS REVISION 8 . JANUARY 8, 1985 SAFETY RELATED O /2 A A./ ff DISCIPyESUPERVMOR / DaAe N}h An APPROVAE AUTHORITY Gats AFR 0 1965 DATE ISSUED RECORD OF CHANGES CHANGE TYPE DATE DATE CHANGE TYPE DATE DATE I NO. CHANGE APPROVED CANCELLED NO. CHANGE APPROVED CANCELLED 4 0

EPP-005 PAGE i <-~s, REVISION 8 .(Ns) 1/8/85 TABLE OF CONTENTS Pace 1.0 PURPOSE 1

2.0 REFERENCES

1 ~ 30 LIMITS AND PRECAUTIONS 2 4.0 " PROCEDURE ~2 50 BASES 6 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 ATTACHMENT IV - Sample Form: Activity Release Status ( ATTACHMENT V - Sample Form:- Out of Plant Monitoring Dispatch & Data Form ATTACHMENT VI - Sample Form: Dose Off-Site (Dose Rate) Calculation from Environmental Monitoring ATTACHMENT VII -Dose-Concentration Conversion ATTACHMENT VIII-Delta T Atmospheric Stability Classification ATTACHMENT IX - Sigma Theta Atmospheric Stability Classification ATTACHMENT X - Meterological Sector Definition ATTACHMENT II - Correction Factor for High Range Monitors ATTACHMENT XII -Protective Action Guides (PAGS) 4 ) (-,' (-

EPP-005 PAGE 11 IN REVISION 8 k_,) 1/8/85 TABLE OF CONTENTS (cont) List of Effective Pages ATTCHMENT XIII - Pasqui,ll-Turner Method for Determining Atmospheric Stability. ATTACHMENT IIV - Volume-Pressure Steam Curve ATTACHMENT XV - Containment Leakage Source Term ' ATTACHMENT XVI - Calibration Constant (pre HPP-906 Amplementation) ATTACHMENT XVII - Calibration Constent (post HPP-906 implementation). ATTACHMENT XVIII - Projected Whole Body and Thyroid Exposure Rate at 1 Mile ATTACHMENT XIX - Estimation of Release Rates From FSAR Listed Accidents ATTACHMENT XX - Estimation of Release Rate From Main Steam Releases Q,/ f I l l () t j A l. b () t 'L.

c = EPP-005 REVISION 8 73 ( ) - 1/8/85 v 1.0 PUR POSE 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 to 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 - g-s 1968", TID-24190, Division of Technical Information, USAEC j (1968). 25 Turner, D. B., " A Diffusion Model for an Urban Area", Journal of Applied Meteorology, February 1964. 2.6 U. S. Nuclear Regulatory Commission, Proposed Revision 1 to Regulatory Guide 1.23, " Meteorological Programs in Support of Nuclear Power Plants", September 1980. 2.7 NUREG-0654 / FEM A-REP-1, "Criter.ia 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. 29 EPA-520/1 001 (Revised June 1980) " Manual of Protective Action Guides and protective actions for Nuclear Pla ;ts.".. 2.10 EPP-002 Communication and Notification. rh 'V) PAGE 1 OF9 6 s

EPP-005 REVISION 8 i-r-) 1/8/85 I 2.11 Virgil C. Summer Nuclear Station Final Safety Analysis Report Chapter 15, Sections 15 3 and 15.4. 2.'12 HPP-906 Preplanned Altern' ate Method for Monitoring Post Accident Parameters as required by Technical Specifications. ~ 2.13 Reg' Guide 1.145, Atmospheric Disperation Models for, Potential Accident Consequence Assessments at Nuclear Power Plants. i 2.14 Farley Nuclear Station EDCM. 2.15 HPP-707 Health Physics Action and Surveillance for Unplanned Releases. 2.16 Nuclear Measurements Corp. Radiation Monitoring Systems, IMS-94B-800-1, 2 and 3 2.17 Victoreen Model 845 Area Monitor, VCS-94B-838. 30 LIMITS AND PRECAUTIONS 31 Refer to Ref. 2.15 for source term methodology for (}' unmonitored releases. ss-4.0 PROCEDURE NOTE: This procedure delineates two (2 ) methods by which offsite doses may be calculated (i.e., computer calculation and manual calculation). Either method, or a combination of both methods, may be used since comparable results can be obtained. The computer method is intended to be used by plant or corporate health physics personnel. Any other groups needing to use this procedure should use the manual method unless trained in the computer method. Also, the " Turner's Algorithm" method of determining stability class should not be used by operations personnel. 4.1 Overlay Selection 4.1.1 If the computer is not available p'rdceed^to s'ep ~ t 4.2 to initiate manual calculations. l t l ( PAGE 2 0F 9 L-

~ EPP-005 REVISION 8 .f~'g 1/8/85 t '~' 4.1.2 Use the HP9845B in the Technical Support Center to run the menu driven real-time dose projection system. The program is started by following guidance derived through Reference 2.8. 4.1 3 Complete the applicable steps in 4.2 and step 4.3 so that the manual method map is available for use in case of computer failure. The map is also useful in dispatching out of plant monitoring teams. Proceed to step 4 5 4.2 Manual Method 4.2.1 Stability' Class Determination If the meteorological tower is inoperable proceed to step 4.2.2 otherwise, complete Part 1 of ' Attachment I to obtain meteorology and source term data from control room instrumentation. Method A. (below) is preferred. NOTE: All meteorological data must be obtained from strip charts by averaging the most previous 15 minutes of data for a 3 parameter. Ns A. Differential Temperature ( A T) 61-10 meters and l 40-10 meters Method. 1. Obtain A T information from the Control i Room instrumentation.' i 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 with a portable radio may be dispatched to the meteorological tower to obtain AT information directly i from the met tower instrumentation. Keys l to towers are available in the Emergency Planning Key Box located in the Emergency Operations Area of the T.S.C. s I. 1 + 3 Determine the Pasquill Category by using Attachment VIII and select appropriate X/Q overlay found near the plotting map. ' A lN] PAGE 3 0F 9 m

EPP-005 REVISION 8 1/8/85 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 hour. 2. Wind range is determined by the diff rence between~ 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 us'ing Attachment IX and select appropriate overlay. ) 4.2.2 Backup meteorological data can be obtained from the National Weather Service (NWS). A. If meteorological tower data is not available call the NWS (see ref. 2.10 for. phone number) j and obtain windepeed, wind direction,.4 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 XIII 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. 4 3.2 Orient the centerline of the overlay along the direction theD'lnd is' blowing. 9 e O PAGE 4 0F 9

EPP-005-REVISION 8 j3 1/8/85 \\ )' NOTE: Wind directions are given as directions from which the wind is blowing; affected directions are 180* from the wind direction. When ccomunicating wind direction, specify the direction from which the wind is blowing-(e.g. wind is blowing from 270* ) 4 3.3 The conversion from wind direction measured in degrees to wind direction in sectors is presented in Attachment X. 4.4 Manual Dose Calculation 4.4.1 Complete Part 2 of Attachment I. A. To perform a quick estimate of the projected offsite radiation exposure, complete Attachment XVIII as per the instructio.ns on the back of the' form. 4.4.2 Complete Attachment II if radiation monitor RM-A3 (Gas) or RM-A4 (Gas) is on scale. Compare results with the PAGS (Attachment XII). 4.4 3 If RM-A3 (Gas) or RM-A4 (Gas) is offscale or if there is a steam release complete Attachment III. /} ' Compare resalts with the PAGS ( Attachment-XII). NOTE: Attachments VII, XI and XIV, will be necessary for completing Attachment III. Attachment XX must be used for steam releases. 4.4.4 Complete Attachment XV if either radiation monitor RM47 or RM-G18 are on scale. Compare results with PAG's (Attachment XII). 4.4.5 If the radiation monitors on the effluent path are offscale or inoperable and HPP-906 has not been implemented, refer to Attachment XIX for estimated Release Rates and Iodine to Noble Gas Ratios derived from Reference 2.11. a) Choose the listed accident and accident assumptions from Att... XIX that mo.st closely matches the event at hand. b) C]nter'on line C of Att. II the Noble Gas Release Rate from the ch.osen accident in Att. XIX. / iv) PAGE 5 0F 9

EPP-005 REVISION 8 f~T 1/8/85 V c) -Enter on line I of Att. II the Iodine to Noble Gas Ratio from the cho'sen accident in Att. XIX. NOTE: For the Control Rod Ejection Accident and the Loss of Coolant Accident, the Noble Gas Release Rate must be adjusted if containment leakage is other than the assumptions stated. For the Fuel. Handling Accident, the Noble Gas Release Rate must be adjusted if the number of fuel rods damaged is more than the assumption in the realistic case as stated. d) Using Att. II, compute o'ff-site dose projections. Compare with PAG's (Att. XII). 4 4.6 Complete Attachment IV to maintain curie accountability. Total activity of iodine, noble gas, particulates, and tritium must be kept current. (Hourly updates if possible) 4 4.7 Transfer all applicable results to EPP-002 Attachment II for transmittal and documentation purposes. '/~N ( l 45 Environmental Monitoring s/ 451 As soon as practical, dispatch monitoring teams to the affected meteorological sectors. At tac hment V, should be used to record location and results. NOTE: Dose projections based on source terms should be verified as soon as possible by supportive measurements. Based on these measuremen s, a reassessment of the PAG's should be taken. 4 5.2 Attachment VI can be used to project doses based on environmental samples. These can then be compared with source term projections. 5.0 BASES 5.1 This section is included to provide a'brief explanation of 4the soprces of constants and graphs used in the procedures and associated attachments. I tV PAGE 6 0F 9 S

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m EPP-005 ' REVISION 8 (~m) 1/8/85 A. Step 4 3.1 - Until a full class A model is developed, subsequent to the completion by Dames and Moore of a detailed study of the Summer Station Meteorology, the (X/Q) overlays will be based on a straight line gaussion plume model as described in Reg. Guide 1.145 B. Attachment II, Line I - The Iodine to noble gas l activity ratio of 0.3, until measured, is a' conservative estimate from Ref. 2 9 page D-59. would suggest that the actual ratio could be 10-]MI-2 or less. A fast and accurate measurement of the actual ratio is important to avoid unnecessary evacuation orders based on the Iod The pglibration constants 3 3x10 -{ge PAGS. and 3 8 x 10 - are-based on the manufacturer's calibration (Ref. 2.16) and various unit conversions as follows: 3 3X10-10 =1 min x 106 x 10-6 Ci i uCi/ml m W see m uCi YOITO cea 3 8X10-iO 6-x 10-6 Ci X 1 uCi/ml 1 min x 10 .m = ETT see m I2Ii 44x10" GFM (} C. Attachment III, Section-I - Same comment as 3. G' The calibration cogstants 4.0 x 10-5, g,5 x 10-5 and 8. 5 x 10-are based on the manufacturer's calibration (Ref. 2.17) and various conversion as follows: 4.0 X 10-3 = 0.028 m3 x 106 X 10-6 Ci x 1 min x 1 uCi/ml m Yt3 Ei W see 11.7 mR/ hr m 9.5 x 10-5 = 0.028 m3 x 10 - x 10-6 Ci x 1 min x 1 uCi/ml 6 m Yt3 uE W sec 4.89 mR/ hr m 8 5 x 10-4 = 0.028 p x 10 3 6 ft 12 jo-6 Ci x 1 hr x1 uCi/c1 m Efi 3000 sec 9 13x10 s mR/hr D. Attachment VII - The curves follow the methodology and assumption of Ref. 2 9. The noble gas curve comes from EQ. 2 9, the Iodine curve from EQ. 2.13 !) E. Attachment XIII - This description of the Pasquill-Turner method was supplied by Dames and Moore. The calculation of the solar altitude was obtained from the Alabama Power Company Parley Station EDCM. It was verified lar comparison with selected values from the Smithsonian Meterological Tables. O ' V PAGE 7 0F 9 e

l EPP-005 REVISION 8 1/8/85 (,\\ (_/ F. Attachment XII - Protective actions are taken from Ref. 2 9 The particulate concentration, 7 5 x 10-7 Ci/ml, would lead to an exposure of 2000 MPC Hours in 8 hours. That is, it is analogous to a whole body exposure of 5 REM. Other concentrations are related by ratio to the specified whole body exposure found in Ref 2 9 G. Attachment *XIV is a plot of standard steam table data. for saturated steam. H. Attachment II is a plot of the ratio of DOSE to concentration for mixed fission noble gas to that for 133 Xe as a function of time after trip. I. Attachme 2 56 f t.St XV - the conservative leak rate of / min is based on the Tech. Spec. allowable limit (Section 3.6.1.2) of 0.2% by weight of containment air per 24 hours at 47.1 psi which is the pressure expected with a steam line break. No pressure correction is needed since RM-G7 and RM-G18 readings are made at containment pressure and the leak rate is used only to. calculate source term, not actual containment volume released. (1.84E6 f t. 3)x(0.OO2 ) x (1 hr.) = 2 56 ft.3/ min. (O-) (24 hrs.) (oo min.) J. Attachment XVI is a plot of calibration constant versus time post-accident for BM-G7 and RM-G18. Data is based on a report by GAI on RM-G7 and RM-G18 l calibration. The calibration constants were derived as follows: (1_uci/ml) x (1 hr.) x 3 (souv sec)(1E-6 01) x (1E6ml) x (0.028,e ) (c' mr/ nr > (uull (m3) (rt. s/ =7.78E-6 = calibration constant C' where CF = conversion factor derived from data supplied by GAI. l K. Attachment XVII is a plot of calibration constant versus time post-accident for a RM-16/RD-17A monitoring system outside the Reactor Building air lock when HPP-906 has has been implemented for either RM-G7 or RM-G18. Data ~ and derivations are as in "J" above. l t (3 \\s l _PAGE 8 0F 9 l

EPP-005 REVISION 8 1/8/85 L. Attachment XX is a formula for calculating the 1bs/hr release rate from main steam in the event of a main steam line rupture or main steam relief valve actuation. The formula is based on the assumption that the amount of steam released directly - to the atmosphere is equal to the steam flow from the leaking steam generators minus any steam flow dumped to the condensor. 4 0 3 t { O l PAGE 9 0F 9 i b

EPP-005 ATTACEMENT I METEOROLOGY AND SOURCE TERM PAGE 1 0F 1 REVISION 8 REPORT FORM i \\s / PART I l '41ndepeed mph (10 meter preferred) Time Direction degrees (10 meter preferred) . Delta T degrees (61-10) or (40-10) (Circle One, 61-10 is. preferred) Stability Class -(Use Delta T and' Attachment VIII or Sigma Theta and Attachment II or Turners Algorithm and Attachment XIII Delta T_ g preferred). PART II [ Source Term Time. RM-A3(G) net CPM RM-A3(I) CPM; Time Obsrv'd (A) CPM; Time Ovsrv'd (B) {} . Difference in CPM between (A) and (B) CPM (C) Difference in Time between (A) and (B) Min (D) (C) : (D) = CPM / min (use in Att. II) RM-A4(G) net CPM RM-A4(I) CPM; Time Oberv'd (A) CPM; Time Obstv'd (B) Difference in CPM between (A) and (B) CPM (C) Difference in Time between (A) and (B) Min. (D) (C) : (D) = CPM / min (use in Att. II) RM-A13 mr hr RM-G19A mr hr RM-A14 mr hr RM-G19B mr hr RM-G7 mr hr RM-G19C mr hr RM-G18 mr hr Main Plant Vent Flow Rate CFM Reactor Bldg. Purge Flow Rate CFM I Sceam Flow lbs./hr. \\,/ D

\\ EPP-005 ATTACI@ENT II PAGE 10F 2 Q(~N REVISION 8 DtERGalCY OFF-SITE D6SE CALCULATION ] USING STACK !ONTIOR SOURCE TERM Time of Trip Current Time Time after Trip RM-A3 (Gas) RM-A4 (Gas) 4 Count Rate CPM CPM (A) Calibration 3 3 x 10-10 3.8 x 10-10 (A1) m3 min. (B) Flow rate: CFM x 0.028 = / Release Rate (A) x (A1) x (B) C1 7 (C) (C) x 3600 = C1/hr (use in EPP-001) Wind Speed: MPH x 0.45 = Wsec (D) (X/Q)u from isopleth for 1 mile m-2 (El) X/Q: (E1)+(D) = sec/m3 (p) Noble gas dose to concentration conversion from Attachment VII x2= ren/2hr (G) C1/m3 WHOLE EODY DOSE (2 hrs): (F) x (C) x (G) = rem T Er. (H) Iodine to noble gas activity ratio (use 0 3 unless measured) (I) Iodine dose to concentration conversion from Attachment VII rem /2hr C1/m3 (J) O'

EPP-005 ATTACHMENT II ) PAGE 2 0F 2 V REVISION 8 DERGENCY OFF-SITE DOSE CAICULATION USING SPACK PONI'IOR SOUkCE TERM The of Trip Curmnt Time The after Trip Iodine to noble gas dose ratio (I) x (J) 4. (G) (K) CHILD 'IHYROID DOSE: (K) x (H) = at 1 mile (2 hour) nun /2hr. (X/Q)u at 2 miles (E2) (E2)/(E1) (I2) 5 miles (ES) (ES)/(E1) (L5) 10 miles (E10 (E10)/(E1) (L10) Projected Integrated Dose in Rem per Unit Time 2 miles (I2) x (H) ' ren x (K) = rem 5 miles (L5) x (H) mm x (K) = rem 10 ciles-(L10) x (H) can x (K) = rem WHOIE BODY CHILD 'IHYROID (2 Hour) (2 Hour) L O ~

.A. .%b - +, - EPP-005 ATTACPlENT III A PAGE 10F 2 - Q REVISION 8 0FF-6ITE DOSE CAIfUIATION USING HIGH RANGE MONI'IORS Time of Trip Current Time Time after Trip i M-A13 RM-14 RM-019 A, B, or C l DOSE RATE mr/hr mr/hr mr/ fir (A1) FIDW RAN C1H CIH lb/hr (A2) (from Att. XX) 3 MASS /VOL 1 1 ft /lb (A3) (from Att. XIV) Calibration 4.0 x 10-5 9 5 x 10-5 8.5 x 10-4 (B1) i ' Correction Factor from Attachnent XI (B2) Release Rate (A1) x (A2) x (A3) x (B1)/(B2) C1 (C) O ~ (C) x 3600 = C1/hr (use in EPP-001) t Wind Speed: MPH x 0.45 = m/sec (D) (X/Q)u from isopleth for 1 mile m-2 (E1) X/Q: (El)+(D) = sec/m3 (F) Noble gas dose to concentration conversion frun Attachment VII x2= mm/2hr (0) C1/m3 WOLE B)DY DOSE (2 hr.): (F) x (C) x (0) = rem (H) 2hr Iodine to noble gas activity ratio (use 0 3 tinless ceasured) (I) Iodine dose to' concentration conversion fran Attachment VII rem /2hr (J) ci/m3 O O ,f-. ,7.. c.. - -, -.- ,--._--.---~m..m.m. -.-._.,...-m..,...,.,. .,-n, . - = -. - ...-.e

EPP-005 ATIACIMNT III Q PAGE 2 0F 2 ty REVISION 8 0FF-SI'IE DOSE CALCULATIONS USING HIGH RANGE ?0NI'ITS Time of Trip Current Time Time after Trip Iodine to noble gas dose ratio (I) x (J) + (G) (K) CHILD 'IHYROID DOSE: (K) x (H) = at 1 mile 92 hour) rem /2hr. (X/Qu at 2 miles (E2) (E2)2(E1) (L2) 5 miles (ES) (ES)/(El) (L5) 10 miles (E10) (E10)/(E1) (L10) O e k O e E ...w- ~ - - - 3

EPP-005 ATfACHMH7f IV C') PAGE 10F 1 REVISION 8 ACTIVITY REEASE STATUS Time: Elapsed time since last release calculation sec (A1) he (A2) Noble Gas Average release rate since.last calculation C1/sec (B1)*** Activity released since last calculation (Alx B1) C1 (C1) Previous total of noble gas released C1 (D1) Total activity released (Cl + D1) C1 CURRENT DOSE ELAPSED TIME CURRBTf OLD 'bCTfAL TUfAL DISTANCE RATE (rem /hr) (A2) DOSE DOSE DOSE 1 mile X = + = rem 2 X = + = rem 5 X = + = rem O 10 X = + = mm Iodine Average release rate since last calculation C1/sec (B2) Activity released since last calculation (Al X B2) C1 (C2) Previous total of Iodine released C1 (D2) Ibtal activity mleased (C2 + D2) Ci CURRDff DOSE ELAPSED TIME CURRDff OLD TUfAL TOTAL l-DISTANCE RATE (ren/hr) (A2) DOSE DOSE DOSE l 1 mile X = + = rem 2 X = + = mm l 5 X = + = mm l 10 X = + = rem

- - B1 x.3600 =

C1/hr, This figure is to be used for determining Emergency Action Ievels in EPP-001 Attachment I. I ' O y l l t

EPP-005 ATTACHMENT V b' PAGE 1 0F 1 \\ REVISION 8 OUT OF PIAVf MONI'IORING DISPA'ICH AND DATA F0fM Dispatch Unit Time l Iocation Miles Degrees j Conrents: J e Report 1 f\\ ~ Incation Confimation YES/NO TLme Rad Ievel R per hour (A) Air Sample Volume cubic ft. x 28320 = cm3 Particulate net epm uC1/cm3 (B) Particulate Concentration = Iodine net epm (c) u C1/cm3 (c) Iodine Concentration = Iodine dose to concentration conversicn rem /2hr frun Attachmnt VII u C1/m3 (D) 2 hr. child thyroid dose (C) x (D) rem (E) 2hr NOTE: Cortpare (A), (B), and (E) to PAGS (Attach:ent XII) O h p ..-.___,_Q_.

EPP-005 ATTACHMBff VI \\ PAGE 1 0F 1 REVISION 8 0FF-SITE DOSE CAILULATIONS FROi ENVIR0fMENTAL MONI'IORING Sample Time Tirae After Trip Location Noble Gas - Direct Measurement R/hr (A) Iodine - Direct Measurement net cpn (B) Sample Volume ft.3 (C) ~ (B) + [(C) x 2.09E8] = C1/ml (D) Dose-Concentration Conversion Fac' tor ' from Att. VII (E) (E) x (D) = Rem /2hr (F) XA$I at sample location fran isopleth (G) s \\ ( A) + (G) = (H) (F) + (0) = (I). X/6 from isopleth at 1 mile = (J1) 2 miles = (J2) 5 miles = (J5) 10 miles = (J10) Irsergrated Dose Rate NOBLE GAS (WHOIE BODY) IODINE ('IlffROID) 1 mile (H) x (J1) x 2 = Rem /2hr I x J1 = Ren/2hr 2 miles (H) x (J2) x 2 = Rem /2hr I x J2 = Rem /2hr 5 miles (H) x (JS) x 2 = Rem /2hr I x J5 = Rem /2hr 10 miles (H) x (J10) x 2 = Rem /2hr I x J10 = Rem /2hr OV. i I

( DOSE CONCENTRATION CONVERSION ~ i Noble Gas EPP-005 Radiofodine Attachinent VII rem /t]r 3/m Fage 1 of 1 Ci/m' rem /Rhr Revision 8 600 ~ ~. 500 3.5EG 400 3.0E6 N* ~ ~ ^ ~- ~, a 2.5E6 300 s/s' ~ l /' / '/ ~ s 2.0E6 200 /e /- / ./ 1.5E6 100 ,/. - e i fm m,, ~ ] '~ ~ -[ 1 see8 ' ' 0E6 L aeaa aaeaa anaea aanaa aae ae saiea aaaa: 3 0 12 24 36 48-60 72 . 8'4 96 l, .f. TIMEPOSTTR}h(HR) i f. s s 1

EPP-005 ATTACHMBfr VIII PAGE 1 of 1 REVISION 8 ADOSPHERIC STABILITT CIASSIFICATION Temperature Differential ( aT) l Stability Pasquill T in 'F Classification Categories _ 61-10 m 40-10 m Extremely Unstable A f-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 Slightly Stable E -0.45 to 1 37 -0.26 to 0.80 Moderately Stable F 138 to 3.67 0.81 'to 2.16 Extremely Stable G >3 67 >2.16 0 8 4 f O .5 + t a e ~

<-e-v q

,_w,,,,

EPP-005 ATTACHMENT IX s PAGE 1 of 1 PS/ISION 8 ADOSPHERIC STABILITY COLSSIFICATION Sigma 'Iheta (o O Stability Pasquill (degrees)* Classification 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 0

Standard deviation ol' horizontal wind direction fluctuation over a period of 15 mirutes to 1 hour.

(Wind Range divided by 6) l Ref. USNRC Reg. Guide 1.23, Rev.1, Sept.1980. l l O o e M

c-EPP-005 ATTACHMENT X O PAGE 1 of 1 REVISIN 8 FETEOROIOGICAL SSHOR DEFINITION Wind Central Direction Value Limits of Sector Secter (degrees) in Degrees NNE 22 5 11.25 < 1 33 75 NE 45 0 33 75 < 1 56.25 DE 67 5 56.25 < 1 78.75 E 90.0 78.75 < 1101.25 ESE 112 5 101.25 < 1 123 75 ~ SE 135 0 123 75 < $ 146.25 SSE 157 5 146.25 < f 168.75 S 180.0 168.75 < 1191.25 SSW 202 5 191.25 < 1213 75 SW 225 0 213 75 < 1236.25 WSW 247 5 236.25 < I 258.75 W 270.0 258.75 < 1281.25 WNW 292 5 281.25 < 1303 75 NR 315 0 303 75 < 1 326.25 NNW 337 5 326.25 < 1348.75 N 360.0 348 75 < 1 11.25 CAIR Wind speed less than 0 75 c:ph l MISSING Unreliable data o l l-5 i t

O i 's N CORRECTION FACTOR .f l i ~m U= IIIGH RANGE MONITORS '-l 6 OC an m.o o m QU M g l es G 'e= pe 4J tio > pe as se as. ,t DJ < pea: e e

0.20 i

F. s . A. w,. 0.15 - - ~ l e e i = 0.10 __8 .-4 bu LaJ a: .o 0.05 4 g b g -l h.l $ $ $ I $ $ I l $ I l l $ P ,0 12 24 36 48 60 72 84 96 TIME POST TRIP (ilR) i e. p _- (.,.

O O O EPP-005 a ATTACINDff XII PAGE l or 2 REVISION 8 REC 019 ENDED PfmECTIVE ACTIONS TO REDUCE MOIEDODY AND illYROID DOSE FROM EXPOSURE TO A GASEOUS PLLME Projected Dose-(Hem) to (a) the Population Recommended Actions Comnents (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 j Particulate <1.5x10-7 and await further instmetion. or tenninated. uC1/ml Monitor envircranental radiation levels. Wholebody 1 to < 5 Seek shelter as a minimisn. If constraints exist, special Thyroid 5 to < 25 Consider evacuation. Evacuate unless consideration should be given Pargiculate15,to<75m constraints mke it impractical. for evacuation of children and 10- uCi SEE PAGE 2 OP 2. Monitor environmental pregnant women. ml radiation. levels Control access. j Wholebody 5 and above Conduct mandatory evacuation. Seeking shelter would be an i Thyroid 25 and abov2 SEE PAGE 2 OP 2. Monitor environmntal alternative if evacuation were Particulate 7 5x10-I radiation levels and adjust area for not immediately possible u01 and above mandatory evacuation based on these levels. I ml Control access. Projected Dose (Rem) to i Emergency ibam Workers Wholebody 25 Control exposure of emergency team members Although respirators and stable to these levels except for lifesaving iodine should be used where missions. (Appropriate controls for emer-effective to control dose to j gency workers, include time limitations, emergency team workers, thyroid respirators and stable iodine.) dose may not be a limiting Wholebody 100 (c) Control exposure of energency team members factor for lifesaving missions. l performing lifesaving missions to this level. (Control of time of exposure will be most effective.) (a) These actions are recommended for planning purposes. Protective action decisions at the time of the incident must take existirg conditions into consideration. l (b) At the time of the incident, officials may implemnt low-impact protective actions.in keeping with the principle of mintaining radiation exposures as low as reasonably achievable. (c) Take all reasonable actions to keep lifesaving exposures below 75 Rem. 1 I. 1

EPP-005 O ATTACHMENT XII PAGE 2 OF 2 V REVISION 8 ESTIMATED EVACUATION TIMES FOR EMERGENCY PLANNING ZONES Re, commend evacuat' ion of the public within a zone when projected doses are 1 Rem or greater whole body, or 5 Rem or greater thyroid, unless restraints make evacuation impractical. If the plume will' arrive within the zone before evacuation can be completed, recommend sheltering. ESTIMATED EVACUATION TIMES (MINUTES) ZONE POPULATION AVERAGE WEATHER ADVERSE WEATHER A-0 312 138 167 .A-1 396 166 199 A-2 960 149 199 B-1 284 142 166 B-2 528 112 128 c-1 304 132 155 c-2 832 112 128 D-1 816 116 135 b]s D-2 712 107 121 E-1 668 137 165 E-2 2524 153 182 F-1 268 133 158 F-2 800 138 162 G + O m-n gg,,y,7- -g-n -y ,ww ,,._e,,,, y --m m ew,.-,,wg,----,, -.,-,--m,,>g-n- .,--,a -n

EPP-005 ('~') ATTACEMENT XIII (" s PAGE 1 0F 3 REVISION 8 The Pasquill-Turner Method for Determining Atmospheric Stability' If both the primary and secondary T 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 sytem, 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 is determined as follows: 1) If the total cloud cover is 10/10 and the ceiling is less than 7000 feet, use net radiation index equal to O (whether day or night). 2) For nighttime (defined.as the period from one hour'before sunset to one hour after sunrise'): a) If total cloud cover < 4/10, use net radiation index ~ (~~} equal to -2. b) If total cloud cover > 4/10, use net radiation index equal to -1. 3) For daytime: a) Calculate the Solar Altitude as follows: Calculation of Solar Altitude a = arcsin l'sind sin 0+ cos ( ( s-12 ) 180*) cos 6cos 0] T where 0 = station latitude = 34 3* H = hour of day (24 hour clock, E.S.T) 6 = arctan ( - tan (23 5*) cos (360* ( N+10) J 365 where N = number of days from the beginning of the year AO

-,W-m,- EPP-005 ATTACHMENT XIII - [s' 5-- PAGE 2 0F 3 REVISION 8 The Pasquill-Turner Method for Determining Atmosoheric Stability b) Determine the insolation class number as a function of solar altitude from Table 2. c) If-cloud ' cover '< 5/10, use the net.radis. tion index corresponding to the insolation class number. d) If cloud cover > 5/10, modify the insolation class number by the following stepe: 1) If ceiling < 7000 feet, subtract 2 ii) If ceiling > 7000 feet, but <16,000 feet, subtract 1 iii) If 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 modified insolation class number is less than 1, - (wf' let it equal 1 vi) Use the net radiation index corresponding to the 4 ' modified insolation class number Thus, it can be seen from Table 1 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. e e h V --n., g ._e ,,-_,---,-,-n.., y .-,a- ,s,

EPP-005 ATTACHMENT XIII f'~T PAGE 3 0F 3 ( i REVISION 8 TABLE 1 STABILITY CLASS AS A FUNCTION OF NET RADIATION AND WIND SPEED Wind Speed

Net Radiation Index (MPH 1 (knots) 4 3

2 1 0 -1 -2 0, 1.15 0, 1 A A B C D F G 2, 3.45 2, 3 A B B C D F G 4.6, 5 75 4, 5 A B C D D E F 69 6 B B C D D E F 8.05 7 B B C D D D E 9 2, 10 35 8, 9 B C C D D D E 11 5 10 C C D D D D E 12.65 11 C C D D D D D >13 8 > 12 C D 'D D D D D ' Table 1 was developed for wind speed in knots., To convert from knots to meters per second, ' multiply roughly by .5, accurately by.51444. TABLE 2 INSOLATION AS A FUNCTION OF SOLAR ALTITUDE Insolation l Solar Altitude (a) Insolation Class Number 60' < a Strong 4 l 35* < a 1 60 Moderate 3 '1)* < a 1 35 Sli ght 2 a 1 15' Weak 1

- See Page 2 of this attachment.

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l EPP-005 ATTACHMENT XV PAGE 1 0F 1 (s) REVISION 8 0FFSITE DOSE CALCULATI'ON USING CONTAINMENT LEAKAGE SOURCE TERM Time of trip: Current time: Time after trip I RM-G7 RM-G18 Dose Rate: mr/hr mr/hr (A1) l Flow Rate: 2 56 CFM 2.56 CFM (A2). Calibration: (from Attachment XVI or, if HPP-906 has been (B1) initiated then Attachment XVII) l Release Rate: (A1) x (A2) x (B1) C1/Sec (C) = (Continue calculations following release rate 7-sc derivation in Attachment III) N,, l O 6 g-w..

10 - - a = = g y 9,_, A -= --. 7 E EPP-005 =- 7 V 8.. .r. =E- - := Page 1 of 1 7 -- _ _. l~ T. ~_- Revision 8 6.. ____-i-x; s... 4.. l 3.. l l l I i i 1 6 e e 4 l f f t I e i i 2,, I i .. s. x. L. s -- 3 i RM-G18 i i ,I E t, i f a 6 RM-G7 - /s e' l e , * -s e t ' 1 1 q q Vl f, r 1E-9 2'--=..-.._-

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( Ni)E'RdM/HR l PROJECTED WHOLE BODY EXPOSURE RELEASE RATE RATE (NOBLE GAS) AT I MILE I__ 3 NOBLE GAS RELEASE CFM ^ e-- ! :- IX 10 f PREPARED BY: CONCENTRATION I X 10, 8-DATE/ TIME : 4-- o 2-2-- f REVIEWED BY: Cl/Sec -2 i -l I XIO -- lX IO jsCIAni i 2 3 ~ ~ SHUTDO N I X16 - - 2 4 4 g .j-- ENERAL HRS f.X I -2 IXIO2 i 6-- EMERGENCY 2-t IXIO - 4-f_ _4 e-4_ s: 4 s-s 2-- #:: IXIO.3 -a e

- l y sitt eucacewCv _

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EPP-005 ATTACHMENT XVIII ~') PAGE 2 OF 4 REVISION 8 NOMOGRAM INSTRUCTIONS 1.0 Dete.rmine each concentration of noble gas and iodine in the effluent. Record values, uC1/ml, separately on the two nomograms.. The following measurement. methods should be used based.on obtaining the most accurate results under the time restrictions present. 1.1 Use grab sample results whenever possible. A'Iways verify nomogram results with computer calculations and grab sample results whenever practical. 1.2 Utilize RMS readings (low range) and correlation graphs in HPP-904. 13 Utilize high rande RMS channels to estimate the noble gas concentration. Assume the iodine concentration is 0 3 of the noble gas concentration unless grab sample results show otherwise. 2.0 Record the following information on each nomogram based on control room indications. 2.1 Time after shutdown in hours. 2.2 At from 61-10m in

F.

23 Wind speed in MPH, preferably at 10 m. 2.4 Release rate in CFM. 30 Using the numbered scales, connect the following points: L 31 A to B to obtain C (4). I.2 1 to 2 to obtain 3. 33 3 to C (4) to obtain 5 l 3.4 5 to 6 to obtain 7 4.0 Obtain an independent review to assure scales are properly used. l l 5.0 If the release concentration exceeds the range of the l scale, the release concentration can be divided by 1000 in l order to utilize the nomogram. However, the result must be multiplied by 1000. l 6.0 Results are accurate to within 30% of actual calculations if the nomogram scales are properly used. l L ,-.,.n. p

l 3 N AT I Mll.E : RELEASE RATE 3.ci/mi I a.M/2lla PROJECT -D THYROID DOSE RATE 1 X 10 - ._ $,,. d N LODINE CFM e- , I X 103 u- - g3 PREPARED BY : RELEASE - - I X 108 l 4- .DATE / TIME CONCENTRATION 2-2- REVIEWED BY l Cl/Sec -2 i XIg5-_ 2 - :IX10 pCihnl l g-I 7 GENERAL TIME AFTER d

-- I XIO4

-7 EMERGENCY SHUTDOWN A dMhh I X IO - 2~ 4- ~ 4-- l , l X IO l 4 -s u g -6 ll: HRS. 6 O'T" MSE -I X 10* - lx102 - 9 or >c c utas. sir 1 X IO. -- 4- -4 r uin. n s- - .s 4--

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EPP-005 ATTACHMENT XVIII r~s PAGE 4 0F 4 (_,) REVISION 8 NOMOGRAM INSTRUCTIONS 1.0 Determine each concentration of noble gas and iodine in the effluent. Record values, uC1/ml, separately on the two nomograms. The following measurement methods should be used based on obtaining the most accurate results under the time restrictions present. 1.1 Use grab sample results whenever possible. Always verify nomogram results with computer calculations and grab sample results whenever practical. 1.1 Utilize RMS readings (low range) and correlation graphs in HPP-904. l.3 Utilize high range RMS channels to estimate the noble gas concentration. Assume the iodine concentration is 0 3 of the noble gas concentration unless grab sample results show otherwise. 2.0 Record the following information on each nomogram based on control room indications. 2.1 Time after shutdown in hours. O - (,). 2.2 at from 61-10m in 'F. 23 Wind speed in MPH, preferably at 10 m. 2.4 Release rate in CFM. 30 Using the numbered scales, connect the following points: 31 A to B to obtain C (4). 32 1 to 2 to obtain'3 3.3 3 to C (4) to obtain 5 3.4 5 to 6 to obtain'7 4.0 Obtain an independen.t review to assure scales are properly used. 50 If the release concentration exceeds the range of the scale, the release concentration can be divided by 1000 in order to utilize the nomogram. However, the result must be multiplied by 1000. 6.0 Results are accurate to within 30% of actual calculations if the nomogram scales are properly used. e b D

EPP-005 ATTACHMENT XIX () PAGE 1 0F 7 (,,/ REVISION 8 ESTIMATION OF RELEASE RATES FROM FSAR LISTED ACCIDENTS STEAM LINE BREAK ACCIDENT Accident Duration: 8 hours Accident Assumptions: Realistic Case: 0.12% Fuel Defects prior to accident; 42 GPM Steam Generator Blowdown. Conservative Case: 1.0% Fuel Defects prior to accident; 15 GPM Steam Generator Blowdown; 5% Fuel Failure during accident. Noble Gas Release Iodine-to-Noble Rate (Ci/S) Gas Ratio Realistic Case 0-2 hours 3 15E-6 0.288 2-8 hours 3 15E-6 0.063 Conservative Case 0-2 hours 2.0218 0.0812 2-8 hours 2.0218 0.0109 (T CVCS LETDOWN LINE. RUPTURE .Q Accident Duration: Up to 1 hour Accident Assumptions: Realistic Case: Shutdown long period of time (up to 90 days); 0.12% Fuel Defects at time of accident. Conservative Case: Shutdown short period of time (can be operational); 1.0% Fuel Defect at time of accident. Noble Gas Release Iodine-to-Noble Rate (01/S) Gas Ratio Realistic Case 0.-10 min. .0278 0.0176 10-20 min. .0276 0.0174 20-30 min. .0275 0.0172 30-40 min. .0274 0.0170 40-50 min. .0273 0.0168 50-60 min. .0272 0.0167 f I

EPP-005 ATTACHMENT XIX [~h. PAGE 2 OF 7-REVISION 8 .V CVCS LETDOWN LINE RUPTURE (Cont'd) Noble Gas Release Iodine-to-Hoble Rate (C1/S) Gas Ratio Conservative Case 0-10 min. 1 529 .0032 10-20 min. 1 525 .0031 20-30 min. 1 523 .0031 30-40 min. 1 521 .0030 40-50 min. 1 519 .0030 - 50-60 min. 1 517 .0029 CONTROL ROD EJECTION ACCIDENT Accident Duration: 24 hours Accident Assumptions: Realistic Case: 0.12% Fuel Defects prior to accident; 100 lbs/ day -Primary-to-Secondary Leakage; Dump Steam to Condenser Conservative Case: 1.0% Fuel Defects prior to accident; 1.0 GPM Primary-to-Secondary Leakage; 10% Fuel Fa11'ure 7-~ during accident; Dump Steam to Atmosphere. - # ~ Ultra-Conservative Case: 1.0% Fuel Defects prior to accident 1.0 GPM Primary-to-Secondary Leakage; 10% Fuel Failure and 0.25% Fuel Melt during Accident; Dump Steam to Atmosphere. Noble Gas Release Iodine-to-Noble Rate (Ci/S) Gas Ratio Realistic Case 0-2 hours 2 57E-5 0.18-2-8 hours 2.46E-5 0 336 8-24 hours 2 37E-5 0.126 Conservative Case 0-2 hours 0.1366 1.15 2-8 hours 0.0916 1.102 8-24 hours 0.063 0 973 Ultra-Conservative 0-2 hours 0.1707 1.031 2-8 hours ~0.113 1.0 8-24 hours 0.038 0.876 NOTE: The above Noble Gas Release Rate is for 0.2% contdinment leak rate per 24 hours (2 5 cfm). If containment leakage is other than assumed, relate proportionally. A(s I =c 3 y 4

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EPP-005 ATTACHMENT XIX PAGE 3 0F 7 REVISION 8 LOCKED PUMP ROTOR ACCIDENT Accident Duration: 8 hours Accident Assumptions: Realistic Case: 0.12% Fuel Defects prior to accident. Conservative Case: 1.0% Fuel Defects prior to accident; 10% Fuel Defects during accident. Noble Gas Release Iodine-to-Noble Rate (C1/S) Gas Ratio Realistic Case 0-2 hours - 3 15E-6 6.5 4E-3 2-8 hours 3 15E-6 3.62E-3 Conservative Case 0-2 hours 2.044 0.0114 2-8 hours 2.044 0.0069 O b I f e-

l EPP-005 ATTACHMENT XIX PAGE 4 OF 7 -(O} REVISION 8 LOSS OF COLLANT ACCIDENT (LOCA) Accident Duration: 1000 hours Accident Assumptions: Realistic Case: 100% of RCS Noble Gases and 50% of RCS Iodines ' l released. Conservative Case: 100% of Gap and RCS Noble Gases and 50% of Gap and RCS Iodines released. Regulatory Guide 1.4 Case: 100% of Core, Gap and RCS Noble Gases and 25% of Core Iodines + 50% of Gap and RCS Iodines released. Noble Gas Release-0-2 2-8 8-24 24-96 4-30 Rate (Ci/S) hours hours hours hours davs Realistic Case 0.00153 0.0015 0.00143 0.0013 0.00088 Conservative Case 0.0467 0.0754 0.0416 0.0339 0.0200 Reg. Guide 1.4 Case 13 456 7 388 5.032 3.693 2 327 "T (U Iodine-to-Noble 0-2 2-8 8-24 24-96 4-30 Gas Ratio hours hou rs 'hou rs hours days Realistic Case 0.015. 0.0131 0.0101 0.0068 0.0028 Conservative Case 0.047 0.25 0.36 0 304 0.187 Reg, Guide 1.4 Case 0.29 0 35 0.29 0.163 0.085 NOTE: The above Noble Gas Release Rate is for 0.2% containment leak rate per 24 hours (2.5 cfm). If containment leakage is other than the assumed relate proportionally. t v O . ~ -, - v

4 EPP-005 ATTACHMENT XIX PAGE 5 0F 7 [sT REVISION 8 s._/ WASTE GAS DECAY TANK RUPTURE Accident Duration: 0 5 to 10 hours Accident Assumptions: 1.0% Fuel Defects while collecting Waste Gas in tank; accident immediately after isolation from Waste Gas System; complete contents of WGDT dumped. Time to Empty Tank Noble Gas Release Iodine-to-Noble (Release Period) Rate (C1/S) Gas Ratio 0 5 hour 12.23

1. 2 9E-5 2 hours 3.04 1.2 6E-5 4 hours 1.51 1.2E-5 6 hours 0 997 1.16E-5 8 hours 0.74 1.13E-5 10 hours 0.86 1.lE-5 STEAM GENERATOR TUBE RUPTURE Accident Duration:

'8 hours fs Accident Assumptions:, ( ) Realistic Case: 100% lbs/ day (0.0083GPM) Primary-to-Secondary Leakage; 0.12% Fuel Defects; 42 GPM Steam Generator Blowdown. Conservative Cases: 0.1 to 1.0 GPM Primary-to-Secondary Leakage; 1% Fuel Defects; 15 GPM Steam Generator Blowdown. Noble Gas Iodine-to-Noble Gas Release Rate (C1/S) Ratio 0-2 hours 2-8 hours 0-2 hours 2-8 hours Realistic Case 4.45E-2 2.11E-6' 4.24E-4 5 98E-3 Conservative Case 2 73 1.42E-4 6.7E-5 3 2E-2 (0.010PM) Conservative Case 2.73 1.42E-4 8.35E-5 3 2E-2 (0.lGPM) Conser'vative Case 2 73 1.42E-4 2 37E-4 3 2E-2 (1.0GPM) t .d 5 -y-- __w. -.---m.-- g

EPP-005 ATTACHMENT XIX PAGE 6 OF 7 r-'g REVISION 8 FUEL HANDLING ACCIDENT Accident Duration: 2 hours Accident Assumptions: Realistic Case: Average - Power Assembly; > 100 hours af ter fuel assembly subjected to Reactor flux; and one row of fuel pins damaged. Conservative Case: Highest.- Power Assembly; 100 hours after plant shutdown, all fuel pins damaged; good retention of Iodine in Spent Fuel Pool Water. Regulatory Guide 1.25 Case: Highest-Power Assembly; 100 hours af ter shutdown; all fuel pins damaged; all gap activity released; poor Iodine retention in Spent Fuel Pool Water. Noble Gas Release Iodine to Noble Gas Rate 0-2 hours (C1/S) Ratio Realistic Case 0.0117 0.00005 Conservative Case 2.233 0.000093 ~ Regulatory Guide 16.51 0.00073 1.25 Case NOTE: The realistic case values above are for one row of fuel rods. If more than one row is damaged, multiply the number of rows times the realistic case data. S 9 f h

EPP-005 ATTACHMENT XIX PAGE 7 0F 7

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~ REVISION 8 LOSS OF OFFSITE POWER ACCIDENT Accident Duration: 8 Hours Accident Assumptions: Realistic-Case: 100 lbs/ day Primary-to-Secondary Leakage; 0.12% Fuel Defects prior to accident; 42?GPM Steam Generator Blowdown. Conservative Case: 1.0 GPM Primary-to-Secondary Leakage; 1.0'% Fuel Failure-prior to Accident, 15 GPM Steam Generator Blowdown. Noble Gas Release Iodine-to-Noble Rate (Ci/S) Gas Ratio ~ . 0-2 hours 3 15E-6 0.00654 Realistic Case 2-8 hours 3 15E-6 0.00362 Conservative Cast 2 0-2 hours 0.0218 1 76E-3 2-8 hours 0.0218 8.54E-4 e ,A O s e. 4g 'em l I l t i t /' lO ~ ~ + s, f1 ---.------.,,,,s h m s~., s,,, ,-,--.,,,,,--,---.-.-,--._-ln'

EPP-005 l ^ ATTACEMENT XX PAGE 1 0F 1 7 3 REVISION 8 i \\- ESTIMATION OF RELEASE RATE FROM MAIN STEAM RELEASES The formula shown below can be used to calculate the 1bs/hr release rate for use in Attachment III when estimating off-site doses from main steam relief valve actuation or a main steam line rupture with primary to secondary leakage. The formula estimates only the release from main steam and does not include releases from the main plant vent via the condensor off-gas. Off-site dose calculations must be independently performed for both source terms with the results summed to calculate total off-site doses. 6 RELEASE RATE, lbs/hr = MSF - (.06)(ODV)(G)(4.1 x 10 ) where; MSF = Main Steam Flow from leaking generator (s) in lbs/hr from Control Roon readout ODY = Number of open condensor dump va1ves (maximum of 8)* l G = Number of leaking generators .06 j([~) = Fraction of steam passed by each condensor dump valve ,/ at 100% power 4.1 x 106 = lbs/hr steam flow from each generator at 100% power NOTE: In the event of a main steam line rupture and/or MSIV closure, ODY = 0 and the 1bs/hr release rate is equal to the main steam flow from the leakin8 6enerator(s). Status Lights on Main Control. Board for Condenser Dump Valves PFV-2116 PPV-2096 PFV-2097 PFV-2106 PPV-2107 .c PPV-2117 PFV-2126 PPV-2127 /'

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SOUTH CAROLINA ELECTRIC AND GAS COMPANY , - ~, .( i VIRGIL C. SUMMER NUCLEAR STATION q.; NUCLEAR OPERATIONS NUCLEfJ1 CEERAi!ONS COPY lio..... h.3....... EMERGENCY PLAN PROCEDURE EPP-009 ON-SITE MEDICAL REVISION 4 , JANUARY 23, 1985 NON-SAFETY RELATED %..,) Md)o 8S' DISC {PLINE SUPERYTSOR / Dgte l AA ri n 3)M/Gg - f l APPROVAL AUTHORITY Date ~ APR 0 21965 DATE ISSUED RECORD OF CHANGES l CHANGE] TYPE l DATE l DATE l CHANGE TYPE DATE DATE NO. CHANGE APPROVED CANCELLED NO. CHANGE APPROVED CANCELLED l l e a

.. =. c_.__..._ , -i -.. :. r EPP-009 PAGE i REVISION 4 1/23/85 TABLE OF CON'ENTS PAGE List of Effective Pages i 1.0 PURPOSE 1. l

2.0 REFERENCES

1 3.0 CONDITIONS AND PREREQUISITES 1 4.0 PROCEDURES 2 ATTACHMENTS ' ATTACHMENT I - Personnel Injury and Contamination Report ATTACHMENT II - V.C. Summer Station Helicopter Landing Sites. 9 i x I J e l e an._ 8 .f \\ 4 a = - e .,.....e,- ,_y, y evn-,-, -p%,9...w,,p,,,,_,-.,,y. w.,.wie,3-,wmww,,,m,_ ,,w,.,,,,,-,_,,,,.my,,m%,__,w,.w.,,_,--

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1. 0 PURPOSE 1.1 To provide guidelines for handling individuals who have been injured, with or without associated contamination, and may be in need of off-site medical treatment.

2.0 REFERENCES

2.1 " Virgil C. Summer Nuclear Station Radiation Emergency Plan." 2.2 EPP-010, " Personnel / Vehicle Decontamination." 23 EPP-002, " Communications and Notifications. " 2.4 NUREG-0654, " Criteria for Preparation & Evaluation of Radiological Emergency Response Plan; & Preparedness in Jupport of Nuclear Power Plants." 25 EPP-018, " Emergency. Facilities Activation and Evacuation"

2. 6 EPP-020, " Emergency Personnel Exposure Control. "

m I 30 CONDITIONS AND PREREQUISITES 4 31 The first level of treatment shall be given on-site. If the injury occurs in the Radiation Controlled Area (area beyond the 412' elevation of the Control Building) and the patient becomes contaminated, injury should be treated at the 412' elevation of the Control Building (H.P. Lab area). ' 3. 2 If the injury does not inv.olve contamination and the patient can be moved,the injury should be treated at either the first aid room located in the Control Building, or the first aid dispensary located in the Service Building, 436' elevation. 33 The First Aid Team Leader should be the "B" Nuclear l Reactor Operator or his alternate as available. Other members of the First Aid Team should be available Auxiliary Operators, Maintenance personnel, Chemistry personnel, etc. as per EPP-016, Attachment II. O' PAGE 1 of 5 4 -e.

.. ~.. EPP-009 REVISION 4 () 1/23/85 4.0 PROCEDURES 4.1 The Shift Supervisor / Emergency Director shall dispatch the first aid team and Health Physics representative to the area of the injured individual. The team shall initiate li'fe saving actions where required; and then perform the following: ~ 4 1.1 Survey the patient and determine if any contamination is present. Determine if off-site assistance is needed. A. A member of the team should. contact the Control Room /TSC and apprise them of the situation, i.e., name and location of victim, physical and radiological condition of. victim, team recommendations for off-site assistance, and team recommendations, for next actions. If the patient is not contaminated, continue first aid treatment. The patient should be moved to the first aid room for treatment when such a move would not endanger the patient. B. If the patient is or is expected to be externally contaminated, initially perform only ( the first aid treatment necessary. Follow ' - ^ procedure EPP-010 " Personnel / Vehicle Decontamination." 4.2 If requested by the First Aid Team, the l Communicator / Interim Emergency Director /ED will notify' the Company Physician, 945-7475 - 43 If the report of the First Aid team indicates the person must be transported. to the hospital, the IED/ED will assure that the following is performe'd: 431 The First Aid Team shall: A. Decontaminate the patient to the 'ullest extent f possible, considering the extent of the injuries. ~ 1. Where difficulty in decontamination is encountered, wrap the affected area in a blanket, - plastic, or sterile dressing (in the case of a wound) to isolate the opntamination. NOTE: Avoid excessive wrapping due to the possibility of overheating the victim. G PAGE 2 of 5

^ ^ .. _.... -.. ~. .EPP-009 REVISION 4 1/23/85 7-_ k B. Prepare the person for transport as follows: s-1. Complete the Personnel Injury and Contamination Report with all available information to accompany patient (see Attachment I). 2. Notify the Technical Support Center / Control Room that the individue is ready for transport to the hospital. 3 The TSC/ Control Room should inform First Aid Team where victim is to be picked up by the ambulance. 432 At the same time that the person is being prepared for transport, the Communicator will: 4 3 2.1 Notify the hospital, 765-7561, so the l medical personnel there will have the time to prepare th., proper facilities. NOTE: All injuries occurring within the RCA should be treated at Richland Memorial Hospital. (A 4 3 2.2 Request assistance from Ambulance Services, ). b' 635-5511. I NOTE: Depending upon Radiological conditions, inform ambulance personnel of the preferred ingress and egress routes that should be taken. Helicopter landing sites are per Attachment II. 4.4 The' Shift Supervisor / Emergency Director will: 4.4.1 En'sure that a Health Physics representative or qualified radiation worker accompanies the injured person to the hospital and performs the necessary actions. p \\~- PAGE 3 of 5 l

. __ i' ^ ~ _ ~ ~ "cJ ~ ^ ' ' EPP-009 . REVISION 4 D 1/23/85 1,_) 4.4.2 Direct Security Personnel to meet the ambulance at the site entrance and accompany it to the patient 's location. j NOTE: If the injury occurred outside of the radiation control area, and no contamination is involved, the Shift Supervisor / Emergency Director may assign any z.- plant personnel to accompany the victim. NOTE: Security shall provide Dosimetry to Ambulance personnel before entry if they are to enter the RCA or otherwise handle a contaminated victim and as directed by H.P. or~ED/IED. 4.4 3 The Control Room /TSC shall notify hospital of departure of ambulance'from plant site and maintain communication with the hospital via the. appropriate communications equipment. 45 The person accompanying the injured will: 451 Ensure that the Ambulance Radiation Emergency Kit (located in the First Aid Room on the 412' elevation of the Control Building) is taken with a contaminated person who is injured. Items in the Kit are'to be used on an as needed basis. NOTE: The Ambulance Radiation Emergency. Kit contains protective clothing to be used by Ambulance personnel for contamination control, poly bags to collect contaminated waste, absorbent' material to cover clean areas, supplies for posting and controlling areas, and a survey instrument. ~ 4.5 2 Ensure that the transporting vehicle uses the. appropriate hospital receiving area. 453 Notify Control Room /TSC of arrival at hospital. j 4.5.4 Assist in the radiological aspects of the treatment as necessary. A. Assist the hospital. staff in the decontamination activities for the hospital receiving area. Ensure all waste products are properly contained for future disposal. 4.5 5 If protective plastic has been used in the . ambulance,C carefully remove and bar . Summer Nuclear StatioM.it for return to Virgil (} PAGE 4 of 5 s-r j-r. - --

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4 EPP-009 ~ REVISION 4 1/23/85 (] 4.5.6 If contaminated, decontaminate himself prior to leaving the hospital.- 4.5 7 Ehsure that the ambulance and its personnel are surveyed prior to being released. A. The personnel, if contaminated shall be decontaminated at the hospital. B. The vehicle shall be decontaminated at t'he hospital facility or the Virgil C. Summer Nuclear Station. C. Collect dosimetry from ambulance attendants and obtain appropriate information. 4.5.8 Keep the Emergency Director /Shif t Supervisor informed at all times as pertinent information concerning the patient becomes available. 459 Retain all survey documentation and samples and forward to the Radiological Assessment Supervisor as soon as pra'ctical.

4. 6 If the injured or any of the First Aid Team have been over exposed, the requirements of EPP-020, " Emergency Personnel r'/'g.

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l- -8 SOUTH CAROLINA ELECTRIC AND GAS COMPANY VIRGIL C. SUMMER NUCLEAR STATION NUCLEAR OEPR ATIONS V NUCLET.P OPERATIONS COPY No......lg,9 ~~ EMERGENCY PLAN PROCEDURE EPP-019 EMERGENCY EQUIPMENT CHECKLIST REVISION 6 JANUARY 28, 1985 NON-SAFETY RELATED . 1Tff.C DISC {LINE SU.EERVISOR / DgTE 9 b/b //b-3h>lF1' AP7RUVAL AUTHORITY. 'DATE MAR 3 01985 DATE ISSUED PECORD'0F CHANGES CHANGE TYPE DATE D A '.'E CHANGE TYPE DATE DATE NO. CHANGE APPROVED CANCELLED NO. CHANGE APPROVED CANCELLED 1 I l l I l l O j k

EPP-019 PAGE i REVISION 6 1/28/85 TABLE OF CONTENTS Pace List of_ Effective Pages 1 _l.0 PURPOSE 1

2.0 REFERENCES

1 -30 CONDITIONS AND PREREQUISITES 2 4.0 PROCEDURE 2 ATTACHMENTS Control Room Radiation Emergency Eq.uipment Checklist ATTACHMENT I Technical Support Center Emergency Equipment Checklist ATTACHMENT II ATTACHMENT III - Radiation Emeegency Kit Surveillance Requirerents ATTACHMENT III.1 - Control Room Radiation Energency Kit Equipment Che cklist [] ATTACHMENT III.2 ~ - Operations Suppc-t Center Radiation Emergency 's> Equipment Kit Checklist ATTACHMENT III.3 - Firs t Aid (412' Control Bldg) Ambulance Radiation Emergency Kit Emergency Checklist ATTACHMENT III.4 - Security Annex Radiation Emergency Kit Equipment Checklist ATTACH 1ENT III.5 - Aux. Bldg. (436' ) & Fuel Handling Building (463') Radiation Emergency Kit Equipment Checklist ATTAC3 MENT III.6 - T.S.C. Radiation Emergency Kit Equipment Checklist AT!ACHMENT III.7 - Richland Memorial Hospital Radiation Emergency Kit Equipment Checklist ATTACHMENT III.8 - E.O.F. Radiation Emergency Kit Equipment Checklist ATTACHMENT III.9 - E.O.F. Survey Kit Equipment Checklist ATTACHMENT III.10- E.O.F. Dosinetry Issuance Kit Equipment Checklist - ATTACH"ENT III.ll-Guard House Emergency Dosine try Issuance Kit Equionent Checklist r-ATTACH"ENT III.12-CREP Roon Ene rgency Kit \\ s# - ATTACHMENT III.13-Radioactive Materials Transportation Accident Response Kit 4 9 4 _w

EPP-019 REVISION 6 1/28/85 c. -t 8 1.0 PURPO$E G 1.1 This procedure establishes the actions to be taken to ensure the operationh1 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 PDP-101, " 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 2.1.4 HPP-603, Decontamination, Inspection, Maintenance 'and Storage of Respiratory' Equipment. 2.1.5 SAP-134, " Control of S.tation Surveillance Test Activities". /N 2.2 Glossary N. 2.2.1 Abbreviations The following abbreviations appear in the attachments to this procedure: A. BRH - Bureau of Radiological Health B. CHP - Chemistry Procedures C. CR - Control Room D. DHEC-Department of Health and Environmental Control E. E0A - Emergency Operations Area F. EOC - Emergency Operations Center G. EOF - Emergency Operations Facility PAGE 1 0F 3 e

EPP-019 REVISION 6 1/28/85 m() H. E0P - Emergency _ Operating Procedures EPP - Emergency Pl'an Procedures I. J. FEP - Fuel Handling Procedure K. FPP - Fire Protection Procedure 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. S0P - Systems Operating Procedures T. TSC - Technical Support Center U. SC3A - Self Contained 3reathing Apparatus V. SAP - Station Administrative Procedures 30 CONDITIONS AND PREREQUISITES 31 Specific procedural requirements for the operation of the survey instruments listed,in this procedure will be adhered to except for source / daily response checks. The instruments in this procedure shal1 be checked for response to radiation with the source provided in the kits prior to use. 4.0 PROCEDURE 4.1 Surveillance of emergency equi ment shall be in accordance with the requirements specifie in the attachments to this procedure and in accordance with Ref. 2.1 5 [ 6

EPP-019 REVISION 6 1/28/85 1(, 4.2' The 5mergency Coordinator shall assure that. surveillance of the equipment and supplies is accomplished within the specified frequencies and within 10 working days af ter the -use of a kit or kits in a drill, exercise, or actual emergency. 43 All discrepancies detected during surveillance activities shall be corrected within fourteen (14) days. Those 'ot n corrected within (14) days will be brought to the attention of-the Director, Nuclear Plant Operations by the Eme'rgency l Coodinator. l 4.4 Upon successful completion of each surveillance requirement, acceptable results will be documented by signing and dating in the spaces provided. 45 All drawings and procedures shall be controlled in accordance wi.th Ref. 2.1.2. 4.6 All completed equipment checklists will be retained in accordance with Ref. 2.1 5 bv E f PAGE 3 0F 3 '

EPP-019 ATTACHMENT I PAGE 1 0F ? REVISION 6 CONTROL ROOM RADIATION MM ERGEflCY EQUIPMEllT CllECK l.IST QUARTERLY STTS fl0. ITEM EQUIPMENT SURVEIL. MIN. PERPORMED BY: SilELP DESCRIPTION REQMT QTY. INITIAL COMMENTS LIFE 1 VCSNS Radiation Emergency Plan Inventory 1 copy N/A 2 Emergency Plan Procedures Inventory 1 set N/A 3 Map of 10 mile radius Inventory 1 copy 13/A 4 Overlays for 10 mile map 1 each II/A (Stab. Clacces A - G) Inventory of 7 5 Plant Drawings (Control Copy f384) Inventory I set fi/A 6 Pirst Aid Kit Inventory by list 1 each N/A inside Kit 7 Portable Radios (in Inventory N/A normal use) & verify 4 operability Inventory fi/A 8 Operations Frequency & veri fy 1 each Base Radio Operability 9 Security Prequency Base Inventory N/A Radio & verify 1 each operability' EMERG. COORDINATOR DATB e S 9

I EPP-019 ATTA.CIIMENT I J PAGE 2 0F 2 REVISION 6 CONTROL ROOM RADIATION EMERGENCY KIT EQUIPMENT CllECK 1,IST I QlIARTEHLY STTS NO. ITEM EQUIPMENT SURVEIL. MIN. PERPORMED BY SilELP DESCRIPTION REQMT QTY. INITIAL COMMENTS LIFB' 10 Telephone Inventory (Control Room & Verify 1 ea. N/A Supervisor's Desk) Operability g l 11 Intercom Inventory l & Verify I ca. N/A Operability 12 Emergency Director's Log Book Inventory 1 ea. N/A EM EltG. COORDINATOR DATE ~ e G G

EPP-019 TECIINICAL SUPPORT CENTER RADIATION EMERGENCY ATT ACIIM ENT H EQUIPMENT CllECK LIST PAGE 1 0F 3 QU ARTElt LY STTS NO. REVISION 6 ITEM EQUI PM ENT SUlt VEI L. MIN. PEHPOllMED BY DESCRIPTION REQMT QTY. INITIAL COMMENT 3 LIFE UllELP 1 Safety parameter display Verify system operability 1 N/A of software 2 TSC computer and TSC Verify displays operability 1 N/A of software 3 Aperature card reader-Inventory printer & verify 1 N/A operability 4 Copying Machine Inventory 1 N/A & verify operability 5 Map of 10-mile radius and Inventory 1 set Stability Class Overlaps N/A A-G 6 Plant Procedures Audit I set 1 - GOP each 2 - SOP N/A 3 - E0P 4 - EPP 5 - IIPP 6 - PPP 7 - PflP 8 - CilP 9 - SAP EMEHO. C00llDINATOR DATE e G G

EPP-019 TECHNICAL SUPPORT CENTER RADIATION EMERGENCY ATTACllMENT II EQUIPMENT Cif ECK LIST PAGE 2 OP 3 QUARTERLY STTS NO. REVISION 6 l ITEM EQUIPMENT SUltVEib. MIN. PEHFORMED BY SilELP DESCRIPTION REQMT QTY. INITIAL COMMENTS LIFE 7 Drawings of facilliy and systems to the component level (Aperture Card Inventory I set N/A Reader and set of Aperture Cards) 8 FSAR including the Environmental Report Audit 1 set N/A 9 VCS Technical Specifications Audit 1 N/A 10 Miti6ating core damage manual Audit 1 N/A 11 Precautions, Limitations and Setpoints Documents Audit 1 N/A 12 State Radiological Emergency Response Plan Audit 1 N/A 13 County Radiological Emergency Response Plan Audit 1 - Fairfield County 1 N/A 2 - Newberry County 1 N/A 3 - Lexington County 1 N/A 4 - Richland County 1 N/A 14 Title 10, Code of Federal Regulations Audit 1 N/A EMEHO. COORDINATOR DATE O e G G

EPP-019 TECHNICAL SUPPORT CENTER RADI ATION EMERGENCY ATTACl! MENT II EQUIPMENT CllECK LIST PAGE 3 0F 3 QUARTEftLY $TTS NO. REVISION 6 l ITEM EQUIPMENT SURVEIL. MIN. PERFORMED BY DESCRIPTION REQMT QTY. INITIAL COMMENTS LIFE SilELF 15 V. C. Summer Stati~on Radiological Emergency Plan Inventory 1 N/A 16 Potassium Iodine Pillo Inventory & check 100 expiration (min) 3 yrs date EM Eltfi. COORDINATOR DATE ~ e O O

EPP-019 ATTACHMENT III PAGE 1 OP 5 REVISION 6 (m)\\ ~' 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.13 except for kits listed in Attachments III.8 and III.9 which.are the responsibility of i Corporate Health Physica and Environmental Programs. The required frequency of inventories is at least qua,rterly. Respiratory Protective equipment shall be inspected monthly in-accordance with HPP-603 If a kit is used (the seal is broken), the required surveillance shall be performed prior to the kit being placed back into service. 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 requirements are coded and used to verify completion of each kit-surveillance. Any. discrepancies four.d 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 /~s) attachments to this procedure are used prior to signing off each . \\s / item. Surveillance Requirements Code A. Check procedures, maps or forms listed as emergency equipment to ensure that the latest approved / issued revision is in place. Replace as necessary. 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 with 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 (HPP-405 Att.I), a

EPP-019 ATTACHMENT III PAGE 2 0F 5 REVISION 6 !(_- Code Surveillance Reauirements 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 contsin 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 in 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 semiannually. ~ F. Operability of portable survey instruments is verified during calibration on a quarterly basis in accordance with HPP-611 I Calibration of Station Survey Instruments or HPP-610 Certification of Flow Rates for Portable Air Samplers, as applicable. Verify tha.: calibration is current during inventory.. If calibration is past due, remove the instrument after 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 inventory and ensure that the monthly inspection of respiratory equipment has been performed in accordance with HPP-603 Decontamination, Inspection, Maintenance, and Storage of Respirat.ory Equipment, prior to sign-off. e lo l w --w,-- v e.e-, -w-w -,w --e-w-w,----nw-,, -e--w.y--.m,,-_-.-v. - - - - e ,u mn .e-,- e-wc--- ~ -- g,-

EPP-019 ATTACHMENT III PAGE 3 0F 5 REVISION 6 n ( ) Surveillance Reauirements N/ Code H. Ensure this tool kit packet contains a minimun of: 1 allen wrench, 4 hases, 4 nails, 1 screwdriver / nut drive set and 1 hamme r. I. These items require a physical invc package is sealed. . visual. inspection of-condition prior to sign-off unless th If seal is intact, only the presence of the package'. is necessary for sign-off. J. Ensure this pos ting / survey ' packet' contains a mininun of: 50 - particulate air filters 2 ea. - pencil, pens, grease pencils 4 - 3 pocket radiation signs with inserts 50 - smears in envelopes 1 pr. - tweezers 120 - environmental envelones ~ 1 roll - radiation ribbon or 100 ft. of Pad rope (approx.) 1 - Record Logbook 1 - scratch pad 10 - planchets 10- vegetation bags 1 - clipboard 10 - Labeled Air Sample Bags

7. m

(,) 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. K. Place visitor TLD's in a plastic bag and label bag with date of TLD changeout. TLD's are to be changed quarterly. L. Inventory, check calibration date(s), re-zero if >20% of full scale or off scale. P Inventory and functionally check charger at each battery replacement by zeroing a pocket dosimeter. N. 71rst Aid Kits - Ensure each kit contains the following cotton, gauze bandage, elastic bandage, bandaids, and sponge. f . V

EPP-019 ATTACHMENT III PAGE 4 0F 5 REVISION 6 Code ~ ' ( Surveillance Recuirenents 0. Ensure the protective clothing ' packets' contains a minimum of the following items: coveralls (cloth or paper) 1 pair-1 head cover or hood cloth gloves (liners) -1 pair 1 pair riober or work gloves (heavy) 1 pair disposable gloves (light) 1 pair disposable shoe covers 1 pair rubber shua 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 spec ' fied 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 flashlight. t 7-~s Q. Ensure the radiation emergency monitoring kit battery " packet" v) contains a minimum of: \\ 1 set of batteries for the calculator 1 set of batteries for the flashlight i set of batteries for each portable survey inst ument 2 ea. - 1 amp slow blow fuses for the air sampler 2 ea. - 1/8 amp slow blow fuses for RM-14 (or + equivalent. R. Replace-the survey. instrument in the kit with a calibrated instrument with a fully-charged battery. S. Ensure the Decon Kit includes a minimum of: 100 - Smears and envelopes 4 cans - Radcon foam (or equivalent) - Check for expiration 2 rolls - Paper towels 1 - Scratch pad f l N_.] 9

EPP-019 ATTACHMENT III PAGE 5 0F 5 REVISION 6 Surveillance-Recuirements -Code 4 - 3 pocket radiation signs with inserts ~ 2 each - Pens, Pencils, Grease Pencils' 1 - Rol] of Rad ribbon 2 - Poly sheets (approx. 20' x 50') 3 ' Poly bags ( a pp.ro x. 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", s everal " packets", or individually stored. Ensure all items are present in each kit. Z. Run Hewlett Packard 1000 Ocmputer Program to read neteorological data and obtain a listing of latest met tower values to verify (/) , proper operation of met tower to.Hewlett Packard 1000 data link x-as-outlined by EARS Progran Software Package. U. Ensu're the survey ' packet' contains a minimum of 1 - roll of Radiation Ribbon 4 - 3 pocket Radiation Signs with inserts 50 - Smears and Envelopes 2 ea - pencils, pens, grease pencils 5 pr . Disposable gloves F f f '.!v W

EPP-019 ATTACllMENT III.1 PAGE 1 0F 1 REVISION 6 CONTROL ROOM RADIATION Ef1ERGENCY KIT EQUIPMENT CllECK bl8T STTS NO. l ITEM EQUIPMENT SURVEIL. MIN. PERPORMED BY GIIELP i DESCRIPTION REQMT. QTY. INITIAL COMMENTS LI P8' 1 Self Contained Breathing G 6 Apparatus (1 IIour) N/A 2 SCBA Spare Bottles (1 Hour) G 6 N[A 3 Respirators (Full Face) G 6 N/A 4 Spare filter cartridges D' 12 for full face respirators 4 yr. 5 SCBA Spare Bottles (1 Hour) G 36 N/A stored on 485' Elev. of Control Building EMERG. COORDINATOR DATE ~ e 9 9

'-~ ~ -~ O EPP-019 ATTACifMENT III.2 PAGE 1 0F 1 REVISION 6 OPERATIONS SUPPORT CENTER RADIATION EMERGENCY KIT EMERGENCY CliECK LIST STT3 NO. ITEM EQUIPMENT SURVEIL. MIN. PEltPollMED BY: 311 ELF DESCRIPTION REQMT. QTY. INITIAL COMMENTS LIFE 1 Protective clothing C,0 10 6 mo. " packets" (gloves) 2 Respirators (Pull Pace) G 5 N/A l 3 Spare filter cartridges D 10 4'yr. for full face respirators 4 5 rolla of Tape " packet" C 1 1 1 yr. i 5 Plashlight P 5 N/A 6 Battery " Packet" for 5 C,E 1 6 mo. Plashlights 7 GM Survey fleter (E-400/ P 1 N/A E-530) or equivalent ) 8 1 set of batteries for C,E 1 6 mo. l survey instrument 1 9 Vamp Area Monitor (or equiv.) P 1 N/A 10 Co-137 Check Source I 1 N/A 11 SCBA G 2 N/A EMERG. COORDINATOR DATE e e O-

EPP-019 ATTACifMENT III.3 PAGE I 0F 1 FIRST AID ROOM (412 ' CONTROL BUILDING ) AMBULANCE HADIATION EM EltGENC Y KIT EQUIPMENT CliECKLIST STTS NO. ITEM EQUI PM ENT SUHVEIL. MIN. PMHPORMED BY UllELP DESCRIPTION REQMT. QTY. I NIT I A L COMMENT 3 LIPS 1 Protective Clothin8 C,0 4 6 mo. Packeto (Disposable) (gloves) 2 Poly bags (appr.18"x36") I 5 N/A 3 Poly bags (appr.12"x25") I 5 N/A 4 Poly bags ( ap pr.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 Personnel Contamination A 5 N/A Report (IIPP-405 Att. 1) 8 Radiation Tape (roll) I 1 N/A 9 Survey " Packet" C, U 1 N/A 10 RM-14/ IIP-210 Probe (or equivalent) P, R I N/A EMERG. COORDINATOR DATE G 9 1

EPP-019 ATTACHMENT III.4 PAGE 1 OP S REVISION 6 SECURITY ANNEX RADIATION EMERGENCY KIT EQUIPMENT CHECK LLST STTS NO. ITEM EQUIPMENT SURVEIL. MIN. PEHFORi4ED BY UllMLP DESCRIPTION REQMT. QTY. INITIAL COMMENTS LIFE 1 Radiation Emergency /Moni-2

Per listed items N/A toring Kits (Each kit to cont'ain 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 tape " packet" C 1 1 yr. d) Too'1 Kit " packet" C,H 1 N/A e) First Aid Kit N 1 N/A f) Bottles (1 liter) I 3 N/A g) Cs137 Check I 1 N/A Source

1) AgZ Pilters (Plant)

D 10 " packet" 4 yr. j) AgZ Pilters (Environ-D 5 4 yr. mental) " packet" k) Calet21ator P 1 N/A EMERG. COORDINATOR DATE ~ e 9 9

EPP-019 SECURITY ANNEX RADIATION EMERGENCY KIT ATTACHMENT III.4 PAGB 2 OP 5 EQUiFMENT GlihGh, bluT REVISION 6 STTS NO. l 1ThM EQU1FMENT UUHVElb. MIN. l'El( FU MM EU UY: SilMbF DESCRIPTION REQMT. QTY. INITIAL COMMENTS LIFE i (1 Cont)l) Watch 1

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

I 1 set N/A n) Map of 10 mi. EPZ/ A 1 Sampling Stations N/A o) Disposable gloves "pk,t" I 5 pr. 6 mo. p) Roll of paper towels I 1 N/A q) Flashlight P 1 N/A r) Battery " Packet" C, E, Q 1 6 mo. s) E-400/E-530 (or equiva-F 1 lent) N/A t) PIC-6A (or equivalent) P 1 N/A u) RM-14/RP-210 probe (or P, R 1 equivalent) N/A v) 12V Air Sam (or F 1 equivalent)plerw/ cables N/A w) Low Range Dosimeter L 2 (0-500 mr) N/A x) Ifigh Range Dosimeter L 2 (0-lR) N/A y) Whole Body TLD K 2 N/A (1 ) Control TLD K 1 N/A ,EMMHG. COORDINATOR DATE e 9 9

EPP-019 ATTACllMENT III.4 PAGE 3 0F 5 SECURITY ANNEX RADIATION EMERGENCY KIT REVISION 6 EQUIPMENT CllECK LIST STTS NO. l ITEM EQUIPMENT SURVEIL. MIN. PERF0HMED BY: 31[BLP DESCRIPTION REQMT. QTY. INITIAL COMMENT 3 LIFE (1 Cont) Z) Procedures / Forms A 1 ea II/A

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

1

2) EPP-007 Environmental N/A Monitoring A

1 N/A

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

1 N/A 4.) EPP-020 Emergency Per-sonnel Exposure Con-N/A trol A 1 N/A

5) Out of Plant Survey /

Sample record (EPP-004 N/A Att. I) A 10 N/A

6) Personnel Contamina-tion Report (IIPP-405 Att. I)

A 10 N/A EMEHG. COORDINATOR DATB ~ ~ 9 - 9 9

EPP-0.19 ATTACilMENT III.4 PAGE 4 0F 5 REVISION 6 SECURITY ANNEX Thin nT]uti EMERGETICY KIT HQUIPMEiT CllECK 1,1 ST STTS NO. I ITEM EQUIPMENT SURVEIL. MIN. PHitPOHMEI) BY: SilELP DESCRIPTION REQMT. QTY. IfiITI A L COMMENTS LIFE 2 Off-Site IIolding Area Kit 2

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

a) Decon Kit " Packet" C,8 1 N/A b) Protective Clothing C,T 1 6 mo. " Packet" (gloves) c) First Aid Kit N 1 N/A d) Check Source (Co-137) I 1 N/A e) E-400/E-530 (or equiva-P 1 lent) N/A f) 1 Sets of batteries for C,E 1 6 mo. survey instrument (" packet") g) RM'-14/ IIP-210 probe (or P,R 1 equivalent) N/A h) Irrigation bottles I 2 (500 ml) N/A l EMElt0. C00RDINATGR DATE ~ e e 9

EPP-019 ATTACllMENT III.4 PAGE 5 0F 5 REVISION 6 SECURITY ANNEX RADIATION EMERGENCY KIT EQUIPMENT CllECK LIST STTS NO. l ITEM EQUIPMENT SURVEIL. MIN. PERFORMED BY: 311ELP DESURIPTION REQMT. QTY. INITIAL COMMENTS LIFE h) Procedures /Porms A 1 en N/A 2 (Cont) 1 ) EPP-010 Personnel / N/A Vehicle Decontamination A 1

2) Personnel Contamination Report (IIPP-405 Att. I)

A 20 N/A

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

A 20 N/A 0 0 EMERG. COORDINATOR DATE ~ G G G

EPP-019 ATTACHMENT III.5 PAGE 1 0F 1 REVISION 6 AUXILIARY BUILDING (436 ' ) Tc FUEL NANDLING BUILDING (463') HADIATION EMERGENCY KIT EQUIPMENT CllECK LIST STTS NO. ITEM EQUIPMENT, SURVEIL. MlH. PEHPORMED BY: UllELP DESCRIPTION REQMT. QTY. INITIAL COMMENTS LIFE 1 Aux. & FIIB Kito I* 2

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

1.1 Protective Clothing' C,0 10 " Packets" 6 mo. (Sloves) 1.2 Respirators (Full Face) G 5 N/A 13 Spare filter cartridges D 10 for full face respirators 4 yr. 1.4 5 roll - tape " packet" C 1 1 yr. 9 9 EMERG. COORDINATOR DATE ~ e G G

EPP-019 ATTAClIMENT III.6 PAGE 1 OP 4 REVISlott 6 T.S.C. RADIATIOri EMERGENCY KIT EQUIPMENT CilECK LIST STTS NO: ITEM EQUI PM ErlT SURVEIL. MIri. PEHPORMED BY: SIIELP DESC R I PT IOrl' REQMT. QTY. INITIAL COMMEtiT3 LIFE 1 S.C.B.A. G 8 li/A 2 S.C.B.A. Spare Bottles G 8 li/A 3 Respirators (Pull Pace) G 8 ti/A 4 Spare filter cartridges D 16 4 yr. for full face respirators 5 Radiological and meteoro-Z l II/A logical data computer 6 Whole Body TLD's " packet" K. 25 N/A 7 Extremity TLD IIolders I 15 II/A "pkt" (for ankle or wrist) 8 liigh Range Dosimeter L 25 N/A " packet" (0-5R) 9 Low Range Doometer L 25 13/A " packet" (0-500mr) 10 Dosimeter charger with 2 D,M,E 1 6 mo. "D" cell batteries attached batt. 11 PIC-6A (or Equivalent) P 1 ti/A 12 E-400/E-530 (or P 1 N/A (Equivalent) EMEltG. COORDINATOR DATE

EPP-019 ATTACllMENT III.6 PAGE 2 0F 4 T.S.C. RADIATION EMERGENCY KIT' HEVISION 6 EQUIPMENT CHECK bl3T STT3 NO. l ITEM EQUIPMENT SURVEIL. MIN. PERPORMED BY: SilELP DESCHIPTION REQMT. QTY. INITIAL COMMENTS LIFE 13 Portable P&I Air Samplers F* 2

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

6 mo. high range survey instru-ment, and 1 set of bat-teries for low range survey instrument and 1 set of batteries for the I alarming dosimeters 15 First Aid Kits N 2 N/A 16 Plashlights " Pocket" P 10 N/A 17 Battery " Packet" for 10 C,E 1 6 mo. Plashlights 18 5 rolls of Tape " Packet" C 1 2 yr. 19 Protective Clothing' C,0 25 6 mo. " Packet" (6 0Ves) 1 20 Survey ' packets' U 2 N/A 21 Alarming Dosimeter P 2 N/A 22 Plastic P.C. Set " packet" D 10 2 yr, 23 Particulate air filters I 10 "pkt" N/A 24 ARZ Pilters (Plant) "pkt" D 10 4 yr. EMERG. COORDINATOR DATE ~ g e 9

EPP-019 ATTACHMENT III 6 PAGE 3 OP 4 T.S.C. RADIATION EMERGENCY KIT HEVISION 6 EQUIPMENT CHECK bl3T STTS NO. l ITEM EQUI PM ENT SURVEIL. MIN. PEHPORMED BY: Gl!ELP DESC RIPT I0fi REQMT. QTY. INIT I A L COMMENTS LIPS 25 Personnel Contamination Report (HPP-405 Att. I) A 20 N/A 26 Perimeter Survey Maps I 20 N/A 27 Rad Vork Permit (IIPP-151 Att. I) A 10 N/A 28 (3)RWP Signature Att (H P P-151 Att. III) A 10 N/A 29 self Read. Dos. Card (HPP-152 At t. I) A 50 N/A 30 Auth. To Exceed Exp. Limits (HPP-153 Att.. I) A 10 N/A l 31 Resp. Issue Log (HPP-154 At t. I) A 10 N/A 32 Air. Rad Area Entry Log (HPP-155 Att. I) A 10 N/A 33 Co-137 Check source I 1 N/A 34 Curvey Record (IIPP-302 A t t. I) A 50 N/A EM ERG. COORDINATOR DATE

I EPP-019 ATTACHffENT III.6 PAGE 4 0F 4 T.S.C. RADIATION EMEltGENCY KIT HEVISION 6 EQUIPMENT CliECK I,IST STTS NO. l ITEM EQUIPM ENT SURVEIL. MIN. PElfPORMED BY: 311gLp DESCRIPTION REQMT. QTY. INITIAL COMMENT 3 LIFE 35 RWP Issue / Termination Log (HPP-401 Att. I) A 10 N/A 1 i EMERG. COORDINATOR DATE ~ 9 9 9

EPP-019 ATTACHMENT III.7 s PAGE 1 0F 3 RICHLAND MEMORIAL HO;!PITAL RADIATION REVISION 6 EMEHGENCY KIT EQUIPMENT CHECKLIST l STTS NO. I ITEM EQUIPMENT SURVEIL. MIN. PERFORMED BY: S!!ELP DESCRIPTION REQMT. QTY. INITIAL COMMENTS LIFE 1 E400/E530 (or equivalent) P 1 N/A 2 Pic-6A (or equivalent) P 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 (0-1R) L 2 N/A 6 Ilospital survey Packet A,C,B 1 N/A 7 Disposable Shoe Covers I 25 pr. N/A " packet" 8 Waste Containers (Liquid) with lids I 2 N/A 9 waste containers (Solid) with lids I 2 N/A EMERG. COORDINATOR DATE ~ g e. O

EPP-019 ATTACllMENT III.7 PAGE 2 OP 3 REVIGION 6 RICffLAND MEMORI AL IIO;1PITAL RADI ATION EMERGENCY KIT EQUll' MENT CliECKLIST STTS NO. { ITE!! EQUIPMENT SURVELL. MIN. l'EHFORMED BY: !illMLP DE"CRIPTION~ REQMT. QTY. INITIAL COMMENT 3 LIFE 10 Decon Colution D, I 5 gal' An Labled 11 Movable Shield 1" steel with 4" Lead glass window I 1 N/A 12 Lead Container Approx. 6"x8" I 1 N/A 13 Decontamination Tabletop I 1 N/A 14 Portable Cart I 1 N/A 15 Blotter Paper I 1 roll N/A 16 5 rolls of tape " Packet" C 2 1 year 17 IIerculi te approx. 10'x100' I 1 N/A. 18 Polyethylene I 1 roll N/A 19 Poly Baga approx (38"x63") (yellow, labled) I 10 N/A EMERG. COORDINATOR DATE l 1 1 O O O

EPP-019 ATTACilMENT III.7 PAGE 3 OP 3 REVISION 6 RICllLAND MEMORIAL IIO IPITAL RADIATION EMEHGENCY KIT EQUIPMENT CllECKLIST STTS NO. [ ITEM EQUIPMENT SURVELL. MIN. PEHFOHMED BY: 311EbP DESCRIPTION ' REQMT. QTY. INITIAL C'OMMENTS LIFE 20 Battery ' packet' to contain one complete set of batteries for instruments (Item #1 & 2) C,E 1 6 months 9 0 EMERG. C00RDIllATOR DATE 9 e e O

EPP-019 ATTACflMENT (([.8 PAGE 1 0F 4 REVISION 6 E.O.P. RADIATION EMERGENCY KIT _ EQUI PMErlT CH BCK LiUT l STTS NO. ITEM EQU i PM ENT SUllVEIL. MIN. PEHPORMED BY: UllELP DESCRIPTION ~ REQMT. QTY. INITIAL 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 20' x 50') N/A c) 2 roll tape " packet" C 1 1 yr. d) Tool Kit " packet" C,N 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 Source N/A h) Decontamination Materials I 2 N/A i) AgZ Pilters (Plant) pkt D 10 4 yr. j) AgZ Pilters (Environ-D 5 mental) " packet" 4 yr. k) Calculator P 1 N/A EMEHG. COORDINATOR DATE 9 ~ e 9 9

EPP-019 ATTACHMENT III.8 PAGE 2 OP 4 REVISION 6 E.O.P. RADIATION EMERGENCY KIT EQU L YMEr4T GlibGK LLUT l STTS NO. ITEM EQU I PMEllT UUHVElb. MIN. FEHFUHMED BY: UllEbV I DESCRIPTION-REQMT. QTY. INITIAL COMMENTS LIFE l (1 Cont)l) Watch 1

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

I 1 set N/A n) Map of 10 mi. EPZ/ A 1 N/A Sampling 3tations o) Disposable gloves "pkt" I 5 pr. 6 mo. p) Roll of paper towels I 1 N/A q) Plashlight P 1 N/A . r) Battery " Packet" C, E, Q l 6 mo. c) E-40 /E-530 (or equiva-P 1 N/A lent t) PIC-6A (or equivalent) P 1 N/A u) RM-14/ IIP-210 probe (or P, R l' N/A equivalent) v) 12V Air Sampler (or P 1 N/A equivalent) w/ cables w) Low Range Dosimeter L 2 N/A (0-500 mr) x) I gh ange Dosimeter L 2 N/A y) Whole Body TLD K 2 N/A

1) Control TLD K

1 N/A EMERG. COORDINATOR DATE ~ G G G

EPP-019 ATTACHMENT,III.8 PAGE 3 0F 4 HSVISION 6 E.O.F. RADI ATION EMERGENCY KIT EQULFNMHT Ull bC K L10T STTS NO. IT EM EQULPMENT JUHVElb. MIN. FEHFUHMED BY: BliKLF DESCRIPTION REQMT. QTY. INIT I A L COMMENTS LIFE (1 Cont) Z) Procedures / Forms A 1 ea N/A 1 ) EPP-004 Out of Plant N/A-Radiological Surveying A 1

2) EPP-007 Environmental N/A Monitoring A

1 N/A Att. IV Misc. Emergency 1 Environmental Samples A 10 N/A 3 ) EPP-010 Personnel /Ve-hicle Decontamination A 1 N/A 4 ) EPP-020 Emergency Pe r-N/A sonnel Exposure Con-trol A 1 N/A

5) Out of Plant Survey /

Sample record (EPP-004 N/A Att. I) A 20 N/A

6) (7osogngorgo7,jppiggg, Att. I)

A 10 N/A 7 ) IIPP-301 Operation of Station Portable N/A Survey Instruments A 1 N/A

8) IIPP-302 Hadiation and Contamination Survey Techniques A

1 i N/A EMEHG. COORDINATOR DATE I 4 ~ e e . 9

EPP-019 ATTACHMENT III.8 PAGE 4 OP 4 REVISION 6 E.O.P. RADIATION EMERGENCY KIT EQUll'flENT CilECK LIST ~ STTS NO. l ITEM EQUIPMENT SURVEIL. MIN. PEHPORMED BY: UllELP DESCRIPTION REQMT. QTY. INITIAL COMMENTS LIFE (1 Cont) 9) ESP-301 Air Sampling for Radioactive Particulate and Radioiodine A 1 N/A

10) ESP-801 Emergency Plan Procedure Introduction A

1 N/A 11 ) ESP-802 Emergency Plan Procedure Sampling A 1 N/A

12) ESP-803 Emergency Plan

. Procedure Sample Preparation A 1 N/A

13) ESP-804 Emergency Plan Procedure Sample Counting A

1 N/A EMERG. - COORDINATOR DATE e e 9'

EP P-019 ATTACHMENT III.9 PAGE 1 0F 1 REVISION 6 E.O.P. SURVEY KIT EQUll' MENT CilECK LIST DATE PERPORMED: ITEM EQUIPMENT S ullVE I L. MIN. PEltFORMED BY SilELP DESCRIPTION R EQMT. QTY. SIGNATURE COMMENTS LIFE 1 Dosimeter charger with 2 D-cell batteries attached D,M,E 1 N/A 2 RM-14 with HP-210 probe (or equivalent) P,R 1 N/A 3 E-400 (or equivalent) P 1 N/A H.P. REVIEWER DATE EMERG. COORDINATOR DATE __ ~ ~ O O O

EPP-019 ATTACllMENT III.10 PAGE 1 0F 1 HBVISION 6 E.O.P. DOSIMETHY ISSUANCE KIT EQUIPMMNT CilBCK LIST STTS NO. l ITEM EQUIPMENT GUHVEIL. MIN. PEllFORMED BY: UllELP DESCRIPTI6N REQMT. QTY. INITIAL COMMENTS LIPS 1 Whole Body TLD's K 50 N/A 2 Control TLD K 1 N/A 3 0-500mR Dosimeters L 50 N/A 4 0-1R Dosimeters L 20 N/A e EMERG. COORDINATOR DATE ~ g e O'

s a EPP-019 ATTACIIMENT III.11 PAGE 1 0F 1-REVISION 6 GUARD IIOUSS EMERGENCY DOSIMETRY ISSUANCE KIT EQUIPM8NT CilHCK LIST STTS NO. l ITEM EQUIPMENT SUHVEIL. MIN. PEHP0HMED BY: UllHLP DESCRIPTION REQMT. QTY. INITIAL-COMMENTS LIFE 1 Whole Body TLD's K 15 N/A 2 Control TLD's K 1 N/A 3 0-500mR Dosimeters L 15 N/A 4 EPP-020 Emergency Personnel Exposure Control A 1 copy N/A EMERO. COORDINATOR DATE l l e e O

EPP-019' ATTACilMENT III.12 PAGE 1 0F 1 R EV I3 IC'.16 CHEP ROOM EMERGENCY KIT STTS NO. ITEM EQUIPMENT CURVEIL. MIN. PERPORMED BY: UllELP DESCRIPTION REQMT.- QTY. INITIAL COMMENTS LIP 8 1 E-400/E-530 (or P 2 equivalent) N/A 2 Respirators (full face) G 2 N/A 3 Spare filter cartridges D 4 for respirators 4 yr 4 'l set of batteries for survey instrument C,E 1 6 mo 5 Cs--137 Check Cource I 1 N/A EMERG. COORDINATOR DATR I I ~ e G G

EPP-019 ATTACINENT III.13 PAGE 1 0F 1 REVISION 6 RADIOACTIVE MAT 9tIAIB TRAfGPORTATION ACCIDErIT fla3lUrGM KIT l STTS NO. l 1T84 StRIVEI L. MIN. PERP0lMED BY: UllELP FQIITY1ENT DmCRIPflori HEQr4T. QPY. INITIAIB C0rif4 flits ' # LIPR 1 Yellow Ih1 The;5 I 10 N/A 2 Note Pads with Pens I 2 N/A 3 Radlation Gigns with inserts I 4 N/A 4 Gets of Air Grunple Filters in bags D 4 4 y/A rs. 5 Decon Spray (can) I 1 N 6 Roll /lbx Paner Towels I 1 N/A 7 Protective Ulothing Packets C,0 2 6 mo. 8 Radiation Tape (roll) (gloves) I 1 N/A 9 Sets of blank shipping Inpers I 2 N/A l 10 "Itvlioactive" Placards I 15 N/A 11 Roll "ftelicactive IBA" Tape I 1 li/A 12 Aircraft Inhels I 25 N/A 13 "Ihpty" Inbels I 25 N/A 13 White "I" Inbels I 25 N/A 14 Yellow "II" Inbels I. 25 N/A i 15. Yellow "III" Inbels I 25 N/A 16 Wire Geals I 25 N/A 17 Roll "Possible Internal Contamination" Tape I 1 N/A 18 Roll " Caution Ihlionctive Material" Tape I 1 N/A 19 IIPP-703 "Jiipping Itulioactive Phterials A 1 N/A 20 IIPP-702 " Receipt of Palloactive lhterials A 1 N/A 21 Smears in Thvelopes I 100 N/A M1FIlG. COORDINATOR DATE e e G 9

T SOUTH CAROLINA ELECTRIC & GAS COMPANY post orsica te4 COLuweiA. south CAmouNA 29218 c w. Druom. Ja. we$*.5m'o"uIt[on. April 8, 1985 Dr. J. Nelson Grace, Regional Administrator U. S. Nuclear Regulatory Commission Region II, Suite 2900 101 Marietta Street, N.W. Atlanta, GA 30323

Subject:

Virgil C. Summer Nuclear Station Docket No. 50/395 Operating License No. NPF-12 Emergency Plan Procedure Revisions

Dear Dr. Grace:

In compliance with 10CFR50.54(q), South Carolina Electric and Gas Company, acting for itself and as agent for South Carolina Public Service Authority, submits the following Emergency Plan Procedure IEPP) revisions: EPP-002, Revision 12 EPP-005, Revision 8 EPP-009, Revision 4 EPP-019, Revision 6 Updated Table of Contents This revision of the Emergency Plan Procedures Manual does not decrease the effectiveness of the Virgil C. Summer Nuclear Station Radiation Emergency Plan. If you have any q'uestions, please contact us at your convenience. Ver truly ou Yh O. W.

ixon, j

/tm ) Attachment i I g3 liqi

4 'e Dr. J. Nelson Grace, Regional Administrator U. S. Nuclear Regulatory Commission Region II, Suite 2900 101 Marietta Street, N.W. Atlanta, GA 30323 April 8, 1985 Page 2 cc: V. C. Summer K. E. Nodland T. C. Nichols, Jr./O. W. Dixon, Jr. R. A. Stough E. H. Crews, Jr. G. O. Percival E. C. Roberts C. W. Hehl W. A. Williams, Jr. J. B. Knotts, Jr. D. A. Nauman R. R. Mahan (w/ attach.) Group Managers I. E. Washington O. S. Bradham Document' Control!- C. A. Price ' ' Desk :(w/2 attach 7F D. A. Lavigne K."E.'Beale C. L. Ligon (NSRC) NPCP File I .m ,p n .--n en- - - --g- --n,,- -, -, - -}}

ML20116B119

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Dear Dr. Grace:

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