ML20039B984
| ML20039B984 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 12/01/1981 |
| From: | SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | |
| Shared Package | |
| ML20039B982 | List: |
| References | |
| PROC-811201-01, NUDOCS 8112280190 | |
| Download: ML20039B984 (125) | |
Text
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hUCLEAR O PE RATIONS DEPARTNE\T 9 E V E RG E \ CY 3 _A\ 3ROCEJ RES 1 l VOLUME V OF l l - PLANT OP ER ATING MANUAL i a F PDR l
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_ _ - - _ - . _ - - - . - - - . - - . - - . _ _ . - . _ - - - - . _ . . . - . ~ _ . - - . L L - 12/01/81 VIRGIL C. SUMMER NUCLEAR STATION i {} - NUCLEAR OPERATIONS PROCEDURES l EMERGENCY PLAN PROCEDURES i i l TABLE OF CONTENTS i PROCEDURE DATE :
!TUMBER PROCEDURE TITLE REVISION ISSUED j EPP-001 Activation and Implementation of l Emergency Plan 0 12/1/81 -t EPP-002 Con =unication and Notification 0 12/1/81 l
[ t EPP-003 In-Plant Radiological Surveying 0 12/1/81 EPP-004 Out-of-Plant Radiological Surveying 0 12/1/81 j , EPP-CO5 Offsite Dose Calculations 0 12/1/81 i l EPP-006 Emergency Reactor Coolant Sampling 0 12/1/81 ! l i EPP-007 Environmental Monitoring 0 12/1/81 l \ On-Site Assembly 0 12/1/81 l (])EPP-008 l EPP-009 On-Site Medical 0 12/1/81 l l EPP-010 Personnel / Vehicle Decontamination 0 12/1/81 EPP-011 Personnel Search and Rescue 0 12/1/81 l r i EPP-012 Onsite Personnel Accountability & Evacuation 0 12/1/81 8
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EPP-013 .Pire Emergency 0 12/1/81 , li EPP-014 Toxic Release 0 12/1/81 j t EPP-015 Natural Emergency (Earthquake, To rnad o) 0 12/1/81 l EPP-016 Emergency Pacilities Activation & Evacuation 0 12/1/81 l
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EPP-017 Post-Recovery and Re-Entry 0 12/1/81 ! EPP-018 Emergency Training and Drills 0 12/1/81 EPP-019 Ecergency Equipment Checklist 0 12/1/81 ! i i E=ergency Personnel Exposure Control 0 12/1/81 EPP-020 f k O* Safety Related Procedure I _1_ f I
SOUTH CAROLINA ELECTRIC AND GAS COMPANY VIRGIL C. SUMMER NUCLEAR STATION NUCLEAR OPERATIONS
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I Emergency Plan Procedure EPP-001 ACTIVATION AND IMPLEMENTATION OF EMERGENCY PLAN ! REVISION O MAY 20, 1981 I i NON-SAFETY RELATED i !O Reviewed by: ( [ i n UDateHsi < ORIGI!ATOR (of this revision) ( Ie+t br/Wb/d QUALIFIED REVIE' DER "S
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CANT MANAGER AAY M llJ$0ll
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Date Issued:
- REVIEWED BY PSRC +" Form AP-101-2, (1/80)
A x s.1 CHAIRMAN /__ .. 11 nfet DATE l
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EPP-001
- PAGE i REVISIO:I r 5/20/81 LISE OF EFFECTIVE PAGES h PAGE REVISIO!!
1 0 11 0 1 0
- O 3 0 4 0 5 0 6 0 7 0 8 0 9 0 10 0 n.--,,y,.-,,
. . a u ...u..1 S Attachment I Pages 1 thru 13 0 Attachment II O O
1 l l 9
EPP-001 PAGE if i RE7ISION O 5/20/e1
- b. TABLE OF CONTENTS Pege List of Effective Pages i 1.0 PURPOSE 1-
2.0 REFERENCES
1 30 CCNDITIONS AND PREREQUISITES 1 I. 4.0 PROCEDURES 1 4.1 CLASSIFICATION OF EVENT 1 4.2 IMPLEMENTATION OF EMERGENCY PLAN 1 l 43 UNUSUAL EVENT 1 4.4 ALERT 2 45 SITE EMERGENCY 4 4.6 GENERAL EMERGENCY 6 o V ,AITACRMENTS Attach =ent I Energency Action Level Summaries Attach =ent II I= mediate Actions Su. mary l O i,
EPP-001 PAGE 1 REVISION O 5/P0/S1 1.0 PURPOSE kk To define and implement the Emergency Action Levels (EAL's) that will initiate the Energency Plan and to provide a means of classifying the emergency. , 1 l a
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" Virgil C. Summer Nuclear Station Radiation Emergency Plan." l 2.2 "URE S-0 6 51, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants.
30 CONDITIONS AND PREREOUISITES 31 The Emergency Plan shall be initiate <1 whenever an " Initiating Condition" (as defined in Attachment I) has been reached or exceeded. NOTE: The implementation of any specific emergency plan procedure does not necessarily implement the Emergency Plan, but may do so at the discretion of the Emergency Director /Interi: Emergency Director. Por example; a small chlorine leak would 3 implement the toxic release procedure but not necessitate W implementation of the Emergency Plan; whereas a large release with the potential for affecting the level of safety of the plant would implecent the toxic release procedure and the Emergency Plan due to the declaration of an Unusual Event. 32 The " Initiating Condition" shall be used to determine the applicable Energency Action Level (EAL) per Attachment I. 33 The " Detection Methods" of Attachment I are to be used only as an aid to determine if an " Initiating Condition" has been reached or exceeded. Other detection methods, not listed in Attachment I, may be used to determine if an " Initiating Condition" exists. The existence of one or more of the detection methods could be but is not necessarily an indication that an " Initiating Condition" exists. 4.0 PROCEDURES 1.1 Upon recognition of an abnor=al plant or site condition the observer shall notify the Shift Lupervisor of the potential emergency plan condition. O
l l EPP-001 l PAGE 2' ' REVISION O 5/20/81 : 4.2 The Shift Supervisor shall: A. Evaluate the conditions and determine the applicable Emergency Action Level (EAL) per the Emergency Action Leve.1 l Sur:ary, Attachment I. ! i
- 3. Declare an EAL and implement the Energency Plan per the l applicable section of this procedure. ;
i Unusual Event (Section 4 3) l or Alert (Section 4.4) or Site Energency (Section 4.5) i or General Emergency (Section 4.6) 43 Unusual Event , I 431 I: ediate Actions: (I mediate Action Suntary, See ! Attachment II) The Energency Director (ED) or Interim Emergency Director (IED) shall acco:plish or cause to be accomplished the following: A. Announce the energency condition to all plant personnel over the plant paging sy. stem. AITEliTIO!i ALL PERSONNEL: THE STATI0II IS IN AN UNUSUAL EVE!iT CONDITION. IHE I!ilTI ATI!!G IVENI IS .
?!OTE: [ REPEAT ANiOUN0EMEti?].
E. Iiotify the Security Shift Leader to implement appropriate security measures. C. Ensure that on-shift personnel have responded to : their emergency response stat.ons. l D. Ensure that the Initial Notifications are completed per EPP-002. 1 E. Ensure that the Emergency Le< i .; established and maintained. i , > . . ==-.. . _ . -
EPP-001 PAGE 3 RE7ISION O 5/20/81 F. Request Offsite Z ergency Services (Fire, Medical, LLEA, etc.) if required per EPP-002. NOTE: Consideration should be given to access routes taken. 432 Follow-Up Actions: The ED/IED shall continually assess the status of the Unusual Event per Attachment I for possible escalation to a higher energency classification or termination of energency condition. 433 Final Actions:
- hen the energency condition has cleared, close out the Unusual Event with a verbal surcary to offsite authorities within 24 hours and close out of the 2:ergency Log.
4.4 Alert 4.4.1 I ediate Actions (ED/IED): (I:=ediate Action Succary, Attachment II) The E=ergency Director (ED) or Interi: Z:ergency Director (IED) shall accostlish or cause to be acco lished the ' ' following: (g) A. Announce the energency condition to all plant personnel over the plant paging syster. a ,. sa,..1, , U h. nau rse c0 h... Jsa- : s- t a.--
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ALL EMERGENCY RESPONSE PERSONNEL REPORT TO THEIR l l STATIONS. l l l l l E. If necessary, sound the Radiation Emergency Alarm. NOTE: [ Repeat the Alar: and Announce=ent] . C. Notify the Security Shift Leader to i=ple=ent appropriate security =easures. D. Ensure that on-shift personnel have responded to their energency response stations. ll)
PP-001 FAGE A REVISION O 5/20/81 O s/ E. Ensure that the Initial Notificatione e.;e completed per EPP-002. F. Ensure that the E:ergency Log is es tablished and maintained. , G. Request Offsite Energency Services (Fire, Medical, LLIA, etc.) if required _per EPP-002. NOTE: Consideration should be given to access routes taken. H. Ensure that TSC/OSC are being activated'per EPP-016 and/or notification of Emergency Response Personnel is initiated per EPP-002. I. Deter = ire if the site evacuation is required. (Including Fairfield Pump Storage Facility). 4.4.2 Immediate Actions (All other personnel): A. Emergency Response Personnel report to their designated stations. 3 Non-essential personnel continue assigned duties and (} await further instructions. If the radiation energency alars is initiated, all C. Personnel in the Radiation Control. Area report to the Radiation Access Control Area on the 412' level of the Control Building. 4.4 3 Follow-up Actions The ED/IED shall: A. Notify the Offsite Energency Coordinator of the energency-and current plant conditions.
- 3. Verify that the TSC/OSC are canned and activated per EPP-016.
C. Ensure that updated follow-up notifications are enie per EPP-002. D. Continue wsesstents and corrective actions to nitigate the e=ergency condition and place the plant into a safe and controlled condition. E. Make assignments to his staff to citigate the emergency conditions per established Emergency Plan Procedures (EPP's) or as require 1 for conditions not O- covered by procedures.
EPP-001 PAGE 5 REVISION 0 5/20/81 F. Continually assess the status of the Alert condition per Attachment I for possible escalation to a higher emergency classification, down-grading to an Unusual Event, or close out of emergency condition. 4.4.4 Final Actions: A. When emergency conditions clear to allow for close out or down-grading of the Alert condition, the ED shall ensure that offsite authorities are:
- 1. Notified verbally by norcal emergency communications.
- 2. Provided with a written sucmary within 8 hours of the close out of the emergency or down-grade of the emergency classification.
l B. Initic e EPP-017, Post-Recovery and Re-Entry as required. 45 Site Emergency 451 Ic=ediate Actions (ED/ LED): (I :ediate Action Summary, see Attachment II) l The Emergency Director (ED) or Interim Emergency Director ggg , (IED) shall acco plish or cause to be accomplished the ( following: 1 j A. Announce the emergency condition and site evacuation ) to all plant personnel over the plant paging system. . ATTENTION ALL PERSONNEL: 1 1 THE STATION IS IN A SITE EMERGENCY CONDITION. THE INITIATING EVENT IS . ALL EMERGENCY RESPONSE PERSONNEL REPORT TO THEIR STATIONS. ALL NON-ESSENTIAL PERSONNEL EVACUATE THE SITE PROCEED TO .
- 3. Sound the Radiation Emergency Alarm.
NOTE: [ Repeat the alarm and announcement) O
. EPP-001 FAGE 6 REVISION O 5/20/e1 O_ C. Notify the Security Shift Leader to imple nent appropriate security ceasures.
D. Notify the Fairfield Pump Storage Facility of site evacuation. E. Ensure that on-shift personnel have respondei to their energency response stations. F. Ensure that the Initial Notifications are completed per EPP-002. , G. Ensure that the Emergency Log is establi s h ed and caintained. H. Request Offsite Energency Services (Fire, Medical, LLEA, etc.) if required per EPP-002. NOTE: Consideration should be given to access routes taken. I. Notify the Offsite Emergency Coordinator of the emergency and current plant conditions. J. Ensure that TSC/OSC/20? are being activated per EPP-016 and/or notification of Emergency Response Personnel is initiated per EPP-002. 452 I:nediate Actions ( All other personnel): A. E=ergency Response Personnel report to their designated stations.
- 3. Non-essential personnel evacuate the site, proceed to their private residence or offsite holding area as designated by the ED, and await irrther instructions.
C. Personnel in the Radiation Control Area report to the Radiation Access Control Area on the 412' level of the Control Building, unless otherwise directed. J.5 3 Follow-:p Actions The ED/IED shall: A. Verify that the TSC/OSC/ EOF are canned and activated
- per EPP-016.
- 3. Ensure that updated follow-up notifications are made per EPP-002.
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EPF 001 PAcc REVISION O 5/20/81 c C. Continue asseestents and corrective actions ta citigate the e=ergency condition and place the plant into a safe and controlled condition. D. Make assignments to his staff to citigate the emergency conditions per established Emergency Plan Procedures (EPP's) or as required for conditions not ecvtred by procedures. E. Continually assess the status of the Site Emergency condition per Attachment I far possible escalation to a higher e=ergency classificc* ion, down-grading to an Unusual Event, or Alert, or close out of emergency condition. F. Verify site evacuation is co=plete 9nd all personnel are accounted for. (Including Fairfield Pump Storage Personnel). 454 Final Actions: A. When. emergency conditions clear to allow for close out or down-grading of the Site E=ergency condition, the ED shall ensure that offsite authorities are:
- 1. Hotified verbally by normal emergency communications.
lll and 2. Provided with a written suecary within S hours of the close out of the ecergency or down-grade of the e=ergency classification. B. Initiate EPP-017, Post-Recovery and Re-Entry as required. 4.6 General Emergency 4.6.1 Immediate Actions (ED/IED): (Inmediate Action Summary, see Attachment II) The Emergency Director (ED) or Interim E=ergency Director (IED) shall accomplish or cause to be accomplished the following: A. Announce the emergency condition and site evacuation to all plant personnel over the plant paging system. O
EPP-001 PAGE 8 REVISION O 5/20/81 O 'V ATTENTION ALL PERSOUNEL: THE STATION IS IN A GENERAL EMERGENCY CONDITION. THE INITIATING EVENT IS . ALL EMERGENCY RESPONSE PERSONNEL REPORT TO THEIR STATIONS. ALL NON-ESSENTIAL PERSONNEL EVACUATE THE SITE. PROCEED TO .
- 3. Sound the Radiation Emergency Alar =.
NOTE: [ Repeat the Alar an'd Announce=ent] . C. Notify the Security Shift Leader to i=ple=ent appropriate security =easures. D. Notify the Fairfield Pu=p Storage Facility of Site Evacuation. E. Ensure that on-shift personnel have responded to their emergency response stations. []} F. Notify local authorities of the VCS reco=sendations regarding activation of the Early Warning Syste= (EWS). G. Upon direction by local authorities, request the Shift Supervisor to activate the Early Warning System. H. Ensure that the Initial Notifications are completed per EPP-002. I. Ensure that the E=ergency Log is established and maintained. J. Request offsite E=ergency Services (Fire, Medical, LLEA, etc.) if required per EPP-002. NOTE: Consideration should be given to access routes taken. K. Notify the Offsite Emergency Coordinator of the e=ergency and current plant conditions. L. Ensure that TSC/OSC/ EOF are being activated per EPP-016 and/or notification of Emergency Response Personnel is initiated per EPP-002.
EPP-001 PAGE 9 RE7ISIO:! O 5/20/81 4.6.2 I ediate Actions ( All other personnel): lll A. Emergency Response Personnel report to their designated stations.
- 3. Non-essantial personnel evacuate the site, proceed to their private residence or offsite holding area as designated by the ED, await further instructions.
C. Personnel in the Radiation Control Area report to the Radiation Access Control Area on th e 412 ' level of the ! Control Building, unless othcrwise directed. l 4.6 3 Follow-up Actions The ED/IED shall: A. Verify that the TSC/OSC/ EOF are canned and activated per EPP-016.
- 3. Ensure that updated follow-up notifications are made per EPP-002.
C. Continue assessments and corrective ac tions to citigate the energency condition and place the plant into a safe and controlled conlition. k D. ':ake assignments to his staff to mitigate the energency con 11tions per established Energency Plan Procedures (EPP's) or as required for conditions not covered by procedures. E. Continually assess the status of the General Energency condition per Attachment I for possible down-grading to an Unusual Event, Alert, or Site Energency, or close out of energency condition. F. 7erify site evacuation is complete and all personnel are accounted for. (Including Fairfieli Pump Storage Personnel). 4.6.4 Final Actions: A. When energency conditions clear to allow for close out or down-grading of the General Energency condition, tha ED shall ensure that offsite authorities are: O
l 1 EPP-001 PAGE 10 REVISIOI O l 5/20/81 I h .
- 1. Ilotified verbally by normal emergency con =unications.
- 2. Provided with a written summary within 8 hours of the close out of the e=ergency or down-grade of the emergency classificatic h
- 3. Initiate EPP-017, Post-Recovery and Re-Entry as -
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EMERGEPCY ACTION LEVELS StM4A1 (ATTAC m ENT I PAGE 2 OF 13) SYSTEM SITE dNERAL INVOLVED UNUSUAL EVENT ALERT EMERGENCY EMERGENCY STEAM INITIATING CONDITION INITIATING CONDITION INITI ATING COHolTION SYSTEM RAPID SECONDARY SYSTEM MAJOR STEAM LINE DREAK (e.g. , MAJOR STEAM Lite OREAK W ITH DEFRESSWlZATION. G1 EATER THAN 6 IN. EQUl VALENT mEATER THAN 50GFN DIAMETER) WITH A SIGNIFICANT FHIMARY-TO-SECONDARY LEAKAGE AND Detection Method: FHIMARY-TO-SECONDARY LEAK RATE. INDICATION OF FUEL IW4 AGE. Increased steam flow; and Detection Method: Detection Method: Reduced RCS temperature and pressure; and Rapidly decreasing reactor Rapidly decreasing reactor ObservatioUf break or steam dunp, , Fesstr i zer Coolant T,yg, relief or safety valve coolant pressure,Ta,kd pressrizer level; presswizer gresstre and inadvertentl y opened, and RM-L3, f44-L7, F#4-L10 high presstr i zer level M rms; and
- 1) Steam line differential 1) Steam line difforential pressure safety injection presstre, safety injection signal; and High Reactor signal; and Building ~"li~esstre alarm; High ReaMr Dullding and HM-A2 high alarm for Iresstre alarm and RM-A2 higt Tupture in Reactor Dullding alarm ar.d
-OR- Fal1edTuul Monitor A1 arm for
- 2) High steam flow and to-lo rupture in Reactor Building Toy or low steam or pre $stre safety injection 2) IITgh steam flow and Lo-Lo signal for rupture downstrea,, Tavg or low steam gresstro of MSlV's. safety injection signal and 144-A9 high alarm and
-- - - - - - Falled Fuel MonttF INITIATING CONDITION high alarm RAPID WO55 FAILWE OF OPE STEAM GENERATOR TUBE WITH LOSS OF OFFSITE IW ER.
Detection Method: Pressurizer low pressire alarm and reactor trip; and Presstrizer low le W alarm; and - HM-A9 high alarm and FYesstrizer low pTrstre safety injection signal; and Undervoltage alarmTon IDA and 100 buses; and F44-L3, f44-LWL10 high alarms
EMERGEPCY ACTION LE VELS St#4MRY ( AT TAC 6 f4ENT I, PAGE 3 U 13) S) STEM SITE GENERAL INVOLVED UNUSUAL EVENT ALERT E ME RGEtCY EMLRGEfCY HA04 0 LOGIC AL INITIATING CONDITION SUSTAINED HlOt RADIATION LEVELS O< INITI ATING CONDITION INITI ATit4G C0t(stTION EFFLt[NIS GA5EOUS EFFLtLNT INSTANTANEOUS HIOl AIRBO{NE CONTAMINATION WHICH RADI AT10tT~ Mot 4l Tats RTECT LEVELS FFLLA NT MONITORS FCTECT LEVELS RELEASE RATE ILCHNICAL INDICATES A SEVERE IGRAfATION IN COlRESPONDING TO UtEATER TtAN 50 CutRESH)NDING TO l-RD4/til wHOLE BODY SitCIFICATION LIMITS EXCEEDED Fat 1 THE CONTROL OF RADIOACT IVE MREN/ tit WHOLE HODY F(F 0. 5 Hl. 04 04 5-RD4/6f t THYR 0lO AT THE HR. ( APPENDIX D TABLE . i t, COLlf4N MATERIALS (e.g., IPCREASE Of GtEATER THAN 500 MRD4/ tit WHotE EXCLt610N AREA HOl#4LARf t#4ff R ACTUAL 10CFR20) FACTut 0F 1000 IN DIRECT RADI AT lot BODY Fut 2 M IN. (OH FIVE TIMES Mr TEut0 LOGICAL CONDIT IONS. READINGS). THLSE LEVELS TO THE THYH0lD) AT Detection Mothod: THf EXCLUSION AREA DOUN[ARY FOt Detection Mothod: Outection Method: ADVERSE METLut0 LOGY (PASQUILL F An y o f it's foi low i ng ga seous S TAB I L I T Y, IM/SLC WIND VEL (CITY). 1) Radiation Monitor levels owce+*1 Ml uont mnitors in valid ciarm 1) Unexpocted ING readings as those s pec i f i ed for Si te Emorgency; mode for more than I hr .
- follows: Detection Method: and a) FNG 2-4, 8-13, 16: greater Mal c ut at ion on rose Assessmen t RM-A3 RM-A9 than 2.5 R/hr Any of the following valid Forms indicates levels escewfing RM-A4 RM-AIO b) RMG 7, 17A, 17B, 18 greater a tmosphoric radiation mnitor I-r mi/ hr who l e tu1 y or 5-r em/ tr IN-A13 than 100 R/hr readings: thyrold at the escl usion area c) ING-1 : greater than 1 R/hr 1) FN-A 3, IN-A4, FN-A9, IN-A 10, boundary using rs11ation monitor (duo to radioactiv i ty releases to RM-A13 readings and anal ysis shown readings and of fi tunt strea n fl ow the environment) 2) Unex pec ted plant area lodine or eq ui va l en t 1-131 release rate r ates (meastrol or assm1) for particulate airborne concontratior greater than 1.14 Cl/hr for 0.5 actual muteorological coniltions; greater than 1000 MFC. hr or greater than 11.4 Cl/tr for or meastred in-situ.
(as par 10CFR20 Appendix B, Tab le 2 min utes. 1)
- 2) FN-A3, IN-A 4, FN-A9, %-A 10, RM-A13 readings anc anal ysis showa eq ui va l en t Xo-133 release rate greater than 489 C1/hr for 0. 5 hr or greater than 4690 Cl/hr for 2 minutes (CONTINUE CN NEXT PACE)
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-_ _ - . - .. _ -- - - ~ - - - .. - . _ - _ . ~ . ~. - . , _ _
EMERCEtCY ACTION LEVELS SlNWw (ATTACINENT I PAGE 4 0F 13) SYSItM SIIt. GENERA L INVOLVED UNUSUAL EVENT ALERT EMERGEPCY EMERGEtCY , RADIOLOGICAL INITIATING CONDITION INITIATING CONDITION INill AL CONDITION I EFFLLENTS LIQUID EFFLUENT CotCENTRATIONS RADIOLOGICAL EFFLIENT RELEASE RATE DO5E RATES LISTED DELOW ARE ( CON' T) TECHNICAL SPECIFICATIONS LIMITS EXCEEDING 10 TlHES TECHNICAL FHOJECTED HASED ON GAMMA RADIATION l EXCEEDFD FOR 15 MIN. (APPENDlX B SPECIFICATION INSTANTANEOUS MONITOR (RPG) READINGS AND/OR TABLE 11 COLINN 2 10CFR20). L IM ITS. OTHER PLANT PARAMETERS 01 ARE Detection Method: MEASlHED AT THE EM:LUSION AREA l An y of t he following valid liquid Detection Method BOUNDARY. a ef fluent monitor readings for longer than '15 min. which are Any of the following valid Detection Method: j
~
greater than: radiation monitor readings for longer than 15 minutes 1) Reactor Bullding look rate RM-LS: high alarm setpoint results in calculated dose RM-L9: established in a) 10 times alarm setpoint for rate at exclusion area ! l discharge permit; and boundary greater than 50 . IN-A3 RM-A9 RM-A13 isolation valve falls to nrem/hr whole body for 0.5 hr; , j close; TN-A4 RM-A10 or I 1 cr , De mrom/br whole body for 2 l' IR-L3: while steam generator b) RM-L5 10 times alarm min. RM-L7: blowdown is FN-L9 setpoints established i RM-LIO: directed to the nuclear in discharge permit and 2) Radiation Monitoring Teams [ blowdown system isolation valve . falls meastret. dose rates greater ; i and Isolation valves fall to close or
~
than 50 mrom/hr for 0.5 hr or i to close (due to greater than 500 mrem /hr for 2 radioactivity releases to IN-L3 10 times alarm min. (beta + gamma) at the the environment). IN-L7 setpoints while steam exclusion area bomdary; or ' generator blowdown is directed to the nuclear 3) Radiation M>nitoring Teams
! blowdown system and maastre thyrold dose rates 4
isolation valves fall (equivalent 1-131 , to close (due to concentrations) greater than; radioactivity releases t to the environment). a) 250 mrem /hr (1.3x104 Cl/cc for 0.5 hr; or t:) 2500 eren/hr (1.3x @ Cl/cc) for 2 min at the excl usion area bomdary. t
fMERGEPCY ACT ION LE VELS Stf1 MARY ( AT!?DtiLNT I PRGE 5 C7 13) 5YSTEM SilL MNERAL INVOLVED UNUSUAL EVENT ALERT EMERGEtCY (MERGElCY F UE L ~IITITI ATING COhDITION INITI ATING CONDITICN INITTATTTETHEf1TTOh 7TITTAT1TETTRJIT1T;T4 (W4 AGE FLEL [MMAGE IN6TCATTON. POSSIDLE FUEL IAMAff. DECHADED COINITiTTOSSIBLE LOSS LOS5 & InO & TH<EE flSSION OF COOLABLE 4(NEIRY. FNODtC T BARR IER W I TH (UTE N T I A L Detection Mothod: Detection Mothod: LOSS & THE DilRD BARRIER ( e.g. , 00so equivalenTi-131 activi ty Detection Mothod: LOSS & FULL INTEGilTY AND concentration gruater than llmlt lo 1) Pr imar y cool an t sam pl e FRlHARY COOLANT BOUNTARf AND HlGi f i g ur o 3. 4-1 o f Tec hn ica l indicatos eqiilvalent 1-131 Val id readirigs on incore POTENTI AL FOR RADIOACT IVI TY Spoc i f ica t ion s; concentrat'on greater than thermocouples above 700*F, and RELE ASE FROM CON 19 0 tNLHT) or 300 Cl/cc; T hat and Tcold Foss failed f tu i detector alarm; or rapidly divering ( T rapidly Detection Method: and Laboratory anal ysis which 2) Foss fa il ed fml detoctor increasing) or no T across core; indicates an increaso in failed alarm and laboratory anal ysi s and f alled FEl Monlior of f scale 1) LO:A as identl flet Ir Site f ml of 0.1 parcent in 30 minutes. which indicates on increase W eater t ha n 106c yn) Emergency; and Containment in falled fml of I por cun t ir status pinoNndicates 30 min or a total f a i l ed f tail Inctsn pl e te isolation: of 5 p,rcent. ----------------- INITIATING CONDITION -or-MXJOR E6MAGL 10 MJ4E THAN ONE
----------------- SPENT FUEL ASSEMBLY IN REACTUt 2) L(CA as identi find in Site INITIATING CONDITION BillLDiv dt FUEL FANDLING BUILDir# Emergency; and FUE L HANDL ING ACC l[t NT W I T H LEAnit6 TO CLAD RUPTG1E (e.g., IN-A2 high Wrm; and RELEASE & RADIOACTivlTY TO LARGE (IL;ECT (AMAGES FUEL (r! WATU FNG-7 and/or Fo4G-18 read ing 4
REACTO4 04 ftEL FANDLING BulLDito. LOSS BELOW FUEL LEVEL). gr ea tor than 10 R/hr ; and Roactor Building gressirT Detection Method: Detection Method: gr ea t er than 30 psig for at least 2 min. Observation of damage to stent Obsorvations of major damago to ftel assembly; and more than one spont f iss t assemb l y 3) br eac h o f con t a i nmon t or intejr I ty (Heactor Dul lding)
- 1) RM-A2 high alarm and/or Tp~en t f im,1 p>ol wa ter bel ow fml and Indicated cladding rupttre; ING- 17A , 17B high alarm after level and accident in Reactor Dullding; -or-s 1) RM-A2 and/or RMG-17A, 178 higt
- 2) RM-A6 high clarm; or~ a l >+. m fo r accident in Reactor 4) Dose rate outside Fml ING-8 high alarm; Building P3ndilng Building Indicates af ter a:cident i n F ts,1 2) RM-A6 an>f/or RMG-8 high alarm 100% cap release trom s p>n t Ibndling Building, for accident in Fuel Hand l i ng tml; bui l d ing
-and or-S) Mor e than ga p ec t i v i t y r e t o s s.v3 O O O
i l j p) ( p LNERGEFCY ACTION LEVELS SUNA1_,/ 1 ATTICtNENT I F%E 6 0F 13) ,/ l SYSTLM SITE R NERAL INVOLVED UNUSUAL EUC.NT ALERT EMERGOCY EMERGEtCY STATlON INITIATING CONDITION INITI ATING Cot 4DIT 1ON INITIATltG CONDITlON INITlATlto cot 201IION POWER TOTAL LOSS & nFSITE 10WER OR LOSS LOSS & OtFSITE FOWER AND LOSS 0 LOSS & OFFSITE lOWLR AND LOSS 0 FAILutE G MFSITE AND Ot61TE OF ONSITE A-C FOWER CAPABILITY ALL Ot61TE A-C IOWER Fut A IERIOl ONSITE A-C 10WER F01 MoliE ftMN l' FOWER ALONG WITH TOTAL LOSS OF OtEATER TIMN 5 MINUTES M I N. ENERCEtCY FEEDWATER MAKEUP CAPABILITY F01 SEVERAL H00tS. Detection Method: Detection Mothod: Dorection Methods COULD LIAD TO EVENTUAL C0'E MELT At4D f0SS10LE FAllt!!E OF THE Undervoltage alarms on IDA and 1D0 lbdervoltage alarms on llM and 1) thdervoltage alarms on IDA ItEACT01 BUILOltG. buses; ESF power supply A aWor D 100 buses, ESF IVR Supply A 100 buses; and Fall w e Alarm. and/or B Fallwe Alarms 2) ESF ibwbr Shly A/B fall me Detection Method: alarm thdervoltage alarms on IDA and 100
----------------- buses for greater than 2 hors and INITIATING CONolTION ----------------- Steam driven Emergency foedwateI LOSS OF ALL Ot6 tTE LW FOWER F04 INITIATING CONDITION ptanp f all s to start.
A FERIOD OtEATER TIMN 5 MINtfTES. LOSS OF ALL VITAL Ot6lTE 0-C FOWER F04 Mute TIMN 15 M IN. Datoction Method: Detection Mottx>d: D-C bus tndervoltage alarms (all D-C bus mdervoltage alarms on buses); and ESF Fbwer Suppl y A/D all buses; ESF PWR Supply A fallme alarm. and/or B Falltre Alarm INITIATING CONDITION LOSS & FUtCT 10t6 tEEDED F01 PLANT HDT SHUTDOWN. Detection Method: Inability to establish charging pump Injections; and Inability to establish mergency feodwater flow; or lnebility to establish serv ice % ter flow; and inability to establish component cooling water f l ow.
LNERGEPCY ACTION tEULLS SlHMARY ( AI TACIN E NT I PAGE 7 OF 13)
~SWTEM SITE GiNfRAt I NSOLVL D Ut4 USUAL LVENT AllRT tMERGEtCY FMf RGt PCY DmhEERED ' TrilTFATUCTRETIN4 (NTTIATTWi C01GTIDf4 N TATING condition INITIATitICCGiDITl0N SAFEGUARDS ECC5 TFTITTATED (cUTil:lliLNT WilH ~ALL ANtDCIATUT ATATNS tosi. ATE ATEntfAT(TCAT@ PLANT TRKrNMITTATTijY toss or POSliivE FINDING THAT INITIATION lt C(Nf'UT E R L OS T HH MtH E THA N 15 F EEINATER AND CONI 4 t6 ATE SYSilNS NOT SPlHIOUS), lb t oc t ion Mo t tot : MINUILS At4D PLANT TRANSIENT (FHitC IPAL HC AT RtA0 VAL SYS TEM)
INITIA1LI) 04 IN IHOGRESS. FOLLOWED OY f AltlHE & LNFlKX tC Y lbtuction Ksthod: Observation tsy opsrator. F EflMATER SYSif M F0lt EXTENI(D Dntoction Mothod: PtRIOD. CtHL ML LTlHG IOSSIBLE IN Satoty inja.ction Signal vortfled tn SEVI RAL HomS. ULT IMATE F Al t.tHE r od todan t indication. ==-- -- Observation of evont. (( Hl ACilN bulLDING FOSSIBLE If INITIATING CONDITION Cute MtlTS. TVACUATioN of coffm0L Rom ----------------- ANi tCIPATED m RE QUIRED WlIH INITIATING CONulTION (b t oc t i on Mot tot : INITIATING CONDITION CONTROL (f SHUTlA)wN SYSitM TVAETSTION OF C0t4THOL rom AND TATfINTT A f 0ESStillZER P $1E Atl LSIAULISiiED FRtN L(CAL STATIONS. CONTROL (f SHUTOUWN SYS TEMS t#)T R. sac tor tr i p on low foutwater GLNLRATut SAFETY (H RELitt VALVL It ESTABLISHED FIMH LtCAL STAT IOt6 flow; and Rt' SLAT (EXCLEDING N HMAL WELPAGL). IN IS M IN. IbcreasI79 wido-rango steam (Ptuction Mothod: genorator level s toward of f-scaf e Ibtuctlon Mothod: low on ali steam generators; a,ed-(Mtoctlon Mothod: Pr esstr iier or stuam gonorator I) Emorgonc y foof water flow sa f u t y or rul l u t va l vo opon s and Indicators indicate tor o f l ow then f a l l s to r oso t as i nd ica t ed Samo as I n i t i a t i ng avon t . 2 min et ter requiral; g by: Samo as initiating condition. 2) Status lamps indicato
- 1) Pr osstriior rol lof valvo omor gone y f ood w s tor p m ps not position light Indicatos opon; r un n ing 2 m in . a f t er r oq ui r ai ;
or Emorqoncy fen 1w stor cannot teo TFosstr iier s.s f ot y vai vo res tore.1 wi t hin 30 min. po s i t ion Ind ica tor re+ad s gr ea t er than I porcont oe' valid aqous t ica l n >n i tor ind lUt lon .
- 2) Vismi and/or audibio Indication at vont stacks of open sto.u gonorator sa fet y or rol lof val vo; or t xcess foodwafE tiow to and stoom flow f run o f f ac ted gunorator.
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I ( AT TACINENT I PA M 8 OF 13) v v IMER&tCY ACTION LDELS StNMA.s silt a rIETTAL
'~~5Y5TDi EMERGEtCY ALERT EMERGEtCY INYOLVED UNUSUAL EVENT INITIATING CONDITION INIII ATING CONDITION E NGINEERED INITIATING CONDITION REActu< COOLANT ~TUW LOCKED ROTO, WATGIENT HEQUITTTFCUTRATION &
SM EQUARD) LOS5 Ut EFCINLtuto SAFETY FEATURE WITH FUEL lAMAM. StalTICWN SYS TEMS WlIll FAltfRE TO (CON'T) Ft#CTION REQUIRING TECHNICAL TRIP WHICH RESULTS IN Cute iW4A& SITC IF ICAl lON SiluT OOWN. ( T ECliN 1-Detection Mothods m ADDITIONAL FAlt fRE O~ CORE CAL SPEC IF ICAT lONS 3.3.2) Reactor coolant punp auto tr Ip ; C00LitG AND MAKEUP SYSTD4S WHICH alarm; and COULD LE AD TO CGtE MELT. Dutoction Method:
- 1) Enginuored Safety features Reactor TrTp on low Activation System fomd i no p- coolant flow; and Detection Method:
erable Reactor coolant %p phase cver l
----------------- current relay actmtion; ~and Roactor revnains cri tical after i INL-l Al arm. a t t em pt ed trip and INillATING CONDITION
'TW5Ttm.5 cf HADI ATION MONITut-ING IMCESS AND EFFLUENT PARA-
- 1) INL-1 alarm. or -
METtRS WHICH REQUIRE PLANT SHUT- ----------------- l
- 2) Flow Indicators on safety i DOWN Ot INITIATING CONDITION TU55 cf .=LL rimCTioNs M[ tvd Fat injection systum and RlH syst .ns !
LOSS TT VITAL ASSES 94ENT ot sho w tero flow wi t h sa f e t y COMMUNICATION LQUllMENT StCH PLANT COLD SHUILXMN. THAT THE ",AFF OPERATION & THE Injection Initiated, -or PLANT l$ t
- CTED. Detectlon Method
- 3) W tus lights show safety RlH system not imctional and injection system and Rift punps Detection Mothod 1) LDss of not rmning with safety Radiation Monitoring System 2) _ Inability to sustain nattral or Injection initiatod.
loss of meteorological equi p- w.1 forced circulation.
- 3) Significant loss of commmica-tion capability of f si te INiilATING CONDITION FAILutE & TK REACTut HtuiECTiot SYSILM TO INIT I ATE AND C04PLETE /
TRIP WHICH IHINGS THE REACTut StHCRITICAL. Detection Mothod: Reactor romains critical after trip initiation. g
LNERGEPCY ACTION LEUELS SU44ARY ( ATTACtf4ENT I PAGE 9 0F 13) SYSTEM SITE GEtERAL INVOLVED UNUSUAL EVENT ALERT EMERGENCY EMERGEtCY f IRE INITIATING CONOlilON INITI ATING CONDlilON INiilAllNG CONDITIOtt F IRE LASTING MiltE THAN 15 M INS. FIRE FUTENTIALLY AffLCTING FIRE AFFECTING REDUNIMNT SAFETY SAFETY SYS1 EMS. TRAINS 04 FLtCTiottS. Detection Method:
~
Ditection Method: Dutection Method: Observation or fire detection devico alarm 7 th conf irming Observation of fire that could Observation of major fire that obser va t ion indicating a fire affect sa fety systems. defeats raimdant safety system lasting nore than 15 min. tralns { f mctions. O O O
_ _ _ __ ..m ._ _. _ . _ . - . . _ _ m - _ _ - .- - - _ .m_._ . .__. . - _ - . _ i O O 4 l EMERGEtCY ACTION LEVELS SLNMARv (ATTACI A ENT I PAGE 10 0F 13) l . i SYSTEM SITE CENERAL j INYOLVED UNUSUAL EVENT ALERT EMERGENCY EMERGEtCY I SECtHITY INITIATING CONDITION INITIATING CONDITION INITIATING CONDITION INITIATING CONDITION i ! SECtHITY TlftEAT 01 ATTEMPTED ENTR1 ONGOING SEVERE SECtHITY Tif1 EAT SECtHITY T6ftEAT INVOLVING SEClftlTY TiftEAT RESULTitG IN LOSS l OR ATTEMPTED SABOTAGE. lHMINENT LOSS & lHYSICAL CONTROL OF lHYSICAL CONTROL OF THE Detection Method: OF THE PLANT. FACILITY. Detectica Method: Security safeguards contingency j event which results in Detection Metnod: Dutoction Method ! l} Report to the Control Room by adversarles commandeering an j observer. erea of the plant, but not l'hysical attack on the Plant Physical attack on the Plant has
. control of shutdown capability. Involvi g imminent occupancy of resulted in occupstion of the l 2) Alarm of integrated Fire and control room and auxillary control room and the auxiliary i Sec tr i ty Panel . shutdown panels. shutdown pnnels by mauthorized personnel.
6 e
EMERGEtCY ACI DON lEt'ELS SutNARY (4TTRCit4ENT I PAGE 11 OF 13) ~~~5TS RM 5IIL U NERAL INVOLVE D UNUSUAL EVENT ALERT EMERGEtCY EMERGEtCY NATutAL INITIATING CONDITION INITIATING CONDITION INI TI ATit4G CONDITl0t1 iMENUMENON NATulAL EVENTS SEVERE tATutAL EVENT REAR SITE. SEVERE tATutAL RfEtmENON BElio EXPERIEtCED 04 HtOJE('TED WITil
- a. EARTHQUAKE PLANT TOT IN COLD St!.'Tif MN.
- b. TutNADO ON S8TE a. EARTHQUAKE OtEATER TilAN THE
- c. ItutRICANE TEAR SITE (00E) LEVEL a. EARTHQUAKE GtEATER TFAN SSE
- b. T0tNADO $1RIKitO FACILITY LE VE LS.
- c. tutRICANE WINDS OtEATER TIAN b. WINDS IN EXCESS OF 100 MHi Of Detection Nthod: 75 MHt SITE.
Detection Method:
- a. Seismic % cording System
- Detection Nthod:
Start Indication, a) Seismic Response Spoctria
- b. Observation of event. Trouble Anntsiciator Reactor Building Foundation
- c. Obsorvation of event. b) Observation of event Seismic Swi tch (SSE) c) Nteorological Moni toring System lhta or Woather 8trau Meteorological Monitoring Systen Re por t . Data.
9 O O O
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ENERGEtCY ACTION LEVELS StfMA. (ATTAC6NENT I PAGE 12 0F 13) SYSTEM L IE GENERAL INVOLVED UNUSUAL EVENT ALERT EMERGENCY EMERGEtCY INITI ATING C0tIDITION Mare 4ADE INITIATING CONDITION INITlATING CONDITION PHENLNENON OTHER FMZARDS BEING EFERIEtCED OTHER IMZARDS DElNG EXPERIEtCED 0< OTHER IMZARDS BEING EXPERIEtCED 04 FROJECTED WITH PLANT NOT IN PROJECTED WHICH IMVE IHE FUTENTIAt 01 FROJECTED WHICH IMVE A COLD SHUTDOWN: Fat EN(MNGERING TtE FACILITY SlDilFICANT FUTENTIAL Fat AFFECTING PLANT SAFETY. a. AIRCRAFT CRASH INTO VITAL
- a. ONSITE AIRCRAFT CRASH. a. AIRCRAFT CRASH ON FACILITY. STRUCTlJtES.
- b. ONSITE TRAIN KRAILMENT. b. MISSILE IMPACTS ON FACILITY b. MISSILE 01 EWLOSION IMPACT
- c. ONSITE EXPLOSION (E)CLUDING WITH RESULTANT MAJul [MMAM. ON FACILITY RENDERING SEVERE PLANNED ACTIVITIES). c. KNOWN EXPLOSION AT FACILITY [MMAGE TO SHlfTDOWN EQUIPMENT
- d. NEAR 01 ONSITE T0XIC 01 RESULTING IN MAJOR IMMAGE To c. ENTRY OF T0xlC 01 FLAMMABLE 1 FLAMMABLE CAS RELEASE OF A PLANT STRUCTutES Ut CASES INTO VITAL AREAS WHICH MAGNITUDE TIMT TiflEATENS EQulH4ENT. INVOLVE A SIGNIFICANT PERSONNEL. d. ENTRY INTO FACILITY ENVIRONS K01AIAT10N OF PLANT '
- e. TLRalNE CENERATOR ROTATING OF ToxlC 01 FLAMMA8LE CASES SAFETY.
COMPONENT FAILLRE CAUSING IN C0tCENTRATION WHICH EXCEEl RAPID PLANT SHUTDOWN. THE LIMITS & FLAMMABILITY 0< Detection Method: T0XICITY. Detection Methods e. TLRBINE CENERATG1 FAILutE a) Aircraft <. rash m using CAUSING CASING KNETRATION. damage or fire in:
- a. 4 servation of event. 1) Reactor Building; or
- b. Observation c' event. Detection Method: 2) Control Room; or
~
- c. Cbservatlo of explosion or 3) Auxillary Bull 3Tng; or warning from of f site, a) Observation of aircraf t crest- 1) Fuel Handling BuildiW;or'
- d. Observation of release or into Plant str uctures. 5) Turbbe Building; or-wacning from of f si te, b) Observation of missile 6) Intake Structres
- e. Turt Ine tr ip and observation impacts on Plant structures b) Loss of itnctions needed for of turbine mal f unction s or components, hot shutdown. (see page 6 of fa ll we. c) Observation of damaje by this Attachment) ex plosion.
d) Observ stion or warning from c) Entry of toric or flammable i outside the Plant; detection gases into- . of gases (using portable 1) Control room; or instrunentation) which exist 2) Cable spreadinfrooms; or' in concentrations which 3) Rnac+~~ Bullding; or ~ exceed the limits of 4) Switchgear rom: or-f l ammab i l i t y or tox ic i t y. 5) Safe shutdown peneI's; or el Twbine trip and observation 6) Emergency diesel of penetration of casing, generator rooms; as detected by portable In-strunentation and which ren-ders a train oT a safety-related system inoperable.
k* LMERGEPCY ACTION LEt'ELS SU4MArtY ( AT TAC 6 f4ENT I PAGE 13 Of 13) SYSTEM SITE GE NERAL l UNUSUAL tvENT ALERT E MERGEPCY EMERGEPCY INVOLVED O THER INITIATING CONDITION INITI AllNG CONDITION INITIATING CONDITION i LOSS Of CONTAlrNENT INTEGRITY OTHER PLANT CONDITIONS EXIST THA1 OTHER PLANT CONDITIONS ExlST THA1 WARRANT ACT avATION & IECHNICAL WARRANT ACTIVATION OF D4ERGEtCY REQUIRING TLCHNICAL SPLCif lCATION SHUTDOWN (TLCHNICAL SPEClf lCATION SUPPORT CENTER AND D4ERGEPCY F ACILITIES AND RADI ATION 3.6.1.I) OPERATlONS fAC1LITY. MONITutIto TEAMS AND A DRECAIJTIONARY PUDLIC WARNIPC. Detection Method: Detection Method: !
- 1) Any automatic containment Detection Method:
( Isolation valve found to be As determined by Gnorgency ' Inoperable or Dir ector . As determined by Emergency
- 2) Reactor building air lock Di r ector .
inoperable or
- 3) Penetration (s) fait leak test l l (as, speci fied in Technical 1 Specifications) l l NIT I AT ING CONDl?lON TRANSPORTATION Of OVEREXPOSED AND/04 CONTAMINATED, INJURED INDivlDUAL FRO 4 SITE TO HOSPITAL.
Detection Mettni: Same as initiating condition. INITIATit6 CONDITION ODER FtANT CONDITIOr4S EXIST REQUIRING OTHER THAN NO< MAL PLANT SWDOWN AND REQUIRING ltCHEASED AWARENESS ON THE PART Of STATE OfflCIALS. Detection Muthod: As determined by Emergency Director. O O O
n ~,. n . () (d EPP-00,_.) ATTACHMENT II ~ PAGE 1 of 1 REVISION O IMMEDIATE ACTION
SUMMARY
UNUSUAL l ALERT SITE GENERAL IMMEDIATE ACTIONS EVENT
- 1. ANNOUNCEMENT TO PLANT PERSONNEL
- 2. SOUND RADIATION ALARM 3 NOTIPY SECURITY SilIP LEADER '
4 NOTIFY PAIRPIELD PUMP STORAGE PACILITY _ 5 ENSURE ON-SHIFT PERSONNEL RESPONSE
- 6. F' W I IG T RECOMMEND 7 ACTIVATE EWS IP REQUIRED
- 8. INITIAL NOTIFICATIONS PER EPP-002 9 EMERGENCY LOG ESTABLISHED
- 10. OPP SITE EMERGENCY SERVICES, IP REQUIRED ACTIVATE TSO/OSC OR NOTIFY EMERGENCY
- 11. RESPONSE PERSONNEL
- 12. NOTIPY OPP-SITE EMERGENCY COORDINATOR ENSURE TSC/OSC ARE ACTIVITED OR EMERGEllCY 13 RESPONSE PERSONNEL NOTIFIED ENSURE E0P IS ACTIVATED OR EMERGENCY 14 RESPONSE PERSONNEL NOTIFIED - _
DETERMINE IP SITE EVACUATION IS REQUIllED
- 15. (INCLUDING PAIRPIELD PUMP STORAGE PACILITY) _
) .l .
4 i i SOUTH CAROLINA ELECTRIC AND GAS COMPANY O ^ VIRGIL C. SUMMER NUCLEAR STATIO!! NUCLEAR OPERATIONS NJCE:A7 0?aAr0Xs COPY No. . . . . . . g7.p EMERGENCY PLAN PROCEDURE EPP-002 , COMMUNICATION AND NOTIFICATION REVISION 0 MAY 20, 1981 i NON-SAFETY RELATED
- O sevie ea dr:
CXS . - ORIG ur TOR (of this revision) Il zffS Date'
,N lf-24~-8/
QUALIFIED REVIEWER Date - l Appeoved: 1v - //}_2tt/ i PLANT MANAGER ~Date'
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Date Issued: -- m iDC iL.k[J4 L. G S f 'UI.) Ui CT/I n]{#F" Form AP-101-2, (1/80) l l 3 k ~ j' CHAIRMAN Ik3*l@l DATE l0
EPP-002 ' y PAGE i BEVISION 0 5/20/81 LIST OF EFFECTIVE PAGES (g) PAGES REVISION i 0 11 0 iii 0 1 0 2 0 0 3 ATTACHMENTS Attachment IA. Pages 1 -3 0 Attachment IE, Pages 1 -3 0 Attachment IC, Pages 1 -3 0 Attachment ID, Pages 1 4 0 lll Attachment IIA, Pages 1 4 0 Attachment IIB, Pages 1 -3 0 Attachment III, Pages 1 -3 0 Attachment IVA, Pages 1 - 5 0 l Attachment IVE, Pages 1 -6 0 Attachment IVC, Pages 1 -5 0 l 1 ! Attachment V , Pages 1 &2 0 Attachment VI, Pages 1 &2 0 A ttachment VII, Pages 1 -3 0 i 1 O l l l
i EPP-002 PAGE 11 REVISION 0 5/20/81 ( TABLE OF CONTENTS PAGE List Of Effective Pages i 1.0 PURPOSE 1
2.0 REFERENCES
1 1 30 DEFINITIONS 1 4.0 PREREQUISITES 2 5.0 PROCEDURE 2 5.1 Initial Notifications , 2 5.2 Notifications for Change of Emergency Classification 2 5.3 Off-site Emergency Services 3 5.4 Follow-up Notifications 3 ( 5.5 Vital Personnel notification 3 ATTACHMENTS ' Attachment IA - Initial Notifications - Unusual Event Attachment IB - Initial Notifications - Alert . Attachment IC - Initial Notifications - Site Emergency l Attachment ID - Initial Notifications - General Emergency 1 Attachment IIA - NRC One-Hour Notifications l 1 Attachment IIB - ANI Eight-Hour Notification Attachment III - Off-site Emergency Services Attachment IVA - Follow-up Notifications - Alert Attachment IVB - Follow-up Notifications - Site Emergency Attachment IVC - Follow-up Notifications - General Emergency Attachment V - VCS Plant Data and Status i! - I l l l l
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EPP-002 ' PAGE iii- . . REVISION 0 5/20/81 TABLE OF CONTENTS (Continued) ([ Attachment VI - TSC/OSC Emergency Telephone List Attachment VII- Off-site Emergency Telephone List w, e a S 9 e '- w wy -m-- r*w- -+ + - - -e---+-, - -- - s-ye.-+-or- y-e------%,+ y eww =.e- e-y ,e , w -.-ye.= s g --e-- %.sw-+. , , - , ,g g y --aww. -er* c- m - e
EPP-002 PAGE 1 REVISION 0 5/20/81 (' 1.0 PURPOSE - 1.1 The purpose of this procedure is to delineate the specific notification requirements for each class of emergency and to provide a method for affecting these notifications.
2.0 REFERENCES
2.1 " Virgil C. Summer Nuclear Station Radiological Emergency Plan" 2.2 NUREG-0654, " Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants" 2.3 EPP-001, "Activiation and Implementation of the Emergency Plan" 2.4 Voluntary Assistance Agreement (by and among Electric Utilities involved in Nuclear Generation) - Article 9 - Transportation of Nuclear Materials; and Emergency Resources Manual (ERM) - [RP/EP-1] 1980. "INF0" Institute of Nuclear Power Operations. 3.0 DEFINITIONS AND ABERE7IATIONS , (~
'- 31 Definitions 3.1.1 Initial Notification - The transfer of informa, tion 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.
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) 1s to be notified within eight (8) hours of declaration l ~ of an Alert, Site 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 information is required at 15 minute intervals following completion of initial or previous follow-up notifications. EXCEPTIONS: Following initial notification of the NRC, an open communication line will be established and l maintained to provide continuous updating to the NRC.
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.?P-002 . .
PAGE 2 REVISION O 5/20/81 (~ 3.2 Abbreviations 3.2.1 TSC - Technical aspport Center
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3 '. 2 . 2 OSC - operations Support Center 3.2.3 EOF - Emergency Operations Facility . 3.2.4 ED - Emergency Director 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. 5.0 PROCEDURE 5.1 Initial Notifications (reference paragraph 3.1.1) 3 5.1.1 Upon declaration of the appropriate emergency classification, the ED/IED will direct the communicator to implement the appropriate notifications. (- i 5.1.2 The ED/IED will assure that the required information is available to effect prompt notification. 5.1.3 The communicator will, upon direction from the ED/IED, l implement the initial notifications per the applicable section of Attachment I and Attachments IIA and IIB. I NOTE: Attachments I, II and III list.alternatet for various personnel. These notifications attempts are tc be made i in numerical sequence as indicated and will be considered ! complete upon successful notification of one of the i listed. j 5.2 Notifications for Change in Emergency Classification l NOTE: If classification change is made in the middle of a no,tifications sequence the communicator will terminate that notification sequence, and initiate the new notification for current status. l 5.2.1 Upon escalation to a higher emergency classification, the l communicator will, upon direction from the ED, implement notifications per the section of Attachment I which corresponds to the higher emergency classification, and Attachments IIA and IIB. ! 5.2.2 When the emergency classification is downgraded, the
- communicator will, upon direction from the ED, implement i
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EPP-002 PAGE 3 REVISION O 5/20/81
,r - ,
- notifications per the section of Attach =ent IV which corresponds to the classification which is being changed. -
5.3 Off-site EmerEency Services 5.3.1 Upon direction from the ED/IED, the communicator will implement the requested notification (s) per Attach =ent i III. 4
" 3.2
. Upon direction fro the ED/IED, the communicator will contact other utilities for assistance using the "INP0" Resource Guides Reference 2.4 (NOTE: The alluded to Resource guides are available for communication use in the Control Roo=/TSC/OSC and EOF.)
5.4 Follow-up Notifications (reference paragraph 3.1.2) 5.4.1 Follow-up notifications are required for all e=ergency classifications except Unusual Event. 5.U.2 The coc=unicator will implement follow-up notifications per the section of Attachment IV which corresponds to the applicable emergency classification. 5.4.3 Follow-up notifications will be made by the site co==unicator(s) until the EOF is activated and assumes all off-site notification responsibilities. Thereafter, the site co==unicator will transmit updated information to the EOF as it becomes available, via Attachment V. L 5.4.4 Follow-up notifications to the Emergency Preparedness Division and the counties shall be made by the TSC or EOF . Co==unicator until such time that the S. C. State forward EOC is staffed and co==unications are established. NOTE: All transfers of notification responsibilities shall be documented. 5.5 Vital Personnel Notification 5.5.1 The communicator will notify vital personnel as directed . by the ED/IED per (The Vital Personnel Telephone Listing.) 5.6 TSC/OSC/ EOF Cc=munications 5.6.1 TSC-OSC - telephone list are provided in Attachment VI. 5.6.2 EOF - telephone list are provided in Attachment VII.- 9-y , s--,.-.yy9--.,_., ,4-. y ,,,_w.-3y, , c., ., .f,_,, _ p,____,,,,__,...,_.p., , . _ _ . - - , - . , , . , , _ _ ,
EPP-002 ATTACHMENT IA PAGE 1 0F 3 1 REVISION O ( ' INITIAL NOTIFICATION - UNUSUAL EVENT (1) This . (Name) (Title) (2a) This is a drill. (2b) This is not a drill. (3) I am notifying you of an accident at the V. .C. Summer Nuclear Station which occurred at: , (Dat e) - ' (Time) (4) The class of Emergency is an Unusual Event. (Time cui Classification) , (5) Description of Event: (6) Radiation Release Yes No: If yes compete 7 through 14. (7) Type of Actual Release or Type of Projected Release: , 1 (8) Estimation of Duration of Public Impact.
- (9) Release Rate: (9A). Noble Gas (93).
(90) Release Height l _ (10) Meteorological Conditions: (10A) Wind Speed (=ph) Site (11A) Dose Rate--Whole Body (MR/HR) l l (113) Integrated Whole Body Dose ( hour projection) (MR) (llc) Dose Rate--Thyroid (MR/HR) (11D) Integrated Infant Thyroid ( hour projection) (MR) i. l
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EPP-002 ATTACHMENT IA PAGE 2 0F 3 REVISION O INITIAL NOTIFICATION (con't) - UNUSUAL EVENT (12) Sectors Affected (13) Does involve the release of some radioactive material from the station at a level at which the following Protective Action is advisable: Yes No. (If yes, select one of the below options) (13A) People living in zones arcund the station remain inside with doors and windows closed. These zones are in a direction from the station out to a radius of about miles. (133) People in zones EVACUATE tneir homes and businesses. These zonec are in a direction from the station out to a radius of about miles. We urge people in these areas to leave their home or 'ousiness in a safe, orderly fashion. (14) Off-Site Emergency Actions Recommended
I EPP-002 . ATTACE4EIT IA PAGE 3 0F 3 REVISION O INITIAL NT IFICATION ( UNUSUAL EVHTT
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EASY . PERSON AGETCY/PERSO E NORMAL ACCESS SITE NOTIFIED TIME
- 1. Management Duty Supervisors
], (per Duty Roster)
- 1) Ollie Bradhan
?) John Connelly .
+
4
- 3) Lou Stor: -
- 4) Bob Croley 3 5.)SteveSmith-6)' Vince Albert
- 2. +S.C. Dert. of Health &
- Environiental Centrol, Eureau of Radiological Health ,
- 3. *NRC See Attach =ent IIA of EPF-002 for NRC Initial Notification Re ,
- 4. Media Coord. (Sapv. Nuclear Info.)
Ecce Office
- 1) Becky McSwain -
i 2) ist Alt. - Buddy Clark -
- 3) 2nd Alt. - Beth Williams
- 5. Site Services Manager-3cb Stough
- 6. Institute of Nuclear Power Operations (INPO) 1
- 7. American Nuclear Insurers (ANI) See Attachment 113 of EPP-002 for ANI
; Notification i
NOTIFICATICUS COMPIME: CAIME'S SIGNA 1UltE DATE
+ Dedicated Line Also Exists. -(
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EPP-002 ATTACHMENT IB PAGE 1 OF 3 REVISION O ( INITIAL NOTIFICATION _ ALERT (1) This (Name) (Title) (2a) This is a drill. (2b) This is not a drill. (3) I am notifying you of an accident at the V. C. Su=mer Nuclear Staion which occurred at: (Date) (Time) (4) The class of Emergency is an Alert . Classification Upgraded From AT Tim e (5) Description of Event: (6) Radiation Release Yes No: If yes complete 7 though 14 , (7) Type of Actual Release or Type of Projected Release: (8) Estimation of Duration of Public Impact: (9) Release Rate: (9A) Noble Gas (9B) (9C) Release Height (10) Meteorological Conditions: (10A) Wind Speed (mph) (10B) Wind Direction (blowing to) (10C) Stability Class (10D) Precipitation (11) Projected Dose At: Site Boundary 2 Miles 5 Miles 10 Miles (11 A) Dose Rate--Whole Body (MR/HR) (11B) Integrated Whole Body Dose ( hour. projection (MR) (11C) Dose Pate--Thyroid (MR/HR) (11D) Integrated Infant Thyroid ( hour projecticn) (MR)
EPP-002 ATTACHMENT IB - PAGE 2 0F 3 REVISION O , C INITIAL NOTIFICATION (con't) .. ALERT (12) Sectors Affected (13) Does involve the release of some radioactive material from the station at a level at which the following Protective Action is advisable: Yes No . (If yes, select one of the below Options) (13A) People living in zones around the sta' ion remain inside with doors and windows closed. These zones are in a direction from the station out to a radius of about Elles. (13B) People in zones EVACUATE their homes and businesses. These zones are in a direction from the station out to a rndius of about miles. We urge people' in these areas to leave their home or business in a safe, orderly fashion. (14) Off-Site Emergency Actions Recommended u O
EPP-002 ATTACHMENT IB PAGE 3 0F 3 ! REVISION O
'f INITIAL NOTIFICATION AtERT j
EASY PERSON AGENCY / PERSONNEL NORMAL ACCESS SITE NOTIFIED TIME
- 1. Management Duty Supervisors (per Duty Poster) -
4
- 1) Ollie Bradham -
, i T' Jchn Connelly ?'
- 3) Lou Stor: ,
- 4) Bob Croley .
- 5) Steve Smith .
- 6) Vince Albert
^ '
- 2. 'S.C. Dept. of Health & .
Envirennental Control, Bureau of Radiological Health
'C 3. "NRC See Attach ent IIA of EPP-002 for NRC Initial Notification Requirements
! 4. Media Coord. (Supv. Nuclear Info.) Ecce Office
~ ~ ! 1) Becky McSwain
) 2) 1st Alt. - Buddy Clark
- 3) 2nd Alt. - Beth Williams
- 5. Site Services Manager-Bob Stough
- 6. Institute of Nuclear Power Operations (INPO) r -
i
- 7. Fairfield Pu= ped Storage Facility
- 8. American Nuclear Insurers (ANI) See Attachment IIB of EPP-002 for ANI Notification NOTIFICATIONS COMPLETE:
CALLEPS SIGNATURE DATE
- Dedicated Line Also Exists.
EPP-002 ATTACHMENT IC - PAGE 1 0F 3 REVISION O INITIAL NOTIFICAT~0N , SITE EMERGEN;Y (1) This (Name) (Title) (2a) This is a drill. - (2b) This is not a drill. (3) I am notifying you of an accident at the V. C. Summer Nuclear Station which occurred at: (Date) (Time) (4) The class of Emergency.is a Site Emergency Classification Upgraded From at Time (5) Description of Event: (6) Radiation Release Yes No: If yes, complete 7 through 14. (7) Type of Actual Release or Type of Projected Release: , ( 5 (8) Estimation of Duration of Public Impact: (9) Release Rate: (9A) Noble Gas (9B) (9C) Release Height
- (10) Meteorological Conditions: (10A) Wind Speed (mph)
'(10B) Wind Direction (olowing to)
(100) Stability Class (10D) Precipitation (11) Projected Dose-At: Site ~' Boundary 2 Miles 5 Miles 10 Miles (llA) Dose Rate--Whole Body (MR/HR) (11B) Integrated Whole Body Dose ( hour projection) (MR) (11C ) Dose Rate--Thyroid (MR/HR) (llD) Integrated Infant Thyroid ( hour projection)(MR) (
EPP-002 ATTACHMENT IC PAGE 2 0F 3 REVISION O ( INITIAL NOTIFICATION (con't) . SITE EMERGENCY
/
(12) Sectors Affected (13 ) Does involve the release of some radioactive material from the station at a level at which the following Protective Action is advisable: Yes No (If yes, select one of the below options.) (13A) People living in zones around the station remain inside with doors and windows closed. These zones are in a direction from the station out to a radius of about miles. .
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(133) People in zones EVACUATE their homes and businesses. These zones are in a direction from the station out to a radius of about miles. We urge people in these areas to leave their home or business in a safe orderly fashion. (14) Off-Site Emergency A.ctions Recommended s 9
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i EPP-002
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ATTACHMENT IC- - PAGE 3 0F 3 REVISION O INITIAL NOTIFICATION
" SITE EMERGENCY"
( - NAME.0F EASY PERSON AGENCY / PERSONNEL NORMAL ACCESS SITE NOTIFIED TIME
- 1. Manage =ent Duty Supervisors (per Duty Roster) '
- 1) Ollie Bradham - -
"P
- 2) John Connelly .
3) Lou Storz -
- 4) Bob Croley 5)
Steve Smith -
- 6) Vince Albert __
'S.C. Dept. of Health &
2.' - N ". Environmental Control, .
'N?ureau 'of Radiological
- Health -
- t- .
- 3. *NRC See Attachment IIA of EPP-002 for NRC '
.s s , Initial Notification Requirements , +,, % *
"\- '4 '
- 4. Media Coord.'(Supv. Nuclear Info.) -
Home Office b'ecky McSwain
- 1) -_
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i . . , 1 l
- 2) 1st Alt. - Buddy Clark -
- 3) ' 2nd Alt. - Beth Williams
- 5.
- Site Services Manager -
! Bob Stough - - l
- 6. Institute of Nuclear Power Operations (INPO) __c- -
- 7. Fairfield Pumped Storage Facility -
?
i 8. American Nuclear Insurers See. Attachment IIB of EPP-002 for ANI
- Notification.
NOTIFICATIONS COMPLETE: Caller's Signature Date
#Dediba'ted Line Also Exists. (
e, .- ,,w e,, e - y- -
EPP'-002 ATTACHMENT ID PAGE 1 OF 4 REVISION 0 INITIAL NOTIFICATION _ GENERAL EMERGENCY 4 (1) This (Name) (Title) (2a) This is a drill. - (2b) This is not a drill. (3) I am notifying you of an accident at the V. C. Summer Nuclear Station which occurred at: (Date) (Time) (4) The class of Emergency is a General Emergency , Classification Upgraded From at Time (5) Description of Event: (6) Radiation Release Yes _ No: If yes, complete 7 through 14. (7) Type of Actual Release or Type of Projected Release: ( ) (8) Estimation of Duration of Public Impact: (9) Release Rate: (9A) Noble Gas (9B) (9C) Release Height
- (10) Meteorological Conditions: (10A) Wind Speed (mph)
. (10B) Wind Direction (blowing to)
(100) Stability Class (10D) Precipitation (11) Projected Dose At: Site Boundary 2 Miles 5 Miles 10 Miles (llA) Dose Rate--Whole Body (MR/HR)
- (llB) Integrated.Whole Body Dose j ( hour projection) (MR) i i (llc) Dose Rate--Thyroid (MR/HR)
! (llD) Integrated Infant Thyroid ( hour projection)(MR) e I
EPP-002 ATTACHMENT ID
- PAGE 2 OF 4 REVISION 0 INITIAL NOTIFICATION (con't) -
GENERAL EMERGENCY (12) Sectors Affected
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(13) Does involve the release of some radioactive material from the station at a level at which the following Protective Action is advisable: Yes , No (If yes, select one of the below options.) (13A) People living in zones around the station remain inside with
. doors and windows closed. These zones are'in'a direction from the station out to a radius of about miles.
(13B) People in zones EVACUATE their homes and businesses. These zones are in a direction from the station out to a radius of about miles. We urge people in these areas to leave their home or business in a safe orderly fashion. (14) Off-Site Emergency Actions Recommended b 5
EPP-002 ATTACHMENT ID PAGE 3 0F 4 REVISION 0 INITIAL NOTIFICATION { '
- " GENERAL EMERGENCY" NAME OF
- EASY PERSON AGENCY / PERSONNEL NORMAL ACCESS SITE NOTIFIED TIME
- 1. Management Duty' Supervisors -
(per Duty Roster) --
- 1) Ollie Bradham ' _ ..
- 2) _V _~
~
J)hn Connelly ._
- 3) Lou. Storz -
- 4) Bob Croley ;w -
m
"' # ' O 5)
Steve Smith
- 6) Vince Albert -
- 2. 'S.C. Dept. of Health & ~
Environmental Control, -- : Bureau of Radiological ; h -Health .
- 3. 'NRC. See Attachment IIA of EPP-002 for NRC
- Initial Notification Requirements 4 Media Coord. (Supv. Nuclear In fo. ) Home Office
- 1) Becky McSwain -
- 2) 1st Alt. - Buddy Clark '. -
- 3) 2nd Alt. - Beth Williams _
- 5. Site Services Manager -
Bob Stough T' ._
- 6. Fairfield Pumped Storage '
C Facility
- 7.
- Emergency Preparedness Division- ~~
Adjutant General's Of fice (State EOC) eDedicated Line Also Exists. ( - 1
EPP-002 . . ATTACHMENT ID' PAGE 4 0F 4 REVISION O INITIAL NOTIFICATION
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{
" GENE'RAL EMERGENCY" NAME OF EASY PERSON AGENCY / PERSONNEL NORMAL ACCESS SITE NOTIFIED TIME
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- 8. 'Fairfield County ,
9..*Newberry County 'i- ' . i '
- 10. 'Richland County .
.: 3
- 11. 'Lexington County ,
- 12. Institute of Nuclear Power Ooerations (INPO) ,
13 American Nuclear Insurers See' Attachment IIB of EPP-002 for ANI Notification.
! i NOTIFICATIONS COMPLETE:
Caller's Signature Dte 1 .i
# Dedicated Line Also Exists.
-~ . - . , _ _ _ _ - .,-.__.m.__ _ _ . . . - . . . , ,- ., ,-__ _ ,___.__- , - , - - _ .-.
EPP-002 ATTACHMENT IIA
, PAGE 1 OF 4 REVISION O NRC ONE HOUR
(.- NOTIFICATION , The NRC shall be notified within 1 hour of Declaration of an
)
Emergency in accordance with Pages 2 through 4 of this attachment. -
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EASY PERSON NORMAL ACCESS CONTACTED
- 1. NRC - Bethesda, Md. Dedicated Phone N/A i
a) Alternate: NRC - Atlanta, Ga. _ i ___ ..< b) Commercial telephone system to NRC Operations Center (Via Bethesda Central Office).
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NOTE: . c) Commercial Telephone System to NRC Operations Center (Via ' Silver Spring Central Office).
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I NOTE: - O d) Health Physics Network to NRC Operations Center. NOTE: 22 (Touch-Tone) - 22 (Rotary Dial) . e) Commercial Telephone System to NRC Operator (Via Bethesda Central Office).
- 2. NRC - Resident Inspector Yes No s -' (N.O. Ext)
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Jack Skolds - . Home Phone NO.
~- :
or w l l CALLERS SIGNATURE DATE TIME i f l l ' l
EPP-002 ATTACHMENT IIA PAGE 2 0F 4 REVISION O CHECKLIST FOR NOTIFICATION OF SIGNIFICANT EVENTS MADE IN ACCORDANCE WITH 10 CFR 50.72 (" A. Identification: Date Time Name of Person Making Report Licensee Facility Affected - Applicable Part of 10 CFR 50.72 B.
Description:
Date of Event Time Description of What. Happened- - C. Consequences of Event: (Complete depending on t'ype of event) Injuries Fatalities Contamination (personnel) (property) Overexposures (known/possible) Safety Hazard (describe - actual / potential) _ U Offsite Radiation Levels Intergrated Dose Location Meteorology (wind cpeed) From (direction) Weather Conditions (rain, clear, overcast, temperature) - Equipment / Property Damage D. Cause of Event - E. Licensee Actions: Taken Planned
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EPP-006 ATTACHMENT IIA PAGE 3 0F 4 REVISION O Emergency Plan Activated (Yes/No) Classification of Emergency {' _ Resident Inspector Notified (Yes/No) Sthte Netified (Yes/No) Press Release Planned (Yes/No) - News Media Interest (Yes/No) Local / National - 1 F. Current Status: (Complete depending on type of event)
- 1. Reactor Systems Status Power Level Before Event After Event Pressure Temp.(t hot) (tcold)
RCS Flow (Yes/No) Pumps On (Yes/On) Heat Sink: Condenser Steam Atm. Dump Other Sample Taken (Yes/No) Activity Level ECCS Operating (Yes/No) ECCS Operable (Yes/No) ESF Actuation (Yes/No) (~ PZR or RX Level Possible Fuel Containment Water Level Indication Equipment Failures Normal Offsite Power Available (Yes/No) Major Busses / Loads Lost
~ Safeguards Busses Power Source D/G Ru'ning n (Yes/No) Loaded (Yes/No)
( '
EPP-Ca6 , ATTACHMENT IIA PRGE 4 0F 4 REVISION 0 Radioactivity Release U, ' Liquid / Gas Location / Source Release Rate Duration
. Stopped (Yes/No) Release Monitored (Yes/No)
Amount of Release Tech Spec. Limits - Radiation Levels in Plant Areas Evacuated
- 3. Security /Safegua~es 1 Bomb Threat: Search Conducted (Yes/No) Search Results Site Evacuated (Yes/No) ,
Intrusion: Insider Outsider _ Point of Intrusion Extent of Intrusion Apparent Purpose Strike / Demonstrations: Size of Group l Purpose ( Sabotage: Radiological (Yes/No) Arson (Yes/No) Equipment / Property Extortion: Source (phone, letter, et Control of Facility Compromised or Threatened (Yes/No) Stolen / Missing Material Agencies Notified (FBI, State Police, Local Police, etc.) Media Interest (Present, anticipated) 1 See 10 CFR 73.71(c), effective April 6, 1981.
EPP-002 ATTACHMENT IIB PAGE 1 0F 3 REVISION O ANI EIGHT HOUR NOTIFICATION _ ANI is to be notified within eight (8) hours of the declaration of an Alert, Site Emergency, or General E=gergency in accordance with pages 2 - and 3 of this attachment. American Nuclear Insurers (ANI) Phone No. - Easy Access Person Contacted Time Date Callers Signature \_,
EPP-002 ATTACHMENT II3 FAGE 2 0F 3 REVISION O ANI NOTIFICATION f (1) This is e) (Titl ) (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) ,. (6c) Release Height
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(- (6d) Meteorological Conditions: (6a) Wind Speed (=ph) (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) (103) (10C) (10D)
(6g) Integrate Whole Body Dose ( hour projection) (11A) (113) (11C) (11 D) (6h) Dose Rate--Thyroid (12A) (123) (12C) (12D) (61) Integrated Infant Thyroid ( hour' projection) (13A) (133) (13C) (13D) (6j? Sectors Affected (14A) (143) (140) (14D)
EPP-002 ATTACHMENT IIB
.PAGE 3 0F 3 REVISION O
(' ANI NOTIFICATION _ (7) Injured Personnel Yes No. (if yes, complete 7a through 7d) (7a) Number of injured personnel _ (7b) Is Is Not Radioactively Contaminated (7c) Injury
Description:
(7d) Requires Transportation to off-site Medical Facility Yes No. (8) Off-Site Emergency Assistance / Actions Requested Yes No. (If yes, complete 8a through 8c) Yes/No . Reason (8a) Law Enforcement (8b) Fire Departments (/ (Sc) Hospital Facilities (9) Public evacuation required Yes No Not at this time (9a) If "Yes" or "Not at t'his time", affected sectors ligem i i iii Im
EPP-002 ATfACHMB.'T 'III-PAGE 1 0F 3 REVISION 0 OFF-SIE DERGSiCY SEVICES . NAIE OF PERSON AGENCY / PERSONNEL PHONE NOTIFIID TIME .A. Corgany Physicians (Pinner Clinic)
- 1) Carrol A. Pinner III M.D. - Prinej .-
- 2) Carrol A. Pinner Jr. M.D. - 1st Alternate
- 3) Harriet A. Pinner,. M.D. - 2nd Alternate - ~
B. Hospital Facilities
~~
- 1) Richland Memorial Hospital -
Give the fcllowing inforration: , This is the Virgil C. Su=ner Nuclear Station. This is a Drill Tnis is not a Drill We have contaminated /non-contaminated injured person beirs transported to your facility. {
- 2) Radiation Emergency Assistance Center Training Site (Reacts) _: :- :-
C. Ambulance Service la) Erergency Medical Services ~ of Fairfield County _ lb) Alert MAST for standby transportation. -
. r
- 2) U.S. Arg
' ~ '
MAST Operat' ions d NOE: Aler Security of Emergency Vehicle arrival es soon as request (s) for Off-Site Emergency Services are cor:pleted. 9
EPP-002 ATIACHIGT2 III PAGE 2 0F 3 EEVISION O OFF-SI'IE DEENCY SERVICES (
' NAME OF PERSON AGDICY/PEESONNEI, PHONE !DKmt.u TDE
! Give the followire information for items la and 2 above.
'Ihis is a Drill 'Ihis is not a Drill We have contaminated /non-contaminated injured person (s) requirirs transportaticn to Richland Memorial Hospital. ('Ihe ecbulance cust enter the site via the main gate, using (dencte route to be taken) or the helicopter should land at the primary landing pad (denote route to be taken)
D. NSSS Supplier /A.E. 1 Title Naue Office Hcce HHL
- 1. Site Service Marager Bob Stough (1) The area code of the above phone n=bers is
~
Notes: (2) The phone beeper number'is~ ~ ~_ J ' l.*
- 2. Operatire Plant Service Frar2 Noon i (".. Parager ist Alternate r m a.s Lokay 2nd Alternate Ron Von Osinski 3 Service Response Joe Leblarg Y2:2ger 1st Alternate Frar2 Nocn i 2nd Alternate John PJ.ller
- 4. Emergency Response Har2 Ruppel -
Director 5 Energency Response Ron Lehr
- - Deputy Director l
- 6. Emergency News Mike Margan Coctunicatiors i
l Note: Unless indicated otherwise, all phone r:=bers are area code 412. khere an i area code other than 412 is shown, it applies to the office, hcce, and HEL ( numbers
- 2) GAI ,
L (Non al ! j norking Hours) e i.
,.,-.w-, ,s.---- . . , , --.w.. -..,m..-,r,.4 4.y ._,m ,,y e - , . . . - g. , - - +e - $ 9,m- -e
ATIACHMENT III - PAGE 3 of 3~ - i REVISION O OFF-SITE EMERGENCY SERVICES NAME OF ~ t 2 PERSON l AGENCY / PERSONNEL PHONE NOTIFIED TIME-
- E. Fire Services I ; 1) Fairfield County Fire Services .
Give the following information:
.This is the Virgil C. Sum =er Nuclear .
[ Station. This is a Drill This is not a Drill We reonest fire fighting assistance ~ at out facility. The fire trucks
! c:ust enter via the main gate, using (denote route to be taken) .
F. Local Law Enforce =ent G. National Weather Service (Backup to Load Dispatcher for weather inforr.ation).
- 1) Colt =bia -
{
- 2) Greer 1
1 .. CALLER'S SIGNARTRE DATE , j b 1 I 4 l i 4 i
. - _ ~ - . _ _ _ . - . . _ . . . , _ . . . _ _ _ - , _ . ._ - . _ _ , _ _ , , _ - _ _ . _ _ . _ _ _ _ . . _ _ _ _ . _ _ _ . ~ , _ _ _ . _ .- _ _ . - -
EPP-002 ATTACHMENT IVA PAGE 1 0F 5 REVISION O DATE TIME (~ ~ POLLOWUP-NOTIFICATION , ALERT i (1) This is (Name) (Title) (2a) This is a drill. l (2B) This is not a drill. (3) I am providing you with follow-up information of an incident which occurred-at the Summer Nuclear Station at: (Date) (Time) (4) The class of Emergency is - ALERT No change in classification Classification Downgraded (5) The initiating event causing the Emergency classification in'(4) above:
! er-
^
%2 (6) The type of Actual or Projected release is: .
Airborne / Waterborne /Not Applicable t (7) The estimated duration of the release in time is: (8) The chemical and Physical form of the released material is: i (9) Radiation Release - Total: TYPE RADIATION RELEASE RATE (C1/Sec) TOTAL ACTIVITY RELEASE (C1) Noble Gases
; Iodines Particulates
( . 1
EPP-002 ATTACHMENT IVA PAGE 2 0F 5. REVISION O DATE TIME ('
~
(10) Radiation Release - Breakdown (when available): TYPE RADIATION RELEASE RATE (C1/Sec) TOTAL ACTIVITY. RELEASE (C1) Noble Gases-Krypton Xenon 133 ' Xenon 135 Iodines I2 131
- I2 132 I2 133 l I2 134 I2 135 Particulates-Principle Gamma Famitters Cerium 141 Cerium 144_ (
Cobalt 57 Cobalt 58 Cobalt 60 Iron 59 Manganese 54 Zinc 65 ~ Molybdenum 99 Cesium 134 Cesium 137 (Other) a
EPP-002 . , PAGE 111-REVISION 0 5/20/81 TABLE OF CONTENTS (Continued) ( Attachment VI - TSC/OSC Emergency Telephone List Attachment VII- Off-site Emergency Telephone List C. S e
2
, . EPP-002
~ PAGE 11 . REVISION 0 5/20/81 i (x TABLE OF CONTENTS 1 PAGE List Of Effective Pages 1
' l.0 PURPOSE 1
2.0 REFERENCES
1 , 3.0 DEFINITIONS 1 4.0 PREREQUISITES 2 50 PROCEDURE 2 s 5.1 Initial Notifications , 2 5.2 , Notifications for Change of Emergency-Classification 2 53 off-site Emergency Services 3
, 5.4 Follow-up Notifications 3 l ([, 5.5 Vital Personnel Notification 3 ATTACHMENTS Attachment IA - Initial Nctifications - Unusual Event Attachment IB - Initial Notifications - Alert .
Attachment IC - Initial Notifications - Site Emergency Attachment ID - Inititl Notifications - General Emergency Attachment IIA - NRC One-Hour Notifications J Attachment IIB - ANI Eight-Hour Notification , Attachment III - Off-site Emergency Services
- Attachment ITA - Follow-up Notifications - Alert Attachment IV3 - Follow-up Notifications - Site Emergency i
t Attachment IVC - Follow-up~ Notifications - General Emergency i Attachment V - VCS Plant Data and Status I ( r m _
EPP-002 PAGE 2 REVISION O 5/20/81 3.2 Abbreviations 3.2.1 TSC - Technical Support Center 3.2.2 OSc - operations Support center 3.2.3 EOF - Emergency Operations Facility . 3.2.4 ED - Emergency Director 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. 5.0 PROCEDURE 51 Initial Notifications (reference paragraph 3.1.1) 5.1.1 Upon declaration of the appropriate emergency classification, the ED/IED will direct the communicator to implement the appropriate notifications. 5.1.2 The ED/IED will assure that the required information is available to effect prompt notification. 5.1.3 The communicator will, upon direction from the ED/IED, implement the initial notifications per the applicable section of Attachment I and Attachments IIA and IIB.
~
- NOTE
- Attachments I, II and III list. alternates for various .
l personnel. These notifications attempts are to be made' in numerical sequence as indicated and will be considered complete upon successful notification of one of the listed. l 52 Notifications for Change in Emergency Classification NOTE: If classification change is made in the middle of a l nc.tifications 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 I which corresponds to the higher emergency classification, and Attachments IIA and IIB. I ! 5.2.2 When the emergency classification is downgraded, the communicator will, upon direction from the ED, implement l
EPP-002 PAGE 1 REVISION 0 5/20/81 ( l.0 PURPOSE - i 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" Voluntary Assistance Agreement (by and among Electric Utilities
~
2.4 involved in Nuclear Generation) - Article 9 - Transportation of Nuclear Materials; and Emergency Resources Manual (ERM) - [RP/EP-1] 1980. "INP0" Institute of Nuclear Power Operations. 3.0 DEFINITIONS AND ABBREVIATIONS , i {~' 3 1
' Definitions 3.1.1 Initial Notification - The transfer of informa, tion 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 i after' declaration of the applicable emergency classification.
EXCEPTION: (1) The NRC, Bethesda, Maryland office and the Site Resident Inspector are to be notified within I 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 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 information is I required at 15 minute intervals following completion of i initial or previous follow-up notifications. EXCEPTIONS: Following initial notification of the NRC, an open communication line will be established and maintained to provide continuous updating to the NRC. s
i ' EPP-002 . ATTACHMENT IA PAGE 1 OF 3 REVISION O b INITIAL NOTIFICATION - , UNUSUAL EVENT i (1) This . (Name) (Title) (2a) This is a drill. l (2b) This is not a drill. 4 (3) I am notifying you of an accident at the V. C. Summer Nuclear Station which occurred at: (Dat e) - * (Time) (4) The class of Emergency is an Unusual Event. (Time of Classification) l (5) Description of Event: ! (6) Radiation Release Yes .No: If yes compete 7 through 14. (7) Type of Actual Release or Type of Projected Release: , (8) Estimation of Duration of Public Impact: - (9) Release Rate: (9A) Noble Gas (93).
-(9C) Release Height f - (10) Meteorological Conditions: (10A) Wind Speed (mph) Site (11A) Dose Rate--Whole Body (MR/HR)
(11B) Integrated Whole Body Dose , ( hour projection) (MR) (llc) Dose Rate--Thyroid (MR/HR) l l (11D) Integrated Infant Thyroid ( hour projection) (MR) (
+
EPP-C02 PAGE 3 REVISION 0 5/20/81 notifications per the sectic of Attach =ent IV wh.ich corresponds to the classification which is being changed.' 5.3 off-site E=ergency Services 5.3.1 Upon direction fro = the ED/IED , the co==unicator will implement the requested notification (s) per Attach =ent III. 5.3.2 Upon direction fro = the ED/IED, the co==unicator will contact other utilities for assistance using the "INP0" Resource Guides Reference 2.4 (NOTE: The alluded to Resource guides are available for co==unication use in the Control Roo=/TSC/OSC and EOF.) 5.4 Follow-up Notifications (reference paragraph 3.1.2) 5.4.1 Follow-up notifications are required for all emergency classifications except Unusual Event. 5.4.2 The co==unicator will implement follow-up notifications per the section of Attach =ent IV which corresponds to the applicable e=ergency classification. 7-s- 5.4.3 Follow-up notifications will be =ade by the site co==unicator(s) until the EOF is activated and assu=es all off-site notification responsibilities. Thereafter, the site co==unicator will transcit updated infor=ation to the EOF as it becomes available, via Attach ent V. 5.4.4 Follow-up notifications to the E=ergency Preparedness Division and the counties shall be cade by the TSC or EOF Co==unicator until such time that the S. C. State forward EOC is staffed and co==unications are established. NOTE: All transfers of notification responsibilities shall be documented. 5.5 Vital Personnel Notification 5.5.1 The co==unicator will notify vital personnel as directed by the ED/IED per (The Vital Personnel Telephone Listing.) 5.6 TSC/OSC/ EOF Co==unications 5.6.1 TSC-OSC - telephone list are provided in Attachment VI. 5.6.2 EOF - telephone list are provided in Attachment VII.
. EPP-002 ATTACF2ENT IA PAGE 3 0F 3 REVISION O INITIAL NOTIFICATION UNUSUAL EVENT
~
EASY . PERSON AGENCY / PERSONNEL NORMAL ACCISS SITE NOTIFIED TIME
- 1. Managment Duty Supervisors (per Duty Roster)
- 1) Ollie Bradham
- 2) John Connelly c_ A - -
- 3) Lou Storz - -
i 4) Bob Croley I 5) Ste m .3=ith-6)' Vince Albert
- 2. *S.C. Dept. of Eealth &
Environmental Centrol, Bureau
' of Radiolopcal Health {
- 3. *NRC See Attachnent IIA of EPP-002 for NRC Initial Notification Re ,
- 4. Media Coord. (Supv. Nuclear Info.)
Hone Office
- 1) Pecky McSwain
- 2) 1st Alt. - Buddy Clark -
l- 3) 2nd Alt. - Beth Willians
- 5. Site Services Manager-Bob Stough >
- 6. Institute of Nuclear -
PowerOperations(INFO)
- 7. Anerican Nuclear Insurers (ANI) See Attachnent IIB of EPP-002 for ANI Notification NOTIFICATIONS COMPIF2E:
! CALLER'S SIGNATURE DATE
- Dedicated Line Also Exists. , (
EPP-OO2 ' i ATTACHMENT IA PAGE 2 0F 3-REVISION O r k INITIAL NOTIFICATION (con't) - k ' UNUSUAL EVENT (12) ' Sectors Affected (13) Does involve the release of some radioactive material from the
- station at a level at which the following Protective Action is advisable: Yes {N o .
(If yes, select one of the below options) (13A) People living in zones around the station remain inside
, with doors and Windows closed. .These zones are in a direction from the station out to a radius of about miles.
(13B) People in zones EVACUATE their homes and businesses. These zones are in a direction from the station out to a radius of about miles. We urge people in these areas to leave their h'ome or business in a safe, orderly fashion. (14) Off-Site Emergency Actions Recommended i: /~N\j I 4
- I
~
i t t
-m Y e
5 o v , , - .
EPP-002 ATTACHMENT IB PAGE 2 0F 3 ' REVISION 0 , INITIAL NOTIFICATION (con't) _ ALERT i j (12) Sectors Affected - (13) Does involve the release of some radioactive material from the station at a level at which the following Protective Action is advisable: Yes No (If yes, select one of the below Options) (13A) People living in zones around the station remain inside with doors and windows closed. These zones are in a direction from the station out to a radius of about miles. 1 (13B) People in zones EVACUATE their homes and businesses. These . zones are in a direction from the station out to a radius of about miles. We urge people' in these areas to leave their home or business in a safe, orderly fashion. (14) Off-Site Emergency Actions Recommended ( e 6 1
~
( n - - - _s,-,- ,ex-g-w...,--e,,+,,~,-e - - , - ,,v , , < ~ y.w- ,4- -,,,,,,n. -,,e,., ,,v-n ,,, - -y-m .g,- , - - - - , n,n-w ,, , e ew,
EPP-002 ATTACHMENT IB PAGE 1 0F 3 REVISION 0 [' INITIAL NOTIFICATION , ALERT
/
(1) This (Name) (Title) (2a) This is a drill. (2b) This is not a drill. (3) I am notifying you of an accident at the V. C. Summer Nuclear , Staion which occurred at: (Date) (Time) (4) The class of Emergency is an Alert . Classification Upgraded From AT Time (5) Description of Event: i (6) Radiation Release Yes No: If yes complete 7 though 14 (- (7) Type of Actual Release or Type of Projected Release: ss (8) Estimation of Duration of Public Impact: (9) Release Rate: (9A) Noble Gas (9B) (9C) Release Height
-(10) Meteorological Conditions: (10A) Wind Speed (mph)
(10B) Wind Direction (blowing to) (10C) Stability Class (10D) Precipitation (11) Projected Dose At: Site Boundary 2 Miles 5 Miles 10 Miles (11 A) Dose Rate--Whole Body (MR/HR) (11B) Integrated Whole Body Dose ( hour projection (MR) (11C) Dose Fate--Thyroid (MR/HR) (11D) Integrated Infant Thyroid ( hour projection) (MR)
.EPP-002 ATTACHMENT IC PAGE 1 0F 3 REVISION 0 INITIAL NOTIPICATION ,
SITE EMERGENCY (1) This (Name) (Title) (2a) This is a drill. (2b) o a drilli This is n't
-(3) I am notifying you ofe-an accident' at the V. C. Summer Nuclear Station which occurred at:
4 Dat e ) ~ (Time) (4) The class of Emergency.is a~ Site Emergency , Classification Upgraded From at Time (5) Description of Event: (6) Radiation Release Yes No: If yes, complete 7 through 14. (7) Type of Actual Release or Type of Projected Release: (8) Estimation of Duration of Public Impact: O (9) Release Rate: (9A) Noble Gas (9B) (90) Release Height
- (10) Meteorological Conditions: (10A) Wind Speed (mph)
'(10B) Wind Direction (blowing to)
(100) Stability Class (10D) Precipitation (11) Projected Dose At: Site Boundary 2 Miles 5 Miles 10 Miles (llA) Dose Rate--Whole Body (MR/HR) (11B) Integrated Whole Body Dose ( hour projection) (MR) (llc) Dose Rate--Thyroid (MR/HR)
- (llD) Integrated Infant Thyroid I -,
( hour projection)(MR)
~
EPP-002 ATTACfEENT IB- . PAGE 3 0F 3 REVISION O (' INITIAL NOTIFICATION ALERT , I EASY PERSON GENCv/PEllSONNEL NORMAL ACCESS SITE NOTIFIED M
- 1. Management Duty Supervisors '
(per Duty Poster) - I 1)0111oIBradham
~-
,? -
--s
'- ~
- 2) John Connelly f - - -
~
- 3) Lou Storz ,
- 4) Bob Croley _
~
,, ) Steve h ith, -
.. s s
==
iQ \$.)VinceAlbert
~
s r 2A 'S.C. Dept. oT Health & '~ f. Environmental Control, Bureau - of Rs.diological~ Health h A 'NRC See Attachment IIA of EPP-002 for NRC Initial Notification Requirements
- 4. M'edia Coord. (Sup'v. Nuclear Info.) '
Hcce Office
~
- 1) Becky McSwain 2
~
- 2) 1st Alt. - Buddy Clark .
\
'3) 2nd Alt. - Beth Williams
_ 5. Site Services Manager-Bob Stough
- 6. Institute of Nuclear .
~
Power Operations (INFO) , - 2
~
- 7. Fairfield Ptsped Storage Facility
~
y
, 8. American Nuclear Insuc ers (ANI)~
See Attachment IIB of EPP-002 for ANI
~? Notification W'
NCTIFICATIONS COMPLETE: j
~ -
CALLEPS SIGNATURE DATE Y # Dedicated Line Also Exists. f -
~
ww.
.,a.
s A
. . . - _ ... ~ - - . _ ___ - - - - - . - _ .
- EPP-002 .
~
ATTACHMENT IC-PAGE 3 0F 3 REVISION 0 INITIAL NOTIFICATION
' f' _'
" SITE EMERGENCY" .
NAME OF EASY PERSON AGENCY / PERSONNEL NORMAL ACCESS SITE NOTIFIED TIME 1.- Managemant Daty Supervisors ' (per Duty Router) ,
~ -
- 1) Ollie Bradham 3-T
- 2) John Connelly "; -6 i
- 3) Lou Storz ..
1
- 4) Bob Croley
- 5) Steve Smith -
- 6) Vince Albert - __- -
- 2. #S.C. Dept. of Health & ~
Environmental Control, ' Bureau of Radiological I Health -t . ('; 3 *NRC See Attachment IIA of EPP-002 for NRC Initial Notification Requirements , 4 Media Coord. (Supv. Nuclea.- In fo . ) Home pffice
- 1) Becky McSwain - __~ 0
~ -
- 2) 1st Alt. - Buddy Clark -
~
- 3) 2nd Alt. - Beth Williams
- 5. Site Services Manager -
Bob Stough l
- 6. Institute of Nuclear Power '
Operat.: is (INPO) ..
-c ice a .
- 7. Fairfield Pumped Storage
' " ~~?
~ ^ ~
Facility !
- 8. American Nuclear Insurers See. Attachment IIB of EPP-002 for ANI Notification.
NOTIFICATIONS COMPLETE: Caller's Signature Date
# Dedicated Line Also Exists.
( e w.,w -m me- -m-,o ,m- m --n- en-, - ,, , w----
EPP-002 ATTACHMENT IC - PAGE 2 OF 3 REVISION O ( INITIAL NOTIFICATION (con't) _ SITE EMERGENCY
/
(12) Sectors Affected (13) Does involve the release of some radioactive material from the station at a level at which the following Protective Action is advisable: Yes No (If yes, select one of the below options.) (13A) People living in zones around the station remain inside with doors and windows closed. These zones are in a direction from the station out to a radius of about miles. (13B) People in zones EVACUATE'their homes and businesses. These zones are in a direction from the station out to a radius of about miles. We urge people in these areas to leave their home or business in a safe orderly fashion. (14) Off-Site Emergency Actions Recommended (_-
EPP-002 ATTACHMENT IVA PAGE 3 OF 5 REVISION 0 DATE ( TIME __ (11) The Prevafling Weather is:
- a. Wind Velocity: mph
- b. Wind Direction: ,
degrees i
- c. Temperature at the release point is:
- d. Atmospheric Stability Data (Vertical Temperature Difference) is:
- e. The form of precipitation, if any, is:
(12) The actual or projected dose rate at the Site . Boundary is:
- a. Actual MR/HR
- b. Projected MR/HR (13) The projected dose rate and the 2 hr. Integrated dose at 2, 5, 10 miles is:
WHOLE BODY (MR/HR) CHILD THYROID (MR/HR) a. ({ - Projected Dose Rate 2 miles 5 miles
. 10 miles
- b. 2 hr. Integrated dose WHOLE BODY (MR) CHILD THYROID (MR) l 2 miles 5 miles 10 miles
- (14) The sector (s) affected are
(15) Estimate of any surface radioactive contamination is: ( l - i
.s I
EPP-0.02 - ATTACHMENT IVA PAGE 4 0F 5
. REVISION 0 DATE Time
{ (16) The Emergency response action (s) underway are: (17) Needed on-site support by off-site organizations is: (18) The prognosis for worsening or termination of the emergency " based on plant information is: (19) A formal written copy of this message will be forwarded to you for your records. (20) You are requested to authenticate this message, by verification of my name on an approved list of notification personnel you have been provided. (21) A follow-up message: a) Will follow in approximately minutes b) No follow-up messaage at this time . () 0
. EPP-002 ATTACHMENT IVA PAGE 5 0F 5 REVISION O
{ FOLLOWUP NOTIFICATION
~
ALERT NAME OF EASY PERSON AGENCY / PERSONNEL NORMAL , ACCESS NOTIFIED TIME 1.0 S.C. Dept of Health & ! ~_ Environmental Control, 7 7 . Bureau of Radiological I Health , Nctifications complete: Caller's Signature
. Date
- Dedicated Line Also Exists. -
l ( -
.I
EPP-002 ATTACHMENT IVB PAGE 1 0F 6
. REVISION O DATE TIME
{ FOLLOWUP-NOTIFICATION SITE EMERGENCY (1) This is ~- (Name) ; (Title) p - (2a) This is a drill. , (2B) This is not a drill. (3) I as providing you with follow-up information of an incident'which occurred at the Summer Nuclear Station at:
~
(Date) , (Time) (4) The-class of Emergency is - SITE EMERGENCY No change in classification Classification downgraded from (5) The initiating event causing the Emergency classification in (4) above: () (6) The Emergency Condition (Select one of the below options)
- a. Does not involve the release of radioactive material
, from the station or involve the public.
- b. Involves the POTENTIAL for the release of radioactive materials, but NO radioactive materials have.been released.
- c. Does involve the release of some radioactive material from the station, but a level below that considered a public hazard.
- d. Does involve the release of rar.ioactive materials from the station at a level at which the following Protective Action is advisable:
t 4 d
EPP-002 ATTACHMENT IVB PAGE 2 OF 6 REVISION 0 DATE TIME { .
.(1) People living in zones around the station remain inside with doors and windows closed. These zones are in a direction from the station out to a radius
~
of about miles. (2) People in zones EVACUATE their homes or businesses. The zones are in a direction from the station out a radius of abouI- m11ec. We urge people in these areas to leave their home or business in a safe, orderly fashion. (7) The type of Actual or Projected release is: Airborne / Waterborne /Not Applicable - (8) The estimated duration of the release in time is: (9) The chemical and physical form of the released material is: (~ (10) Radiation Release - Total: , TYPE RADIATION RELEASE RATE (Ci/Sec) TOTAL ACTIVITY RELEASE (C1) Noble Gases Iodines Particulates (11) Radiation Release - Breakdown (when available): TYPE RADIATION RELEASE RATE (C1/Sec) TOTAL ACTIVITY RELEASE (C1) Noble Gases-Krypton Xenon 133 Xenon 135 \
EPP-002 ATTACHMENT IVB PAGE 3 OF 6
. REVISION 0 DATE TIME
~
{. Iodines 'Ia 131 I2 132 I2 133
~
I2 134 I2 135 Particulates-Principle Gamma Emmitters Cerium 141 Cerium 144 Cobalt 57 Cobalt 58 Cobalt 60 _ Iron 59 Manganese 54 Q Zinc 65 Molybdenum 99 Cesium 134 Cesium 137 (Other) * (12) The Prevailing Weather is :
- a. Wind helocity: mph -
- b. Wind Direction: degrees
- c. Temperature at the release point is:
i a
EPP-002 ATTACHMENT IVB PAGE 4 0F 6 REVISION O DATE Time @- d. Atmospheric Stability Data (Vertical Temperature Difference)_ is:
- e. The form of precipitation, if any, is:
(13.) The actual or projected dose rate at the 31te Boundary is: .
- a. Actual MR/HR
- b. Projected MR/HR (14) The projected dose rate and the 2 hour integrated dose at 2, 5,10 miles is:
WHOLE BODY (MR/HR) CHILD THYROID (MR/HR)
- a. Projected Dose Rate 2 miles 5 ciles 10 miles
- b. 2 hour Ir.tegrated Dose
(~ WHOLE BODY (MR) CHILD THYROID (MR) 2 miles 5 miles 10 miles (15) The sector (s) affected are: (16) Estimate of any surface radioactive contamination is: (17) The Emergency response action (s) underway are: (18) Needed on-site support by off-site organizations is: (
EPP-002 - ATTACHMENT IFB PAGE 5 0F 6 REVISION O DATE TIME . (19) The prognosis for worsening or termination of the emergency based on plant information is: (20) A formal written copy of this message will be forwarded to you for
.your records. ;
(21) You ar e requested to authenticate this message by verification of my na'ae on an approved list of notification personnel you have been provided. (22) A follow-up message:
-a) Will follow in approximately minutes.
b) No follow-up message at this time , 1 e (:) e me k.
EPP-002 i ATTACHMENT IVB PAGE 6 0F 6 REVISION 0 FOLLOWUP NOTIFICATION ({- . SITE EMERGENCY _ T. NAME OF EASY CALLERS PERSON AGENCY / PERSONNEL NORMAL ACCESS SITE SIGNATURE NOTIFIED TIME
-r~
! 2.0 S.C. Dept of Health & 9 - l Environmental Control, ;
~
Bureau of Radiological i Health ! Notifications complete: Caller's Signature Date NOTE: When. the State EOC is established the State BRH will move their operation to the State EOC and communication will be via the State Dedicated Phone Line. Emergency Preparedness Division Adjutant General's office
/
- Dedicated Line Also Exists.
.I 9 h # J p -,..,-.3- -.w, , . _.-,..,_y..,__,__y_, . ., , , , - _ , . , _ . _. - - ~ - - , . , - - - - - y--.
EPP-002 ATTACHMENT IVC PAGE 1 0F 5 REVISION O DATE TIME {' FOLLOWUP NOTIFICATION GENERAL E?iERGENCY (1) This is (Name) (Title) (2a) This is a drill. l (2b) This is not a drill. (3) I am providing you with follow-up information cf an incident which occurred at the Sum =er Nuclear Station at: (Date) (Time) (4) The class of Emergency is - General Emergency (5) The initiating event causing the Emergency. classification in (4) above: (6) The Emergency Condition (Select one of the below options) '
- a. Does not involve the release of radioactive caterial from the station or involve the public.
- b. Involves the POTENTIAL for the release of radioactive materials , but NO radioactive materials have been released.
- c. Does involve the release of some radioactive material from the station, but a level below that considered
! a public hazard.
- d. Does involve the release of radioactive caterials from the station at a level at which thc following Protective Action is advisable:
~ ,
[ -
' EPP-002 2
ATTACHMENT IVC PAGE 2 OF 5 REVISION 0 k DATE TIME _ (1) People living in zones around the station
~~ remain inside with doors and windows closed. These cones are in a direction from the station out to a radius of about miles. ,
(2)-People in zones EVACUATE their homes or businesses. These zones are in a direction from.the station out a radius of about miles. We urge people in these areas to leave their home or business in a safe, orderly fashion. 9 (7) The type of Actual or Projected release is: i . Airborne / Waterborne /Not Applicable (8) The estimated duration of the release in . time is: ] (9) The chemical and Physical form of the released material is: m (10) Radiation Release - Total: I Type Radiation Release Rate (ci/sec) Total Activity Release (ci) Noble gases Iodines Particulates l l (11) Radiation Release - Breakdown (When Available): l j Type Radiation Release Rate (ci/sec) Total Activity Release (ci) Noble Gases-Krypton XENON 133 XENON 135 Iodines - I2 131 Ij 132 I2 133 I2 134 Il 135 (
EPP-002 . ~ ATTACHMENT IVd PAGE 3 0F 5 REVISION O DATE TIME
~
{} Type Radiation Release Rate (ci/sec) Total Activity Release (ci) Particulates - Principle Gamma Emmitters CERIUM 141 . CERIUM 144 - - COBALT 57 - COBALT 58 COBALT 60 IRON 59 MANGANESE 54 ZINC 65 MOLYBDENUM 99
- CESIUM 134 CESIUM 137 (OTHER) ,
(12) The Prevailing Weather is:
- a. Wind Velocity: mph
~
- b. Wind Direction': degrees
- c. Temperature at the release point is
O
- d. Atmospheric Stability Data (Vertical Tedperature Difference) is:
~
- e. The form of precipitation , if any, is:
(13) The actual or projected dose rate at the Site Boundary is:
- a. Actual (mr/hr)
(mr/hr)
'o . Projected (14) The projected dose rate and the 2 hour integrated dose at 2, 5, 10 miles is:
WHOLE BODY (cr/hr) CHILD THYROID (mr/hr)
- a. Projected Dose Rate:
2 miles 5 miles 10 miles M m-m- - m- m - v n- - , , g -,,y, ,4 g----v - eg---- ,,-v,-w-o, - - , , ,,-,mn+ - , - -
. EPP-002 .
ATTACHMENT IVC PAGE 4 OF 5
. REVISION 0 DATE TIME
({' . s
~
WHOLE BODY (mr) CHILD THYROID . (me)
- b. 2 hour integrated dose:
2 miles 5 miles - -u_. _ - _ .
. 10 miles -- _ . , -- .
c- _ - - (15) The sector (s) affected are:
~
(16) Estimate of any surface radioactive contaminttion is: (17) The Emergency response action (s) underway are: _(18) Needed on-site support by off-site organizations is: (19) The prognosis for worsening or termination of the emergency based on plant.information is: (20) A formal written copy of this message will be forwarded to you for (]) your records. _ f_- (21) You are requested to authenticate this message by verification of my name on an approved list of notification personnel you have been provided. (22) A follow-up message:
- a. Will follow in approximately minutes.
- b. No follow-up message at this time .
O 4
EPP-002 -
, ATTACHMENT IVC -
PAGE 5 0F 5
. REVISION O FOLLOW-UP NOTIFICATION
~
{
?' GENERAL EMERGENCY"'
NAME OF EASY PERSCN ' AGENCY / PERSONNEL NORMAL ACCESS NOTIFIED TIME
- l. 'S.C. Dept. of Health' -
& Environmental Control, Bureau of Radiological -(
l I
~_
Health ! The following notifications shall ce made by the TSC or EOF Ccamunicator until such time that the S. C. State forward EOC is staffed. .
- 2.
- Emergency Prepared-ness Division Adjutant General's Office
- 3. *Fairfield County _
- 4. *Newberry County
- 5. *Richland County (~j{
- 6. *Lexington County NOTIFICATIONS COMPLETE: /
(Caller's signature) (Date)
# Dedicated Line Also Exists.
Note: When the State E00 is established the State BRH will move their operation to the State EOC and communication will be via the State Dedicated Phone Line. Emergency Preparedness Division Adjutant General's office s,
I
, I:4EECINCY .
V.C. SU..'4IR NUCLT.AR STATION' EPP-002 CLASSIP CATICN (Circle) *, ATTACE:ENLV PLANT DATA AND STATUS pAGE 1 of 2 {. Usual; Event - Ale'rt . REVISION O
'- tite'Ener - Gen. Iber ,
.- TE -
_ _ _ TI ATT
- 1. PRIMARY COO:. ANT SYS m ',-
4.. SAFETY INJECTION SYSTIM .
- a. T/Ec't - Icop A -
F
- a. C/SI Pun;s Running , A 3 C
- h. T/ Hot - Loop B F b.
, , Total SI Flow to RCS ,
'GP!:
' c,. T/Ect - Loop C ~ ~- F'~ . c. RWST Level ,ef,'
i
- d. T/ Cold - Loop A F
, d. Safety Inj. Actuation? b h C N . .
- e. T/ Cold - Loop B F .
- e. Safety Inj. Accumulator '
- f. T/ Cold - Lecp C F., .
. Level
- In.
Pressure ~PSIG'
- g. RC Systa= Press ..PSIG . *
- h. - P:R Water I.evel 4 5. COW aim I W SYS m S ,
- i. RCP's Running A' B .C -
* .a.. .Rd Bldg. Press - ' .* .PSIG
- j. Beren Concentratica PPM
'
- d*I '
**2. . . .
- k. Reacter Power % AMPS CPM '?* I d I* E#2 **1
- 1. T/ Avg - I4cp A F d. h Bldg E ^
- 2 --
o e.' Rx Bldg Spray
=. ./. Avg w
, ep B F Yes - No
- n. T/ Avg - I4cp C F , $.~ . _310 *9. . solatic,n
.. Yes O N:
n a O vent :so. O e; . S===N=Aar CCe=N= SrS=rM Phase A O
. .= . . - .. . . _ . . . . _
- a. SC/A Level '.
4 - 2-t *
- h. SG/3 I.evel % - *** ~
~ ..
- c. SG/C I4 vel % -
- d. SG/A Stea= Press PSIG i . 1.
l
- e. SC/B Stea= Press PSIG :
1
- f. SG/C Staa= Pres's PSIG
- g. FW P'.=:p A Flev MPPE
- h. FW P'.=:p B Flow
- MPPE '
- i. FW P=p C Flev MPPE -
- j. SC/A ZF Flow GPM ~
- k. SG/B I'F Flcw GPM -
- 1. . SG/C ." Flow GPM '
=. Condensata Systa= 0 Avail O Not Avail . .
- n. Ccadensate Storage Tank *
' Level In. .
~
- 7. ME TcRcLoc: CAL I';FCP.w.AT:CN
- 3. AUX 1 ARY SYS-'Iu.S
- a. Letdewn Flew
- a. Wind Speed MPH CPM
( b. Charging Flcw (.7 -122)
- ~
- b. Wind Directicn GPM o AT 10-60 e
- c. Total Seal Injec icn Flow
- c. F 4 10-35 F GPM .
- d. Mai . Plant vent Flev CFM
- d. Seal Rat..rn Flew GP.w.
- 8. A :T:: MAL := POP.v.AT M
- e. PJ'R P.:=p Run 1 2
- w. _ . . u w. . .-
* * . EPP-00 2 Page 2 of 2 7g -
A IAmc V Revisien 0 4.
, ,, , RADIA ION MONITORING SYSTIM ,
~
FE - Al Par:. ep= RM - G1 mR/Er. -) Ie ep= ',' I_ _ CP - 2 - G2 .
=R/Er. - -
E - A2 Part.
~
cp= - 73 - G3
.* . rI/Er.
- Ie ep= , PX - G4 =R/Er.
I cp=
."RM - G5- -- =R/Er. -
~ ~ RM - A3 Part. cp: -
Ie ep= , RM - G6 =R/Er. '- . . I cp= . RM - G7
=R/Er. .
E - A4 Parl. cp :
. RM - GS -
=R/Er.
g
.e -
cr-I cp= .
- 33 _ gg .=R/Er. .
E - G10 ' FM - A5a.Part. cp= .
~ e.R/Er.
Ie ep= M - Gil =R/Er. *
. I- C7:
- g - ct2 g[c. -
~'
EM - A5h Par:. ep= . Ie- c?= . ~ RM-G53 =R/Er.
~.. ~ .
I cp= ..;i , RM'- GIO-
=R/Er. , ;,
73 - A6 ?ar:. ep= ' RM - G15 ' '
- =r/Er.~ ,
~
I* CY 4 I cp= PE - G16 =R/Er. 7 , 73 - G17a =R/Er. Ie ep= -- EM - G17b =R/Er.
- t
- Cr- . u - Gig -
RM - AS ? art. cy: . Ie c7= RM - G19 =R/Er. - I cp=
- A9 ? . cp - L1 uti/cc (Cs-137)
Ie c7= 73 '- L2a uC1/cc (Cs-137) ' I cr- RM - L2d - uC1/cc (Cs-137) m - A10 ? art. - - cp= Ie ep: E M - I.3 uCi/e (Cs-137) I e7= RM - Lt. uC1/cc (C2-137) EM - All Part. cp= RM - L5 uCi/cc (Cs-137) I* c RM - L6 uCi/cc (Cs-137) I c7=
? . cp= RM - L7 uC1/cc (Cs-137) i In ep= M - LS uC1/cc (Cs-137) t' c ' "*
RM - L9 uCi/cc (Cs-137) D ~ A13 I**** *E Ia ep= KS - L10 uC1/c (Cs-137) I_ cp=
?M - All. Part. c7:
Ia c7: I cp=
. EPP-002 ATTACHMENT VI PAGE 7 of 2 REVISION O TSC/OSC EMERGENCY TELEPHONE LIST
(}) ~
. . . . _ . Technical Suppert Center
--.. ~ . - -
t
; Nuclear Regulatory Co==ission
~
Nuclear Regulatory Com=ission Nuclear Ragulatory Commission TSC Display Roo= _ TSC Display Room . TSC Display.Roo= Dose Assessment Area , Technical Support Engineers Technical Support Engineers Technical Support Engineers
~
Technical Support Center-Co===unicators Telecopier Phone to EOF A(]) Padiation Monitoring Teams Assistant Manager, Support Services-Vince Albert Radiological Assess =ent Supervisor-L. A. Blue Assistant Manager, Technical Support-B. Croley 5ecurity Supervisors-J. Sefick/Capt. Tuttle
~
Assistant Manager, Maintenance Services-S. Smith Assistant Manager,' Operations-L. Storz Westinghouse GAI OSC _ OSC OSC ( .
EPP-002 ATTAQog m VI Page 2 of 2 TECHN1 CAL Su PPORT CE >JTE R Revision 0 E,
, b *
. ... . . . . . . . = - - . . . . . - - - - . . . . - . . . - - - - - - - . ---- . - . -- - - - -
PLANT STATu57 MGc-lP. a;, I'WU D15PLA'T AREA , i
\ DO SE ' - .
*: -:1-f h - C . .
V: 2, '_)- . . ASSESS MENT AREA ' 14500 -
.- _ l a - 3 y
.4 q
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,Os ..
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' ' ' v
.c'i ' !
~
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-(Tatr.copis4 \ / -
- -- - % /
MTICR.lN {1 Nsss AE TEAM 5
.A m Aas.A AR=.A J-_d 1.Q-jil 152:.fW j .i fi.!
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--. _ - _ _ - - . - . . . _.- - . -. - . . .._. - _ . . . .-= . - .
EPP-002 ATTACHMENT VII PAGE 1 of 3 REVISION O ( OFF-dITE EMERGENCY TELEPHONE' LIST
- Emergency,0perations Facility e
l EOF Communicator Area j EOF-NRC EOF-NRC EOF-NRC EOF-NRC EOF-Technical Support Coordinator-M. B. Whitaker , l EOF-Security Coordinator-J. Harrison l EOF-Media Coordinator-R. McSwain EOF-General Services Coordinator-J. Bailey i l EOF-Construction / Repair Coordinator-0. W. Dixon EOF-Offsite Radiological Monitoring Coordinator-I - Bill Baehr EOF-Technical Support Engineers EOF-Technical Support Engineers EOF-Technical Support Engineers EOF-Technical Support Engineers l
- - - , ,- ,we. ..e..,-,,.r. y_. r_- - .. _ , . . ,..w,%.- w9 w_.,.y,. ,...~.__ 9 s. f ew*w w ww r"F- w -y w - r 7
--r----- T " * - - - - -
EPP-002 - j ATTACHMENT VII - l PAGE 2 of 3 REVISION 0 OFF-SITE EMERGENCY TELEPHONE. LIST (cont.) _
/
Emergency Operations Facility
; - ~i EOF-Telecopier between TSC/ EOF EOF-General Services Support Area EOF-General Services Support Area EOF-General Services Support Area EOF-General Se'evices Support Area EOF-General Services Telecopier EOF-Security Office EOF-Security Office EOF-Construction / Repair Support Areas C EOF-Construction / Repair Support Areas EOF-Construction / Repair Support Areas EOF-Media Coordination Support Area EOF-Telecopier for Media Area EOF-Offsite Radiological Monitoring Area EOF-Offsite Radiological Monitoring Area
(
EMERGENCY OPERATIONS FACILITY IPP-00 2 COMPANY TELEPHONE LAYOUT ATTAC E m VII f Pago 3 of 3
/
Revision O l
~
l 9 8 8 i
/ / '
1 /
,/
7 6 ! 2 ' J S e
; ~
3 10 4
/
- 1. Command Centel 5. Security Area
- 6. Media Area
- )
- 7. Offsite Radiological Monitorinc
- 2. Technical Sgpport Area Area
- 8. NRC Area r)
- 3. General Services Area 1
i 9. Communications Area O
- 4. Construction / Repair Area j
f
4 SOUTH CAROLINA ELECTRIC AND GAS COMPANY ! . O, VIRGIL C. SUMMER NUCLEAR STATION NUCLEAR OPERATIONS 4 l-E C @ R 0?ER E1 . COPY NO EMERGENCY PLAN PROCEDURE , , EPP-003 IN-PLANT RADIOLOGICAL SURVEYING REVISION O MAY 20, 1981 ! Non-Safety Related O Reviewed by: MC . ORIG /Ill TOR (of this revision) Date M .x -- N-N-$/ Date QUALIFIED REVIE' DER Approved: L /}b Wf~)
'LANT MANAGER 'Date/'
M te Issued:OEC 1 - 19117 REVIEWED BY 'SRC *# Form AP-101-2, (1/80) O II 30lal R.x.%f_____ CHA!RMAN DA
--o- - -..-,..- ,. - -. ,_,,-- ,.. - --. _ ,.- , , ,- , -- , ,.
EPP-003 h. PAGE i REVISION 0 5/20/81 LIST OF EFFECTIVE PAGES h PAGE PEVISION i 0 11 0 1 0 2 0 3 0
*4 0 ATTACHME!!TS ATTACHMENT I O ATTACHMENT II O ATTACHMENT III O ATTACHMENT IV 0 9 ' Indicates that a (later) is contained on the respective page of this procedure. The responsible Assistant Manager during subsequent revisions will upcate or renove this (later) when infornation is available.
O
l... '
/ k '
4 Li e 1 [ EPP-003 ) j - j r, ~ Page it 9' ^ ll i ' l . Revision 0 'i ' ^ --- 5/20/8)c, l?,; L
" ~ '
I, TABLE OF CONTENTS , < ; { PACE , l List of Effective Pages i i 1.0 PURPOSE 1 i s ,1 I
2.0 REFERENCES
1 . l* s ,/
~
i 30 CONDITIONS AND PREREQUISITES m 1
-/;
l 4.0 PROCEDURE 2 ~ '
, .s- ;, i l
/ '
.)
,,n
. ATTACHMENTS i ,- , ,',. ~~ j Attachment I - Survey Record , , . 4 > n-[ 7 z.< 4, n > 5 1 Attachment II - Approximation of Air Sample Iodine and Partip'i.a'te ;l,,-r __' l ) Concentrations with RM-14 and HP-210.
~
Attachment III - Estimate of Iodine Concentration with RM-14 ani #w i HP-210 ,
/
Attachment IV - Estimate of Particulate Concentration -
~
I
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EPP-003
< PAGE 1
/ REVISION O 5/20/81 1.0 PURPOSE (g) 1.1 Provide guidance for the direction and implementation of Radiological Surveys inside the plant in the event of an emergency.
2.0 REFERENCES
' 2 .1 " Virgil C. Summer Nuclear Station Radiation Emergency Plan".
2.2 AP-702. "Use of Fadiation Work Permit (RWP) and Standing Radiation Work Permit (SRWP)". 2.3 HPP-401, " Issue, Termination, and Use of RWP's". 2.4 AP-704, " Administrative Exposure Limits".
- 2 . 5, EPP-019, " Emergency Equipment Checklist".
i 3.0 CONDITIONS AND PREREQUISITES 31 In-Plant surveys will be directed from the TSC , Control Room, or HP Lab. 32 The In-Plant Monitoring Director should report to the TSC immediately after notification or upon Protected Area lll Evacuation. 3.3' In-Plant monitoring persunnel should report to the H.P. Lab or as directed by the In-Plant Monitoring Director immediately upon notification or upon Protected Area Evacuation. 3.4 Standing RWP's are not applicable for entries into areas with severe or unknown exposure potential. 3.5 Entries into areas where a severe or unknown potential for radiation exposure exists should be limited to:
~
i 3.5.1 Operation of valves and components essential to the safe operation of the plant. 1 5.2 Repair activities essential to the safe operation of the p l a r. t . j' 3.5.3 obtaining information necescary for proper evaluation of , , j e existir.g conditions. 3 5.u Rescue attempts to preserve human life.
'~
lh
's'
/
/
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. .s> .
y s
. EPP-003
, , S\ PAGE 2 J
^
REVISION O T_xm , 5/20/81
^
$3 6 Areas with severe or , suspected severe radiological conditions s will,be entered using the " buddy system", with a two man back-up o -
team dressed for entry, (Vith the exception of donning SCBA),
- in stand-by.
I?CfE': $ minimum of one back-up team, in stand-by, is sufficient for cultiple team entries. t . 37 Protective requirements for entering areas where high levels of stad'ioactive contamination are suspected are as follows:
-3 731 _Mknimum dress' requirements:
Cloth overalls 2 pr. disposable plastic shoe covers Cloth hood 1 pr. rubber boots
, Plastic suit 2 pr. rubber gloves
- Cloth gloves Extremity Dosimetry (as applicable)
TLD and dosimeter High range dosimeter "5 7.2 Additional pro.tective requirements are as follows: (]) Protective Requirement
; ; Condition Noble gas concentrations TLD placed under protective suspected > 1 x 10-3 clothing.
ci/ml Eye protection if fuel damage has occurred or suspected. Iodine' concentrations SCBA suspedted > 10 x MPC Lapel Air Sampler H3 concentrations SCBA suspected > l'0 x MPC Plastic Suit Particulate concentrations Particulate mask or SCBA suspected > 10 x MPC (SCBA required if > 50 x MPC suspected). Lapel Air Sampler Standing water > 1" Waders suspected Extremity dosimetry Protective requirements may be altered at the discretion of In-Plant Monitoring Director or the Radiological Assessment Supervisor as survey and sample data are available. o
EPP-003 PAGE 3 REVISION O 5/20/81 38 Continuously monitor radiation levels as surveys are performed. lh Avoid entrance into any area where the radiation levels exceed 3 R/hr, unless directed by the Plant Manager (Emergency Director) . At least one person in each entry party should wear an alarming audible dosimeter, if high radiation levels are expected. 39 Maintain exposure ALARA - Coordinate all ei orts with TSC to prevent unnecessary exposure. 3 10 AgZe cartridges must be installed in radiation monitors RM-A3 and RM-A4 as soon as possible. Other radiation monitors affected should have AgZe cartridges installed as time and conditions permit. 3 11 AgZe iodine filter cartridges should be used for air sampling when noble gas concentrations are suspected greater than 1 x 10-3 uci/cl. 4.0 PROCEDURE 4.1 In-Plant Monitoring Director (guidelines) 4.1.1 Activate In-plant survey teams as needed. 4.1.2 Monitor readings from the radiation monitoring system and 3 maintain display drawings and data logs current W 4.1.3 Establish and ne.intain communications with in-plant surveyors. 4.1.4 Identify and coordinate survey and sampling locations and routes taken, with the Emergency Director, Radiological Assessment Supervisor, and in-plant surveyors, to minimize exposure. 4.1.5 Coordinate issuance of Radiation Work Permits as specified in References 2.2 and 2.3 NOTE: If time does not permit the generation of RWP's to be used initially, ensure the following is entered in the logbook: date, time, work performed, location, originator / department, known radiological conditions, approvals and ac tual doses received after the job is completed. 4.2 In-Plant Surveyors 4.2.1 Don high range personal dosimeter. O
EPP-003 PAGE 4 REVISION O S/20/81 () 4.2.2 Obtain radio (s). From H.P. Lab or TSC and establish communications with TSC. NOTE: Communications to be keph open at all times to ensure surveyors are kept advised of changing conditions. 4.2 3 Evaluate the situation ('using current data from TSC) and prepare equipment needed for entry. Don protective clothing and respiratory protection, as required. NCTE: A teletector, or equivalent, should be used when entering areas of unknown exposure potential. If there is a potential for high level beta exposure, an instrument calibrated for beta measurements (eg. R0-2) shall be used.
^
4.2 4 Prior to entry, determine amount of allowable exposure. Adjust setpoint on alarming Dosimeter accordingly. 4.2 5 Perform surveys, as directed from TSC, per HPP's( ) NOTE: TSC and surveyors should collaborate to determine appropriate post accident ef forts (eg. type g sampling, sample locations, routes, etc.), to
/ ensure maximum data obtained with a minimum of manpower / man Rem expended.
4.2.6 Record sample data on Attachment I. 4.2 7 Relay survey results to TSC via radio, GAI-Tronics page or best means available. 4.2.8 Transport samples and smears to count room for analysis. 4.2 9 Perform analysis of air samples at the 412' elevation in the Control Building unless excessive background is present. 4291 If excessive background is present, send samples to the Environmental Lab for Analysis. If results are needed quickly, analyze samples using RM-14 and HP-210 probe as instructed by Attachments II and III. 4.2.10 Retain and file all survery records in the TSC. O
EPP-CO3 ATTACE4E!T I PAGE 1 of 1 RFIISIO!! O SURVEY RECO;D IYPE OF SURVEY DATE TIME RADIOLCGICAIJ l SMEAR l l SURVEY EY IMf. TYPE II:ST. RFIIEED EY SERIAL I;O. EFFY. EUILDI?!G DATE CALIE EKG'D RE4 ARKS COUIIED BY RADIOLJGICAL Mr/nr liETA SMEAR ALPHA Iter Equiunent or Total Count Grose I;et DPM No Location Distance G9-% Eeta ?!eutron Counte Tice c/m c/m 1COcco I O I
! l l 1 ! !
I I l l 1 i I I l _.__ O
EPP-003 ATTACHMENT II PAGE 1 0F 1 REVISION O O
~#
ATTACHMENT II APPROXIMATION OF AIR SAMPLE IODINE AND PA RTICULATE CONCENTRATION WITH RM-14 and HP-210 Instructions
- 1. Obtain contact reading (not 1") on front of iodine filter cartridge once it is placed in poly bag. Particulate filters cannot be placed in poly bag until after a count rate is obtained.
- 2. Determine volume of air sampled in liters or ft3 as indicated on instrument.
3 Use graph ( Attachment III) to approximate iodine concentration. Recommended allowable background is <100 cpm.
- 4. Use graph (Attachment IV) to approximate gross particulate concentration. Recommended allowable background is < 100 cpm.
Bases () 1. Attachment III is derived using 37% detection efficiency with an I-131 standard and a 90% filter collection efficiency.
- 2. Attachment III does not compensate for noble gas interference.
This method is limited for counting AgZe filters or charcoal filters used in the absence of noble gas atmospheres. 3 Attachment IV is derived using 10% detection efficiency and a 99% filter collection efficiency. i l l us
EPP-013 ATTACHMENT III PAGE 1 of 1 REVISION 0 1.n e C
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EMERGENCY PLAN PROCEDURE EPP-004 OUT-OF-PLANT RADIOLOGICAL SUhYEYING , REVISION O MAY 20, 1981 O non-s^rstr ast^rso j Reviewed by: I l
;.) l- L {Y Date t
ORIGINATOR (of this revision) d A f 2-Y8l
-QUALIFIED REVIEWER 'Date f
1 Approved:
//~l30/P1 D6t(
4 ~P ANT MANAGER Date resueg: DEC 1 - 1981 REV!EWED EY PSRC'""
' *
- Fo rm AP-101 -2, (1/60) f CHAIRMAT4 DA I
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EPP-004 PAGE i REVISION O 5/20/81 LIST OF EFFECTIVE PAGES PAGE REVISION i 0 ii 0 1 0 2 0
+3 0 ATTACEMENTS Attachment I O Attachment II O Attachment III O Attachment IV O O
+ Indicates that a (later) is contained on the respective page of this procedure. The responsible Group Supervisor during subsequent revisions will update or remove this (later) when information is available. O
EPP-004 PAGE 11 REVISION O 5/20/81 O T ABLE OF CONTENTS Page List of Effective Pages i 1.0 PURPOSE 1
2.0 REFERENCES
1 30 CONDITIONS AND PREREQUISITES 1 4.0 PROCEDURES 2 ATTACHMENTS Attachment I - Survey Record Attachment II - approximation of Air Sample Iodine and Particulate Concentration with RM-14 and HP-210 Attachment III - Iodine Graph Attachment IV - Particulate Graph i l 1 i 1 . 1 i i l O L
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3 _ n ,.. . 7 .n- .Ler .r .=u 1n.v e c. 2.1 "71r-il a C. Surrer Nuclear Station Radiation Emer.z. enc.y Plan." . 2.2 EFP-005, "Of fsite Dose Calculations" 23 HPP-303, " Airborne Activity Sampling Techniques and Procedures'". z.. 2 .p r - 0,0 r , ,, 2 nvironmenta, .,onitoring., . s.O L, ,L-u .r m. 0 n.. va A,D, : r.a..r.e
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EPP-004 PAGE 2 REVISIGH 0 l S/20/81 ()3.8 Limit the use of protective clothing, as radiological conditions warrant, to minimize public concern. 3.9 Retain all samples and sample data for re-evaluation. 3 10 Monitoring results shall be maintained by the TSC and EOF. All monitoring results from outside the 1 mile radius should be maintained by the EOF and stored wit. environmental program data for subsequent report preparation. cionitoring results within the 1 mile radius should be maintained by the TSC and stored w7th plant records. 4.0 PROCEDURE 4.1 Out-of-Plant Monitoring Director (guidelines) 4.1.1 Dispatch out-of-plant survey teams as needed. 4.1.2 Establish and maintain communications with Out-of-Plant surveyors and EOF when activated. 4.13 Frequently monitor meteorological and effldent conditions, keeping surveyors updated. 4.1.4 Identify sampling locations and routes, using priorities (~% listed below as guidelines: O 4.1.4.1 Residential areas.within projected plume. 4.1.4.2 Centerline plume concentrations. 4.1.4.3 Identify plume edges. 4.1.5 Maintain current status of out-of-plant maps in TSC. 4.1.6 Maintain dialogue with the In-Plant Monitoring Director to coordinate post accident efforts. 4.1.7 Determine the need for further environmental sampling (e.g., grass, water and soil). 4.1.8 Transfer control of survey effort (outside one mile exclusion area) to EOF when practical. NOTE: TSC will continue to maintain overall control of out-of-plant monitoring, within the 1-mile exclusion area. 4.2 Out-of-Plant Surveyors
EPP-004 PAGE 3 REVISION O S/20/81 4.2.1 Obtain emergency kits from Service Building Annex and radios from Health Physics Lab or TSC. Check seals and inspection on Euergency Kits. NOTE: If seals are broken or inspection date is not current on energency kits, perform a quick check to ensure emergency kits are adequate for field use. 4.2.2 Source check instruments in kit per (HPP- ). 4.2 3 Obtain vehicle from Security for off-site transportation. 4.2.4 If not already wearing personal dosimetry, don TLD and self-reading dosimeter contained in energency kit. 4.2.5 Establish communication with TSC. 4.2.6 Obtain current pertinent data from TSC/ EOF (estimated release rates of: particulate, iodine and noble gases; wind direction; projected pluce area; etc.) 4.2.7 Perform surveys, as directed froc TSC/ EOF, per applicable HPP's. NOTE: TSC/ EOF and surveyors should collaborate to determine acpropriate post accident efforts (e.g., type sampling, g sacple locations , etc.) to ensure maximum data obtained W with a minitum of canpower/canRe: expended. 4.2.8 Analyze samples in accordance with applicable HPP's using available equipment. Approximate air sample iodine and particulate concentration in accordance with Attachment II. 4.2 9 Record sample and survey data on Attachment I. 4 2.10 Contain, label and retain samples for subsequent analysis in the laboratory. 4.2.11 Collect and replace TLD's and particulate and iodine filters at Environmental Stations when requested by the TSC/ EOF. NOTE: Take precautions to cinimize exposure to environmental TLD's dur'.ng trans portation either to or frca sampling station. O
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EPP-004 ATTACHMENT I PAGE 2 0F 2 REVISION O SURVEY INSTRUMENT INFORMATION -INSTRUMEIi? NUMBER 1 INSIRUME:;2 NUMBER 2 INST. TYPE INST. TYPE SERIAL NUMBER SERIAL liUMBER CALIB. DATE CALIB. DATE SOURCE CHECK SOURCE CHECK ( I!iIT ) (INIT) EFFICIENCY (IF REQUIRED)_ EFFICIENCY (IF REQUIRED) IIiSTRUMENT NUMBER 3 INSTRUME!!T NUMBER 4 INST. TYPE INST. TYPE SERIAL NUMBER SERIAL NUMBER CALIB. DATE CALIB. DATE SOURCE CHECK SOURCE CHECK (INIT) ( IIIIT) EFFICIENCY (IF REQUIRED) EFFICIENCY (IF REQUIRED) NOTES: 1. Instrument number on front sheet should be 1 thru 4 from above information. O REMARKS: O
EPP-004 ATTACHMENT II PAGE 1 0F 1 REVISION O (' V) APPROXIMATION OF AIR SAMPLE IODINE AND PARTICULATE CONCENTRATIONS WITH RM-14 AND HP-210 Instructions
- 1. Obtain contact reading (not 1") on front of iodine filter cartridge once it is placed in poly bag. Particulate filters .
cannot be placed in poly bag until after a count rate is obtained.
- 2. Determine volume of air sampled in liters or ft3 as indicated on instrument.
3 Use graph (Attachment III) to approximate iodine concentration. Recommended allowable background is < 100 cpm.
- 4. Use graph (Attachment IV) to approximate gross particulate concentration. Recommended allowable background is < 100 cpm.
Bases
- 1. Recommended allowable background is 100 cpm. Attachment III is derived using .375 detection efficiency with an I-131 standard and a 90% filter collection efficiency.
- 2. Attachment III does not compensate for noble gas interference.
This method is limited for counting AgZe filters or charcoal filters used in the absence of noble gas atmospheres. 3 Attachment IV is derived using 10s detection efficiency and a 994 filter collection efficiency. l l l 1
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NUCLEAR OPERATIONS , 4 VUC_ EAR OPERK10hS ^ C O PY No. . . . . ./.5. . 7. .F. . . . . , EMERGENCY PLAN PROCEDURE
- EPP-005 0FFSITE DOSE CALCULATIONS I REVISION 0 1
MAY 20, 1981 IO NON-SAFETY RELATED + Reviewed by: i ,1 i L Gow } kjh ORIGINARJR (of this revision) Date ' s NA /. , QUALIFIED REVIEWER /Dage 1 Approved: 1
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I , Date Issued: RE\!Es^s/8 "oY M N #" rorm AP-101-2 <1,803 A C R. A l _ -
t, EPP-005 PAGE i REVISION O 5/20/81 O LIST OF EFFECTIVE PAGES Pace Revision 1 0 11 0 iii 0 1 0 2 0 3 0 4 0 5 0 ATTACHMENTS I O II O III O IV O V O VI O VII O VIII O X IX 0 0 XI O XII O XIII O XIV 0 XV O XVI O XVII O O
. EPP-005 Page 11 Revision 0 5/20/81 TABLE OF CONTENTS Page
()ListofEffectivePages i Flow Chart 111 1.0 PURPOSE 1
2.0 REFERENCES
1 30 CONDITIONS AND PREREQUISITES 1 4.0 PROCEDURE 1 50 BASES 4 ATTACHMENTS ATTACHMENT I - Sample form "A" Meteorology and Source Tera Report For: ATTACHMENT II - Sample Form "B" E=ergency Off-Site' Dose Calculation Using Stock Monitor Source Term ATTACHMENT III - Sample For= "C" Off-Site Dose Calculation Using High Range Monitors ()ATTACHMENTIV - Sa=ple Form "D" Activity Release Status ATTACHMENT V - Sa=ple Form "E" Projected Offsite Doses ATTACHMENT VI - Sample Form "D" Out of Plant Monitoring Dispatch
& Data Form ATTACHMENT VII --
Sample Form "E" Dose Off-Site (Dose Rate) Calculation from Environmental Monitoring ATTACHMENT VIII - Sample Form "Q" Quick Dose Projection ATTACHMENT IX - Delta T Atmospheric Stability Classification ATTACHMENT X - Sigma Theta Atmospheric Stability Classification ATTACHMENT XI - Meterological Sector Definition ATTACHMENT XII - Fig. 1 Stack Monitor Response (0-24 hrs) ATTACHMENT XIr.' - Fig. 2 Stack Monitor Response (0-30 Days) ATTACHMENT X17 - Fig. 3 Steam Dump Monitor Response (0-24 hrs.) ATTACHMENT XV - Fig. 4 Steam Dump Monitor Response (0-30 daye) ()ATTACHMENTXVI -
'rotective Action Guides (PAGS)
ATTCHMENT XVII - gggg1p((g-TurnerMethodforDeterminingAtmospheric
stain EPP-005 PAGE 111 REVISICS 0 5/20/81 3*I*CC l Computer Method
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Method 4.0 I , Driven Manual I I Method 4.2 I s IX a t or 39 3ack up Stability Stability XVII I 4.2.1 4.2.2 s l Plu e
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EPP-005 PAGE 1 REVISION 0 5/20/81 () 1.0 PURPOSE 1.1 To provide methods for estimating wholebody and child thyroid dose rates due to abnormal releases of radioactive materials to the environment. 1.2 To provide a method of comparing the integrated wholebcdy and child thyroid doses of the EPA Protective Action Guides (PAG's).
2.0 REFERENCES
2.1 " Virgil C. Summer Nuclear Station Radiation Emergency Plan". 2.2 American Society of Mechanical Engineers, " Recommended Guide for the Prediction of the Dispersion of Airborne Effluents", May 1968. 2.3 Dames and Moore, " Data Reduction Procedure for Virgil C. Summer Nuclear Station", September 1974. 2.4 Slade, D. H., (ed.), " Meteorology and Atomic Energy - 1968", TID-24190, Division of Technical Information, USAEC (1968). g3 2.5 Turner, D. B., "A Diffusion Model for an Urban Area", Journal of () Applied Meteoroloev, 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/ FEMA-REP-1, " Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Huclear Power Plants", December 1980. 2.8 Emergency Assessment and Response Systems, (EARS 1,000 and EARS 9845). Technical Manual. Applied Physics Technology, Inc. 30 CONDITIONS AND PREREQUISTTE 3.1 None 4.0 PROCEDURE NOTE: This procedure delineates two (2) methods by which offsite doses may be calculated (i.e., computer calculaticn and manual calculation). Either method. ur a combinatica of both methods, may be used since the same gg results can be obtained. V
EPP-005 PAGE 2 REVISION O 5/20/81 4.1 Overlay Selection lll 4.1.1 If the computer is not available proceed to step 4.2 to initiate manual calculations. 4.1.2 Use the HP9845C in the TSC to run the menu driven real-time dose projection system. The program is started by following guidance derived through Reference 2.8. 4.1.3 Complete step 4.3 so that the manun' method map is available for use in case of computer failure. The map is also useful in dispatching out of plant monitorin5 teams. Proceed to step 4.5 4.2 Manual Method 4.2.1 Stability Class Determination If the primary meteorological tower is inoperable ;roceed to step 4.2.2 otherwise, complete Part 1 of Attachment I to obtain meteorology and source term data from control room instrumentation. Method A. is preferred. A. Differential Temperature ( A T) 10-60 meters and 10-35 meters Method.
- 1. Obtain AT information from the Control Room instrumentation.
lll NOTE: Priority should be given to the 10-60 meter information with the back up being the 10-35 meters.
- 2. If the Control Room instrumentation is inoperable, personnel may be dispatched to the meteorological tower to obtain AT information directly from the met tower instrumentation.
3 Determine the Pasquill Category by using Attachment IX and select appropriate overlay.
- 4. Proceed to Step 4.3 for determination of plume location and X/q values.
B. Sigma Theta Method
- 1. Review the wind direction chart located in Control Room and determine wind range for a period of 15 minutes to 1 hour.
O
EPP-005 PAGE 3 REVISION 0 5/20/81 () 2. Wind range is determined by the difference between the highest and lowest values measured. If the wind direction chart shows one or two spikes, these should be 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 Categcry by using Attachment X and select appropriate overlay. 4.2.2 Backup meteorological data can be obtained from two sources, the site 2 tower and/or the National Weather Service (NWS ) . A. Dispatch personnel to site 2 tower and use data from local strip charts for windspeed and direction. Use method B of step 4.2.1 to obtain stability class.
- Data from site 2 is preferred over NWS data. Radio should be established for the duration of the incident. Dosimetry is required for personnel q
\_- B.
at site 2. If primary tower daca is not available call the NWS (Phone: 794-2593) and obtain windspeed, wind direction, % cloud cover and ceiling height. Also, obtain current forecast and note any fronts that may cause a rapid shift in wind speed or direction. Conplete Attachment XVII " Turner's algorithm" to obtain stability class. 4.3 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 overlay along the direction the wind is blowing. NOTE: Wind directions are given as directions from which the wind is blowing; affected directions are 180 from the wind direction. When communicating wind direction, specify the direction from which the wind is blowing and the direction to which the wind is blowing (e.g. wind is blowing from 270 to 90o). 4.3.3. The conversion from wind direction measured in degrees to wind direction in sectors is presented in Attachment XI. O. mm a
EPP-005 PAGE 4 , REVISION 0 5/20/81 4.4 Manual Dose Calculation ggg 4.4.1 Complete Part 2 of Attachment I. 4.4.2 Complete Attachment II if radiation monitor RM-A3 is on scale. Compare results with the PAGS (Attachment XVI). 4.4.3 If RM-A3 is offscale complete Attachment III. Compare results with the PAGS (Attachment XVI). NOTE: Attachment XII, XIII, XIV, or XV will be necessary for completing Attachment III. 4.4.4 Complete Attachment IV to maintain curie accountability. Total activity of iodine, noble gas, particulates, and tritium must be kept current. (Hourly updates if possible) 4.4.5 Transfer all applicable results to Attachment V for transmittal and documentation purposes. 4.5 Environmental Monitoring 4.5.1 As soon as practical, dispatch monitoring teams to the effected meteorological sectors. Attachment VI, should be used to record location and results. NOTE: Dose projections based on source terms should be verified as soon as possible by supportive lll measurements. Based on these measurements, a reassessment of the PAG's should be ta 'n. 4.5.2 Attachment VII can be used to project doses based on environmental samples. These can then be compared with source term projections. 5.0 BASES This section is included to provide a brief explanation of the sources of constants and graphs used in the procedures and associated attachments. 4.3.1-B Until a full class A model is developed, subsequent to the completion by Dames and Moore of a detailed study of the Summer Station Meteorology, the (X/Q) overlays will be based on a strait line gaussion plume model as described in Reg. Guide 1.145 O
^
- EPP-005 PAGE 5 REVISION O 5/20/81
/~% II-B The Iodine to noble gas activity ratio 0.~3, until
\- measured, is a conservative estimate from Ref. 2.7 page D-59 TMI-2 would suggest-that the actual ratio could be 10-5 or lees. A fast and accurate measurement of the actual ratio is important to avoid nnnecessary evacuat.'.on orders based on the Iodi.fie PAGS.
Same comment as II-B III-B VIII-B The curves follow the methodology and assumption of Ref. 2.7 The noble gas curve comes from EQ. 2.9, the Iodine curve from EQ. 2.13 XVII-B This description of the Pasquill-Turner method was supplied by Dames and Moore. The calculation of the solar altitude was obtained from the Alabama Power Company Farley Station EDCM. It was verified by comparision with selected values from the Smithsonian Meteorological Tables. XVI-B Taken from Ref. 2.7 I~') v l ()
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O a..r .ve en t ,. . 0.o.u. . firlspeed _ ' -. mp h Tine Direction _ degreee Delta T degrees (10-60) or (10-35) (circle one) Sigra Theta degrees Stability Class (Use Delta T and Attachment II or Sigma Theta and Attachment X or Turners Algorith and Attachment XVII) Part 2: Source Ter: RMA3 CPM (net) Flow Rate h RM- A13 R/hr Tice RM-G19 R/hr O
EPP-005 ATTACHMENT II PAGE 1 0F 2 REVISION O O EMERGENCY OFF-SITE DOSE CALCULATION USING STACK MONIT0h SOURCE TERM
- Time of Trip Current Time Time after Trip RM-A3 Noble Gas Reading _
CPM (A). Flow rate': CFM x 0.028 = m3/ min. (B) Releace Pct,c': (A)x(B)x(3 3x10-10) = Ci/sec (QN Wind Speed: MPH x 0.45 = m/sec (C) (X/Q)3 from isopleth for 1 mile m-2 (pr X/Q: ( D J )-t ( C) = sec/m3 (X/Q) doble as dose to concentration conversion
, from Aitachment VIII X2= rem /2hr (G)
, C1/m>
O wa0 E E0er uOSE (2 hre): (r) x (C) x (G) = rem in 2 hr. (H) s Iodine to noble gas activity ratio (use 0 3 unless measured) (I) l-Iodine dose to concentration conversion from Attachment VIII rem /2hr C i / m'- (J) O
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EPP-005 ATTACHME!IT II PAGE 2 0F 2 REVISIO:I O EMERGE: ICY OFF-SITE DOSE CALCULATION USIIIG STACK M0?iITOR SOURCE TERM Time of Trip Current Time Time after Trip Iodine to noble gas dose ration (I) x (J) + (G) (K) CHILD THYROID DOSE: (K) x (H) = at 1 mile (2 hour) rem (X/Q) at 2 miles (E2) ( E2) /( E1 ) (L2) 5 miles (D5) ( 25) /( E1 ) (L5) 10 miles (D10 ( E10) /( E1 ) (L10) DOSE 2 miles (L2) x (H) ren x (K) = ren 5 miles (L5) x (H) rem x (K) = rem 10 miles (L10) x (H) rem x (K) = rem WHOLE BODY CHILD THYROID (2 Hour) (2 Hour) h l l 1 0
EPP-005 ATTACHMENT III PAGE 1 0F 2 REVISION 0 f'T
. OFF-SITE DOSE CALCULATION USING HIGH RANGE MONITORS Time of Trip Current Time Time after Trip RM-A13 .
reading R/hr (A) (RM-G19) Dose Rate to Release Rate Ratio Attachment XII or XIII R/hr (B) Attachment XIV or XV Ci/s Release Rate (A)/(B) - 01/sec (C) Wind Speed: MPH x 0.45 = m/sec (D) (X/Q)u from isopleth for 1 mile m-2 X/Q: (E1)+(D) = , __ sec/m3 ( F) Noble gas dose to concentration conversion from Attachment VIII X2= rem /2hr (G) Cij ' C WHOLE BODY DOSE (2 hr.): (F) x (C) x (G) = rem (2 hr) (H) Iodine to noble gas activity ratio (use 0.3 unless measured) (I) Iodine dose to concentration conversion from Attachment VIII rem /2hr 'J) ci/ms
EPP-005 ATTACHMENT III PAGE 2 0F 2 REVISION O OFF-SITE DOSE CALCULATION USING HIGH RANGE MONITORS Time of Trip Current Time Time after Trip Iodine to noble gas dose ration (I) x (J) + (G) (K) CHILD THYROID DOSE: (K) x (H) = at 1 mine (2 hour) rem (X/Q)u at 2 miles (E2) (E2)/(Ei) (L2) 5 miles (D5) (E5)/(E1) (L5) 10 =iles (D10 (E10)/(E1) (L10) DOSE 2 miles (L2) x (H) rem x (K) = ren 5 miles (L5) x (H) rem x (K) = rem 10 miles (L10) x (H) rem x (K) = res
' DHOLE BODY CHILD IHYROID (2 Hour) (2 Hour) lll 1
O
EPP-005 ATTACHMENT IV PAGE 1 0F 1 REVISION O O ACTIVITY RELEASE STATUS l Time: ! Elapsed time since last release calculation sec (A1) hr (A2) Noble Gas Average release rate since last calculation Ci/sec (B1) Activity released since last calculation ( A x B1) C1 (C1) Previous total of noble gas released Ci (D1) Total activity released (C1 4; D1) Ci 4 CURRENT DOSE ELAPSED TIME CURRENT OLD TOTAL TOTAL DISTANCE RATE (rem /hr) (A2) DOSE DOSE DOSE 1 mile X =
+ = rem 2 X = + = rem 5 X = + = rem 10 X = + = rem O Iodine I
Average release rate since last calculation Ci/sec (B2) Activity released since last calculation ( A1 X B2) C1 C Previous total of Iodine released Ci D Total activity released (C2 + D2) C1 CURRENT DOSE ELAPSED TIME CURRENT OLD TOTAL TOTAL DISTANCE RATE (rem /hr) (A2) DOSE DOSE DOSE 1 mile X = + = rem 2 X = + = rem 5 X = + = rem 10 X = + = rem l . C<
,- -w- -
EPP-005 ATTACHMENT V PAGE 1 0F 1 REVISION O
** PROJECTED OFFSITE DOSES **
METER 0 LOGICAL DATA Time: WS: aph WD: to Class: AT SAMPLE DATA Sample Concentrations ( Ci/ml) Source Date Time Number Iodine NG Part. H-3 MONITOR READING Iodine to NG Grab Time Since Inst. Gross BKDG. Het Sample Result Ratio Accident S'c art hr min TWO HOUR DOSE PROJECTION IN REM 1 mi. Whole body (REM /2hr.) 2 mi. 5 mi. 10 mi. 1 mi. Child Thyroid (REM /2hr.) 2 mi. 5 mi. 10 mi. llI ACTIVITY RELEASE STATUS AS OF (TIME): Release Rate (Ci/sec) Total Released (C1) Noble Gas Indine Particulate Tritium CURRENT TOTAL DOSE Whole body (rec) Child Thyroid (rec) 1 mi 2 mi 5 mi 10 mi 1 mi 2 mi 5 mi 10 mi e
EPP_005 ATTACHMENT VI PAGE 1 0F 1 REVISION O F) OUT OF PLANT MONITORING - DISPATCH AND DATA FORM Dispatch Unit Time Location Miles Degrees Co=ments: Report
- Location Confirmation YES/NO Time Rad Level R per hour Air Sa=ple Volume cubic ft. x 28320 = cm3 Particulate net ep:
Particulate Concentration = u C1/cm3 Iodine net cp=(c) Iodine Concentration = pCi/c=3 (A) Iodine dose to concentration conversion ren/2hr from Attachment VIII C1/m> (B) 2 hr. child thyroid dose (A) x (3) rem O \.J
EPP-005 ATTACHME:i? VII PAGE 1 0F 1 REVIS!0!! 0 0FF-SITE DOSE (DOSE RATE) CALCULATION FROM INVIRONME:TAL MONITORI:iG Sample Ti=e Rad level Check Cne: Location __ Iodine Measured Dose res (A) (Dose Rate) or/hr xu at location from isocieth ~ (B) T (A) + (3) = (C) xu fro: isocieth at 1
~ mile (D1)
U- 2 miles (D2) 5 =iles (D5) 10 =iles (D10) Dose (Dose Rate) at 1 =ile = (C) x (D1) = 2 =iles = (C) x (D2) = re: 5 miles = (C) x (D5) = ( r/hr) 10 miles = (C) x (D10) = i e
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/ EPP-005 ATTACHMENT IX PAGE 1 of 1 REVISION O ( ATMOSPHERIC STABILITY CLASSIFICATION h Te=perature Differential (a T) Stability Pasquill AT in *F Classification Categories 10-c0 = 10-35 : Extre=ely Unstable A <-1 71 <-0.36 Moderately Unstable 3 -1 71 to -1 53 -0.S6 to -0 77 Slightly Unstable C -1 52 to -1 35 -0.76 to -0.68 Neutral D -1 34 to -0.45 -0.67 to -0.23 Slightly Stable 2 -0.44 to 1 35 -0.22 to 0.67 Moderately Stable ? 1 36 to 3 60 0.68 to 1.80 Extre ely Stable G >3 60 >1.30 C 9 til
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+ Standard deviation of hori:Ontal vind direction fluctuation over a period of 15 =inutes to 1 hour. (Wind Range divided by 6)
Ref. US:iRC Reg. Guide 1.23, Rev. 1, Se pt . 1080.
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EPP-005 ATTACHMENT XI PAGE 1 of 1 REVISION 0 ( METEOROLOGICAL SECTCR DEFINITION lll Wind Central Direction Value Li=its of Sector Sector (degrees) in Degrees NNE 22 5 11.25 < 1 33 75 NE 45 0 33 75 < 1 56.25 ENE 67 5 56.25 < 1 78 75 7 90.0 78 75 < 1 101.25 ESE 112 5 101.25 < 1 123 75 SZ 135 0 123 75 < 1 146.25 SSE 157 5 146.25 < 1 168 75 , S 180.0 168.75 < $ 191.25 SSW 202 5 191.25 < 1 213 75 SW 225 0 213 75 < 1 236.25 WSW 247 5 236.25 < 1 258.75 W 270.0 258.75 < 1 281.25 O WNW 292 5 281.25 < 1 303 75 NW 315 0 303 75 < 1 326.25 NNW 337 5 326.25 < 1 348 75 N 360.0 348.75 < 1 11.25 CALM Wind speed less than 0.75 mph MISSING Unreliable data O
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EPP-005 ATTACEMENT XVII PAGE 1 0F 3 REVISION 0 Thc Zeicup '..-Turner ':9thod for Determining Atmospheric Stability 0 If both the pri=ary and secondary i! sensors are inoperative and sig=a theta is not available, the Pasquill-Turner methet for defining Fasquill 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 pri=arily upon net radiation and wind speed. Determination of stability cles as a function if wind speed and net radiation is given in Table 1. In this syste=, insolation is estimated by solar altitude and modified for existieg conditicns of total cloud covet and cloud ceiling height. At night estimates of outgoing radiation are made by considering cloud cover. The net radiation index 'i's determined as fo.11ews:
- 1) If the total cloud cover is 10/10 and the ceiling is less than 7000 feet, use net radiation index equal to 0 (whether day or night).
- 2) For nighttime (defined as the period from one hout before sunse.t to one hour after sunrise):
a) If total cloud cover <4/10, use net radiation inder equal to -2. b) If total cloud cover >4/10, use net radiation index equal to -1. gg
- 3) For dayti=e:
a) Determine the insolation class nu=ber as a function of solar altitude from Table 2. b) If cloud cover < 5/10, use the net radiation index corresponding to the insolation class number, c) If cloud cover > 5/10, modify the insolation class number by the following steps: ' i) If ceiling < 7000 feet, subtract 2
- 11) If ceiling > 7000 feet, but < 16,000 feet, subtract 1 111) If total cloud cover is 10/10 and ceiling is >7000 feet, subtract 1 (ce= pare to 1 above) iv) If total cloud cover is not 10/10 and ceiling is > 16,000, assu=e nodifiedclassnu=berequaltoinsolationclassnEmber v) If =adified insolation class number is less than ', let it equal 1 vi, Use the net radiation index corresponding to the =odified insolation class number Thus, it can be seen frc= Table 1 that instability occurs with high positive net h radiation and low wind speeds, stability with negative net radiation and light winds, and neutral conditions with cloudy skies or hign wind speeds.
EPP-005 ATTACHMENT XVII PAGE 2 0F 3 REVISION 0 Calculation of Solar Altitude a = arcsin (sin $ sin? + cos ((H-12 12
) 180*) cos6 cos)]
where 0 = station latitude = 34.3* H = hour o f. day (24 hour clock) . 6 = arctan [ -tan (23.5') cos (360'3o2 (N+10))) , where N = number of days fr.om the beginning of the year i }
~
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EPP-005 ATTACRMENT XVII PAGE 3 0F 3 REVISION 0 llh TABLE 1 STABILITY CLASS AS A FC;CTION OF NET RADIATION AND WIND SPEED Wind Speed
- Net Radiation index
!I- (knots) 4 3 2 1 0 -t -2
.15 0, 1 A A B C D F G
, 3.45 2, 3 A B B . C D F G
, 5.75 4, 5 .
A B C D D E F 6 B B C D D E F 5 7 B B C D D D E
- . 10. 35 8, 9 B C C D D D E
.5 10 C C D D D D E
.65 11 C C D D D D D 13.3 > 12 C D D D D D D O
Table I was developed for wind speed in knots. To convert from knots to ceters per second, cultiply roughly by .5, accurately by .51444. TABLE 2 INSOLATION AS A FC;CTION OF SOLAR ALTITUDE , polar Altitude (a) Insolation Insolation Class Number 60 * < a Strong 4 35' < a < 60* Moderate 3 15' < a e 35
- Slight 2 a < 15 ' Weak 1
- See Page 2 of thia attachment O
.1 SOUTH CAROLINA ELECTRIC AND GAS COMPANY O VIRGIL C. SUMMER NUCLEAR STATION NUCLEAR OPERATIONS L C'_'EA'1 OP'ilAT.0)S COPY No..... 5 75 ; -
EMERGENCY PLAN PROCEDURE EPP-006 EMERGENCY REACTOR COOLANT SAMPLING REVISION O MAY 20, 1981 Ncn-Safety Related Reviewed by: M b ORIG N "0R (of This revision) Date
? CZ Mr. - N Af /
TUALIFIEDREVIE'4ER / Defee Approved: fd PLANT MANAGER
//DW9 Date' O RN EWED EY PSRC'"' Deze 1eeuea: oee 1 - iss,
'k Kb" /
30 8[ Fo rm AP-101 -2, (1/80) CHAIRMAN - _ DAR
EPP-006 I - PAGE i REVISION 0 5/20/81 LIST OF EFFECTIVE PAGES PAGE REVISIO!I t i - O 11 0 I 1 0 2 0 l O i i O
i I j - EPP-006 l Page 11 Revision 0 ' ' 5/20/81 TABLE OF CONTENTS Page j l i i List of Effective Pagen i I : i 1.0 PURPOSE 1 l
2.0 REFERENCES
1 l 30 CONDITIONS AND PREREQUISITES 1 i ! 4.0 PROCEDURES 1 1 i
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EPP-C06 PAGE 1 REVISION O 5/20 /81 1.0 . . m
=U2_:u~m:.
1.1 The purpose of this procedure is to specify those actions necessary to meet the post-accident reactor coolant sampling requirements of NUREG 0737. 2.0 R m= =. _= =. _= .w = -.. v _ a 2.1 NUREG-0737, Sept. 5, 1980. 2.2 Virgil C. Suc=er Nuclear Station Radiation Energency Plan. 23 CEP-902, "Ecergency Reactor Coolant Sampling". 2.4 UUREG-0654, Criteria for Preparation & Evacuation of
. Radiological Emergency Response Plans & Preparedness in Support of Uuclear Power Plants.
30 CONDITIONS AND PREREOUISITES 31 The ceasures for post accident sa:pling corrence at the time that a decision is made by the Shift Supervisor that an accident situation exists and that a s am ple is necessary. 32 This procedure is written assuming the worst situation, i.e., lh the accident occurs on the backshift and there is one chemist on site and no supervision. iith additional personnel and supervisory assistance, analytical and sa pling activities cay be carried out with more than one che ist. Priorities however will retain as stated. 4.0 PROCEDURE 4.1 When an accident situation is declared, the on-shift chemist should proceed as soon as practical to the Control Root. 4.2 When directed by the Shift Supervisor, the chemist will preceed to the radio-chemistry lab and prepare to take the post-ace.!cnt samples in accordance with reference 2 3 He will observe sil applicable radiological precautions as required by reference 2 3 and health physics procedures. 43 From the ti e a decision is cade to sa ple, the chemist has three hours to perfor: radiological, bcron, and das analyses. In drawing and analyzing samples, the following nriorities should be observed. O
1 \ * ^ l EPP-006 PAGE 2 : REVISION O l 5/20/81 l O 431 The first sample taken should be for boron to give the shift supervisor an indication of the reactivity condition of the core. 432 The next sample in priority is the reactor coolant activity sample. This is to detercine the physical condition of the core. Noble gases indicate possible cladding failure, lodines, and cesiu=s indicate high fuel . l temperatures, and other non-volatile isotopea indicate , possible fuel =elting. l 4.4 After the priority samples and analyses of section 4 3 are l completed, the next sample should be for chlorides. A chloride result should be available within 24 hours of the ti=e the initial decision to take a post accident sample was made. 45 Results of all analyses should be-reported by phone to the technical support center or the Control Roo: with written data sheets to follow. NOTE: It is vital that results be channeled ic=ediately to the shift supervisor, who requires knowledge of the Boron concentration and the radioactivity of the fluid. O i i I t r k f I t t I
- - _ _ _ = _ - - _ _ _ _ _ .-- . . . . . . 1.
SOUTR CAROLINA ELECTRIC AND GAS COMPANY O VIRGIL C. SUMMER NUCLEAR STATION i 4 l NUCLEAR OPERATIONS 4 \!LCLEAR OPIRA"ONS i CO PY N o. . . . . . ./.{ M. . . . . . . . . . . Emergency Plan Procedure EPP-007 ENVIRONMENTAL MONITORING , REVISION O MAY 20, 1981 Non-Safety Related i
- O i
Reviewed by: 1, %W , 1 ORIG 3NA90R (of this revision) Date
! /ff2 Bf QUALIFIED REVIEWER /Daye Approved:
h_NTMANAGERYn' PLA
/J/3c/fr Date Date Issued: N O I t' ~
i' RI: V EWED BY 3SRCe*
' " ^'-
O E HAIRMAI/ ray. ///so/s/ D.1TS
' "' )
l i EPP-007
- Page i Revision 0 5/20/81 LIST OF EFFECTIVE PAGES h PAGE REVISION i 0 11' O 1 0 2 0 3 0 4 0 ATTACHITEUTS -
Attachment I O Attachment II . O Attachment III O Attachment IV 0 Attachment V O 0 O
7
! EPP-007 l Page i. j l
! Revisim O t j 5 /20 /81 TABLE OF CONTENTS \ l 1 Page [ l ! List of Effcetive Pages i l 1.0 PURPOSE 1 l t
2.0 REFERENCES
1 j i 30 C0!!DITI0IIS AND PREREQUISITES ~ 1 l l i 4.0 PROCEDURE 2 l i t I j ATTACHMENTS l ATTACHMENT I - Radiological Monitoring Program Local ' Indicator Sample Sites ; i ; i i ATTACHMEliT II - Radiological Monitoring Program Remote i Sample Site l ATTACHMENT III - Miscellaneous E=ergency Environmental Samples j
&W ATTACHMENT IV -
Emergency Environmental TLD Report Form ; I ATTACHMENT V - Emergency Air Monitoring Sample Collection j Sheet ; I l t 5 t O I l 4 I i G ! l i f _ _ J. _
EPP-007 Page 1 Revision .0 5/20/81 O 1.0 PURPOSE 1.1 To provide guidance for the surveying of Environmental Monitoring Stations during an emergency or for post-accident monitoring.
2.0 REFERENCES
2.1 V.C.. Summer Radiation Emergency Plan. 2.2 EPP-004 "Out-of-Plant Radiological Surveying. " 2.3 NUREG 0654 " Criteria for Preparation and Evaluation of Radiological Emergency Response Plans sad Preparedness in Support of Nuclear Power Plants." 2.4 ESP-30, " Environmental Surveillance Procedure Sampler Control". 3.0 CONDITIONS AND PREREQUISITES 3.1- The Shift Supervisor has determined that conditions for a site or General Emergency exists. 3.2 The Technical Support Center, (TSC),/ Emergency Operations Facility (EOF) are activated and have collaborated to determine the g Environmental Monitoring Stations to be serviced, and the safest route of travel. 33 Radiation Monitoring teams have been formed. 3.4 Radio (s) have been obtained and communications established with TSC and/or EOF. NOTE: Communications are to be kept open at all times to ensure surveyors are kept advised of changing conditions. 3.5 'dhen handling Environmental TLD's , take precautions to minimize exposure during tranportation to and/or from Environmental stations. 3.6 off-Site Radiation Monitoring Teams will service Environmental Stations by direction f rom TSC/ECF (as indicated in Attachments I and II). 3.7 Ensure that access gates usei 'n at- are left as found (e.g. open, closed, locked, etc. O
E EPP-007 Page 2 Revision 0 5/20/81 0 4.0 PROCEDURE 4.1 Obtain an Emergency Off-Site Monitoring Kit and any add [tional equipment required. NOTE: Ensure kit seal is unbroken and inspection date is current. 4.2 Obtain vehicle for off-site monitoring from Security if team is dispatched from site. Other designated teams should use assigned vehicles. Also obtain the necessary keys to access gates for the monitored areas. 43 Source check instrumentation prior to leaving to ensure continuous radiation monitoring enroute. 4.4 Environmental TLD Replacement. - 4.4.1 Ensure proper placement of Environmental TLD sticks into designated sampling stations. 4.4.2 When placing TLD's in field stand, align the scribe = arks on the stick with the edges of the hasp. Tighten allen 3 screw only enough to ensure tne stick does not rotate in s-) the hasp. 443 Record date, time, TLD number and any remarks on Attachment.IV. NOTE: To install additional sites, nail hasp on appropriate wooden object with long hinged end down. Using a wood bolt and wrench, secure the TLD stick to the object by bolting hinged end down (only one bolt required) making sure center line of stick is parallel to the ground, perpendicular to the direction of the plant and approximately one meter above the ground. 45 Environ = ental Particulates and Radioiodine Samples 451 Re=ove the previous (sample's) coin envelope from the unit. 452 Note on the envelote the ending date and time, elapsed running time (E.T.), integral flow and initials of collector. 453 Switch off the air sampler. O
EPP-007 Page 3 Revision 0 5/20/81 0 4.5.4 Carefully remove the filter holder face. Hold the coin envelope open below the filter and use forceps or a sharp object to free the sample filter making sure both filter and loose particulate matter on it are transferred to the envelope. 4.5.5 Remove the previous (sample's) cartridge and replace with fresh labeled cartridge. Mark direction of air flow on cartridge. NOTE: Replace charcoal cartridges with AgZe cartridges unless otherwise directed from TSC/ EOF. 4.5.6 Annotate Attachment V with information requested in 4.5.2. 4.5 7 Turn unit on, place a new Gelman glass fiber type E 47 mm filter in the holder and replace the holder face. 4.5.8 Utilizing both watch and "One Cubic Foot" dial of the meter, adjust ths flou to 0.5 - 2.0 CFM. Ideally set flee rate to 1 CFM or the noted value on the attached calibration tag. 4.5 9 Note on a coin envelope, the starting date, time, E.T., ggg integral flow and initials of collector. 4.5.10 Note any sampler malfunction on both the affected sample envelope and Air Sampler Log. Motify the Offsite Radiological Coordinator of sampler failure and repair the unit as soon as practicable. Should the unit be inoperable and be a required sampling location, install a portable RAS-1 Air Sampler. Adjust the flow rate to 30 liters per minute (lcFm = 28.32 Lpm) following step 4.5 7 (with the exception of integral flow). 4.5.11 Return the labeled envelope and cartridge to the designated counting facility for analysis. NOTE: For immediate results of particulate and/or iodine samples, count on the instrument provided in Emergency Kit. Ensure background radiation levels do not interfere with sample analysis. 4.5.12 If placing a new sampler see ESP-30 for details. (Environmental Surveillance Procedure Sampler Control). O
EPP-007 Page 4 Revision 0 5/20/81 0 4.6 'date r Sampling 4.6.1 TSC/ EOF will determine water sampling points and the safest route of travel.
"OTE: The following locations should be ased, as a minimum, for sampling locations:
a) Downstream of Fairfield Pump Storage. b) Parr Hydro Plant c) Broad River, at S.C. Route 213. 4.6.2 Thoroughly rinse the sampling container with water from the source to be sampled. . 4.6.3 Allow water spigots to flush thoroughly, (at least one minute), prior to filling container. 4.6.h Surface watar grab samp1,es are taken by ra.p!dly , submerging the rinsed, uncapped container approximately one foot beneath the surface and retrieving the filled container. O 4.6.5 Label all samples with date, time and location. 4.6.6 Return all samples to designated counting facility for , analysis. 4.7 Miscellaneous Samples. 4.7.1 Take samples per instructions of the Offsite Radiological Monitoring Coordinator and record data on Attachment III. l 9 l
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EPP-007 ATTACHMENT III Page 1 of 1 Revision 0 VIRGIL C. SUMMER STATION MISCELLANEOUS EMERGENCY ENVIRONMENTAL SAMPLES Collector: I Station Taken Type Quantity No. Grab Sample Remarks (Location Date Time Water Other Gallons Liter Pound Code No. 9 O 9
EPP-007 ATTACHMENT IV Page 1 of 1 Revision'0 U VIRGIL C. SUMMER STATION EMERGENCY ENVIRONMENTAL TLD REPORT FORM Collector: Station No. Collected Installed Remarks (Location) TLD No. Date Time TLD no. Date Time O O
*' ~
EPP-007 ATTACHMENT V Pa;;e 1 of 1 Revision 0 O VIRGIL C. SUMMER STATION EMERGENCY AIR MONITORING SAMPLE COLLECTION SHEET Collector: Integrated Gas Reading . Sample Remarks Station No. Removed Installed Removed _ Code No. (Location) Date Time Particulate Particulate Particulate Iodine Io ditie~ Iodine a I I I O
-}.
i C S0 'H CAROLINA ELECTRIC AND GAS COMPANY VIRGIL C. SUMMER NUCLEAR STATION NUCLEAR OPERATIONS NUCI..'A1 DPMATONS COPY No.. . . . . .#~ 7. ......
.F. . . .
EMERGENCY PLAN PROCEDURE EPP-008 i ON-SITE ASSEMBLY 1 REVISION O MAY 20,1981 h Non-Safety Related Reviewed by:
@ i 1 OR' 'IFATOR (of this revision) 1 Date 8
QUALIFIED REVIEWER W > lik4 8/
/ Deyte Approved:
PLANT MANAGER
- Nb Date
? $
h J. EY PSRC.**" Date Issued:~0EC 1 - 199f '-
// Form AP-101-2, (1/80) j l
A CHAIRMAN [C - . f DATE
/
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EPP-008 PAGE i REVISI0tI O 5/20/81 O LIST OF EFFECTIVE PAGES PAGE REVISIO?I i 0 ii 0 1 0 2 0 3 0 4 0 ATTACHMEIITS Attachment I O Attachment II O O O
EPP-008 PAGE 11 REVISION O 5/20/81 k TABL2 0F CONTENTS _ PAGE List Of Effective Pages i l 1.0 PURPOSE 1
2.0 REFERENCES
1 3.0 CONDITIONS AND PREREQUISITES 1 4.0 PROCEDURES 2 ATTACHMENTS AttacPaent I - On-Site Asse=bly Attachment II - Asse=bly Area / Duty Station List r L i
EPP-008 - PAGE 1 REVISION O 5/20/81 1.0 PURPOSE - C To provide guidelines for conducting personnel on-site assembly i verifications durina normal operating hours or during other than normal operating hours, weekends, or holidays. These guidelines are for personnel on-site assembly verifications when immediate site evacuation is not required. - 2.0 EEFERENCES , 2.1 " Virgil C. Summer Nuclear Station Radiation Emergency Plan". 2.2 EPP-011, " Personnel Search and Rescue". 23 SPP-114, " Security Force Responsibilities Duri'ng Emergencies. 2.4 NUREG-0654, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants. 25 EPP-012 "Onsite Personnel Accountability and Evacuation. 30 CONDITIONS AND PREG"C;UISITES ((
- 31 Personnel on site assembly verification will be performed when ordered by the Emergency Director. Dtring normal operating hours personnel are directed to proceed to their designated assembly areas / duty stations. During periods other than normal operating hours, weekends or holidays, personnel on-site assembly verifications shall be conducted as prescribed in paragraph 4.2.
l 32 When personnel are ordered to their assembly area / duty stations, l they should have in their possession the personal effects
- necessary to evacuate to an off-site holding area if so directed.
33 If the personnel on-site assembly verification has not been I completed within a reasonable time due to missing personnel, [ procedure EPP-011, " Personnel Search and Rescue," may be l implement d at the discretion of the ED/IED. 34 Personnel on-site assembly verification will interface with SPP-114 and EPP-012. I 35 Each group's designated Foreman / Supervisor will maintain a i current listing of their personnel and badge numbers per ! Attachment I and report any changes to the Assistant Manager of Support Services. ; i I
,.e- .- - - , . . , - , , . - . _ , - . . , - . - . . --. , - -
.' EPP-008 PAGE 2 REVISION 0 5/20/81 G
4.0 PROCEDURES - 41 Normal operating hours (0800. - 1630 hours daily except weekends and holidays): Personnel on-site assembly verifications will be performed by designated Foreman / Supervisor per Attachment I, after personnel .. are notified to proceed to their assembly areas / duty stations. 4.1.1 The Emergency Director has the overall responsibility for personnel on-site assembly verifications. 4.1.2 The Assistant Manager Support Services will coordinate the overall plant on-site assembly verification and - report same to the Emergency Director. He will also periodically compile personnel information reported to him into a personnel on-site assembly. verification checklist (Attachment I) for each reporting unit to aid in expediting collection and reporting of required information. (List of assembly areas / duty stations are
..ntained in Attachment II).
4.1 3 The following personnel will submit an on-site assembly verification report to the Assistant Manager, Support e7 Services located in the TSC:
\;ij ..
4.131 The Assistant Manager, Technical Support for personnel located in the Technical Support Area of the Technical Support Center (TSC) . 4 1 3 2 The Director of Health Physics for Radiological Assessment personnel. 4.1 3 3 The Supervisor of Operations, in coordination with the Director of Administration, for personnel assigned to the Operations Group and the Operations Support Center (OSC). 4.1 3 4 The Director of Administration for personnel reported assembled in other designated assembly areas. (Contained in Attachment II).
)
I
EPP-008 ' PAGE 3 REVISION O 5/20/81 Upon direction by announcement over the plant paging C 4.1.4 - system and (Fairfield Pump Storage by phone, 345-5830, Microwave 8-3644; or Control Room on back shift, 8-3639) personnel will proceed to their assembly areas or predetermined duty station. All contractor and visitor personnel not permanently assigned to a specific Summer Nuclear Station group will proceed or be escorted through . the guard house to the Q. A./ Security Building. They will remain there until further instructions are received. 4.1.5 Each Foreman / Supervisor will initially report the status of his group to the Director of Administration located in the Operations Support Center, by a co=pleted personnel On-Site Asse=bly Verification checklist (See Attachment I). If the _ station is in " Site E=ergency" or
" General Emergency" the On Site Assembly Verification will be performed per EPP-012; if in " Alert" the completed checklist is required as soon as practicable.
Essential personnel should be identified to support the requirements of the particular emergency as soon as feasible and reported by a second report if possible before evacuation is directed. 4.1.6 The Security organization will obtain a copy of the completed checklists from the. Assistant Manager, Support gs Servic's. (_/ 4.1.7 The Security Shift Leader will compile a list of any . personnel who are unaccounted for by comparing the checklist received to the Security badge accounting i results. Any discrepancies will be noted and reported to the ED/SS.
- 4.2 Other than normal operating hours
i l 4.2.1 The Shift Supervisor has the overall responsibility for
- personnel On-Site Assembly Verification until relieved by
+he ED or his DA.
l l l l i l l l l
,s o EPP-008 PAGE 4 REVISION O 5/20/81 4.2.2 The Security Shift Leader will coordinate personnel -
on-site assembly verification and provide the Shif t . Supervisor with a report of all personnel present within the protected area when directed. The Shift Supervisor will continue to be responsible for. personnel On-Site Assembly Verification until the on-site Emergency Center is activated and he is properly relieved by the ED or his . DA. - 4.2 3 All shift personnel shall report to the Control Room to allow the Shift Supervisor to verify accountability. 4.2.4 All personnel not ass 15 ned to shift work shall report to the area adjacent to the Guard house and service building to allow their supervisor to verify accountability, and forward same to the Security Shift Leader or DA. 43 Persons unaccounted for will be searched for in accordance with EPP-Oll, " Personnel Search and Rescue".
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.. . . .. . . - - ~ .
EPP-008 '. 4 ATTACHMENT I PAGE 1.OF 1
; ' REVISION O ON-SITE ASSEMBLY VERIFICATION CHECKLIST (.
i s DATE TIME LOCATION: (PHONE EXT. -)
, TYPE AND REMARKS-AND/
UNACCOUNTED ESSENTIAL- OR LAST KNOWN BADGE NUMBER NAME PRESENT- FOR LOCATION WORK LOCATION v i i l 1 i f l
. , . . . . - . . . . . . _ = ~ . . _ _ -._.- ,..__ ___ .._ _.._.___ _ . - . _ . . . _ _ , . _ _ . . _ _ _ _ . . _ . . . _ _ , _ _ , . _ _ _ . - _ - . . _ . _ . , .
EPP-008
- ATTACHMENT II PAGE 1 0F 2 REVIS0N O
( ASSEMBLY AREA / DUTY STATION LIST LOCATION COMPOSITION OF GROUP PHONE NUMBER REMARKS is-Control Room Shift Complement ! . QC Office Service Bldg. QC Inspectors Operations Various support units Support plus Supervisory Center (OSC) Personnel I&C Personnel - SCE&G/ I&C Shop Butler Arde Water Treat-Lab - 463'elev. Chemistry Start-Up Start-Up Supervisors Office & Clerical Engineering Engineers, Techs, Area-Serv.Bld Computer Maintenance NUS/ We sting- NUS/ Westinghouse / Welding house Office Supervisor Support Warehouse "C" Naterial Support C'1 Planning / Scheduling Rm Champs / SCI Support Electrical Elec. Maint. - SCE&G/ Shop Harrison Machine Shop Utility Personnel QA Office QA Inspectors [ Office Sect. Service Bldg. Clerical Guardhouse Security Personnel Training Area
. Service Bldg. Training Personnel l' Security Offices Security Personnel l Machine Shop Mech. Maint. - SCE&G l Q. A./ Security Visitors and Non-Building permanently assigned personnel ;
I I i r
EPP-008 ATTACHMENT II i PAGE 2 0F 2 t REVIS0N O ASSEMBLY AREA / DUTY STATION LIST _ {' ! i 4 LOCATION- COMPOSITION OF GROUP PHONE NUMBER REMARKS Hydro Operators, Land Fairfield Department Utility ) Pump Storage iPersonnel k r Tech. Support Area Tech. 3, Support Center Engineers, STA's ) 2 Health Physic Laboratory Rad. Teams, H/P _ Personnel Emer. Ops. Area - Tech Emer. Director Support Personnel Accountability /
~~
Center. Assistant Manager, Support Services j Rad. Assess. Supv. Assistant Manager, Technical Support ({,p Security Supv. Assistant Manager, Maintenance Services , 4 Assistant Manager, Operations i o i . 1
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SOUTH CAROLINA ELECTRIC AND GAS. COMPANY VIRGIL C. SUMMER NUCLEAR STATION NUCLEAR OPERATIONS
. 'N UC_ EAR 0 3 E RA".0 NS COPY No /E7 E -
EMERGENCY PLAN PROCEDURE EPP-009 ON-SITE MEDICAL REVISION 0 MAY 21, 1981 NON-SAFETY RELATED O Reviewed by:
! CnC 1 ORIGIVATOR (of this revision) Date'
\
$W ; / Y/
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/Dats
/
QUALIFIED REVIEWER Approved: h PLANT MANAGER 6 -
//b
' ' Da tre
[i,' t
/ Date Issued: 0.EC1-tesI
. [Cov -
Form AP-101-2, (1/80) CHAIRMAN _ _ - . _ _ . _ DATEf .
EPP-009 ,f PAGE i - REVISION 0 5/21/s1 LIST OF EFFECIIVE PAGES h PAGE REVISION i 0 11 0 1 0 2 0 . 3 0 4 0 ATTACHMENTS Attachment I O Attachment II O O O
l EPP-009 PAGE 11
- REVISION O 5/21/81 h TABLE OF CONTENTS PAGE-List of Effective Paces i 1.0 PURPOSE 1
~
1
2.0 REFERENCES
i 30 CONDITIO!IS ANL ?REREQUISITES 1 1 4.0 PROCEDURES i ATTACHMEITTS l ATTACHMENT I - Indicate Contacinated Areas As To Location, Degree Of Contamination, Decon Effort. ATTACHMENT II - V.C. Summer Station Helicopter Landing Sites. i l O 1 e f l l 9 i i 1
- - , . -w,,._------m-,_-e,.____-__.z-. . - _ , , , . . _ . -
. . - - - - -. .. + - - - . . - --r
EPP-009 , PAGE 1 REVISION O 5/21/91 1.0 PURPOSE lll 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 /7ehicle Decontamination." 23 EPP-002, " Communications and Notifications." 2.4 NUREG-065 4, " Criteria for Preparttion & Evaluation of Radiological Emergency Response Plans & Preparedness in Support of Nuclear Power Plants." 25 EPP-020. " Emergency Personnel Exposure Control." 30 CONDITIONS AND PREREQUISITES 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 llh contaminated, injury should be treated at the 412' elevation of the Control Building (H.P. Lab ar e a) .
32 If the injury does not involve 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. 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 life saving lctions 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. O
EPP-009 PAGE 2 REVISION 0 5/21/81 llg A. A member of the team should contact the control 3' 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 removed to the first aid room for treatment when such a nove 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 Communicator / Interim Emergency Director /ED will notify the Company Physician, as per EPP-002. 4.3 If the report of the First Aid team indicates the persor. must be transported to the hospital, the IED/ED will assure that the following is performed: 4.3 1 The First Aid Team shall: A. Decontaminate the patient to the fullest extent (l) possible, considering the extent of the injuries.
- 1. Where difficulty in decontamination is encountered, wrap the area in a blanket (or equivalent).
- 2. Every effort should be made to reduce the external contamination levels to a non-detectable level.
3 Wrap any individuals who have external contamination in order to prevent the spread of contamination. Take precautions to prevent overheating the individuals due to excessive wrapping. B. Prepare the person for transport as follows:
- 1. Complete the Radiation and Medical Status Record Sheet to accompany patient (see Attachment I).
O l
EPP-009 PAGE 3 REVISION 0 5/21/81
- 2. Notify the Technical Support Center that the (g) individual is ready for transport to the hospital.
3 The TSC should inform First Aid Team where victim is to be picked up by the ambulance. 4.3.2 At the same time that the person is being prepared for transport, the Communicator will: 4.3.2.1 Notify the hospitsl, per EPP-002,
" Communications and Notifications ", so the medical personnel there will have the time to prepare the proper facilities.
4.3 2.2 Request assistance from Ambulance Services, per EPP-002. 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 Ensure that a Health Physics reprecentative or qualified radiation worker accompanies the injured person to the hospital and performs the necessary actions. lll 4.4.2 Direct Security Personnel to meet the ambulance at the site entrance and accompany it to the patient's location. NOTE: If the injury occurred outside of the radiation control area, and no contamination is involved, the Shift Supervisor / Emergency Director may assign any plant personnel to accompany the victim. NOTE: Security shall provide Dosimetry to EMS Staff before entry. 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. 4.5 The person accompanying the injured will: 4.5.1 Ensure that the transporting vehicle uses the appropriate hospital receiving area. 3.5 2 Notify Control Room /TSC of arrival at hospital. O
EPP-009 PAGF 4 REVISION O 5/21/81 () 4.5 3 Assist in the radiological aspects of the treatment as necessary. A. Assist the hoapital staff in the decontaminaticn activities for the hospital receiving area. Ensure all waste products are properly contained for future disposal. 454 If protective plastic has been used in the ambulance, carefully remove and bag it for return to Virgil C. Summer Nuclear Station. 4 5.5 If contaminated, decontaminate himself prior to leaving the hospital. 456 Ensure 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 the hospital facility or the Virgil C. Summer Nuclear Station. C. Collect dosimetry from ambulance attendants and obtain appropriate information. 4.5.7 Keep the Emergency Director / Shift Supervisor informed at all times as pertinent information concerning the patient becomes available. 4.6 If the injured or any of the First Aid Team have been over exposed,'the requirements of EPP-020, " Emergency Personnel Exposure Control", will be met. 4 O
EFF-009
- ANACFD7 I
~
PAGE 1 0F 2 U.VIS10'i. O _
- ndicate qcntaminst'ed Areas As To Icc atien, Ca7:ee of p0_g ; contamination, cecon Effert I , Indicate Iccation of 'a'c'.nds o
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' ~ EPP-009
. ATTACRMEi? I PAGE 2 of 2-I REVISI0li 0 PERSOUNEL COIITAMINATION REPORT NAME OF PERSONS (S) INVOLVED:
DATE: TIME: RWF/SRWP NO.: .
,' LOCATION OF INCIDENT:
SUSPECTED OR KNOWN CAUSE: WERE CORRECT REALTR PRYSICS PRACTICES 3EING FOLLOWED? YES NO PORTION OF BODY CONTAMINATED: 1
, INITIAL READINGS: Fixed: DPM READINGS AFIER DECONTAMINATION: Fixed DPM PERSONITEL I:iJURY INVOLVED: YES N0 i ACTI0ti TAKEN FOR DECONTAMINATION:
i i MEDICAL ACTION TAKEN:
- 30DT 3URDEII ANALYSIS PERFORMED: YES NO L
l RESULtS OF BODY BURDEN ANALYSIS / EXPOSURE ASSIGNED:
- l. CORRECTIVE ACIION TAKEN TC PREVENT REOCCURRE: ICE:
l l l- / , ./ f
,IN}iVIDUAL' S SUPERVISOd DATE HEALIH PHYSICS SUPERVISOR DATE l
EPP-009 ATTACitMENT II, Page 1 of I Revision 0
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) 1 SOUTH CAROLINA ELECTRIC AND GAS COMPANY O VIRGIL C. SUMMER NUCLEAR STATION NUCLEAR OPERATIONS N_ CLEAR 03 ERA 10\S C0 PY No. . . . . . M 7E. . . . . . . . . . . . - EMERGENCY PLAN PROCEDURE , EPP-010 PERSONNEL / VEHICLE DECONTAMINATION , REVISION O MAY 21, 1981 EON-SAFETY RELATED O Ragwedby:
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I EPP-010 FAGE i ' REVISI0ii 0 5/21/e1 LIST OF EFFECTIVE PAGES el i PAGE REVISION i 0 11 0 1 0 2 0 3 0 ATTACHME:ITS Attachment I O Attachment II O i - 0 1 e
EPP-010 PAGE 11 REVISION O 5/21/e1 h TABLE OF CONTENTS PAGE List Of Effe'etive Pages i 1.0 PURPOSE 1 2.0 REFERENCE 1 30 CONDITIONS AND PREREQUISITES 1
- 4.0 PROCEDURES 1 l
l ATTACHMENTS At ts.chment I Attachment II O
EPP-010 PAGE 1 REVISION O 5/21/81 1.0 PURPOSE To provide instructions for the decontamination of personnel and vehicles during emergency conditions.
2.0 REFERENCES
2.1 " Virgil C. Summer Nuclear Station Radiation Emergency Plan. " 2.2 HPP-405, " Personnel Decontamination". 2.3 EPP-012, "Onsite Personnel Accountability and Evacuation.". 2.4 EPP-009, "On-site Medical". 2.5 NUREG-0654, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants. 3.0 CONDITIONS AND PREREQUISITES 3.1 All injuries occurring within the Radiation Control Area will be considered contaminated until monitored and cleared by Health Physics. lll 32 Potentially contaminated vehicles will be monitored and decontaminated on-site unless evacuation to an off-site area is required. '4 hen evacuated to off-site holding areas, nonitoring and decontamination of vehicles will be performed at locations designated by Health Physics. 3.3 All decontamination shall be supervised by Health Physics personnel. 3.4 All personnel and vehicles found to be contaminated will be reported to the Radiological Assessment Supervisor. 4.0 PROCEDURE 4.1 Perconnel Decontamination 4.1.1 The following Radiation / contamination limits shall be utilized: O
EPP-010 PAGE 2 REVISION 0 5/21/81 , ($)
- a. All personnel shall be limited to non-detectable loose surface contamination of less than 100 cpm above background at.1/2 inch using a pancake GM tube (HP-210 probe), with an efficiency greater than or equal to 10% and background less than or equal to 400 cpm.
4.1.2 All personnel who have or are suspected of having internal contamination shall have a whole body count at the earliest possible time. 4.1 3 During emergency conditions, it may become necessary to evacuate contaminated or potentially contaminated personnel. These individuals should be monitored and decontaminated at the designated off-site holding area, if that is their destination. 4.1.4 Personnel decontamination performed inside the plant will be accomplished in the decontamination facilities described in HPP-405 " Personnel Decontamination". 4.1 5 Personnel decontamination to be performed outside the Protected Area may be accomplished by direct HP coverage in the Q.A./ Security Building (whenever possible). All rT waste . generated , both solid and liquid, shall be
\_/ collected for subsequent disposal. Precautions to minimize waste should be used whenever possible.
4.1.6 If personnel decontamination is performed at the offsite holding area, decontamination suppliec located in the Q.A./ Security Building should be utilized. 4.1 7 Complete Attachment I for all contaminated personnel. 4.1.8 Bioassays will be administered, based upon levels of skin . contamination, at the discretion of the Radiological Assessment Supervisor. 4.2 Vehicle Decontamination. 4.2.1 Vehicle monitoring should be performed by Health Physics personnel using the appropriate equipment stored in the emergency kits. 4.2.2 The following limits will be used for unconditional release of vehicles: O
EPP-010 PAGE 3 RE7ISIO:4 0 5/21/81 4.2.2.1 Less than 200 DPi/1CO cn2 E e:a/G anna , Icose surface contamination. 4.2.2.2 Less than 100 cpn at 1/2" using a pancake GII Tube (HP-210 probe). 4.2.3 All vehicles found to be contaminated in excess of the above limits should be decontaminated using the following guidelines. tiOTE: Don appropriate protective clothing prior to decontanination attenpts. 4.2.3.1 Rope and post an area accordingly. 4.2.3.2 Lay out plastic in the roped area and place the vehicle upon the plas. tic. 4.2.3 3 Using the decon supplies in the off-site conitoring kits, decon the vehicle using decon foam and towels or disposable rags. u.2 3.4 Ensure that all contaminated towels and rags are placed in the radioactive trash bags provided in the Energency Kit.
'!CTE: If, after several decon attenpts, the llk contanination levels still do not meet the criteria listed in section 4.2.2, contact the Director of Health Physics or Health Physics Supervisor for further instructions in decontaraination techniques.
4.2.3.5 Complete Attachment II for all contaminated vehicles. O
EPP t- 010 ATTACH?IENT I PAGE 1 0F 2 REVIS_LQLl_ . '
,-- %dic_ste ce=*mi ated Areas As "*o Location, De7:ee of
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EPP-010 ATTACHMENT I PAGE 2 of 2 REVISION O PERSONNEL CC:!TAMIIIATION REPORT h NAME OF PERSO:IS(S) INVOLVED: DATE: TIME: RWP/SRWP NO.: LOCATION OF I:iCIDE!iT: SUSPECTED OR KIIOW:I CAUSE: WERE CORRECT HEALTH PHYSICS PRACTICES BEING FOLLOWED? YES ITO PORTION OF BODY CONTAMINATED: INITIAL READINGS: Fixed:__ DPM READINGS AFTER DECONTAMINATION: Fixed DPM PERSO:iNEL INJURY I:!VOLVED: YES NO ACTIO!i TAKEN FOR DECONTAMINATION: MEDICAL ACTION TAKE:i: BJDY BURDEN ANALYSIS PERFORMED: YES _ NO RESULTl 0F BODY BURDEN A!TALYSIS/ EXPOSURE ASSIGNED: CORRECTIVE ACTIO?i TAKEI TO PREVENT RECCCURRENCE:
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INDIVIDUAL'S SUPERVIdun uATE HEAL 2H PHYSICS SUPERVISCR DATE ggg
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. l I27-010 A::achzen: II
- Pace 1 of 2 7.evisien 1 .
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, .- . VEMICLE MONITORINC INSTRUCTIONS l VEHIC1.E SU AVEY TO?J1 l t
1 . NOTE: Use this for: for centanincted vehicles caly. I . Cuner's Nace I.ieense fo. l . T i i
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EPP-010 ATTACHME:iT II PAGE 2 of 2 REVISIO:I O Veli!CLE SURVEY RECORD NOTE: Indicate vehicles needing decontamination. Survey Survey License State Results License State Results i O Instrumentation Used Survey Completed by Date s Re'tiewed by Date 9 I
9 SOUTH CAROLINA ELECTRIC AND GAS COMPANY VIRGIL C. SUMMER NUCLEAR STATION NUCLEAR OPERATIONS
,0 CLEAR OPi?K ONS COPY No. . . . . . g g g. . . . . . . . . . . . . .
EMERGENCY PLAN PROCEDURE EPP-011 PERSONNEL SEARCH AND RESCUE REVISION O MAY 21, 1981 NON-SAFETY RELATED ( O Reviewed by:
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EPP-011 PAGE i REVISION O 5/21/81 LIST OF EFFECTIVE PAGES PAGE REVISION i 0 11 0 1 0 2 0 3 0 4 0 l l l ATTACHMENTS l Attachment I O Attachment II 0 9 O 4
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- EPP-011
- PAGE 11 i REVISION O j
S/21/e1 i 1
$ TABLE OF CONTENTS !
i PAGE ! List Of Effective Pages i ' j 1.0 PURPOSE 1 . 2.0 REFERENCE 1 8 ll 30 CONDITIONS AND PREREQUISITES 1 i
- 4.0 PROCEDURES 1
( ATTACHMENTS Attachment I - Plant Area for Search and Rescue + Attachment II - Search Preplans for Auxiliary Building, Reactor Building and Fuel Handling Building, i 4 e ; v 't i . t 4 ..
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EPP-011 PAGE 1 REVISION O 5/21/81 1.0 PURPOSE gl To provide guidelines for performing a search and rescue operation to find rissing individuals. ; 1
2.0 REFERENCES
2.1 " Virgil C. C amer "uclear Station Radiation 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-009, "Cn-Site Medical". 2.4 EPP-020, " Emergency Personnel Exposure Control". 25 EPP-008, "Onsite Asse bly" 2.6 .EPP-012, "Onsite Personnel Accountability and Evacuation" 30 CONDITIONS AND PREREQUISITES l 31 Personnel accourtability has been performed and it has been determined that a person on-site =ay be missing. lll 32 At least one member of the Search and Rescue Tean will be qualified in Health Physics monitoring techniques. 33 If necessary, the me bers of the Search and Rescue Tea =ay be authorized by the P=ergency Director to receive 100 re to save the life of the =issing individual (s). 4.0 PROCEDURE 4.1 When the Personnel Accountability Verification has been completed and it is determined that one or more individuals are unaccounted for, the ED/SS shall: 4.1.1 Make the following announcement over the plant paging syste:: Attention, tne following personnel report your location to the Control Roc =. [ Names , ,J. (Repeat this message) O
EPP-011 PAGE 2 - ., REVISION O 5/21/81 ( NOTE: If Security has already made this announcement in accordance with T.fP-012, the ED/S3 may elect to skip steps 4 1.1 and 4 1.2. 4.1.2 If after atstt l'ive (5) minutes the individual (s) are still unaccounted for, contact the individual ( s) supervisor in an attempt to determine the general location of the Individual (s). 4.1 3 Assemble ( 9earch end Pescue Tess that should consist of pereonnel from the foll 3winC ;<0ups: (as available) A. Operetions B. Maintenance C. Health Pwysics D. Security Force NOTE: At least one team member should have current certification in Multi-Media First Aid as a minimum. 4.1.4 The team will be outfitted with necessary protective clothing, monitoring instruments, and a portable radio. O 415 Using coordinates gained from implementation of EPP-008, the team will be provided with the folleving information as available: A. Plant conditions that may affect the rescue effort. B. The name, description, and affiliation of the missing person. C. The last known location.
- 1) Check with Security for following information:
a) Any keys checked out to individual. b) Door the victim last went through using card reader.
- 2) Check with Health Physics for any keys checked out to victim.
- 3) Check Control Room key logs for any keys checked out to victim.
O
EPP-011 PAGE 3 REVISION O 5/21 /81 D. The job last being perforced by the person. lll 4.1.6 Eased on the information provided in step 4.1 5 above, the Shift Supervisor assisted by the designated team leader shall plan the routes to be followed with consideration of the ALARA prograr. The te am leade r, as a designee of the shift supervisor, will be responsible for ensuring that: A. A thorough search of each area is conducted using Attach =ents I and II.
- 3. The search and rescue team stays together and conducts the search as a team.
C. Attach =ent I is signed off as each area is searched. 4.1.7 The search and rescue team will: A. Obtain floor plans for building being searched and determino the best route to cost probable location. Obtain any necessary keys. NOTE: The team leader will be assigned keys should certain suspected areas be locked, and need searching.
- 3. Check with Health Physics for route ecproval or codification for radiological reascns.
lll C. Search most probable area first using infor ation supplied in 4.1.5 D. Inform Shift Supervisor when each elevation is thoroughly searched. The Shift Supervisor will direct the search and rescue team to the next area to be searched and assign further search tears as needed. 4.1.8 As soon as victic is found: A. Assess condition of victic and admini.ste r any necessary first-aid. B. Monitor victim for contamination and determine actions necessary to remove victic from the area. C. Inform Shift Supervisor / emergency director of:
- 1. Identity of victic.
9
EPP-011 ' PAGE 4 REVISIO:I O 5/21/81 ( 2. Physical condition of victic. 3 Requirements for renoval of victic from the area. D. Recove victic fro = area as soon as possible. 4.2 The Shift Supervisor will ensure that back-up personnel are . standing by to assist as needed. 43 The search and rescue team will report all data to the ED/ Shift Supervisor as it is received and based upon the condition of the individual, reco=cend initiation, if required, of one of the following Emergency Plan procedures: A. EPP-009, on-Site Medical
- 3. EPP-020, E=ergency Personnel Eiposure Control 44 After the missing individual or individuals has/have been found and safely recoved from the hasardous area, notify the ED/ Shift i Supervisor as to the current status and report for debriefing when the Shift Supervisor authorizes termination of the search and rescue team assign =ent.
() I l () I
EPP-011 ATTACHME!iT I PAGE 1 0F 2 REVISIOi 0 PLA!!T AREAS FOR SEARCH A!!D RESCUE BUILDI!!r, LEVEL II U "'I A L
- Auxiliary 374' 338' to 397' 412' 436' l
463' 485' Stairwells Fuel Handling Euilding 412' h36' 463' Stairwells Control Puilding 412' h 425' 436' 448' 463' 482' Stairwells Intermediate Building 412' 436' 463' O l 1
EPP-011 ATTACHI4EtiT I PAGE 2 0F 2 REVISIO!I O fs PLAliT AREAS FOR SEARCH AliD RESCUE BUILDIIIG LEVEL INITIAL Stairwells Turbine Building 412' 436' 463' Stairwells Service Building 436' 448' Stairwells Diesel Generator Eu11 ding 427' 436' Water Testing Area 7 V Service Water Intake Structure Others I \ '\_)
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SOUTH CAROLINA ELECTRIC AND GAS COMPANY O VIhGIL C. SUMMER NUCLEAR STATION _ NUCLEAR OPERATIONS MJCMA1 OPE 7K10XS . j COPY No,,,,,,g77
! EMERGENCY PLAN PROCEDURE
^
EPP-012 ONSITE PERSONNEL ACCOUNTABILITY AND EVACUATION REVISION O - MAY 21, 1981 NON-SAFETY RELATED i O-l j-Rev ewed-by: l
< O'RE . 50 $f Ltate /
OR)GII ATOR (cf th'is -revision) b V W' //h0,l2/
/
QUALIFIED REVIEWEE 'Dete Approved: PLANT MANAGER
&1= ///3O/q Datd REV EWED BY PSRC'#" Date Issued: REC 1 - 1981
' 71 ' - f SO f Form AP-101-2, (1/80)
O CHAIRMAN DATE
EPP-012 ** . PAGE i REVISION O 5/21/81 LIST OF EFFECTIVE PAGES g Page Revisior 1 0 L 11 0 1 0 2 0 3 0
- 4 0 5 0 6 0-ATTACHMENTS Attachment I O Attachment II O O
i l 1 l
EPP-012 PAGE ii REVISION 0 5/21/s1 1 {1 TABLE OF CONTENTS - t 2. age _ o List of Effective Pages i 1.0 PURPOSE 1
2.0 REFERENCES
1 d- = 30 CONDITIONS AND PREREQUISITES 1 4.0 PROCEDURES 2 l . ATTACHMENTS Attachment I - Evacuation Routes Attachment II.- On-Site Assembly Verification Checklist
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EPP-012 PAGE 1 REVISION O 4 5/21/81 1.0 PURPOSE (- t 1.1 To describe the actions to be taken in the event that the evacuation of personnel, either in a specific area of the plant or the entire plant, is required.
2.0 REFERENCES
s 2.1 " Virgil C. Summer Nuclear Station Radiation Emergency Plan" 2.2 EPP-DOS, "On-Site Assembly Verification" ! q 23 EPP-010, " Personnel / Vehicle Decontamination" , 2.4 EPP-011, "Perconnel Search and Rescue" 25 SPP-114, " Security Responsibilities During Emergencies". 2.6 SPP-405, " Security Force Responsibilities for Emergencies During Construction" 2.7 NUREG-0654, Criteria for Preparation & Evaluation of Radiological E=ergency Response Plans & Preparedness in Support of Nuclear Power Plants (~ u 30 CONDITIONS AND PREREQUISITES - 31 A specific area within the plant will be evacuated under the following conditions:
- a. Confir=ed report of-a significant radioactive spill in a work area. .
- b. Confirmed report of an unexpected increase in the level of radiation or airborne activity in a work area.
1 . . c. One or = ore area radiation monitors. in a single building
- reach their alert setpoint.
! d. Or as designated by the Shift Supervisor / Emergency Director. J 4 32 All non-essential personnel will be evacuated from the plant i site under the following conditions:
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EPP-012 PAGE 2 REVISION O
- a. Site Emergency
- b. General . Emergency -
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- c. AsdirectedbytheShiftSupervisor/EmergencyDirector 33 Sounding of the Reactor Building Evacuation Alarm will be cause ,
to evacuate the Reactor Building. The Reactor Building Evacuation Alarm will sound:
- a. Automatically - by source range (N-31 and N-32) nuclear instrumentation.
- b. Manually - by the reactor building evacuation button located in the control room.
3.4 Evacuaticn signs have been placed throughout the plant. Red signs have been placed in the Radiation Control Area and direct personnel to the 412' elevation for personnel decontamination procedures implementation if applicable. Green signs have been placed throughout the rest of the plant and direct personnel out of the Protected Area by the way of the Guard House. 4.0 PROCEDURES
'41 Evacuation of Personnel from a Specific Area within the Plant. .
4.1.1.a When personnel become aware that the conditions outlined in Section 3 1 exist in their area or an announcement of the plant paging system _ instructs them to evacuate the area they are in, they shall immediately proceed to a location away from the affected area. 4.1.1.b The personnel shall remain together as a group and contact the control room for accountability. The Shift Supervisor will be notified of the names of any individuals thought to still be in this area. 4.1.1. c The area will be searched for possible remaining personnel. Results will be reported to the Shift Supervisor. (
EPP-012 PAGE 3 REVISION O 5/21/81 Upon direction by announcement over the. plant C' 4.1.1.d - paging system and Fairfield Pump Storage by l phone .. >, microwave - ; or Control Room on back shift, -
, personnel will proceed to their assembly areas or predetermined duty station. All contractor and - visitor personnel not permanently assigned to a specific Summer Nuclear Station group, will -
proceed or be escorted through the guard house to the Q.A. Security Building. They will remain there until further instructions are-received. NOTE: "Onsite Assembly Verification" EPP-008 may be initiated at the discretion of the Shift Supervisor /ED. 4.1.2 Personnel who have evacuated from the affected area shall remain in the location evacuated to until monitored for. loose surface contamination or directed.otherwise by health physics personnel. Personnel decontamination as per EPP-010, " Personnel / Vehicle Decontamination" will be ! . performed as required. 4.2 Evacuation of Personnel from the Reactor Building. 4.2.1 Upon sounding of the Reactor Building Evacuation Alarm, (; all personnel will evacuate the Reactor Building and will go to the access control point located at the 412' . , elevation of the Control Building following red arrows. NOTE: Follow normal E.P. procedures upon exit of the "RCZ". 4.2.2 Following area evacuation, the Shift Supervisor will notify the Emergency Director of the circumstances that ccused the sounding of the Reactor Building Evacuation Alarm. 4.2 3 Personnel who have evacuated the 3eretor Building will be monitored for loose surface contamication, as necessary. Decontamination procedures will be instituted, as required, per EPP-010. Radiation exposure will be determined and evaluated by the reading of pocket dosimeters and TLD's, if necessary. NOTE: Sections 4 3 and 4.4 or 4 5 are to be performed simultaneously. 43 Personnel accountability when evacuation of non-eesential ' personnel from the site is required. 1
-, - , . . . - --e,-%-, - - , . - - - - - - - , - . - - - , - . - - - - - - - , - - -
EPP-092 PAGE 4 RE. VISION O 5/21/81 (~ t 431 After notification that a site evacuation is required, the following shall be performed.
~
4 3 1.a If not already on station, all essential personnel shall report to their assigned duty ~ stations. 4 3 1.b All non-essential personnel shall exit the plant thru the guard house, using normal exiting routine. 4 3 1.c Personnel working in the Radiation Control Area shall proceed to the 412' elev. of the Control Building for monitoring prior to proceeding to either a or b above. 432 Accountability for all personnel shall'be performed by security at the guard house in the following manner: 4 3 2.a The Shift Supervisor, Operations Support Center Supervisor and Technical Support Center Supervisor shall account for the personnel in their respective areas and report to the guard house those personnel present per Attachment II. 4 3 2.b Security personnel in the guard house will ("- verify by badge count that all personnel other than the essential hcVe left the station. 4 3 2.c Security will report any suspected missing personnel to the ED/SS. _ 4 3 2.d Suspected missing personnel shall be paged from the guardhouse.
" Attention, the following personnel report your location to Security, (Names , , ) for accountability (Repeat this message) 4 3 2.e If after waiting for 5 minutes the suspected -
missing personnel have not reported to the guard house the SS/E.D. shall be notified that these individuals cannot be accounted for. 4 3 2.f At the direction of the ED/SS EPP-011,
" Personnel Search and Rescue" shall be implemented.
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EPP-012 PAGE 5 REVISION O 5/21/81 4.4 Evacuation of Non-Essential Personnel From the Site to.their _ private Residence. (At the discretion of the E.D./SS'this should include personnel at Fairfield Pumped Storage Facility). The Emergency Director / Shift Supervisor shall instruct all , non-essential personnel to evacuate to their private residences by making the following announcement on the plant page.
"All Non-Essential Personnel Evacuate the station. Proceed to your private residence and avait further instructions".
REPEAT THE AE0VE INSTRUCTION. NOTE: Under certain conditions it may be necessary for personnel to evacuate to predesignated offsite holding l areas i.e.
- a. potential personnel contamination
- b. need for additional personnel on short. notice
- c. radiation exposure considerations 45 Evacuation of Non-Essential Person'nel to Offsite Holding Areas (See Attachment I area map).
(At the discretion of the E.D./SS this should include personnel at Fairfield Pumped Storatge Facility). 451 The Emergency Director / Shift Supervisor shall determine which holding Area to evacuate to based on a review of , j prevailing wind data. 452 The Emergency Director / Shift Supervisor shall instruct all non-essential personnel to evacuate to the desired Holding Area by making the following announcement. 4.5.2.a For the south holding area "All Non-Essential Personnel Evacuate to Parr Steam Plant and await further instructions". Repeat the above instruction. t I I
EPP-012 PAGE 6
, REVISION O 5/21/81 C- 4 5 2.b For the north holding area -
"All Non-Essential Personnel Evacuate to the Monticello Reservoir Recreational Facility and await further instructions".
Repeat the above instruction. . 4.6 General guidance for conduct of evacuation. 4.6.1 Non-essential personnel will proceed through the Guard House, leave their security badges, be checked for contamination and further proceed to the off-site holding-area or private residence by vehicles. (Unless otherwise directed in a drill). Personnel proceeding to an offsite holding area must keep their TID and do.simeter unless otherwise directed by HP or Security. 4.6.2 The Security Shift Leader will ensure all non-essential-personnel have exited the Guard House and all essential personnel have been accounted for within 30 minutes or will report the situation to the Shift Supervisor or Emergency Director who will initiate EPP-011, " Personnel Search and Rescue". (] 4.6.3 The Emergency Director will ensure notification of the personnel at the Fairfield Pumped Storage Facility (Phone n ~r.1__ . , SG , o r -
-=) is performed and they are instructed to take the same actions as other non-essential personnel.
4.6.4 The Emergency director will ensure that a member (s) from _ the security force surveys the area within the exclusion area for personc. He will also ensure that members of-
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radiation montoring teams that are sent out to do surveys are instructed to observe the area for personnel. 4.6.5 In the event of evacuation to an offsite holding area, a senior supervisor shall be assigned by the E.D. or S.S. to maintain communications with-the site and establish ~ control at the'offsite holding area if activated. 4.6.6 The Emergency Director will ensure that a person (s) qualified in personnel monitoring and decontamination is sent to the designated off-site holding area. 4.6.7 The Emergency Director will ensure that the Fairfield County Emergency Services Dispatcher is notified to assist in ' decontamination of vehicles and personnel as necessary. l .
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. . . . . . EPP-012 ATTACHMENT II PAGE 1 0F 1 REVISION O ON-SITE ASSEMBLY VERIFICATION CHECKLIST DATE TIME
-LOCATION: (PHONE EXT. )
TYPE add REMARKS-AND/ I BADGE UNACCOUNTED ESSENTIAL- OR LAST KNOWN NUMBER NAME PRESENT FOR LOCATION WORK LOCATION 1 i l C M a
SOUTH CAROLINA ELECTRIC AND GAS COMPA!IY VIRGIL C. SUMMER NUCLFAR STATION NUCLEAR OPERATIONS TUCL_ EAR OPERA 10hS COPY No. . . . . Af.7/~ . . . . , , , , , ,, , , EMERGENCY PLAN PROCEDURE EPP-013 FIRE EMERGENCY REVISION 0 MAY 22, 1981 O NOII-SAFETY PELATED Rev' M d ,
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~ ,P % w OF GIN iTOR (or'this revision)
//'Date v J'/
A ' Nf / " 2Y/ / QUALIFIED REVIEWER e
/D Approved:
( PLANT MANAGER
///30/fy
' Dat'e 7 Date Issued: DEC 1 - 1981 3 7';,r --* - - -- ,
7n, jp.yp Porm AP-101-2 (1/80) L '. 1. . . __ . s _ , , j 'y O hli?K CHAIRMAN lll3o(8[ r,q
EPP-013 - PAGE i REVISIOf1 0 5/22/81 LIST OF EFFECTIVE PAGES - PAGE REVISION i 0 11 0 1 0 2 0 3 0 4 0 5 0 6 0 7 0 8 0 ATTACIIME!!TS g Attachment I O l l l O
. EPP-013 PAGE 11 REVISION ~0 -
5/22/81 TABLE OF CONTENTS _ PAGE. List of Effective Pages - 1' 1.0 PURPOSE 1
2.0 REFERENCES
1 3.0 CONDITIONS AND PREREQUISITES 1 4.0 PROCEDURES 1 ATTACHMENTS Attachment I
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EPP-013 PAGE 1 REVISION O 5/22/81 PURPOSE 1.0 { To provide guidelines for the prompt and efficient handling Of a fire emergency.
2.0 REFERENCES
2.1 " Virgil C. Summer Nuclear Station Radiation Emergency Plan" - 2.2 " Virgil C. Summer Fire Protection Program Plan" 2.3 AP-1401, " Fire Protection Program" 2.4 " Fire Preplans" 2.5 FPP-002, " Fire Report" 2.6 AP-1502, "NRC Report Preparation" 2.7 EPP-010, " Personnel / Vehicle Decontamination" 2.8 EPP-009, "onsite Medical" . 29 EPP-020, "E=ergency Personnel Exposure Control" 2.l'0 NuReg 0654, Criteria for Preparation & Evaluation of Radiological Emergency Response Plans & Preparednee-o in Support (~ of Nuclear Power Plants 2.11 " Security Safeguards Contingency Plan" 30 CONDITIONS AND PREREQUISITES 3.1 This procedure is to be used whenever a potentially hazardous fire has been discovered or the Emergency Plan has been activated for a fire emergency. Attachment I provides a Flo~w diagram related to Implementation of Procedure. 4.0 PROCEDURE 4.1 The individual at V. C. Summer Nuclear Station discovering the fire shall: 4.1.1 Contact the control room by emergency number 'or plant Gai-tronics and report the fire by stating the location, class and approximate size of the fire. (
EPP-013 PAGE 2 REVISION 0 5/22/81 . ( 4.1.2 Unless undue personal risk is apparent or doubt exists on ability to properly use extinguishers, attempt to control _ and/or extinguish the fire using fire extinguishers appropriate for the class of fire. 4.1.3 Remain in the vicinity at a safe distance until arrival of the Fire Brigade and inform the Fire Brigade of the - circumstances. 4.2 The individual at the Fairfield Pumped Storage Facility discovering the fire shall: 4.2.1 Contact the shift supervisor and/or control room by Emergency Number .
.or normal telephone, and report the fire and the need for outside assistance. The individual will also state the location and size of the fire.
4.2.2 Unless undue personal risk is apparent or doubt exists on ability to properly use extinguishers, attempt to extinguish the fire using fire extinguishers, and await the arrival of -outside ass'istance. 4.3 Persons within an area where fire occurs shall ensure 4.1 or 4.2 are accomplished, evacuate the immediate fire area to the nearest safe distance and comply with further authorized e instructions as may be given during the fire emergency. If the (' fire is at the V. C. Summer Station within the radiation control area, persons will comply with health physics procedures for exit from su'ch areas unless conditions warrant immediate evacuation. 4.3.1 Upon direction by announcement over the plant paging system and (Fairfield -Pump Storage by phone, -
, Microwave ^ . -;
or Control Room on back shift, - ) personnel will proceed to their assembly areas or predetermined duty station. All contractor and visitor personnel not permanently assigned to a specific Summer Nuclear Station group will proceed or be escorted through the Guard House to the Q. A./ Security Building. They will remain there until further instructions are received. 4.4 The Control Room Operator, upon receipt of a report of fire or fire alarm annunciation, sh&11: 4.4.1 Notify the Shift Supervisor or Control Room Foreman of the fire report or Integrated Fire and Security System Alarm.
k EPP-013 PAGE 3-REVISION 0 5/22/81 4.5 The Shift Supervisor / control room foreman snall ensure that: ( i j 4. 5 .'l If the fire is at the Summer Station: A. The following announcemeit shall be made over the plant I paging system:
! . Attention all personnel, there is a (state condition as '
- known) fire (or smoke) in (state room, elevation, and building). Personnel in the vicinity of (state room, elevation, and building)should leave this area.
l B. The fire alarm is soraded. NOTE: Repeat steps A & B above. i
;_ C. Notify the duty Security Shift Leader of the fire'and
' ensure Security support.and assistance have been initiated for the fire response. t-D. Ensure the plant is in a safe condition commensurate ! with the real or potential consequences of the fire. i E. Provide general direction at the fire location and/or l support to the Fire Brigade Team Leader. 7 NOTE: Support to the fire brigade may include radiation monitoring, first aid, evacuation, and assembling additional Fire Brigade Teams, etc. Appropriate health 4 physics and emergency plan procedures should be used as
- warranted by the circumstances.
F. Determine the Emergency Action Level (EAL)
- represented by the fire and advise the Emergency l Director of the EAL and corresponding E=ergency
( classification, e.g., unusual event, alert, site _ emergency, or general emergency. NOTE: The corresponding fire preplan identifies the safety j related equipment which may be affected by the fire. - G. If offsite assistance is required, example:
; -(a) Safety Related Equipment is jeopardized.
(b) Fire is in excess of Fire Brigade Capabilities l (c) Fire is located outside of perimeter fence, i notify the fire department. Phone: s.. (Fairfield County Dispatcher) Give the following information:
EPP-013 PAGE 4 REVISION O 5/22/81 b This is Virgil C. Summer Station, (This is a drill , _ l This is not a drill .) We request fire fighting assistance at our facility. The fire trucks must assemble at the main gate, and await further instruc-tions from Security. H. Upon extinguishment of the fire, direct necessary
- recovery to normal plant operation giving consideration to the following:
- 1. Need for fire watches as required by Technical Specifications while fire detection and suppression systems are out of service.
- 2. Restoring fire detection and fire suppression systems to normal operational alignment in accordance with governing System Operating Procedures.
NOTE: Maintenance may be required prior to resetting fire suppression systems. See 4.8.5.e of this procedure. 3 Initiating Licensee Event Report if required by AP-1502, NRC Report Preparation. ({; 4.5.2 If the fire is at the Fairfield Pumped Storage Facility: A. Notify offsite fire hssistance as follows: Phone Give the following information: (Fairfield County Dispatcher) This is Virgil C. Summer Nuclear Station, (this is a drill , this is not a drill .) We request fire fighting assistance at the Fairfield Pump Storage Facility. B. Notify duty security shift leader of fire and en'sure security support and assistance has been initiated for the fire response. 4.6 The Emergency Director shall: 4.6.1 Activate provisions of'th'e Emergency Plan consistent with the Emergency Classification of the fire. 4.6.2 Ensure notification of NRC I&E Regional Office is accomplished, if required. 4.7 The Fire Brigade shall: 4.7.1 Assemble at one of the two inplant fire stations or report directly to the announced fire scene dependent on the location of the fire, and watch station assignment.
EPP-013 - PAGE 5 REVISION 0 5/22/81 A. Fire Brigade Leader: Respond directly to the scene (' of the fire. B. Fire Brigade Members:
- 1. The Watchstander whose Watch-Station is closest t.o the reported fire shall respond directly to
, the scene of the fire.
- 2. All other on shift Fire Brigade Members will report to one of the two assembly points dependent upon the location of the fire.
Assembly Points Responding For all other Fire Location Aux. Ooerator FB members Aux. bldg., West Penetration, Auxiliary 412' Level Druming Area, Building Control Bldg. Hot Machine Shop, Fuel Edl. Aux. Operator Southeast Stairwell Bldg, Reactor Bldg. Intermediate 436' Level Intermediate b1dg, Building Turbine Bldg. East Penetration Aux. Operator West End Diesel Generator bldg. Service water & circulating wat'er pump house, warehouse (v Turbine building, Service Turbine bldg. 436' Level bldg. Transformer areas Aux. Operctor Turbine Bldg. Water Treatment Plant West End Control b1dg. Operator as 412' Level Control assigned building, Southeast Stairwell Outside of perimeter fence Aux. Operator 436' Level. Turbine As directed Bldg. West End By Fire Brigade Leader . 4.7.2 Those personnel reporting to the assembly area will don full fire protection and self-contained breathing apparatus, unless otherwise directed by the fire Brigade Team Leader, or Control Room and standby for further directions. A set of fire preplans shall be taken to the scene, if applicable, and when requested. (
EPP-013 PAGE 6 REVISION O 5/22/81 ( 4.7.3 Under the direction of the Fire Brigade Team Leader extinguish the fire using the following guidelines. - A. Use the fire preplan appropriate to the room for basic information on the fire hazards, room contents, and fire fighting techniques, if applicable. B. Observe activation of automatic suppression systems ~ where installed. C. If necessary, manually activte the automatic suppression system. D. Conduct fire fighting in two person teams as directed by the Fire Brigade Team Leader. 4.8 The Fire Brigade Team Leader shall: 4.8.1 Establish a Fire Fighting Command Fost. 4.8.2 Direct the fire fighting effort. . 4.8.3 Advise the Shift Supervisor of the fire conditions. .This should be done upon arrival at the scene and at intervals during the fire emergency as appropriate to the 7- circumstances. (
'~
4.8.4 Request from the Shift Supervisor necessary support such as radiation monitoring, first aid, or offsite fire companies. 4.8.5 coordinate support by offsite fire companies appropriate to the circumstances. NOTE: The Fire Brigade Team Leader directs, in co-ordination with the Shift Supervisor, the activities of responding fire companies by direct communications with the Fire Chief. The Fire Brigade Team Leader keeps the Shift Supervisor apprised throughout the fire emergency, informs the responding Fire Chief of circumstances, and assigns firefighting objectives to the Fire Chief. Fire command of responding fire companies is provided by the Fire Chief in Charge subject to directions, restrictions and objectives assigned by the Shift Supervisor or Fire Brigade Team leader. 4.8.6 The Fire Brigade Team Leader should ensure the following actions are taken upon extinguishment of the fire: A. Notify the Shift Supervisor.
-_________.m_ _ _ . . _ _ _ . _ _ . _ _ . - m .___ _.m___. __.__-._.._m __.____.._.m_ . . - . _ _ _ _ _
EPP-013
- PAGE 7 REVISION O 5/22/81 B. Secure fire suppression systems if activated by /
closing the supply valve (s). _ NOTE: Refer to " Fire Preplan" for valve location. C. Request the Shift Supervisor to assign a Fire Watch if there is potential for reflash or reignition. D. Direct Fire Bridgade members' activities with respect - to' restoring fire fighting equipment. E. Initiate necessary Maintenance Work Requests to restore housekeeping conditions and fire suppression systems. For fire suppression systens, Maintenance Work Requests should require replacement or recharge as necessary fusible links, portable fire extinguishers, halon and CO2 systems. F. Prepare a Fire Report in accordance with FPP-002,
" Fire Report".
4.9 The Fairfield County Fire Services shall: 4.9.1 Report to the designated staging area located at the main gate next to the guard house. The chief in charge will report to Security. ,. I 4.9.2 Receive instructions from the Security Force which ('~ include current status of fire if known and location to meet with the Fire Brigade Team Leader. 493 If applicable receive personnel dosimetry equipment necessary for the location of the fire. . 1 4.9.4 Conduct fire fighting in coordination with the Fire Brigade Team Leader, and Shif t Supervisor. 4.10 The Security Force shall: 4.10.1 If the fire is at Summer Station: As Implement requirements of Security Safeguard Contingencies Plan. B. When directed by the Fire Brigade Team Leader or Shift Supervisor, admit responding.offsite fire companies to the protected area and perform the following:
- 1. Ensure vehicle is not under duress, and that all responding personnel are members of the fire company. . (
EPP-013 PAGE 8 REVISION 0 5/22/81 1
- 2. Distribute dosimetry devices assigned for
(- this purpose. . 3 Escort the offsite fire companies within the protected area.
- 4. Escort the Fire Chief of offsite fire companies I ta the Fire Brigade Team Leader. -
5 Maintain the staging area for additional fire l companier. The staging area will be established I so as not te interfere with ingress & egress from the station, but will be such that entry into the l facility, if necessary, will not be impaired.
- 6. Act as liaison between the Fire. Brigade Team Leader and the staging area.
- 7. Prior to permitting offsite fire companies to exit the protected area, ensure that requirements of references 2.7 and 2.9 have been accomplished.
4.10.2 If the fire is located at the Fairfield Pumped Storage Facility: A. , W.it responding offsite fire companies to the k- Fairfield Pumped Storage Facility. B. Provide security support as applicable during the emergency condition. C. Establish a staging area for additional fire companies. The staging area will be established so as not to interfere with evacuation routes, but will be such that entry into the facility, if necessary will not be impaired. ., D. Act as Liaison between Fairfield Pumped Storage Personnel and the staging area. 4._. The Health Physics group shall: A. Log persons, their assigned dosimetry identification, and vehicles, per reference 2.9 B. Collect dosimetry devices. C. Ensure radiation monitoring of persons and, survey of vehicles and equipment are taken.
r . . O i EPP-013
^
Ciscover / Attachment I Fire Alarm Fire Page 1 of 1 Annunciation Revision 0 1 (' - Remain in
- Vicinity Y
Notify '
; Control "
Room { . 6 I .
.J .
Y
. ,-- Announce Fire Location and *
. Sound Fire Alarn
- i y
[ Y ;
'v F: , Brigade . .y t Scene Plant No No l Notify Plant s
. . Status Evacuation l '
Offsite Change Fire . Company
** Yes Extin u shed i f
/ I' No
/
Action
]/i No Yes Offsite ' "
Support I ._ f i NecessarY Change Plant Evacuate per l Status Emergency Plan Extinguish , Fire No ' Y Secure .Y Y
\ = Offsite M Fire Support
! T U l Restore Plant / System Fine Systems > > Recovery to and Equipmcut tktmal Operations I l ( Secu e
- Fire Brigade .
l j . __,_I Prepare Licensee Event Repoit b_
, Pr ep:: e F ,, e nmrt t - . . . . . - , ,..n.-.- . - - - - . - - . . - . - -
- . .i .
SOUTH CAROLINA ELECTRIC AND OAS COMPANY O VIRGIL C. SUMMER NUCLEAR STATION NUCLEAR OPERATIONS NUC'_EA'R 03E'lA'10NS
~
COPY No.... K?E - EMERGENCY PLAN PROCEDURE EPP-014 T0XIC RELEASE REVISION 0 MAY 21, 1981 i NON-SAFETY RELATED Revi g d o be . Afy Date l 0#IGIlATOR (of this revision) a M !
* - // Y S/
i QUALIPIED REVIEWER / Day'b l Approved:
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PL';;71MANAG'ER" ~ ~ '
// $8/E
'Datb' Date Issued:
I ~ I901 Form AP-101-2, (1/80) REViEJ/ZD EiY PSRC"" O A ,R. w CHAIRMAN - ilb481 DAT~
i EPP-014 Page i Revision 0 5/21/81 LIST OF EFFECTIVE PAGES g PAGE REVISION
,. ,- 1 , 0 11' O 1 0 2 , 0 3 -
0 4 0 5 0 4 O O
EPP-014 < Page 11 Revision 0 5/21/81 O ristE OF c0NrENrS Page List of Effective Pazes i 1.0 PURPOSE 1
2.0 REFERENCES
1 CONDITIONS AND PREREQUISITES 1 30 4.0 PROCEDURE 2 O e e-O
EPP-014 Page 1 Revision 0 5/21/81 1.0 PURPOSE llh 1.1 To provide guidelines for the protection of plant personnel in the event of a significant unplanned or plannel release of toxic or flammable material on-site. 1.2 To tercinate the release of toxic or flaccable caterial on-site.
2.0 REFERENCES
2.1 "71rgil C. Summer Nuclear Station Radiation Emergency Plan." 2.2 " Virgil C. Summer Nuclear Station Environmental Report, Sectir:n 73 3." 23 EPP-009, "On-Site "edical' 2.4 FPP-006, " Handling of Flaenable Liquids and Gases . " 2.5 NUREG-0654, Criteria for Preparation & Evaluation of Radiological Ener6ency Response Plans and Preparedness in Support of :iuclear Power Plants. 3.0 COUDITIONS AND PREREQUISI"ES 31 A toxic release exists when there is leakage or spillage on or around the following:
- a. Chlorine cylinders
- b. Sodium hydroxide tanks
- c. Sulfuric acid tanks
- d. Acconia tanks
- e. Any flammable liquid container
- f. Any flammable gas cylinder
EPP-014 Page 2 Revision 0 5/21/31 () v 4.0 PROCEDURES 4.1 In the event of a gaseous chlorine leak, the following steps should be taken immediately. NOTE: When searching for the location of a chlorine leak, a rag dipped in ammonia on a stick 4111 facilitate the operation. The ammonia will emit a white vapor in the presence of high concentrations of chlorine. NOTE: Unplanned or planned releases could occur on site from plant equipment or from units off-site (such as a tanker truck). 4.1.1 Evacuate the affectea area immediately. 4.1.2 Immediately inform the Shift Supervisor of the incident. 4.1.3 The Shift Supervisor /Emergepcy Directcr will assure that the following are accomplioWd:
- a. Announce over the plant paging system:
There is a release of chlorine in the (area of Plant).l
,, _All persons in the vicinity evacuate this area. l
'~~
- b. Notify the Security Shift Leader of the details of the release.
- c. Dispatch an emergency team and they will:
- 1. Don a Scott AirPak (or equal) and other protective equipment as necessary and immediately remove any overcome personnel in the area.
~
- 2. Attempt to isolate the leak.
- 3. When the emergency no longer exists, take steps to return cylinders to normal operating condition with all precautions.
4.1.4 In the case of chlorine inhalation, these first aid procedures should be followed:
- a. Keep the patient quiet and warm.
- b. Do not give the patient alcohol.
- c. If the patient is conscious, give black coffee.
p
%,)
EPP-014 Page 3 Revision 0 5/21/81
- d. Give the patient warm milk or cream to relive throat llI irriation.
- e. If required. Cardio-Pulmonary Resuscitation should be commenced.
- f. Additional first aid and followup treatment will be in accordance with Reference 2 3 4.2 In the event of a sodium hydroxide leak these actions should be followed:
4.2.1 Evacuate the affected area to ensure safety of plant personnel. 4.2.2 I= mediately inform the Shift Supervisor. 4.2 3 The Shift Supervisor / Emergency Director will assure that the following are accomplished:
- a. Announce on the plant paging system:
FThere is a release of sodium hyroxide in (area of plant). All persons in the vicinity evacuate this area.
- b. IIotify the Security Shif t Leader of the details of h the release.
- c. Dispatch an emergency team and they will:
- 1. Evaluate the situation and isolate the tank area.
- 2. Don the necessary protective equipment.
3 Wash down the leakage with a large volume of water. 43 In case of a sulfuric acid leakage or spillage these emergency steps should be taken im=ediately: 431 Small leaks
- a. Inform the Shift Supervisor.
- b. The Shift Sapervisor/ Emergency Director will:
(1 ) Take the necessary actions to stop the spill and wash acid down the drain with a large volume of water. 432 Spontaneous large release. 1 I
EPP-014 Page 4 Revision 0 5/21/81
- a. Inform Shift Supervisor.
(])
- b. The Shift Supervisor / Emergency Director will assure that the following are accomplished:
- 1. Announce over the plant paging system:
There is a release of sulfuric acid in (area of plant). All persons in the vicinity evacuate , this area.
- 2. Notify the Security Shift. Leader of the details of the release.
3 Dispatch an emergency team and they will:
- a. Evaluate the situation and isolate the affected area to ensure the safety of plant personnel.
- b. Don the necessary protective equipment and take the action necessary to stop the spill.
- c. Dilute the acid with large volumes of water.
4.4 In case of an aqueous ammonia release these steps should be
] followed:
~4.4.1 Inform the Shift Supervisor immediately.
4.4.2 Direct all personnel away for the affected area. 4.4.3 The Shif t Supervisor / Emergency Director will assure that the following are accomplished: l a. Announce over the plant paging system: There is a release of aqueous ammonia in (area of
- plant). All persons in the vicinity evacuate this area.
- b. Notify the Security Shift Leader of the details of the release.
l l
- c. Dispatch an emergency team and they will:
- 1. Don a Scott Air Pak and take action necessary to stop the spill.
- 2. Dilute the ammonia with a spray of water. Add dilute acid if available.
( l i
EPP-014 Page 5 Revision 0 5/21/81 4.5 In the event of a flarnable liquid leak these emergency steps should be followed: 451 Immediately inform the Shift Supervisor. 452 The Shift Supervisor /Ecergency Director will assure that the following are accomplished.
- a. Announce over the plant paging systen:
There is a release of flaccable liquid in (area of plant). All persons in the vicinity evacuate this area.
- b. Notify the Security Shift Leader of the details of the release.
- c. Dispatch an emergency team and they will:
- 1. Don the necessary protective clothing.
- 2. Stop the leak.
3 Wash down the area with a large volume of water. 4.6 In the event of a flammable gas leak thece emergency steps g should be taken: W 4.6.1 I: ediately inform the Shift Supervisor. 4.6.2 The Shift Supervisor / Emergency ~ Director will assure that the ft . lowing are accomplished:
- a. Announce over the plant paging system:
~T here is a release of flanna' ole gas in (area of plant). All persons in the vicinity evacuate this area.
- b. Notify the Security Shift Leader of the details of the release.
- c. Dispatch an emergency team and they will:
- 1. Don the necessary protective clothing.
2- Attempt to increase the ventilation flow of the area. 3 Stop the leakage. O
. 1 -
1 A SOUTH CAROLINA ELECTRIC AND GAS COMPANY V VIRGIL C. SUMMER NUCLEAR STATION NUCLEAR OPERATIONS TLC _7_AR 0?aA?0NS ! COPY N0.. . . . E 8" Emergency Plan Procedure i EPP-015 NATURAL EMERGENCY (EARTHQUAKE, TORNADO) ! REVISION O MAY 21, 1981 Non-Safety Related Reviewed by: 4
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-ORIGIN TOR (of this revision) l.M Date T
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-QUALIFIED REVIEWER /Jatg l
Approved:
$) As ///30//T]
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Date Issued: fM it!* *f
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' ~' D Fo rm AP-101 -2, (1/80) 0.E.MW:1
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EPP-015 PAGE i REVISION 0 5/21/81 LIST OF EFFECTIVE PAGES Page Revision 1 0
'il 0 1 0 2 0 0
O
- _ - - - . . . ~ - . _ - . - . . . --. _ _ _ . -.
i EPP-015 l PAGE 11 i i REVISION O ! 5/21/81 !O i TABLE OF CONTENTS Page
' List of Effective Pages i 1.0 PURPOSE 1
2.0 REFERENCES
1 3.0 CONDITIONS AND PREREQUISITES 1 4.0 PROCEDURES , 1 1 I O . i I i o i f i
.-r
EPP-015 PAGE 1 REVISION O l l 5/21 /51 1.0 PURPOSE h 1.1 To provide guidelinee for initiating actions when either a tornado or earthquake threatens plant structures or personnel. l 2.n. =. . = =..= .=. _=. ' _: C = *m ( i ) l 1 2.1 Virgil C. Suceer Nuclear Station Radiation Z:ergency Plan. l 1 2.2 " Virgil C. Succer Nuclear Station Final Safety Analysis Report. ! Chapter 3". l l 2.3 NUREG-0654, Criteria for Preparation & Evaluation of P.adiological Z:ergency Response Plans & Preparedness in Support of Nuclear Power Plants. l l 2.4 EPP-012, "Cnsite Personnel Accountability and Evacuation. l l l 30 CONDITIONS AND PREREQUISITES 31 A tornado watch is declared by the National Yeather Services when meteorological conditions in an area are such that the potential for the formation of tornadoes exists. 32 A tornado warning is declared by the National Weather Services when surveillance (radar sighting, verified visual observation) has shown that a tornado has been sightei. a.O PROCEDURES 4.1 Tornadoes
, 4.1.1 When information is received, from either the load i dispatcher or other reliable source, that a tornado-watch / warning is in effect for the area surrounding 7.C.
Summer Nuclear Station, the Shift Supervisor shall perform the following: l a. Infor: the Management Duty Supervisor.
- b. Announce the watch / warning over the clant paging syster and inform the guard house.
- c. Ensure all exterior doors to plant structures are shut and secure (include non-protected buildings. if time per:its).
O
EPP-015 PAGE 2 REVISION 0 5/21/81
d. Designate shift personnel or, if the Operations Support Center is activated, an Emergency Repair Team to stand by in the event emergency assessment and corrective actions are required. The Emergency Repair Team should consist of the following:
- 1. Operations Personnel
- 2. Health Physics Personnel 3 Maintenance Personnel NOTE: Should a situation arise which would require the presence of an armed individual such as work being done on the physical security system, assistance from the Security Force may be requested.
- e. If evacuation of the site is required, follow the procedure outlined in EPP-012, Onsite Personnel Accoun'tability and Evacuation.
- f. Upon cancellation of the watch / warning by the 13ad dispatcher or the National Weather Service, make the appropriate announcement over the plant paging system and resume all normal activities.
4.2 Earthquake (~T 4.2.1 In the event of seismic disturbance, the Shift Supervisor V will initiate the appropriate corrective actions for any resulting damage. 4.2.2 If the seismic instrumentation in the Control Foom indicates that the operating basis earthquake has been exceeded, the plant must be shutdown. 4.2.3 If evacuation of the site is required , follow the procedures outlined in EPP-C12. NOTE: Backup to load dispatcher for weather information is'the National Weather Service: Columbia 794-2593 l 765-5501 ! 765-5502 or Greer 877-6998 877-4791 O Q/
1 . ,_ SOUTH CAROLINA ELECTRIC AND GAS COMPA!IY VIRGIL C. SUMMER NUCLEAR STATION NUCLEAR OPERATIONS NUf0R 0? ERAT!0NS Co?Y N3.. . M?'E. . . . . . . . . . . . EMERGENCY PLAN PROCEDURE EPP-016 EMERGENCY FACILITIES ACTIVATION AND EVACUATION REVISION 0 MAY 21, 1981 NON-SAFETY RELATED n V deviewed by:
, &MW ORIGINATOR (of this revision) iDate 40 - // 4 /
QUALIFIED HEVIEWER /Daye Approved: Ad 4 s~ - - //}3 PLANT MANAGER 'Ifat Date Issued: " ISOI
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- . -. - m . ; ' C .%- Form AP-101-2 (1/80) b's N.R l]2(El
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. I EPP-016 PAGE i REVISION 0-5/21/81 .
LIST OF EFFECTIVE PAGES g PAGE REVISION i 0 11 0 1 0 2 0 3 0 4 0 5 0 6 0 ATTACHMENTS Attachment I 0 Attachment II O g O
EPP-016 1 PAGE 11 REVISION O , 5/21/e1 n V TABLE OF CONTENTS PAGE List of Effective Pages i 1.0 PURPOSE 1 !
2.0 REFERENCES
1 30 DEFINITIONS AND ABBREVIATIONS 1 4.0 CONDITIONS AND PREREQUISITES 1 4 ATTACHMENTS ATTACHMENT I - Emergency Organization i' ATTACHMENT II - (On-Site Emergency Organization Response) O I i l 1 J t t l
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O EPP-016 . FAGE 1 REVISION 0 5/21/81 O 1.0 PURPOSE 1.1 The purpose of this procadure is to delineate the actions necessary to activate and conditions for evacuation of, the Technical Support Center, Operations Support Center, the Health Physics Lab, the Emergency Operations Facility, and the News Media-Area.
2.0 REFERENCES
2.1 " Virgil C. Summer Nuclear Station Radiation Emergency Plan" 2.2 NUREG 0654, " Criteria for Preparation & Evaluation of Radiological Emergency Response Plans & Preparedness in Support of Nuclear Power Plants". 23 SPP-114 - Security Force Responsibilities During Emergencies 2.4 EPP-019 - Emergency Equipment Checklist 25 "CEMP" - Corporate Emergency Management Plan 2.6 CEP-001 - Corporate Emergency Procedure.- 001 (g) 2.7 CEP-007 - Corporate Emergency Procedure - 007 30 DEFINITIONS AND ABEREVIATIONS 31 Definitions 3 1.1 Activation of Facility - A facility is activated when the facility is manned with the necessary personnel. prepared to provide its support function, as determined by the Facility Leader. 32 Abbreviations 3 2.1 TSC - Technical Support Center 3 2.2 OSC - Operations Support Center 323 EOF - Emergency Operations Facility 3 2.4 NMA - News Media Area 3 2.5 ED - Emergency Director G
r 1 EPP-016 PAGE 2 REVISION O 3 2.6 IED - Interim Emergency Director 3 2.7 OEC - Offsite Emergency Coordinator 3 2.8 CR - Control Room 4.0 CONDITIONS AND PREREQU7 SITES 4.1 Plant conditions exist requiring implementation of the Emergency Plan; and the conditions have been classified as an Alert, Site or General Emergency. 4.2 Each emergency facility is equipped per appropriate procedure. 4.2.1 TSC/OSC/HP lab per EPP-019 4.2.2 E0F/ News Media Area per CEP-007 43 At the discretion of the Interim Emergency Director, turnover of various responsibilities to the appropriate designated personnel can be accomplished as those persons respond to the emergency prior to the activation of the TSC/OSC. ([) 50 PROCEDURE 51 Activation of Technical Support Center (TSC) 5 1.1 Upon declaration of an Alert, Site Emergency, or General Emergency the following essential perconnel shall proceed to the TSC. A. Emergency Director (ED) B. TSG Communicator C. ED Administrative Assistants (2) D. Radiological Assessment Supervisor (1) E. Out-of-Plant Monitoring Director F. In-plant Monitoring Director O
EPP-016 PAGE 3 REVISION 7 5/21/o1 - G. Personnel with: ggg
- 1. Core Expertise
- 2. Mechanical Expertise 3 Electrical Expertise 5 1.2 Upon declaration of an alert, tite emergency, or general emergency the following key per.onnel should proceed to the TSC.
A. Security Supervisor B. Assistant Manager Support Services C. Assistant Manager Technical Support D. Assistant Manager Maintenance Services' E. Deputy Manager 5.1.3 At the discretion of the Radiological Assessment Supervisor, a radiological survey is performed to determine the habitability of the TSC. If the radiation dose rate is greater than 100MR/hr. or the airborne radiation levels exceed 10CFR20 Appendix B, Table 1 limits, the evacuation requirements of Section 5.2 of this ll) procedure shall be carried out. 5.1.4 A personnel accountability check shall be performed. 5.1 5 The Emergency Director (ED) shall receive an update en the emergency condition from the Interim Emergency Director (IED). 5.1.6 Following the update of the ED, the IED shall officially turnover the Emergency Director duties and responsibilities to the ED along with the Emergency Log. 5.1.7 The emergency log shall be kept by the ED's logger following the official turnover. 5.1.8 The TSC communicator shall report to the CR to receive official turnover of the Emergency Notification Log from the interim communicator. O
EPP-016 PAGE 4 REVISION O 5/21/81 r8
\#
519 Upon the request of the ED, the TSC staff shall provide technical evaluations of the emergency condition and/or courses of action to be taken to minimize the effects of the emergency condition. ' 52 Evacuation of the TSC If the airborne radiation levels exceed 10CFR20, Appendix B, Table 1 limits or the radiation levels exceed 100 MR/hr. in the TSC, the following actions shall be taken. 5 2.1 The Emergency Director (ED) shall designate the personnel required to stay in the TSC and Control Room. 5.2.2 The renainder of the personnel shall proceed to the Emergency Operations Facility (EOF). 523 If the E0F is or becomes uninhabitable, the ED shall designate the alternate assembly area. 53 Activation of the Operational Support Center (OSC) 531 Upon declaration of an Alert, Site Emergency, or General Emergency the following personnel shall proceed to the OSC. O A. Rad-Waste Operator (1 ) B. Mechanical Maintenance (1 ) C. I & C Maintenance (2) D. Electrical Maintenance (2) 532 The Operations Support Center Supervisor, upon being notified, should proceed to the OSC along with other personnel as designated by the Emergency Director. 533 At the discretion of the Radiological Assessment Supervisor, a radiation monitoring shall be performed to determine of the OSC. If radiation dose rate is greater habitability than 100 mr/hr or airborne levels exceed 10CFR20, Appendix B, Table 1 limits, the OSC shall be evacuatcd in accordance with Section 5 4 of this procedure. 534 A personnel accountability check shall be performed.
EPP-016 PAGE 5 - REVISICN O . 5/21/81 535 When the OSC is manned the OSC Supervisor shall report to 9 the ED/IED that the OSC is activated and prepared to perform its support function. 536 Upon the request of the ED/IED, the OSC staff shall provide personnel to man fire brigade teams, search and rescue teams, first-aid teams, maintenance and repair teams, and any other support deemed necessary by the L'/IED. 3.4 Evacuation of the OSC If the airborne radiation levels exceed 10CFR20, Appendix B, Table 1 limits or the radiation levels exceed 100 mr/hr in the OSC, the following actions will be taken: 5 4.1 The OSC will be transferred to a location designated by the ED/IED. The ED/IED will designate any personnel who must remain in the OSC. 55 Activation of the Health Physic's Lab (HP Lab). 5.5 1 Upon declaration of an Alert, Site Emergency, or General Emergency the following personnel shall proceed to the HP Lab: A. Inplant HP Support (2) ll) B. Chemistry Specialist C. Offsite Survey Team (2) D. Onsite Survey Team (1) 552 At the discretion of the Radiological Assessment Supervisor, a radiological survey is performed to determine the habitability of the HP Lab. If radiation dose rate is greater than 100 mr/hr or airborne levels exceed 10CFR20, Appendix B, Table 1 limits the HP Lab shall be evacuated per Section 5.6 of this procedure. 553 A personnel accountability check shall be performed. 554 The Radiological Assessment Supervisor shall report to the ED/IED when the Radiological Monitoring team (s) is/are ready to perform their support function. O
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PAGE 6 REVISION O 5/21/81 555 Upon the' request of the ED/IED, the Radiological Monitoring Group shall provide in-plant and out-of-plant survey teams, personnel to accompany OSC support teams into the plant,
(]) and any other support deemed necessary by the ED/IED. 56 Evacuation of the HP Lab: If the airborne radiation levels exceed 10CFR20, Appendix B, Table 1 limits or the radiation levels exceed 100 mr/hr. in the HP Lab, the following actions shall be taken. 5 6.1 The ED/ Radiological Assessment Supervisor shall designate the personnel required to stay in the HP Lab. 5 6.2 The remainder of the personnel shall proceed to the Technical Support Center (TSC). 57 Activation of the Emergency Operations Facility (EOF) - News Media Area (NMA), will be in accordance with "CEMP" and-CEP-001. 58 Attachment I provides general information regarding the interface between the onsite and offsite emergency organizations. 59 Attachment II provides guidelines for the response of the onsite
. emergency organization; duty stations and basic responsibilities.
~l
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l l O l
EPP-016 AT TACtNENT I PAGE 1 0F 1 REVISIOrt 0 Emorgency Control Officer i I OFFSITL EMERGENCY UtE RGEfC COORDINAT06< DIRECTOR l l .. TECHNICAL CONTROL O'ERATIONS EMERGENCY SUPPORT CENTER ROOM SUPPORT CENTER OPERATIONS FACILITY ASST. M(R. RAD ASST. MGR. OPERATIOr45 TECilN ICAL ASSESSMENT OPERATIONS SUPf0RT CENTER SUPERVISOR ( TLCHN1 CAL CONSTRUCT lON/ SUPPORT SUPERV I SOF; SHIFT
'uPPORT a MPAIP PLANT RAD SUPERVISOR FIRE (RIGADE COURDINATOR CfGlD INATOR SYSTEM ASSESSMENT OPERATORS FIRST AfD
& & ASSESSMENT PERSONNEL % OPERAT lONS STAFF STAFF PERSONNEL g AUXILIARY OPERS. SUPPORT ffE DI A SECURITY EMERG. fEPAIR (XXHDINATOR M DINATOR GENERAL OFFSITE RAD l SLHVICES MONITORING COORDINATOR COORDINATOR EOF FEDERAL,STATt CO NUN ICAT0d LOCAL FIGURE 5-5 g OFFICIALS INTERFACE DETWEEN Oct 1988 ONSITE/0FFSITE Rev. 5 '
EMERGENCY OPERATlONS 6 e O O O :
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.C SOUTH CAROLINA ELECTRIC AND GAS COMPANY VIRGIL C. SUMMER NUCLEAR STATION NUCLEAR OPERATIONS
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NJC_ EAR 0? ERA ~!0XS WY L'o. . . . . . . M7E. . . . . . . . ;. . EMERGENCY PLAN PROCEDURE EPP-020 EMERGENCY PERSONNEL EXPOSURE CONTROL REVISION O MAY 22, 1981 Non-Safety Related O Reviewed by: ) If C4 j ORIGINATOR (of this revision) Dat'e'
'6 Yl / 4 8/ -
~@TALIFIED REVIEWER /Dap
( Approved: N M /8 l PLANT MANAGER DatV i
+ Date Issued: 1 - ISSI C $1 m . .~ Y $s \
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[ Fo rm AP-101 -2, (1/80) j o en4 6{ '*"- 6/e/ DATE i l
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V EPP-020 PAGE i REVISIO!i 0 5/22/s1 LIST OF EFFECTIVE PAGES $ Pace Revision 1 o 11 0 1 0 2 0 3 0 4 0 ATTACHME?i:S 7 Attachment I o Attachment II o Attachment III o e' 9 O
EPP-020 PAGE 11 REVISION O ' 5/22/81 . TALLE OF CONTENTS 4 Page List of Effective Pages i . l a 1.0 PURPOSE 1
2.0 REFERENCES
1 , 30 CONDITIONS AND PREREQUISITES 1 ! 4.0 PROCEDURES 2 l ATTACHMENTS Attachment I - Emergency Dosimetry Issue Log Attachment II - Requirements For Entry Into The Radiation Control Area During An Emergency Attachment III - Actte Uptakes Involving Projected Thyroid Dose () Commitments Greater Than 10 REM i I I O
EPP-020 PAGE 1 REVISION O 5/22/81 1.0 PURPOSE 1.1 Provide guidelines for issuing dosimetry and controlling personnel exposure when responding to conditions that have placed the plant in an Alert, Site, or General Emergency status.
2.0 REFERENCES
2.1 Virgil C. Summer Nuclear Station Radiation Emergency Plan. 2.2 10CFR20. 23 NCRP Report #39 " Basic Radiation Protection Criteria". 2.4 HPP-506, " Personnel Monitoring Devices". 2.5 AP-704, " Administrative Exposure Limits". 2.6 AP-701, " Issuance and Control of Personnel Dosimetry. 2.7 NCRP Report #55, Protection of the Thyroid Gland in the Event of Releases of Radiciodine. 30 CONDITIONS AND PREREQUISITES ggg 31 Limits and Precautions. 3 1.1 This procedure may be activated by the Interim Emergency Director / Emergency Director or Radiological Assessment Supervisor when conditions dic' ate. Any deviations from this procedure should be authorized by the Interim Emergency Director / Emergency Director or Radiological Assessment Supervisor and documented. As soon as conditions allow return to normal plant procedures. 32 In an emergency, the following exposure limits may be utilized: 3 2.1 Normal Administrative exposure limits may be suspended or modified verbally by the Interim Emergency Director / Emergency Director, Radiological Assessment Supervisor, or Shift Supervisor. Verbal exposure extens ons should be followed-up with the appropriate documentation as defined by reference 2.4. 3 2.2 Federal limits of 10 CFR 20 will not knowingly be exceeded, except as d ese .-ibed in Section 3 2.4 of this procedure. 3.2.3 Maintain exposure ALARA. O l
EPP-020 PAGE 2 REVISION O 5/22/81 () 3 2.4 Planned exposures of up to 100 Rem to save human life or prevent the serious endangerment of human life, or up to 25 Rem to save or mitigate significant damage to vital equipment and/or facilities must be approved by the Interim Emergency Director / Emergency Director or Radiological Assessment Supervisor. NOTE: This does not apply to " spontaneous reactions" by on the scene personnel in a threatening situation. 4.0 PROCEDURE 4.1 Dosimetry Issue for non-plant Emergency Personnel requiring
" Rapid Access" to the station". (i.e. ambulance crews, fire fighters, etc).
4.1.1 Dosimetry should be issued at the Main Security Guardhouse. 4.1.2 Responsibility of Security Personnel: ,
- a. Issue TLD's and self-reading dosimeters.
- b. Complete columns (1) thru (4) of Attachment I.
() c. Notify the ED/IED and Health Physics upon issuance of dosimeters to non-plant emergency personnel.
- d. Escort emergency personnel to the appropriate locations as directed by the ED/IED.
4.1 3 Responsibilities of Health Physics:
- a. Oversee activities of rapid access personnel with regard to radiological safety and Station Health Physics procedures.
- b. Collection of dosimetry upon completion of radiologically related activities.
- c. Ensure completion of dose cards and-Attachment I following termination of radiologically related activities.
O F
EPP,020 Pn.naz 3-REVISION 0 5/22/81 NOTE: Steps b and c may be accomplished enroute to h hoapital or at hospital as time and coniitions allow. 1.2 Dositetry issue for support personnel not requiring " rapid access" (i.e. contractors, tendor and governmental representatives, etc.T and person.7el not posessing adequate losimetry for emergency actions. a.2.1 Eadges and Dosimetry should be issued at the EDF for "on ec ing" personnel and "On-Site" personnel who do not already have dosimetry issued and stored at Guard House. d.2.? Document dosimetry issue using Attachments I and II. d.2 3 As soon as conditions allow and at the direction of the Interi Emergency Director /Energency N rector or the RadioloS'.al Assessment Supervisor, normal dosinetry issue anc exposure control should be re i ns t i tut e.1 in accordance with references 2.a and 2 5 4.2.4 Responsibilities of Health Physics: a) Proper collection of dosimetry. b) Completion of dose cards and Attachment I's. c) Completien of all required personnel exposure records. a.3 Use of EI thyroid blocking agent. d.3 1 The Director of Health Physics or Radiological Assessment Supervisor shall determine the need for a:1 ministering EI (stored in the TSC). d.3 2 EI should be adcinistered within one hour following-an acute uptake that involves a projected thyroid exposure greater than 10 Rec. Guidelines are: a . 3 2.1 Individuals suspected to have received greater than 650 MPO-hours of internal exposure to radiciodines should be showered and analyced by whole body counting (torso) incediately following the uptake. Measured torso burdens greater than a pCi (I-131) may result in a thyroid exposure greater than 10 Rec. O
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'PP-020 i PAGE 4
! REVISI0li 0 t j 5/22/81 l h 4 3 2.2 If conditions do not ailow whole body counting within two hours after the uptake, the estimated
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! MPC-Hour exposure should be used to determine the ' f l , need for KI. 4 3.2 3 KI (100-300 mg) should be taken on a daily basie ') i not to exceed 7-10 days until the thyroid uptake d j of radiciodine is' adequately blocked. [ ! l
- 4 3 2.4 Any individual has the right to refuse KI and 'i i accept the resulting thyroid exposure. .l l -
l l 433 Attachment III must be completed prior to administerina 'l KI. l
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[1 ) ( ~3 ) i TT4) AGP CDHR E TIT - }:r t . NAME , I f! ' T Li> DOS IM ET ER DOSIMETER QTR. C WB P,.x po . SSIT DOB SIGriATURE 1 YEARS
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(A) I !! AVE READ AND UNDERSTAND EMERGENCY DOSIMETRY USAGE ( ATTACilMENT II). ( B) THE INDICATED ESTIMATE OF CURRENT QTR. W.B. E(POSURE IS CORRECT TO Tile BEST OF MY Efl0WLEDGE. EPP-020 ATTACl! MENT I PAGE 1 0F 1, Rev. O
EPP-020 ATTACHMENT II PAGE 1 0F 1 REVISION 0 Il
'~' REQUIREMENTS FOR ENTRY INTO THE RADI ATION CONTROL AREA DURING AN EMERGENCY
- 1. Stay with your assigned escort at all times.
l u 2 Notify Health Physics immediately if: a.) you are separated from your escort. b.) your escort is not capable of escorting you for any reason. c.) if TLD or Pocket Dosimeter is lost. d.) if Pocket Dosimeter reads 250 mR, off-scale oc has been dropped. 3 Obey all radiological postings in the plant. t 4 Obey all instructions given by your escort, or by Health Physics personnel.
'3 TLD's and Pocket Dosimeter will be worn on the front trunk of the body between the neckline and waistline.
r s . 6. Wear your TLD and pocket dosimeter at all times. g "7 . Have your escort read your pocket dosimeter frequently. a .' Stand clear of all areas marked " HOT SPOT". 8 9 Do not enter any area marked " Airborne Radioactivity Area".
- 10. Do not enter,any area that is' marked with Radiation Postings without specific instructions from your escort.
- 11. Do not enter areas marked "High Radiation Area". -
- 12. Administrative exposure limits for the whole body is 1,000 mres/qtr. minus current qtr. estimate, 500 mrem /qtr. minus current qtr. estimate for females.
- 13. Use self
- ing Dosimeter card to record Pocket Dosimeter readings, upon entering and exiting Radiation Control Area.
- 14. Return Dosimetry and Dose Cards to H.P. before leaving site unless otherwise notified by Health Physics.
I have been shown how to use the plant paging system and will comply with all of the above requirements. O sisneture Dete
EPP-020 ATTACHMENT III PAGE 1 0F 2 REVISION 0 ACUTE UPTAKES INVOLVING PROJECTED ggg THYROID DOSE COMMITMENTS GREATER THAN 10 REM Date: Time: MPC-HRS / Time of I-131 Torse/ Time of Name TLD# Estimate / Uptake Burden ( C1) Count Time KI Taken The threshold for the possibility to experience thyroid abnormalities after uptake of radiciodines is estimated at 20 Rem (low probability of 6 x 10-4 Higher probabilities (greater than .075) exist with thyroid exposures greater than 2500 Ren. KI can be taken after an uptake to prevent accumulation of radioactive iodine in the thyroid due to saturation of the thyroid with stable iodine. KI is over 90% effective if administered within one hour after the uptake and over 50% effective if administered within three to four hours af ter the uptake. Usually, side ef fects of potassium iodide happen when people take higher doses for a long time. You should be careful not to take more than the recommended dose or take if for longer than you are told. Side effects are unlikely because drug. of the low dose and the short-time you will be taking the lll Possible side ef fects include skin rashes, swelling of the salivary gln:ds, and " iodism" (metallic taste, burning mouth and throat, sore teeth and gums, symptoms of a head cold , and sometimes stomach upset and clarrhea). A few people have an allergic reaction with more serious symtoms. These could be fever and joint pains, or swelling of parts of the face and body and at times severe shortness of breath requiring immediate medical attention. Taking iodide may rarely cause overactivity of the thyroid gland, underactivity of the thyroid gland , or enlargement of the thyroid gland (goiter). If side effects are noted or if you have an allergic reaction, stop taking potassium iodide. Then, notify the V. C. Summer Plant Manager and obtain medical assistance as needed. The only people who should not take potassium iodide are people who know they are allergic to iodide. You may take potassium iodide even if you are taking medicines for a thyroid problem (for example, a thyroid hormone or antithyroid drug). Pregnant and nursing women and babies and children can also take this drug. O 4
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EPP-020 ATTACHMENT III PAGE 2 0F 2 REVISION O ACKN0hTLEDGEMENT I understand and accept the risk associated with receiving KI and will not hold SCE&G Company liable for any payments or costa resulting from side effects excluding that provided by normal Company policies. Signature (s) Date Time I choose to accept thyroid exposure instead of minimizing thyroid exposure by taking KI. I will not hold SCE&G Company liable for any i subsequent thyroid abnormalities which may be related to thyroid exposure. Signature (s) Date Time Director of Health Physics (or) Station Manager (or) Radiological Assessment Supervisor Emergency Director l l l l lO i
.O SOUTR CAR 0t1Ni EtECTaIC Aso GAS COMPANr VIRGIL C. SUMMER NUCLEAR STATION NUCLEAR OPERATIONS N CLEAR 0) ERA"0NS~ COPY N0.. . . . . MZE. . . . . . . . . . .. EMERGENCY PLAN PROCEDURE EPP-017 POST-RECOVERY AND RE-ENTRY REVISION O MAY 21, 1981 O Non-Safety Related Rev%w,edby: w _ ;>
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RIG 1NATOR (of this-revisien) Date f YY ?/ lf f/ .. QUALIFIED REWIEWER
/Date Approved:
[ PLAliT MANAGER
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Date ' Date Issued: I ~ 1981
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DCj/iwiVL- Q\/ Lei C Q ,1D{.c 1 \ h-d Form AP-101-2, (1/80) R,R. k%l. ll3al81 CHAIRMAN _ _ _ CA ~
l EPP-017 , PAGE i REVISI0fi 0 5/21/81 LIST OF EFFECTIVE PAGES Page Revision 1 0 11 0 1 0 2 O 3 0 4 0 5 0 6 0 7 0 ATTACHMENTS Attachment I O g I i l l l l 9
- i
EPP-017 PAGE 11 REVISION 0 5/21/81 TABLE OF CONTENTS Page List of Effective Pages i 1.0 PURPOSE 1 2.0 REFERENCE $ 1 30 CONDITIONS AND PREREQUISITEb 1 4.0 GENERAL 1 5.0 PROCEDURE 1 ATTACHMENTS Attachment I - Recovery Organization l O i 3 I i ,I I t 4
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EPP-017 . PAGE 1 REVISION 0 5/21/81 1.0 PURPOSE 1.1 Te provide guidelines for the followin6 emergency actions: 1.1.1 Re-entry into affected areas of the plant. 1.1.2 Initial recovery operations to the establishment of the Long Ter= Recovery Organization.
2.0 REFERENCES
2.1 " Virgil C. Summer Nuclear Station Radiation Emergency Plan". 2.2 NUREG-0654, Criteria for Preparation & Evaluation of Radiological Emergency Response Plans & Preparedness in Support of Nuclear Power Plants. 23 EPP-020 Emergency Personnel Exposure Control. 2.4 AP-711 Control and Posting of Radiation Control Zones. 30 CONDITIONS AND PREREQUISITES 31 Immediate corrective and protective actions have established an ggg effective control.over the emergency condition. 32 Radiological conditions for affected areas within the plant have been determined. 33 Plant personnel, who have completed the onsite radiation control and Safety Training Program and are eligible to receive emergency dose rates as delineated in EPP-020, are available. 34 Extended actions are necessary to return the plant to its normal operating status and the following recovery phase criteria ~have been met: 3 4.1 Radiation levels in all in-plant areas except waste processing systems are stable or decreasing with time. 3 4.2 Releases of radioactive materials to the environment from the plant are under control or have ceased. 343 Any fire, tornado or similar emergency condition is controlled or has ceased. O 3
. EPP-017 PAGE 2 REVISION O 5/21/81 4.0 GE NER A L 41 All Post-Recovery and Re-entry activities will be carefully planned and reviewed prior to implementation of any such activities.
50 PROCEDURE 51 Planning of Re-entry Operations. l l 5 1.1 Review the following data prior to authorizing re-entry by the emergency teams: A. Radiological surveillance data to determine plant areas potentially affected by high levels of radiation and
- contamination.
B. Current radiation exposure of emergency personnel who will participate in the re-entry operation. C. Environmental conditions such as temperature, gases, smoke that the re-entry team will encounter. 5 1.2 Preplan the activities of the Re-entry Teams taking the '(]) following items into e.ccount: NOTE: Since it is no', possible to anticipate, in advance, all the conditions that may be encountered in any emergency situation, the recovery plan must be flexible enough to allow for any unanticipated occurrences and/or conditions encountered during the recovery operation. A. Areas to be surveyed
- 3. Anticipated radiation and contamination levels C. Adequacy of radiation survey instrumentation and equipment shall be reviewed. Additional equipment which may be needed to effect the recovery /re-entry will.be made available from emergency operation facility.
O
EPP-017 - PAGE 3 REVISION O 5/21/31 D. Shielding requirements and availability llh E. Protective clothing and equipment required F. Access control procedures G. Decontamination requirements H. Communications I. Exposure control limits, personnel dosimetry requirements, and allowable exposures J. Route to be followed 513 Designate a Re-entry Team which should consist of the following personnel: A. Appropriate Technical Personnel - 3
- 3. Health Physics - 1 NOTE: Ensure that each member of the team has sufficient exposure remaining to complete the re-entry procedures and not exceed the normal Virgil C. Summer exposure limits . (Re: Section 3 3) 52 Actions to be Accomplished During Initial Reentry.
5 2.1 Give the members of the emergency team the following instructions: A. Do not deviate from the planned route unless unanticipated conditions are encountered. 3 If dose rates encountered during re-entry are - significantly greater than anticipated, reentry personnel shall return to a safe area and contact the Emergency Director for further instructions. 5 2.2 Instruct the members of the Re-entry Team to assess the following items in the specified priority: O
~ EPP-017 PAGE 4 REVISION O 5/21/81 A
\-./ A. Determination of initial required recovery operations including assessment of equipment damage.
B. Determination of real or potential hazards associated with the required recovery operation. C. Without delaying the mission or causing unnecessary exposures, the Re-entry Team should monitor the dose . rate along the route followed to obtain as much radiological information as pessible. 523 After reentry procedures have been completed, the Re-entry Team will: A. Follow established self-monitoring and personnel decontamination procedures, as necessary, under the supervision of the individual charged with health physics m]nitoring of the Re-entry Team. B. Record and report to the Emergency Director the radiological conditions and damage assessments in the emergency area. C. If possible, areas of contamination shall be isolated and posted with appropriate warning signs. These ("% areas will be posted in accordance with AP-711. \s' Portable shielding material should be used whenever practical. 53 Evaluation of Conditions 531 The ED/0EC will evaluate the radiological conditions and the damage assessment report, and then determine: A. The areas that have been affected by the emergency. B. What must be done to restore the station to normal conditions. C. Radiological controls to be instituted. . D. Personnel, equipment, and time required.
EPP-017 , PAGE 5 REVISION O 5/21/81 54 Recovery 5 4.1 During recovery operations, station supervisory personnel will take the action necessary to ensure that: A. . Recovery and clean-up techniques are in accordance with good health physics practices and procedures. B. Personnel radiation exposure during the recovery stage of the incident is closely controlled and documented. Individual exposures shall be in accordance with 10 CFR 20 limits. C. Recovery activities and repairs are properly documented and controlled. D. Test programs to confirm fitness of equipment for return to service are developed and executed. 5 4.2 Based upon the extent of the emergency, long-term recovery operations may be required. The Emergency Director will notify the Offsite Emergency Coordinator and make recommendations as to the establishment of the Long Term Recovery Organization. 543 Recovery Organization (See Attachment I) (g) A. The Offsite Emergency Coordinator, with concurrence by the Emergency Control Officer, will shift from an Emergency Organization to a Recovery Organization. When a Recovery Organization is implemented, the Offsite Emergency Coordinator will inform appropriate offsite agencies. B. The Recovery Organization will depend upon the nature of the accident and the situation after the accident. A general organization is shown in Attachment I. Specific crganizational structure and staffing of the organization will be the responsibilty of the Emergency Control Officer. He will also determine the required scope and function of the recovery organization. The Emergency Control Officer is the Vice President and Group Executive, Nuclear Operations. C. The Recovery Manager, the General Manager, Nuclear Operations, will be responsible for recovery activities, including technical decisions and courses of action. He will coordinate the functional activities of the various groups. O
EPP-Oli PAGE 6 REVISION O
- 5/21/81
() D. The Technical Support Macager, Group Manager, Nuclear Engineering and Licensing, is responsible for recovery activities including analysis and the development of plans and procedures in direct support of Plant , Operations personnel with the objective of taking the plant to a safe shutdown condition in a manner which minimizes the effect on the health an.d safety of the public. This provides the central facility for the collection, retention, retrieval, and transmitting of plant and local environmental parameters. E. The Plant Operations Manager, Station Manager at the V.C. Summer Nuclear Station, is responsible for implementation of in-plant recovery activities with the objective of taking the plant to a safe shutdown condition in a manner which minimizes the effect to the health and safety of the public. F. The Construction / Repair Manager, Group Manager, Production Engineering Quality Control and Construction, coordinates the construction activities of the recovery operation. , G. Advisory Support, a staff function consisting of senior technical personnel, will serve on the Recovery Manager's staff. Typically, they consist of senior (N)
\- representatives from the NSSS supplier, the A.E., and the NRC. Representatives for the recovery organizatio'n will be management personnel who have the requisite authority to represent their respective organizations in making resource commitments and resolving technical issues.
This group provides day-to-day support to the Recovery Manager and his staff and will be -in attendance at the routine meetings of the recovery organization. H. The Scheduling / Planning Manager, Senior Engineer, Nuclear Operations, serves as a support resource for the Recovery Manager, assisting him in the short-term planning, scheduling, and expediting of recovery operations. In emergency situations, the normal techniques for outage planning and scheduling are two cumbersome and slow. Usual measures are required to identify key problems; significant operations, technical decisions, resource limitations, and schedule milestones. The organisation of this function will be strongly dependent upon the specific needs of the Recovery Manager. This group would develop the agenda for recovery staff meetingn and follow up with expediting of commitments made at these meetings. O
EPP-017 PAGE 7 REVISIO!! O 5/21/S1 I. The Administrati.on ani logistics Manager, Manager of Purchasing, Production, and Construction, provides lll administration, logistic, communications, and personnel support for the recovery operation. J. The Me!ia Coordinator, Supervisor, IIuclear Information at the V. J. Summer ITuclear Station, is the ranking public information representative at the IIews Media Area who (1) relays information to other employees at the center, (2) sunervises all communications operations at the center, (3) distributes all news releases and statements, and (i) maintains direct contact with public information specialists to develop guidance on policy and background material. The Media Coordinator will also coordinate information at the news center with counterparts from local, state, federal agencies, and other companies involved ith the emergency, and provide a means of meeting t' media's needs. O O
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4 SOUTH CAROLINA ELECTRIC AND GAS COMPlNY 4 pd VIRGIL C. SUMMER NUCLEAR STATION NUCLEAR OPERATIONS N CR OPERKE0KS COPY No.... ./52E EMERGENCY PLAN PROCEDURE EPP-018 EMER3ENCY TRAINING AND DRILLS REVISION O MAY 22, 1981 O NON-SAFETY RELATED 1 Reviewed by: ORI TOR (of'this revision) e I Date SY fI ~ w%77 QUALIFIED REVIEWER duk
/ Date Appeoved:
PLANT MANAGER d ///3WefDate ( l , Date Issued: "&C i - iM,!
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# l '- Y t LJ LJ i C1/6D&Dfff Q4$V 8 Form AP-101-2 (1/80) n)
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EPP-018 l PAGE i - ,l REVISION 0 l 5/22/81 LIST OF EFFECTIVE PAGES PAGE REVISION ' i 0 11 0 1 0 2 0 3 0 4 0 5 0 6 0 ATTACHMENTS Attachment I, Pages 1 through 3 0 Attachment II, Pages 1 through 4 0 0 e i i
. EPP-018 PAGE 11 REVISION 0 5/22/81 TABLE OF CONTENTS PAGE List of Effective Pages i 1.0 PURPOSE 1
2.0 REFERENCES
1 3.0 CONDITIONS AND PREREQUISITES 1 4.0 PROCEDURES 1 ATTACHMENTS ATTACHMENT I - Training Groups & Associated Training Requirements ATTACHMENT II - Exercise Evaluation Criteria O e
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EPP-018 PAGE 1 ' REVISION 0 5/22/81 1.0 PURPOSE 1.1 The purpose of this procedure is: 1.1.1 To establish the Virgil C. Summer Emergency Plan Training requirements as they apply to emergency organization personnel, general SCE&G empicyees, contractors and support agencies. 1.1.2 To delineate the administrative controls and procedures for the performance of Virgil C. Summer Radiation Emergency Plan drills and exercises. 1.1.3 To provide a standerd method to be used for the performance evaluation and documentation of Virgil C. Summer Radiation Emergency Plan drills and exercises.
2.0 REFERENCES
2.1 " Virgil C. Summer Nuclear Station Radiation Emergency Plan" 2.2 " Virgil C. Summer Nuclear Station Final Safety Analysis Report, Section 13A.7.1, Organization Preparedness" 2.3 AP-1101, " General Employee Training" 2.4 AP-1103, " Fire Protection Training and Drills" 2.5 NUREG-0654/ FEMA-REP-1, January 1980, " criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants" 3.0 CONDITIONS AND PRERECUISITES . 3.1 An emergency plan drill tests a portion of the emergency ~ organization. 32 An emergency plan exercise tests all or most of the emergency organizations. 4.0 PROCEDURE 4.1 Emergency Plan Training O
EPP-Old PAGE 2 REVISION 0 5/22/81 () 4.1.1 The Manager, Nuclear Operations / Education and Training is responsible for coordinating the training of all Virgil C. Summer Nuclear Station personnel. 4.1.2 The Manager, Nuclear Operations / Education and Training may delegate the training responsibilities to those personnel . qualified to teach a specific subject. 4.1.3 Lesson plans should be provided for each instructor's program and the designated instructor will be responsible for identifying and correcting weak areas within his part of the training program. 4.1.4 All on-site and off-site Virgil C. Summer Nuclear Station staff listed in the Training Groups and Associated Training Requirements (Attachment I) shall be required to attend, on an annual basis, a training session covering a revjew of the Emergency Plan and Emergency Plan Procedures. 4.1.5 All non-essential personnel, including contract people, shall receive Emergency Plan training, on an annual basis, as part of the General Employee Training Program, AP-1101. 4.1.6 All off-site emergency organizations listed shall be () invited, on an annual basis, to attend an Emergency Plan and Emergency Plan Procedure Training Program per the requirements of Attachment I. 4.2 Emergency Plan Drill and Exercise Development 4.2.1 The Emergency Coordinator is responsible for the planning, scheduling and coordination of all emergency planning related drills and exercises, with assistance provided by other groups and individuals,.such as the Nuclear Training Coordinator. , 4.2.2 All drills and exercises are approved by the Station Manager, with the exception of the Annual Radiation Emergency Drill which shall be approved by the General Manager Nuclear Operations. 4.2.3 The following is the sequence of events for the development and implementation of drills and exercises: A. Determine the type of drill to be held and the date and time that it will occur.
- 3. Develop the scenario for the drill, including plant status prior to the occurance of the emergency.
A
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EPP-018 . PAGE 3 REVISION O 5/22/81 NOTE: Scenarios for drills and exercises shall include but not be limited to, the i'cllowing: lll
- 1. The bacic objectivels) of each drill and exercise. ,
- 2. The date(s), time period, place (s) and participating organizations.
3 The simulated events.
- 4. A time schedule of real and simulated initiating events.
5 A narrative summary describing the conduct of the exercises or drills to include such things as simulated casualties, offsite fire department assistance, rescue of personnel, use of protective clothing, deployment of radiological monitoring teams, and public information activities.
- 6. Arrangements for qualified observers.
Drill scenarios shall be prepared that involve particication of several emergency teams and all or a specific parts of the non-site and off-site W emergency organizations including varying degrees of participation of State, County. and Federal . organizations and agencies, and local services support personnel and organizations. The Emergency Coordinator shall notify the off-site emergency restonse organization and agencies at least thirty (30) days in advance of the scheduled date of the drill or exercise. C. Forward the completed scenario to the Station Manager or General Manger Nuclear Operatons for review and approval. D. Assign personnel who will be evaluators / controllers / observers during the course of the drill. E. will be held to brief A pre-exercise evaluators meeting / observers on the
/ controllers scope, sequence of events, and individual responsibilities.
F. Conduct the drill as scheduled. O
EPP-018 PAGE 4 REVISION O 5/22/81 - G. Upon completion of the drill, conduct a post-exercise critique during which time evaluators / controllers / observers comments shall be heard. The criteria for evaluation of the exercise is given in Attachment II. H. The names of all emergency personnel who participated in the drill shall be documented as per AP-1101
" General Employee Training."
I. Recommendations of improvements in the E=ergency Plan or Emergency Plan Procedures, based upon the critique, shall be forwarded to the Station Manager for his review. J. All documents generated as a result of the drill shall be forwarded to the Emergency Coordinator. K. Ensure that deficiencies discovered are reported to the Station Manager and PSRC for review and corrective action. 4 2.4 Scheduled drills and' exercises shall be held involving off-site as well as on-site emergency personnel, organizations, and agencies. Each scheduled drill will be conducted in a manner that (]) 4.2 5 ensures: , A. The drill participants are familiar with their respective duties and responsibilities.
- 3. The adequacy of the methods used in the Emergency Plan Procedures.
C. A check has been performed on the availability of i emergency supplies and equipment. D. The operability of e .cgency equipment. E. Plant conditions and operations will not be jeopardized. 4.2.6 The Emergency Coordinator is responsible for preparing drill scenarios. Section Sueprvisors/ Superintendents shall prcvide assistance as requested by the Emergency Coort.nator to ensure the drills achieve the desired effect to the maximum extent possible. ( l [
EPP-Old PAGE 5 REVISIOh 0 5/22/81 4.2.7 The Emergency Coordinator should ensure the notification of & W any offsite agencies to be involved in a drill at leact thirty days prior to the drill initiation. He should, as a reminder, also verify that the off-site agencies can still support their involvement in the drill by contacting them within ferty-eight hours of the drill initiation. 4.2.8 Prior to the running of a drill, a pre-drill briefing should be conducted by the Drill Coordinator. All drill nonitors should be in attendance ;o discuss the expected sequence of events and to receive instructions en precautions to be observed during the drill sequence. After completion of the drill, the individual specified as the Head Controller should conduct a post-drill critique with drill monitors and participants at the earliest time when all applicable personnel can be gathered. 4.3 E=ergency Plan Drill and Exercise schedule 4.3.1 Drills will be scheduled so that the following periodicity is adhered to: A. Medical Drills
- 1. An'iually with the participation of local medical support personnel and organizations and should ggg involve cases of radiation over-exposure and contaminated personnel with and without injuries.
B. Fire Energency Drill
- 1. Fire Brigade Members (cuarterly)
- 2. Fire Brigade and off-cite fire fighting support (annually)
C. Radiological Monitoring Drills (annually) D. Health Physics Drills (semi-annually) E. Cottunication Drills
- 1. 'ionthly with state and counties
- ithin the 10 mile plume exposure Emergency Planning Zone.
- 2. Quarterly wftn Federal and State agencies within the 50 mile ingestion Emergency Planning Zone.
O 4
. EPP-018 PAGE 6 REVISION 0 5/22/81
() 3 Annually between site, State and local emergency operations centers and field assessment teams. F. Site Evacuation Drills (annually) G. Radiation Emergency Exercise
- 1. Annually such that all plans and preparedness organizations are tested within a five year period.
- 2. Once every six year the annual exercise will start between the hours of 6:00 p.m. & midnite; and another between the hours of midnite and 6: 00 a.m.
v
EPP-018 ATTACHMENT I PAGE 1 0F 3 REVISION 0 Emergency Plan Training Topics MODULE 1 EP-LP-01 Rev. 1 (7/81) Introduction to Emergency Planning EP-LP-01-01 Rev. 1(7/81) VC Summer Emerganay Organization EP-LP-01-02 Rev. 1(7/81)~ SCE&G Corporate Emergency Organization EP-LP-01-03 Rev. 1(7/81) State Emergency Organization EP-LP-01-04 Rev. 1(7/81) Role of Federal Support Agencies EP-LP-01-05 Rev. 1(7/81) Emergency Classification System EP-LP-01-06 Rev. 1(7/81) Emergency Facilities EP-LP-01-07 Rev. 1(7/81) Emergency Equipment and Supplies EP-LP-01-08 Rev. 1(7/81) Summary of Potential Actions of Non-Essentials EP-LP-01-09 Rev. 1(7/81) MODULE 2 EP-LP-02 Rev. 1 (7/81) $ Notification Procedures EP-LP-02-01 Rev. 1(7/81) MODULE 3 EP-LP-03 Rev. 1 (7/81) EP-LP-01-01 Rev. 1(7/81) Personnel Accountability and Evacuation EP-LP-03-02 Rev. 1(7/81) Radiation Exposure Control for Plant Personnel EP-LP-03-02 Rev._1(7/81) MODULE 4 EP-LP-04 Rev. 1 (7/81) l In-Plant Radiation Monitoring EP-LP-04-02 Rev. 1(7/81) Out-of-Plant Radiation Monitoring EP-LP-04-03 Rev. 1(7/81) Protective Action Monitoring EP-LP-04-04 Rev. 1(7/81) Dose Assessment EP-LP-04-05 Rev. 1(7/81) Environmental Assessment EP-LP-05-06 Rev. 1(7/81) O
EPP-018 ATTACHMENT I PAGE 2 OF 3 REVISION 0 MODULE 5 EP-LP-05 Rev. 1 (7/81) Site Access Control During Emergencies EP-LP-05-01 Rev. 1(7/81) First Aid / Medical Capabilities and Response EP-LP-05-02 Rev. 1(7/81) Review of Onsite Firefighting Practices EP-LP-05-03 Rev. 1(7/81) First-Aid Team Response EP-LP-05-04 Rev. 0(7/81) MODULE 6 EP-LP-06 Rev. 1 (7/81) Post Recovery and Re-Entry EP-LP-06-01 Rev. 1(7/81) MODULE 7 EP-LP-07 Rev. 1 (7/81) Public Affairs Procedures EP-LP-07-01 Rev. 1(7/81) MODULE 8 EP-LP-08 Rev. 1 (7/81) Basic Health Physics for Cffsite Personnel EP-LP-08-01 Rev. 1(7/81) Radiation Exposure Control EP-LP-08-02 Rev. 1(7/81) Site Access Control During Emergencies EP-LP-08-03 Rev. 1(7/8'l) Facility Layout and Orientation EP-LP-08-04 Rev. 1(7/81) MODULE 9 EP-LP-09 Rev. 1 (7/81) Firefighting Practices and Equipment EP-LP-09-01 Rev. 1(7/81) Local Law Enforcement Response EP-LP-09-02 'Rev. 1(7/81) Ambulance Response to Medical Emergencies EP-LP-09-03 Rev. 1(7/81) RMH-ER Staff Response EP-LP-09-04 Rev. 1(7/81) i o
EPP-018 ATTACHMENT I PAGE 3 0F 3 REVISION 0 . EMERGENCY PLAN TRAINING GROUPS INDEX ggg GROUP 1 - Operations Personnel Shift Supervisor, Reactor Operators, Auxiliary Operators Shift Technical Advisors Modules: 1, 2, 3, 4, 5, 6, all EPP's that are not in cluded in Modules. GROUP 2 - Management, Supervisory, Emergency Personnel, and Essential Corporate Personnel Fmergency Coordinator , TS,C Staf f, EOF Staf f , Emergency Planning S Coordinator Modules: 1, 2,3,4, 5, 6, 7, all EPP's trat are not in modules. GROUP 3 - Health Physics and Environmental Surveillance Personnel Modules: 1, 2, 3, 4, 5, 6, EPP-01% GROUP 4 - Essential Maintenance Personnel Modules: 1, 3, 6, EPP-011 GROUP 5 - Chemistry Personnel ggg Modules: 1, 3, EPP-006, EPP-009. EPP-011, EPP-014 GROUP 5 - Security Force Personnel Modules: 1, 2, 3, 5, EPP-011 GROUP 7 - Personnel not involved with Emergency Plan Modules 1, 3 GROUP 8 - Off-Site Support Personnel - News Media --- MODULES: 7, 8 Fire Departments --- MODULES: 8, Fire Fighting Practices and Equipment. Ambulance Services --- MODULES: 8, Ambulance Response to Medical Emergencies RMH-ER Staf f --- Basic Health Physics for Off-Site Personnel, RMH-ER Staff Response LLEA --- MODULES: 8, Local Law Enforcement Response 9
3 EPP-018 - ATTACF.5ENT II PAGE 1. OF 4 REVISION O 7-) (. Exercise Evaluation Criteria GENERAL PROCEDURES
- 1. Each evaluator, controller, observer has been furnished and should be familiar with:
- a. Emergency Exercise Objectives.
- b. The specific objectives to test the Virgil C. Summer Nuclear Station, State and Local Emergency plant with the ten-mile Emergency Planning zone,
- c. The exercise scenario, initiating events, and expected courses of action to be undertaken.
- 2. For each area to be surveyed the following should be discussed with the evaluators, controllers, observers.
- a. A summary and description of the area's location, emergency mission, and personnel and their emergency responsibilities.
3 Evaluators, controllers, observers should be at their assigned posts between 30 and 45 minutes prior to the commencement of the exercise, even though the area being evaluted may not be (s) activated until later in the exercise. 4 If controllers are to provide information (initiating events, instrumentation readings, environmental monitoring results, etc.) to the exercise participants, the information must be provided exactly as prescribed and exactly when prescribed. Failure to provide the information appropriately may invalidate the resulta of the exercise. 5 A Chronological Record cust be kept for areas surveyed. The record should show the actual time of the event or occurrence, the result or action taken, elapsed time, (where applicable) and pertinent comments.
- 6. Controllers should offer no information, advice or assistance to the drill participants other than what is intended by the scenario. Any such requests should be respectfully declined.
Controllers will only interpose the=selves if the participants. are taking an action that will cause the exercise to go far afield of the anticipated time schedule and/or outcome. Examples of proble=s requiring such interpositions may include: e. dose calculstion/ projection that is so grossly inaccurate that an actior level other than the one postulated for the scenario would ~ be inatituted; an activity that is taking so much lon~ger.than predicted that the exercise scenario is in danger of not progressing as postulated.}}