ML20027D988
| ML20027D988 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 09/10/1982 |
| From: | Connelly J, Counts M SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | |
| Shared Package | |
| ML20027D985 | List: |
| References | |
| PROC-820910-01, NUDOCS 8211110134 | |
| Download: ML20027D988 (350) | |
Text
{{#Wiki_filter:/ ,g 7. Q , VIRGIL C. SUMMER NUCEEAR STATION m NUCLEAR OPERATIONS PROCEDURES EMERGENCY PLAN PROCEDURES TABLE OF CONTENTS PROCEDURE DATE NUMBER PROCEDURE TITLE REVISION ISSUED EPP-001 Activation and Implementation of Emergency Plan 3 9/10/82 EPP-002 Communication and Notification 3 9/10/82 EPP-003 In-Plant Radiological Surveying 2 7/27/82 EPP-004 Out-of-Plant Radiological Surveying 3 7/27/82 EPP-005 Offsite Dose Calculations 3 9/10/82 EPP-007 Environmental Monitoring 1 7/27/82 EPP-008 On-Site Assembly 1 7/27/82 SEPP-009 On-Site Medical 2 7/27/82
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'v sPP-010 Personnel / Vehicle Decontamination 2 7/27/82-EPP-011 Personnel Search and Rescue 2 7/27/82 EPP-012 Onsite Personnel Accountability & Evacuation 3 7/27/82 EPP-013 7 Fire Emergency 2 8/23/82 EPP-014 Toxic Release 1- 7/27/82 EPP-015 Natural Emergency (Earthquake, Tornado) 1 7/27/82 EPP-016 Emergency Facilities Activation & Evacuation 2 7/27/82 EPP-017 Post-Recovery and Re-Entry 2 7/27/82 E P P-O'18 Emergency Training and Drills 1 7/27/82 EPP-019 Emergency Equipment Checklist 3 9/10/82 E PP-020 Emergency Personnel Exposure Control 1 7/27/82 4 Safety Related Procedure
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8211110134 821103 PDR ADOCK 05000395 F PDR m
PROCEDURE DATE TflUf1BER PROCEDURE TITLE REVISION ISS UED b EPP-021 Activation of the Early Warning Siren System (EWSS ) 3 9/10/82 PP-022 Verification of Communications Operability 1 7/27/82 U [ SOUTH CAROLINA ELECTRIC AND GAS COMPANY VIRGIL C. SUMMER NUCLEAR STATION
- NUCLEAR OPERATIONS
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kGLkliR 0PER!\T 0l;S COPY No.. . . . . ggy..c. . . . . . . . . . . ., EMERGENCY PLAN PROCEDURE EPP-001 ACTIVATION AND IMPLEMENTATION OF EMERGENCY PLAN REVISION 2 JUNE 15, 1982 NON-SAFETY RELATED O Reviewed by: YAD.b'L ORIGINATOR Tof this revision) Dite A 2.1& ,/uk
' QUAI /IFIED 4tEVIEWER 'Date Approved:
h///; ~7!6/ $2. PLg MAN AGER /Mf f(ate ' Date Issued: Form AP-101-2, (1/80) O
r . EPP-001 PAGE'1 REVISIOff 2 6/15/82 LIST OF-EPPECTIVE PAGES PAGE REVISION 1 2 11 2 1 2 2 2 - 3 2 4 2 5 2 6 2 7 2 8 2 9 2 10 2 11 2 ATTACHMENTS Attachment I Pages 1 thru 13 2 Attachment II 2 O i i i i lO i
EPP-001 PAGE 11 REVISION 2 6/15/82 k-) TABLE OF CONTENTS P_ag l List of Effective Pages 1 1 1.0 PURPOSE REFERENCES 1 2.0 CONDITIONS AND PREREQUISITES 1 30 4.0 PROCEDURES 2 4.1 CLASSIFICATION OF EVENT 2 4.2 IMPLEMENTATION OF EMERGENCY PLAN 2 UNUSUAL EVENT 2 43 4.4 ALERT 3 6 4.5 SITE EMERGENCY 7._ 4.6 GENERAL EMERGENCY 9
~- ATTACHMENTS Attachment I Emergency Ac tion Level Summaries Attachment II Immediate Actions Summary 4
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EPP-001 REVISION 2 6/15/82 () 1.0 PURPOSE To define and implement the Emergency Action Levels (EAL's) that will initiate the Emergency Plan and to provide a means of classifying the emergency.
2.0 REFERENCES
2.1 " Virgil C. Summer Nuclear Station Radiation Emergency Plan."
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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-021, Activation of the Early Warning Siren System. 2.4 Policy Memorandum No. 25, Issuance, Control, and Usage of Radio Pagers. 30 CONDITIONS AND PREREQUISITES 31 The Emergency Plan shall be initiated whenever an
" Initiating Condition" (as defined in Attachment I) has 4
() NOTE: been reached or exceeded. The implementation of any specific emergency plan procedure (except this procedure) does not necessarily implement the Emergency Plan, but may do so at the discretion of the Emergency Director / Interim Emergency Director. Fo r example; a small chlorine leak would implement the toxic release procedure but not necessitate implementation of the Emergency Plan; whereas a large release with the potential for affecting the level of safety of the plant would implement the toxic release procedure and the Emergency Plan due to the declaration of an Unusual Event. 32 The " Initiating Condition" shall be used to determine the applicable Emergency Action Level (EAL) per Attachment I. O PAGE 1 of 11
EPP-001 REVISION 2 6/15/82
) 33 The " Detection Methods" of Attachment'I are to be used / only as an aid to determine if an " Initiating Other Condition" detection methods, has been reached or exceeded.
not listed in Attachment I, may be used to determine if an
" Initiating Condition" exists. The existence of one or more of the detection methods could be but is not necessarily an indication that an " Initiating Condition" exists.
4.0 PROCEDURES 4.1 Upon recognition of an abnormal plant or site condition the observer shall notify the Shif t Supervisor of the potential emergency plant condition. 4.2 The Shift Supervisor shall: A. Evaluate the conditions and determine the applicable Emergency Action Level (EAL) per the Emergency Action Level Summary, Attachment I. B. Declare an EAL and implement the Emergency Plan per the applicable section of this procedure. Unusual Event (Section 4.3) f3 (Section 4.4) or Alert () or Site Emergency (Section 4.5) or General Emergency (Section 4.6) 4.3 Unusual Event 4.3.1 Immediate Actions: (Immediate Action Summary, See Attachment II) The Emergency Director (ED) or Interim Emergency Director (IED) shall accomplish or cause to be accomplished the following: A. Announce the emergency condition to all plant personnel over the plant paging system. ATTENTION ALL PERSONNEL: THE STATION IS IN AN UNUSUAL EVENT CONDITION. THE INITIATING EVENT IS . I PAGE 2 of 11
EPP-001 REVISION 2 6/15/82 s NOTE: [ REPEAT ANNOUNCEMENT]. B. Notify the Security Shif t Leader to implement appropriate security measures. C. Ensure that on-shift personnel have responded to their emergency response stations. D. Ensure that the Initial Notifications are completed per EPP-002. E. Ensure that the Emergency Log is established and maintainod. F. Request Offsite Emergency Services (Fire, Medical, LLEA, etc. ) if required per EPP-002, l if necessary. NOTE: Consideration should be given to. access routes taken. 4.3.2 Follow-Up Actions: The ED/IED shall continually assess the status of the Pnusual Event per Attachment I for possible escalation to a higher emergency classification or O' termination of emergency condition. 4.3.3 Final Actions: When the emergency condition has cleared, close out the Unusual Event with a verbal summary to offsite authorities within 24 hours and close out of the Emergency Log. 4.4 Alert 4.4.1 Immediate Actions (ED/IED): (Immediate Ac tion Summary, Attachment II) The Emergency Director (ED) or Interim Emergency Director (IED) shall accomplish or cause to be accomplished the following: PAGE 3 of 11
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i EPP-001 REVISION 2 6/15/82 [ T A. Announce the emergency condition to all plant \- ' personnel over the plant paging system. ATTENTION ALL PERSONNEL: THE STATION IS IN AN ALERT CONDITION. THE INITIATING EVENT IS . . ALL EMERGENCY LESPONSE PERSONNEL REPORT TO THEIR STATIONS. B. If necessary, sound the Radiation Emergency Alarm. . C. Repeat the announcement. NOTE: [ Repeat steps A, B, and C every two minutes for six minutes.] D. Notify the Security Shif t Leader to implement appropriate security measures. E. Ensure that on-shift personnel have responded
-s to their emergency response stations.
%- F. During off-normal hours , call in emergency response personnel by activating the SCE&G Radio Pager System as per Policy Memorandum No. 25 G. Ensure that the Initial Notifications are completed per EPP-002. H. Ensure that the Emergency Log is established and maintained. I. Request Offsite Emergency Services (Fire, Medical, LLEA, etc.) if required per EPP-002. NOTE: Consideration should be given to access _ routes taken. O us E PAGE 4 of 11
EPP-001 REVISION 2-6/15/82 I) J. Ensure that TSC/OSC are being activated per l
\ EPP-016 and/or notification of Emergency Response Personnel is initiated per EPP-002.
Determine if the site evacuation is required. l K. (Including Fairfield Pump Storage Facility). 4.4.2 Immediate Actions ( All other personnel): . A. Emergency Response Personnel report to their designated. stations. B. Non-essential personnel continue assigned
' duties and await further instructions.
C. If the radiation emergency alarm is initiated, all Personnel in the Radiation Control Area report to the Radiation Access Control Area on the 412' level of the Control Building. 4.4 3 Follow-up Actions The ED/IED shall: A. Notify the Offsite Emergency Coordinator of the emergency and current plant conditions. gs B. Verify that the TSC/OSC are manned and activated per EPP-016. C. Ensure that updated follow-up notifications are made per EPP-002. D. Continue assessments and corrective actions to mitigate the emergency condition and place the plant into a safe and controlled condition. E. Make assignments to his staff to mitigate the emergency conditions per established Emergency Plan Procedures (EPP's) or as required for conditions not covered by procedures. F. Continually assess the status of the Alert condition per Attachment I for possible escalation to a higher emergency classification, down-grading to an Unusual Event, or close out of emergency condition. [ l PAGE 5 of 11 L
EPP-001
' REVISION 2 6/15/82
() 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 , I authorities are:
- 1. Notified verbally by normal emergency communications.
Provided with a written summary within 8 l 2.
; hours of the close out of the emergency or down-grade of the emergency ! classification.
B. Initiate EPP-017, Post-Recovery and Re-Entry as required. 45 Site Emergency 4 4.5.1 Immediate Actions (ED/IED): *(Immediate Action j Summary, i see Attachment II) I The Emergency Director (ED) or Interim Emergency l Director (IED) shall accomplish or cause to be j accomplished the following: A. Announce the emergency condition and site evacuation to all plant personnel over.the plant paging system. , 1 ATTENTION ALL PERSONNEL: THE STATION IS IN A SITE EMERGENCY CONDITION. THE ' INITIATING EVENT IS . ALL EMERGENCY RESPONSE PERSONNEL REPORT TO THEIR STATIONS. ALL NON-ESSENTIAL PERSONNEL EVACUATE THE SITE PROCEED ~ TO . B. Sound the Radiation Emergency Alarm. C. Repeat the announcement. NOTE: [ Repeat steps A, B, and C every two-l minutes for six minutes.] !O PAGE 6 of 11 l I
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EPP-001 REVISION 2 6/15/82 D. Notify the Security Shift Leader to implement l O' appropriate security measures. E. Notify the Fairfield Pump Storage Facility of site evacuation. , I F. Implement EPP-021. G. During off-normal hours, call in Emergency Response Personnel by activating the SCE&G Radio Pager System as per Policy Memorandum No. 25 I H. Ensure that on-shif t personnel have responded to their emergency response stations. I. Ensure that the Initial Notifications are completed per EPP-002. J. Ensure that the Emergency Log is established ! and maintained. K. Request Offsite Emergency Services (Fire, l Medical, LLEA, etc.) if required per EPP-002. NOTE: Consideration should be given to access () L. routes taken. Notify the Offsite Emergency Coordinator of the I emergency and current plant conditions.
.M. Ensure that TSC/OSC/ EOF are being activated per l EPP-016 and/or notification of Emergency Response Personnel is initiated per EPP-002.
4.5 2 Immediate Actions (All other personnel): A. Emergency Response Personnel report to their designated stations. B. Non-essential personnel evacuate the site, proceed to their private residence or offsite holding area as designated by the ED, and await further instructions.
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EPP-001 REVISION 2 6/15/82 I \ C. Personnel in the Radiation Control Area report \' to the Radiation Access Control Area on the 412' level of the Control Building, unless otherwise directed. 4.5 3 Follow-Up Actions A. Verify that the TSC/OSC/ EOF are manned and activated per EPP-016. B. Ensure that updated follow-up notifications are made per EPP-002. C. Continue assessments and corrective actions to mitigate the emergency condition and place the plant into a safe and controlled condition. D. Make assignments to his staff to mitigate the emergency conditions per established Emergency Plan Procedures (EPP's) or as required for conditions not covered by procedures. E. Continually assess the status of the Site Emergency condition per Attachment I for possible escalation to a higher emergency classification, down-grading to an Unusual ('S i Event, or Alert, or close out of emergency condition. F. Verify site evacuation is complete and all personnel are accounted for. (Including Fairfield Pump Storage Personnel). 4.5 4 Final Actions: A. When emergency conditions clear to allow for close out or down-grading of the Site Emergency condition, the ED shall ensure that offsite authorities are:
- 1. Notified verbally by normal emergency communications.
and 2. Provided with a written summary within 8 hours of the close out of the emergency or down-grade of the emergency classification. B. Initiate EPP-017, Post-Recovery and Re-Entry as required. O PAGE 8 of 11
EPP-001 REVISION 2 6/15/82 (') 4.6 General Emergency Immediate Actions (ED/IED): (Immediate Action 4.6.1 Sumrary, see - Attachment II)
- The Emergency Director (ED) or Interim Emergency Director (IED) shall accomplish or cause to be secomplished the following:
A. Announce the emergency condition and site evacuation ,to all plant personnel over the plant paging system. ATTENTION ALL PERSONNEL: THE STATION IS IN A GENERAL EMERGENCY CONDITION. THE INTIATING EVENT IS . ALL EMERGENCY RESPONSE PERSONNEL REPORT TO THEIR STATIONS. ALL NON-ESSENTIAL PERSONNEL EVACUATE THE SITE. PROCEED TO , a B. Sound the Radiation Emergency Alarm. C. Repeat the announcement. NOTE: [ Repeat steps A, B, and C every two minutes for six minutes]. D. Notify the Security Shift Leader to implement appropriate security measures. E. Notify the Fairfield Pump Storage Facility of Site Evacuation. F. Implement EPP-021. G. During off-normal hours, call in Emergency Response Personnel by activating the SCE&G Radio Pager System as per Policy Memorandum No. 25 H. Ensure that on-shift personnel have responded to their emergency response stations. PAGE 9 of 11
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EPP-001 REVISION 2 6/15/32 (- - b) I. Ensure that the Initial Notifications are completed per EPP-002. l I J. Ensure that the Emergency Log is established and maintained. K. Request offsite Emergency Services (Fire,
- Medical, LLEA, etc.) if required per EPP-002.
NOTE: Consideration should be given to access routes taken. I L. Notify the Of fsite Emergency Coordinator of the emergency and current plant condition.- f M. Ensure that TSC/OSC/ EOF are being activated per EPP-016 and/or notification of Emergency Response Personnel is initiated per EPP-002. 4.6.2 Immediate Actions (All other personnel): A. Emergency Response Personnel report to their designated stations. , B. Non-essential personnel evacuate the site, O proceed to their private residence or offsite holding a as designated by the ED, await further instructions. C. Personnel in the Radiation Centrol Area report to the Radiation Access Control Area on the 412' level of the Control Building., unless otherwise directed. l O l PAGE 10 of 11
EPP-001 REVISION 2
. 6/15/82
() 4.6.3 Follow-up Actions The ED/IED shall: , A. Verify that the TSC/OSC/ EOF are manned and activated per EPP-016. B. Ensure that updated follow-up notifications are made per EPP-002. C. Continue assessments and corrective actions to mitigate the emergency condition and place the plant into a safe and controlled condition. D. Make assignments to-his staff to mitigate the emergency conditions per established Emergency Plan Procedures (EPP's) or as required for conditions not covered by procedures. E. Continually assess the status of the General Emergency condition per Attachment I for possible down-grading to an Unusual Event, Alert, or Site Emergency, or close out of emergency condition. . s F. Verify site evacuation is complete and all personnel are accounted for. (Including Fairfield Pump Storage Personnel). 4.6.4 Final Actions: A. When emergency conditions clear to allow for close out or down-grading of the General Emergency condition, the ED shall ensure that offsite authorities are:
- 1. Notified verbally by normal emergency communications .
- 2. Provided with a written swnmary within 8 hours of the close out of the emergency or down-grade of the emergency classification.
B. Initiate EPP-017, Post-Recovery and Re-Entry as required. PAGE 11 of 11
D4ERGEtCY ACTION LEVELS
SUMMARY
EPP-0010 ATTACtNENT I PAGE 1 of 13, REVISION 2 SYSTD4 SiiE GENERAL INVOLVED UNUSUAL EVENT ALERT EMERGENCY EMERGENCY REACTOR INITIATING C0tolT10N INITIATING C0tolT10N INITI ATING C0t01 TION INI T I AT ING CO@l T ION COOLANT EXCEEDING TECINICAL SPECIFICATION RAPID FAlllRE OF SEVERAL STEAM KNOWN LOSS-OF-COOLANT ACCIDENT SMALL AND LAF.JE LOCAs WITH FAILURE SYSTEM PRIMARY TO SECONDARY m FRIMARY GENERATOR TWES (e.g., SEVERAL (LOCA) GREATER TIMN CHARGING PUPP OF ECCS TO PERFORM LEADitG TO SYSTEM LEAK RATES IUNORED GPM PRIMARY-TO-SECONDARY CAPACITY. SEVERE CORE DEmADATION OR PELT. LEAK RATE). ULTIMATE FAILURE OF REACTOR Detection Method: Detection Method: BUILDING POSSIBLE F(R MELTDOWN Primary to secondary leak rate Detection Method: Pressurizer low pressure reactor SEQUENCES. greater than 1 gpm total for more trip; g than 4 hours or greater than 500 Pressurizar low pressure alarm anc Pressurizer low Iressure safety Detection Method: gpd per steam generator as reactor trip; a_nd, _n injection signal, af Identified by dally ICS leakage Pressurizer low level alarm; and High Reactor Building pressure, Safety Injection signal with evaluation; or RM-A9, Gl9A, G190, or G19C valid and, reactor trip; and, Primary system leak rate greater high alarm: 3 High Reactor Building smp level 1) Status lamps Indicate safety than those speelfled in Technical Steam .. orator water level and ; injection and RFR pumps not Specification 3.4.6.2 as identitiet ragedly increasing in one or more High Reactor Building humidity; running g by daily FCS leakage evaluation. steam generator (s), falling in tho and, n .
- 2) Flow Indicators for Safety others; g RM-A2 high alarm injection System read zero; g
- 1) > 0 pressure boundary leakage RM-L3, or RM-L10 valid high alarm RMG-5, ING-7, ING-18, high alarm;
- 2) > 1 gpm unidentified for more and ------------------
and RM-A2 high alar a; than 4 hours Possible lifting of steam INITIATING COtolTION
- 3) > 10 gpm Identifled RCS leakage generator PRV's and/or safety RAPID FAILURE OF SEVERAL STEAM for more than 4 hours. val ve s. GENERATOR TUBES (SEVERAL FUNDRED -----------------
- 4) > 33 gpm controlled leakage (at GPM PRIMARY-TO-SECONDARY LEAK INITI ATING C0tolTION 2235 + 20 psig for more than 4 ----------------
RATE) WITH LOSS OF OFFSITE POWER. SMALL LOCA NO INITI ALLY SUCCESSFUL hr s. ) , INITIATING C0tolTION ECCS. StBSEQUENT FAILURE OF
- 5) >_1 gpm RCS pressure Isolation REACTOR COOLANT LEAKAGE RATE Detection Method: REACTOR BUILDING TEAT REMOVAL valve per table 3.4-1 for EXCEEDS 50 GPM. SYSTEMS OVER SEVERAL totHS ODULD
, _ _ ar? talar lhaa_4_ho_ursu__ Pressurizer low pressure alarm and LEAD TD (X)RE MELT AND FOSSIBLE INITIATING C0tOIT10N Detection Methods reactor trip, or pressurizer level FAILtRE OF TFE REACTOR BUILDitG. ABNORMAL REACTOR COOLANT TEMP. rapidly decreasing g AND/OR IRESSLRE OR /BNORMAL FUEL 1) Excessive Reactor Make-up to Pressurizer low-level alarm; and Detection Method: TEMPERATLRE THAT WOULD INDICATE A the Volume Control Tank RM-A9, G19A, G198, or G19C valid Pressurizer low pressure reactor l LOSS OF SUBC00 LING MARGIN OR 2) Operational Leakage Test high alarm; and loss of 115KV and trlp; and OVERPRESSUR IZ ATION. Procedure STP-114.002/ 230 KV ESF potential lights, g Pressurizer low pressure safety Detection Method: Steam Generator water level injection signal g
- 1) Reactor Coolant Tavj greater rapidly Increasing in ons or more 1) RIR flow Indicators show zero than 590'F; g steam generators, faliIng in the fIow atter shif t to RtR Is
- 2) RCS pressure greater than 2310 others; and attempted and for greater than 2 psig; or RM-L3, or RM-LIO valid high alarm; hr. subsequently and,RCS l
- 3) RCS pressure less than 1765 n d,
_a,n temperature rising, M psig; and core exit temperature 2) Reactor Building spray and greater than 620*F as Indicated by Possible lif ting of steam genera- Reactor Building air handling a valid Incore thermocouple; or for PRV's and/or sa fety valves. system fall to f unction.
- 4) Inadequate Core Coolleg Alarm.
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EMERGENCY ACTION LEVELS StNMARY EPP-001, ATTACINENT I PAGE 2 of 13, REVISION 2 SYSTEM SITE GENERAL INVOLVED UNUSUAL EVENT ALERT EMERGENCY EERGENCY STEAM INITI ATING COWITION INITI ATING C0tolTION INITIATING CONDITION SYSTEM RAPID SECONDARY SYSTD4 MAKR STEAM LINE EEEAK (e.g., MAJOR STEh4 LINE tEEAK WITH DEPRESSlR IZ ATION. GREATER TPMN 6 IN. EQUIVALENT GREATER THAN 50GPM DIAMETER) WITH A SIGNIFICANT PRIMARY-TO-SECOt0ARY LEAKAGE Ato Detection Method: PRIMARY-TO-SECOt0ARY LEAK RATE. IPolCATION OF FUEL DAMAGE. Rapid decrease In S/G pressure; anc, De+ection Method: Detection Method: Reduced RCS temperature and pressure; and Rapidly decreasing reactor Rapidly decreasing reactor Observation of break or steam dump, , yesswlzer Coolant T,yg, relief or safety valve coolantT,y$dpressurizerlevel; pressure, a pressurizer pressure and inadvertently opened. g RM-L3, or RM-LIO or RM-A9 pressurizer level; g l high alarms; and
- 1) Steam line differential 1) Steam line differential pressure, safety injection pressure, safety injection signal; g High Reactor signal; a d Building pressure alarm; High Reactor Building a d RM-A2 high alarm for pressure alare a d valid rupture in Reactor Bullding m-A2 anJ RM-L1 high alarm
-oR- and
- 2) High stearn flow and Lo-Lo or or low steam 2) High steam flow and Lo-Lo T,yEsure pre safety injection Tavg or low steam pressure signal for rupture downstrean safety injection signal and of MSIV's. m-A9, Gl9A, G19B, or Gl90 or high alarm and RM-L1 valid INITIATING COtolTION high alarm
- RAPID GIOSS FAILtRE OF ONE STEAM GENERATOR TtBE WITH LOSS OF OFFSITE POWER.
Detection Method: Pressurizer low pressure alarm and reactor trip; g Pressurizer low level alarm; and RM-A9, Gl9A, G190, or Gl9C valid high alarm and Pressurizer low pressure safety injection signal; and loss of 115 KV and 230 KV ESF M ential Lights; g RM-L3, or RM-LIO valid high alarms 9 O O O
D4ERGEtCY ACTION LEVELS StNMARY EPP-001, f.TTACINENT I PAGE 3 of 13 REVISION 2 SYST D4 StTE GENERAL INVOLVED UNUSUAL EVENT ALERT EERGENCY EMERGENCY RADIOLOGICAL INIT 1 AlltG C0tolTION SUSTAltED HIGN RADI ATION LEVELS 0- INIT I AT ltG C0tol T ION INI T 1 AT l tG COtol T ION EFFLUENTS GASEOUS EFFLUENT INSTANTANEOUS HIGH AIRBORNE CONTAMINATION WHICH RADIATION MONB10RS DETECT LEVELS EFFLUENT PONITORS DETECT LEVELS RELEASE RATE TECFNICAL IPolCATES A SEVERE DETADATION IN CORRESPOtol?C TO mEATER TIMN 50 CORRESPOtoltG TO 14 TEM /tR WFDLE E0DY SPECIFICATION LIMITS EXCEEDED FOR L TtE CONTROL OF RADIOACTIVE MREM /FR WFOLE 30DY FOR 0.5 FR. m OR 5-REM /FR TINROID AT TE FE. ( APPENDIX B TABLE II, COLUMN 1 MATERI ALS te.g., IPCREASE OF GREATER TIEN 500 MREM /tR WFOLE EXCLUSION NtEA BOUNDARY LNDER ACTUAL 10CFR20) FACTOR OF 1000 IN DIRECT RADIAT10t< PCOY Fm 2 241N. (OR TlVE TIMES METEOROLOGICAL CotolTIONS. READINGS). ItESE LEVELS TO TFE TaitolD) AT Detection Method: TFE EXCLUSION NtEA BOUNDARY FOR Detection Method: Detection Method: ADVERSE METEOROLOGY (PASQUILL F An of the following gaseous STABILITY, IM/SEC WIPO VELOCITY). 1) Radiation M>nitor levels owcoed ef fluent monitors in
- high valid 1) Unexpected valid RMG readings alarm mode for more than I hr.: ' those specified for Site Emergency; l as follows: Detection Method: and a) RMG 2-4, 8-13, or 16: greater FCalculation on Dose Assessment l (due to radioactivity releases to than 2.5 R/hr Any of tne following valid Forms Indicates levels arcesiing, the environment) b) RMG 7,17A,17B, or 18 gaseous of fluent monitor readings: 1-rem /hr whole body or 5-rem /hr l greater than 100 R/hr thyrold at the exclusion area RM-A3 (lodine) c) RMG-1: greater than 1 R/hr 1) RM-A13 (Gas) > 0.3 Mr/ft above boundary using radiation monitor RM-A4 (lodine) Bkdg. for 2 min. OR readings and ef fluent stream flow o 2) Unexpected plant area lodine or rates (measured or assuned) for Any of the following reading 4 particulate airborne concentratfor 2) RM-A14 (Ges) > 2.2 mR/hr. above actual meteorological conditions; times the high alarm setpoint for greater than 1000 MPC. bkgd. For 0.5 hr. w > 22 mR/hr or measured in-situ.
more than I hour. (as per 10CFR20 Appendix B, Table above bkgd. for 2 min. 1) RM-A3 (Gas) RM-A4 (Gas) (CONTINUE 04 EXT PAGE)
- A valid high alarm will include verification of radioactivity concentrations In the sampling media.
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D4ERGENCY ACTION LEVELS StJ4 MARY EPP-0010 ATTACtNENT I PAGE 4 of 13, REVISION 2 SYSTEM SITE GENERAL INVOLVED UNUSUAL EVENT ALERT EMERGENCY EMERGENCY RADIOLOGICAL INITIATING COPolTION INITI ATING COtolTION INITIAL COW il10N EFFLUENTS LIQUID EFFLUENT CotCENTRATIONS RADIOLOGICAL EFFLUENT RELEASE RATE DOSE RATES LISTED BELOW ARE (CON'T) TECINICAL SPECIFICATIONS LIMITS EXCEEDitG 10 TIMES TECINICAL PROJECTED BASED ON GAMMA RADIATION EXCEEDED FOR 15 MIN. ( APPEt0lX B SPECIFICATION INSTANTANEOUS MONITOR (RMG) READINGS AP0/OR TABLE II COLI.NN 2 10CFR20). LIMITS. OTKR PLANT PARN4ETDlS OR ARE Detection Method: MEASURED AT TtE EXCLUSION NtEA Any of the following Ilquid Detection Method: BOUNDARY. ef fluent monitors In ' valid High Alarm for longer than 15 min. g Any of the following
- valid Detection Methods isolation valve (s) faII to close radiation monitor readings for longer than 15 minutes 1) Reactor Building leak rate i RM-L5; w results In calculated dose RM-L7; or a) 10 times High Alarm setpoint rate at exclusion area RM-L9 for lodine for boundary greater than 50 mrom/hr whole body for 0.5 hr; RM-A3 or RM-A4 500 mrem /hr whole body for 2 min.
b) 40 times High alarm setpoint or
, for Gas for 2) Radiation Monitoring Teams measures dose rates greater RM-A3 than 50 mrem /iw for 0.5 hr or RM-A4 g. enter th?n 500 mrem /hr for 2 min. (beta + gamma) at tyV c) RM-L5 or RM-L7 or RM-L9 exclusion area boundary; or 10 times High Alarm setpoint and Isolation valves fall to 3) Radiation Monitoring Teams close. measure thyrold dose rates (equtvaim t I-131 concentrations) greater thant a) 250 mrem /hr (1.3x10-7 CI/cc for 0.5 hr; or b) 2500orom/hr(1.3xtD
^ Cl/ce?,foryminatthe j exclusion area %dary.
- A valid high alarm will include veri fication of radioactivity concentration In the sampling media.
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. a9 O O O
- D4ERGENCY ACTION LEVELS SUPf4ARY EF7-001, ATTACif4ENT I PACE 5 of 13, REvlSION 3 SITE GENERAL SYSTEM EMERGENCY UNUOUAL EVENT ALERT EMERGENCY 1NVOLVED INIT1 ATING C0tolTlON INIT1ATING CONDITION INITI ATING C0tolT10N FUEL INIT!ATING COtolTION POSSIBLE FUEL DAMAGE.
DEmADED CORE WITH POSSIBLE LOSS LOSS OF TWO OF TIREE FISSION DAMAGE FUEL DAMAGE INDICATION. OF C00LABLE GEOMETRY. PRODUCT BARRIER WITH POTENTI AL Detection Method: LOSS OF TIE THIRD BARRIER (e.g., Detection Method: Dose equivalent 1-131 activity - Detection Method: LOSS OF FUEL INTEmlTY Ato PRIMARY COOLANT BOUNDARY AND HIGH concentration greater than limit ir 1) Primary coolant sample Figure 3.4-1 of Technical Indicates equivalent 1-131 POTENTIAL FOR RADIOACTIVITY Speci f ica tions; concentration greater than Wide Range Thot above 700*F, a d RELEASE FROM CONTAltNENT 300 UC1/cc; adT n cold or, Tg,dly diverging (AT rapidly Detection Method: RM-L1 High alarm; and Laboratory or rapi analysi s which Indicates an 2) RM-L1 High alarm and Increasing) or no AT across core; increase in failed f uel of 0.1 laboratory anaylsis which an RM-L1 of f scale (greater than 1) LOCA g Containment Isolation Indicates an increase In 10 cpm) status lights Indicate percent in 30 minutes. incomplete Isolation: failed fuel of 1 percent In 3C min or a total failed fuel of ----------- ---- INITIATING CONDITION -or-5 percent. MAJOR DAMAGE TO t0RE TIMN ONE SPENT FUEL ASSEMBLY IN REACTOR 2) LOCA; a d
----------------- BUILDING OR FUEL IMPOLING BUILDINC FN-A2 high alarm; and INITIATING CONDITION LEADING TO CLAD RUPTURE (e.g., RMG-7and/orRMp18 reading FUEL IntOLING ACCIDENT WITH LARGE WJECT DAMAGES FUEL OR WATEI greater than 10 R/hr; a d RELEASE OF RADIOACTIVITY TO LOSS BELOW FUEL LEVEL). Reactor Building pressure REACTOR m FUEL (MNDLING BUILDING.
greater than 30 psig for at Detection Method: 'least 2 min. Detection Method: or Observations of major damage to 3) Breach of containment Observation of damage to spent more than one spent fuel assembly Integrity (Reactor Building) f uel assembly; and or and RM-L1 off-scal e (> 10 6 Spent fuel pool water below fuel epm)
- 1) RM-A2 high alarm and/or level and ING-17A,17B hlgh alarm af ter accident in Reactor Building; 1) RM-A2 and/or RMG-17A,178 higt or alarm for accident in Reactor
- 2) E -A6 high alarm; E Building or RMG-8 high alarm; 2) RM-A6 and/or RMG-8 high alarm af ter accident in Fuel for accident in Fuel ibniling thndling Building. Building O O O
EMERGEtCY ACTION LEVELS SlNMARY EPP-00lo ATTACINENT I PAGE 6 of 13, REVISION 2 SYSTD4 SITE GENERAL INVOLVED UNUSUAL EVENT ALERT EMERGENCY EE RGENCY STATION INITIATING C0m lTION INITIATING COtolTION INITI ATING C0tolTION INITIATING C0tolTION POWER TOTAL LOSS OF T FSITE POWER OR LOS5 LOSS & OFFSITE POWER AND LOSS Of LOSS OF OFFSITE POWER Ato LDSS Of FAILURE & OFFSITE AND ONSITE OF ONSITE A-C POWER CAPABILITY ALL Ot4 SITE A-C R)WER FOR MORE ONSITE A-C F'0WER FOR MORE TtMN 15 POWER ALONG WITH TOTAL LOSS & THAN 5 MINUTES M I N. EMERGEtCY FEEDWATER MAKEUP Detection Method CAPABILITY Fm SEVERAL 60VRS. Detection Method: Detection Method: COULD LEAD TO EVENTUAL CX)RE MELT
. 1) Loss of 115 KV and 230 KV ESF Ato POSSIBLE FAILURE & TK
- 1) Loss of 115 KV and 230 KV ESF 1) Loss of 115 KV and 230 KV Potential Lights REACTOR BUILDitG.
Potential Lights ESF. Potential Lights g g and 2) A or B Trn. Blackout Seq. Detection Method
- 2) A or B Trn. Blackout Seq. Int. Alarm
- 2) A or B Trn Blackout Seq. Int. Int. Alarm and 1) Loss of 115 KV and 230 KV ESF.
Alarm g 3) Both Diesel Generators Potential Lights. g 3) Both Diesel Generator inoperable. and inoperable ---------------- 2) A or B Trn. Blackout Seq. In t.
- 3) Both Diesel Generators ---------------- lNITIATING CONDITION Alarm inoperable for> 1 hour INITI ATING C0tolTION LOSS OF ALL VITAL ONSITE D-C g LOSS & ALL ONSITE D-C POWER FOR POWER FOR MORE THAN 15 MIN. 3) Both Diesel Generators A PERIOD @ EATER TtMN 5 MitUTES. Detection Method: Inoperable.
Detection Method: 1) D-C bus undervoltage alarms oo 4) Steam driven Emergency all buses; feedwater pump falls to start M and is inoperable for several
- 1) D-C bus undervoltage alarms 2) 480V ESF Channel A or B Loss hours.
- l on alI buses; and ,
of DC Alarm a g!,,,,
- 2) 480 V ESF Channel A or B Loss 3) DG A or B loss of DC Alarm of DC Alarm g -----------------
INITI ATING COtolTION
- 3) DG A or B Loss of DC Alarm LOSS OF FUNCTIONS EEDED FOR PLANT TOT StUTDOWN.
Detection Method:
- 1) Inability to establish charging pump Injection: g.
Inability to establish emergency Feedwater Flow. E
- 2) RtR System not functional l O O O
ENERGENCY ACTION LEVELS StM4ARY EPP-001, ATTACit4ENT I PACE 7 of 13, REVISION 2 SITE GENERAL SYSTEM ALERT EMERGENCY EMERGENCY INVOLVED UNUSUAL EVENT INITIATING CONDITION INITIATING CONDITION INITIATING CONDITION EfGINEERED INITIATING CO WITION ALL ANNUNCIATOR ALARMS LOST. ALL ANNUNCI ATGIS APO PLANT TRANSIENT INITIATED DY LOSS OF SAFEGUARDS ECCS INITIATED (ColNCIDENT WITH FEEDWATER AND CONDENSATE SYSTEMS POSITIVE FarolNG Tmi INITIATION 15 COMPUTER LOST F01 M)RE TIRN 15 Detection Method: MINUTES A,0 PLANT TRANSIENT (PRINCIPAL KAT REMOVAL SYSTEM) NOT SPURIOUS). INITIATED OR IN PROGRESS. FOLLOWED BY FAILURE OF EMERGENCY Observation by operator. FEEDWATER SYSTEM FOR EXTENDED Detection Method: PERIOD. CORE MELTING POSSIBLE IN Detection Method: Valid Safety Injection Signal SEVERAL FOURS. ULTIMATE FAILtRE Observation of event. OF REACTOR BUILDitG POSSIBLE IF INITIATING CONDITION CORE MELTS. EVACUATION OF CONTROL ROOM ANTICIPATED m REQUIRED WITH INITIATING CONDITION Detection Method: INITIATING C0tolT10N CONTROL OF SFUTDOWN SYSTEM EVACUATION OF (X)NTROL ROON AND FAILIRE OF A PRESSURIZER 01 STEAM Reactor trip on steam flow > ESTABLISKD FROM LOCAL STATIONS. CONTROL OF SIUTDOWN SYSTEMS NOT GENERATOR SAFETY OR RELIEF VALVE TC feodwater flow; a d ESTABLISIED FRO 4 LOCAL STATIONS RESEAT (EXCEEDING NORMAL WEEPAGE). Decreasing wide-range steam IN 15 MIN. Detection Method: generator levels toward off-scale Detection Method: low on all steam generators; Detection Method: and Pressurizer or steam generator 1) Emergency feedwater flow safety or relief valve opens and Indicators Indicate zero flow
- then falls to reset as Indicated Same as initiating event. 2 min. af ter required; by:
Status lamps Indicate
- 1) Valid open Indication of same as initiating condition.
emergency feedwater pumps not Pressurizer reIIef or safety running 2 min after required; valvs position Indication and, lights 3) Emergency Feedwater cannot be or restored within 30 min. g valld acoustical monitor Indication. or
- 2) Esual and/or audible Indication at vent stacks of open steam generator safety or relief valve; g Excess feedwater flow to and steam flow from af fected generator.
O O e
D4ERGEtCY ACTION LEVELS SIM4ARY EPP-00lo ATTACINENT I PAGE 8 of 13, REVISION 2 SYST D4 SITE GENERAL INVOLVED UNUSUAL EVENT ALERT EMERGENCY EMERGENCY EtGI NEERED INITIATING C0tOIT10N INITIATING C0tolTION INITI ATito C0tolTION SAFEQUARDS LOSS OF ENGINEERED SAFETY FEATLRE REACTOR COOLANT PUMP LOCKED ROTOF TRANSIENT REQUIRING OPERATION OF (CON'T) FUFCTION REQUIRING TECINICAL WITH FUEL DAMAGE. SFUTDOWN SYSTD4S WITH FAILURE TO SPECIFICATICN SFUTDOWN. (TECFN i- TRIP WHICH RESULTS IN (DRE LW4 AGE CAL SPECIFICATIONS 3.3.2) Detection Method: OR ADDITIONAL FAILURE OF CORE Reactor coolant pump auto trip C00LitG AND MAKEUP SYSTEMS WHICH Detection Method: alarm; M COULD LEAD TO CORE MELT.
- 1) Engineered Safety Features Reactor trip on low Activation System found Inop- coolant flow; g Detection Methods erable Reactor coolant ptnp phase over current relay actuation; and Reactor remains critleal af ter INITIATING C0tolT10N valid RML-1 Alarm. attempted trip and s tolCATIONS OR ALARMS ON PROCESS OR EFFLUENT PARAMETERS NOT l } RML-1 a larm, o FUtCTIONAL IN THE CONTROL ROOM TO -----------------
AN EXTENT REQUIRING SFUTDOWN AS INITI ATING C0tolT10N 2) Flow Indicators on safety PER TECFNICAL SPECIFICATIONS; OR, LOSS OF ALL FUtCTIONS NEEDED FOR injection system and RIR systems OTHER SIGNIFICANT LOSS OF PLANT COLD SFUTDOWN. show zero flow with safety ASSESSMENT OR COMMUNICATION Injection initiated. o CAPABILITY. Detection Method:
- 3) Status lights show safety Detection Method 1) Loss of RfR system not functional and injection *ystem and RtB pumps Radiation Monitoring System; or 2) Inability to reject heat to the not running with safety Loss of alI meteorological systems condenser. Injection Initiated.
or 3 SignifIcant loss of communication capability of f site; ----------------- - _o,r, 4 ) Loss of the plant computer INITIATING C0tolTION and the TSC computer FAILtRE OF TIE REACTOR PROTECT 100 SYSTD4 TO INITIATE Ato C04PLETE / TRIP WHICH BRINGS TIE REACTOR SUBCRITICAL. Detection Method: Reactor remains critical after trip Initiation. O O O
2 N O I O I TS Y NI C EV LN 4 E AE HR RG ER C A , NE T3 EM T1 GE A
,fo 1
09 0
- E PG PA EP 1
0 t a E S h s N t n AI eai R irr t T f Y m Y N T re C O E ot N I F js EE T A : ay T G l S d o ms t R o 0 o SE t h f y M t t ot E C T i e e M nf G C . N ES n ioa s s . F N t n I T F O io a s o A AI t vt i Y I T c r at R T EC e eec A Rt t sf n N IN I U e b eu I F F D Od f f i S S L E d V l E u o O L G c N N O I t I T a T C h . C E t s A N F m O F ee Y T A rt C N R E IT I Y d i ys f E L D L . o s G A N LS h f oy R O AM t E C I E e t N TT M ne E G NS iof a N EY n I TS o t s T O i a A P Y t vt I T c rc T EE e ee I RF t sf N I A e bf I F S D Oa S N n e I ogr M ini ti f 5 1 cm er an t i N ef gmi d nn T N Nm O T ect1 oi5 E I r a T E : V E I R d ih f t icna D O o i dh L A U N M O C G h t e gwnt mI e S N M nr nr U G I iloaoo N N T n i m U I S o t at ag T A i a A L t c v* v n rcri TI E e eiet R t s vs s IN I e b eb a I F D Od ol D E O MV EL T O SV E Y N R SI I F
D4ERGENCV ACTION LEVELS
SUMMARY
EPP-001, ATTACINENT I PAGE 10 of 13 0REV1SION 2 SITE GENERAL SYSTEM UNUSUAL EVENT ALERT EMERGENCY EMERGENCY INVOLVED INITI ATING COFOITIOh INITip'ING CotolTION SECtRITY INITIATING COtolTION INITIATING CONDITIGN ONGOING SEVERE SECLRITY TIRE %T SECURITY TIREAT INVOLVING SECURITY TIREAT RESULTitG IN LOSS SECURITY TIREAT OR ATTEMPTED ENTR1 IMMINENT LOSS OF PtnSICAL 00NTROL OF PF#SICAL CONTROL OF TIE OR ATTEMPTED SABOTAGE. Detection Method OF TIE PLANT. FACILITY.
., Detection Method: Security safeguards contingency event which results in Detection Method: Detection Method:
- 1) Report to the Control Room by adversarios commandeering an observer. area of the plant, but not Physical attack on the Plant Physical attack on the Plant has or Impacting shutdown capability. Involving imminent occupancy of resulted in occupation of the
- 2) Alarm of Integrated Fire and control room and auxiliary control room and the auxillary Security Panel. shutdown panels. shutdown panels by unauthorized personnel.
O O O
EMERGENCY ACTION LEVELS StNMARY EPP-001, ATTACINENT I PAGE 11 of 13, REVISION 2 SYSTEM SITE GENERAL INVOLVED UNUSUAL EVENT ALERT EMERGENCY EMERGENCY NATlHAL INITIATING C0tolTION INITI ATING C0tolTION INITIATING CONDITION PIENOMENON NATURAL EVENTS SEVERE NATLRAL EVENT NEAR SITE. SEVERE NATURAL PHENCNENON BEIPO EXPERIENCED m FROJECTED WITN
- a. EARTHNAKE PLANT NDT IN COLD SFUTDOWN.
- b. TORNADO ON SITE a. EARTfQUAKE mEATER TtRN TIE
- c. FE RICANE NEAR SITE (OBE) LEVEL a. EARTIQUAKE mEATER TIMN SSE
- b. TORNADO STRIKING FACILITY LEVELS.
- c. SYSTAIED ImRICAE wit 0S b. SYSTAINED WIPOS IN EXCESS OF Detection Method: GREATER TIMN 75 MPN 100 MPH ON SITE.
Detection Method:
- a. Seismic Recording System Detection Method:
Start Indication. a) Seismic Response Spectrum
- b. Observation of event. Trouble Annunciator a. Reactor Building Foundation
- c. Observation of event. b) Observation of event Seismic Switch (SSE) c) Meteorological Monitoring System Data or Weather Bureat b. Meteorological Monitoring Re port. System Data.
F O O O
D4ERGENCY ACTION LEVELS SINMARY EPP-001, ATTACINENT I PAGE 12 of 13, REVISION 2 SITE GENERAL SYSTEM UNUSUAL. EVENT - ALERT EMERGENCY EMERGENCY INVOLVED INITIATING CONDITION MAtNADE INIT I ATING COtolTION INITIATING CONDITION PHENOMENON OTTER FAZARDS BEING EXPERIENCED OTTER FAZARDS BEING EXPERIEtCED 01 OTER FAZARDS BEING EXPERIENCED OR PROJECTED WITH PLANT TOT IN PROJECTED WHICH FME TIE POTENTI Al OR PROJECTED WHICH IAVE A COLD SHITDOWN: FOR ENDANGERING TIE FACILITY SIGNIFICANT POTENTIAL FOR a. AIRCRAFT CRASH INTO VITAL AFFECTING PLANT SAFETY. STRUCTtRES.
- a. ONSITE AIRCRAFT CRASH. a. AIRCRAFT CRASH ON FACILITY. b. MISSILE OR EXPLOSION IMPACT
- b. ONSITE TRAIN DERAILMENT. b. MISSILE ItfACTS ON FACILITY ON FACILITY RENDERING SEVERE
- c. ONS!TE EXPLOSION (EXCLUDING WITH RESULT ANT MAJOR DAMAGE. DAMAGE TO StUTDOWN EQUIPMENT PLANNED ACTIVITIES). c. KNOWN EXPLOSION AT FAClf.lTY c. ENTRY OF T0XIC 01 FLAMHABLE
- d. HEAR OR ONSITE T0XIC OR RESULTING IN MAJOR DAHAGE TO GASES INTO VITAL AREAS WHICH FLAMMABLE GAS RELEASE OF A PLANT STRUCTLRES 01 INVOLVE A SIGNIFICANT MAGNITUDE TtMT TIREATENS EQUIPMENT. DEGRADATION OF PLANT PERSONNEL. d. ENTRY INTO FACILITY ENVIRONS SAFETY.
- o. TURBINE ENERATOR ROTATING OF T0XIC OR FLAMMARLE GASES Detection Method:
C0t('ONENT FAlLlRE CAUSING IN C0tCENTRATION WHICH EXCEEL RAPID PLANT SHITDOWN. TIE LIMITS OF FLAMMABILITY ON a) Alrcraf t crash causing T0XICITY. damage or fire in: Detection Meti.A: e. TtRBINE GENERATOR FAILURE 1) Reactor Building; or CAUSING CASING PENETRATION. 2) Control Room; or
- a. Observation of event. 3) Auxillary Bullding; g
- b. Observation of event. Detection Method: 4) Fuel thndling Dullding;or
- c. Observation of explosion or 5) DG Building; or warning from offsite. a) Observation of aircraf t crast 6) Intermediate Building
- d. Obser:vation of release or into Plant structures. 7) SW Intake Structures warning from of fsi te. b) Observation of missile
- e. Turbine trip and observation impacts on Plant structures b) Loss of functions needed for -
of turbine mal f unction or or congonents. hot shutdown. (see page 6 of failure. c) Observation of damage by this Attachment) explosion. d) Observation or warning from c) Entry of toxic or flammable outside the Plant; detection gases into: of gases (using portable 1) Control room; or Instrumentation) which exist 2) Cable spreading rooms; g in concentrations which 3) Reactor Building; o exceed the limits of 4) Switchgear room: or flammability or toxicity. 5) Saf e shutdown panels; or e) Turbine trip and observation 6) Emergency diesel of penetration of casing, generator rooms; as detected by portable in-strumentation g which ren-ders a train of a safety-related system inoperable. G G e
ENERGENCY ACTION LEVELS
SUMMARY
EPP-001, ATTACINENT I PAGE 13 cf 13, REVISION 2 SYSTEM SITE GENERAL INVOLVED UNUSUAL EVENT ALERT EMERGENCY EMERGENCY OTTER INITIATING CONDITION INITIATING CONDITION INITIATING CONDITION LOSS OF CONTAltNENT INTEGilTY OTTER PLANT CONDITIONS EXIST TIM 1 OTIER PLANT COrolTIONS EXIST TIM 1 WARRANT ACTIVATION OF TECINICAL WARRANT ACTIVATION OF ENERGENCY REQUIRING TECtNICAL SPECIFICATION SFUTDOWN (TECFNICAL SPECIFICATION SUPPORT CENTER AND PLACING FACILITIES Ato RADIATION 3.6.1.1) EMERGENCY OPERATIONS FM:lLITY MONITORING TEAMS AND A PERSONNEL ON STAND DY PRECAUTIONARY PUBLIC WARNING. Detection Method:
- 1) Any automatic containment Detection Method: Detection Method:
Isolation valve found to be Inoperable or As determined by Emergency As determined by Emergency
- 2) Reactor Building air lock Diractor. Director.
Inoperable g
- 3) Penetration (s) f all leak test (as specified in Technical Specifications)
INITIATING CONDITION TRANSPORTATION OF OVEREXPOSED AND/OR CONTAMlNATED, 1NJURED INDIVIDUAL FROM SITE-TO IDSPITAL. Detection Method: Same as initiating condition. - INITIATING CONDITION OTIER PLANT CONDIT10NS EX1ST REQUIRING OTTER TIAN NORMAL PLANT SIUTDOWN AND REQUIRING INCREASED AWARENESS ON TIE PART OF STATE OF F ICI ALS. Detection Method: As determined by Emergency Director. d O O O
EPP-001 ATTACHMENT II PAGE 1 of 1 REVISION 2 IMMEDIATE ACTION
SUMMARY
UNUSUAL IMMEDIATE ACTIONS EVENT ALERT SITE GENERAL
- 1. ANNOUNCEMENT TO PLANT PERSONNEL
- 2. SOUND RADIATION EMERGENCY ALARM N/A 3 NOTIFY _ SECURITY SHIFT LEADER
- 4. NOTIFY FAIRFIELD PUMP STORAGE FACILITY N/A N/A 5 ENSURE ON-SHIFT PERSONNEL RESPONSE NOTIFY LOCAL AUTH OF
- 6. EARLY WARNING SIREN SYSTEM RECOMMENDATION N/A N/A 7 ACTIVATE EWSS IF REQUIRED N/A N/A
- 8. INITIAL NOTIFICATIONS PER EPP-002 ,
~
9 EMERGENCY LOG ESTABLISHED _
- 10. OFF SITE EMERGENCY SERVICES, IF REQUIRED -
ACTIVATE TSO/OSC OR NOTIFY EMERGENCY
- 11. RESPONSE PERSONNEL N/A
- 12. NOTIFY OFF-SITE EMERGENCY COORDINATOR N/A ENSURE TSC/OSC ARE ACTIVITED OR EMERGENCY 13 RESPONSE PERSONNEL NOTIFIED N/A ENSURE EOF IS ACTIVATED OR EMERGENCY
- 14. RESPONSE PERSONNEL NOTIFIED N/A N/A DETERMINE IF SITE EVACUATION IS REQUIRED 15 (INCLUDING FAIRFIELD PUMP STORAGE FACILITY) N/A O .
O e
.( s
. l SOUTH CAROLINA ELECTRIC AND GAS COMPANY ;
VIRGIL C. SUMMER NUCLEAR STATION NUCLEAR OPERATIONS ECIAR OP,.ERATIONEI
. COPY Mo. IS'E"' '"""' '
EMERGENCY PLAN PROCEDURE EPP-001 ACTIVATION AND IMPLEMENTATION OF EMERGENCY PLAN REVISION 3 AUGUST 12, 1982 NON-SAFETY RELATED O Reviewed by:
}l/ dzv:b E 2 7 f.'L ORIGINATOR TCif this revision) / Date f2 aldr DISCIPLINE SUPERVISOR ebok
~/ Date Approved:
l PLANT MANAGER YlW
~'Date Date Issued:
O V
=
~-_. .
- EPP-001
! PAGE i REVISION 3 8/12/82 LIST OF EFFECTIVE PAGES i
PAGE REVISION i i ! 1 3 i 11 3 : 1 3 l 2 ' 3 3 - 3 4 4 3 5 3 s 6 3 , 7 3 8 3 c 9 3 10 3 4 11 3 ATTACHMENTS Attachment I Pages 1 thru 13 3 Attachment II 3 l lO I O w--.mv---eew- m. - c - , - < - - - - - - - - . - - - _y-w-e ---,-r---n-m,, -,w v m -
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.-. . - . . _ _ _ _ ~ .
EPP-001 PAGE 11 REVISION 3 8/12/52 TABLE OF CONTENTS
=
List of Effective Pages i 1.0 PURPOSE 1
2.0 REFERENCES
1 30 CONDITIONS AND PREREQUISITES 1 4.0 PROCEDURES 2 4.1 CLASSIFICATION OF EVENT 2 4.2 IMPLEMENTATION OF EMERGENCY PLAN 2 4.3 UNUSUAL EVENT 2 4.4 ALERT 3 4.5 SITE EMERGENCY 6 4.6 GENERAL EMERGENCY 9 ATTACHMENTS Attachment I Emergency Action Level Summaries Attachment II Immediate Actions Summary l O I
.-,.._..-,m _ -, , . - - , . - - , _. _ . . _ _ . - _ . . - --. , -. - - _ _ _ _ .
EPP-001 REVISION 3 8/12/82 p 1.0 PURPOSE V To define and implement the Emergency Action Levels (EAL's) that will initiate the Emergency Plan and to provide a means of classifying the emergency.
2.0 REFERENCES
2.1 " Virgil C. Summer Nucleair 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. 2.3 EPP-021, Activation of the Early Warning Siren System. 2.4 Policy Memorandum No. 25, Issuance, Control, and Usage of Radio Pagers. 3.0 CONDITIONS AND PREREQUISITES 31 The Emergency Plan shall-be initiated whenever an-
" Initiating Condition" (as defined in Attachment I) has been reached or exceeded.
NOTE: The implementation of any specific emergency plan procedure (except this procedure) does not necessarily implement the Emergency Plan, but may do ao at the discretion of the Emergency Director / Interim Emergency Director. For example; a small chlorine leak would implement the toxic release procedure but not necessitate implementation of the Emergency Plan; whereas a large release with the potential for affecting the level of safety of the plant would implement the toxic release procedure and the Emergency Plan due to the declaration of an Unusual Event. 3.2 The " Initiating Condition" shall be used to determine the applicable Emergency Action Level (EAL) per Attachment I. i i O PAGE 1 of 11
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- - - - - 3
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EPP-001 REVISION 3 8/12/82 j /"'s 33 The " Detection Methods" of Attachment I are to be used "s s
,) only as an aid to determine if an " Initiating Condition" has been reached or exceeded. Other detection methods, not listed in Attachment I, may be used to determine if an
" Initiating Condition" exists. The existence of one or more of the detection methods could be but is not necessarily an indication that an " Initiating Condition" exists.
4.0 PROCEDURES 4.1 Upon recognition of an abnormal plant or site condition the observer shall notify the Shift Supervisor of the potential emergency plant condition. 4.2 The Shift Supervisor shall: A. Evaluate the conditions and determine the applicable Emergency Action Level (EAL) per the Emergency Action Level Summary, Attachment I. B. Declare an EAL and implement the Emergency Plan per the applicable section of this procedure. Unusual Event (Section 4.3) or Alert (Section 4.4) O. or Site Emergency (Section 4.5) or General Emergency (Section 4.6) 43 Unusual Event 431 Immediate Actions: (Immediate Action Summary, See Attachment II) The Emergency Director (ED) or Interim Emergency Director (IED) shall accomplish or cause to be accomplished the following: A. Annoance the emergency condition to all plant personnel over the plant paging system. ATTENTION ALL PERSONNEL: THE STATION IS IN AN UNUSUAL EVENT CONDITION. THE INITIATING EVENT IS . O PAGE 2 of 11
EPP-001 REVISION 3 8/12/82 NOTE: [ REPEAT ANNOUNCEMENT]. B. Notify the Security Shift Leader to implement appropriate security measures. C. Ensure that on-shift personnel have responded to their emergency response stations. , D. Ensure that t'he Initial Notifications are completed per EPP-002. E. Ensure that the Emergency Log is established and maintained. F. Request Offsite Emergency Services (Fire, Medical, LLEA, etc.) if required per EPP-002, if necessary. NOTE: Consideration should be given to access routes taken. 4.3.2 Follow-Up Actions: l The ED/IED shall continually assess the status of the Unusual Event per Attachment I for possible escalation to a higher emergency classification or (m- termination of emergency condition. 4.3 3 Final Actions: When the emergency condition has cleared, close out the Unusual Event with a verbal summary to offsite authorities within 24 hours and close out of the Emergency Log. 4.4 Alert 4.4.1 Immediate Actions (ED/IED): (Immediate Action i Summary, Attachment II) The Emergency Director (ED) or Interim Emergency Director (IED) shall accomplish or cause to be accomplished the following: !O PAGE 3 of 11
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EPP-001 REVISION 3 8/12/82 A. O Announce the emergency condition to all plant personnel over the plant paging system. ATTENTION ALL PERSONNEL: THE STATION IS IN AN ALERT CONDITION. THE INITIATING EVENT IS . ALL EMERGENCY RESPONSE PERSONNEL REPORT TO THEIR STATIONS. B. If necessary, sound the Radiation Emergency Alarm. C. Repeat the announcement. NOTE: [ Repeat steps A, B, and C every two minutes
'for six minutes.]
D. Notify the Security Shift Leader to implement appropriate security measures. E. Ensure that on-shift personnel have responded to their emergency response stations. F. During off-normal hours, call in emergency response personnel by activating the SCE&G Radio Pager System as per Policy Memorandum No. 25. G. Ensure that the Initial Notifications are completed per EPP-002. H. Ensure that the Emergency Log is established and maintained. I. Request Offsite Emergency Services (Fire, l Medical, LLEA, etc.) if required per EPP-002. l l NOTE: Consideration should be given to access routes taken. i O PAGE 4 of 11
. . . ~ - . . . , . . . , . . . . . . - ,m ,n -
c
EPP-001 REVISION 3 8/12/82 J. Ensure that TSC/OSC are being activated per O. EPP-016 and/or notification of Emergency Response Personnel is initiated per EPP-002. . K. Determine if the site evacuation is required. (Including Fairfield Pump Storage Facility). 4.4.2 Immediate Actions (All other personnel): A. Emergency Res'ponse Personnel report to their designated stations. B. Non-essential personnel continue assigned duties and await further instructions. C. If the radiation emergency alarm is initiated, all Personnel in the Radiation Control Area report to the Radiation Access Control Area on . the 412' level of the Control Building. 4.4.3 Follow-up Actions The ED/IED shall: A. Notify the Offsite Emergency Coordinator of the emergency and current plant conditions. () B. Verify. that the TSC/OSC are manned and activated per EPP-016. C. Ensure that updated follow-up notifications are made per EPP-002. D. Continue assessments and corrective actions to mitigate the emergency condition and place the plant into a safe and controlled condition. E. Make assignments to his staff to mitigate the emergency conditions per established Emergency Plan Procedures (EPP's) or as required for conditions not covered by procedures. P. Continually assess the status of the Alert i condition per Attachment I for possible escalation to a higher emergency classification, down-grading to an Unusual l Event, or close out of emergency condition. O PAGE 5 of 11
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EPP-001 REVISION 3 8/12/82 4.4.4 Final Actions: A. When emergency conditions clear to allow for close out or down-grading of the Alert condition, the ED shall ensure that offsite authorities are:
- 1. Notified verbally by normal emergency communica,tions.
- 2. Provided with a written summary within 8 hours of the close out of the emergency or down-grade of the emergency classification.
B. Initiate EPP-017, Post-Recovery and Re-Entry as required. 4.5 Site Emergency 451 Immediate Actions (ED/IED): (Immediate Action Summary, see Attachment II) The Emergency Director (ED) or Interim Emergency Director (IED) shall accomplish or cause to be accomplished the following: () A. Announce the emergency condition and site evacuation to all plant personnel over the plant paging system. ATTENTION ALL PERSONNEL: THE STATION IS IN A SITE EMERGENCY CONDITION. THE INITIATING EVENT IS . ALL EMERGENCY RESPONSE PERSONNEL REPORT TO THEIR STATIONS. ALL NON-ESSENTIAL PERSONNEL EVACUATE THE SITE PROCEED TO . B. Sound the Radiation Emergency Alarm. C. Repeat the announcement. NOTE: [ Repeat steps A, B, and C every two minutes for six minutes.] PAGE 6 of 11
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EPP-001 REVISION 3 8/12/82
/)
k,s,/ D. Notify the Security Shift Leader to implement appropriate security measures.
\
E. Notify the Fairfield Pump Storage Facility of site evacuation. F. Implement EPP-021. j G. During off-no,rmal hours, call in Emergency Response Personnel by activating the SCE&G Radio Pager System as per Policy Memorandum No. 25. H. Ensure that on-shift personnel have responded to their emergency response stations. I. Ensure that the Initial Notifications are completed per EPP-002. J. Ensure that the Emergency Log is established and maintained. K. Request Offsite Emergency Services (Fire, Medical, LLEA, etc.) if required per EPP 002 . - NOTE: Consideration should be given to access (~ routes taken. O] L. Notify the Offsite Emergency Coordinator of the emergency and current plant conditions. M. Ensure that TSC/OSC/ EOF are being activated per EPP-016 and/or notification of Emergency Response Personnel is initiated per EPP-002.
- 4.5.2 Immediate Actions (All other personnel):
A. Emergency Response Personnel report to their designsted stations. l B. Non-essential personnel evacuate the site, j proceed to their private residence or offsite holding area as designated by the ED, and await , further instructions. \ () v PAGE 7 of 11
EPP-001 REVISION 3 8/12/82 /~') C. Personnel in the Radiation Control Area report (m/ to the Radiation Access Control Area on the 412' level of the Control Building, unless otherwise directed. 4.5.3 Follow-Up Actions A. Verify that the TSC/OSC/ EOF are manned and activated per, EPP-016. - B. Ensure that updated follow-up notifications are made per EPP-002. C. Continue assessments and corrective actions to mitigate the emergency condition and place the plant into a safe and controlled condition. D. Make assignments to his staff to mitigate the emergency conditions per established Emergency Plan Procedures (EPP's) or as required for conditions not covered by procedures. E. Continually assess the status of the Site Emergency condition per Attachment I for possible escalation to a higher emergency classification, down-grading to an Unusual ( Event, or Alert, or close out of emergency condition. F. Verify site evacuation is complete and all personnel are accounted for. (Including Fairfield Pump Storage Personnel). 4 5.4 Final Actions: A. When emergency conditions clear to allow for close out or down-grading of the Site Emergency condition, the ED shall ensure that offsite ' authorities are:
- l. Notified verbally by normal emergency communications.
and 2. Provided with a written summary within 8 hours of the close out of the emergency or down-grade of the emergency classification. B. Initiate EPP-017, Post-Recovery and Re-Entry as required. PAGE 8 of 11
EPP-001 REVISION 3 8/12/82 4.6 General Emergency (~
'~
4.6.1 Immediate Actions (ED/IED): (Immediate Action Summary, see Attachment II) The Emergency Director (ED) or Interim Emergency Director (IED) shall accomplish or cause to be accomplished the following: A. Announce the ' emergency condition and site evacuation to all plant personnel over the plant paging system. I ATTENTION ALL PERSONNEL: THE STATION IS IN A GENERAL EMERGENCY CONDITION. THE INTIATING E*.*ENT IS . ALL EMERGENCY RESPONSE PERSONNEL REPORT TO THEIR STATIONS. ALL NON-ESSENTIAL PERSONNEL EVACUATE THE SITE. PROCEED TO . O B. Sound the Radiation Emergency Alarm. C. Repeat the announcement. NOTE: [ Repeat steps A, B, and C every two minutes for six minutes]. D. Notify the Security Shift Leader to implement appropriate security measures. E. Notify the Fairfield Pump Storage Facility of Site Evacuation. F. Implement EPP-021. G. During off-normal hours , call in Emergency Response Personnel by activating the SCE&G Radio Pager System as per Policy Memorandum No. 25. H. Ensure that on-shift personnel have responded to their cmergency response stations. q (J PAGE 9 of 11
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EPP-001 REVISION 3 8/12/82 () I. Ensure that the Initial Notifications are completed per EPP-002. J. Ensure that the Emergency Log is' established and maintained. K. Request offsite Emergency Services (Fire, Medical, LLEA,, etc.) if required per EPP-002. NOTE: Consideration should be given to access routes taken. L. Notify the Offsite Emergency Coordinator of the emergency and current plant condition. M. Ensure that TSC/OSC/ EOF are being activated per EPP-016 and/or notification of Emergency Response Personnel is initiated per EPP-002. 4.6.2 Immediate Actions (All other personnel): A. Emergency Response Personnel report to their designated stations. B. Non-essential personnel evacuate the site, proceed to their private residence or offsite Os holding a as designated by the ED, await further instructions. C. Personnel in the Radiation Control Area report to the Radiation Access Control Area on the 412' level of the Control Building, unless otherwise directed. i O PAGE 10 of 11 y- - - - - --- ,,v. - , . - - - - , - .---,n- - - ,
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EPP-001 REVISION 3 8/12/82 4.6.3 Follow-up Actions
)
The ED/IED shall: A. Verify that the TSC/OSC/ EOF are manned and i activated per EPP-016. B. Ensure that updated follow-up notifications are
. made per EPP,002.
C. Continue assessments and corrective actions to mitigate the emergency condition and place the plant into a safe and controlled condition. D. Make assignments to his staff to mitigate the emergency conditions per established Emergency Plan Procedures (EPP's) or as required for conditions not covered by procedures. E. Continually assess the status of the General Emergency condition per Attachment I for possible down-grading to an Unusual Event, Alert, or Site Emergency, or close out of emergency condition. F. Verify site evacuation is complete and all personnel are accounted for. (Including O Fairfield Pump Storage Personnel). 4.6.4 Final Actions: A. When emergency conditions clear to allow for I close out or down-grading of the General Emergency condition, the ED shall ensure that offsite authorities are:
- 1. Notified verbally by normal emergency communications.
- 2. Provided with a written summary within 8 hours of the close out of the emergency or down-grade of the emergency classification.
B. Initiate EPP-017, Post-Recovery and Re-Entry as required. l l O PAGE 11 of 11 , _ . . _ _ . . . . . _ . . . , . _ . - . _ _ . _ _ ._ _._._. _ _ _ . _. . . . . . _ _ . ~
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U) \ EMERGEtCY Aci d LEVELS
SUMMARY
EPP-001, ATTACIN PAGE 1 of 13, REVISION 3 SYSTEM SITE GENERAL INVOLVED UNUSUAL EVENT ALERT EMERGENCY EMERGENCY REACTOR INITIATING CotolTION INITI ATito COtolTION INITI ATING COtOITION INITIATING cot 0lTION COOLANT- EXCEEDING TECifilCAL SPECIFICATION RAPID FAILURE OF SEVERAL STEAM KNOWN LOSS-OF-COOLANT ACCIDENT SMALL APO LARGE LOCAs WITH FAILURE SYSTEM PRIMARY TO SECONDARY 01 PRIMARY GENERATG1 TUBES (e.g., SEVERAL (LOCA) GREATER TIAN CHARGING PUW OF ECCS TO PERFORM LEADING TO ' SYSTEM LEAK RATES FUNDRED GPM PRIMARY-TO-SEC0tOARY CAPACITY. SEVERE CORE DEGRADATION 01 MELT. i LEAK RATE). ULTIMATE FAILURE & REACTOR Detection Method: Detection Method: BUILDING POSSIBLE FOR MELTDOWN Primary to secondary leak rate Detection Method: Pressurizer low pressure reactor SEQUENCES. greater than 1 gpn total for more trip; a d than 4 hours or greater than 500 Pressurizer low pressure alarm and Pressurizer low pressure safety Detection Method: gpd per steam generator as reactor trip; g injection signal, a d Identitled by daily RCS leakage Pressurizer low level alarm; a d High Reactor Building pressure, safety injection signal ulth evaluation; or RM-A9, Gl9A, G198, or G19C valid and reactor trip; g Primary system leak rate greater high alarm; M High Reactor Building sump level 1) Status lamps Indicate safety than those specified In Technical Steam generator water level and ; injection and Rift pumps not Speci fication 3.4.6.2 as identi fied rapidly increasing in one or more High Reactor Building hornldity; r unning : w by dally RCS leakage evaluation, steam generator (s), falling In the and 2) Flow Indicators for Safety others; g RM-A2 high alarm injection System read zero; and
- 1) > 0 pressure boundary lealiage RM-L3, or RM-L10 valid high alarm RMG-5, FNG-7, RMG-18, high al arm;
- 2) > 1 gpm unidentified for more and -----------------
and RM-A2 high alarm; than 4 hours Possible lif ting of steam INITI ATING COtolTION
- 3) > 10 gpm identitled RCS leakage generator PRV's and/or safety RAPID FAILURE & SEVERAL STEAM for more than 4 hours. valves. GENERATOR TUBES (SEVERAL WHORED ------------------
- 4) > 33 gpm controlled leakage (at GPM PRIMARY-TO-SEC0tOARY LEAK INITIATING CONDITION 2235 + 20 psig for more than 4 ----------------- RATE) WITH LOSS OF &FSITE POWER. SMALL LOCA AND INITI ALLY SUCCESSFUL hrs.) INITIATING CONDITION ECCS. SUBSEQUENT FAILURE OF
- 5) > 1 gpm RCS pressure Isolation REACTOR COOLANT LEAKAGE RATE Detection Method: . REACTOR BUILDING KAT REMOVAL valve per table 3.4-1 for EXCEEDS 50 GPM. SYSTEMS OVER SEVERAL FOURS (X)ULD
_ _ Srealef,1ha,n_4_h_our,s ____ Pressurizer low pressure clarm and LEAD TD (X)RE MELT AND POSSIDLE INITI ATitG C0tolTION Detection Methods reactor trip, or, pressurizor level FAILURE OF TE REACTOR BUILDING. ABNORMAL REACTOR COOLANT TEMP. rapidly decreasing a_nd, n AND/OR PRESSURE OR ABNORMAL FUEL 1) Excessive Reactor Make-up to Pressurizer !ow-level alarm; M Detection Method: TEMPERATURE TtAT WOULD itolCATE A the Volume Control Tank RM-A9, G19A, G198, or G19C valid Pressurizer low pressure reactor LOSS OF SUBCOOLING MARGIN OR 2) Operational Leakage Test high alarm; and loss of Il5KV a-J trip; a d OVERPRESSURIZATION. Procedure STP-114.002/ 230 KV ESF potential lights, a d Pressurizer low pressure safety Detection Method: Steam Generator water level injection signal and
- 1) Reactor Coolant Tavg greater rapidly increasing in one or more 1) Rift flow Indicators show zero than 590*F; w steam generators, falling in the flow af ter shi f t to RFf1 1 s
- 2) RCS pressure greater than 2310 others; a_nd attempted and for greater than 2 psig; w RM-L3, or RM-L10 valid high alarm; hr. subsequently and RCS
- 3) RCS pressure less than 1765 g temporature rising, g psig; and core exit temperature 2) Reector Building spray and greater than 620*F as indicated by Possible lif ting of steam genera- Reactor Building air handling a valid incore thermocouple; or for PRV's and/or safety valves. system fall to function.
- 4) Inadequate Core Cooling Alarm.
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EMERCENCY AC. ,2 LEVELS
SUMMARY
EPP-001, ATTACtM PAGE 2 of 13, REvlSION 3 SYSTEM SITE GENERAL INVOLVED UNUSUAL EVENT ALERT EMERGENCY EMERGENCY . STEAM INITIATitG CONDITION INITIATING CONDITION INITI ATitG CorolTION SYSTEM RAPID SEC0f0ARY SYSTEM MAJOR STEAM LINE OREAK (e.g., MAJOR STEAM LINE BREAK WITH DEPRESSUR IZ ATION. GREATER THAN 6 IN. EQUIVALENT GREATER TinN 50GPM ' DIAMETER) WITH A SIGNIFICANT PRIMARY-TO-SEC0f0ARY LEAKAGE AND Detection Method: PRIMARY-TO-SEC0f0ARY LEAK RATE. INDICATION OF FUEL DAMAGE. Rapid decrease in S/G pressure; g Detection Method: Detection Mothod: Reduced RCS temperature and pressure; M Rapidly decreasing reactor Rapidly decreasing reactor Observation of break or steam dump, , pressurizer rollet or safety valve coolant pressure,T,yEd a pressurizer level; Coolant T,yg,ressure pressurizer p and inadvertently opened. M RM-L3, or RM-LIO or RM-A9 pressurizer level; and high alarms; g
- 1) Steam IIne differential 1) Steam line differential pressure, safety injection pressure, safety injection signal; a d High Reactor signal; a d Building pressure alarm; High Reactor Building and RM-A2 high alarm for pressure alarm a_nd n valid rupture in Reactor Building IN-A2 and RM-L1 high alarm
-OR- -
and .
- 2) High steam flow and Lo-Lo or or low staan 2) High steam flow and Lo-Lo T
pre,!sure safety injection Tavg or low steam pressure signal for rupture downstrean safety injection signal M of MSIV's. RM-A9, Gl9A, Gl9B, or Gl9C or high alarm M RM-L1 valid INITIATING COtolTION high alarm RAPID m0SS FAILURE OF ONE STEAM GENERATOR TUBE WITH LOSS OF OFFSITE POWER. Detection Method: Pressurizer low pressure alarm and reactor trip; a d Pressurizer low level alarm; M RM-A9, Gl9A, Gl98, or Gl9C valid high alarm M Pressurizer low pressure safety Injection signal; and loss of 115 KV and 230 KV ESF M ential Lights; a d RM-L3, or RM-LIO valid high alarms I
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) (D l D4ERGEtCY Achs' LEVELS
SUMMARY
EPP-001, ATTACH 4 PAGE 3 of 13, REVISION 3 SYSTEM StTE GENERAL INVOLVED UNUSUAL EVENT ALERT EVERGENCY EMERGEtCY , R AD IOLOGICAL INITI ATING COtolTION SUSTAINED HIGH RADIATION LEVELS OF INITIATING CONDITION INITIATING COFOITION EF FLUENTS GASEOUS EFFLUENT INSTANTANEOUS HIGH AIRBORNE CONTAMINATION WHICH RADIATION MONITORS DETECT LEVELS EFFLUENT MONITORS DETECT LEVELS RELEASE RATE TECINICAL INDICATES A SEVERE DEGRADATION IN CORRESP0FOING TO CREATER TtRN 50 CORRESPOtolNG TO 1-RD4/tR Wl0LE BODY ' ' SPECIFICATION LIMITS EXCEEDED FOR 1 TIE CONTROL OF RADIOACTIVE P4 TEM /tR WHDLE BODY FOR 0.5 tR. (R OR 5-REM /tR THfR010 AT TIE tit. ( APPENDlX B TABLE 11, (X)LUMN 1 MATERIALS (e.g., INCREASE OF GREATER THAN 500 MREM /tR WFOLE EXCLUSION NIEA DOUNDARY LFCER /CTUAL 10CFR20) FACTOR OF 1000 IN DIRECT RADIAT106 BODY FOR 2 MIN. (OR FIVE TIMES METEOROLOGICAL COtolTIO45. READINGS). TIESE LEVELS TO TE THYROID) AT Detection Methods TtE EXCLUSION AREA BOUNDARY FOR Detection Method: Detection Method: ADVERSE METEOROLOGY (PASQUILL F
- 1) RM-A3 (Gas) increases > 1 X STABILITY, 1M/SEC Wito VELOCITY). 1) Radiation Monitor levels exceed 105 cpm above bkgd in any 1 1) Unexpected valid RMG readings those specified for Site Emergency; hour. or as follows: Detection Methods and a) FNG 2-4, 8-13, or 16: greater 2) Calculation on Dose Assessment
- 2) RM-A3 (lodine) increases > 8 X than 2.5 R/hr or Any of the following valid Forms Indicates levels exceeding 104 cpm above bkgd in any 1 b) ING 7,17A, 178, or 18 gaseous ef fluent monitor readings: 1-rem /hr whole body or 5-rea/hr hour. g greater than 100 R/hr g thyro!d at the exclusion area c) RMG-1: greater than 1 R/hr 1) RM-A13 (Gas) > 0.3 Mr/tr above boundary using radiation monitor
- 3) RM-A4 (Gas) exceeds 4 times or Bkdg. for 2 min. ,OR, readings and of fluent stream flow the high alarm setpoint for 2) Unexpected plant area lodine or rates (measured or asstaned) for more tha I hour. or particulate alrborne concentratfor 2) RM-A14 (Gas) > 2.2 mR/hr. above actual meteorological condiffons; greater than 1000 MPC. bkgd. For 0.5 hr. g > 22 mR/hr or measured in-situ.
- 4) RM-A4 ( todine) In valid a high (as per 10CFR20 Appendix B, Table above bkgd. for 2 min.
alarm for more than I hour. 1) (CONT 1NUE ON EXT PAGE) I
- A valid high alarm will include verification of radioactivity concentrations in the sampling media.
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r v EMERGENCY ACTw, A EVELS
SUMMARY
EPP-001, ATTAC644C PAGE 4 of 13, REVISION 3 i SYSTLM SITE GENERAL INVOLVED UNUSUAL EVENT ALERT EMERGENCY ENERGENCY , RADIOLOGICAL INITI ATING CO@lTION INITI ATING COM)lTION INITI AL CO@lTION
, EFFLUENTS LIQUID EFFLUENT CotCENTRATIONS RADIOLOGICAL EFFLUENT RELEASE RATE DOSE RATES LISTED BELOW ARE (CON'T) TECmlCAL SPECIFICATIONS LIMITS EXCEEDING 10 TIMES TEC m lCAL PROJECTED BASED ON GAMMA RADIATION
- EXCEEDED FOR 15 MIN. ( APPEPOlX B SPECIFICATION INSTANTANEOUS MONITOR (RMG) READINGS AM)/OR i TABLE il COLUMN 210CFR20). LIMITS. OTER PLANT PARAMETERS (R ARE Detection Method: MEASURED AT T K EXCLUSION AREA Any of the following liquid Detection Method BOUM)ARY.
ef fluent monitors in
- valid High Alarm for longer than 15 min. M Any of the following
- valid Detection Method:
Isolation valvets) fall to close rodlation monitor readings for _. j longer than 15 minutes 8) Reactor Building leak rate or results in calculated dose " RM-L5; RM-L7; E- a) RM-A3 (Gas) Increases > 1 X rate at excligion area - ~_. 106 cpm above bkgd. or r RM-L9 ,
- boundary greater the 2 aram/hr whole body for 0.5 hr; ' ' b) IW-A3 (lodine) Increases > 2 ) or 105 cpm above bkdg. w -500 mren/hr whole body for 2 min.
, c) RM-A4 (Gas) exceeds 40 times or
~~
high alarm setpoint w 2) Radiation Monitoring Teams measures dose rates greater . i d) RM-A4 (Iodine) exceeds 10 than 50 mren/hr for 0.5 hr or times high alarm setpoint. greater than 500 mrom/hr for 2 or min. (beta + gamma) at the exclusion area boundary; or e) RM-L5,IM-L7, or RM-L9 exceeds 10 times high alarm setpoint 3) Radiation %Itoring Teams g isolation valves fall to measure thyroid dose rates close. (equivalent 1-131 concentrations) greater thant
, a) 250 mrem /hr (1.3x10-7 CI/cc for 0.5 hr; or b) 2500 arem/hr (1.3xlY
+
~
. Cl/cc) for 2 min at the exclusion area boundary. +
- A valid high alarm will include verification of radioactivity concentration in the sampling media.
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[. _. x - FMERGENCY MTLdVELS Supe 4ARY . EPP-001, ATTAct94Es / l ! A N '
- y PME 5 of 13, REVISION 3 SYSTEM SITE GENERAL
, INVOLVED UNUSUAL EVENT ALERT '
EMERGENCY EDERGENCY . FUEL INITIATING COBOITION INITIATING C0 m lTION INITI ATI@ COWITION INTI ATING @@lTION ; j DANME FUEL DAMME l@lCATION.~ PCSSIBLE FUEL CAMAGE. DEGRADED mRE WITH POSSIBLE LDSS LDSS & TWO OF TWEE FISSION OF C00LABLE GEG4ETRY. PRODUCT BMIRIER WITH POTENTIAL , Detection Method: Detection Methods LOSS OF TtE THIRD BARRIER (e.g.,
! , Dose equivalent 1-131 activity Detection Method: LOSS OF FUEL INTEGRITY A% t concentration greater than limit le 1) Primary coolant sample PRIMARY COOLANT BOUWARY AND HIGH
)i l Figure 3.4-1 of Technical Indicates equivalent 1-131 POTENTIAL FOR RADIOACTIVITY Specifications; concentration greater than wide Range T g above 700*F, g RELEASE FROM (X)NTAlp04ENT 1
- or 300 UCl/cc; T hat and Tcold RP4-LI High alarm; and Laboratory w rapidly diverging ( T rapidly Detection Method: .i analysis which Indicates an 2) RM-LI High alarm and increasing) or no T across core; 4
increase in failed fuel of 0.1 laboratory anayisis which and RM-L1 of fscale (greater than 1) LOCA and Containment isolation i percent in 30 minutes. Indicates an increase in 7 clui) statu U lghts Indicate l failed fuel of 1 percent in 3( Incomplete Isolation:
- , min or a total failed fuel of -----------------
j 5 percent. INITI ATING C0pelTION -or- l l MAJOR DAMAGE TO MGtE TMN ONE ,, j SPENT FUEL ASSDeLY IN REACTOR 2) LOCA; g ;
----------------- BUILDING m FUEL mWLING BulLDINC 144-A2 high alarm; and
- INITIATING CONDITION LEADING TO C1.*D SUPTURE (e.g., It4G-7 and/or Q 18 reading i FUEL m@ LING ACCIDENT WITH LARGE OBJF'.,i DAMIGES FUEL Gt WATEli . greater than 10 R/hr; g
, RELEASE OF RADIOACTIVITY TO LOSS BELOW FUEL 'tEVEL). Reactor Building pressure i j REACTOR Gt FUEL mpOLING BUILDING. greater than 30 psig for at I Detection Metted: ~ least 2 min. 5
'i Detection Method: or
- Observattors of major damage to , 3) Breech of containment .[
Observation of damage to spent more than one spent fuel assembly Integrity (Reactor Building)
- f uel assembly; and or and RM-L1 of t-scale (> 10 6 Spent fuel pool water below fuel cpm)
- 1) RM-A2 high alarm and/or level and 594G-17A, 178 high alarm after
, accident In Reactor Building; 1) RM-A2 and/or RMG-17A,178 higt or alarm for accident in Reactor
- 2) ~IW4-A6 high alare; or Building or
- 194G-8 high alarm; 2) ID4-A6 and/or R06-4 high alarm after accident In Fuel for accident in Fuel Handling tendling Building. Building f
i i f 4 J 1. i+ l 1 I
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\. E*IERGEPCY AC LEVELS
SUMMARY
EPP-001, ATTAC6Ht. PAGE 6 of 13, REVISIO4 3 SYSTEM StTE GENERAL UNUSUAL EVENT ALERT EMERGENCY EMERGENCY 1NVOLVED STATION INITI ATitG CONDITION INITIATING CONDITION INITI ATitG (DrolTION INITI ATitC COtolTION POWER TOTAL LOSS & WFSITE POWER OR LOS$ LOSS & WFSITE POWER Ato LOSS Of LOSS & &FSITE IVWER Ato LOSS 0 FAILURE & W FSITE Ato Ot4 SITE OF ONSITE A4 POWER CAPABILITY ALL ONSITE A-C POWER FOR MORE ONSITE A-C POWER FOR MORE THAN 15 POWER AL0tG WITH TOTAL LOSS & i T MN 5 MINUTES MIN. EMERGEtGY FEEDWATER MAKEUP Detection Method CAPABILITY FOR SEVERAL SOURS. Detection Method: Detection Method: COULD LEAD TO EVENTUAL CORE KLT
- 1) Loss of 115 KV and 230 KY ESF APO FOSSIBLE FAILURE & TIE
- 1) Loss of 115 KV and 230 KV ESF 1) Loss of 115 KV and 230 KV Potential Lights REACTOR BUILDitG.
Potential Lights ESF. Potential Lights and and and 2) A or B Trn. Blackout Seq. Detection Method
- 2) A or B Trn. Blackout Seq. Int. Alarm
- 2) A or B Trn Blackout Seq. Int. Int. Alarm M 1) Loss of IIS KV and 230 KV ESF.
Alarm ad 3) Both Diesel Generators Potential Lights. or 3) Both Diesel Generator Inoperable. g inoperable ----------------- 2) A or B Trn. Blackout Seq. Int.
- 3) Both Diesel Generators ----------------- INITI ATING COtolTION Alarm inoperable for> 1 hour INITIATING CONDITION LOSS & ALL VITAL ONSITE D-C and LOSS & ALL ONSITE D-C POWER FOR POWER FOR R]RE TMN 15 MIN. 3) Both Diesel Generators A PERIOD GlEATER TMN 5 MINUTES. Detection Method: Inoperable.
a,nd, Detection Method: 1) D-C bus mdervoltage alarms or 4) Steam driven Emergency all buses; Feedwater pump falls to start and is inoperable for several and_
- 1) D-C bus undervoltage alarms 2) 480V ESF Channel A or B Loss hours. j on all buses; and of DC Alarm M
- 2) 480 V ESF Channel A or B loss 3) DG A or B Loss of DC Alarm of DC Alarm g -----------------
INITI ATitC CONDITION
- 3) DG A or B Loss of DC Alarm LOSS & FUNCTIONS tEEDED FOR PLANT FOT StUTDOWN.
Detection Method:
- 1) Inability to establish charging pump Injection: anc I
Inability to establish emergency Feedwater Flow. l SF.
- 2) Rift System not functional e
d (_) 4 , y EMERGEtCY AC v / LEVELS
SUMMARY
EPP-001, ATTACtk PAGE 7 cf 13, REVISION 3 SYSTD4 SITE GENERAL INVOLVED UtMSUAL EVENT ALERT EMERGENCY EMERGDCY . E *GI NE ERED INITI ATitG COtOITION INITIATitG COtOITION INITI ATING C0tolTION INITI ATING C0tolT10N SAFEGUARDS ECCS INITIATED (ColtCIDENT WITH ALL ANNutCIATOR ALARMS LOST. ALL AtNutCI ATORS AtO PLANT TRANSIENT INITIATED BY LOSS & POSITIVE FINDING THAT INITIATION 15 C01PUTER LOST FOR MORE TMN 15 FEEDWATER Ato C0tOENSATE SYSTD4S , NOT SF W100S). Detection Method: MINUTES AND PLANT TRANSIENT (PRINCIPAL TEAT REMUVAL SYSTEM) INITIATED CR IN PROGRESS. FOLLOWED BY FAILURE & EMERGENCY Detection Method Observation by operator. FEEDWATER SYSTEM FOR EXTErOED Detection Method PERIOD. CORE MELTitG POSSIBLE IN Valid Safety injection Signal SEVERAL FOURS. ULTIMATE FAILURE Observation of event. OF REACTOR BulLDING FOSSIBLE IF INITIATING CONDITION CORE MELTS. EVACUATION & CONTROL R004 INITIATING COtolTION ANTICIPATED OR REQUIRED WITH INITI ATING C0tOITION Detection Method: FAILURE OF A PRESSURIZER G1 STEAM CONTROL & SFUTDOWN SYSTEM EVACUATION OF CONTROL ROOM MO GENERATOR SAFETY OR RELIEF VALVE TC ESTABLISFED FROM LOCAL STATIONS. CONTROL OF SIUTDOWN SYSTEMS NOT Reactor trip on steam flow > RESEAT (EXCEEDING NORMAL WEEPAGE). ESTABLISFED FROM LOCAL STATIONS feedwater flow; and IN 15 MIN. Decreasing wide-range steam Detection Method: Detection Methods generator levels toward of f-scale low on all steam generators; Pressurizer or steam generator Detection Methods and safety or relief valve opens and 1) Emergency feedwater flow then falls to reset as Indicated Indicators Indicate zero flow by: Same as initiating event. 2 min. af ter required; l) Valid open Indication of Same as Initiating condition. Status lamps indicate Pressurizer relief or safety emergency feed =ater pumps not valve position Indication running 2 min. af ter required; lights and { or 3) Emergency Feedwater cannot be i E valid acoustical monitor restored within 30 min. 3dication. EL
- 2) Visual and/or audible Indication at vent stacks of open steam generator safety or relief valve; or Excess feedwater flow to and steam flow from af fected generator.
' D4ERGENCY ACitutEVELS
SUMMARY
EPP-001, ATTAC mE m / PAGE 8 cf 13, REVISION 3 1 i SITE GENERAL SYSTEM UNUSUAL EVENT ALERT EMERGENCY EMERGENCY . INVOLVED INITI ATING CO@lTION
,' EtCINEEHED INITIATING CONDITION INITI ATING CO@lTION LOSS OF ENGINEERED SAFETY FEATURE REACTOR COOLANT PUW LOCKED RDT0F TRANSIENT REQUIRING OPERATION OF ,
SAFEQUARDS WITH FUEL DAMAGE. SHITDOWN SYSTEMS WITH FAILtRE TO (CON'T) FUNCTION REQUIRING TEC mlCAL SPECIFICATION SHJTDOWN. (TECmi- TRIP WHICH RESULTS IN CORE DAMAGE CAL SPECIFICATIONS 3.3.2) Detection Method: OR ADDITIONAL FAILURE OF CDRE Reactor coolant po p auto trip COOLING AM) MAKEUP SYSTEMS WHICH Detection Method: a1 arm; and COULD LEAD TO CORE MELT. ; l) Engineered Safety Features Reactor trip on low Activation System found inop- coolant flow; and Detection Method: ' erable Reactor coolant pump phase over
---------------- current relay actuation; g Reactor remains critical after INITIATING CO@lTION valid RML-l Alarm. attempted trip g INDICATIONS OR ALAfWS ON m0 CESS I I) INL-l alarm, or OR EFFLUENT PARAMETERS NOT l FUNCTIONAL IN T E CONTROL ROOM TO INITI ATING CO@lTION 2) Flow Indicators on safety AN EXTENT REQUIRING SHJTDOWN AS PER TECWICAL SPECIFICATIONS; OR, LOSS OF ALL FUNCTIONS EEDED FOR Injection system and R$ systems OTIER SIGNIFICANT LOSS OF PLANT COLD SHJTDOWN. show zero flow with safety Injection Initiated, or i ASSESSMENT OR COMMUNICATION '
! CAPA8ILITY. Detection Method ,
- 3) Status lights show safety !
I Detection Method 1) Loss of R $ system not functional and injection system and R$ pops Radiation Monitoring System; or 2) Inability to reject heat to the not running with safety Loss of all meteorological systems condenser. Injection Initiated, or 31 Significant loss of communication capability offsite; ----------------- or 4) Loss of the plant computer INITI ATING (X)@lTION Ed the TSC computer FAILtRE OF TE REACTOR PROTECT 10e j SYSTEM TO INITI ATE AW C04PLETE / i TRIP WHICH BRINGS TE REACTOR SUBCRITICAL. Detection Method Reactor renalns critical after trip initiation. l l
. 4
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's/ EMERGEPCY ACTiMVELS SLM4ARY EPP-001. ATTACtN PAGE 9 of 13, REVISION 3 SYSTLM SITE GENERAL INVOLVED UtAJSUAL EVENT ALERT E'TRGENCY EMERGEtCY FIRE INITI ATING CotolTION INITI ATitG COtOITION INITI ATitG COtolTION FIRE LASTitG NORE TinN 15 MINS. FIRE POTENTIALLY AFFECTING FIRE AFFECTitG SAFETY TRAINS 01 .
SAFETY SYSTEMS. FUNCTIONS. Detection Method: Detection Method: Detection Method: Observatioi or fire detection device ala. Tith confirming Observation of fire that could Observation of major fire that observation Indicating a fire af fect safety systems, defeats safety system trains or lasting more than 15 min. functions. O
!1 n
D4ERGENCY ACT4MEVELS SUNMARY O EPP-001, ATTAC C -/ PAGE 10 of 13, REVISION 3
. SYS TEM SITE GENLRAL INVOLVED UNUSUAL EVENT ALERT EMERGENCY ENERGENCY SECURITY INITI ATING COWITION INITI ATING CO@lTION INITIATING (D OITION INITIATING COBOITION SECURITY TmEAT (R ATTEMPTED ENTR1 ONG0 LNG SEVERE SECtRITY TmEAT SECURITY TmEAT INVOLVING SECURITY T
- EAT RESUlilNG IN LOSS OR ATTEMPTED SABOTAGE. IMNINENT LDSS OF PHYSICAL CONTROL OF PHYSICAL CONTROL OF TK Detection Method: OF T K PLANT. FACILITY.
Detection Method: Security safoguards contingency event which resulis in Detection Method Detection Method:
- 1) Report to the Control Room by adversaries commandeering an
! observer. area of the plant, but not Physical attack on the Plant Physical attack on the Plant has or impacting shutdown capability. Involving laminent occupancy of resulted in occupation of the
- 2) Alarm of Integrated Fire and control room and auxillary control room and the auxillary Security Panel, shutdown panels. shutdown panels by unauthorized personnei.
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k._ D4ERGENCY AC u.dEVELS SLNMARY EPf%OOI, ATTACt PAGE 11 of 13 REVISION 3
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7 YSTEM StiE GENERAL INv0tVED UNUSUAL EVENT ALERT EMERGENCY EMERGENCY _ NATtHAL INITIATING CONDITION INITIATING cot 01 TION INITIATING COtolTION PIEtO4ENON , NATURAL EVENTS SEVERE NATURAL EVENT NEAR SITE. SEVERE NATURAL PIEtatENON BEING EXPERIENCED OR PROJECTED WITH
- a. EARTtQUAKE PLANT TOT IN COLD SIUTDOWN.
- b. TORNADO ON SITE a. EARTtQUAKE GREATER THAN TtE
- c. tURRICANE TEAR SITE (00E) LEVEL a. EARTtQUAKE GREATER THAN SSE
- b. TORNADO STRIKING FACLitTY LEVELS.
- c. SYSTAINED FURRICANE WINDS b. SYSTAINED WitOS IN EXCESS OF Detection Methods mEATER TtRN 75 WH 100 MPH m SITE.
Detection Method:
- a. Selsmic Recording System Detectio_n Method:
Start Indication. a) Selsmic Response Spectrum
- b. Observation of event. Trouble Annunciator a. Reactor Building Foundation
- c. Observation of event. b) Observation of event Selsmic Switch (SSE) c) Meteorological Monitoring System Data or Weather Bureat b. Meteorological Monitoring Re por t. System Data.
g g *
) (
D ENERGENCY L LEVELS
SUMMARY
EPP-001, ATTACtet FAGE 12 of 13. REVISION 3 STSTEM SITE GENERAL INVOLVED UNUSUAL EVENT ALERT EMERGENCY EMERGENCY - INITI ATitG C0tolTION MAtNADE INITI ATING C0tolTION INITIATING CONDITION P KNOMENON OTER mZARDS BEING EXPERIENCED OTKR mZARDS BEING EXPERIENCED OF OTER MZARDS BEING EXPERIENCED OR PROJECTED WITH PLANT POT IN PROJECTED WHICH MVE TIE POTENTIAL OR PROJECTED WHICH mvE A COLD SIUTDOWN: FOR Ef0 ANGERING THE FACILITY SIGNIFICANT POTENTIAL FOR a. AIRCRAFT GASH INTO VITAL AFFECTING PLANT SAFETY. STRUCTURES.
- a. ONSITE AIRCRAFT G ASH. a. AIRCRAFT CRASH ON FACILITY. b. MISSILE m EXPLOSION IWACT
- b. ONSITE TRAIN DERAILMENT. b. MISSILE IMPACTS ON FACILITY ON FACILITY RENDERING SEVERE
- c. ONSITE EXPLOSION (EXCLUDING WITH RESULTANT MAJOR DAMAGE. DAMAGE TO St0TDOWN EQUIPMENT PLANNED ACTIVITIES). c. KNOWN EXPLOSION AT FACILITY c. ENTRY & T0XIC m FLM94ABLE
- d. NEAR OR ONSITE TOXIC OR RESULTING IN MAJOR DAMAGE TO GASES INTO VITAL NIEAS WHICH FLAW 4ABLE GAS RELEASE & A PLANT STRUCTURES OR INVOLVE A SIGNIFICANT MAGNITUDE TmT TritEATENS EQUIPMENT. OEGRADATION & PLANT PERSONNEL. d. ENTRY INTO FACILITY ENVIRONS SAFETY.
- e. TURBINE GENERATOR ROTATING & T0XIC m FLAMMABLE GASES Detection Method:
(X)WONENT FAILURE CAUSING IN CONCENTRATION WHICH EXCEEL RAPID PLANT StUTDOWN. TK LIMITS & FLApe4 ABILITY OF a) Alrcraft crash causing T0XICITY. damage or fire In: Detection Method: e. TURBINE GENERATOR FAILURE 1) Reactor Building; e CAUSING CASING PENETRATION. 2) Control Room; o
- a. Observation of event. 3) Auxillary Building; or
- b. Observation of event. Detection Method: 4) Fuel 2ndling Building;w .
- c. Observation of explosion or 5) DG Building; or warning from of f site. a) Observation of aircraf t crest 6) Intermediate Building
- d. Observation of release or into Plant structures. 7) SW Intake Structures warning from of f site. b) Observation of missile
- e. Turbine trip and observation impacts on Plant structures b) Loss of functions needed for of turbine malfunction or or components. hot shutdown. (see page 6 of failure. c) Observation of damage by this Attactinent) explosion.
d) Observation or warning from c) Entry of toxic or flammable outside the Plant; detection gases Into: of gases (using portable 1) Control room; or Instrumentation) which exist 2) Cable spreading rooms; or in concentrations which 3) Reactor Building; or exceed the limits of 4) Switchgear room: or flammability or toxicity. 5) Safe shutdown panels; or e) Turbine trip and observation 6) Emergency diesel 1 of penetration of casing, generator rooms; as detected by portable In- , strumentation and which ren-ders a train of a safety-related system inoperable. L e
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(\s) EMERGENCY AC'.w_jiEVELS
SUMMARY
EPP-001 ATTAct PAGE 13 et 13, CEVISION 3 SYSTEM SITE GENERAL INVOLVED UNUSUAL EVENT ALERT EMERGENCY ENERGENCY OTIER INITIATING COtolTION INITI ATING COtolTION INITIATING COtolTION LOSS OF COtRAltNENT INTEGRITY OTTER PLANT COtolTIONS EXIST Tml OTTER PLANT CONDITIONS EXIST Tm1 . REQUIRING TECINICAL SPECIFICATION WARRANT ACTIVATION OF TECINICAL WARRANT ACTIVATION OF EMERGENCY SIUTDOWN (TECtfilCAL SPECIFICATION SUPPORT CENTER Ato PLACING FACILITIES AND RADIATION 3.6.1.1) EMERGENCY OPERATIONS FACILITY MONITORING TEAMS NO A PERSONNEL ON STAND BY PRECAUTIONARY PUBLIC WARNlto. Detection Methods
- 1) Any automatic containment Detection Method: Detection Methods isolation valve found to be inoperable g As determined by Emergency As determined by Emergency
- 2) Reactor Building air lock Director. Director.
Inoperable or
- 3) Penetration (s) fall leak test
. (as specified in Technical SpectfIcations)
INITIATING CONDITION TRANSPORTATION OF OVEREXPOSED APO/OR CONTAMINATED, INJURED INDIVIDUAL FROM SITE TO IDSPITAL. Detection Method: Same as Initlating condition. INITIATING COFOITION OTTER PLANT CONDITIONS EXIST REQUIRING OTTER TNAN NORMAL PLANT SIUTDOWN AND REQUIRING INCREASED AWARENESS ON TIE PART OF STATE OFFICIALS.
, Detection Method: ; As determined by Emergency Director.
l 1 l I e
EPP-001 , ATTACHMENT II PAGE 1 of 1 , fSVISION 3 IMMEDIATE ACTION
SUMMARY
UNUSUAL IMMEDIATE ACTIONS EVENT ALERT SITE GENERAL t
- 1. ANNOUNCEMENT TO PLANT PERSONNEL
- 2. SOUND RADIATION EMERGENCY ALARM N/A 3 NOTIFY SECURITY SHIFT LEADER
- 4. NOTIFY FAIRFIELD PUMP STORAGE FACILITY N/A N/A
- 5. ENSURE ON-SHIFT PERSONNEL RESPONSE NOTIFY LOCAL AUTH OF
- 6. EARLY WARNING SIREN SYSTEM RECOMMENDATION N/A N/A
! 7. ACTIVATE EWSS IF REQUIRED N/A N/A . i
- 8. INITIAL NOTIFICATIONS PER EPP-002 9 EMERGENCY LOG ESTABLISHED
- 10. OFF SITE EMERGENCY SERVICES, IF REQUIRED ACTIVATE TSC/OSC OR NOTIFY EMERGENCY
- 11. RESPONSE PERSONNEL N/A
- 12. NOTIFY OFF-SITE EMERGENCY COORDINATOR N/A ENSURE TSC/OSC ARE ACTIVITED OR EMERGENCY 13 RESPONSE PERSONNEL NOTIFIED N/A ENSURE EOF IS ACTIVATED OR EMERGENCY
! 14. RESPONSE PERSONNEL NOTIFIED N/A N/A . DETERMINE IF SITE EVACUATION IS REQUIRED i 15 (INCLUDING FAIRFIELD PUMP STORAGE FACILITY) N/A i
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. NUCLEAR OPERATIONS Bj j in! [f r 7 ( [ 5 i ,*: W
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~ EMERGENCY PLAN PROCEDURE EPP-002 COMMUNICATION AND NOTIFICATION REVISION 2 JUNE 17, 1982 NON-SAFETY RELATED O
Reviewed by: 7 !#L ORIGINATOR (ef this revision) ' / Date
~ J[/L QUALIFIED REVIEWER Date Approved:
873rd,/YM ~7 82, PLAJ)' MANAGER / Date' Date Issued: EUl b 7 I902 Form AP-101-2, (1/80) l
- L
j .- i EPP-002 ~ PAGE i REVISION-2 LIST OF EFFECTIVE PAGES PAGES REVISION l i 2 i 11 2 111 2 !, 1 2 2 2 3 2 4 2 5 2 ATTACHMENTS Attachment IA, Pages 1 - 3 2 Attachment IB, Pages 1 - 3 2 Attachment IC, Pages 1 - 3 2 Attachment ID, Pages 1 - 4 2 Attachment II A, Pages 1 - 4 2 l ! Attachment IIB, Pages 1 - 3 2 Attachment III, Pages 1 - 3 2 Attachment IVA, Pages 1 - 5 2 Attachment IVB, Pages 1 - 6 2 l Attachment IVC, Pages 1 - 5 2 Attachment V, Pages 1 & 2 2 . Attachment VI, Pages 1 - 3 2
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EPP-002 PAGE 11 s REVISION 2 6/17/82 TABLE OF CONTENTS PAGE List Of Effective Pages i 1.0 PURPOSE 1
2.0 REFERENCES
1 DEFINITIONS 1 30 4.0 PREREQUISITES 2 50 PROCEDURE 2 5.1 Initial Motifications 2 52 Notifications for Change of Emergency Classification 2 Off-site Emergency Services 4 53 () 5.4 55 Follow-up Notifications Vital Personnel Notification 4 5 ATTACHMENTS , Attachment I - Warming Message: Nuclear Facility to State / Local Government Part I Attachment IIA - Warning Message: Nuclear Facility to State / Local Government Part II i Attachment IIIA- Initial Notification-Unusual Event i Attachment IIIB- Initial Notification - Alert Attachment IIIC- Initial Notification-Site Emergency , Attachment IIID- Initial Notification-General Emergency Attachment IVA - NRC One-Hour Notification Attachment IVB - ANI Eight-Hour Notification O
i EPP-002 PAGE 111 REVISION 2 TABLE OF CONTENTS (Continued) ] Attachment V - Off-Site Emergency Services Attachment VIA - Follow-up Notifications - Alert Attachment VIB - Follow-up Notifications - Site Emergency Attachment VIC - Follow-up Notifications - General Emergency Attachment VII - TSC/OSC Emergency Telephone List Attachment VIII- dff-Site Emergency Telephone List O l l l O
EPP-002 , REVISION 2 6/17/82 ( V) 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 REPERENCES i 2.1 " Virgil C. Summer Nucl' ear 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" e 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, "INP0" Institute of Nuclear Power Operations. O
\/ 2.5 Policy Memorandmn No. 25 Issuance, control, and Usage of Radio Pagers.
30 DEFINITIONS AND ABBREVIATIONS 31 Definitions 3 1.1 Initial Notification - The transfer of information to designated organization (s)/ person (s) following change of plant status from normal operations directly into any of the four emergency classifications or upon escalation to a higher emergency classification. This transfer of information is required to begin within fifteen minutes after declaration of the applicable emergency classification. i f . PAGE 1 0F 5 l - . --
'EPP-002 REVISION 2 6/17/82 EXCEPTION: (1) The NRC , Bethesda, Maryland office and the Site Resident Inspector are to be notified within 1 hour of declaration of the event in accordance with Attachment IIA. 2) The American Nuclear Insurers (ANI) is to be notified within eight (8) hours of declaration of an Alert, Site Emergency, or General Em'ergency 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 maintained to provide continuous updating to the NRC. Follow-up notifications are not required for the Unusual Event classification. 32 Abbreviations m 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 3 2.5 IED-Interim Emergency Director 3.2.6 E.O.0-Emergency Operations Center 4.0 PREREQUISITES and CONDITIONS 4.1 Unusual or abnormal plant or site conditions exist which necessitate implementation of the Emergency Plan and the applicable Emergency Classification has been declared. 50 PROCEDURE 51 Initial Notifications n v PAGE 2 0F 5
. EPP-002 REVISION 2 6/17/82 (s\
V 5 1.1 Upon declaration of the appropriate emergency classification, the ED/IED will direct the communicator to implement the appropriate notifications. NOTE: ' Refer to EPP-016 Attachment II for personnel, by title, who should be the designated communicator. 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. The information in Attachment I is to be given to the personnel / agencies as listed in Attachments III A~, III B, III C, or III D depending upon the classification of emergency. NOTE: Attachments III, IV and V list alternates for various personnel. These notifications attempts are to be made in numerical sequence as indicated.and will be considered complete upon successful notification of one [' s of the listed. 52 Notifications for Change in Emergency Classification NOTE: If classification change is made in the middle of a notifications sequence the communicator will terminate that notification sequence, and initiate the new ' notification for current status. 5.2.1 Upon escalation to a higher emergency classification, the communicator will, upon direction from the ED, implement notifications per the section of Attachment III which corresponds to l the higher emergency classification, and Attachments IVA and IVB. 5 2.2 When the emergency classification is downgraded, the communicator will, upon direction from the ED, implement notifications per the section of Attachment VI which corresponds to the l ! classification which is being changed. l O PAGE 3 0F 5 l
. .. .= . - . -
4 . EPP-002 REVISION 2 6/17/82 53 Off-site Emergency Services 531 Upon direction from the ED/IED, the ceramunicator will implement the requested notification (s) per Attachment V.
~
532 Upon direction from the ED/IED, the communicator 1 will contact other utilities for assistance using the "INP0" Resource Guide, Reference 2.4. NOTE: The Resource Guide is available in the TSC and EOF. 5.4 Follow-up Notifications , 5 4.1 Follow-up notifications are required for all emergency classifications except Unusual Event. 5.4.2 The communicator will implement follow-up notifications. (The information in Attachment I and II is to be given to the personnel / agencies as listed in Attachments VI A, VI B, or VI C depending upon the emergency classification.) 5.4.3 Follow-up notifications will be made by the site O communicator (s) until the EOF is activated and assumes all off-site notification responsibilities. Thereafter, the site communicator will transmit applicable updated information to the EOF as it becomes available. 5.4.4 Follow-up notifications to the Emergency Preparedness Division and the counties shall be made by the TSC or EOF Communicator until such time that the S.C. State. Forward EOC is staffed and communications are established. When the S.C. Forward E.O.C. is activiated, all communications, between the plant and state and county agencies will go to the S.C. Forward E.O.C. via the i dedicated phone line or established land line. NOTE: All transfers of notification responsibilities shall be documented. PAGE 4 0F 5
EPP-002 REVISION 2 6/17/82 l l 55 Vital Personnel Notification 551 The communicator will notify vital personnel as directed by the ED/IED per the Vital Personnel i Telephone Listing available in the Control Room and ' the TSC or by radio pager as per Policy Memorandum No. 25 I 5.6 TSC/OSC/ EOF Communications 5 6.1 TSC-OSd - telephone list are provided in Attachment VII. 5.6.2 EOF - telephone list are provj.ded in Attachment . VIII. l t O l 1 i e O PAGE 5 op 5
, EPP-002 ATTACHMENT I PAGE 1 OF 2 REVISION 2 WARNING MESSAGE: NUCLEAR FACILITY TO STATE / LOCAL GOVERNMENT Part I
- 1. This is the Summer Nuclear Station.
- 2. My name is 3 This message (number' ):
(a) Reports a real emergency.
. (b) Is an exercise message.
- 4. Mu telephone number / extension is: ,
or
~
5 You may call back at the end of the message for verification.
- 6. The class of the emergency is: (a) Notification of Unusual Event (b) Alert (c) Site Emergency (d) General Emergency 7 This classification of emergency was declared at:
(a.m./p.m.) on (date).
- 8. The intiating event causing the emergency classification is:
9 The emergency condition: (a) Does not involve the release of radioactive materials from the plant. (b) Involves the potential for a release, but no release is occurring. (c) Involves a release of radioactive material.
- 10. We recommend the following protective action:
(a) No protective action is recommended at this time. (b) People living in zones remain indoors with the doors and windows closed. N .
i i EPP-002 ATTACHMENT I ! t PAGE 2 0F 2 REVISION 2 (c) People living in zones evacuate their homes and businesses. (d) Pregnant women and children in zones remain indoors with the Coors and windows closed. - (e) Pregnant women and children in zones evacuate to the nearest reception center. (f) Other recommendations:
- 11. There will be:
(a) A followup message (b) No further communications
- 12. I repeat, this message:
(a) Reports an actual emergency (b) Is an exercise message ,
- 13. Are there any questions?
O i t 1 O l [ I L-- - ___ __ _ . _ , _ _ _____ _ _ _ _ ._ _ _ _ _ __ _
- EPP-002 ATTACHMENT II PAGE 10F 2 REVISION 2 WARNING MESSAGE: NUCLEAR FACILITY TO STATE / LOCAL GOVERNMENT Part II
- 1. The type of actual or projected release is:
(a) Airborne (b) Waterborne - (c) Surface spill (d) Other
- 2. The source and description of the release is:
3 (a) Release' began /will begin at a.m./p.m.; time since reactor trip is hours. (b) The estimated duration of the release is hours.
- 4. Dose projection base data:
Radiological release: curies *, or curies /sec. Windspeed: mph : Wind direction: From , Stability class: (A,B,C,D,E,F, or G) (} Release height: Ft. Dose conversion factor: R/h'r/C1/m3 (whole body) l R/hr/01/m3 (child thyroid) Precipitation: Temperature at the site: 'F 5 Dose projections: l # Dose Commitment
- Whole Body -
Child Thyroid l Distance Rem / hour Rem / hour of inhalation Site boundary l 2 miles 5 miles 10 miles t 0 t l
._ _ _ _ . _ . . . _ _ , _ _ - . _ . , _ _ _ _ _ . _ _ . . _ _ _ _ _ _._____ _ - - _ - - . ~ -
_ = . - . . _- .- - .. - . - - . .- .- EPP-002 ATTACHMENT II PAGE 2 OF 2 REVISION 2 WARNING MESSAGE: NUCLEAR FACILITY TO STATE / LOCAL GOVERNMENT Part II (cont.)
#Peojected Integrated Dose in Rem per Unit Time' Distance Whole Body Child Thyroid Site Boundary 2 miles 5 miles 10 miles
- 6. Field measurement of dose rate or contamination (if available):
7 Emergency actions underway at the facility include:
- 8. Onsite support needed from offsite organizations:
9 Plant Status: (a) Reactor is: not tripped / tripped O (b) Plant is at (c) Prognosis is:
% power / hot shutdown / cold shutdown /
cooling down stable / improving / degrading / unknown.
- 10. I repeat, this me'asage:
(a) Reports an actual emergency. (b) Is an exercise message.
- 11. Do you have any questions?
i I l l l O I
- -. - . , . , , , , , , , . - . _ . . . - . + . - - . _ . . - . - - _ - . , - - . . - - - . - - , . - . , , - , - . ,
EPP-002 ATTACIBS4T IIIA PAGE 1 0F 1 REVISION 2 INITIAL' NOTIFICATION UNUSUAL EUNP PAGE EASY PERSON . AGENCY / PERSONNEL NUMBER NORMAL -ACCESS SITE turmw TIME
- 1. Managenent Duty Superviso'es (per Duty Roster)
- 1) Ollie Bradham
- 2) John Connelly
- 3) Lou Storz
- 4) Bob Cr.oley
- 5) Mike Quinton
- 6) Vince Albert ,
- 2. *S.C. Dept. of Health &
Environnental Control, Bureau of Radiological Health !
- 3. 'NRC See Attachment IVA of EPP-002 for NRC Initial Notification
- 4. Media Coord. (Mgr., Nuclear Info.)
Home Office
- 1) Becky McSwain
- 2) 1st Alt. - Buddy Clark
- 5. Site Services Manager-Bob Stough
- 6. Institute of Nuclear Power Operations (INPO)
- 7. American Nuclear Insurers (ANI) See Attachnent IVB of EPP-002 for ANI Notification NOTIFICATIONS COMPIEIS:
CALLER'S SIGNATURE DATE
*Cedicated Line Also Exists. .
'l EPP-002
' ATTACFRE?ff IIIB i- PAGE 1 OF 1 REVISION 2 -
INITIAL tUfIFICATION
~
ALERT
. PAGE EASY PNRSON AGENCY / PERSONNEL NUMBER NORMAL ACCESS SITE NOTIFIED TIME
- 1. Management Duty Supervisors (per Duty Roster) '
~
i
- 1) Ollie Bradham '
- 2) John Connelly
- 3) Im Storz
- 4) Bob Croley
- 5) Mike Quinton
- 6) Vince Albert NOTE: To contact additional Emergency Response Personnel refer to Policy Memorandum No. 25.
- 2. *S.C. Dept. of Health & 020 Environmental Control, Bureau of Radiological Health 017 N/A
- 3. *fEC See Attachment IVA of EPP-002 for NRC Initial Notification
- 4. Media Coord. (Mgr., Nuclear Info.)
Home Office
- 1) Becky McSwain
- 2) 1st Alt. - Buddy Clark
- 5. Site Services Manager-Bob Stough
- 6. Institute of Nuclear Power Operations (INPO)
- 7. Fairfield Pumped Storage Facility l
- 8. American Nuclear Insurers (ANI) See Attachmnt IVB of EPP-002 for ANI Notification NOTIFICATIONS COMPL'c.IE:
)
CALLER'S SIGNA'lVriE DATE
'Cedicated Line Also Exists.
EPP-002 ATTACHMENT IIIC PAGE l'0F.1 REVISION 2 INITIAL NOTIFICATION
" SITE EMERGENCY" i
NAME OF
. PAGE EASY PERSON AGENCY / PERSONNEL NUMBER NORMAL ACCESS SITE NOTIFIED TIME I
- 1. Management Duty Supervisors (per Duty Roster)
- 1) Ollie Bradham i
- 2) John Connelly
- 3) Lou Storz
- 4) Bob Croley
- 5) Mike Quinton
- 6) Vince Albert NOTE: To contact additional Emergency Response Personnel, ref.er to Policy Memorandum No. 25
- 2. *S.C. Dept. of Health &
Environmental Control, Bureau of Radiological Health N/A 3 *NRC See Attachment IVA of EPP-002 for NRC Initial Notification Requirements
- 4. Media Coord. (Mgr.,
Nuclear Info.) Home Office
- 1) Becky McSwain 131
- 2) 1st Alt. - Buddy Clark 5 Site Services Manager - ;
Bob Stough ;
- 6. Institute of Nuclear Power Operations (INPO) (
( 7 Fairfield Pumped Storage Facility
- 8. American Nuclear Insureps See Attachment IVB of EPP-002 for ANI
-'j , Notification.
NOTIFICATIONS COMPLETE: 0 Dedicated Lfne Also Exists. Caller's Signature Date
l *
' EPP-002 ATTACHMENT IIID PAGE 1 0F 2
, REVISION 2 INITIAL NOTIFICATION
" GENERAL EMERGENCY" NAME OF PAGE EASY. PERSON AGENCY / PERSONNEL NUMBER , NORMAL ACCESS SITE NOTIFIED TIME
- 1. Management Duty Supbevisors (pcr Duty Roster)
- 1) Ollie Bradham
- 2) John Connelly
- 3) Lou Storz
- 4) Bob Croley
- 5) Mike Quinton
- 6) Vince Albert NOTE: To contact additional Emergency Response Personnel, refer
< to Pclicy Memorandum No. 25.
- 2. 'S.C. Dept. of Health &
Environmental Control, Bureau of Radiological Health N/A
,_ _ . _ - ~ ,
3 #NRC See Attachment IVA of EPP-002 for NRC Initial Notification Requirements
- 4. Media Coord. (Mgr. , Nuclear Info.) Home Office
- 1) Decky McSwain 131 '
- 2) ist Alt. - Buddy Clark i
5 Site Services Manager - Bob Stough
- 6. Fairfield Pumped Storage Facility 7
- Emergency Preparedness, Division- r_ y . .
~
.) Adjutant General's Office ' C -
). i (State EOC)- _ . .
- ' ' ' ~ '
eDedicated Line Also Exists.
s7 - - - -g-
.,1
] >j s f ',
t \ l 5 EPP-002
-g' ATTACHMENT IIID .
FAGE 2 0F 2 O'
. RWISION 2
, ,3 INITIAL NOTIFICATION N
" GENERAL EMERGE!!CY" i
N AME OF '
' EASY. PERSON '--
AGENCY / PERSONNEL NORMAL ACCESS SITE I
, NOTIFIE_D. TIME ; 8. *Fairfield County --
N/A 1 i N/A -
-9..*Newberry' County 5 N/A
- 10. *Richland County i N/A
- 11. *Lexington County N/A
- 12. Institute of Nuclear Power Operations (INPO) N/A g
1 ._ 13 American Nuclear Insurers See Attachment IVB of EPP-002 for ANI Notification..
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NOTIFICATIONS COMPLETE: '
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, -EPP-002 ATTACHMENT IVA PAGE 10F 4 REVISION 2 i
(, , 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. EASY PERSON NORMAL . ACCESS CONTACTED
- 1. NRC - Bethesda, Md. Dedicated Phone N/A a) Commercial telephone system to NRC Operations Center (Via Bethesda Central Office).
b) NRC-Atlanta, Ga. c) Commercial Telephone System to NRC Operations Center (Via Silver Spring Central Office). NOTE: . d) Health Physi.s Network to NRC Operations Center. NOTE: (Touch-Tone) (Rotary Dial) e) Commercial Telephone System to NRC Operator (Via Bethesda Central Office). s._. .
- 2. NRC - Resident Inspector Yes __ N o Jack Skolds (N.O. Ext)
Home Phone NO. OP u
's Beep'ef Ro.
CALLERS SIGNATURE DATE TIME i i I . h
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EPP-002 ATTACHMENT IVA PAGE 2 0F 4 REVISION 2 NRC ONE HOUR NOTIFICATION A. Identification: This is the Summer Nuclear Plant. My name is - Our phone number is . B. Event Classification: We are now in a(n) EVENT CLASSIFICATION which was declared at . TIME C. DESCRIPTION: What Happened: Cause: Consequences: 1 i Ac tions : l l Current Status: D. LICENSEE NOTIFICATIONS: (What notifications have been made.) STATE (S) LICENSEE MANAGEMENT LOCAL OTHER NRC RESIDENT OTHER E. PRESS RELEASE: Has a press release been made or planned? Yes No
EPP-002 ATTACHMENT IVA PAGE 3 0F 4 () NRC ONE HOUR NOTIFICATION REVISION'2 Part II-Complete for all ALERT, SITE ARE.a., and GENERAL emergencies Licensee Actions: Taken Planned Property Damage l Radioactivity Released (or Increa' sed Release): Liquid / Gas? Location / Source of Release Elevation Release Rate Duration Stopped? l Release Monitored? Amount of Release
% Tech. Specs.
Increased Radiation Levels in a Plant: Location (s) Radiation level (s) Areas Evacuated Maximum site boundary dose rates Location Integrated dose Location Meteorology: Wind Direction from Wind Speed (Meter /sec or miles /hr) T ( C or F) Temperature ('C or *F) O- Stability Class A B C D E F G Raining (Yes/No) Projected Peak: Dose Rates Integrated Dose 2 mi (WB/I) (WB/I) 5 mi (WB/I) (WB/I) 10 mi (WB/I) (WB/I) Sectors (WB/I) (WB/I) Contamination (Surface): inplant onsite offsite Reactor Operations: Reactor System Status Power Level Pressure Temp Flow (pumps on) Cooling Mode ECCS Operatin6/ Operable Containment Status Containment Isolated? Containment Temp Containment Press Containment Radiation R/hr. Leak Rate R/hr. Reactivity Control Control Rods Inserted Status of Emer. Boration System O
EPP-002 ATTACHMENT IVA PAGE 4 0F 4 REVISION 2 INCIDENT NOTIFICATION INFORMATION Part II Steam Plant Status: S/G Levels Equip. Failures Feedwater Source / Plow S/G Isolated? Electrical Dist. Status: Normal Offsite Power Available? Major Busses / Loads Lost D/G Running? Loaded? Security / Safeguards: Bomb Threat: Search Conducted? Search Results Site Evacuated? Extortion: Source (Phone, letter, etc.)? ' Location of Letter Intrusion: Insider? Outsider? O' Furthest Point of intrusion Fire arms related? Stolen / Missing Material? Demonstration: Size of Group Demands Violence? Fire arms related? Sabotage / Vandalism: Radiological? Arson Involved? - Stolen / Missing Material?
O EPP-002 ATTACHMENT IVB PAGE 1 0F 3 REVISION 1 ANI EIGHT HOUR NOTIFICATION ANI is to be notified .within eight (8) hours of the declaration of' an Alert, Site Emergency, or General Emgergency ,in accordance with pages 2 and 3 of this attachment. . American Nuclear Insurers ( ANI) Phone No.- Easy Access Person Contacted Time Date Callers Signature 4 i i
D EPP-002 ATTACHMENT IVB
, PAGE 2 0F 3 O ANI NOTIFICATION REVISION.1 (1) This is (N ame) (Title)
(2a) This is a drill (2b) This is NOT a drill (3) I am notifying you of an accident at the V. C. Swnmer 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: (S (6c) Release Rate: (6a) Noble Gas (6b) (6c) Release Height (6d) Meteorological Conditions: (6a) Wind Speed (mph) (6b) Wind Direction (blowing to) (6c) Stability Class (6d) Precipitation (6e) Projected Dose At: Site Boundary 2 Miles 5 Miles 10 Miles (6f) Dose Rate--Whole Body (10A) (10B) (10C) (10D) (6g) Integrate Whole Body Dose ( hour projection) (llA) (llB) (11C) (11D) (6h) Dose Rate--Thyroid (12A) (12B) (12C) (12D) (61) Integrated Infant Thyroid ( hour projection) (13A) (138) (13C) (13D) (6j) Sectors Affected (14A) (14B) (140) (14D) O
EPP-002 ATTACHMENT IVB PAGE 3 0F 3 REVISION 1 (} 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) Of f-Site Emergency Assistance / Actions Requested 1 Yes No. , (If yes, complete 8a through 8c) Yes/No Reason (Ba) Law Enforcement () (8b) (8c) Fire Departments Hospital Facilities (9) Public evacuation required Yes No Not at this time j (9a) If "Yes" or "Not at this time", af fected sectors f e lO i
EPP-002 AITACR4ENT V
. PAGE 1 CF 3 RE'lISION 1 0FF-SITE EMERGENCY SERVICES NAME OF PERS0tl AGBICY/PEBSONNEL PHONE NOTIFIED TIME A. Company Physicians (Pinner Clinic)
- 1) Carrol A. Pinner III M.D. - Prinary (24 hrs.)
- 2) Carrol A. Pinner Jr. M.D. - 1st Alternate
- 3) - Harriet A. Pinner, M.D. - 2nd Alternate _
B. Hospital Facilities
- 1) Richland Memorial Hospital l
'~ ~
Give the following information:
'Ihis is the Virgil C. Summer Nuclear Station..
'Ihis is a Drill 'Ihis is not a Drill We have contaminated /non-contaminated injured person being transported to your facility.
- 2) Radiation Emergency Assistance Center Training Site (Reacts) 24 hour C. Ambulance Service
; la) Emergency Medical Services of Fairfield County ,or lb) Alert MAST for standby a transtnetation.
- l or i
- 2) U.S. Anny ,
MAST Operations > or NUIE: Alert Security of anergency Vehicle arrival as soon as request (s) for Off-Site Fr.ergency Services are ccmpleted. . Ext. ' or
I EPP-002 ATPACHFSTP V
.f -
PAGE 2 0F 3 REVISION 1 OFF-SITE EMERGENCY SERVICES NAME OF PERSON AGBICY/ PERSONNEL PHONE NOFIFIED TIME
- Give the following infonration for itens la and 2 above.
, 'Ihis is a Drill This is.not a Drill We have contam1nated/non-contaminated injured person (s) requiring transportation to Richland Memorial Hospital. ('Ihe ambulance must enter the site via the main gate, using (denote route to be taken) or the helicopter should land at the primary landing pad (denote route to be taken)
D. NSSS Supplier /A.E. . Title Name Office Home HHL
- 1. Site Service Manager Bob Stough ,
Notes: (1) The area code of the above phone numbers is (2) The phone beeper number is (
- 2. Operating Plant Service John Miller I Manager 1st Alternate Tim Sulliun 2nd Alternate John Gallik ,
3 Service Response Joe Leblang
}
Manager i lst Alternate John Miller ! 2nd Alternate Dave Campbell l
- 4. Bnergency Response Hank Ruppel Director i
5 Snergency Response Ron Lehr Deputy Director f
- 6. Energency News Mike Fangan Communications --
Note: Unless indicated otherwise, all phone numbers are area code 412. Where an area code other than 412 is shown, it applies to the office, home, and HHL numbers
- 2) GAI .
6 i (Nonral r , Working Hours') /
b EPP-002 ATTACR1BTP V PAGE 3 OF 3 REVISION 1 OFF-SITE EMERGENCY SERVICES NAIE OF PERSON AGalCY/ PERSONNEL PHONE NOTIFIED TDIE E. Fire Services ,
- 1) Fairfield County Fire ~ Services -
Give the following infonnation:
'Ihis is the Virgil C. Simner Nuclear Station.
This is a Drill 'Ihis is not a Drill We request fire fighting assistance . at the Sunmer Nuclear Station. 'Ihe fire truck must enter via the main gate, using (denote route to be taken) F. Incal Law Ehforcenent .or I (off-normal hours) #
-.I G. National Weather Service (Backup to Load Dispatcher for weather information).
- 1) Columbia - -
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- 2) Greer - j 1
CALLER'S SIGNATURE DATE LJ
EPP-002
. ATTACHMENT VIA
. PAGE 1 0F 1 REVISION 2 FOLLOWUP NOTIFICATION ALERT
.NAME 0F EASY PERSON
, AGENCY / PERSONNEL NORMAL ACCESS NOTIFIED TIME 1.# S.C. Dept.of Health..&
Environmental Control, Bureau of Radiological Health Notifications complete: - Caller's Signature Date
- Dedicated Line Also Exists.
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EPP-002 ATTACHMENT VIB 1
' AGE 1 0F 1 REVISION 2 FOLLOWUP NOTIFICATION SITE EMERGENCY NAME OF EASY CALLERS PERSON AGENCY / PERSONNEL NORMAL ACCESS SITE SIGNATURE NOTIFIED TIME 1.0 S.C. Dept of Health & - or-~ N/A Environmental Control, ,
Bureau of Radiological Health Notifications complete: Caller's Signature Date NOTE: When the State Forward EOC .is established the State BRH will move their operation to the State Forward EOC and communication will be via the State Fo rward E.O.C. Dedicated Phone Line.
- Dedicated Line Also Exists.
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1 - EPP-002 l - ATTACHMENT VIC PAGE 1 0F 1 REVISION 2 FOLLOWUP NOTIFICATION c1NERAL EMERGENCY NAME OF EASY PERSON AGENCY / PERSONNEL NORMAL ACCESS NOTIFIED TIME 1.0 S.C. Dept of Health & - Environmental Control, Bureau of Radiological Health The following notifications shall be made by the TSC or EOF Communicator until such time that the S.C. State forward EOC is staffed. 2.0 Emergency Preparedness Division Adjutant General's ! Office 30 Fairfield County
' Newberry County ,
5.0 Richland County 6.0 Lexington County Notifications complete: Caller's Signature Date NOTE: When the State Forward EOC is established the State BRH will move their operation to the State Forward EOC and communication will be via the State Forward E.O.C. Dedicated Phone Line.
' Dedicated Line Also Exists.
.v -
o .EPP-002 RTTACHMENT VII PAGE 1 OF 2 REVISION 2 TSC/OSC EMERGENCY TELEPHONE LIST Tecnnical Support Center-Nuclear Regulatory Commission Nuclear Regulatory Commission Nuclear Regulatory Commission
! TSC Display Room l
TSC Display Room TSC Display Room , Dose Assessment Area Technical Support Engineers Technical Support Engineers Technical Support Engineers Technical Support Center Communicators Telecopier Phone to EOF Radiation Monitoring Teams Assistant Manager, Support Services-Vince l Albert t Radiological Assessment Supervisor-L.A. Blue Assistant Manager, Technical Support-B. Croley Security Supervisors-J. Sefick/Capt. Tuttle Assistant Manager, Maintenance Services-M. Quinton l Assistant Manager, Operations-L. Storz Westinghouse GAI OSC OSC
t EPP-002 ATTAC&IENT VII
'PAGE 2 of 2 REVISION 2 TE C *A N icA.L SU PPORT C c N i m R.
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PLA.NT STATu S I t . m DISPLM - AREA L DOSE . ASSE SS M~=MT M@
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1 O. tscuwicAL a ssm.c.,sucy - sus ,- , D-2.l - J 0-31 . SOF7cc OPERAGORS SqPERy)SoR., 8.. A2.EA, 1 A C-EA. _ c1: Fica 7-C I G' CcxxusicxT. css
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- EPP-002 ATTACHMENT VIII-
- PAGE 1 0F 3 REVISION 2 OFF-SITE EMERGENCY TELEPHONE LIST Emergency Operations Facility EOF Communicator Area i i EOF-NRC '
EOF-NRC EOF-NRC EOF-NRC EOF-Technical Support Coordinator-M.B. l Whitaker , EOF-Security Coordinator-J. Harrison EOF-Media Coordinator-R. McSwain I i - EOF-General Services Coordinator-J. i3a11ey EOF-Construction / Repair Coordinator-J. Woods l f f EOF-Offsite Radiological Monitoring Coordinator-Bill Baehr EOF-Technical Support Engineers EOF-Technical Support Engineers EOF-Technical Support Engineers EOF-Technical Support Engineers 9 O
cPP-002 ATTACHMENT VIII PAGE 2 0F 3 REVISION 2 OFF-SITE EMERGENCY TELEPHONE LIST
' Emergency Operations Facility 5
EOF-Telecopier between TSC/ EOF i EOF-General Services Support Area
~
EOF-General Services Support Area EOF-General Services Support Area EOF-General Services Support Area EOF-General Services Telecopier i EOF-Security Office EOF-Security Of fice l I EOF-Construction / Repair Support Areas EOF-Construction / Repair Support Areas EOF-Construction / Repair Support Areas EOF-Media Coordination Support Area EOF-Telecopier for Media Area EOF-Offsite Radiological Monitorie.g Area EOF-Offsite Radiological Monitoring Area w O T 4 t k
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) SOUTH CAROLINA ELECTRIC Arid GAS COMPANY -v, f VIRGIL C. SUMMER NUCL' EAR STATION NUCLEAR OPERATIONS R C _ ~A,R 0,) .dAT.0NS COPY No...../...f.... 7 C -
a . EMERGENCY PLAN PROCEDURE EPP-002 COMMUNICATION AND NOTIFICATION REVISION 3 SEPTEMBER 3, 1982 NON-SAFETY RELATED
.s Reviewed by:
93!FL ORIQINATOR T3f this revision) ' Cate llt alLr DISCIPLINE SUPERVISOR 9hk- Date Approved: PMNT MAN AGER m SM/A
~Dits .
Date Issued: O V.
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EPP-002
, PAGE i o REVISION 2 9/3/82 O LIST OF EFFECTIVE PAGES i
V PAGES REVISION
'1 3 11 3 111 3 -
~
I 1 3 2 3 3 3 4 3 5 3 ATTACHMENTS Attachment I, Pages 1 & 2 3 .; Attachment II, Pages 1 & 2 3 Attachment IIIA 3 Attachment IIIB 3 Attachment IIIC 3 Attachment IIID, Pages 1 & 2 3 Attachment IVA, Pages 1 - 4 3 Attachment IVB, Pages 1 - 3 3 Attachment IVC, Pages 1 - 5 3 Attachment V, Pages 1 - 3 3 Attachment VIA 3 Attachment VIB ~ 3 i Attachment VIC 3 Attachment VII, Pages 1 &2 3 I Attachment VIII, Pages 1 - 3 3
- O I
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o e e EPP-002 PAGE 11 REVISION 3 9/3/82 [} TABLE OF CONTENTS PAGE List Of Effective Pages 1 1.0 PURPOSE . 1
2.0 REFERENCES
1 30 DEFINITIONS 1 4.0 PREREQUISITES 2 5.0 PROCEDURE 2 51 Initial Notifications 2 52 Notifications for Change of Emergency Classification 2 53 Off-site Emergency Services 4 5.4 Follow-up Notifications 4 [) 5.5 Vital Personnel Notification 5 ATTACHMENTS Attachment I - Warming Message: Nuclear Facility to State / Local Government Part I Attachment IIA - Warning Message: Nuclear Facility to State / Local Government Part II Attachment IIIA- Initial Notification-Unusual Event Attachment IIIB- Initial Notification - Alert Attachment IIIC- Initial Notification-Site Emergency Attachment IIID- Initial Notification-General Emergency Attachment IVA - NRC One-Hour Notification Attachment IVB - ANI Eight-Hour Notification f i C)
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. PAGE 111 REVISION 3 )
9/3/82 ) l TABLE OF CONTENTS (Continued) 1 Attachment V- - Off-Site Emergency Services Attachment,VIA - Follow-up Notifications - Alert Attachment VIB - Follow-up Notifications - Site Emergency Attachment VIC - Follow-up Notifications -- General Emergency Attachmen) VII - TSC/OSC Emergency Telephone List Attachment VIII- Off-Site Emergency Telephone List
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- EPP-002 REVISION 3 9/3/82 O%.
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" 23 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, "INP0" Institute of Nuclear Power Operations. l O(,,/ 25 Policy Memorandum No. 25 Issuance , Control, and Usage of Radio Pagers. 30 DEFINITIONS AND ABBREVIATIONS 31 Definitions 3 1.1 Initial Notification - The transfer of information to designated organization (s)/ person (s) following change of plant status from normal operations directly into any of the four emergency classifications or upon escalation to a higher emergency classification. This transfer of information is required to begin within fif teen j minutes after declaration of the applicable ' emergency classification. O PAGE 1 0F 5
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. EPP-002 REVISION 3 9/3/82 t
v EXCEPTION: (1) The NRC, Bethesda, Maryland office and the Site Resident Inspector are to be notified within 1 hour of declaration of the event in accordance with Attachment IIA. 2) The American Nuclear Insurers (ANI) is to be notified within eight (8) hours of declaration of an Alert, Site 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 maintained to provide continuous updating to the NRC. Follow-up notifications are not required for the Unusual Event classification. 32 Abbreviations
/"'S 3 2.1 TSC - Technical Support Center U 3 2.2 OSC - Operations Support Center 323 EOF - Emergency Operations Facility 3 2.4 ED - Emergency Director 325 IED-Interim Emergency Director 3 2.6 E.O.0-Emergency Operations Center 4.0 PREREQUISITES and CONDITIONS 4.1 Unusual or abnormal plant or site conditions exist which necessitate implementation of the Emergency Plan and the
- applicable Emergency Classification has been declared.
50 PROCEDURE 5.1 Initial Notifications O DAGE 2 0F 5 l l i ., .- - - . -.m .-m -... .. v -. . .- - m ,--., c-~.e.--.- -- we- 4--- -r -r -. ,
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e EPP-002 REVISION 3 9/3/82 5.1.1 Upon declaration of the appropriate emergency classification, the ED/IED will direct the communicator to implement the appropriate notifications. NOTE: Refer to EPP-016 Attachment II for personnel, by title, who should be the - designated communicator. 5 1.2 The ED/IED will assure that the required information is available to effect prompt notification. 513 The communicator will, upon direction from the ED/IED, implement the initial notiff cations. The information in Attachment I is to be given to the personnel / agencies as listed in Attachments III A, III B, III C, or III D depending upon the classification of emergency. NOTE: Attachments III, IV and V list alternates for various personnel. These notifications attempts are to be made in numerical sequence as indicated and will be considered complete upon successful notification of one (~ of the listed. (, 52 Notifications for Change in Emergency Classification NOTE: If classification change is made in the middle of a notifications sequence the communicator will terminate that notification sequence, and initiate the new notification for current status. 5 2.1 Upon escalation to a higher emergency classification, the communicator will, upon direction f rom the ED, implement notifications per the section of Attachment III which corresponds to the higher emergency classification, and , Attachments IVA and IVB. 5 2.2 When the emecgency classification is downgraded, the communicator will, upon direction from the ED, implement notifications per the section of Attachment VI which corresponds to the classification which is being changed. O V PAGE 3 0F 5
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m- w-. .= = EPP-002 REVISION 3 9/3/82 q U 53 Off-site Emergency Services 531 Upon direction from the ED/IED, the communicator will implement the requested notification (s) per Attachment V. 532 Upon direction from the ED/IED, the communicator - will contact other utilities for assistance using the "INP0" Resource Guide, Reference 2.4. NOTE: The Resource Guide is available in the TSC and EOF. 5.4 Follow-up Notifications 5.4.1 Follow-up notifications are required for all emergency classifications except Unusual Event. 5.4.2 The communicator will implement follow-up notifications. (The information in Attachment I and II is to be given to the personnel / agencies as listed in Attachments VI A, VI B, or VI C depending upon the emergency classification.) s 5.4.3 Follow-up notifications will be made by the site ( communicator (s) until the EOF is activated and assumes all off-site notification responsibilities. Thereaf ter, the site communicator will transmit applicable updated information to the EOF as it becomes available. 5.4.4 Follow-up notifications to the Emergency Preparedness Division and the counties shall be made by the TSC or EOF Communicator until such time that the S.C. State. Forward EOC is staffed and communications are established. When the S.C. Forward E.O.C. is activiated, all communications , between the plant and state and county agencies will go to the S.C. Forward E.O.C. via the dedicated phone line or established land line. NOTE: All transfers of notification responsibilities shall be documented. 'l
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- 55 Vital Personnel Notification 551 The communicator will notify vital personnel as directed by the ED/IED per the Vital Personnel Telephone Listing available in the Control Room and i
the TSC or by radio pager as per Policy Memorandum No. 25
- 5.6 TSC/OSC/ EOF Communications 1
5.6.1 TSC-OSC - telephone list are provided in Attachment VII. 5.6.2 EOF - telephone list are provided in Attachment VIII. l O i e
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, EPP-002
. , ATTACHMENT I 7 PAGE 1 0F 2 REVISION 3
!) UARNING MESSAGE: NUCLEAR FACILITY TO STATE / LOCAL GOVERNMENT Part I
- 1. This is the Summer Nucleat-^ Station. [
- 2. My name is 3 This message (numbed * ): \ .
(a) Rep 6 cts a; real emergency. ., (b) Is an exerciso message. '
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- 4. 'ty ' telephone number / extension is : 'or
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5 You may call back at the end of the message for verification.
- 6. The class of the emergency is: (a) Notification of Unusual Event (b) Alert
( c) Site Emergency (d) General Emergency
., 7 This classification of emergency was declared at:
') (a.m./p.m.) on (date).
- 8. The intiating event causing the emergency classification is: l 9 The emergency condition: (a) Does not involve the release of radioactive materials from the plant.
(b) Involves the potential for a release, but no release is occu'rring. (c) , Involves a release of radioactive material.
- 10. Ve recommend the following protective action: ,
(a) No protective action 11s recommended at this time. (b) People living in' zones remain indoors with the doors and windows closed. I
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< ATTACHMENT I PAGE 2 0F 2 REVISION 3 (c) People living in zones evacuate their homes and businesses. ,
(d) Pregnant women and children in zones ! remain indoors with the doors and windows closed. (e) Pregnant women and children in zones - i evacuate to the nearest reception center. 4 (f) Other recommendations:
- 11. There will be:
(a) A followup message (b) No further communications
- 12. I repeat , this message:
(a) Reports an actual emergency (b) Is an exercice message
- 13. Are there any questions?
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. EPP-002 ATTACEMENT II
. PAGE 1 0F 2 REVISION 3 WARNING MESSAGE: NUCLEAR FACILITY TO STATE / LOCAL GOVERNMENT b(N Part II
- 1. The type of actual or projected release is:
(a) Airborne (b) Waterborne
'(c) Surface spill .
(d) Other -
- 2. The source and description of the release is:
3 (a) Release began /will begin at a.m./p.m.; time since reactor trip is hours. (b) The estimated duration of the release is hours.
- 4. Dose projection base data:
Radiological release: curies, or curies /sec. Windspeed: mph Wind direction: From Stability class: (A,B,C,D,E,F, or G)
) Release height: Ft.
Dose conversion factor: R/hr/01/m3 (whole body) R/hr/C1/m3 ( child thyroid) Precipitation: Temperature at the site: 'F
- 5. Dose projections:
# Dose Commitment
- Whole Body Child Thyroid Distance Rem / hour Rem / hour of inhalation Site boundary 2 miles l 5 miles i 10 miles
\
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-r-,- - - - , v
EPP-002
,- ATTACHMENT II
. PAGE 2 0F 2 !
REVISION 3 l . WARNING MESSAGE: NUCLEAR FACILITY TO STATE / LOCAL GOVERNMENT a Part II (cont.) ' # Projected Integrated Dose in Rem per Unit Time # Distance Whole' Body Child Thyroid -- Site Boundary ., 2 miles 5 miles 10 miles 1
- 6. Field measurement of dose rate or contamination (if i
available):
; 7 Emergency actions underway at the facility include :
- 8. Onsite support needed from offsite organizations:
u 9 Plant Status: (a) Reactor is: not tripped / tripped (b) Plant is at % power / hot shutdown / cold shutdown / O cooling down 1 (c) Prognosis is: stable / improving / degrading / unknown.
- 10. I repeat, this message:
(a) Reports an actual emergency. (b) Is an exercise message. I
- 11. Do you have any questions?
i 1 1 1 _ , - _ - - - . - w,. . .. . . , _ _ _ -.-y .__m_ _ ,,m, _ . , . - . _
.m----- ,, ,- _ , ~ , . _ _ . , , - - . . - . . . . . . . _ - - - - - _ _ - , , , - - . _ _ . _ _ - - ,
. i EPP-002
- ATTAGME2iT IIIA PAGE 1 0F 1 REVISION 3 1 1
INITIAL NOI'IFICATION UNUSUAL EVEfff PAGE FJLSY PERTN AGENCY / PERSONNEL NUMBER NORiAL ACCESS SI'IE ?UPIFIED TDC
- 1. Managenent Duty Supervisors *
(per Duty Roster) - 7
- 1) Ollie Bradhan h
- 2) John Connelly
- 3) Iou Storz
} ' :y . i -
- 4) Bob Croley l S
- 5) Mike Quinton l. .
- 6) Vince Albert
- 2. 'S.C. Dept. of Health & N- ;
'~ '
Environmental Control, Bureau ' i \;_ ' . ' % '*' n. : '
- of Radiological Health A. - ' Mj-
- 3. 'NRC See Attachment IVA of EPP-002 for NRC Initial Notification
- 4. Media Coord. (Mgr., Nuclear Info.)
Home Office r- ~ _ _ _ _ _
- 1) Becky McSwain i -
7 i
~
- 2) Ist Alt. - Buddy Clark 'N l
- 5. Site Services Manager-Bob Stough '
- 6. Institute of Nuclear - .: [4 ,. 4 Power Opetutions (INPO) .- ,. - ~ :s ' -
1 3_ J
- 7. American Nuclear Insurers (ANI) See Attachnent IVB of EPP-002 for ANI Notification NOPIFICATIONS COMPLEIE:
CALLER'S SIGNAIURE DATE 9 Dedicated Line Also Exists. _ . .. . . . . . . . . . . g.-# .,q.,. e. . . . . ...s,g. ...g r.... .wm
EPP-002 ATTAGEiENT IIIB PAGE 1 OP 1
, REVISION 3 INITIAL NOTIFICATION Sh
- ALERP
~ ' 3/
PAGE EASY PERO N AGENCY / PERSONNEL NUMBER 'NOINAL' ACCESS SITE talrmw TIME
- 1. Mulagement Duty Supervisors (per Duty Roster) .. .
- 1) Ollie Bradham - !
- 2) Jorn Connelly :
1
- 3) Inu Stor f
- 4) Bob Croley l ,
- 5) Mike quinton l -
- u a
- 6) Vince Albert -'"
_- -. ..--J NOTE: To contact additional Bnergency Response Personnel refer to Policy Memorandum No. 25
- 2. 'S.C. Dept. of Health & .;- ,
Environmental Control, Bureau t .f, . (.a g of Radiological Health g# ; _3 . N/A
- 3. 'NRC See Attachment IVA of EPP-002 for NBC Initial Notification
- 4. Media Coord. (Mgr., Nuclear Info.)
Ihne Office
/
. ~ .
- 1) Becky McSwain .
./
- 2) 1st Alt. - Buddy Clark 3 .
T
- 5. Site . Services Manager-Bob Stough v . i .L,,ju
'y.._ .
/
, sy j, .
l
- 6. Institute of Nuclear
;.% m,z7f;. . cg;y; u. . . N/A Power Operations (INPO) i^ ~;
b =';
. w;g
.L
- 7. Fairfield Pumped Storage Facility \ _ , o W> , N/A
%& : ~ ~<
- 8. American Nuclear Insurers (ANI) See Attachment IVB of EPP-002 for ANI Notification N0f1FICATIONS COMPLETE:
CALLER'S SIGNATUPE DATE .._.-
- Dedicated Line Also Exists. --
. . . . . . - . , . . , - . , . - . - , . . - -...._-.,,.-n . . . . , . - - . - . . . - . . . . . . , .
l .
EPP-002 ATTACHMENT IIIC
, . PAGE 1 0F 1 REVISION 3 INITIAL NOTIFICATION
" SITE EMERGENCY" NAME OF PAGE EASY PERSON AGENCY /PERS0!!NEL NTIMBER NORMAL ACCESS SITE NOTIFIED TIME
- 1. Management Duty Supervisors (per Duty Roster) -
(
- 1) Ollie Bradham -
- 2) John Connelly :
f
~
- 3) Lou Storz .
~
- 4) Bob Croley e-
- 5) Mike Quinton .<
,; & .; .. ~
-e m g
. . n l
- 6) Vince Albert NOTE: To contact additional Emergency Response Personnel, refer to Policy Memorandum No. 25
- 2. *S.C. Dept. of Health &
Environmental Control, b '^ ^ ,
~; ? .~
"s4
(.h'
. Bureau of Radiological ","
Health - A @' .s. 3,x. .
- 5. N/A
~% .
/
3 *NRC See Attachment IVA of EPP-002 for NRC Initial Notification Requirements
- 4. Media Coord. (Mgr.,
Nuclear Info.) Home Office
- 1) Becky McSwain 703 i
[ I
;[t
- 2) ist Alt. - Buddy Clark .
R ;< .. Site Services Manager - J 3ba:.g 5 Bob Stough . E
';6
~
dzif.t.3.; m : _ gQ '
- ge , .ll@ g.Q . ,
- 6. : A '.c
~
Institute of Nuclear Power' - t SSuc Operations (INPO) (/ i ,
- 'I Mdfi. ; N/A
,.;.'s.4% - M$$cN$
('('I.,L.~.~.5;P2...JM?ACM 7 Fairfield Pumped Storage. Facility
; d . h ... S p y gg if P
. y 4 N/A
;2MT. 'fRu - _ m-
- 8. American Nuclear In.surers See Attachment IVB of EPP-002 for ANI Notification.
NOTIFICATIONS COMPLETE:
~
' Dedicated Line 'Also Exists.
. . . . , , -.,..m .,.-. m ...-%.. --.-..,.w, -.--o..,.,..eg... .
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, EPP-002 ATTACHMENT IIID PAGE 1 0F 2 REVISION 3
(;2 INITIAL NOTIFICATION
" GENERAL EMERGENCY" NAME OF PAGE EASY PERSON AGENCY / PERSONNEL NUMBER N0RMAL ACCESS SITE NOTIFIED TIME -
- 1. Management Duty Supervisofs ~
(per Duty Roster) _ .. . . _ _ _ _ , _ _ . . . - - . . ~
- 1) Ollie Bradham ' ,
- 2) John Connelly , _
! l
- 3) Lou Storz !
~
- 4) Bob Croley l'
t
- 5) Mike Quinton ! .
- 6) Vince Albert ' -
1 NOTE: To contact additional Emergency Response Personnel, refer to Policy Memorandum No. 25
- 2. 'S.C. Dept. of Health & _.
\'
i_ Environmental Control, Bureau of Radiological \ .. Health \ N/A
~,.,. f 3 'NRC See Attachment IVA of EPP-002 for NRC Initial Notification Requirements
- 4. Media Coord. (Mgr., Nuclear Info.) Home Office f
- 1) Becky McSwain -
@ ;., - , u.. . t
- 2) 1st Alt. - Buddy Clark .. e ' :, ; .
- [?/ - -
5 Site Services Manager - cI' y - [ ',,. .7_ -- - Vi' ' - b 'I Bob Stough ?;' '.i ; . g y _ 7 :_.;..;_ ,_..f, 6.- Fairfield Pumped' Storage _ s Facility r.r?q 'O. 7 ; D.s,-y. :# M ,;rm?ll N/A s . ; : 7
- Emergency Preparedness ~ . g'$'^f.s;y .; y' w +.-e
^ m m =,. ,:
Division-
. u. Adjutant General's Office. @C $'4M8Eygv-il T[g'd j N/ A _. . -
tg (State EOC) , d NIM W _
' Dedicated Line Also Exists.
~ ~ av . - . . . , - . J ...,.. .- -~ . . . _ . -. . . .
l
EPP-002
. ATTACHMENT IIID PAGE 2 0F 2 INITIAL NOTIFICATION
" GENERAL. EMERGENCY" NAME OF EASY PERSON AGENCY / PERSONNEL NORMAL ACCESS SITE NOTIFIED TIME -
- 8. 'Fairfield County N/A N/A 9..'Newberry County -
N/A
- 10. 'Richland County , N/A
- 11. 'Lexingtcn County f N/A 12.
Institute of Nuclear a' .. Power Operations (INPO) . N/A 13 American Nuclear Insurers See Attachment IVB of EPP-002 for ANI Notification. O NOTIFICATIONS COMPLETE: Caller's Signature Dte 4 DDedicated'Line Also Exists. _ ,
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- 7. ...... .
EPP-002 o ATTACHMENT IVA PAGE 1 OP 4
. REVISION 3 (dyi 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.
. EASY PERSON
~
NORMAL ACCESS CONTACTED
- 1. NRC - Bethesda, Md. Dedicated Phone N/A a) Commercial telephone system to NRC Operations Center (Via ~
Bethesda Central Office). J. .
. . /. ~
b) HRC-Atlanta, Ga. , n
/. N s
c) Commercial 026 . . _ _ _ _ .
\ y
- 6) Vince Albert }
- 2. *S.C. Dept. of Health & .,
Environmental Control, Bureau \ C,; .),. """""'""'"*"" --' '
.__"'^
- 3. 'NRC See Attachment IIAto NRC Operator Central Office).
.h
, s N
- 2. NRC - Resident Inspector Yes No
~
\Home~Fhone NO.
Jack Skolds i
\(N.O. Ext)
, N or _
T Beeper No. CALLERS SIGNATURE DATE TIME
~
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. EPP-002 ATTACHMENT IVA PAGE 2 0F 4 NRC ONE HOUR NOTIFICATION A. Identification:
This is the Sumner Nuclear Plant. My name ja . . Our phone number is'
- B. Event Classification
We are now in a(n) EVENT CLASSIFICATION which was declared at . TIME C. DESCRIPTION: What Happened: Cause: i. Consequences: Actions: Current Status:
- D. LICENSEE NOTIFICATIONS: (What notifications have been made.)
STATE (S) ' : LICENSEE MANAGEMENT LOCAL OTHER
- NRC RESIDENT OTHER
.. E.. PRESS RELEASE: Hasl a press release been made or planned? Yes No
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7
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. . . . . . . . . . - . ... . - . . _ . - . , - - - - . ~ - - . . . .- .- .,--..:... . . . . . .
. EPP-002 ATTACHMENT IVA PAGE 3 0F 4 NRC ONE HOUR NOTIFICATION Part II-Complete for all ALERT, SITE AREA, and GENERAL emergencies Licensee Actions:
Taken Planned - Property Damage . Radioactivity Released (or Increased Releasa): Liquid / Gas? Location / Source of Release Elevation Release Rate Duration Stopped? Release Monitored? Amount of Release
- f. Tech. Specs.
Increased Radiation Levels in a Plant: Location (s) Radiation level (s) Areas Evacuated Maximum site boundary dose rates Location Integrated dose Location Meteorology: Wind Direction from Wind Speed (Meter /sec or miles /hr) T ( C or F) Temperature ('C or *F) O Stability Class A B C D E F G Raining (Yes/No) Projected Peak: Dose Rates Integrated Dose 2 mi (WB/I) (WB/I) 5 mi (WB/I) (WB/I) 10 mi (WB/I) (WB/I) Sectors (WB/I) (WB/I) Contamination (Surface): inplant onsite offsite Reactor Operations: Reactor System Status Power Level l Pressure Temp Flow (pumps on) Coolinc; Mode ECCS Operating / Operable l Containment Status l Containment Isolated? Containment Temp Containment Press Containment Radiation R/hr. l Reactivity Control l Control Rods Inserted Status of Emer. Boration System 1 O l -. - - ,- --, . - . ._ .
TJCLEAR OPBAT.0)S EPP oo2 ATTACHMENT IVA CO PY No. . . . . . . ./8.f.0. . . . . . . . . PAGE 4 0F 4 REVISION 3 INCIDENT NOTIFICATION INFORMATION Part II Steam Plant Status: S/G Levels Equip. Failures Feedwater Source / Flow S/G Isolated? Electrical Dist. Status: Normal Offsite Power Available? Major Busses / Loads Lost D/G Running? Loaded? Security / Safeguards: Bomb Threat: Search Conducted? Search Results Site Evacuated? Extortion: Source (Phone, letter, etc.)? Location of Letter Intrusion: Insider? Outsider? , Furthest Point of intrusion () Fire arms related? Stolen / Missing Material? Demonstration: Size of Group Demands Violence? Fire arms related? Sabotage / Vandalism: Radiological? Arson Involved? l Stolen / Missing Material? 4 i O
- EPP-002 ATTACHMENT IVB PAGE 1 OF 3 gfd>)
' REVISION 3 S-is ANI EIGHT H0UR NOTIFICATION ANI is to be notified within eight (8) hours of the' . declaration of an Alert, Site Emergency, or General Emgergency in accordance with pages 2 and 3 of this attachment, ,
American Nuclear Insurers (ANI) Phone No. Easy Access'u / Person Contacted Time Date Callers Signature
- ~
1 4 O
- . .-. . . .- ~. . . _._._ _._ .. .. .
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EPP-002 ATTACHMENT IVB PAGE'2 0F 3
<- REVISION 3 ANI NOTIFICATION (1) This is (Name) (Title)
(2a) This is a drill (2b) This is NOT a drill - . (3) I am notifying you of an accident at the V. C. 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: O s-(6c) Release Rate: (6a) Noble Gas (6c) Release. Height (6b) (6d) Meteorological Conditions: (6a) Wind Speed (mph) (6b) Wind Direction (blowing to) (6c) Stability Class (6d) Precipitation (6e) Projected Dose At: Site Boundary 2 Miles 5 FEles 10 Miles (60) Dose Rate--Whole Body (10 A', (10B) (100) (10D) (6g) Integrate Whole Body Dose ( hour projection) (llA) (11B) (110) (11D) (6h) Dose Rate--Thyroid (12A) (12B) (120) (12D) (61) Integrated Infant Thyroid ( hour projection) (13A) (13B) (130) 13D) (6j) Sectors Affected (14A) (14B) (14C) (14D)
. . ~ . . . . _ .. .. . . _ _ . . . . . - .
- EPP-002 ATTACHMENT IVB PAGE 3 0F 3 REVISION 3 V 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, completo 8a through Sc) Yes/No Reason (8a) Law Enforcement (8b) Fire Departments (8c) Hospital Facilities (9) Public evacuation required Yes No Not at this time (9a) If "Yes" or "Not at this time", affected sectors O G
-w,n - - , - s- y----- , . - - . - . - - - - ., ,
,, . - - , - - - - , . . , , , - w--
EPP-002 ATTACHMENP V PAGE 1 0F 3 REVISION 3 1 0FF-SI'IE EMERGDICY SERVICES NA!E OF PERSON AGBICY/ PERSONNEL PHONE Nurmw TIME A. Canpany Physicians (Pinner Clinic) .
- 1) Carrol A. Pinner III M.D. - Primary i !(24 hrs.)
- 2) Carrol A. Pinner Jr. M.D. - 1st Alternate f
- 3) Harriet A. Pinner, M.D. - 2rri Alternate B. Hospital Facilities ,.
- 1) Richland Menorial Hospital Give the followirg information:
This is the Virgil C. Suniner Nuclear Station. This is a Drill This is not a Drill We have contaminated /non-contaminated
') injured person being transported to your facility.
- 2) Radiation Bnergency Assistan Center Training Site (Reacts) ig 24 hour-{ -
-Beeper Q -
^
C. Anbulance Service 1a) Energency Medical Services of Fairfield County ; or lb) Alert MASP for standby ,
^
transportation. ll _
-T or ,
- 2) U.S. Army fGST Operations t or .
l NOIE: Alert Security of Bnergency Vehicle arrival as soon as request (s) for Off-Site Bnergency Services are canpleted.- Ext.;j+, - m
. P's d ..
C',I)
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f
., . . EPP-002 ATTACHMENT V PAGE 2 0F 3 f OFF-SITE E4ERGENCY SERVICES NAME OF PERSON AGENCY / PERSONNEL PHONE NuruJ.tv TLVE Give the following info 1mation for itens la and 2 above.
1his is a Drill 'this is not a Drill , We have contamstated/non-contaninated injured person (s) requirirg transportation to Richland Memorial Hospital. (The anbulance ' must enter the site via the main gate, using (denote route to be taken) or the helicopter should lard at the primary landigr, pad (denote route to be taken) D. NSSS Supplier /A.E. Title Name Office Home HHL
,. ~
- 1. Site Service Manager Bob Stough 0 'j.
'A.
Notes: (1) The area code of the above phone numbers iss
~
(2) The phone beeper number is c ~ _
.m .g y: -c_ _-
') 2. Operating Plant Service Yanager John Miller t @h;t;dd9 - '
a ' =:-*j?;*? 1 "
':Ji -'
lst Alternate Tim Sullivan ~ v' '
~ ~
2nd Alternate Joln Gallik 3 Service Response. Joe Leblang .' Manager . lst Alternate John Miller ..
.( , '
2nd Alternate Dave Campbell , ,
- 4. Energency Response Hank Ruppel Director ,
e- ,- 5 Energency Response .Ron Lehr ; .. . . 2 Nis Deputy Director .- ' M'.8 #t 2. 19 .. , f E
- 6. Energency News Mike Mangan Q, N3 M ?M :ca((W[j$ Sj ' ~'
Communications Note: Unless irdicated otherwise, all phone numbers are area code 412. Mlere an area code other than 412 is shown, it applies to the office, home, ard HHL numbers "? ; ?
- 2) GAI w r (Nonnal E J'- . J' = -
O%j Working Hours) h. k>
%,N wt l:R.l1 N
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I
EPf-002 ATTAODelT V PAGE 3 & 3 REVISION 3
- OFF-SITE DERGENCY SERVICES NAFE OF PERSON AGDICY/PERSONIEL PHONE NCffIFIED TIME
.~
E. Fire Services ,
- 1) Fairfield County Fire.. Services Give the followirg information:
This is the Virgil C. Sumer Nuclear Station. This is a Drill This is not a Drill We request fire fightirg assistance at the Stmmer Nuclear Station. She fire truck must enter via the main gate, usirg (denote toute to be taken)
\
F. Incal Law Enforcement , ior 3 (off-normal hours) , '[ O . ONational Weather Service (Backup to Load Dispatcher for weather info ~
- 1) Columbia - .7
- 2) Greer -
b+ . :. 4 7 4 CALLER'S SIGNATURE DATE- - -
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y.
, . EPP-002
- ATTACHMENT VIA PAGE 1 0F 1 REVISION 3 FOLLOWUP NOTIFICATION ALERT NAME OF EASY PERSON AGENCY / PERSONNEL NORMAL ACCESS NOTIFIED TIME -
----- ~. .
1.* S.C. Dept of Health &,5. - Environmental Contr61,\' - Bureau of Radiological N ' ^d Health Notifications complete: Caller's Signature Date
' Dedicated Line Also Exists.
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- EPP-002 ATTACHMENT VIB PAGE 1 0F 1 FOLLOWUP NOTIFICATION SITE EMERGENCY NAME OF EASY CALLERS PERSON AGENCY / PERSONNEL NORMAL ,
ACCESS SITE SIGNATURE NOTIFIED TIME - 1.0 S.C. Dept of Health &1.. . N/A Environmental Control, / Bureau of Radiological . . _ . _ _ _ _ . _ d' Health Notifications complete: Caller's Signature Date NOTE: When the State Forward EOC is established the State BRH will move their operation to the State Forward EOC and communication will be via the State Forward E.O.C. Dedicated Phone Line.
' Dedicated Line Also Exists.
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, . EPP-002
- ATTACHMENT VIC-PAGE 1 0F 1 REVISION 3 eG.
W- FOLLOWUP NOTIFICATION GENERAL EMERGENCY NAME OF EASY PERSON AGENCY / PERSONNEL NORMAL ACCESS NOTIFIED TIME - 1.0 S.C. Dept of Health & Environmental Control,' s Bureau of Radiological y- ~ ~ Health The following notifications shall be made by the TSC or EOF Communicator until such time that the S.C. State forward EOC is staffed.
- . .r~"': f " :}; -...
2.9 Emergency Preparedness f P * ^' IE W#T . DivisionAdjutantGeneral'sf i .i Office l - -
- )
r 30 Fairfield County I S
. . .'- u ,q a .
, 14 . 0 Newberry County ,,,f.Qg3feg-fly..
GTi rs:siyyQ::i1
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% Richland County -
a;9 - ^;W; y.-e;a4' Lit?W.
'I S: (," ~E -
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6.0 Lexington County , Notifications complete: Caller's Signature Date NOTE: When the State Forward EOC is established the State BRH will move their operation to the State Forward EOC and communication will be via the State Forward E.O.C. Dedicated Phone Line.
- Dedicated Line Also Exists.
D 4
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EPP-002 o . ATTACHMENT VII PAGE 1 OF 2 REVISION 3 f :) TSC/OSC EMERGENCY TELEPHONE LIST . ,- Technical Support Center QQ Nuclear Regulatory Commission U4h ::D
's :;g y-Nuclear Regulatory Commission
- v. s-v ,
u' Nuclear Regulatory Commission
++: a: .
;[' . . \, TSC. Display Room
- n. V' y '"I' TSC Display Room TSC Display Room Dose Assessment Area Technical Support Engineers
' I
; Technical Support Engineers
-f Technical Support Engineers Technical Support Center Communicators
[ () e -_ - ~; Telecopier Phone to EOF l Radiation Monitoring Teams
. Assistant Manager, Support Services-Vince Albert
, j Radiological Assessment Supervisor-L.A. Blue f
f, Assistant Manager, Technical Support-B. Croley
, Security Supervisors-J. Sefick/Capt. Tuttle Assistant Manager, Maintenance Services-M. Quinton Assistant Manager, Operations-L. Storz Westinghouse .
GAI OSC OSC
.~
d
-.....--.._--..----._-_____s
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'EPP-002
. ATTAC1 2 ENT VII PAGE 2 of 2
&a '
T a c w m e t t_ eunonT ci2xi d "" * "3
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~
J e PLANT STK USI N ' M,' . i ' DISPLAN AAEA f . u ., DOSE. /
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ASSESSMEMT U - ARE.A j :- 7 - < e
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EPP-002
*
- ATTACHMENT VIII -
o PAGE 1.0F 3 REVISION 3 V4 ' 0FF-SITE EMERGENCY TELEPHONE LIST -
' O}} - , *
.e '
q; ~ Emergency Operations Facility .- -
- :- : . .. .. a
[. x,a --. EOF Communicator Area
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EOF-NRC -
'% ar 6 ;1 EOF-NRC
.; . ~ . ,; _
, ;. 'l$.d ' EOF-NRC . , -b
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EOF-Technical Support Coordinator-M.B. l Whitaker EOF-Security Coordinator-J . Harrison EOF-Media Coordinator-R. McSwain
, EOF-Genaral Services Coordinator-J . Bailey EOF-Construction / Repair Coordinator-J. Woods
. EOF-Offsite Radiological Monitoring b] Coordinator-Bill Baehr EOF-Technical Support Engineers i
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SOUTH' CAROLINA ELECTRIC AND GAS COMPANY ' VIRGIL C. SUMMER NUCLEAR STATION NUCLEAR OPERATIONS C,
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EMERGENCY PLAN PROCEDURE EPP-003 IN-PLANT RADIOLOGICAL SURVEYING REVISION 2 JUNE 10, 1982 NON-SAFETY RELATED
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Reviewed by: 1 V 2. ORIQINATOR COT this revision) D&te Y ., -
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1 lL" QUAL'IFIED REVIEWER Date l l Approved:
$71H/2ldd fb2-(Dats PLANyANAGEFF [ Of Date Issued:JUL 2 71982'
( Form AP-101-2, (1/80) O
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1 . ! -4 i EPF-903 i PAGE i ' I REVISION 2 i , 6/10/82 i' LIST OF EFFECTIVE PAGES < PAGE REVISION i I i i 2 6 I 2 'I ! l 11 - s f 1 s. 2
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EPP-003 PAGE 11
. REVISION 2 j 6/10/82 '4 TABLE OF CONTENTS PAGE List of Effective Pages i PURPOSE 1 1.0
2.0 REFERENCES
1 1 ) 3.0 CONDITIONSANDPREREQUINITES 4.0 PROCEDURE 2 ATTACHMENTS . Attachment I - Survey Record Attachment II - Approximation of Air Sample Iodine aid Particulate Concentrations with RM-14 and HP-210.
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Attachment III - Estimate of Iodine Concentration with RM-14 and HP-210 () Attachment IV - Estimate of Particulate Concentration with RM-14 and HP-210 Attachment V - RCA Access Routes i i
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EPP-003 REVISION 2 6/10/82
-- 1.0 PURPOSE 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 HPP-151. "Use of Radiation Work Permit (RWP) and Standing l Radiation Work Permit (SRWP)". 23 HPP-401, " Issue, Termination, and Use of RWP's". 2.4 HPP-153. " Administrative Exposure Limits". l 25 EPP-019, " Emergency Equipment Checklist". 2.6 HPP-302, " Radiation and Contamination Survey Techniques" 2.7 HPP-810, " Sampling of Radioactive Gases and Liquids".
) 2.8 HPP-303, " Airborne Activity Sampling Techniques and V Procedures".
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 .ne TSC immediately after notification or upon Protected .rea Evacuation. 33 or In-Plant monitoring personnel should report to the H.P. Lab as directed by the In-Plant Monitoring Director immediately upon notification or upon Protected Area Evacuation. 3.4 Standing RWP's are not applicable for entries into areas with severe or unknown exposure potential. 35 Entries into areas where a severe or unknown potential for radiation exposure exists should be limited to: k PAGE 1 0F 5
EPP-003 REVISION 2
,-~ 6/10/82 ,g V 3.5 1 operati.on of valves and components essential to the safe operation of the plant.
352 Repair activities essential to the safe operation of the plant. 3 5.3 obtaining information necessary for proper evaluation of existing conditions. 3 5.4 Rescue attempts t.o preserve human life. 3.6 Areas with severe or suspected severe radiological conditions will be entered using the " buddy system", with a. two man back-up team dressed for entry, (with the exception of donning SCBA), in stand-by. NOTE: A minimum of one back-up team, in stand-by, is sufficient for multiple team entries. All personnel who are considered back-up (not actually performing an activity) should remain in an area of low l radiation levels where practicle to keep their exposures ALARA. 37 Protective requirements for entering areas where high levels of radioactive contamination are suspected are as S follows: 371 Minimum 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 NOTE: Backup teams should not don the plastic suit until ready for entry into the affected area. 372 Additional protective regt11rements are as follows: O PAGE 2 0F 5
EPP-003 REVISION 2 6/10/82 L '3} Condition Protective Requirements Noble gas concentrations TLD placed under protective suspected > 1 x 10-3 clothing. pei/ml Eye protection if fuel damage has occurred or suspected. Iodine concentrations SCBA suspected > 10 x MPC Lapel Air Sampler H3 concentrations SCBA' suspected > 10 x MPC Plastic Suit Particulate' concentrations Particulate mask or SCBA suspected > 10 x MPC (SCBA required if > 50 x 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. () 38 Continuously monitor radiation levels as surveys are performed. 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 efforts 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/ml. 3 12 Reference 2.6 should be referred to for survey techniques and considerations. l 3 13 Reference 2.7 and 2.8 should be referred to for sampling techniques and considerations. O PAGE 3 0F 5
EPP-003 REVISION 2 6/10/82
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4.0 PROCEDURE In-Plant Monitoring Director (guidelines)
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4.1 4.1.1 Activate In-plant survey teams as needed. 4.1.2 Monitor readings from the radiation monitoring system and maintain display drawings and data logs current 4.1.3 Establish and maintain communications with in-plant surveyors. 4.1.4 Identify and coordinate survey and sampling locations and routes taken, with the Emergency Director, Radiological Assessment Supervisor, and in-plant surveyors, to minimize exposure. i NOTE: Attachment V of this procedure may be used to evaluate and determine access routes to vital areas l under post-accident conditions. 4.1.5 Coordinate issuance of Radiation Work Permits as specified in References 2.2 and 2.3 If time does not permit the generation of RWP's to be ( NOTE: used initially, ensure the following is entered in the logbook: date, time, work performed, location, originator / department, known radiological conditions, l approvals and actual doses received after the job is l completed. 4.2 In-Plant Surveyors 4.2.1 Don high range personal dosimeter. 4.2.2 Obtain radio (s). From H.P. Lab or TSC and establish I communications with TSC. NOTE: Communications to be kept 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 l ' protective clothing and respiratory protection, as required. O PAGE 4 0F 5
- EPP-003 REVISION 2 6/10/82
( ' A teletector, or equivalent, should be used NOTE: when entering areas of waknown exposure potential. If there is a potential for high level beta exposure, an instrument calibrated for beta measurements (eg. RO-2) shall be used. Check all instruments for response to radiation prior to Lse. 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-302,
" Radiation and Contamination Survey Techniques)
NOTE: TSC and surveyors should collaborate to determine appropriate post accident efforts. (eg. type 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. t
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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. 4.2 9.1 If excessive background is present, send samples to the Environmental Lab for I 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 survey records in the TSC and/or submit the records through the Emergency Coordinator to the Documents Section for retention in the Plant History Files. L) PAGE 5 0F 5
- EPP-003 ATTACHMSff I PAE l of 1 g REVISION 2
( L SURVEY RECORD TYPE OF SURVEY _ DA'IE TIME RADI0IOGICAIl l SMEAR l l SURVEY BY INST. TYPE INST. REVIEWED BY SERIAL NO. EFFY. BUILDING DATE CALIB BKG'D RB4 ARKS COUNTED BY RADIOIDGICAL Mr/hr BEI'A SbEAR ALPHA Iter Equipmnt or Total Count Grosa Net DPM No Location Distance Gamm Beta Neutron Counts Time c/m c/m 100 cmp l l l l l O
. EPP-003 ATTACHMENT II PAGE 1 0F 1
() REVISION 2 ATTACHMENT II APPROXIMATION OF AIR SAMPLE IODINE AND PARTICULATE 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 riiters 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.
Use graph (Attachment III) to approximate iodine concentration or l 3 perform computation at the bottom of the graph. Recommended allowable background is <100 cpm.
- 4. Use graph (Attachment IV) to approximate gross particulate i
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' 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.
- 4. Calculations at the bottom of Attachment III and IV are based on The only variables the constants stated above in steps 1 and 3 are the actual volumes of the samples.
a.) To determine volume in cu.ft., multiply run-time in minutes by flow rate in cu.ft. (20 cfm x 10 min. = 200 cu. f t) . l b.) To determine volume in liters, multiply run-time in minutes by flow rate in liters per minute (20 1/ min x 10 min. = 200 liters)
EPP-003 ATTACHMENT III PAGE 1 of 1 m REVISION 2
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EPP-003 ATTACHMENT V PAGE 1 0F 8 O REVISION 2 POST ACCIDENT RCA ACCESS ROUTES This Attachment provides access routes to specific areas within the Radiation Control Area of the plant. These access routes are the most direct route starting at the HP access control area located on the 412' elevtion of the Control Building. The routes described here are to be used as a guide in determing actual routes to be taken under emergency conditions. EPP-011 " Personnel Search and Rescue", requires routes to be planned and approved by the Shift Supervisor and Health Physics prior to entering the Radiation Control Area during emergencies. Existing and expected radiological conditions will be considered in determing the actual routes taken to ensure that entry team exposures are maintained ALARA. Whenever access routes beginning on the 412' elevation of the Contro' Building are not practical, entries into affected areas of the plant fom other elevations or outside ground level access points should be considered and utilized if practical. O
EPP-003 ' ATTACHMENT V PAGE 2 OF 8 p REVISION 2 ( j ELEV. AREA ROOM ROUTE 374' A - RHR/ Spray Pump Rms. & Cooling Units 74-16&l7 1 388' B - Charging /S.I. Pump Rms. 88-23&24 '3 to A/8 to B&C C - Charging /S.I. Pump "C" Auxiliaries 88-13NE 7 Local Control Panel D - S.F. Pit Hx. 88-13N 9 412' F - S.F. Pit Cooling Pumps & Local 12-18 6' Control Panels G - Eng. Safety Feature Motor Control 12-28 4 Center . H - Waste Processing System Control Panel 12-15 5 400' I - Charging /S.I. Pump Cooling Units 00-02 10 J - Eng. Safety Feature Substation Bus 63-01 14 463' 0 and Motor Control Center K-H2 Recomb. Control & Power Supply 63-19 13 Panels . L-H2 Recomb. Control & Power Supply 63-09 11 Panels ! M1- Reactor Bldg. Atmos. Sample Collect- 63-01S(FHB) 12 Pt. &H2 Gas Analyzer l M2- Reactor Bldg. Atmos. Sample Collect- 63-17 13 Pt. &H2 Gas Analyzer N - TSC 0 - Control Room 412' P - Sample Room 15 (CB) Q - Radio Chem. Room 15 R - Count Room 15 436' S - Nuclear Blowdown 14A (AB) O T - Pressurizer Heater Controls 14A
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SOUTH CAROLINA ELECTRIC AND GAS COMPANY VIRGIL C. SUMMER NUCLEAR STATION NUCLEAR OPERATIONS
\!JCLEC OPERATIONS COPY [10.. . . . 252 :G. . . . . . . . .
EMERGENCY PLAN PROCEDURE
~
EPP-004 OUT-OF-PLANT RADIOLOGICAL SURVEYING REVISION 3 JUNE 11, 1982 NON-SAFETY RELATED Reviewed by:
& O 2.-
ORIGIN ATOR' Tor this revision) U D4te l w h- I $ QUALIFIED' REVIEWER ' Date Approved: l M/Nh? ~7 C/ch2 PLg? MANAGER / M, (Date' Date Issued:hUl. 2 7 fo 2 O' Form AP-101-2, (1/80)
7..__..__ ._, _._ - . _ . - _ . . . . . . . _ . _ _ - _ - - _ _ _ . . _ _ _ . __ ,_ _ - - - , _ _ . _ _ _
~
s EPP-004 PAGE i { ' i- REVISION 3 I - 6/11/82 i i . ! LIST OF EFFECTIVE PAGES 1 i i PAGE REVISION i i l' i 3 ! 11 3 1 i ! 1 3 t ~ 2 3
- 3 3
\ 3 ! 4 1 l i ATTACHMENTS ! i l , Attachment I , 3 Attachment II 3 i
- Attachment III 3
) Attachment IV 3 t i i i i t l l I l l i t i l ll , i a ,i !O i p i l
EPP-004 PAGE 11 REVISION 3 6/11/82 TABLE OF CONTEllTS 1. List of Effective Pages 1 1.0 PURPOSE 1 REFERENCES 1 2.0 CONDITIONS AND PREREQUISITES 1 30 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 't 4 8 O
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EPP-004 REVISION 3 6/11/82 1.0 PURPOSE (} 1.1 To provide guidance for the direction and implementation of radiological surveys outside the plant in the event of an emergency.
2.0 REFERENCES
2.1 " Virgil C. Summer Nuclear Station Radiation Emergency Plan." 2.2 EPP-005, "Offsite Dose Calculations" 2.3 HPP-302, " Radiation and Contamination Survey Techniques" 2.4 HPP-303, " Airborne Activity Sampling Techniques and Procedures". 2.5 EPP-007, " Environmental Monitoring". 30 CONDITIONS AND PREREQUISITES 31 Out-of-Plant survey activities will initially be directed from the TSC. When practical, direction of areas outside a 1 mile radius will be transferred from the plant, to the ( s-EOF. The EOF is responsible for ensuring the TSC/ Out-of-plant Monitoring Director is continuously informed of monitoring results from outside the 1 mile radius. 32 The Out-of-Plant Monitoring Director should proceed to the TSC immediately after notification, or upon protected area evacuation. 33 Out-of-Plant monitoring personnel should be trained on meteorological effects on plume dispersion and projected exposures to the public. 3.4 Coordinate with TSC/ EOF to determine travel routes which minimize plume exposure. 35 Minimize exposure while taking surveys, (e.g., 10 min. air samples). Coordinate surveys with TSC/ EOF to prevent unnecessary exposure. V PAGE 1 0F 4
EPP-004 REVISION 3 6/11/82 I ) 36 As time / conditions permit, surveyors should initiate spot
\/ radiation and/or contamination surveys, to expedite data collection; (e.g., if in the parking lot, conditions may allow surveyor to monitor vehicles in immediate area).
37 AgZe iodine filter cartridges should be used for air sampling when noble gas concentrations are suspected. 3.8 Smears of horizontal surfaces should be taken (ie; automobiles, equipment etc.) to provide data on environmental conditions.. 39 Limit the use of protective clothing, as radiological conditions warrant, to minimize public concern. 3 10 Retain all samples and sample data for re-evaluation. 3 11 Monitoring results shall be maintained by the TSC and EOF. All monitoring results from outside the 1 mile radius should be maintained by the EOF and stored with environmental program data for subsequent report preparation. Monitoring results within the 1 mile radius should be maintained by the TSC and stored with plant records. 3 11.1 All survey and sample results obtained from outside the 1 mile radius will be documented and maintained (y r
'/
) by the EOF. This is the central location for sample / survey results outside of the 1 mile radius.
! 3 11.2 All surveys and samples obtained within the 1 mile radius will be documented and maintained by the TSC. l NOTE: All samples will be retained for laboratory analysis and stored at the locations specified above for possible future analysis and evaluation. Do not dispose of any samples without approval of the Radiological Assessment Supervisor. 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. O V t PAGE 2 0F 4 l
~ EPP-004 REVISION 3 , 6/11/82 ('\ 4.1.3 Frequently monitor meteorological and effluent
\_ conditions, keeping surveyors updated so that routes can be chosen to keep surveyors' exposures ALARA.
4.1.4 Identify sampling locations and routes, using priorities listed below as guidelines: , l 4.1.4.1 Residential areas within projected plume. j 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 environment.a.1 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 4.2.1 Obtain emergency kits from Service Building Annex and radios from Health Physics Lab or TSC. Check seals and inspection on Emergency Kits. NOTE: If seals are broken or inspection date is not current on emergency kits, perform a quick check to ensure emergency kits are adequate for field use. 4'.2.2 Check instruments in kit with the source supplied for l response to radiation. I 4.2 3 Obtain vehicle from Security or the E.D. for off-site transportation. 4.2.4 If not already wearing personal dosimetry, don TLD and self-reading dosimeter contained in emergency kit. o PAGE 3 0F 4
EPP-004 REVISION 3 6/11/82 4.2.5 Establish communication with TSC and/or EOF. If O' radios are not operable, use the nearest telephone for communication. 4.2.6 Obtain current pertinent data from TSC/ EOF (estimated release rates of: particulate, iodine and noble 5ases; wind direction; projected plume area; etc.) 4.2 7 Perform sur'veys, as directed from TSC/ EOF, per References 2.3, 2.4, and/or 2.5 Ensure instruments are source checked for response after each use. NOTE: TSC/ EOF and surveyors should collaborate to determine appropriate post accident efforts (e.g., type sampling, sample locations, etc.) to ensure maximum data obtained with a minimum of manpower /manRem expended. 4.2.8 Analyze samples in accordance with applicable HPP's using available equipment. Approximate air sample iodine and particulate concentration in accordance with Attachment II. 4.2 9 Record sample and survey data on Attachment I. NOTE: Easure that smear results and loc &tions of contamination levels > 1000 dpm/100cm2 are recorded O' in 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 as per Reference 2 5 l NOTE: Take precautions to minimize exposure to environmental TLD's during transportation either to or from sampling station. i l - O PAGE 4 0F 4 l
9
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. ATTACHMENT I PAGE 2 0F 2 REVISION 3 SURVEY INSTRUMENT INFORMATION 7 NSTRUMENT NUMBER 1 INSTRUMENT NUMBER 2 INST. TYPE INST. TYPE SERIAL NUMBER SERIAL NUMBER CALIB. DATE CALIB. DATE SOURCE CHECK SOURCE CHECK (INIT) (INIT)
EFFICIENCY (IF REQUIRED) EFFICIENCY (IF REQUIRED) INSTRUMENT NUMBER 3 INSTRUMENT NUMBER 4 INST. TYPE INST. TYPE SERIAL NUMBER SERIAL NUMBER CALIB. DATE CALIB. DATE SOURCE CHECK SOURCE CHECK (INIT) (INIT) EFFICIENCY (IF REQUIRED) EFFICIENCY (IF REQUIRED) j NOTES: 1. Instrument number on f ront sheet should be 1 thru 4 from above information. REMARKS: l i I l l O l - .- _ - _. _ . ._ _ . _
T EPP-004' ATTACHMENT II PAGE 1 0F 1 REVISION 3 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 f cartridge once it is placed in poly bag.- Particulate filters cannot be placed in poly bag until aftee a count rate is obtained. ,
- 2. Determine volume of air sampled in litera. or ft3 as indicated on instrument.
3 Use graph ( Attachment II ) to approximatie ' iodine concentration or perform computation at the bottom of the graph. Recommended allowable background is < 100 cpm.
- 4. Use graph (Attachment IV) to approximate gross particulate concentration or perform computation at the bottom of the graph. Recammended allowable backgroand is < 100 cpm.
Bases ' 8 O 1. Recommende) allowable background is 100 cpm. is derived using .37% detection efficiency with an I-131 standard and a 90% filter collection erriciency. Attachment III
- 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. , j 3 Attachment IV is derived using 10% detection efficiency and a 99% filter collection efficiency.
- 4. Calculations at the bottom of Attachments III and IV are based on the constants stated above in steps 1 and 4. Tre /
only variables are the actual volumes of the samples. a.) To determine volume in cu.ft., multiply run-time in minutes by flow rate in cu.ft. (20cfm x 10 min = 200 cu. ft). b.) To determine volume in liters, multiply run-time in minutes by flow rate in liters per minute (20 1/ min x 10 min.= 200 liters). E t b i l w s
46 7520 1 ug toommoe c 3. s cycus *
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N i' ESTIMATE OF IODINE CONCENTL(ION WITH RM-14 AND HP-210
-Approximate Iodine Concentration in pCi/ml
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. - l SOUTH CAROLINA ELECTRIC AND GAS COMPANY VIRGIL C. SUMMER NUCLEAR STATION NUCLEAR OPERATIONS g1G 0?3 CONS -
~~******
@ W N0.... I EMERGENCY PLAN PROCEDURE EPP-005 0FFSITE DOSE CALCULATIONS REVISION 3 AUGUST 6, 1982 O' NON-SAFETY RELATED 9/RL ,
ORIGINATOR Cor this revision) IDkte , 1 l IU uu DISCIPLINE SUPERVISOR shtu
' Date Approved:
/
PLANT MAN AGER SY Gare ~ l Date Issued: O
EPP-005 PAGE i REVISI0ri 3 8/6/82 LIST OF EFFECTIVE PAGES . P_aage Revision ; i 3 11 3 -i 111 - 3 1 3 ; 2 3 3 3 4 3 5 3 6 3 ATTACH!!ENTS I 3 II, Pages 1 and 2 3 III, Pages 1 and 2 3 IV 3 V 3 VI 3 VII 3 VIII 3 O P XI 3 XII 3 ' l XIII, Pages 1 through 3 3 XU 3 ; f 3 I i I i lO
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EPP-005 Page 11 Revision 3 73 8/6/82
'- TABLE OF CONTENTS List of Effective Pages Flow Chart 111 1.0 PURPOSE 1- -
2.0 REFERENCES
1 30 CONDITIONS AND PREREQUISITES 1 4.0 PROCEDURE 2 50 BASES 5 ATTACHMEtPPS ATTACHMENT I - Sample form: Meteorology and Source Term Report Form ATTACHMENT II - Sample Form: Emergency Off-Site Dose Calculation Using Stack Monitor Source Term ATTACHMENT III- Sample Form: Off-Site Dose Calculation () ATTACHMENT IV - Sample Fonn: Using High Range Monitors Activity Release Status ATTACHMENT V - Sample Form: Out of Plant Monitoring Dispatch & Data Form ATTACHMENT VI - Sample Form: Dose Off-Site (Dose Rate) Calculation from Environmental Monitoring ATTACHMENT VII -Dose-Concentration Conversion ATTACHMENT VIII-Delta T Atmospheric Stability Classification ATTACHMENT IX - Sigma Theta Atmospheric Stability Classification l ATTACHMENT X - Meterological Sector Definition ATTACHMENT XI - Correction Factor for High Range Monitors ATTACHMENT XII -Protective Action Guides (PAGS) ATTCHMENT XIII- Pasquill-Turner Method for Determining Atmospheric Stability. l () ATTACHMENT XIV- Volume-Pressure Steam Curve l l _ . . . . . . _ . _ . , . . . . . ._ . _ . _ . _ . . .. . .._ _. .._..__ , . _ .... _ . _ . . _ . . . _ _ _ _ _ . _ . _ . .
EPP-005 O suc l Page 111 Revision 3
'f"J 4.0 l :== ! .se l ,, g g3 rives b -
Method *
- 4. 3 .
VIII :Ae ee at task w Stasility Stat 111tv IX 4.2.1 4.2.2 XIII
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EPP-005 REVISION 3 8/6/82
,-s 1.0 PURPOSE I I \ 1.1 To provide methods for estimating wholebody and child thyroid dose rates due to abnorraal releases of radioactive materials to the environment.
1.2 To provide a method of comparing the integrated wholebody and child thyroid doses to the EPA Protective Action p Guides (PAG's). .
2.0 REFERENCES
2.1 " Virgil C. Summer Nuclear Station Radiation Emergency Plan". 2.2 American Society of Mechanical Engineers, " Recommended Guide for the Prediction of the Dispersion of Airborne Effluents", May 1968. 23 Dames and Moore , " Data Reduction Procedure for Virgil C. Summer Nuclear Station", September 1974. 2.4 Slade, D. H., (ed.), " Meteorology and Atomic Energy - 1968", TID-24190, Division of Technical Information, USAEC (1968). [\/ ) 25 Turner, D. B., "A Diffusion Model for an Urban Area", Journal of Applied Meteorology, February 1964. 2.6 U. S. Nuclear Regulatory Commission, Proposed Revision 1 to Regulatory Guide 1.23, " Meteorological Programs in Support of Nuclear Power Plants", September 1980. 27 NUREG-0654/PEMA-REP-1, " Criteria for Preparation ~ and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants", December 1980. 2.8 Emergency Assessment and Response Systems,. (EARS 1,000 and EARS 9845). Technical Manual. Applied Physics Technology, Inc. . 29 EPA-520/1-75-001 (Revised June 1980) " Manual of Protective . Action Guides and protective actions for Nuclear Plants." 2.10 EPP-002 Communication and Notification. 30 CONDITIONS AND PREREQUISITES 31 Hone PAGE 1 0F 6 _ _ , - . . , . . . . . . _ . , . . , _ - - . . _ . . . . . . . _ . ~ . ~ . . - . . . ,_ . _ _ _ , . _ - . . _ ._. .....m.
EPP-005 REVISION 3 8/6/82
N 4.0 PROCEDURE ^
NOTE: This procedure delineates two (2) methods by which offsite doses may be calculated (i.e., computer calculation and manual calculation) . Either method, or a combination of both methods, may be used since comparable results can be obtained. g 4.1 Overlay Selection 4.1.1 If the computer is not available proceed to step 4.2 to initiate manual calculations. 4.1.2 Use the HP98450 in the Technical Support Center to run the menu driven real-time dose projection system. The program is started by following guidance derived through Reference 2.8. 4.1 3 Complete step 4 3 so that the manual method map is available for use in case of computar failure. The map is also useful in dispatching out of plant monitoring teams. Proceed to step 4 5 4.2 Manual Method 4.2.1 Stability Class Determination () If the primary meteorological tower is inoperable proceed to step 4.2.2 otherwise, complete Part 1 of Attachment I to obtain meteorology and source term data from control room instrumentation. Method A. (below) is preferred. A. Differential Temperature ( A T) 61-10 meters and 40-10 meters Method.
- 1. Obtain a T infonnation from the Control Room instrumentation.
NOTE: Priority should. be given to the 61-10 meter information with the back up being the 40-10 meters. .
- 2. If the Control Room instrumentation is inoperable, personnel with a portable radio l may be dispatched to the meteorological tower to obtain AT information directly f rom the met tower instrumentation. Keys to towers are available in the Emergency
}
Planning Key Box located in the Emergency Operations Area of the T.S.C. [v) 4 PAGE 2 0F 6 w- - P- -,.-g,
1 EPP-005 REVISION 3 8/6/82 Determine the Pasquill Category by using f) x/ 3 Attachment VIII and select appropriate X/Q overlay found near the plotting map. I
- 4. Proceed to Step 4.3 for determination of plume location and X/Q values.
B. Sigma Theta Method ,
- 1. Review the' wind direction chart located in Control Room and determine wind range for a period of 15 minutes to 1 hour.
- 2. Wind range is determined by the 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 Category by using Attachment IX and select apprqpriate ;
overlay. 4.2.2 Backup meteorological data can be obtained from two sources, the site 2 tower and/or the National Weather Service (NWS). l l 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 canmunication should be established for the duration of the incident. Dosimetry is required for personnel at site 2. O PAGE 3 0F 6 y - - ,- -
EPP-005 REVISION 3 8/6/82
'S B. If primary tower data is not available call the
! NWS (see ref. 2.10 for phone number) and obtain '
windspeed, wind direction, % cloud cover and ceiling height. Also, obtain current forecast and note any fronts that may cause a rapid shift in wind speed or direction. Complete Attachment XIII " Turner's algorithm" to obtain i stability class. 43 Location of the Effluent' Plume 431 After determination of appropriate overlay in Section 4.2 place overlay to the center of the base map. 432 Orient the centerline of the overlay along the l direction the wind is blowing. NOTE: Wind directions are given as directions from which the wind is blowing; affected directions are 180* from the wind direction. When communicating wind direction, specify the direction from which the wind is blowing (e.g. wind is blowing from 270*) 4.3 3 The conversion from wind direction measured in degrees to wind direction in sectors is presented ps in Attachment X. 4.4 Manual Dose Calculation ! 4.4.1 Complete Part 2 of Attachment I. 4.4.2 Complete Attachment II if radiation monitor RM-A3 (Gas) or RM-A4 (Gas) is on scale. Compare results with the PAGS (Attachment XII). 4.4 3 If RM-A3 (Gas) or RM-A4 (Gas) is offscale or if l there is a steam release complete Attachment III. Compare results with the PAGS (Attachment XII). NOTE: Attachments VII, XI and XIV, will be necessary for completing Attachment III. l J PAE 4 0F 6
EPP-005 REVISION 3 8/6/82 4.4.4 Complete Attachment IV to maintain curie O' 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 EPP-002 Attachment II for transmittal and documentation purposes. 4.5 Environmental Monitoring ' 4.5.1 As soon as practical, dispatch monitoring teams to the affected meteorological sectors. Attachment V, should be used to record location and results. [ NCTE: Dose projections based on source terms should be verified as soon as possible by supportive measurements. Based on these measurements, a reassessment of the PAG's should be taken. 4.5.2 Attachment VI can be used to project doses based on environmental samples. These can then be compared with source term projections. 5.0 BASES () 5.1 This section is included to provide a brief explanation of the sources of constants and graphs used in the procedures and associated attachments. A. Step 4.3.1 - Until a full class A model is developed, subsequent to the completion by Dames and Moore of a detailed study of the Summer Station Meteorology, the (X/Q) overlays will be based on a straight line gaussion plume model as described in Reg. Guide 1.145. B. Attachment II, Section I - The Iodine to noble gas activity ratio of 0.3, until measured, is a conservative estimate from Ref. 2 9 page D-59 TMI-2 would suggest that the actual ratio could be 10-5 l or less. A fast and accurate measurement of the actual ratio is important to avoid unnecessary evacuation orders based on the Iod ne PAGS. The{glibrationconstants3.3x10-{O and 3.8 x 10 - are based on the manufacturer's calibration and various unit conversions as follows: 3.3X10-10 =1 min x 106 m x 10-6 ci 1 w ci/ml E6 sec m y 01 55XI0o CPM gg 3.8X10-10 = 1 min x 106 ci X 1 uci/ml (j E0 sec mg m x 10-6 p 31 44xl'0V CPM PAGE 5 0F 6
EPP-005 REVISION 3 8/6/82 () c. Attachment III, Section I - Same comment as B. The calibration co stants 4.0 x 10-5, 9.5 x 10-5 and 8.5 x 10- are based on the manufacturer's calibration and various conversion as follows: 4.0 X 10-5 = 0.028 m3 x 106 m X 10-6 ci x 1 min x 1 ci/ml ft3 . m , 701 E0 sec 11.7 mr/hr 9.5 x 10 0.028 m3,x 106 mg x 10-6 c1 x 1 min x 1 ci/ml fts m u c1 66 sec 4789 mr/hr 8.5 x 10-4 = 0.028 L3 x 10 6gi x 10-6 ci x 1 hr x 1 _ci/ml ft3 m3 y ci 3600 sec 9 13x10-J mr/hr D. Attachment VII - The curves follow the methodology and assumption of Ref. 2.9 The noble gas curve canes i from EQ. 2.9, the Iodine curve from EQ. 2.13. E. Attachment XIII-This description of the Pasquill-Turner 4 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 canparision with selected values from the Smithsonian Meteorological Tables.
) F. Attachment XII - Protective actions are taken from Ref.
- 29 The particulate concentration, 7.5 x 10-7p ci/ml, would lead to an exposure of 2000 MPc Hours in 8 hours. That is, it is analogous to a whole body exposure of 5 REM. Other concentrations are celated by ratio to the specified whole body exposure found in Ref 2.9.
G. Attachment XIV is a plot of standard steam table data for saturated steam. H. Attachment XI is a plot of the ratio of DOSE to concentration for mixed fission noble gas to that for 133 Xe as a function of time af ter trip. PAGE 6 0F 6
-+ - - - - - y w . --
7 + - -, - -
EPP-005 ATTACHMENT I PAGE 1 0F 1 METEOROLOGY AND SOURCE TERM REPORT FORM Windspeed mph (10 meter preferred) Time Direction degrees (10 meter preferred) . Delta T degrees (61 10) or (40 10) (circle One, 61 10 is preferred) 1 Stability Class (Use Delta T and Attachment VIII or Sigma Theta and Attachment IX or Turners Algorithm and Attachment XIII, 4T is preferred. Part 2: Source Term RMA3 CPM (net) Flow Rate RM-A4 CPM (net) Time RM-A13 mr/hr l RM-A14 mr/hr l RM-G19 mr/hr l O _ _ _ _ . _ _ _ _ __ I_- , , . ._ ,- - - - - - -
EPP-005 ATTACHMDTP II PAGE 1 OF 2 REVISION 3 DERGENCY OFF-SITE DOSE CALCULATION USING STACK IONI'IOR SOURCE TERM Time of Trip Current Time Time after Trip , RM-A3 (Gas) BM-A4 (Gas) Count Rate CPM CPM (A) Calibration 3 3 x 10-10 3.8 x 10-10 (A1) Flow rate: CFM x 0.028 = m3/ min. (B) Release Rate (A) x (A1) x (B) Ci
"'s (C)
(C) x 3600 = 01/hr (use in EPP-001) l Wind Speed: MPH x 0.45 = nVsec (D) (X/Q)u from isopleth for 1 mile nr2 (E1) X/Q: (E1)+(D) = sec/m3 (F) Noble gas dose to concentration conversicri l fran Attachnent VII x2= rem /2hr (G) i ' C1/m3 WHOLE BODY DOSE (2 hrs): (F) x (C) x (G) = ran TEr. (H) Iodine to noble gas activity ratio (use 0 3 unless measured) (I) l Iodine dose to concentration conversion i fran Attachnent VII mm/2hr C1/m3 (J) l l l t O l l l
. . . . . . . . . . . . - - . , . . . . . . ~
\ .
EPP-005 ATfAG MBTf II
- PAGE 2 OF 2
! REVISIGI 3 T
EMERGHICY OFF-SITE DOSE CAIGLATIOt! USING SPACK MONI'IOR SOURCE TEK4 Time of Trip Current Time Time after Trip Iodine to noble gas dose ratio (I) x (J) + (G) (K) l CHILD 'IHYROID DOSE: (K) x (H) = at 1 mile (2 hour) ren/2hr. (X/Q)u at 2 miles (E2) (E2)/(E1) (L2) 5 miles (ES) (ES)/(E1) (LS) 10 miles (E10 (E10)/(E1) (L10) Projected Integrated Dose in Rem per Unit Time 2 miles (L2) x (H) rert x (K) = tun 5 miles (L5) x (H) ren x (K) = ren 10 miles (L10) x (H) ren x (K) = run WHOIE BODY CHIID 'IHYROID (2 Hour) (2 Hour) 1 i l l l l %s
. _ . . . ~ _ . - _ - .,_ . . _ . . .. _ - - -- -~ ---
EPP-005 ATIA004E2ff III PAGE 1 OF 2 REVISION 3 0FF-SI'IE DOSE CALCULATION USING HIGH RANGE 10NI'IORS Time of Trip Current Time Time after Trip RM-A13 M-A14, m-019 .U DTE RATE mr/hr mr/hr mr/hr (A1) FLOW RATE CFM CFM lb/hr (A2) MASS /VOL 1 1 ft3 /lb (A3) (fecm Att. HV) Calibration 4.0 x 10-5 9.5 x 10-5 8.5 x 10-4 (B1) Correction Factor frcm Attachnent XI (B2) Release Rate (A1) x (A2) x (A3) x (B1)/(B2) E (C) s /') (C) x 3600 = C1/hr (use in EPP-001) V Wind Speed: MPH x 0.45 = m/sec (D) (XA)u fecm isopleth for 1 mile nr-2 (El) XA: (El)+(D) = sec/m3 (p) Noble gas dose to concentration conversion feczn Attachnent VII x2= mm/2hr (G) C1/m3 WHOLE EDDY DOSE (2 hr.): (F) x (C) x (G) = rem (H) 2hr Iodine tn noble gas activity ratio (use 0.3 unless measured) (I) Iodine dose to concentration conversion fecm Attachnent VII rem /2hr (J) ci/m3 0
-g- o ----g -
- - - , e -, - - - - - -
EPP-005 ATTA0MNT III PAGE 2 OP 2 O 0FF-SITE DOSE CALCULATION USING HIGH RANGE MONI'IORS Time of Trip Current Time Time after Trip Iodine to noble gas dose ratio (I) x (J) + (0) (K) CHILD THYROID DOSE: (K) x (H) = at 1 mile (2 hour) ren/2hr. (X/Q)ii at 2 miles (E2) (E2)/(E1) (L2) 5 miles (ES) (E5)/(E1) (L5) 10 miles (E10 (E10)/(E1) (L10) Projected Integrated Dose in Rem per Unit Time l 2 miles (L2) x (H) ren x (K) = run 5 miles (L5) x (H) ran x (K) = ren 10 miles (L10) x (H) rem x (K) = run WHOIE BODY CHIID THYROID (2 Hour) (2 Hour) O
== = : :_- ==
EPP-005 A'FTACHMENP IV PAGE 1 0F 1
/O REVISION 3 V
ACTIVITY RELEASE STA'IUS Time: , Elapsed time since last release calculation sec (A1) he (A2) Noble Gas l Average release rate since last calculation C1/sec (B1)*** Activity released since last calculation (A1x B1) C1 (Cl) Previous total d noble gas released C1 (D1) Total activity released (Cl + D1) C1 CURRENT IDSE ELAPSED TDE CURRENT OLD 'IUIRL 'IUIRL l DISTANCE RATE (rem /hr) (A2) DOSE DTE DOSE 1 mile X = + = can 2 X = + = can 5 X =
~
+ = ren 10 _X = + = ren Iodine Average release rate since last calculation C1/sec (B2)
Activity released since last calculation (Al X B2) C1 (C2) Previous total & Iodine released C1 (D2) Total activity released (C2 + D2) C1 CURRENT IDSE ELAPSED TIME CURRENT OLD 'IUIRL '1UIRL DISTANCE RATE (rem /hr) (A2) DOSE DOSE DOSE 1 mile X = + = ren 2 X = + = can 5 X = + = ren 10 X = + = can
### B1 x 3600 = Ci/hr, 'Ihis figure is to be used for detenninirs l Bnergency Action Levels in EPP-001 Attachment I.
lO
~L ; ~-
^^
' ' ' - - -~
t ,~ _: . _ . _- _
i EPP-005 ATTACHMENT V l PAGE 1 0F 1 REVISION 3 O OUT OF PLANT 10NITORING DISPATCH AND DATA FOIM Dispatch Unit Time Incation Miles Degrees Cmments: Report Location Confirmation YES/NO Time Rad Level R per hour (A) Air Sanple Voltme et9;te ft. x 28320 = an3 Particulate net epn Particulate Concentration = pCi/cm3 (B) Iodine net cpn(c) Iodine Concentration = p C1/an3 (C) Iodine dose to concentration conversion ren/2hr fran Attachment VII C1/m3 (D) I 2 hr. child thyroid dose (C) x (D) rem (E) 2hr l NOTE: Canpare ( A), (B), arri (E) to PAGS (Attach.t XII) l 0
EPP405 ATIRCHMENE VI l PAGE 1 0F 1 REVISICN 3 OFF-6ITE DOSE CAILULATION PROM ENVIRONMENTAL 10NI'1DRING Sample Time , Rad level Check One: Location Iodine Measured Dose Rate rem / hour (A) X/QE at location fra isopleth (B) O (A) + (B) = (C) i (X/Q)u fra isopleth at 1 mile (D1) 2 miles (D2) 5 miles (D5) l 10 miles (D10) l Does Rate at 1 mile = (C) x (D1) = l 2 miles = (C) x (D2) = rem / hour 5 miles = (C) x (D5) = 10 miles = (C) x (D10) = 10 l t
O O
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*"- """***'I " " * *I "
',l rem /hr a ent VII rem /2 hr cl/m3 Page 1 of 1 ,, f,3
! Revision 3 600
- I 500 3.5 E6 j _
l - I 400 3.0 k6
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/g iig I g l l I i g l l 3 3 3 l g l l g 3 g g 3 3 g g g 3 g g g g g g g g g , .
O 12 24 36 48 60 72 84 96.1 E6 l TIME POST TRIP (HR) - !
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-. . . - .- - . - . - ~ - - ._--_- =.- _ -.__
EPP-005 A'ITAGEGTf VIII l
, PAGE 1 of 1 REVISIai 3 A'IMOSPHERIC STABILITY CLASSIFICATION Temperature Differential (a T)
Stability Pasquill T in *F Classification Categories 61-10 m 40-10 m Extremely Unstable A 1-175 1-1.03 - Moderately Unstable B -l'.74 to -1 56 -1.02 to -0 92 Slightly Unstable C -1 55 to -1 38 -0 91 to -0.81 Neutral D -1 37 to -0.46 -.0.80 to -0.27
- Slightly stable E -0.45 to 1 37 -0.26 to 0.80 Moderately Stable F 1 38 to 3 67 0.81 to 2.16
. Extremely Stable G >3 67 >2.16
+.
O 1 i h O
, ..~ - - - , . . . . . . - , . . . - . . _ . , - . - . . , . - , - . . , ,
EPP-005 A'ITACHM!2Tf IX PAGE 1 of 1 l A'INOSPERIC STABILITY CLASSIFICATION Sip 'Iheta (ce) Stability Pasquill (degrees)* Classification Categories Extremely Unstable A
>22.4 Moderately Unstable B 22.4 to 17 5 Sli6htly Unstable C 17 4 to 12 5 Neutral D 12.4 to 7 5 i
Slightly Stable E 7 4 to 3 8 Moderately Stable F 3 7 to 2.1 Extremely Stable G <2.1 i O
- Standard deviation of horizontal wind direction fluctuation over a period of 15 minutes to 1 hour. (Wird Range dividal by 6)
Ref. USNRC Beg. Guide 1.23, Rev.1, Sept.1980. l O V
, , - - - --. n,--. - . - , , , , , . . , , . - . , _ . , . , , . ,, , _ _ _ , _ - -__ _ _ _
EPP-005 ATTAGDEff X -l PAGE 1 of 1 WEOROIOGICAL SECTm DEFINITION I Wird Central Dimetion Value IJmits of Sector Sector (degrees) in Degrees NNE 22 5, 11.25 < 1 33 75 - NE 45 0 33 75 < 1 56.25 ME 67 5 56.25 < 1 78 75 E 90.0 78.75 < 1101.25 ESE 112 5 101.25 < 1123 75 SE 135 0 123 75 < 1146.25 i SSE 157 5 146.25 < 1168 75 S 180.0 168 75 < 1 191.25 SS4 202 5 191.25 < 1 213 75 SW 225 0 213 75 < 1 236.25 WSW 247 5 236.25 < 1258 75 W 270.0 258.75 < 1 281.25 WW 292 5 281.25 < 1303 75 NW 315 0 303 75 < 1 326.25 NW 337 5 326.25 < 1348 75 N 360.0 348 75 < 1 11.25 CAUi Wird speed less than 0 75 mph MISSING Unreliable data O a
,w-
--.w. - ,-c---- -- .- -,-.----,y-. __ ,--,, _ . , _ _, , , . - _ _ _ _ _ _ -. -~ -
._, CORRECTION FACTOR f; xs u n HIGH RANGE MONITORS WG Stc ~
I I o .c a .O,4 20 - T g j i. -
- m u te > I -
n< u n e l 54 < n. cr: : I I Ie e ~ i 15 - z - _ 9 . - g ia .10 - - E - - O -
- - 1,' l 5 --
l,, , ,, 1 I I I e lt I e i l ig , , l, ,,g g g,,,t t gt t t 1 t lf t t t O l2 24 36 ,48 60 72 t14 96 TIME POST TRIP (HR) . , e g I
- e. , ,
EPP-005 i ATIR0iMENT XII PAGE 1 of 1 l'i , REVISION 3 REC 0lWENDED PIUlTDTIVE ACTIOf6 TO REDUCE WHOLEBODY AND THYIDID DCEE 14KM EXPOSLEE TO A GASEOLE PLUME l i Projected Dose (Rem) to (a)
! the Population Reconsnended Actions Consnents l (b)
Wholebody <1 No planned protective actions. Previously reconmended protec- t i , Thyroid <5 State may issue an advisory to seenc shelter tive actiom nay be recomiderej Particulate <l.5x10-7 and await further instruction.
;; or tenninated. >
1 uC1/ml Monitor environmental radiation levels. i Wholebody 1 to < 5 Seek shelter as a minimum. If constraints exist, special Thyroid 5 to < 25 Consider evacuation. Bracuate unless consideration should be given j Pa iculate 1.5 to <7.5x constraints nake it impractical. for evacuation of children ani i 10 g Monitor environnental radiation levels peg!;nant wonen. ml Control access.
! Wholebody 5 and above conduct mandatory evacuation. Seekirg shelter would be an Thyroid 25 and above Monitor environnental radiation levels ard alternative if evacuation were '
l Particulate 7.5x10-7 adjust area for mandatory evacuation based not immediately possible i ; f i,and i above on these levels.
! ml Control access.
; Projected Dose (Rem) to i hnergency Team Workers '
l Wholebody 6 Control exposure of emergency team msnbers Although respirators ani stable I ' (' , to these levels except for lifesavirg iodine should be used tere missions. (Appropriate controls for ener- effective to control dose to
, gency workers, include- time limitations, emergency tean workers, tlyroid i
respirators and stable iodine.) dose nay not be a limitirg Wholebody 100 . Control exposure of energency team msabers factcc for lifesavirg missiom. ;
; perfonnirg lifesavirs missions to this level. (Control of time of exposure will f.f +
be most effective.) i
?
(a) Them actions are reconmervied for plannirg purposes. Protective action decisions at the tine of
; the incident nust take existirg conditions into consideration.
1 l (b) At the time of the incident, officials may implement low-impact protective actions in keepirg with { the principle of maintainirs radiation exposures as low as reasonably achievable. r I i 4 ; i 2, - I
I EPP-005 ATTACHMENT XIII l PAGE 1 0F 3 REVISION 3 The Pasquill-Turner Method for Determining Atmospheric Stability If both the primary and secondary T sensors are inoperative and sigma theta is not available, the Pasquill-Turner method for defining Pasquill stability classes may be used. Before using this method, contact should be made with the NWS. This method is based on the principle that stability near the ground is - dependent primarily upon net radiation .and wind speed. Determination of stability class as a function of wind speed and net radiation is given in Table 1. In this sytem, insolation is estimated by solar altitude and modified for existing conditions of total cloud cover and cloud ceiling height. At night estimates of outgoing radiation are made by considering cloud cover. The net radiation index is determined as fol. lows:
- 1) If the total cloud cover is 10/10 and the ceiling is less than 7000 feet, use net radiation index equal to O (whether day or night) .
- 2) For nighttime (defined as the period from one hour before sunset to one hour after sunrise):
a) If total cloud cover < 4/10, use net radiation index equal to -2. g' b) If total cloud cover > 4/10, use net radiation index equal to -1.
- 3) For daytime:
a) Determine the insolation class number as a function of solar altitude from Table 2. b) If cloud cover < 5/10, use the net radiation index corresponding to the insolation class number. c) If cloud cover > 5/10, modify the insolation class number by the following steps:
- 1) If ceiling < 7000 feet , subtract 2
- 11) If ceiling > 7000 feet, but <16,000 feet, subtract 1
111) If total cloud cover is 10/10 and ceiling is > 7000 - feet, subtract 1 (compare to 1 above) A V
EPP-005
.i ' ATTACHMENT XIII l PAGE 2 0F 3
, REVISION 2 The Pasquill-Turner Method for'Det'ermining Atmospheric Stability iv) If total cloud cover is not 10/10 and ceiling is >-
16,000, assume modified class number equal to insolation class number - v) If modified insolation class number is less than 1, let it equal 1 vi) Use the net radiation index corresponding to the i modified insolation + class numbeg Thus, it can be seen from Table 1 ' nat inst:a.bility ' occurs with , high positive net radiation. and lw wind tpeeds, stability with ~ s negative net radiation and light ninds, and neutral conditions ' with cloudy skies or high wind speeds. ; s 3 , Calculation of Solar Altitude , p a = arcsin (sin 6 sin .4 + cos ((H-12) 180 ) cos cos^] .. , 12 .,, where 4= station latitude 1 34 3*
^
H = hour .of day (24 hour clodk) 6 = arctan [ - tan (23 5 ) cos (360* (N+10)] 365 where' N = numb'er of days from the beginning of the year I \
- !i l i l
s A. t' e ) O
. . - - - ,, , . . ~ , . , . , . - . . . _ _ . .
,._....,..w.,,.. .. .,,._,,
EPP-005
-ATTACHMENT XIII l PAGE 3 OF 3
( i REVISION 3 TABLE 1 STABILITY CLASS AS A FUNCTION OF
, NET RADIATION AND WIND SPEED Wind Speed
- Net Radiation Index -
(MPH) (knots) 4 3 2. 1 0 -1 -2 0, 1.15 0, 1 A A B C D F G 2, 3 45 2, 3 A B B C D F G 4.6, 5 75 4, 5 A B C D D E F 69 6 B B C D D E F
, 8.05 7 B B C D D D E 92, 10 35 8, 9 B C C D D D E 11 5 10 C C D D D D E 12.65 11 C C D D D D D v
>13 8 > 12 C D D D D D D 9 Table 1 was developed for wind speed in knots. To convert from knots to meters per second, multiply roughly by .5, accurately by .51444.
l TABLE 2 l 1 l INSOLATION AS A FUNCTION OF SOLAR ALTITUDE q ** Insolation l 1 Solar Altitude (a) Insolation Class Number 60' <a Strong 4 j' ! 35 ( a 1 60 Moderate 3 l 15 < a i 35 Slight 2 a i 15 Weak 1
** See Page 2 of this attachment.
l N) l
9
- M 9
D 4 / s .g 5~e s a i8. . E:t wem TB - 3 r M 2 ' 05s2 ] I
/
1400 1300 1200 1100 1000 900 800 700 600 500 400 300 200 10 0 PRESSURE (PSI A) _- w - -- e
I
,r .
_._ AP-102
] ~
ATTAC1DfENT I PAGE 1 0F 3 REVISION 2 .. PROCECURE DEVELCPMENT FCRM A
% DATE: 6/1/82 PRCC. J EPP-006 REY. #
- fw
/C CHANGE J f[ [
TITLE: Emergency Reactor Coolant Sampling PERMANENT 7 y - RESTRICTED FROM TO SAFETY RELATED7 - NEW PROCT REVISICN7 X CHANGE 7 Yes No X
***"' % ~~l 4k y<oea).ars ia sh id;4y . Ra~ gat < ,,,J eove<tl L c.H P-go 3 Mwod.e +keA&4 AhF- A.eb C'o s-tto~plc G
sqs A Al.u No~l , 5" Ill. WILL THIS REVISICN/ CHANGE /NEW PRCCECURET Yes No 1 Represent a change to the plant as described in the FSM1 X A
- 2. Represent a change to procedures as described in the FSM7
- 3. Represent a test or experiment not described In tne FSAR7 X 4 Result in a violation of or change to Tocanical Specifications? V
- 5. Result in significant increased personnel radiation exposuret v
- 6. Result in- reduction of the margin of safety to the public, environment, ce plant personnel? X 7 Violate tne provisions established in tne FSAR concerning operation and k *)/k 7 (Cite)
~ (Cr iolTiator) (Evaluated ev ClIscrol ine Sucervisor)
NOTE: it tne answer to any of the aoove questions is "YES", furtner processing is withneto etit licensing considerations are discositioned. Forward to tne technical Services coordinater fcr action.
. A. AEGul AED EEVIEW AND coa *ENT 3. CCwENTS vl A TELECCN CC*ENTS '
AA CTHER # Oa+e / time Asesen Cen seted ?ES No ( , Cas k1 M / ) i
/
( e :mt () / _ ( TS X) / _ ( - SPS (x 1 / .
! * ;A ( ) CA / _
( ) QC () / _ ( . ASRC () . Telecon Criginator SIVIEWERS COMMENT! RESCLVED: 7! (Distioline suoervisor t V2
'(Daten
- v. VI. PSRC REVIEW
~
RESPCNSISLE ASSISTANT i4ANAGER: A. Reviewec Dy: Ifa a u
~
0v i i %L CATE / PSRC 04 AIRMAN i 04te J [f 7N 81 Cc.ntnents: v es No PSRC REVIEW REQUIRED YES No S. PSRC Coments Resolved: l
/ b ASSISTANT MANAGE 4 Cate
/
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1AR OPSKTONS s O copyno..g.s.gc.. ....
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p SOUTH CAROLINA ELECTRIC AND GAS COMPANY VIRGIL C. SUMMER NUCLEAR STATION NUCLEAR OPERATIONS ;( , _ _ , .
- /N.!(,. . . . . . . . ,,
EMERGENCY PLAN PROCEDURE EPP-007 ENVIRONMENTAL MONITORING , REVISION 1 JUNE 15,1982 Non-Safe $y Related lO Reviewed by:
&_ TYtA ORlMINATO F(of this revision) ' D6te a km QUALI'FIED REVIEWER i
Date j Approved: A?M/Yl4 '7 k 2.2 (Dath PLANT /jANAGER /] Date Issued: JUL 2 719821 l Form AP-101-2, (1/80)
, . _ . _ _ _ . . . . . . . _ _ _ _ _ _ _ . . . - _ _ . _ _ . _ _ _ . . _ _ _ = . _ _ . . . . _ _ - - . . _. . __ ..
EPP-007 PAGE i
' REVISION 1 LIST OF EFFECTIVE PAGES ,
PAGE - REVISION : 1 1 11 1 1 1 2 1 i 1 3 4 1 1 5 ATTACHMENTS . Attachment I 1 Attachment II 1 Attachment III 1 Attachment IV 1 Attachment V 1 i t o O
EPP-007 PAGE 11 REVISION 1 6/15/82 O TABLE OF CONTENTS Pagg List of Effective Pages i 1 1.0 PURPOSE 1
2.0 REFERENCES
' l 3.0 CONDITIONS AND PREREQUISITES ~ 2 4.0 PROCEDURE ATTACHMENTS ATTACHMENT I - Radiological Monitoring Program Local Indicator Sample Sites ATTACHMENT II - Radiological Monitoring Program Remote Sample Site ATTACHMENT III - Miscellaneous Emergency Environmental Samples ATTACHMENT IV - Emergency Environmental TLD Report Form ATTACHMENT V - Emergency Air Monitoring Sample Collection Sheet i e O
EPP-007 REVISION 1 6/15/82 t
\# 1.0 PURPOSE 1.1 To provide guidance for the surveying of Environmental Monitoring Stations during an emergency or for post-accident montporing.
2.0 REFERENCES
2.1 V.C. Summer Radiation Emergency Plan.
~
2.2 EPP-004 "Out-of-Plant Radiological Surveyin3." 2.3 NUREG 0654 " Criteria for Preparation and hvaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants." 2.4 HPP-303 " Airborne Activity Sampling Techniques and Procedurea". 2.5 ESP-301 " Air Sampling for Radioactive Particulates and Radioiodine.** 2.6 ESP-801 " Emergency Plan Procedure - Introduction". 2.7 ESP-802 " Emergency Plan Procedure - Sampling". ()2.8 ESP-803 " Emergency Plan Procedure - Sample Preparation". 29 ESP-804 " Emergency Plan Procedure - Sample Counting". 30 CONDITIONS AND PREREQUISITES 31 The Shift Supervisor has determined that conditions for a site or General Emergency exists. 32 The Technical Support Center, (TSC),/ Emergency Operations Facility (EOF) are activated and have collaborated to determine the 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 E0P. NOTE: Communications are to be kept open at all times to ensure surveyors are kept advised of changing conditions. U PAGE 1 0F 5
EPP-007 REVISION 1 6/15/82 I k-)'3.5 When handling Environmental Thermoluminescent Dosimeters (TLS's) take precautions to minimize exposure during tranportation to and/or from Environmental stations. Either use lead shielding for TLD's during transport or include a control TLD for determining approximate dose during transport. 36 Off-Site Radiation Monitoring Tea:ns will service Environmental Stations by direction from TSC/ EOF (as indicated in Attachments I and II). 37 Ensure that access gates use'd enroute are left as found (e.g. open, closed, locked, etc.) 4.0 PROCEDURE 4.1 Obtain an Emergency Off-Site Monitoring Kit and any additional 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 s vehicles. Also obtain the necessary keys to access gates for the i monitored areas. 4.3 Check instrumentation for response to radiation with the source provided prior to leaving to ensure continuous radiation monitoring enroute. 4.4 Environmental TLD Replacement. 4.4.1 Pick up annealed TLD's f rom Environmental Surveillance Laboratory or EOF. 4.4.2 Ensure proper placement of Environmental TLD sticks into designated sampling stations. 4.4.3 When placing TLD's in field stand, align the scribe marks Tighten allen
}
on the stick with the edges of the hasp. screw only enough to ensure the stick does not rotate in the hasp. 4.4.4 Record date, time, TLD number and any remarks on l Attachment III. PAGE 2 0F 5
EPP-007 : REVISION 1 6/15/82 q b 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. 4.5 Environmental Particulates and Radioiodine Samples 4.5.1 Permanen't Environmental Air Samplers 4.5 1.1 Remove the previous (sample's) coin envelope from I the unit. 4 5 1.2 Note on the envelope the ending date and time, elapsed running time (E.T.), integral flow from the gas meter and initials of collector. l 4.5.1.3 Switch off the air sampler. 4.5.1.4 Carefully remove the filter holder face. Hold the i coin envelop', open below the filter and use forceps or s chirp object to free the sample (/) s_ filter making sure both filter and loose particulate atter on it are transferred to the envelope. 4.5 1.5 Remoce 'a ,. avious (sample's) charcoal cartridge and regle "ith fresh, labeled cartridge. Mark directic ' air flow on cartridge. NOTE: R:pl de charcoal cartridges with AgZe carct'l.dges unless otherwise directed from T^~N F. l 4.5 1.6 Annot?',e r achment IV with information requested in 4.5 2. 4.5.1.7 Turn unit on, ;1 ace a new Gelman glass fiber type I E , 47 mm fil c a r' in ':he holder and replace the holder face. 4.5.1.8 Note on a col enveloi.e, ?he starting date, time, E.T., integral ficv anc i itials of collector. i O PAGE 3 0F 5 l
~
EPP-007 REVISION 1 6/15/82 '
,-~
N- 4.5.1 9 Time one revolution on the "one cubic foot" dial and record ine time in the flow rate space on the envelope. 4.5.1.10 Note any sampler malfunction on the affected sample envelope. Notify the Offsite Radiological Coordinator of sampler failure and request further instructions. 4.5 1.11 Return the labeled envelope and cartridge to the l 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 (e.g. background levels should be less than 100 cpm). See Attachment II of EPP-004 for details. 4.5 1.12 If placing a new sampler see ESP-301 for details. (Environmental Surveillance Procedure - 301 " Air Sampling for Radioactive Particulates and
-~
Radioiodine"). 4.5.2 Portable Air Samples i 4.5.2.1 Set up sampler and take samples in accordance with HPP-303 4.5 2.2 Fill out appropriate sections of Attachment IV. 4.5 2 3 Field calculations of approximate air sample iodine and particulate concentrations can be made using the RM-14 and HP-210 probe provided in the emergency kits and following instructions in Attachment II of EPP-004. (Iodine dose rates can also be obtained using Attachment VI and VIII of EPP-005, if desired). 4.6 Water Samples 4.6.1 TSC/ EOF will determine water sampling points and the safest routa of travel. NOTE: The following locations may be used for indicator sampling locations:
, i l PAGE 4 0F 5
_._. ~ - . _ - . _ . _ _ _ . . . _ _ _ _ . _ . . . . , . . . . _ . , .-_
e - EPP-007
. REVISION 1 6/15/82 a) Downstream of Fairfield Pump Storage.
b) Parr Hydro Plant c) Broad River, at S.C. Route 213 4.6.2 Label containers with markers before getting them wet. i 4.6.3 Drinking and well water grab samples are taken by allowing I' water spigots to flush thoroughly, (at least one minute), prior to rinsing and filling container. 4.6.4 Thoroughly rinse the sampling container with water from l the source to be sampled. 4.6.5 Surface water grab samples are taken by rapidly submerging the rinsed, loosely capped container approximately one foot beneath the surface, ( removing the cap, allowing container to fill, recapping and retrieving the filled container avoiding surface water contamination). 4.6.6 Label all samples with date, time and loc ^ation and fill out Attachment V. i () 4.6.7 Return all samples to designated counting facility for analysis. 4.7 Grass and other Miscellaneous Samples. 4.7 1 Take samples per instruction.s of the Offsite Radiological Monitoring Coordinator and record data on Attachment V. l 4.7.2 Grass (and broad, leafy vegetable) samples must be sealed in plastic bags as well as possible to avoid loss of
" mobile" activities (e.g. iodines).
O PAGE 5 0F 5
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EPP-007 ATTACHMENT III PAGE 1 0F 1 REVISION 1 v VIRGIL C. SUMMER STATION EMERGENCY ENVIRONMENTAL TLD REPORT FORM Collector: Collected Installed Remarks Location TLD N o . Date Time TLD no. Date Time O
EPP-007 ATTACHMENT IV PAGE 1 0F 1 REVISION 1 VIRGIL C. SUMMER STATION EMERGENCY AIR MONITORING SAMPLE COLLECTION SHEET i Collector: Integrated Gas Reading Remarka Removed Installed Removed (Location) Date Time Particulate Particulate Iodine Iodine 1 e O
O O s k r V a 1 m T 1 e NF R E0N 7M O 0H1I 0C S AEI PTGV PTAE EAPR S E L d P n M u A o S P L A N T y r O N t e I E i t T M t i A N n L O a O T S R E R I V N Q u s n M E o M ' l U Y l S C a N G
. E C G R
L E r I M e G E h R t I S e O V U p 4 O y E T N r A be L at L ra E GW C S I M e m i n T e k a T e t a D n O : r o t i t o a c c e o l L l o C
o "" " ^ " " " ^ " " ^" "^" VIRGIL C. SUMMER NUCLEAR STATION NUCLEAR OPERATIONS VUC_ EAR _ OPERATIONS
- C O P Y N O......... / E 2 ..G .. .... . ,
EMERGENCY PLAN PROCEDURE EPP-008 ON-SITE ASSEMBLY REVISION 1 JUNE 11, 1982 Non-Safety Related Reviewed by:
, 40 91.
ORI41N ATOR '(-of this revision) '/ Dite e - 7/ A QUALIFIED f{EVIEWER Date I l Approved: 9cd(L,se-. ,/s/ez PLA@ MAN AGER Q (Dats Date Issued: N Form AP-101-2, (1/80) l l
EPP-008 PAGE 1
. REVISION 1 6/11/82 ,
LIST OF EFFECTIVE PAGES PAGE REVISION 1 1 1 11 1 1 2 1 1 3 14 1
' ATTACHMENTS 1
Attachment I ! ~ 1 ! Attachment II I \@ f b l l ' l I l i I
^ ~ -
EPP-008 PAGE 11 REVISION 1 6/11/82 TABLE OF CONTENTS PAGE List Of Effective Pages i 1.0 PURPOSE 1 I
2.0 REFERENCES
1 30 CONDITIONS AND PREREQUISITES 1 4.0 PROCEDURES 2 ATTACHMENTS Attachment I - Personnel Accountability Checklist Attachment II - Assembly Area / Duty Station List O i G O
'EPP-008 REVISION 1 6/11/ 82 O
(s,/ 1.0 PURPOSE To provide guidelines for conducting personnel on-site assembly verifications during 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 REFERENCES
2.1 " Virgil C. Summer Nuclear Station Radiation Emergency Plan". 2.2 EPP-Oll, " Personnel Search and Rescue". 2.3 SPP-114, " Security Force Responsibilities During Emergencies. 2.4 NUREG-0654, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants. 2.5 EPP-012, "Onsite Personnel Accountability and Evacuation. 3.0 CONDITIONS AND PREREQUISITES ( 3.1 Personnel on site assembly verification will be performed when ordered by the Emergency Director / Interim Emergency Director. During normal operating hours personnel are directed to proceed l 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 l prescribed in paragraph 4.2. l l 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. 3.3 If the personnel on-site assembly verification has not been completed within a reasonable time due to missing personnel, procedure EPP-Oll, " Personnel Search and Rescue," may be implemented at the discretion of the ED/IED. l 3.4 Personnel on-site assembly verification will interface with SPP-114 and EPP-012. 3.5 Each group's designated Foreman / Supervisor will maintain a 3 current listing of their personnel and badge numbers per Attachment I and report any changes to the Emergency l
,s Coordinator. .
O PAGE 1 0F 4
EPP-008 REVISION 1 6/11/ 82 fa .
> 4.0 PROCEDURES 4.1 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 contained in Attachment II). 4.1.3 The following personnel will submit an on-site assembly verification report to the Assistant Manager, Support Services located in the TSC: 4.1.3.1 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 (0S0). 4.1.3.4 The Director of Administration for personnel reported assembled in other designated assembly l areas. (Contained in Attachment II). I 'O PAGE 2 0F 4 l l
r EPP-008 REVISION 1 6/11/ 82
~
N 1 4.1.4 Upon direction by announcement over the plant paging.' system and (Fairfield Pump Storage by phone,-J~~ , 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 or through the Auxiliary Acce'ss Portal to the AAP Assembly Area, depending on' their point of access. 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 completed personnel ' On-Site Assembly Verification checklist (See Attachment I). If the station is in " Site Emergency" or
" General Emergency" the On Site Assembly Verification will be performed per EPP-012; if in " Ale rt" 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 f rom the Assistant Manager, Support Services. 4.1.7 The Security Shif t Leader will compile a list of any personnel who are unaccounted for by comparing the checklist received to the Security badge accounting results. Any discrepancies will be noted and reported to the ED/SS. 4.2 Other than normal operating hours: 4.2.1 The Shift Supervisor has the overall responsibility for persannel On-Site Assembly Verification until relieved by the ED or his DA. l l 5 9 , FAGE 3 0F 4 t
p - - EPP-008 REVISION 1 6/11/ 82 4.2.2 The Security Shift Lea' der 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 Technical Support Center is activated and he is properly relieved by the ED or his DA. 4.2.3 All shif t personnel shall report to the Control Room to allow the Shift Supervisor to verify accountability. 4.2.4 All personnel not assigned to shif t 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 Shif t Leader or DA. 4.3 Persons unaccounted for will be searched for in accordance with EPP-Oll, " Personnel Search and Rescue". O E PAGE 4 0F 4
f i e e EPP-008
- ATTACIDfENT I-e
'.. PAGE 1 0F 1
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EPP-008 - ATTACHMENT II - PAGE 2 OF 2
,y.
. REVIS0N 1
ASSEMBLY AREA / DUTY STATION LIST LOCATION COMPOSITION OF GROUP PHONE NUMBER REMARKS Hydro Operators, Land --
Fairfield Department Utility , Pump Storage Personnel .
~
l Tech. Support Area Tech. i Support Center Engineers, STA's i Haalth Physic > Laboratory Rad. Teams, H/P Personnel Emer. Ops. Area - Tech Emer. Director Support Personnel Accountability / Center Assistant Manager, i Sdpport Services - 1 i Rad. Assess. Supv. ; I
,. - Assistant Manager, !
~
l L- Technical Support ,' _
- s. ,
Security Supv. Assistant Manager, Maintenance Services Assistant Manager, ! Operations ! l i Machine Shop / Contract Maintenance
; Carpenter 3 Shop 448' Elev Misc Contract Personnel r Control Bldg _;
1 Control Room / Fire Watch OSC I [: S l@ - l l
EPP-008
. ATTACHMENT II '
- PAGE 1 OP32 ~
REVIS0N 1
} "# ASSEMBLY AREA /D TY STATION LIST LOCATION COMPOSITION OF GROUP PHONE NUMBER REMARKS Control Room Shift Complement.
QC Office < Service Bldg. QC Inspectors _,' l Operations Various support units. , Support plus Supervisory i , Center (OSC) Personnel . i I&C Personnel - SCE&G/ i I&C Shop Butler Arde f' ., Water Treat- j l ', Lab - 463'elev. Chemistry i i Start-Up Start-Up Supervisors i Office & Clerical Engineering Engineers, Techs, , q Area-Serv.Bld Computer Maintenanc'e i 4 Welding /ISI Maintenance Engineer , l Office Supervisor. Support _ l ,__
.me l 1
[" Warehouse "C" Material Support i Planning / Maintenance Planner / 1 Champs / SCI Support _ Scheduling Rm > Electrical Elec.-Maint. - SCE&G/ i T' w\ Shop Harrison !
's j ' a'
{- Machine Shop Utility Personnel _ L g QA Office QA Inspectors ' ftvl
- Office Sect. ,
s
'\,-
Service Bldg. Clerical & Miscellaneous c Guardhouse Security Personnel y i Training Area ' Service Bldg. Training Personnel _. Security Administrative , Offices Security Perscnnel ! 3d t Machine Shop Mech. Maint. - SCE&G a Q.A./ Security Visitors and Non- j . g Building permanently assigned - _ f personnel "= Turbine Bldg. K-MAC and other 'M~ -q . p Truck Access contract eersonnel *
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. id U N; N,:~ '
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t soura ciao' ai 8tecra o ^uo ois co ei"' C) VIRGIL C. SUMMER NU. CLEAR STATION NUCLEAR OPERATIONS L\'JCiEAR _OPERAT!0NS C O P Y N O ........ M.... P...c ,...... ,,. EMERGENCY PLAN PROC,EDURE EPP-009
~
ON-SITE MEDICAL
' REVISION 2 JUNE 16, 1982 O r NON-SAFETY RELATED
.3 4 M, i
Reviewed by: , t
~
e n f ate 2 ORIQINATOR'Tof this revision) I [ M QUALIF1ED HEVIEWER 1_ _ 7 Date l l Approved: I f/l /-f b $ PLANT / MAN AGER ( (Datd l I 4
* -
- Date Issued: 00b 2 71982 F$rm AP-101-2 (1/80)
I-t
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.. __n_ c___.1 _ _ _ _
a
, t ;
y,: -EPP-009 i
+ PAGE i '
l REVISION 2 *" : I, l 6/16/82 , l . s l ,' , ! LIST OF 'FFECTIVE E PAGES ' i ~' REVISION , PAGE l , i 2 ' 'l . 3 2 . 11 1 .f - 1 g 2 l .. ' ' I V : { g r. ,' ,/ g ,
< 2 3l.
g 2 ,. i 4 2 1 5 i ; ATTACHMENTS i l Attachment I 2 .; I Attachment II 2 i I . l
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EPP-009 PAGE 11 REVISION 2 . 2 6/16/82 - O TAB $E OF CONTENTS PAGE List of Effective Pages i j 1 1.0 PUR, POSE
' 1
2.0 REFERENCES
1 1 30' CONDITIONS AND PREREQUISITES _ 2 4.0 PROCEDURES
! ATTACHMENTS ATTACHMENT I - Personnel Injury and Contamination Report.
1 ATTACHMENT II - V.C. Smamer Station Helicopter Landing Sites. i O h O
EPP-009 REVISION 2 1.0 PURPOSE 1.1 To provide guidelines for handling individuals who have been injured, with'or without associated contamination, and may be in need of off-site medical treatment.
2.0 REFERENCES
2.1 " Virgil C. Summer Nuclear Station Radiation Emergency Plan.", 2.2 EPP-010, " Personnel / Vehicle Decontamination." 23 EPP-002, " Communications and Notifications." 2.4 NUREG-0654, Oriteria for Preparation & Evaluation of Radiological Emergency Response Plans & Preparedness in Support of Nuclear Power Plants." 25 EPP-018, " Emergency Facilities Activation and Evacuation" 2.6 EPP-020, " Emergency Personnel Exposure Control." () 30 CONDITIONS AND PREREQUISITES The first level of treatment shall be given on-site. If 31 the injury occurs in the Radiation Controlled Area (area beyond the 412' elevation of the Control Building) and the patient becomes contaminated, injury should be treated at the 412' elevation of the Control Building (H.P. Lab area). 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. The First Aid Team Lee. der should be the "B" Nuclear 33 Reactor Operator or his alternate as available. Other members of the First Aid Team should be available Auxiliary Operators, Maintenance personnel, Chemistry personnel, etc. as per EPP-016, Attachment II. i PAGE 1 of 5
EPP-009
. REVISION 2 6/16/8,2 ~
4.0 PROCEDURES 4.1 The Shif t 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 actions where required; and then perform the following: 4.1.1 Survey the patient and determine if any contamination is present. Determine if off-site assistance is n'eeded. A. A member of the team should contact the control room /TSC and apprise them of the situation, i.e., name and location of victim, physical and radiological condition of. victim, team recommendations for off-site assistance, and team recommendations, for next actions. If the patient is not contaminated, continue first aid treatment. The patient should be moved to the first aid room for treatment when such a move would not endanger the patient. B. If the patient is or is expected to be externally contaminated, initially perform only (73) the first aid treatment necessary. procedure EPP-010 " Personnel / Vehicle Follow 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 person 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 possible, considering the extent of the l injuries.
- 1. Where difficulty in decontar.ination is encountered, wrap the affected area in a blanket, plastic, or sterile dressing (in the case of a wound) to isolate the contamination.
NOTE: Avoid excessive wrapping due to the possibility of f-%g overheating the victim. U PAGE 2 of 5
. EPP-009 REVISION 2
. 6/16/82 B. Prepare the person for transport as follows:
- 1. Complete the Personnel Injury and Contamination Report with all available I information to accompany patient (see l Attachment I).
- 2. Notify the Technical Support Center / Control Room that the individual is ready for transport to the hospital.
3 The TSC/ Control Room should inform First Aid Team where victim is to be picked up by the ambulance. 4.3 2 At the same time that the person is being prepared for transport, the Communicator will: 4.3 2.1 Notify the hospital, 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.
t 4.4 The Shift Supervisor / Emergency Director will: 1 4.4.1 Ensure that a Health Physics representative or qualified radiation worker accompanies the injured person to the hospital and performs the necessary actions. 8 O i PAGE 3 of 5 l
EPP-009
- REVISION 2 6/16/.82 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 Ambulance personnel before entry. 4.4.3 The Control Room /TSC shall notify hospital of departure of subulance f rom plant site and maintain communication with the hospital via the appropriate communications equipment. 4.5 The person accompanying the injured will: 451 Ensure that the Ambulance Radiation Emergency Kit (located in the First Aid Room on the 412' elevation of the Control Building) is taken with a contaminated person who is injured. Items in the i Kit are to be used on an as needed basis. () NOTE: The Ambulance Radiation Emergency Kit contains protective clothing to be used by Ambulance personnel for contamination control, poly bags to collect contaminated waste, absorbent material to cover clean areas, supplies for posting and controlling areas, and a survey instrument. 4.5 2 Ensure that the transporting vehicle uses the appropriate hospital receiving area. 4.5 3 Notify Control ..oom/TSC of arrival at hospital. 4.5.4 Assist in the radiological aspects of the treatment as necessary. A. Assist the hospital staff in the decontamination activities for the hospital receiving area. Ensure all waste products are
' properly contained for future disposal.
4.5 5 If protective plastic has been used in the ambulance, carefully remove and bag it for return to Virgil C. Summer Nuclear Station. O PAGE 4 of 5
EPP-009 REVISION 2
- 6/16/82 4.5.6 If contaminated, decontaminate himself prior to leaving the hospital.
457 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. 4.5.8 Keep the Emergency Director / Shift Supervisor informed at all times as pertinent information concerning the patient becomes available. 4.5 9 Retain all survey documentation and samples and forward to the Radiological Assessment Supervisor as soon as practical. N 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. l PAGE 5 of 5
l EPP-009 ATTACHMENT I PAGE 1 0F 2 O PERSONNEL INJURY AND CONTAMINATION REPORT REVISION 2 V.C. SUMMER NUCLEAR STATION 345-5209/345-2620 Name of injured: , Injuries as known: First Aid Treatment: Medical Treatment (Initial): Vital Statistics: External Contamination: [] Yes [] No (if yes, denote levels on back of form). Internal Contamination: [] Yes No Body Burden Analysis Results: Exposure Assigned: Overexposure: Yes [-] No , TLD results: Person accompanying victim: PRINT NAME SIGNATURE 4 e 4 lO 1 1 l i l--- -- - . . . . . ,_ _ _ ,___,_ . _ _ _ __ . _ _ _ , _ _ , . _ _ . _ _ __ __ ,_ _ _ _ _
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EMERGENCY PLAN PROCEDURE EPP-010 1ERSONNEL/ VEHICLE DECONTAMINATION REVISION 2 JUNE 11, 1982 NON-SAFETY RELATED i Reviewed by:
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QU AI/lFIED REVIEWER f% _- 3 Date i ! Approved: l 9#La PLANTIJ AN AGER / 2/w/ez (Date Date Issued: N i . Form AP-101-2, (1/80)
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" REVISION 2 TABLE OF CONTENTS PAGE f L1st Of Effective Pages i 1.0 PURPOSE 1 2.0 REFERENCE 1 3.0 CONDITIONS AND PREREQUISITES 1 4.0 PROCEDURES 2 ATTACHMENTS Attachment I f Attachment II O
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EPP-010 REVISION 2 6/11/ 82 (3 \~ ' 1.0 PURPOSE To provide instructions for the deconttmination 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 Rs3ponsa Plans and Preparedness in Support of Nuclear Power Plants. 30 CONDITIONS AND PREREQUISITES 3.1 All injuries occurring xithin the Radiation Control Area will be fs considered contaminated until monitored and cleared by Health Physics. (G) 32 Potentially contaminated personnel / vehicles will be monitored and decontaminated on-site unless evacuation to an off-site area is required. When evacuated to off-site holding areas, monitoring and decontamination of personnel / vehicles will be performed at locations designated by Health Physics. 3.2.1 For offsite/ Security Annex Monitoring and decontamination. 3 2.1.1 Obtain emergency kits from Service Building Annex and radios f aom Health Physics Lab or TSC. Check seals and inspection on Emergency Kits. NOTE: If seals are broken or inspection date is not current on emergency kits, perform a quick check to ensure emergency kits are adequate for field use. 3.2.1.2 Check instruments in kit with the source supplied in the kit for response to radiation. PAGE 1 0F 4
EPP-010 REVISION 2 6/11/82 V All decontamination shall be supervised by Health Physics 33 personnel. 3.4 All personnel and vehicles found to be contaminated will be reported to the Radiological Assessment Supervisor by radio or closest available telephone. 35 All surveys will be documented and trasmitted to the TSC as soon as practical. s 4.0 PROCEDURE 4.1 Personnel Decontam1' nation 4.1.1 The following Radiation / contamination limits shall be utilized:
- a. All personnel shall be limited to non-detectable loose surface contamination of less than 100 cpm above background at 1/2 inch using a pancake GM tube (HP-210 probe), with an efficiency greater than or equal to 10% and background less than or equal to 400 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 personnel should be dressed in paper coveralls with a yellow and magenta arm band and 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", if possible. 4.1.5 Personnel decontamination to be performed outside the Protected Area may be accomplished by direct HP coverage in the Q.A./ Security Building (whenever possible). All waste generated, both solid and liquid, shall be collected for subsequent disposal. Precautions to minimize waste should be used whenever possible. (~h. V PAGE 2 0F 4
EPP-010 REVISION 2
. 6/11/ 82 O 4.1.6 If personnel decontamination is performed at the of fsite holding area, decontamination supplies located in the Q.A./ Security Building should be utilized.
4.1.7 Complete Attachment I for all contaminated personnel. 4.1.8 Bioassays will be administered, based upon levels of skin contamination, at the discretion of the Radiological Assessment Supervisor. 4.2 Vehicle Decontamination. 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 during offsite evacuation: 4.2.2.1 Less than 1000 DPM/100 cm2 Beta / Gamma, smearable contamination. 4.2.2.2 Less than 100 cpm above background at 1/2" using a pancake GM 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. NOTE: Don appropriate protective clothing prior to decontamination attempts. 4.2.3.1 Rope and post an area accordingly. 4.2.3.2 Lay out plastic in the roped area and place the vehicle upon the plastic. 4.2 3.3 Using the decon supplies in the off-site monitoring kits, decon the vehicle using decon foam and towels or disposable rags. 4.2.3.4 Ensure that all contaminated towels and rags are placed in the radioactive trash bags provided in the Emergency Kit. p V i PAGE 3 0F 4
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EPP-010 REVISION 2 6/11/ 82 1 NOTE: If, after several decon attempts, the : I contamination levels still do not meet r the criteria listed in section 4.2.2, contact the Director of Health Physics or
! Health Physics Supervisor for further instructions in decontamination <
i techniques. 4.2.3.5 Complete Attachment II for all contaminated i vehicles. i 9 l i i ! i O l-1 i r i i i I i
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. PERSONNEL CONTAMINATION REPORT trnnos 2 ,
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EPP-010 ATTACHMENT I PAGE 2 of 2 REVISION 2 PERSONNEL CONTAMINATION REPORT , NAME OF PERSONS (S) INVOLVED: DATE: TIME: RWP/SRWP NO.: i LOCATIOff 0F INCIDENT: SUSPECTED OR KNOWN CAUSE: WERE CORRECT HEALTH PHYSICS PRACTICES BEING FOLLOWED? YES NO PORTION OF BODY CONTAMINATED: i INITIAL READINGS: Fixed: DPM READINGS AFTER DECONTAMINATION: Fixed DPM PERSONNEL INJURY INVOLVED: YES NO ACTION TAKEN FOR DECONTAMINATION: MEDICAL ACTION TAKEN: 9 BODY BURDEN ANALYSIS PERFORMED: YES NO RESULTS OF BODY BURDEN ANALYSIS / EXPOSURE ASSIGNED: CORRECTIVE ACTION TAKEN 'IO PREVENT REOCCURRENCE:
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l . 1 . E27-010 f
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_j, - , VEHICLE SURVEY REPORT * ,
- VEMICLE }t0NITORINC INSTRUCTIONS VEHICLE SURVEY TOL't .
NOTE: k!se this' form for contaminated vehicles only. - Owner's Name License No.
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CDP 1 HD EMERGENCY PLAN PROCEDURE EPP-011 PERSONNEL SEARCH AND RESCUE i REVISION 2 i JUNE 11, 1982 NON-SAFETY RELATED O Reviewed by: m stomub/ 1 L ORIGINATOR Tof this revision) " Dste
+ 3 QUAblFIED REVIEWER Date Appeoved:
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l. 1 EPP-Oli l PAGE 1 j l . REVISION 2 j- 6/11/82 LIST OF EFFECTIVE PAGES i c i PAGE REVISION i i= 1 2 f 11 .2 ! 1 2 2 2-3 2 4 2 ! 5 2 : i I ATTACHMENTS } f Attachment I 2 i Attachment II 2 l i i + i 5 9 r
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EPP-011 PAGE 11 REVISION 2 O TABLE OF CONTENTS 6/11/82 PAG.] List of Effective Pages 1 1.0 PURPOSE 1 2.0 REFERENCE 1 30 CONDITIONS AND PREREQUISITES 1 4.0 PROCEDURES 1 i ATTACHMENTS
- Attachment I - Plant Area for Search and Rescue Attachment II - Search Preplans for Auxiliary Building, Reactor Building and Fuel Handling Building.
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EPP-011 REVISION 2 6/11/82
-s s ,) 1.0 PURPOSE To provide guidelines for performing a search and rescue operation to find missing individuals.
2.0 REFERENCES
2.1 " Virgil C. Summer Nuclear 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, "on-site Medical". 2.4 EPP-020, " Emergency Personnel Exposure Control". 25 EPP-008, "Onsite Assembly" 2.6 EPP-012, "Onsite Personnel Accountability and Evacuation" 27 EPP-016 " Emergency Facilities Activation and Evacuation"
/^x (ml 3.0 CONDITIONS AND PREREQUISITES 31 Personnel accountability has been performed and it has been determined that a person on-site may be uissing. This procedure assumes that a missing person (s) is injured until proven different.
32 At least one member of the Search and Rescue Team will be qualified in Health Physics monitoring techniques and one member will be at least Multi-media First Aid qualified. 33 The leader of the Search and Rescue Team should be the "B" Nuclear Reactor Operator or his designee as available. Other members of the Search and Rescue Team should be: available Auxiliary Operators, Maintenance Personnel, Chemistry Personnel, etc., as per EPP-016 Attachment II. 34 If necessary, the members of the Search and Rescue Team may be authorized to receive 100 rem to save the life of the missing individual (s) as per Reference 2.4. CN V PAGE 10F 5
~
EPP-Oll REVISION 2 s 6/11/82
\-/' 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 system: Attention, the following personnel report your location to the Control Room. [ Names , ,]. (Repeat this message once per minute for five minutes). NOTE: If Security has already made this announcement in accordance with EPP-012, the ED/SS may elect to skip steps 4.1.1 and 4.1.2. 4.1.? If after about five (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 a Search and Rescue Team that should consist of personnel from the following groups: (as O available) A. Operations B. Maintenance C. Health Physics D. Security Force 4.1.4 The team will be outfitted with necessary protective clothing, monitoring instruments, and a portable radio. 4.1.5 Using coordinates gained from implementation of EPP-008, the team will be provided with the following 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. O O PAGE 2 0F 5 ,
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- 1) Check with Security for following- i information: I a) Any keys checked out to individua'1.
1, b) Door the victim last N6nt through ucing - card reader.
- 2) Check with Health Physics for any keys
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checked out to victim. - y
- 3) Check Control Room key loga for any keys ,
checked out to victim. . , ' -r , , D. The job last being performed by the person. , ! ?)
\i 4.1.6 Based on the information provided in step 4.1.5 above, the ED/ Shift Supervisor assisted by the -
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f; b designated team leader shall ' plan the routes to be?
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a followed with consideration of the ALARA program. , Attachment II gives routes which should be used unless radiological / safety hazards cause alternate routes to be used. The team leader, as a'l designee of the shift supervisor, will txt responsible"for ,
'"x ensuring that: e y
A. A thorough search of each area is conducted using Attachments I and II. B. The search and rescue team stays together and conducts the search as a team. C. Attachment I is signed off as each area is searched. NOTE: To speed the search effort, Attachment I may be , signed off by the Control. Room /TSC/OSC as information is received from the search and rescue team ' via t portable radio or PA System. 4.1.7 The search and rescue team will: t3 _. A. Obtain floor plans for building being searched 6 and determine the best route to most probable location. Obtain any necessary keys. NOTE: The team leader will be assigned keys should certain suspected areas be locked, and need searching. B. Check wi,th Health Physics for route approval or modification for radiological reasons. gS b PAGE 3 0F 5
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'j[ ', EPP-011 t
REVISION 2 6/11/82
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h)n N- C. Search most, probable a'rea fit:st using information supplied in 4.1.5 s D. During the search and rescue cffort, utilize all possible means to keep extocuros ALARA. E. Inform ED/ Shift Supervisor when each e.levation is l thoroughly searched. The Shift Supervisor will N1Pect the search and rescue team to the next area Ao.be s'earched and assign further search teams as needed. 9 4.1.8 As soon as v,1ctim is found: A. Assess condition of victim and administer any necessary first-aid. B. Modttor victim 'for contamination and determine i[ actions necessary to remove victim from the
, ', area.
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i , s l'. . Identity of victim.
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, 3 Requirements for removal of victim from the area.
D. Remove victim from area as soon as possible. 4.2 The'ED/ Shift' Supervisor will ensure that back-up personnel l
-are.ctanding by to assist as needed.
! 4.3 The s5 arch and rescue team will report all data to the l l ED/ Shift Supervisor as it is received and based upon the l' condition of the individual, recommend initiation, if required, of one of the following Emergency Plan , procedures: t A. EPP-009, On-Site Medical B. EPP-020, Emergency Personnel Exposure Control ss m PIGE 4 0F 5
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- EPP-011 REVISION 2 6/11/82 4.4 After the missing individual or individuals has/have been
! found and safely removed from the hazardous area, notify the ED/ Shift Supervisor as to the current status and report for debriefing when the ED/ Shift Supervisor authorizes l termination of the search and rescue team assignment.
l P d i 4 I I O I l l l e O PAGE 5 0F 5
EPP-011 ATTACHMENT I PAGE 1 0F 2 i g REVISION 2 PLANT AREAS FOR SEARCH AND RESCUE BUILDING LEVEL INITIAL f Auxiliary 374' 3883 to 397' 412' 436' 463' 485' Stairwells Fuel Handling Building 412' 436' l 463' Stairwells Control Building 412' 425' 436' 448' 463' l 482' Stairwells Intermediate Building 412' l 436' i l 463' O
EPP-011 ATTACHMENT I PAGE 2 0F 2 f O REVISION 2 PLANT AREAS FOR SEARCH AND RESCUE BUILDING LEVEL INITIAL Stairwells Turbine Building 412' 436' 463' Stairwells Service Building 436' 448' Stairwells Diesel Generator Building 427' l 436' Water Treatment Area Service Water In take Structure _ Circulating Water Intake Structure Others m
4 EPP-011 O Attachment II Page 1 of 7 7 Rev. 2 -
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