ML20077H762
| ML20077H762 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 05/31/1983 |
| From: | VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML20077H756 | List: |
| References | |
| PROC-830531-01, NUDOCS 8308110281 | |
| Download: ML20077H762 (476) | |
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, gg EMERGENCY PLAN IMPLEMENTING PROCEDURES oru
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i o I $ $ EPIP NO. Procedure Safety Code Effective Date OO uO $ EPIP-1.01 Emergency Manager Controlling Procedure S 05-24-83 cout mm EPIP-1.02 Response to Unusual Event S 07-22-82 EPIP-1.03 Response to Alert S 05-24-83 EPIP-1.04 Response to Site Emergency S 05-24-83 EPlP-1.05 Response to General Emergency S 05-24-83 EPIP-2.01 Notification of State and I.ocal Governments S 05-24-83 EPIP-2.02 Notification of NRC S 07-22-82 EPIP-2.03 Reports of Offsite Agencies S 09-01-82 EPIP-3.01 Callout of Emergency Response Personnel S 05-24-83 EPIP-3.02 Activation of Technical Support Center S 05-24-83 EPIP-3.03 Activation of Operational Support Center S 05-24-83 EPIP-3.04 Activation of Emergency operations Facility S 05-24-83 EPIP-4.01 Radiological Assessment Director Controlling Procedure S 05-24-83 EPIP-4.02 Radiation Protection Supervisor Controlling Procedure S 05-24-83 EPIP-4.03 Dose Assessment Controlling Procedure S 05-24-83 EPIP-4.04 Emergency Personnel Radiation Exposure S 05-24-83 EPIP-4.05 Respiratory Protect, ion S 09-01-82 8306270186 830622 CF ADDCM 05000338 CF
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EPIP PROC. LIST 05-31-83 d Page 2 of 3 l EPIP NO.
.1 Procedure Safety Code Effective Date EPIP-4.06 Personnel Honitoring and Decontamination L 05-24-83 EPIP-4.07 Protective Hearures S 05-24-83 i EPIP-4.08 Initial Offsite Release Assessment S 05-24-83 EPIP-4.09 Source Term Assessment -
S 05-24-83 EPIP-4.10 Determination of X/Q S 05-24-83' EPIP-4.11 Follow-Up Offsite Release Assessment S 05-24-83 EPIP-4.12 Offsite Envirorunental Honitoring Instructions S 05-24-83 EPIP-4.13 Offsite Release Assessment with Environmental Data S 05-24-83 EPIP-4.14 Inplant Honitoring 'S 09-01-82 EPIP-4.15 Onsite Honitoring S 05-24-83 EPIP-4.16 Offsite Monitoring S 05-24-83 EPIP-4.17 Honitorieg of OSC and TSC S 05-24-83 EPIP-4.18 Monitoring of EOF '
S 05-24-83 EPIP-4.19 Use of Radios for Health Physics Monitoring S 05-24-83 EPIP-4.20 Health Physics Actions for Transport. of Contaminated Injured Personnel S 05-24-83 EPIP-4.21 Evacuation and Remote Assembly Area Monitoring S 09-01-82 EPIP-4.22 Post Accident Sampling of Containment Air S 05-24-83 e.
_ cm----- - . . - _j EPIP PROC. LIST ]j 05-31-83 Page 3 of 3 EPIP NO. ] Procedure Safety Code Effective Date EPIP-4.23 Post Accident Sampling of Reactor Coolant S 05-24-83
- EPIP-4.24 Gaseous Effluent Sampling During an Emergency S 09-01-82 EPIP-4.25 Liquid Effluent Sampling During an Emergency S 09-01-82 EPIP-4.26 High Level Activity Sample Analysis S 09-01-82 EPIP-5.01 Tranportation of Contaminated Injured Personnel -
S 09-01-82 EPIP-5.02 Search and Rescue S 07-22-82 EPIP-5.03 Personnel Accountability S 05-24-83 EPIP-5.04 Access Control S 07-22-82 EPIP-5.05 Site Evacuation S 05-24-83 EPIP-5.06 Emergency Radiation Exposure Authorization S 09-01-82 EPIP-5.07 Administration of Radioprotective Drugs S 09-01-82' EPIP-5.08 Damage Control Guideline S 07-22-82 EPIP-6.01 Re-entry / Recovery Guideline S 07-22-82 9 t
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NO.97887200
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VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION
^ EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCEDURE TITLE REVISION 03 EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE PAGE (With 1 Attachment) 1 of 8 PURPOSE To initially assess a potential emergency condition and initiate corrective actions.
USER Shift Supervisor OR Station Emergency Manager ENTRYCONDITIONS Any one of the following :
- 1. Another station procedure directs initiation of this procedure.
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- 2. A potential emergency condition is reported to the Shift Supervisor.
SAFETY RELATED REVISION RECORO REV. 00 PAGE(S): ENTIRE PROCEDURE DATE: 07-02-82 REV. 01 PAGE(S): ENTIRE PROCEDURE DATE: 07-22-82 REV. 02 PAGE(S): ENTIRE PROCEDURE DATE: 03-09-83 REV. 03 PAGE(S): ENTIRE PROCEDURE DATE: 05-24-83 REV. PAGE(S): DATE: REV. PAGE(S): DATE: R5,7. DAc? m ? nATFe APPROVAL RECOM NCEO APPROVED DA TE
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CHAIRMANSTA TION NUCLEAR SAFETY AND OPERATING COMMITTEE 05~24~83
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- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 1. INITIATE PROCEDLTE:
a) BY: DATE: TIME: NOTE: Continue through this and all further instructions unless otherwise directed to hold.
- 2. IDENTIFY EVENT:
a) Event-TRANSPORT OF CONTAMI- a) GO TO Step 2.b of this in-NATED INJURED PERSONNEL struction.
- 1) Initiate EPIP-5.01 Transport of Contami-nated Injured Personnel
- 2) Verify initiation of EPIP-4.20, H.P. Actions for Transport of Injured Contaminated Personnel
- 3) Continue this instruction b) Event-RADIATION RELEASE b) GO TO Step 2.c of this in-struction.
- 1) Request Health Physics initiate EPIP-4.01, Radiological Assess-ment Director Controlling Procedure, and continue this instruction
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Pts. 97407210 i n NUMBER Pr?OCEDURE TITLE REVISION 03 EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE PAGE 3 of 8
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 2. (CONTINUED) ._
c) Event-FUEL HANDLING INCIDENT c) GO TO Step 2.d of this in- . struction.
- 1) Request Health Physics initiate EPIP-4.01, Radiological Assessment Director Controlling Procedure, and. continue this instruction d) Event-SECONDARY RELEASE d) CO TO Step 2.e of this in-struction.
- 1) Request Health Physics ,
initiate EPIP-4.01,
, Radiological Assessment Director Controlling Procedure, and continue this instruction e) Event-S/G TU3E RUPTURE e) GO TO Step 2.f of this in-struction.
- 1) Request Health Physics initiate EPIP-4.01, Radiological Assessment Director Controlling Procedure, and continue this instruction f) Event-LOCA f) GO TO Step 3 of this in-struction.
- 1) Request Health Physics initiate EPIP-4.01, Radiological Assessment Director Controlling --
Pro:edure, and continue l this instruction. l
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Nr.97847210 t NUMBER PROCEDURE TITLE REVISION 03 EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE PAGE 4 of 8
- STEP ACTIONMXPECTED RESPONSE RESPONSENOTOBTAINED CAUTION: Declaration of the highest emergency class for which an Emergency Action Level is exceeded shall be made.
- 3. ASSESSMENT AND CLASSIFICATION:
a) Refer to Index EPIP 1.01, of Attachment 1, Emergency Action Levels AND
- 1) Using index, determine event category AND GO TO proper EAL tab AND
- 2) Evaluate event, deter-
, mine classification, AND
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Go To Step 4 of this procedure
- 4. VERIFY CLASSIFICATION:
a) EOF- NOT ACTIVATED a) If EOF activated, announce to staff the transfer of commend from TSC to EOF and proceed to 4.b. b) TSC - NOT ACTIVATED b) IF TSC activated, GO TO Step 6_. . W.- $ee.e w W ee
No.97847210 6 NUMBER PROCEDURE TITI.E REVISION 03 EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE PAGE 5 of 8
- STEP ACTIONNXPECTED RESPONSE RESPONSENOTOBTAINED
- 4. (CONTINUED) c) Notify SRO-On-Call or Super- c) Notify Station Manager or intendent of Operations Asst. Station Manager.
d) Verify classification e) If required by Alert, Site, or General Emergency request initiation of ADMIN 19.6, Conduct of Operations, Notification NOTE: Return to Step 2 of this instruction as necessary during the course of the situation for additional events and reclassification.
- 5. VERIFY EALS EXCEEDED:
a) EALS-EXCEEDED a) IF EALS NOT exceeded, DO NOT Eclare an emergency classif-ication. i AND l
- 1) Continue appropriate corrective action IAW procedures.
- 2) GO TO Step 7 of this pro-cedure.
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No.97887210
.- NUMBER PROCEDURE TITLE REVISION 03 EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE PAGE 6 of 8
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINEO S. (CONTINUED) b) Assign appropriate individual as interim Emergency Commun-icator c) Direct senior H.P. personnel on site to initiate EPIP-4.01, Rrdiological Assessment Director Controlling Procedure
- 6. DETERMINE EPIPS:
a) Event classification - UNUSUAL a) CO TO Step 6.b of this in-EVENT struction.
- 1) GO TO EPIP-1.02, Response to Unusual Event b) Event classification - ALERT b) CO TO Step 6.c of this instruction.
- 1) GO TO EPIP-1.03, Response to Alert c) Event classification - SITE c) E TO, Step 6.d of this EMERGENCY instruction.
- 1) CO TO EPIP-1.04, Response to Site Emergency d) Event classification - GENERAL EMERGENCY
- 1) CO TO EPIP-1.05, Response to General Emergency
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i l No. 97817210 t NUMBER PROCEDURE TITLE REVISION 03 EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE PAGE 7 of 8
- STEP ACTION / EXPECTED RESPONSE RESPONSENOT08TAINED
- 7. SECURk FROM EVENT:
a) Notify involved station personnel that emergency condition does not exist b) GO TO Step g of this instruc-tion
- 8. TERMINATE EMERGENCY:
a) Notify involved station personne) that emergency condition is no longer in effect - b) Initiate recovery actions b) IF required actions are be-IAW established station yond the scope of established procedure and capabilities procedures and capabilities. THEN GO TO Step 9 of this instruction. c) Notify OSC Director to deactivate the OSC
- 9. TERMINATION NOTIFICATIONS:
a) Initiate termination notifi-cation to counties and state
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IAW EPIP-2.01, Notification of State and Local Governments b) Initiate termination notifi-cation.to NRC IAW EPIP-2.02, Notification of NRC
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N,0. 97887210
,, NUMBER PROCEDURE TITLE REVISION' 03 EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE PAGE 8 of 8
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 9. (CONTINUED) c) E required recovery actions where considered beyond the scope of normal procedures and capabilities in Step 8 GO TO EPIP-6.01, Recovery and Restortation Guideline
- 10. REPORTINb:
a) Verify required reports and notifications IAW EPIP-2.03, Reports to Offsite Agencies
- 11. ADMINISTRATION:
a) Initiate replacement cf any used procedures and forms b) Forward completed EFIPs, forms and other applicable records to SNSOC for review c) E required, deactivate TSC
- 12. TERMINATE EPIP-1.01:
a) COMPLETED BY: DATE: TIME: _ _ END _E__ _ _ . _ _ _ - - _ _ _ _ - _ _ _ . _ _ _ _ _ _ _ _ - - - _ - - - - -
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No. 97847220 NUMBER A TTACHMENT TITLE - REVISION EPIP-1.01 03 EMERGENCY ACTION LEVEL TABLE A TTACHMENT PAGE 1 INDEX 1 of 38 CAUTION: Declaration of the highest emergency class for which an EAL is exceededshall be made. GO TO IF EVENT CATEGORY IS: , TAB
- 1. Saf ety, Shutdown, or Assessment System Event . . . . . . . . . . . . . . . . . . . . A
- 2. Reactor Coolant System Event ....................................B
- 3. Fuel Failtfre or Fuel Handling Accident. . . . . . . . . . . . . . . . . . . . . . . . . . .C
- 4. Containment Event................................................D
- 5. Radioactivity Event..............................................E
- 6. Contaminated Personnel ..........................................F
- 7. Lo ss o f S e condary Co o ling . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . G
- 8. Ele c t rica l Fa ilu r e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . H
- 9. Fire.............................................................I
- 10. Security Event...................................................J l 11. Hazard to Station Operation......................................K -
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- 12. Na tu ral Ev en t s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . L
- 13. Miscellaneous Abnormal Events....................................M i
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NUMBER A TTACHMENT TITLE REWSION
^
EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 03 (TAB A) A TTACNMENT SYSTEM SHUTDOWN, OR ASSESSMENT FAGE l 1 SYSTEM EVENT 2 of 38 ' l CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 1. Non-transient ECCS Non-spurious ECCS Unusual Event initiation initiation as vali-dated by Emergency
- MODES 1, 2, 3 & 4 Procadures
- 2. Non compliance with Unit (s) placed in Mode 3 or Unusual Event Tech. Spec. Limiting lower status as a result Condition for Opera- of Loss of Engineered tion Safety Feature, Fire Pro-tection System or other MODES 1 & 2 noncompliance with T.S.
Limiting Conditions for Operation
- 3. Failure of a safety Either condition a) or b) Unusual Event or relief valve to exists:
close after pressure - reduction, which may . affect the health and a) RCS safety of the public Pressurizer safety or PORV flow as indicated ALL MODES by accoustical or tem-perature monitoring equipment AND l RCS pressure-LESS THAN 1600 psig b) Main Steam Excessive Steam Generator
' Safety, PORV, or Decay Heat l Release flow as indicated by rapid RCS cooldown l
rate AND MS pressure is GREATER THAN 100 psi below set point of affected valve. o , e-4~..o me m es==.ye .-=>-* *er e =~. w e r e- -+s.=** . * . ~ s a w re- - . ,s x-..- - .- ..s . . . , ~ . - . .-
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No.C7847220 NUMBER A TTACHMENT TITLE REVISION EPIP-1.0L EMERGENCY ACTION LEVEL TABLE 03 ) (TAB A) A TTAC##ENT SYSTEM SHUTDOWN, OR ASSESSMENT FAGE 1 SYSTEM EVENT 3 of 38 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 4. Loss of function need- a) Total loss of Sec- Alert ed for unit CSD con- ondary System cool-dition '- ing capability MODE 5 b) Total loss of any of the following systems:
- 1) Service Water pR
- 2) Component Cooling 0,,R,
- 3) Residual Eeat Removal
- 5. Loss of Function needed Total loss of the following: Site Emergency for unit HSD condition a) Charging /SI System MODES 1,2,3 & 4 OR b) Main feedwater AND Auxiliary Feedwater Systems
- 6. Failure of the Reactor a) Manual or Automatic RX Alert Protection System to trip-INITIATED complete a trip which takes the Rx Suberitcal AND MODES 1 & 2 b) Intermediate Range Mo-nitor indicating-ZERO or POSITIVE SUR e
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No.97847220 NUMBER A TTACHMENT TITLE REVISION
^
EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 03' (TAB A) A TTAC# MENT SYSTEM SHUTDOWN, OR ASSESSMENT FAGE 1 SYSTEM EVENT 4 of 38 CONDITION INDICATION CLASSIFICATION
- 7. Failure of the Reactor Condition a) and b's Site Emergency
' ~ Protection System to exists with c) initiate and complete a required trip while a) RX trip setpoint ud at power coincidences-EXC EDED MODES 1 & 2 AND b) Manual Rx trip-INITIATED AND c) Rx power indication NOT DECREASING
- 8. Indications or alarms Unit (s) placed in Mode 3 or. Unusual Event on process or effluenc lower condition as a re-parameters required for sult of any of the following:
incident assessment NOT functional in the con-trol room . a) Containment Gaseous or Particulate Radiation MODES L,2,3 & 4 Monitors- NOT OPERABLE AND
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Backup grab sample capability is inoperable per leak de-tection T.S.3.4.6.1 i pR b) Meteorological monitor-ing instrumentation- LESS ( THAN mininnne required to , perform offsite dose calculations per Unit 1 T.S.3.3.3.4 SR c) Post-accident instrument- . ation-LESS THAN minimum channels allowable per ! T.S. 3.3.3.6 l l
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NUMBER A TTACHMENT TITLE REVISION l
,~ EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 03 l (TAB A)
ATTACNMENT SYSTEM SHUTDOWN, OR ASSESSMENT FAGE 1 SYSTEM EVENT 5 of 38 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 9. Loss of communications Complete failure of the Unusual Event ;
capability following: a) Station PBX phone system
. ALL MODES AND b) Station Gai-Tronics system AND c) Station UHF radio system
- 10. All main board annunci- Simultaneous loss of all Alert ator alarms and unit annunciator alarms on computer lost panels "A" to "K" with loss of unit computer MODES 1 & 2
- 11. All main board annunci- Complete loss of all Site Emergency ator alarms and unit annunciator alarms on computer lost for more panels "A" to "K" with than 15 minutes during loss of unit computer for a unit transient GREATER THAN g minutes MODES 1 & 2 AND Unit operational transient-IN PROGRESS
- 12. Evacuation of Main Con- Evacuation of the Control Alert trol Room required Room with shut down control established within 15 min- -
ALL MODES utes
- 13. Evacuation of Main Con- Evacuation of the Control Site Emergancy trol Room with control Room with local shutdown
[ NOT established within control NOT established 15 minutes within H minutes ALL MODES l
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No.97007220 NUMBER A TTAC# MENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 03 (TAB B) ATTAC# MENT REACTOR COOLANT SYSTEM EVENT FACE 1 6 of 38 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 1. Safety Limit-RCS Limits of T.S. Fig Unusual Event Temperature / Pressure 2.1.1 - EXCEEDED curve exceedef MODES 1 & 2
- 2. RCS overpressure 2735 psig RCS Unusual Event pressure limit-EXCEEDED MODES 1,2,3,4 & 5
- 3. RCP locked rotor All the following Alert leading to fuel dam- exists:
age a) Flow in one or more MODE 1 RC loons LESS THAN 90% AND b) RCP trip caused by ' Phase Overcurrent Relay actuation
,AND c) High Range Letdown Radiation Monitor indication increasgs to-GREATER THAN 10 cpm -
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- 4. RCS leak rate requiring Unit in Mode 3 or lower Unusual Event plant shutdown IAW. as a result of any T.S. 3.4.6.2 of the following:
MODES 1 & 2 a) Unidentified RCS leakage-GREATER THAN M pR b) Identified leakage-GREATER THAN 10 gpm S ' c) Controlled leakage from RCP seals-GREATER THAN 30 gpm TOTAL OR d) Any pressure boundry
. leakage
- 5. RCS leak rate exceeds Pressurizer Level cannot Alert 50 gpm be naintained GREATER THAN 22% with one(1) Charging /SI MODES 1, 2, 3 & 4 Pump in operation AND RCS inventory balance indi-cates leakage-GREATER THAN E SPm
- 6. RCS leak rate exceeds EP-2, Loss of Reactor Cool- Site Emergency 300 gpm ant, in effect i
MODES 1, 2 , 3 & 4 AND Pressurizer level can not be maintained with two (2) j or more Charging /SI Pumps in operation
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., NUMBER A TTACMENT TITLE REVISION EFIP-1.01 EMERGENCY ACTION LEVEL TABLE 03 (TAB B)
A TTACNMENT REACTOR COOLANT SYSTEM EVENT FAGE 1 8 of 38 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 7. Primary to Secondary Unit in Mode 3 or lower con- Unusual Event leakagc-GREATER THAN dition as a result of I spm actions required by T.S.
3.4.6.2 MODES 1, 2, 3 & 4
- 8. Gross Primary to EP-4, Steam Generator Tube Alert Secondary leakage Rupture, is in effect with SI in progress .
MODES 1, 2, 3 & 4 AND CondenserAirE3ectorOR, Steam Generator Blowdown MonigorGREATERTHAN 1x10 cpm
- 9. Excessive Primary to Unit in Mode 3 or Jower , Alert Secondary leakage with condition as a result of loss of offsite power actions required by T.S.
3.4.6.2 MODES 1, 2 & 3 AND Condenser Air Ejector OR Steam Generator Blowdown Monitor Rgadings-GREATER - THAN 1x10 cpm AND Loss of offsite power indicated by zero volts on voltmeters for 4160V buses D, E & F.
- 10. Gross Primary to EP-4, Steam Generator Tube Site Emergency Secondary leakage with Rupture, is in effect with loss of offsite power SI in progress MODES 1, 2,3 & 4 AND m.e-*** 4* *a g.p, m. e. g
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No.97847223
. NUMBER A TTAC# MENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 03 (TAB B)
A TTAC# MENT REACTOR COOLANT SYSTEM EVENT FAGE ; 1 9 of 38 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 10. (CONTINUED) Condenser Air Ejector OR Steam Generator Blo'.down MonitorGpTER THAN 1x10 cpm AND Loss of offsite power indi-cated by zero volts on volt-meters for 4160V Buses D, E
&2 -
- 11. Loss of 2 of 3 fission Any two of a),b) or c) General Emer-product barriers with exist and the third gency potential loss of 3rd is imminent barrier a) Fuel clad integrity fail-ALL MODES ure as indicated by any of the following:
- 1) RCS specific activity -
GREATER THAN OR EQUAL TO 300.0 uCi/ Gram dose equivalent I-131.
- 2) 5 or more core exit thermocouples GREATER THAN 1200* F gR b) Loss of RCS integrity as.
indicated by any of the following: l 1) RCS pressure-GREATER THAN 2735 psig l 1
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~~ NUMBER A TTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 03 (TAB B)
A TTAC# MENT REACTOR COOLANT SYSTDi EVENT FAGE ' 1 10 of 38 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 11. (CONTINITED) 2) EP-2, LOCA, has been implemented
- 3) Containment High Range Area Radiation Monitor
-GpTERTHAN 10 mR/Hr E
c) Loss of containment inte-grity as indicated by any of the following:
- 1) Containment pressure
-GREATER THAN 60, psia and NOT decreasing
- 2) Loss of containment inte6rity as defined ,
in T.S. 1.8
- 12. Fuel failure with steam Any two of a),b) or c) General Emer-generator tube rupture exists and the third is gency imminent ALL MODES a) Fuel clad integrity failure as indicated by any of the following:
- 1) RCS specific activity-GREATER THAN 300 uCi/
gram dose equivalent I-131
- 2) 5 or more core exit thermocouples
-GREATER THAN 1200* F S
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- 12. (CONTINUED) b) S/G tube rupture as indicated by both of the following:
- 1) SI initiated by RCS Low Pressure
- 2) EP-4, Steam Generator Tube Rupture, initiated SR, c) Loss of Secondary integrity as indi-cated by any of the following:
- 1) Main Steam PORV - OPEN
- 2) Main Steam RV - OPEN
- 3) EP-3, Loss of Secondarv Coolant, initiated e
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- 1. Fuel clad damage Unit shutdown required Unusual Event indication . IAW action statement (b) of T.S. 3.4.8.b MODES 1,2,3 & 4 SR, High Range Letdown Ra-
.diation Monitor indica-tion ingreases GREATER THAN 10 cpm within 30 minutes AND remains Tor at least 15 minutes
- 2. Severe Fuel Clad RCS specific activity- Alert Damage GREATER THAN 300.0 uC1/ gram dose equiva-MODES 1,2,3 & 4 lent I-131 SR High Range Letdown Ra-diation Monitor indica-tion ingreases GREATER THAN 10 cpm within
, 30, minutes AND renains for at least g minutes l l l
- 3. Core damage with pos- Condition a) exists with Site Emergency l l
sible loss of coolable b) I geometry a) Fuel clad failure as MODES 1,2,3.5 4 indicated by any of the following: 1
- 1) RCS Specific activity GREATER THAN 60,uCi/ gram dose equivalent I-131
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NUMBER A TTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 03 (TAB C) ATTACHMENT FUEL FAILURE OR FUEL HANDLING ACCIDENT PAGE 1 13 of 38 l l l CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 3. (CONTINUED) 2) High Range Letdown Radiation Monitor indicatiog-GREATER THAN 1x10 cpm AND b) Loss of cooling as in-dicated by any of the following:
- 1) 5 confirmed core exit thermocouples
- GREATER TH.LN 1200* F
- 2) Core DT-ZERO
- 3) Core DT - RAPIDLY DIVERGING
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No.97847220 NUMBER A TTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 03 (TAB C) . A TTACdMENT FUEL FAILURE OR FUEL HANDLING ACCIDENT FAGE 1 14 of 38 CONDITION? APPLICABILITY INDICATION CLASSIFICATION
- 4. Probable large -radio- EP-2, LOCA has been in- General Emer-activity release ini- plemented AND RCS specific gency ated by LOCA with ECCS activity -GREATER THAN
. failure leading to 3000.0 uci/ s dose equi-core degradation valent I-131 ALL MODES AND High or Low Head ECCS flow ' are NOT being delivered to the core
- 5. Probable large radio- Loss of Main W system and General Emer-activity release ini- Condensate System gency tiated by loss of heat aink leading to core AND degreda tion Loss of Auxilary W System
- 6. Probable large radio- Condition a) exists with General Emer-activity release ini- b) or c) gency tiated by failure of protection system to a) Rx nuclear power after
- bring Rx suberitical a trip -GREATER and causing core de- THAN H gredation b) RCS pressure CREATER ALL MODES THAN OR EQUAL TO 2485 psig c) Containment pressure AND temperature -RAPIDLY INCREASING
.1)
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- 7. Probable large radio- a) Loss of all AC procedures General Emer-activity release init- implemented gency lated by loss'of AC and all feedwater AND ALL MODES b) Turbine Driven Auxilary Feedwater Pump NOT OPERABLE AND c) Restoration of a) or b) above not likely within 2 hours
- 8. Probable large radio- Copdition a) and b) exist General Emer-activity release init- with c) or d) gency iated by LOCA with loss of ECCS and containment a) EP-2 LOCA. initiated cooling AND ALL MODES b) High or Low Head ECCS flow is NOT being de-livered to the core
! AND c) Containment RS sump temp-eratt.re-GREATER THAN 190* F
; , AND NOT DECREASING s
S.R d) Quench Spray and Recircu-lation Spray Systems- NOT
! OPERABLE ,
9 M. a . .
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p.enenso NUMBER A TTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 03 (TAB C) A TTAC# MENT FUEL FAILURE OR FUEL HANDLING ACCIDENT PAGE 1 16 of 38 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 9. Fuel damage accident Condition a) exists with Alert with release of radio- b) or c) activity to containment ,
or fuel buildings a) Verified accident invol-ALL MODES ving damage to irradiated fuel AND b) Health Physics confirms fission product release . - from fuel 0,,,3 c) Readings on the Ventilation Vent Gaseous Monitgr
-GREATER THAN 1x10 cpm
- 10. Major fuel damage Conditions a) or b) exist Site Emergency accident with radio- with c) activity release to containment or fuel a) Water levsl in Rx vessel buildings during refueling -BELOW TOP OF CORE ALL MODES 0,,,R, b) Water level in Spent Fuel Pit -BELOW TOP OF SPENT FUEL AND c) Verified damage to irrad- .
iated fuel resulting in j readin's g on Ventilation VentGaseousMonitgr
-GREATER THAN 1x10 cpm l
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NUMBER A TTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 03
~
(TAB D) A TTACHMENT CONTAINMENT EVENT PAGE 1 17 of 38 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 1. Loss of Containment Unit has been placed in Unusual Event integrity Mode 3 or lower condi-tion due to a loss of containment integrity MODES 1,2,3 & 4 as defined by T.S.I.2.
and prescribed by T.S.
!.6.1.1
- 2. High-high Containment Condition a) exists with b) Alert radiation, pressure or c) and temperature '
a) Containment High Range MODES 1,2,3 & 4 Radiation Monitor GREATER THAN 10* mR/hr AND b) Containment pressure
-GREATER THAN E psia 3
c) Containment temperature
-GREATER THAN 150' F
- 3. High-high Containment Condition a) exists with b) Site Emergency radiation, pressure, or c) and temperattre a) Containment High Range Radiation Monitor MODES 1,2,3 & 4 indicates-GREATER THAN 102 mR/hr AND b) Containment pressure *
-GREATER THAN 27.75 psia AND is NOT decreasing S.R c) Containment temperature in-dicates-GREATER THAN 200* F e
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.- NUMBER A TTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 03 4
(TAB D) A TTACHMENT CONTAINMENT EVENT PAGE t 1 18 of 38 I 1 i j CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 4. Extremely high Con- Condition a) exists with b) General Emergency
.i tainment radiation, or c) 4 pressure and temp-1 perature a) Containment High Range 4 Radiation Monitor - 4 GREATER THAN 10 mR/Hr MODES 1,2,3 & 4 l # b) Containment pressure
-GREATER THAN M psis AND NOT DECREASING S.R c) Containment temperature j -GREATER THAN 280* F I
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- 1. Effluent release Any of the following Unusual Event GREATER THAN T.S.s._ monitors indicate valid allowable Limit readings above the spec-ified value ALL MODES l a) Clarifer Effluent Monitog-CREATER THAN 2.4x10 cpm b) Vent Stack A Gaseous Monito{-GREATER THAN 3.4x10 cpm j c) Vent Stack A Parti-culateMonigor-GREATER THAN 4.5x10 cpm d) Vent Stack B Gaseous Monitor-GREATER THAN 1x106 cpm FOR LESS THAN M MINUTES e) Vent Stack B Particulate Monitog-GREATER THAN 3.8x10 cpm f)AirEjectorMonitorfs)-
GREATER THAN 6.8x10 cpm g)DischargeCanalMon{cor-GREATER THAN 6.0x10 cpm h) Process Vent Gaseous 6 Monitor-GREATER THAN 1x10 ' cpu FOR LESS THAN y MINUTES
- 1) Process Vent Particulate 6 Monitor-GREATER THAN 1X10 cpm FOR LESS THAN 15,'MES
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- 2. Effluent Release Any of the following Alert
+
GREATER THAN 10 monitors indicate TIMES T.S. instan- valid readings above taneous allow- the specified values able limits ALL MODES a) Clarifier Effluent Monitor-GpTER THAN 1x10 cpm b) Vent Stack A Gaseous Monitog-GREATERTHAN 3.4x10 cpm c) Vent Stack A Partic-ulateMonitgr-GREATER THAN 4.5x10 cpm d) Vent Stack B Gaseous Monigor-GREATERTHAN 1x10 cpm FOR GREATER 5 MINUTES THAN 1_5, e) Vent Stack B Partic-ulateMonitgr-GREATER THAN 3.8x10 cpm f) Air Ejector Monitorfs)- GREATER THAN 6.8x10 cpm g)DischargeCanalMongtor-GREATER THAN 6.0x10 cpm h) Process Vent Gaseous Monigor-GREATERTHAN 1x10 epa FOR GREATER 5 MINUTES THAN J_5, i) Process Vent Particulate ! Monigor-GREATERTHAN l 1x10 cpm FOR GREATER THAN I _15 MINUTES
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No.97447220 NUMBER A TTACHMENT TITLE ~ REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 03 (TAB E) ATTACHMENT RADI0 ACTIVITY EVENT FAGE 1 22 of 38 CONDITION /APPLICAEILITY INDICATION CLASSITICATION
- 4. Projected or actual a) Confirmed Health Physics General Emerg-site boundary doses assessments of site bound- ency exceed 2 Rem W.B. or ary actual or projected 12 Rem thyroid ex- doses -GREATER TRAN 2 Rem posure WHOLE BODY OR 12 Rem THYROID EXPOSURE ALL MODES S.R b) Valid indications of the following exist:
- 1) Any Main Steam Line High Range Monitor
-GREATER THAN 6.4 mR/hr
' ER.
- 2) Ventilation Vent A High Range Monitor
-GREATER THAN 2.6x10
-1 1
mR/hr
. g .
- 3) Ventilation Vent B High Range Monitor
-GREATg THAM 3.2x10 mR/hr E
- 4) Process Vent High Range Monitor GREATER THAN 256 mR/hr I -
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- 5. High radiation or Valid unexpected levels Alert airborne contami- on any of the following nation levels in- monitors have increased dicate a severe by a factor of 1000 degradation in con-trol of radioactive a) Ventilation Vent Multi-material sample Gaseous and Particulate Monitor ALL MODES b) Control Room Area Monitor c) Auxiliary Building Control Area Monitor d) Auxiliary Building Drum-ming Area Monitor e) Decontamination Building Area Monitor f) Fuel Pit Bridge Area Monitor g) New Fuel Storage Area Monitor h) Laborator/ Area Monitor
- 1) Sample Room Area Monitor
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, NUMBER A TTACHMENT TITLE ' REVISION EPIP-1.01 EMERGENCY ACTION LEVEL. TABLE 03 (TAB F) l A TTACHMENT CONTAMINATED PERSONNEL PAGE l
1 24 of 38 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 1. Transportation of Contaminated injured indi- Unusual Event contaminated injured vidual enroute to off-site individual to off-site facility for creatment facility .
ALL MODES J d i
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- 1. Major Secondary line EP-3, Loss of Secondarv Unusual Event break Coolant, initiated and verified non-spurious MODES 1,2,3 & 4
- 2. Major Secondary line Condition a) exists with Alert break with significant 'b),c) or d)
Primary to Secondary leakage a) EP-3, Loss of Secondary Coolant, initiated and verified non-spurious MODES 1,2,3 & 4 AND b) Condenser Air Ejector Radiation
-GREATER THAN Monitor 7x10$ epm 0,,R, c) Steam Generator Blow-down Radiation Monitor
.-GpTERTHAN 10 cpm 0,,,R, d) MS Line High Range Radiation Monitor
-GREATER THAN 0.5 mR/hr 1
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- 3. Major Secondary line Conditions a) and b) exist Site Emergency break with signif- with c), d) or e) icant Primary to Secondary leakage and a) EP-3, Loss of Secondarv fuel damage indicated Coolant, initiated and verified non-MODES 1,2,3 & 4 spurious AND b) RCS specific activity exceeds limits of T.S.
Figure 3.4.1 OR Let-dow. High Range Ra-diation Monitor -GREATER THAN 105 cp, c) Condenser Air Ejector RadiationMonitog .
-CREATER THAN 10 cpm pR, d) Steam Generator Blow-down Radiation Mgnitor
-GREATER THAN 1 cpm SR e) MS Line High Range Radiation Monitor
-GREATER THAN 1.6 mR/hr
u,_); : L.- - .,:Lu . s:, ._u -_.:,, ' ' _ :ns 2- g... , ;;;;u-No.97847220 NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 03 (TAB H) A TTAC# MENT ELECTRICAL FAILURE FAGE 1 27 of 38 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 1. Loss of off-site Unit Main Generator and Unusual Event power or on-site _AC both Emergency Diesel power capability Generators out of ser-vice ALL MODES SR Loss of all 34.5KV Reserve Station Service Buses
- 2. Loss of all off-site Ammeters for 4160V Reserve Alert and on-site AC power Station Service Buses D, E.
& F all indicate-ZERO (0)
ALL MODES AMPS AND Ammeters for 4160V Station Service Buses A,B,& C all indicate-ZERO (0) AMPS AND Ammeters for 4160V Emergency Buses H and J both indicate-
, ZERO (0) AMPS
- 3. Loss of off-sita and The following conditions Site Emergency on-site AC power for exist for a period of- ,
more than 15 minutes GREATER THAN 15 minutes ALL MODES a) Ammeters for 4160V Reserve Station Service Buses D,E,& F all indi-cate-ZERO (0) AMPS AND b) Ameters for 4160V' l Station Service Buses l A,B & C all indicate-ZERO (0) AMPS 1 [
- I l
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No.97887220 NUMBER A TTACHMENT TITI.E REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 03 (TAB H) A TTAC# MENT ELECTRICAL FAILURE FAGE 1 28 of 38 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 3. (CONTINUED) c) Ammeters for 4160V Emergency Buses R & J both indicate-ZERO (0)
AMPS
- 4. Loss of all on-site All Station Battery Alert DC power voltmeters indicate-ZERO (0) VOLTS ALL MODES S
No light indication avail-able to Reserve Station Service Breakers 15D1, 15El and 15F1
- 5. Loss of all on-site The following conditions Site Emergency DC power for-GREATER exist for a period of-TRAN 15 minutes GREATER THAN g minutes ALL MODES a) All Station Battery volt-meters indicate-ZERO (0)
VOLTS AND b) No light indication avail-able to Reserve Station Service Breakers 15D1, 15El and 15F1 l t
... .... . . . . . . - . . . _ _ . .. . .____ _ . . _ . . - . _ _ . . .s_.. _ . _ , . _ ~ . . ~ . . . . . . . - . . . . . .4 .+ ..y __ , . , ,._ ,.
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-- NUMBER A TTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 03 (TAB I)
A TTACHMENT FIRE FAGE 1 29 of 38 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 1. Fire lasting-GREATER Fire within the Station Unusual Event THAN 10 minutes which is not under con-trol within 10 minutes ALL' MODES after fire fighting efforts begin
- 2. Fire potentially affect- Fire within the Station Alert ing station safety sys- which has potential for tems causing a safety system MODES 1,2,3,&4 NOT to be operable as defined by T.S.I.6 and 3.0.5
- 3. Fire resulting in de- Fire within the Station Site Emergency 4
gradation of safety which causes major degrad-systems ation of a safety system function required for pro-MODES 1,2,3 & 4 taction of the public AND Affected systems are caused to be NOT operable as defined by T.S.I.6. and 3.0.5 l l
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9.orse7:so n NUMBER A TTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 03 (TAB J) A TTACHMENT SECUR1TT EVENT PAGE 1 30 of 38 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 1. Security threat, un- Security Shift Supervisor Unusual Event authorized attempted has reconsnended Shif t entry, or attempted Supervisor declare an sabotage Unusual Event IAW. ADM-SPIP-35 ALL MODES
- 2. Ongoing Security com- Security Shift Supervisor Alert promise has notified the Shift Supervisor of a confirmed ALL MODES unneutralized intrusion into the Protected Area
- 3. Imminent loss of Security Shift Supervisor Site Emergency physical Station has notified the Shift control Supervisor of iminent intrusion into a Vital ALL MODES Area
- 4. Loss of Station Shift Supervisor has been General Emer-physical control informed that the security gency force has been neutralized ALL MODES by attack, resulting in loss of physical control
. of station .
pR Shift Supervisor has been informed of intrusion into one or more Vital Areas which are occupied OR controlled by an aggressor i I l
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Peo. 97887220
-~ . . NUMBER A TTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 03 (TAB K)
A TTAC# MENT HAZARD TO STATION OPERATION FACE 1 31 of 38 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 1. Aircraft crash or un- Confirmed notification of Unusual Event usual aircraft activity aircraft crash within the site boundary ALL MODES S.R.
Unusual aircraft activity in the vicinity of the site as determined by the Shift Supervisor AND/OR Security Shift Supervisor
- 2. Aircraft crash on'the Aircraft crash within the Alert facility Protected Area ALL MODES -
OR Aircraft crash in Station Switchyard
- 3. Aircraft damage to Aircraft crash which affects Site Emergency vital plant systems vital structures by impact or fire MODES 1,2,3 & 4 .
- 4. Train derailment on Confirmed report of train Unusual Event site derailment onsite ALL MODES -
- 5. Onsite explosion Confirmed report of un- Unusual Event planned explosion onsite ALL MODES
- 6. Explosion damage to Unplanned explosion result- Alert facility ing in damage to plant structure or equipment ALL MODES l
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( No. 97887220 l r' NUMBER A TTAC# MENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 03 (TAB K) A TTAC# MENT HAZARD TO STATION OPERATION FAGE 1 32 of 38 CONDITION /APPLICABILI1T INDICATION CLASSIFICATION
- 7. Severe explosive damage Explosion which results in Site Emergency severe degradation of any of the following systems MODE 1,2,3 & 4 required for safe shutdown:
a) CVCS System CR b) ECCS System 3 -- c) Main / Auxiliary Feedwater System
- 8. On or near site release Notification of' unplanned Unusual Event of toxic or flammable release of toxic OR flam-liquids or gases mable agents whicEmay affect safety of station ALL MODES personnel 3 equipment
- 9. Entry of toxic or flam- Notification of uncontrolled Alert mable gases or liquids release of toxic OR flam-into plant facility mable agent which cause:
ALL MODES a) Evacuation of personnel ' from plant areas AND b) Safety related equipment is rendered inoperable
- 10. Entry of toxic or flam- Notification of uncontrolled Site Emergency mable gases into plant release of toxic _0_RR flam -
vital areas mable agents above life threatening or explosive MODE 1,2,3 & 4 limits into Vital Areas AND l n .w<
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_; i ,, A: _ ..r;, _c,,,.,_.g,__,, No. 97847220 l l NUMBER A TTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 03 (TAB K) A TTACHMENT HAZARD TO STATION OPERATION FAGE 1 33 of 38 i CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 10. (CONTINUED) Any of the following occur:
a) Evacuation of Vital Area required , i OR b) Degradation of safety systems rsulting in less of a safety system function i required for protection of the public
- 11. Turbine rotating a) Failure of Turbine / Unusual Event component failure Generator rotating with no casing equipment resulting penetration in immediate unit shutdown MODES 1 & 2
- 12. Turbine failure or Failure of Turbine / Alert missile impact Generator rotating equip-ment resulting in casing MODES 1 & 2 penetration E
13 Missile damage to Notification of missile Alert safety related equip- impact causing damage ment or structures to safety related equip-MODES 1,2,3 & 4 ment or sturctures
- 14. Severe missile damage Missile impact causing Site Emergency to safety systems severe degradation of safety systems required for unit shutdown MODES 1,2,3 & 4 1
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- 1. Earthquake detected Confirmed earthquake which Unusual Event activates the Event Alarm ALL MODES on the Strong Motion Accelerograph
- 2. Earthquake greater Confirmed earthquake which Alert than OBE levels activates Event Alarm on the Strong Motion Accel-ALL MODES erograph AND Alarms on the Peak Shock l Annunciator indicate a horizontal motion of- l GREATER THAN or EQUAL TO
. 0.09 g or a vertical motion of-GREATER THAN or EQUAL TO 0.06 g
- 3. Earthquake greater Earthquake which activates Site Emergency than DBE levels the Event Alarm on the Strong Motion Accelerograph MODES 1,2,3 & 4 AND Alarms on the Peak Shock Annunciator indicates a horizontal tuotion of GREATER THAN or EQUAL TO 0.18 g or a vertical motion of-GREATER THAN or EQUAL TO 0.12 g
- 4. Tornado onsite. Tornado visually detected Unusual Event onsite ALL MODES
- 5. Tornado striking Tornado visually detected Alert facility striking within the Pro-tected Area or Switchyard ALL MODES e e Ogmh
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~ NUMBER A TTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 03 (TAB L)
ATTACHMENT NATURAL EVENTS PAGE 1 35 of 38 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 6. High winds Any of the following: Unusual Event ALL MODES a) System Operator notifi-cation of Hurricane watch for Louisa County 0,,R b) Sustained wind speed onsite measured OR projected to be in ex-cess of 7_3,3 mph
- 7. Extreme winds Sustained extreme winds in Alert excess of 78 mph caused by MODES 1,2,3 & 4 Hurricane OR other severe weather conditions
- 8. Severe winds Sustained severe winds in Site Emergency excess of 80 mph caused by MODES 1,2,3 & 4 Hurricane, Tornado 3 other severe weather condition
- 9. 50 year flood or low Flood in the Lake Anna Unusual. Event water level Reservoir with indicated level-GREATER THAN 254 ALL MODES feet MSL E
Low water level in the Lake Anna Reservoir with indi-
- cated level-LESS THAN 247 feet MSL
- 10. Flood or low water Flood in the Lake Anna Alert level near design Reservoir with indicated I
levels level-GREATER THAN 263 feet MSL ALL MODES l 3 ! l l - i
442ed.2.4 7 ' na_.ja , - - Im ?' - _ _m., . O - J *. _ .L .s..._. G40.91987220 1 NUMMR ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 03 (TAB L) A TTACHMFNT NATUEAL EVENTS PAGE 1 36 of 38 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 10. (CONTINUED) Low water level in the Lake Anna Reservoir with indi-cated level-LESS THAN 245 feet MSL
- 11. Flood or low water Flood in the Lake Anna Site Emergency level above design Reservoir with indicated levels level-GREATER THAN 280 feet MSL MODES 1,2,3 & 4 f.R, Low water level in the Lake Anna Reservoir with indi-cated level-LESS THAN 244 feet MSL i
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- 1. Station conditions Shif t supervisor judgement Unusual Event which warrant increased that any of the following awareness of state and/ exist:
dr local authorities ALL MODES a) Unit (s) placed in a Mode 3 or lower condition as a result of noncompliance with T.S. Limiting Con-dition for Operation _OR i b) Unit shutdown is other than a controlled shutdown 9.R, J c) Unit is in an uncontrolled condition during operation _ SE d) A conditien exists which has the potential for escalation and, therefore, j warrants notification
- 2. Station conditions Shift Supervisor / Station Alert which warrant precau- Emergency Manager judgement tionary notification to the near-site public ALL MODES
- 3. Station conditions Shift Supervisor / Station Site Emergency which warrant activation Emergency Manager judgement of emergency facilities monitoring teams or pre-cautionary notification to the near-site public ALL MODES i
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NUlf9ER A TTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 03 (TAB M) A TTAC# MENT MISCELLANEOUS ABNORMAL EVENTS FAGE 2 38 of 38 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 4. Any major internal or Shift Supervisor / Station General Emer-external events which Emergency Manager judgement gency singlely or in combin-ation cause massive damage to station fa-cilities ALL MODES e
- 4 l
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JA - - - - - * ~ ~ _.: aim.- E s No. 97881200 VIRGINIA ELECTRIC AND PCWER COMPANY NORTH ANNA POWER STATION e EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROC 200RE TITLE REVISION 02
~
EPIP-1.03 RESPONSE TO ALERT PAGE (With No Attachments) 1 of 12 PURPOSE
- 1. To provide guidance to the Station Emergency Manager during the pro-gress of a classified ALERT emergency.
USER Station Emergency Manager ENTRY CONDITIONS
, 1. Entry from EPIP-1.01, Emergency Manager Controlling Procedure.
SAFETY RELATED REVISION RECORD REV. 00 - PAGE (S)': Entire Procedure DATE: 07-02-82 REV. 01 PAGE(S): Entire Procedure DATE: 07-22-E2 REV. 02 PAGE(S): Entire Procedure DATE: 05-24-83 REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: ( I APPROVAL RECOM NDED APPROVED CA TE w 05-24-83 N CHAIRMANSTA TION NUCLEAR SAFETY AND GPERA TING COMMITTEE .
. - - . . . . - . . - - __ . ~ ~ . . - . - - - - - - .
A .. ... . . . . [ . .. . . . . No.orsers:o 1 NUMBER PROCEDURE TITLE REVISION 02 ' EPIP-1.03 RESPONSE TO ALERT l PAGE 2 of 12
- STEP ACTION /EXTECTED RESPONSE RESPONSENOT08TAINE0 l
1 J
- 1. INITIATE PROCEDURE a) Declare postion of Station ,
Emergency Manager ! b) BY: DATE: _ TIME: NOTE: The Shift Supervisor may be relieved as Station Emergency Manager IAW the NAPS Emergency Plan. 4 s
- 2. INPLANT NOTIFICATION:
a) From the Control Room, sound the ALERT Alarm b) nake announcement on plant Gai-Tronics system as follows:
- 1) "An ALERT has been declared"
- 2) "All Emergency Response personnel report to their assigned stations"
- 3) "All visitors, 2000 and -- -
3000 series badged personnel report to the Security Building"
- 4) "All other personnel report to their Emer-gency Assembly Areas" 1
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- m NUMBER PROCEDURE TITLE REVIS10N 02 EPIP-1.03 RESPONSE TO ALERT PAGE 3 of 12 4
- STEP ACTIONEXPECTED RESPONSE RESPONSENOTOBTAINED
- 2. (CONTINUED) c) Repeat Steps 2a and 2b, THEN continue this in-struction
- 3. ONSITE ACCOUNTABILITY:
a) Initiate EPIP-5.03, Personnel Accountability b) Lirect Security to initiate EPIP-5.04, Access Control 4 FTATE AND COUNTY NOTIFICATION: a) Initiate EPIP-2.01, Notification of State and Local Governments 1
- 5. NRC NOTIFICATION:
a) Initiate EPIP-2.02, Notification of NRC NOTE: Updates to offsite authorities should be provided at approximately 15 minute intervals and after significant changes to plant status, radiological data, or meteorological data.
- 6. CALLOUT OF PERSONNEL:
- a) Verify Emergency Response a) Direct Security to initiate ,
! Personnel - ONSITE EPIP-3.01, Call out of Emer- ' gency Response Personnel. AND GO TO Step 7 of this I instruction.
)
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L :- - _ _ _%s _ _ ___ _ . g.,,;_ ._ s- - _;..-_,__ No. 97887210 NUMBER PROCEDURE TITLE REVISION 02 EPIP-1.03 RESPONSE TO ALERT FAGE 4 of 12
- STEP ACTION / EXPECTED RESPONSE RESPONSENOT08TAINE0
- 6. (CONTINUED) b) Direct Security to activate Corporate Emergency Response Team by calling General Office Security IAW Section 1.2.1 of NAPS Telephone Directory NOTE: Callout of rescue and fire personnel is accomplished by AP- 51 , Personnel Injury, and AP: 50 , Fire respectively.
- 7. EVALUATE STATION CONDITIONS:
, a) Unit (s) are NOT affected a) E a unit is affected, eval-by emergency condition uate safe operation of unaf-fected unit.
- 1) Evaluate safety of any operating unit (s) AND
- 2) Consider unit (s) shutdown Consider unit shutdown if if emergency conditions conditions so indicate.
.so indicate
- 8. VERIFY EMERGENCY CENTERS /
FACILITIES: a) All emergency centers and a) GO TO Step 9 of this instruc-facilities - ACTIVATED tion. b) GO TO Step H of this instruction
- 9. VERIFY TSC ESTABLISHED:
a) Check TSC NOT previously a) GO TO Step 10,of this in-activated struction. l 9 1 I _J_ . . ,. . [ ui'4 h4%mp # =" M A= @ , r* .A' - ygo 9 , M G 6 Sete eN@g e w *v - y9mi-s'=- -*wN** --w gge y
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N'JNBER PROCEDURE TITLE REVISION 02 EPIP-1.03 RESPONSE TO ALERT PAGE 5 of 12
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- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 9. (CONTINUED) b) Relieve the Shift Supervisor b) IF no Shif t Supervisor relief as Station Emergency Manager GO T0_ Step 10,of this in-struction and return to Step
- 1) BY: 9 when appropriate.
DATE: TIME: c) If desired, relocate Station I'_ Emergency Manager position to TSC d) Announce Station Emergency Manager name and location to offsite authorities 4 e'/ Verify TSC - ACTIVATED e) Initiate activation of TSC IAW EPIP-3.02 Activation of Technical Support Center.
- 10. VERIFY OSC ESTAS$1SHED:
a) Check OSC NOT previously a) GO TO Step g of this in-activated struction. b) Assign appropriate individual to position of OSC Director c) Activate OSC IAW EPIP-3.03, Activation of Operational Support Center
- 11. VERIFY EOF ESTABLISHED:
a) Check EOF NOT previously a) GO TO Step212,of this in-
. activated instruction.
'g b) Activate EOF IAW EPIP-3,04, Activation of Emergency Operations Facility
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. NUMBER PROCEDURE TITI.E REVISION 02 EPIP-1.03 RESPONSE TO ALERT PAGE 6 of 12 1
- STEP ACTIONMXPECTED RESPONSE RESPONSENOTOBTAINED
- 12. VERIFY EPIP-4.01:
a) Assure EPIP-4.01, Radiological a) Direct Health Physics to l Assessment Director Controlling initiate EPIP-4.01, Radio- { Procedure - ACTIVATED logical Assessment Director j Controlling Procedure,THEN-
]
GO TO Step g. b) Check. status of EPIP-4.01, Radiological Assessment Director Controlling Procedure l c) Verify Onsite Monitoring Team I
- ACTIVATED
- 13. CHECK RADIOLOGICAL CONDITIONS:
a) Radiological conditions a) Confer with Radiological STABLE OR IMPROVING Assessment Director and Emergency Operations Director AND Initiate ' appropriate mitiga-ting actions
- 14. CHECK UNIT CONDITIONS:
a) Reactor plants.- STABLE a) E TSC activated confer with Emergency Operations Director , IF NOT, confer with SRO-On-Call. AND l Initiate appropraite miti-gating actions. ,
- 15. DAMAGE CONTROL: s a) Damage to Station equip-( a) GO TO Step 3 - j ment has been verified
- - .. .. . , , . . -,..-. - . . . - . . - . - ~ . . . ..
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No. 97 O!M M l l NUMBER PROCEDURE TITLE REVISION 02 EPIP-1.03 RESPONSE TO ALERT PAGE 7 of 12
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
^
- 15. (CONTINUED) b) With Emargency Operations b) IF,TSC NOT activated confer and Maiutenance Directors, with senior operations and evaluate extent of damage maintenance personnel onsite.
c) Evalt*:t: fallowing assist-ance requirements
- 1) Offsite Technical
- 2) Additional personnel
- 3) Material and Equipment d) Instruct Emergency Main- d) E NOT available, initiate tenance Director to initiate interim damage control ac- .
EPIP-5.08, Damage Control tivities.
- 16. VERIFY ONSITE CONDITIONS:
a) Evaluation indicates limited a) GO TO Step H. evacuation of buildings or areas - REQUIRED b) Sound ALERT Alarm and make appropriate announement using the plant Gai-Tronics system
- 17. FOLLOW-UP STATE / COUNTY NOTIFICATION:
a) Verify updated Health Physics [. dose assessments complete b) Verify timely follow-up b) Initiate EPII'-2.01, State / County notification Notification of State and
. IAW EPIP-2.01, Notification Local Governments, of State and Local Govern-ments a
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- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINEQ
- 18. FOLLOW-UP NRC NOTIFICATION:
a) Verify follow-up NRC a) Initiate EPIP-2.02, notification IAW, EPIP-2.02, Notification of NRC. Notification of NRC NOTE: Updates to offsite authorities should be provided at approximately 15 minute intervals.
- 19. ADDITIONAL REPORTING:
a) Direct the Emergency Administrative Director to evaluate reporting criteria IAW EPIP-2.03, Reports to Offsite Agencies b) Initiate reporting require-ments of EPIP-2.03, Reports to Offsite Agencies
- 20. VERIFY ACCOUNTABILITY:
a) All personnel accounted for a) Inititate EPIP-5.02, Search IAW EPIP-5.03, Personnel and Rescue. Accountability
- 21. SITE EVACUATION:
~~
a) Radiological Assessment a) GO TO Step 24. Director recommends site evacuation b) Consider the following:
- 1) Onsite dose greater than 1 Rem whole body O_R R greater l than 5 Remthyroid ~~
[ _ ] }~ '[ ,_
- 2) Direction of plume travel /
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. _; ' ' ::_e.za.,, . .:. a w No. 97867210 NUMBER PROCEDURE TITLE REVISION 02 EPIP-1.03 RESPONSE TO ALERT PAGE 9 of 12
- STEP ACTION /EXFECTED RESPONSE RESPONSENOTO8TAINED l
- 22. INITIATE SITE EVACUATION:
- 1) Initiate EPIP-5.05, Site Evacuation
- 23. EVACUATION NOTIFICATIONS:
a) Notify affected counties and Virginia EOC of evacu-ation initiation IAW EPIP-2.01, Notification of State and Local Governments b) Notify NRC Operations Center of evacuation initiation IAW EPIP-2.02, Notification of NRC
- 24. EMERGENCY EXPOSURE:
a) Evaluati n of conditions indi- a) GO To Step 2_5_. 5 cater authorization of emer-gencj radiation exposure limits should be considered - b) Implemen:: EPIP-5.06 Emergency Radiation Exposure Authorization
- 25. BLOCKING AGENT:
a) On recommendation of a) GO TO Step 21 Radiological Assess-ment Director evaluate issuance of Radioiodide blocking agent to onsite personnel if following exist
- 1) Projected onsite total absorbed dose equiva-lent I-131-GREATER THAN 10 Rem
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.a No. 97447219 NUMBER PROCEDURE TITLE REVISION 02 EPIP-1.03 RESPONSE TO ALERT PAGE 10 of 12
- STEP ACTIONNXPECTED RESPONSE RESPONSENOTOBTAINED
- 25. (CONTINUED) 9.R
- 2) Actual onsite total absorbed dose equiv-alent I-131-GREATER THAN 10 Ren b) Direct Radiological Assessment. Director to implement EPIP-5.07, Administration of Radioprotective Drugs
- 26. VERIFY EVENTS:
c) Review EPIP-1.01, Attach-ment 1, Emergency Action Levels, and return to this step , b) Insure additional events b) Initiate station APs, EPs, have NOT occurred or EPIPs to address new events. AND Notify Radiological Assess-ment Director AND l Insure initiation of EPIP-2.01, Notification of State and Local Governments and EPIP-2.02, Notification of NRC c) Check that emergency has c) E escalated, GO TO EPIP-NOT escalated 1.01, Emergency Manager ' Controlling Procedure, Step 6,. 3 . _ , . . . . _ . . _ . _
- - . .. . 4 - , - - . . . . . . . . . . . . . - . - . -
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~
02 l EPIP-1.03 RESPONSE TO ALERT PAGE 11 of 12
- STEP I ACTION / EXPECTED RESPONSE RESPONSE NOTOSTAINED J
s
- 27. CHECK FOR TERMINATION:
a) Verify EALS - NOT EXCEEDED a) IF EALS are still exceeded, GO TO Step 28. AND b) Verify plant conditions - b) Evaluate conditions and GO TO SAFE AND STABLE Step 7. AND c) Onsite and offsite c) Continue monitoring activi-response personnel - NOT ties and GO TO Step E. REQUIRED
, d) GO TO Step p for termination
- 28. CHECK FOR RECLASSIFICATION:
a) Step _2,6,6 indicates event a) GO TO Step 7 of this in-
, severity - REDUCED struction.
b) Reclassify event and GO TO Step p for. procedure - termination
- 29. TERMINATE EPIP-1.03:
a) Verify Recovery Manager ^~ concurrence b) Close out
- 1) Initiate written summary to offsite authorities within 8_ hours
- 2) COMPLETED BY:
DATE: TIME: - __.._A
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No. 97887210 NUMBER PROCEDURE TITLE REVISION j 02 EPIP-1.03 RESPONSE TO ALERT PAGE 12 of 12
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED GO TO EPIP-1.01, Emergency Manager Controlling Pro-cedure, Step 6_
- 30. EMERGENCY TERMINATION:
a) Verify Recovery Manager concurrence b) Close out
- 1) Initiate written summary to offsite authorities within 8 hours
- 2) COMPLETED BY:
DATE: TIME: c) GO TO EPIP-1.01, Emergency Director Controlling Pro- . . 1 cedure, Step 8, I - I i l .
)
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- -auw a w,- s.Os e 3 No.97887200 VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION m EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCEDURE TITLE REVISION 02 EPIP-1.04 RESPONSE TO SITE EMERGENCY PAGE (With No Attachments) 1 of 13 PURPOSE
- 1. To provide guidance to the Station Emergency Manager during the pro-gress of a classified SITE emergency.
USER Station Emergency Manager ENTRY CONDITIONS
- 1. Entry from EPIP-1.01, Emergency Manager Controlling Procedure.
SAFETY RELATED REVISION RECORO REV. 00 PAGE(S): Entire Procedure DATE: 07-02-82 REV. 01 PAGE(S): Entire Procedure DATE: 07-22-82 REV. 02 PAGE(S): Entire Procedure DATE: 05-24-83 REV. PAGE(S): DATE: REV. PAGE(S): . DATE: _ REV. PAGE(S): DATE: REV. PAGE(S): DATE: APPROVAL RECOMMENDED APPROVED DA TE o A 05-24-83 CHAIRMANSTATION NUCLEAR SAFETY AND GPERA TINGTOMMITTEE- - ~~ ~ ' - - - ~ - - - W
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I No. 97847210 NUMBER PROCEDURE TITLE REVISION ' 02 EPIP-1.04 RESPONSE TO SITE EMERGENCY PAGE 2 of 13
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTQBTAINED
- 1. INITIATE PROCEDURE:
a) Declare position of Station Emergency Manager b) BY: DATE: . TIME: NOTE: The Shift Supervisor may be relieved as Stat'on Emergency Manager IAW the NAPS Emergency Plan. s 1
- 2. INPLANT NOTIFICATION:
a) From the Control Room, sound the ALERT Alarm b) Make announcement on plant Gai-Tronics system as follows: ' t
- 1) "A SITE EMERGENCY has been declared" l
- 2) "All Emergency Response personnel report to their assigned stations"
- 3) "All visitors, 2000 and
~- 3000 series badged personnel report to the Security Building"
- 4) "All other personnel report to their Emer-gency Assembly Areas" T
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.m NUMBER PROCEDURE TITLE REVISION 02 1 EPIP-1.04 RESPONSE TO SITE EMERGENCY PAGE 3 of 13
- STEP ACTION / EXPECTED RESPONSE RESPONSENOT08TAINE0
- 2. (CONTINUED) c) Repeat Steps 2a and 2b, THEN continue this in-struction
- 3. ONSITE ACCOUNTABILITY:
a) Initiate EPIP-5.03, Personnel Accountability b) Direct Security to initiate EPIP-5.04, Access Control
- 4. STATE AND COUNTY NOTIFICATION:
a) Initiate EPIP-2.01, Notification of State and Local Governments
- 5. NRC NOTIFICATION:
a) Initiate EPIP-2.02, Notification of NRC NOTE: Updates to offsite authorities should be provided at approximately 15 minute intervals and after significant changes to plant status, radiological data, or meteorological data.
- 6. CALLOUT OF PERSONNEL:
a) Verify Emergency Response a) Direct Security to initiate Personnel - ONSITE EPIP-3.01, Call out of Emer-gency Response Personnel. AND GO TO~~'Stef f ' of~'-~i:his instruction. 5 ogs g g y9 * >G* e**. *W 4e* **=Deta- s% OeM., +M* ahg& S **@@*g -*N-3
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4 % No. 97887210 NUMBER PROCEDURE TITLE REVISION 02 EPIP-1.04 RESPONSE TO SITE EMERGENCY PAGE 4 of 13
- STEP ACTIONMXPECTED RESPONSE RESPONSENOTOBTAINED
- 6. (CONTINUED) b) Direct Security to activate Corporate Emergency Response Team by calling General Office Security IAW Section 1.2.1 of NAPS Telephone Directory NOTE: Callout of rescue and fire personnel is accomplished by AP- 51 , Personnel Injury, and AP- 50 , Fire, respectively.
- 7. EVALUATE STATION CONDITIONS:
a) Unit (s) are NOT affected a) IF a unit is affected, eval-by emergency condition E te safe operation of unaf-facted unit.
- 1) Evaluate safety of any AND operating unit (s)
Consider unit shutdown if
- 2) Consider unit (s) shutdown conditions so indicate.
if emergency conditions so indicate
- 8. VERIFY EMERGENCY CENTERS /
_.. FACILITIES: a) All emergency centers and a) CO TO Step 9,of this instruc-facilities - ACTIVATED tion, b) GO TO Step M of this instruction
)
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.us No. 97487210 NUMBER PROCEDURE TITLE REVISION 02 EPIP-1.04 RESPONSE TO SITE EMERGENCY PAGE 5 of 13
- STEP ACTIONFEXPECTED RESPONSE RESPONSENOTOBTAINED I
- 9. VERIFY TSC ESTABLISHED:
a) Check TSC NOT previously a) GO TO Step 10 of this in-activated struction, b) Relieve the Shift Supervisor b) IF Shift Supervisor relief as Station Emergency Manager NOT available GO TO Step _10, of this instruction and return to Step 9 when app rop ria te.
- 1) BY:
DATE: TIME: c) If desired, relocate Station Emergency Manager position to TSC _ d) Announce Station Emergency Manager name and location to offsite authorities e) Verify TSC - ACTIVATED e) Initiate activation of TSC IAW EPIP-3.02, Activation of Technical Support Center.
.10 . VERIFY OSC ESTABLISHED:
a) Check OSC NOT previously a) GO TO Step 11 of this in-activated struction. b) Assign appropriate indi-vidual to position of OSC Director c) Activate OSC IAU EPIP-3.03, Activation of Operational Support Center s
No.97887210 NUMBER PROCEDURE TITI.E REVISION 02 i EPIP-1.04 RESPONSE TO SITE EMERGENCY PAGE 6 of 13
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTO8TAINED
- 11. VERIFY EOF ESTABLISHED:
a) Check EOF NOT previously a) CO TO Step g of this activated instruction. b) Activate EOF IAW EPIP-3.04, Activation of Emergency Operations Facility
- 12. VERIFY EPIP-4.01:
a) Assure EPIP-4.01, Radiological a) Direct Health Physics to Assessment Director Controlling initiate EPIP-4.01, Radio-Procedure - ACTIVATED logical Assessment Director Controlling Procedure, THEN GO TO Step M. b) Check status of EPIP-4.01~, I I Radiological Assessment Director Controlling Procedure c) Verify Onsite Dose Assess-ment Team (s) - ACTIVATED
- 13. CHECK RADIOLOGICAL CONDITIONS:
a) Radiological conditions - a) Confer with Radiological STABLE OR IMPROVING
~
Assessment Director and Emer-
/ gency Operations Director.
) AND - Initiate appropriate miti-gating actions.
- 14. , CHECK UNIT CONDITIONS: --
i a) Reactor plant (s) - STABLE a) Confer with Emergency Opera-tions Director. l L. _ AND v i
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No.97887219 NUMBER PROCEDURE TITLE REVISION 02 EPIP-1.04 RESPONSE TO SITE EMERGENCY PAGE 7 of 13 5
- STEP ACTIONNXPECTED RESPONSE RESPONSENOTOBTAINED 1 14. (CONTINUED) i '
Initiate appropriate mici-gating actions.
- 15. DAMAGE CONTROL:
a) Damage to Station Equip- a) GO TO Step 6 1_6,,. j ment has been verified b) With Emergency Operations b) F TSC NOT manned confer j and Maintenance Directors, with senior operations i evaluate extent of damage and maintenance personnel onsite. 4 c) Evaluate following assist-ance requirements l 1) Offsite Technical
- 2) Additional personnel j 3) Material and Equipment j .d) Instruct Emergency Main- d) IF NOT available, initiate tenance Director to ini- interim damage control acti-t1 ate EPIP-5.08, Damage vities.
Control i
- 16. VERIFY ONSITE CONDITIONS:
a) Evaluation indicates limited a) GO TO Step ~17 of this in-evacuacion of buildings or struction. areas - REQUIRED b) Sound ALERT Alarm and make appropriate announcement i using the plant Gai-Tronics system
- 17. FOLLOW-UP STATE / COUNTY NOTIFICATION:
a) Verify updated Health Physics dose assessments completed 1
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- STEP ACTION / EXPECTED RESPONSE RESPONSENOTQBTAINED
- 17. (CONTINUED) b) Verify timely follow-up b) Initiate EPIP-2.01, State / County notification Notification of State and IAW EPIP-2.01, Notification Local Governments.
of State and Local Gavern-ments
- 18. FOLLOW-UP NRC NOTIFICATION:
a) Verify follow-up NRC a) Initiate EPIP-2.02, . notification IAW EPIP-2.02, Not.ification of NRC. Notification-of NRC NOTE: Updates to offsite authorities should be provided at approximately 15 minute intervals.
- 19. ADDITIONAL REPORTING:
a) Direct the Emergency Administrative Director to evaluate reporting criteria IAW EPIP-2.03, Reports to Offsite Agencies b) Initiate reporting require-ments of EPIP-2.03, Reports to Offsite Agencies
- 20. VERIFY ACCOUNTABILITY:
a) All personnel accounted for a) Initiate EPIP-5.02, Search IAW EPIP-5.03, Personnel and Rescue. Accountability
- 21. SITE EVACUATION:
a) Radiological Assessment a) GO TO Step M. Director recommends site i evacuation 8
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- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 21. (CONTINUED) b) Consider the following:
1)' Onsite dose greater than 1, Rem whole body OR greater than 5 Rem thyroid exposure
- 2) Characteristics and direction of the plume
- 3) Contamination vs. per-sonnel safety and ex-posure
- 22. INITIATE SITE EVACUATION: .
a) Implement EPIP-5.05, Site Evacuation
- 23. OFFSITE RECOMMENDATIONS:
a) Radiological Assessment a) GO TO Step g. Director recommends near-site sheltering or evac-uation b) Consider the following:
- 1) Site boundry doses of 0.5 Rem to 2 Rem whole body, OR 1, Rem to g Ram thyroid expo-sure
- 2) Characteristics and direction of plume c) GO TO Step H and make appropriate recommend- I ations to offsite agencies -
)
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No.97887210 NUMBER PROCEDURE TITLE REVISION 02 EPIP-1.04 RESPONSE TO SITE EMERGENCY PAGE 10 of 13
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTO8TAINED
- 24. EVACUATION / RECOMMENDATION NOTIFICATIONS:
a) Notify af fected counties and Virginia EOC of evacu-ation initiation IAW EPIP-2.01, Notification of State and Local Governments b) Notify NRC Operations Center of evacuation initiation IAW EPIP-2.02, Notification of NRC
- 25. EMERGPNCY EXPOSURE:
a) Evaluation of conditions indi- a) GO TO Step g cates authorization of emer-gency radiation exposure limits should be considered b) Implement EPIP-5.06. Emergency Radiation Exposure Authorization
- 26. BLOCKING AGENT:
a) On recommendation of a) GO TO Step 27. Radiological Assess-ment Director evaluate issuance of Radioiodide blocking agent to onsite personnel if following exist l l t . l
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-EPIP-1.04 RESPONSE TO SITE EMERGENCY PAGE 11 of 13
- STEP ACTIONMXPECTED RESPONSE RESPONSENOTOSTAINED
- 26. (CONTINUED) ,
- 1) Projected onsite total absorbed dose equiva-lent I-131-GREATER THAN 10 Rem 0,,,R,
- 2) Actual onsite total absorbed dose equiv-alent I-131-GREATER THAN 10 Rem b) Direct Radiological Assessment Director to implement EPIP-5.07, .
Administration of - Radioprotective Drugs
- 27. VERIFT EVEh7S:
a) Review EPIP-1.01, Attach-ment 1, Emergency Action Levels, and return to Step 27b b) Insure additional b) Initiate station APs, EPs, events have NOT occurred or EPIPs to address new events. AhT Notify Radiological Assess-ment Director. 4 AND Insure initiation of-EPIP-2.01, Notification of State and Local Governments and _. EPIP-2.02, Notification of NRC.
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- STEP ACTION /EXPECTEO RESPONSE RESPONSEN0TOBTAINED
- 27. (CONTINUED) c) Check that emergency has c) E escalated, GO TO EPIP-NOT escalated 1.01, Emergency Manager Controlling Procedure, Step 6.
- 28. CHECK FOR TERMINATION:
a) Verify EALS - NOT EXCEEDED a) E EALS are still exceeded, GO TO Step E. AND b) Verify plant conditions - b) Evaluate conditions and GO TO SAFE AND STABLE Step 7. AND i c) Onsite and offsite c) Continue monitoring activi-response personnel - NOT ties and GO TO Step g. REQUIRED . d) GO TO Step 31,for termination
- 29. , CHECK FOR RECLASSIFICATION:
a) Step E indicates event a) CO TO Step 7 of this in-severity - REDUCED struction. b) Reclassify event and GO TO Step 30,for procedure termination
- 30. TERMINATE EPIP-1.04:
a) Verify Recovery Manager concurrence b) Close out
- 1) Initiate briefing of of f-site authorities at EOF and by phone
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NUMBER PROCEDURE TITLE REVISION 02 EPIP-1.04 RESPONSE TO SITE EMERGENCY PAGE 13 of 13
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTO8TAINED
- 30. (CONTINUED)
- 2) Initiate writtan summary to offsite authorities within 8_ hours
- 3) COMPLETED BY:
DATE: TIME: b) GO TO EPIP-1.01, Energency Manager Controlling Pro-cedure, Step 6,
- 31. EMERGENCY TERMINATION:
a) Verify Recovery Manager concurrence b) Close out
- 1) Initiate briefing of
, offsite authorities at .
EOF and by phone
- 2) Initiate written summary to offsite authorities within 8, hours
- 3) COMPLETED BY:
1 l DATE: TIME: c) GO TO EPIP-1.01, Emergency Director Controlling Pro-cedure, Step 8, T _._.___g,
- .'- '. .:,c - _
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*ee . _.4 g No.97087200 VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCEDURE TITLE REVISION 02 EPIP-1.05 RESPONSE TO GENERAL EMERGENCY PAGE (With No Attachments) 1 of 21 PURPOSE
- 1. To provide guidance to the Station Emergency Manager during the pro-gress of a classified GENERAL emergency.
USER Station Emergency Manager ENTRYCONDITIONS .
- 1. Entry From EPIP-1.01, Emergency Manager Controlling Procedure.
i SAFETY 3 ELATED - REVISION RECORD
~
REV. 00 PAGE(S): Entire Procedure DATE: 07-02-82 REV. 01 PAGE(S): Entire Procedure DATE: 07-22-82 . REV. 02 PAGE(S): Entire Procedure DATE: 05-24-83 REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: APPROVAL RECOM ENCEO APPRov'E0 DA TE I
~
- f CHAIRMANSTA TION NUCLEAR SAFETY AND OPERATINlrCOMMITTEE - - - - - - ' - -
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l l No.97887213 i l NUMBER PROCEDURE TITLE REVISION ~ 02 EPIP-1.05 RESPONSE TO GENERAL EMERGENCY PAGE 2 of 21
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 1. . INITIATE PROCEDURE:
a) Declars position of Station Emergency Manager b) BY: DATE: TIME: NOTE: The Shift Supervisor may be relieved as Station Emergency Manager IAW the NAPS Emergency Plan.
- 2. INPLANT NOTIFICATION:
a) From the Control Room, sound the ALERT Alarm b) Make announcement on plant Gai-Tronics system as follows: -
- 1) "A GENERAL EMERGENCY has been declared"
- 2) "All Emergency Response personnel report to their assigned stations"
- l. 3) "All visitors, 2000 and i 3000 series badges l
personnel report to the Security Building" ! 4) "All other personnel l report to their Emer-gency Assembly Areas"
)
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No. 97887219 NUMBER PROCEDURE TITLE REVISION 02 EPIP-1.05 RESPUNSE TO GENERAL EMERGENCY PAGE 3 of 21
- STEP ACTION / EXPECTED RESPONSE RESPONSENOT08TAINED
- 2. (CONTINUED) c) Repeat Steps 2a and 2b.
THEN continue this in- , struction
- 3. ONSITE ACCOUNTABILITY:
a) Initiate EPIP-5.03, Personnel Accountability b) Direct Security to initiate EPIP-5.04, Access Control _ NOTE: The following Steps 4_ thru 11 determine the offsite protective actions to be recommended for various General Emergency situa-tions.
- 4. CORE MELT AND LOCA WITH CONTAINMENT FAILURE IMMINENT OR OCCURING:
a) Following conditions have a) CO TO Step 5_'of this instruc-been met: tion.
- 1) RCS specific activity -
GREATER THAN 3000 uC1/ gram dose equivalent I-131 SR, 5 or more core exit thermocouples - GREATER THAN 2000*F
- 2) Containment High Range RadiationMonitgr-
! GREATER THAN 10 mR/hr __. . . ._ . _ _ _ _ _ _
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No. 97847210 NUMBER PROCEDURE TITLE REVISION 02 EPIP-1.05 RESPONSE TO GENERAL EMERGENCY PAGE 4 of 21
- STEP ACTIONMXPECTED RESPONSE RESPONSE:.'0TOBTAINED
- 4. (CONTI?mED)
- 3) Containment failure imminent as indicated by pressure - GREATER THAN 60 psia and NOT DECREASING E
Shift Supervisor judgc-ment that containment failure has occured b) Determining protective b) Request Radiological Assess-actions: ment Director aid in determi-nation of sheltering recom-L) Determine wind speed and mandations IAW EPIP-4.01, affected sectors Radiological Assessment Director Controlling a) E vind speed LESS Procedure. THAN 2.5 mph recom-mend sheltering out to and including Zone 5 in affected sectors AN'D Recommend evacuatica in Zones 6 thru 10 in affected sectors , AND Recommend evacuation out to and including Zone 5 in unaffected ~~ ~ sectors t
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No. 91087210 NUMBER PROCEDURE TITLE REVISION 02 , EPIP-1.05 RESPONSE TO GENERAL EMERGENCY l PAGE 5 of 21
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 4. (CONTINUED) b) E wind speed. GREATER THAN 2.5 mph recommend sheltering out to and including Zone 10 in affected sectors AND Recommend evacuation out to and including Zone 5 in unaffected sectors c) GO TO Step H
- 5. CORE MELT AND S/G TUBE RUPTUPI WITH STEAM BREAK:
a) Following conditions bve a) GO TO Step 6,of this instruc-been met: tion.
- 1) RCS specific activity-
. GREATER THAN 3000 uCi/ gram ,
dose equivalent I-131 0,,R, 5 or more core exit thermocouples-GREATER THAN 2000*F
- 2) S/G tube rupture flow greater than capacity of two (2) Charging /SI pumps
- 3) Major S/G secondary ~~
depressurization as indicated by one or more S/G's MS lines below MS header by - GREATER THAN 100 psig ~~
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1- -. ..af L~ No. C7887210 i NUMBER PROCEDURE TITLE REVISION
, 02 EPIP-1.05 RESPONSE TO GENERAL EMERGENCY PAGE 6 of 21
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 5. (CONTINUED) b) Determine protective actions b) Request Radiological Assess-and offsite recommend- ment Director aid in determi-ations IAW Step 4.b Page nation of sheltering recom-4 of 21 of this instruction, mendations IAW EPIP-4.01.
THEN Go_ T_0, 0 Step 12. Radiological Assessment Director Controlling Procedure. c) CO TO Step p
- 6. CORE MELT AND LCCA WITH .
CONTAINMENT FAILURE LIKELY: a) Following conditions have a) CO TO Step 1 of this instruc-been met: tion. i
- 1) RCS specific activity-GREATER THAN 3000.0 uCi/
' gram dose equivalent I-131 S.R, -
5 or more core exit thermocouples-GREATER THAN 2000*F
- 2) Containment High Range Radiation Monitgr - _
GREATER THAN 10 mR/hr
- 3) Containment failure is ._
likely as indicated by significantly impaired ECCS and pressure-GREATER THAN 27.75 psia _. i
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NUMBER PROCEDURE TITLE REVISION 02 EPIP-1.05 RESPONSE TO GENERAL EMERGENCY PAGE 7 of 21
- - STEP ACTION / EXPECTED RESPONSE RESPONSEN0TOBTAINED
- 6. (CONTINUED) b) Recommend the following: b) Request Radiological Assess-ment Director aid in determi-
- 1) Evacuation of the popu- nation of evacuation recom-lation within a radius mendations IAW EPIP-4.01, out to and including Radiological Assessment Zone 5 (360*) Director Controlling Procedure.
- 2) Evacuation of the popu-lation out to and includ-ing Zone 10 in downwind and adjacent sectors (671s* total) c) GO TO Step H
- 7. CORE MELT AND LOCA WITH CONTAINMENT FAILURE NOT LIKELY:
a) Following conditions have a) GO TO Step 8,of this been met: instruction.
- 1) RCS specific activity-GREATER THAN 3000.0 uCi/
gramr dose equivalent I-131 AND 5 or rare core exit thermocouples-GREATER _ THMI 2000*F
- 2) Containment High Range Radiation Monitgr -
GREATER THAN 10 mR/hr
- 3) Containment failure is NOT likely as indicated by pressure - LESS THAN 27.75 psia AND DECREASING
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No. 97se7210 , s NUMBER PROCEDURE TITLE REVISION 02 EPIP-1.05 RESPONSE TO GENERAL EMERGENCY (
, PAGE
, 8 of 21 I l l
~ STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED 3, ,
- 7. (CONTINUED)
\'
b) Recommend the following: b) Request Radiological Assess-ment Director aid in determi-
- 1) Evacuation of the popu- nation of evacuation recom-lation within a radius mandations IAW EFIP-4.01,
. out to and including Radiological Assessment Zone 2 (360*) Director Controlling i
Procedure. i
, 2) Evacuation of 'the popu-lacion out to and includ-ins Zone 5 in downvind and adjacent sectors (67h* total)
\'
- 3) Sheltering in Zones 5 out to 10 in downwind
, and adjacent sectors x (67
- total)
\
[- ; c) CO TO Step g
- 8. LOW CONTAINMENT ACTIVITY:
a) Following conditions have a) CO TO Step 9 of this instruc-
> been met: struction.
- 1) RCS specific activity-GREATER 1HAN 3000.0 uCi/
gram dose equivalent 1-131 l t 5 or more core exit thermocouples-GREATER THAN 2000*F
- 2) Containment High Range Radiation Mogitor -
, LESS THAN 10 mR/hr
)
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No. 9784M10 NUMBER PROCEDURE TITLE REVISION 02 EPIP-1.05 RESPONSE TO GENERAL EMERGENCY , PAGE l 9 of 21
- STEP -
ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 8. (CONTINUED) .
- 3) Containment pressure-LESS THAN 17.0 psia AND NOT INCREASING b) Recommend evacuation within b) Request Radiological Assess-a radius out to and including ment Director aid in determi-Zone 2 (360*) nation of evacuation recom-mendations IAW EPIP-4.01, Radiological Assessment Director Controlling Procedure, c) GO TO Step g
- 9. S/G TUBE RUPTURE WITH MS SAFETY LIFT LIKELY:
a) Following conditions have a) GO TO Step 3 of this in-been met: struction.
- 1) RCS specific activity-GREATER THAN 3000.0 uCi/
g dose equivalent I-131 3 5 or more core exit thermocouples - GREATER THAN 2000*F
- 2) S/G tube rupture flow greater than the capacity of one (1) Charging /SI Pump
- 3) Shif t Supervisor judgement that lifting of MS safety valve (s) is likely
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No.97887213 NUMBER PROCEDURE TITLE REVISION 02 EPIP-1.05 RESPONSE TO GENERAL EMERGENCY PAGE 10 of 21
~ STEP ACTION / EXPECTED RESPONSE RESPONSE NOTO8TAINED
- 9. (CONTINUED) b) Recommend the following: b) Request Radiological Assess-ment Director aid in determi-
- 1) Evacuation of the popu- nation of evacuation recom-lation within a radius mandations IAW E?IP-4.01, out to and including Radiological Assessment Zone 2 (360') Director Controlling Procedure.
- 2) Evacuation of 'the popu-
, latien out to at.d includ- ,
ing Zone 5 in downwind
'and adjacent sections (67h* total)
- 3) Sheltering in Zones 5 out to 10 in down vind and adjacent sectors (67
- Total) c) CO TO Step 3
- 10. SIGNIFICANT RELEASE POTENTIAL:
a) Any of the following exist: a) CO'To Step g of this in-struction.
- 1) Projected site boundry doses exceed 2 Rem whole-body or 3 Rem thyroid exposure SR.
- 2) Control of physical security of station lost l '
b) Recommend evacuation within b) Request Radiological Assess- - i a radius out to and includ- ment Director aid in determi-l ing Zone 2 (360') nation of evacuation recom-mandations IAW EPIP-4.01, Radiological Assessment
)
Director Controlling - Procedure.
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.~ NUMBER PROCEDURE TITLE REVISION 02 EPIP-1.05 RESPONSE TO GENERAL EMERGENCY PACE 11 of 21
- STEP ACTION / EXPECTED RESPONSE RESPONSENOT0 STAINED
- 10. (CONTINUED) c) GO TO Step 3
- 11. MISCELLANEOUS EVENTS:
- a) A General Emergency has been
] declared for any reason other than those specifically men- , tiened 0, R, Shift Supervisor / Emergency Manager judgement indicates actions required to protect the health and safety of j the public l
- b) Reconsnend the following
- b) Request Radiological Assess-ment Director aid in determi-
- 1) Sheltering of the popu- nation of sheltering recom-lation within a radius mandations IAW EPIP-4.01, out to and including Radiological Assessment Zone 2 (360*) Director Controlling Procedure
- 2) Sheltering of the popu-
- lation out to and includ-ing Zone 5 in downwind
, and adjacent sectors (671s' total) i i c) GO TO Step 3 l
- 12. STATE AND COUNTY NOTIFICATION:
a) Initiate EPIP-2.01, l Notification of State . l and Local Governments t l 13. NRC NOTIFICATION: l a) Notify NRC Operations Center IAW EPIP-2.02, Notification of NRC
. _ . . . _ - . . _ - - - _ _ _ . , . _ . - - . , . - . , _ - - - - - --- --- . - - .. - _n
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No.97847210 I NUMBER PROCEDURE TITLE REVISION 02 EPIP-1.05 RESPONSE TO GENERAL EMERGENCY PAGE 12 of 21
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTODTAINED I
NOTE: Updates to offsite authorities should be provided at approximately 15 minute intervals and after.significant changes to plant status, radiological data, or meteorological data.
- 14. CALLOUT OF PERSONNEL:
a) Verify Emergency Response a) Direct Security to initiate
- Personnel - GNSITE EPIP-3.01, Call out of Emer-gency Response personeel.
f AND GO TO Step 15 of this instruction b) Direct Security to activate Corporate Emergency Response Team by calling General Office Security IAW Section 1.2.1 of NAPS Telephone Directory i NOTE: Callout of rescue and fire personnel is accomplished by l AP- 51, Personnel Injury / Overexposure and AP 50 , Fire respectively.
- 15. EVALUATE STATION CONDITIONS:
a) Unit (s) are NOT affected a) IF a unit is affected, eval-by emergency condition uste safe operation of unaf-facted unit. . AND
)
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No.97847210 1 NUMBER PROCEDURE TITLE REVISION 02 EPIP-1.05 RESPONSE TO GENERAL EMERGENCY j PAGE 13 of 21
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 15. (CONTINUED)
~
- 1) Evaluate safety of any Consider unit shutdown if operating unit conditions so indicate.
- 2) Consider unit shutdown if emergency conditions so indicate i
- 16. VERIFY EMERGENCY CENTERS / FACILITIES.
a) All emergency centers and a) GO TO Step H of this l facilities - ACTIVATED instruction. b) GO TO Step p of this l i instruction
- 17. VERIFY TSC ESTABLISHED:
a) Check TSC NOT previously a) GO TO Step 3 of this in-activated struction. b) Relieve the Shift Supervisor b) E Shift Supervisor relief as Emergency Ms.asger RT,available GO T0 Step g of this instruction and
- 1) BY: return to Step g when appropriate.
DATE: TIME: c) If desired, relocate Emergency Manager position to TSC d) Announce Station Emergency Man.ager name and location to offsite authorities e) Verify TSC - ACTIVATED e) Initiate activation of.TSC IAW EPIP-3.02, Activation of Technical Support Center.
#M e m + em e se e
- e,ma 4-5
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i No.97847219 NUMBER PROCEDURE TITLE REVISION 02 EPIP-1.05 RESPONSE TO GENERAL EMERGENCY PAGE 14 of 21 i l l - STE! = ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED l ~ l ! 18. VERITY OSC ESTABLISHED: i a) Check OSC NOT previously a) GO TO Step g of this_in-I activated struction. b) Assign appropriate individual to position of OSC Director c) Activate OSC IAW EPIP-3.03, Activation of Operational Support Center
- 19. VERIFY EOF ESTABLISHED:
a) Check EOF NOT previously a) CO TO Step 20 of this activated instruction. b) Activate EOF IAW EPIP-3.04 Activation of Emergency Operations Facility
- 20. VERIFY EPIP-4.01:
a) Check status of EPIP-4.01, Radiological Assessment 4 Director Controlling l i Procedure b) Verify onsite Dose Assess-ment Team (s) - ACTIVATED l c) Verify offsite dose Assess-ment Team (s) - ACTIVATED
' ~
- 21. CHECK RADIOLOGICAL CONDITIONS:
~
l a) Radiological conditions - a) Confer with Radiologini"
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STABLE OR IMPROVING Assessment Director and Emergency Operations Director. AND , Initiate appropriate miti-' s gating actions. )
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- STEP ACTION / EXPECTED RESPONSE RE:PONSENOT08TAINED -
- 22. CHECK UNIT CONDITIONS:
a) Reactor plant (s) - STABLE a) Confer with Emergency Opera-tions Director. AND Initiate appropriate miti-gating actions.
- 23. DAMAGE CONTROL:
a) Camage to station equip- a) GO TO Step H. ment has been verified b) With Emergency Operations b) E TSC NOT manned confer and Maintenance Directors, with senior operations evaluate extent of damage and maintenance person-nel onsite, c) Evaluate following assist-ance requirements
- 1) Offsite Technical
- 2) Additional personnel
.l) Material and Equipment d) Instruct Emergency Mainte- d) g NOT available, initiate nance Director to initiate interim damage control ac-EPIP-5.08, Damage Control tivities.
- 24. VERIFY ONSITE CONDITIONS:
a) Evaluation indicates limited a) CO TO Step 25_ of this in-evacuation of buildings or struction. areas - REQUIRED b) Sound ALERT Alarm and cake appropriate announcement using the plant Gai-Tronics j system
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- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 25. FOLLOW-UP STATE / COUNTY NOTIFICATION:
a) Verify updated Health Physics dose assessments completed b) Verify timely follow-up b) Initiate EPIP-2.01, State / County notification Notification of State and IAW EPIP-2.01, Notification Local Governments. of State and Local Gov.wn; mer ts
- 26. FOLLOW-UP NRC NOTIFICt. TION:
a) Verify follow-up NRC a) Initiate EPIP-2.02, nctification IAW, EPIP-2.02, Notification of NRC. Notification of HRC . NOTE: Updates to offsite authorities should be provided at approximately 15 minute intervals.
- 27. ADDITIONAL REPORTING:
a) Direct the Emergency Administrative Director to evaluate reporting criteria IAW EPIP-2.03, . Reports to Offsite Agencies b) Initiate reporting require- -- ments of EPIP-2.03, Reports to Offsite Agencies
- 28. VERIFY ACCOUNTABILITY:
l a) All personnel accounted for a) Initiate EPIP-5.02, Search I. IAW EPIP-5.03, Personnel and Rescue. Accountability
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I feo.97087213 NUMBER PROCEDURE TITLE REVISION 02 EPIP-1.05 RESPONSE TO GENERAL EMERGENCY PAGE l 17 of 21 i l
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTO8TAINED i 1
- 29. SITE EVACUATION:
a) Radiological Assessment a) GO TO Step M. Director recommends site evacuation b) Consider the following:
- 1) Onsite dose greater than 1, Rem whole body _0_R R greater than 5_ Rem thyroid exposure
. 2) Characteristics and direction of the plume
- 3) Contamination vs. per-
, sonnel safety and ex-posure
- 30. INITIATE SITE EVACUATION:
a) Implement EPIP-5.05, Site Evacuation
- 31. EVACUATION / RECOMMENDATION ,
NOTIFICAITONS: a) Notify affected counties and Virgina EOC of evacuation initiation IAW EPIP-2.01, Notification of State and Local Governments __ b) Notify NRC Operations Center
. of evacuation initiation IAW EPIP-2.02, Notification of NRC
- 32. EMERGENCY EXPOSURE:
a) Evaluation of conditions a) GO TO Step 31 indicates authorization of emergency radiation expo-sure limits should be considered
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f4 97847210 . NUNDER PROCEDURE TITLE REVISION 02 EPIP-1.05 RESPONSE TO GENERAL EMERGENCY PAGE 18 of 21
- STEP ACTION / EXPECTED RESPONSE RESPONSENOT08TAINE0
- 32. (CONTINUED) b) Implement EPIP-5.06, Emergency Radiation Exposure Authorization
- 33. BLOCKING AGENT:
a) On recommendation of a) GO TO Step g. Radiological Assess-ment Director evaluate
- issuance of Radioiodide blocking agent to onsite personnel if following exist:
- 1) Projected onsite total absorbed dose equiva-lent I-131-GREATER THAN 10 Rem OR
.i
- 2) Actual onsite total absorbed dose equiv- '-
alent I-131-GREATER THAN 10 Rem b) Direct Radiological Assessment Director to implement EPIP-5.07, I Administration of Radioprotective lirugs - - l 34. VERIFY EVENTS: ? - l a) Review EPIP-1.01, Attach- ! ment 1, Emergency Action l Levels, AND return to Step 34.b .
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- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 34. (CONTINUED) b) Insure additional b) Initiate station APs, EPs, events have NOT occurred or EPIPs to, address new events.
1 AND Notify Radiologi:al Assess-ment Director. AND + Insure initiation of EPIP-2.01, Notification of State and Local Governments and EPIP-2.02, Notification of
. NRC.
c) Check emergency conditions- c) GO TO Step 4 to verify CHANGED recommendations.
- 1) IF condition - IMPROVED -
GO TO Step 35, 5
- 2) IF condition - DEGRADED -
M TO Step 4_ for reeval-
- uation of recommendations
- 35. CHECK FOR TERMINATION:
a) Verify EALS - NOT EXCEEDED a) IF EALS are still exceeded. GO TO Step g. AND b) Verify plant conditions - b) Evaluate conditions and GO TO SAFE AND STABLE Step 4. AND , c) Onsite and offsite c) Continue monitoring activi-response personnel - NOT ties and GO TO Step 36. REQUIRED d) GO TO Step E to terminate a m.---. .---.m----~..-
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~ STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINEO j
- 36. CHECK FOR RECLASSIFICATION:
a) Step H indicates event a) GO TO Step 4 of this in-severity - REDUCED struction.
/
b) Reclassify event and GO TO Step 3J7,for procedure termination -
- 37. TERMINATE EPIP-1.05:
a) Verify-Recovery Manager concurrence b) Close out
- 1) Initiate briefing of off-site authorities at EOF and by phone
- 2) Initiate written summary to offsite authorities within 8, hours
- 3) COMPLETED BY:
DATE: TIME: c) GO TO EPIP-1.01, Emergency Manager Controlling Pro-cedure Step 6
- 38. EMERGENCY TERMINATION:
a) Verify Recovery Manager concurrence b) Close out
- 1) Initiate briefing of i offsite authorities at ;
- EOF and by phone /
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, , 1 No. 9784M10 l
NUMBER PROCE00RE TITLE REVISION
- 02 EPIP-1.05 RESPONSE TO GENERAL EMERGENCY PAGE 21 of 21
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 38. (CONTINUED)
- 2) Initiate written summary to offsite authorities within .8 hours
- 3) COMPLETED BY:
DATE:
. TIME:
c) GO TO EPIP-1.01, Emergency Dire 2 tor Controlling Pro-cedure Step 8
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No. 97887200 VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCE0l>RE TITLE REVISION 03 EPIP-2.01 NOTIFICATION OF STATE AND LOCAL GOVERNMENTS pAGE (With 2 Attachments) 1 of 16 PURPOSE
- 1. To initially notify state and local governments of the dcclaration of an emergency; AND
- 2. To provide periodic stacas up3:Tes to st.ste and local governments during an emergency; AND
- 3. To notify state and local governments of any change in emergency status. ,
USER Emergency Cou:municator OR, Otacion Emergency Manager. ENTRY CONDITIONS J Any one of the following:
- 1. Emergency is declared; OR
- 2. Approximately 30 minutes have pa Red since last notification;
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- 3. The status of any notification item has changed; OR
- 4. Entry directed by Station Energe Ey Manager.
SAFETY REWED REVISION RECORO REV. 00 PAGE(S): Entire Procedure DATE: 07-02-82 REV. 01 PAGE(S): Entire Procedure DATE: 07-22-82 REV. 02 PAGE(S): Entire Procedure DATE: 09-01-82 ! REV. 03 PAGE(S): Entire Procedure DATE: 05-24-83 REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DAIE: i APPRO AL RECO ENDED APPROVED DA TE C 05-24 l 1
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- c. CHA RMA STA TION NUCLEAR SAFETY- - - - - . . . . - - - - l AND GPERATING COMMITTEE 1
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- STEP ACTION / EXPECTED RESPONSE RESPONSENOT08TAINE0 NOTE: The initial notification of an emergency must be made within 15 minutes following declaration of the emergency..
Follow-up reports of emergency conditions should be sent , approximately every 30 minutes er when W.re are changes in emergency condiciens.
- 1. INITIATE PEOCEDURE:
a) INITIATED BY: . TIME: DATE:
- 2. OBTAIN EMERGENCY REPORT FORM:
a) Attachment 1, Ritport of a) IF NOT attached, THEN obtain Emergency to State and from procedure file. Local Governments, located at back of this procedure
- 3. OBTAIN EMERGENCY STATUS INFORMATION:
a) Obtain information from a) Obtain from Station Emergency status board Manager. b) Record in Items 1 thru 6 ~ ~ of Attachment 1 N0E: Wind direction is always given as the compass point, NOT the . degrees, the wind is blowing from. Example: Wind direction is from the East North East (ENE).
- 4. DETERMINE WIND DIRECTION:
l l a) IF,in F Control Room, obtain a) IF NOT, contact Control Room . from Met. Panel and request data. ,) t g , a m ,.u. .,
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.. NUMBER PROCEDURE TITLE REVISION 03 EPIP-2.01 NOTIFICATION OF STATE AND LOCAL GOVERNMENTS PAGE 3 of 16
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTORTAINED
- 4. (CONTINUED) b) Read wind direction degrees h) IF NOT operable, read " Backup from " Main Tower Upper Wind Tower Wind Direction" Record-Direction" Reccrder, s r.
c) Use wind direction degrees AND Table i to determine con:pasa point wind is blowit.g from TABLE 1 COMPASS COMPASS CCHPASS DEGREES POINT DEGREES POINT DEGREES POINT 0-11 = N 170-191 = S 350-371 = N 12-34 = NNE 192-214 - SSW 372-394 = NNE 35-56 = NE 215-236 = SW 395-416 = NE 57-79 = ENE 237-259 = WSW 417-439 = ENE 80-101 = E 260-281 = W 440-461 = E 102-124 = ESE 282-304 = WNW 462-484 = ESE 125-146 = SE 305-326 = NW 485-506 = SE 147-169 = SSE 327-349 = NNW 507-529 = SSE
~
530-540 = S' l d) Record compass point in l item 7 of Attachment i ! l 1
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- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 5. DETERMINE WIND SPEED:
a) IF in Control Rocra, a) IF NOT, contact Control Room obtain from Met. Panel and request data, b) Read wind Speed from b) IJ NOT operable, read " Backup
" Main Tower Upper Wind Towar Wind Speed" Recorder.
Speed" Racorder. c) Record wird speed in Item 7 of Actachment I
- 6. CHECK RADI0 ACTIVE RELEASE STATUS:
a) Release-HAS OCCURRED a) IF NOT, record "None" in Item
~8 of Attachment 1- '
~
OR AND Release-IS OCCURRING GO TO Step 10,. O,,R, Release-IS PROJECTED
- 7. DETERMINE AFFECTED SECTORS:
a) Use wind direction from Item 1 of Attachment 1 AND Table 4 to determine affected sectors
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, 4 No.97887210 NUMBER PROCEDURE TITLE REVISION 03 EPIP-2.01 NOTIFICATION OF STATE AND LOCAL GOVERNMENTS PAGE 5 of 16
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 7. (CONTINUED)
. TAELE 4, COMPASS CCMPASS POINT AFFECTED SECTORS POIYr AFFECTED SECTORS N Hotel-Juliett-Kilo S Romeo-Alpha-Bravo NNE Juliett-KiloQina SSW _ Alpha-Bravo _ Charlie N3 _KilcQima-Mike SW Bravo-Charlie-Delta ENE WSW Lima _ Mike-November C_harlie-Delta-Echo E _ Mike-November-Papa W Delta-Echo-Foxtrot ESE November-Papa-g,uebec WNW Echo-Foxtrot _ Golf SE P_apa_ quebec-Romeo NW Foxtrot _ Golf-H_otel SSE _ quebec-Romeo-A_lpha NNW Golf-Hotel-Julietc NOTE: Affected Sectors and Zones are recorded using alphanumeric designations. Example: "The affected Sectors and Zones are Bravo 1 and 2, Charlie 1 and 2, and Delta 1 and 2."
- 8. DETERMINE AFFECTED ZONES:
a) Obtain from Station'Emer- a) IF NOT known, assume Zones 1 gency Manager and 2. b) Record affected Sectors and Zones in Item 8_ of Attach-ment 1 l l
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- ' aL No.97847210 l
NUMBER- PROCEDURE TITLE REVISION 03 EPIP-2.01 NOTIFICATION OF STATE AND LOCAL GOVERNMENTS PAGE 6 of 16
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED NOTE: During the initial stages of an emergency, prior to manning the Technic.11 Support Center (TSC), the Radiological Assess-ment Dira: tor will be the senior H.P. member onsite, who will be located in the Contro.1 Room or H.P. of fice. After the TSC in manned, the Radiolegical Assessment Director will be located in the TSC.
- 9. INTORM RADIOLCGICAL . ASSESSMENT DIRECTOR OF MET DATA:
a) Inform Radiological Assessment Director df:
- 1) Wind direction
- 2) Wind speed
- 3) Stability class
- 10. UPDATE STATUS BOARD:
a) E status board is,being a) IF NOT, GO TO next step. maintained, insure following
- updated:
- 1) Wind direction
- 2) Wind speed
- 3) Stability class _
- 4) Affected sectors
- 11. RECORD REMARKS:
a) Cbtain from status board a) Obtain from Station Emergency Manager. l b) E there are any remarks, I record them in Item 9 of I Attachment 1 \
)
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. s No. 97847210 NUMBER PROCEDURE TITLE REVISION 03 EPIP-2.01 NOTIFICATION OF STATE AND LOCAL GOVERNMENTS PAGE 7 of 16
- ' STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 12. EECOR? YOUR FAME AND TITLE:
a) Record in Item 10 of ~
~ Attachment J.
- 13. 03TAIN APPROVAL TO TRANSMIT MESSAGE:
a) Shcw completed Attachment J,to Station Emergency o Manager b) Receive approval to transmit
- 14. TRANSMIT MESSAGE TO STATE AND .
LOCAL GOVEILNMENTS: a) Use Insta-Phone a) IF NOT opereble, use normal station telephone. Call following in order listed:
- 1) Louisa County 9-967-1234
- 2) Spotsylvania County 9-1-582-6384
- 3) State of Virginia 9-1-804-323-2300 Ask for Duty Officer
- 4) Caroline County 9-1-804-633-5400
- 5) Orange County 9-1-672-1234
- 6) Hanover County 9-1-804-798-3241 b) Read Attachment i exactly as written
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No.978472:0 NUMBER PROCEOURE TITLE REVISION 03 EPIP-2.01 NOTIFICATION OF STATE AND LOCAL GOVERNMENTS PAGE 8 of 16
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTO8TAINED 1
- 15. RECORD TIME MESSAGE SENT: l l
a) Reccrd on bottom of Attach- - ment i
- 16. RETAIN ATTACIIMENT. ;
I a) Retain Attachment 1
- 17. INFORM STATION EMERG'ENCY MANAGER:
a) Inform Station Emargency Manager that message was sent
- 18. VERIFT RELEASE STATUS:
a) Item 6 of Attachment a) IF NOT, CO TO Step p. 1 indicates: Release-HAS OCCURRED 0,,R Release-IS OCCURRING pR, Release-IS PROJECTED l 19. INFORM STATE THAT REPORT WILL BE SENT: a) Use State EOC ring down a) IF NOT operable, use normal phone station telephone _ AND Call State EOC at 9-1-804-323-2300, AND i Ask for Duty Officer.
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NUMBER PROCEDURE TITLE REVISION 03 EPIP-2.01 NOTIFICATION OF STATE AND LOCAL GOVERNMENTS PAGE 9 of 16
- STEP
[ ACTION / EXPECTED RESPONSE RESPONSENOT08T.alNED
- 19. (CONTINUED) b) Read folleving message:
"This is VEPCO North Anna Contrcl Roon (or TSC). We will transmit a report of radiologicd eenditions shortis "
c) GG TO Step 21
- 20. INFORM STATE THA'? REPORT WILL NOT BE SENT:
a) Use State EOC ring down a) IF NOT operable, use normal phone station telephone AND Call State EOC at 9-1-804-323-2300, AND Ask for Duty Officer, b) Read following message:
"This is VEPCO North Anna Control Room (or TSC).
Since we have no release of radioactive material, we will not transmic a report of radiological conditions." c) GO TO Step 3J7, I l l
. -. 3 l
. - . . .. . . . . - . . . - - - - . . . - - . . l
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- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT08TAINE0
- 21. OBTAIN RADIOLOGICAL REPORT FORM:
a) Acts.chment 2, Report of a) IF NOT attached t.c this pro-RadiologicaI Conditions to cedure, obtain from procedura. the St. ate, located at the file. back of this procedure NOTE: The initial report of radiological conditions must be trant-mitted to the state as soon as possible following the declar-ation of an emargency involving release of radioactive mater-ial. Follow-up reports should be sent to the state approximately every 30 minutes or when there are changes in radiological conditions. ,
- 22. DETERMINE RELEASE DATA:
a) Obtain from status board a) Obtain from Station Emergency Manager, b) Record in Items 1 thru 4-of Attachment 2 ~
- 23. DETERMINE STABILITY CLASS:
a) IF in Control Room, a) IF NOT, contact Control Room obtain from Met. Panel and request data. b) Read Delta T from " Main b) IF NOT operable, read Sigma Tower Delta T" Recorder. Theta from " Backup Tower Sigma Theta" Recorder, AND AND -- . Use Table 2 to determine Use Table 3 to determine stability class. stability class. 1._ . . . . , -- - ~ ~ - - ~- - -- - - - - - - - O g y . . ae = = -
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No. 97887219 NUMBER PROCEDURE TITLE REVISION 03 EPIP-2.01 NOTIFICATION OF STATE AND LOCAL GOVERNMENTS PAGE 11 of 16
- STEP ACTION / EXPECTED RESPONSE RESPONSENOT08TAINED l
- 23. (CONTINUED)
TABLE 2 DELTA T STABILITY DELTA T STABILITY J'F1 CLASS _ (*F) CLASS
-2.0 to -1.4 = A -0.4 to +1.0 = E
-1.4 to -1.2 = B +1.0 ts +2.8 = F
-1.2 to -1.1 = C +2.8 to +3.0 = G
-1.1 to -0.4 = D TABLE 3 SIGMA THETA STABILITY SIGMA THETA STABILITY (DEGREES) CLASS (DEGREES) CLASS 45.0 to 22.5 = A 7.5 to 3.8 = E 22.5 to 17.5 = B 3.8 to 2.1 = F 17.5 to 12.5 = C i.1 to 0 = G 12.5 to 7.5 = D c) Record stability class in Item 7 of Attachment i d) Obtain wind direction, wind speed, and stability class
. from most recent Attachment 1 completed. Record in item 5 of Attachment 2
- 24. DETERMINE TEMPERATURE:
a) IF in Control Room, obtain a) IF NOT, contact Control Room l Emperature from " Main and request data. j Tower Temperature" Recorder.
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No. 97887219 NUMBER PROCEDURE TITLE REVISION 03 EPIP-2.01 NOTIFICATION OF STATE AND LOCAL GOVERNMENTS PAGE 12 of 16
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED 1
- 24. (CONTINUED) b) Record temperature in Item
)
6_ of Attachment. 2 . .
- 25. DETEP.MINE PRECIPITATION:
i , a) Determine AND record pre-cipitation form in Item 6 of Attachment ,2,
- 26. INFORM RADIOLOGICAL ASSESSMENT DIRECTOR:
a) Inform Radiological Assessment Director of temperature ,A_ND precipitation data
- 27. UPDATE STATUS BOARD:
a) E status board being main- a) IF NOT, GO TO next step. tained, insure temperature and precipitation data updated
- 28. RECORD RADIOLOGICAL DATA:
l a) Obtain from status board a) IF NOT known, record as Tnknown't . _OR Radiological Assessment Director . b) Record in Items 7 through M of Attachment 2
- 29. RECORD RECOMMENDED OFFSITE PROTECTIVE ACTIONS: ...-
l a) Obtain from status board a) Obtain from Station l Emergency Manager. l b) Record in Item M of ..',,,._ Attachment 2. /
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No. 97847213 NUMBER PROCEDURE TITLE' REVISION 03 EPIP-2.01 NOTIFICATION OF STATE AND 1.0 CAL GOVERNMENTS PAGE \ 13 of 16
)
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 30. RECORD STATION CONDITIONS:
a) Obtain from st.atus board a) Obtain from ?tation Emergenc7 l hansgec. b) Include status of following:
- 1) Fuel Failure
- 2) Containment Leakage
- 3) RCS Integrity '
c) Record in Item 16 of ~ Attachment 2
- 31. RECORD YOUR NMfE AND TITLE:
a) Record in Item,17,of Attachment 2
- 32. OBTAIN APPROVAL TO TRANSMIT MESSAGE:
a) Show complaced Attachment 2 to Station Emergency Manager b) Receive approval to transmit
- 33. TRANSMIT MESSAGE TO STATE:
a) Use ringdown phone to state a) IF NOT operable, use normal EOC station telephone AND Call state EOC at 9-1-804-323-2300, AND Ask for Duty Officer. b) Read Attachment 2 exactly as written _ m. _, ~=
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- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 34. RECORD TIME MESSAGE SENT:
a) Record in Item 17 of - Attcchment 2
- 35. RETAIN ATTAC192iT 2:
a) Retain Attachment 2 ,
- 36. INFORM STATION EMERGENCY MANAGER:
t l i a) Inform Station Emergency } Manager that message was sent i ! 37. VERIFY EMERGENCY STATUS: s a) Notification of termination a) E sent, GO TO Step M. of emergency - NOT SENT
- 38. RELIEF:
a) E your relief arrives, a) IF NOT, GO TO Step H. i perform following: l (
- 1) Brief your relief on current status of emergency
- 2) Review last Attachments
! 1,and 2 completed 1
- 3) Transfer this procedure and all completed attach-ments to your relief b) Record relief:
Relieved By: Time: - Date: s 9
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No.97887210 i l l NUMBER PROCEDURE TITLE REVISION 03 EPIP-2.01 NOTIFICATION OF STATE AND LOCAL GOVERhTENTS PAQs \ 15 of 16 l
- STI? ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED 1
- 39. RELOCATION:
a) IF,in TSC, GO TO Step p a) IF NOT in TSC, relocate to
. TSC when TSC is being manned AND
\'
Station Emergency Manager directs you to relocate to TSC.
- 40. DETERMINE EOF STATUS:
a) Eme'rgency Operations Faci- a) IF, EOF manned lity (EOF) - NOT MANNED AhT l ' EOF has assumed responsibi-lity for notification of state and local governments, GO TO Step M.
- 1) GO TO Step M
- 41. ASSUME TSC PHONETALKER DUTIES:
a) Man ringdown phone to EOF b) Maintain Emergency Status Board and Radiological Status Board I
- 42. MAINTAIN EOF COMMUNICATIONS:
a) Keep EOF updated on emergency status
- 43. OBTAIN METEOROLOGICAL DATA:
a) Approximately every 15 minutes, request update of meteorological data from the Control Room j phonetalker
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No. 97887210 NUMBER PPOCEDURE TITLE REVISION 03 EPIP-2.01 NOTIFICATION OF STATE AND LOCAL GOVERNMENTS PAGE 16 of 16
-_=
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED b) Inform EOF AND Radiolo-gical Assessment Director of latest meteorological data c) Record on status boards
- 44. VERIFY EMERGENCY STATUS:
a) Emergency - NOT TERMINATED a) Emergency - TERMINATED
- 1) GO TO Step ,4_2, 2 1) GO TO Step g.
- 45. DETERMINE NEED FOR FOLLOW-UP NOTIFICATION:
a) Status of any information a) IF NOT changed, wait approx-on Attachment l_ or Attach- imately 30 minutes from time ment 2_ - CHANGED last notification form initi-ated. THEN GO TO Step 2.
- 1) GO TO Step 2
- 46. TERMINATE EPIP-2.01:
a) COMPLETED BY: TIME: DATE: b) Forward all completed EPIPs -
- ' - ~
and' attachments to SNSOC
- for review r
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._ ,_ _. a .,. a _ _ _ a __ .__.__ a. .l No. C7s37220 NUMBER A TTACHMENT TITLE REVISION EPIP-2.01 03 REPORT OF EMERGENCY TO STATE AND LOCAL GOVERNMENTS A TTACHMENT PAGE 1 1 of 1 s
MESSAGE: This is 7EPC0 North Anna O co= trol aco= TSC O ter. Sta=4hr for a ratt-cati rottow 4 57 == energency message. Use a Report of Energency form to copy this message. (Conduct a roll-call and check the boxes as each party answers.) QVirginiaStateEOC QOrangeCounty BLouisaCounty Spotsylvania County 0 Banover Cour.sy O Caroline County The energency maassage is as follows: Ites 1. Emergency class: I Notification of Unusual Event Declared at on / / (ll
" Alert Site Emergency (16 br. time) j General Energency
@ Emergency terminated (if checked, go to Ites 9)
Ites I. Assistance requested: lNone (no.) Fire Units from (no.) Police Units from (no.) Rescue Units frca (Other) 1 Ites 3. Zaergency response acticus underway F " None Station moultoring terms dispatched offsite Station emergency personnel called in C(Other) Ites 4 Evacuation of onsite personnel: O No C Yes. Evacuated to Itea $. Prognosis of situastion: [ Improving C Worsening O Seable O (other) Item 6. Release of radioactive material Has NOT occurred and is NOT projacted lHas occurred and is now terminated
, is presently occurring is projected to occur Item 7. Wind direction is from the ; Wind speed is MPR.
Stability class is Item 8. Areas affected are QNone O Sectors and Zones Ites 9. Remarks: Item 10. This is / (name) (position) Please acknowledge receipt of this message (Conduct roll-call and check boxes) O virginia State Ecc Cor==secount? Bt.ouisaCounty Spotsylvania County Q Hanover County Q Caroline County
, This is YEPC0 North Anna O controt ace = 0 Tsc O Ear out at ti=e 1
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No.978*722) NUMBER ATTACHMENT TITLE REVISION EPIP-2.01 03 REPORT OF RADIOLOGICAL CONDITIONS TO THE STATE ATTACHMENT PAGE 2 1 of 1 This is vtPCC North Anna O control aco= 0 Tsc O ror. I hav. a r., ort of radiotosteal conditions. Use a Report of Radiological Conditions form to copy this message. Please inform ' as when your are resoy to copy. (Proceed unen informed). Iten 1. . e of release is O airbor==. rala==ad == *1=vacia= af fe O vacarbar=a-surface spill. Iten 2. Release Q began at . O i= *=ct=* cad ca $=sia == , , . - Item 3. Release duration O a= hr=- O is a=ct== cad == 6* hr=. Item 4. Time between reactor shutdown and time of beginning of release 0 *= hr=- O ta =ac =PP ite=61=- Ites 3. Wind direction is from the . Wind speed is MPH. Stability class is . Item 6. Temperature is *F. Precipitation form is None 0 a41= sleet Q Snow 0 (ocn=r) - Item 7. l TheIodine/NobleGasRatiois0 - O ==k=a =- Item 8. Pro! acted total release equivalent Curies of 1-131 is O curies. O ~- Item 9. Predected total release equivalent Curies of 19-133 is O curia =- Qunsnova. Iten 10. Actual dess rate at the site boundary is O =a/hr- O ==k=c n-Ites 11. Estimated dose rates are O =a/hr == =ica bo==darr. mR/hr at 2 miles. O ==k=a = mR/hr at 3 miles, and i 3A/hr at to siles Iten 12. Prefected total integrated Whole Body dose is 0 -
=a == *ite boundarr.
mR at 2 miles. O ==k=c = 31 at 5 miles, and sa at to miles Iten 13. Profected total integrated Thyroid dose is an at site boundary. mA at 2 miles. O ==k=o = ! 31 at 5 miles, and at at 10 miles 2 g,g,,, I DFM/100cm Iten 14. Actual surface radioactive contamination is Q ,
~@kno en Iten 15. Recommended offsite protective actions:
i O None l Oswelterins in sectors and sones O rv cuation of sectors and zones Cocher Iten 16. Station conditions are as follows: (Give brief status and cause of energency. Use back if needed). i .
\
Iten 17. This is / out at time . (name) (position 1_._ . _ . . . _ . . . . . . . . . . . _ _ _ , _ , __
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' No. 97887200 l VIRGINIA ELECTRIC AND POWER COMPANY
)
NORTH ANNA POWER STATION
)
EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCEDURE TITLE REVISION 02 EPIP-3.01 CALLOUT OF EMERGENCY RESPONSE PERSONNEL PAGE (With No Attachments) 1 of 3 PURPOSE
- 1. To callout station AND corporate emergency response personnel if they are not already at their normal work locations.
USER Security Team Leader ENTRYCONulTIONS
- 1. Initiation directed by the Station Emergency Manager.
SAFETY RELATED REVISION RECORO REV. 00 PAGE(S): Entire Procedure DATE: 07-02-82 REV. 01 PAGE(S): Entire Procedure DATE: 07-22-82 REV. 02 PAGE(S): Entire Procedure DATE: 05-24-83 REV.
.)
PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: APPROVAL RECO ENDED APPROVED DA TE 05-24-83 G CHAIRMANSTATIONNUC EARSAFETY AND OPERATING COMMITTEE _ . ._ __ _ ..__. e , p.- -
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NUMBER PROCEDURE TITLE REVISION 02 'N EPIP-3.01 CALLOUT OF EMERGENCY RESPONSE PERSONNEL PAGE (WITH NO ATTACHMENTS) 2 of 3
- STEP ACTION / EXPECTED RESPONSE RESPONSENOT08TAINE0
- 1. INITIATE PROCEDURE:
a) Initiated By: Time: . Date:
- 2. OBTAIN EMERGENCY PERSONNEL NOTIFICATION LIST:
a) Section 1.2 of the North Anna Power Station Telephone Directory
- 3. NOTIFY EMERGENCY RESPONSE PERSONNEL:
a) Use all available telephones and Security personnel AND make notifications as rapidly as possible b) Call, in order, the individuals listed in the' Emergency Notifi-cation List until at least one individual in each department is reached c) Call following departments in order listed: General Office Security Assistant Station Manager Health Physics Department Operations Department . Technical Services Dept. \
)
. . . . . . . . _ . . . . _. .. . . . _ . . . - - , . .- . ~ . . - . . - - - - - - - - - - - - . .
m a:~ -; No.97847213
-~
NUMBER PROCEDURE TITLE REVISION 02 EPIP-3.01 CALLOUT OF EMERGENCY RESPONSE PERSONNEL PAGE (WITH NO ATTACHMENTS) 3 of 3
- STEP ACTION / EXPECTED RESPONSE RESPONSENOT08TAINEO
- 3. (CONTINUED)
Maintenance Department Security Department Administrative Services Dept. Training Department Quality Control Department NRC Resident Inspector d) Read messages exactly as written in Section 1.2 of the North Anna Power Station ~ Telephone Directory to each individual contacted
- 4. RECORD TIME CALLOUT COMPLETED:
a) Callout of above departments completed at time
- 5. INFORM STATION EMERGENCY MANAGER:
a) Inform Station Emergency Manaher that callout completed
- 6. TERMINATE EPIP-3.01:
a) Completed By: -- - Time: Date: b) Forward EPIP-3.01 to SNSOC for review
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EGn.%,wMexie %Ssaw ' '_- ~ ___ w sa: . a,n i u' - _ s No.97887200 VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCEDURE TITLE REVISION 03 EPIP-3.02 ACTIVATION OF TECHNICAL SUPPORT CENTER PAGE (iJith 10 Attachments) 1 of 6
=
PURPOSE
- 1. To provide guidance to personnel charged with TSC Activation; AND
- 2. To provide guidance to TSC members.
USER Station Emergency Manager AND TSC personnel ENTRY CONDITIONS
- 1. Declaration of Alert, Sice Emergency or General Emergency; AND
- 2. Entry from another EPIP; S.R
- 3. Direction of Station Emergency Manager.
SAFETY 3 ELATED l \ l l l REVISION RECOR0 REV. 00 PAGE(S): Entire Procedure DATE: 07-02-82 - ---- REV. 01 PAGE(S): Entire Procedure DATE: 07-22-82 REV. 02 PAGE(S): Entire Procedure DATE: 03-09-83 - - - l REV. 03 PAGE(S): Entire Procedure DATE: 05-24-83 REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: APPROVAL RECOMM DED APPROVED DA TE l k 05-24-83 Cf CHAIRMANSTA TION NUCLEAR SAFETY
~ ~ '
AND OPERA TING COMMITTEE ^~ ~ ~~ 1
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No. 97847210 ' NUMBER PROCEDURE TITLE REVISION 03 EPIP-3.02 ACTIVATION OF TECHNICAL SUPPORT CETIER PAGE (WITH 10 ATTACHMENTS) 2 of 6
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED NOTE: During normal hours of business, activation of the TSC is the responsibility of the Emergency Administrative Director or his alternace. If callout of emergency response personnel is required, the first person to report to the TSC should implement this procedure.
- 1. INITIATE PROCEDURE:
a) Initiated By: Date: Time:
- 2. ACCOUNTABILITY a) Log TSC personnel on Attach- I ment 1 as they arrive b) Maintain accountability c) Notify Station Security of personnel in TSC NOTE: To switen between Unit 1 and Unit 2 first take the typers - 0FF LINE.
- 3. TYPER SET UP:
a) On alarm modem insure:
- 1) Ready LED-GREEN l 2) Carrier LED-RED . . _ _ . _ _ .
)
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.og. en a me . .. , e-- .*e'e oe-s ,= messe - e -am ne - **pm ==*to auss ap -@ g *g 4 wA9 **- que g men ,, g , esg , ,t =+*W e
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NE. 97027213 NUMBER PROCEDURE TITLE REVISION 03 EPIP-3.02 ACTIVATION OF TECHNICAL SUPPORT CENTER PAGE (WITH 10 ATTACHMENTS) 3 of 6
- STET' ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 3. (CONTINUED) b) On utility modem insure: b) Check powerswitch at rear of set.
- 1) Power LED-ON
- 2) Carrier LED-ON c) On typer insure online/
offline button - NOT depressed d) Select Unit 1 OR Unit 2 on switch box e) Place typer power switch - ON f) On typer side keyboard perform the following in order
- 1) [ ESC]
- 2) [9]
- 3) [3]
- 4) [HI]
g) To verify typer programmed perform the following:
- 1) [ ESC]
i l
- 2) HOLD [BRK]
l SIMULTANEOUSLY PUSH [1]
- 3) Verify - BPYAIF IF NOT, perform following a) Depress OFF LINE a) [ ESC]-
I button to ON LINE position. b) [9] ! l l l
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No.97887210 l I NUMBER PROCEDURE TITLE REVISION l 03 1 EPIP-3.02 ACTIVATION OF TECHNICAL SUPPORT CENTER PAGE (WITH 10 ATTACIDfENTS) 4 of 6
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 3. (CONTINUED) c) {9]
d) (HI] e) GO TO Step 3.f f) Depress Offline Button to Online positon. g) Verify all other front panel buttons - NOT depressed.
- 4. HEAD PHONES:
a) Locate two (2) telephone - head phenes in closet outside Emergency Opera-tions Director's Office b) Connect to jacks on either side of Plant Status Board
- 5. COMMUNICATION:
a) IF. desired, and personnel a) IF NOT, GO TO Step 5.b available, establish com-munication to Control Room via TSC-Control Rm. ringdown phone b) IF,F desired, and personnel b) IF NOT, GO TO Step 6_ available, establish communications to OSC via PBX phone c) Refer to Attachment 10 for Emergency Facility Phone Numbers, i 1 l e a w '+=-P e wM e%
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. , . mu... .. , i. , . . : .- . s. . '. 7. 1 No.97847213 NUMBER PROCEDURE TITLE REVISION 03 EPIP-3.02 ACTIVATION OF TECHNICAL SUPPORT CENTER PAGE (WITH 10 ATTACHMENTS) S of 6
- STEP ACTION! EXPECTED RESPONSE RESPONSENOTOSTAINED
- 6. CHECKLISTS:
a) As each Emergency Manager / Director g alternate arrives in TSC distribute appropriate attachment
- 1) Station Emergency Manager Guideline, Attachment 2, 10
- 2) Emergency Operations Director Guideline, Attachment 3, 10
- 3) Emergency Technical
- Director Guideline, Attachment 4, 10
- 4) Emergency Administrative Director Guideline, Attachment 5, 10
- 5) Emergency Maintenance Director Guideline, -
Attachment 6, 10
- 6) Radiological Assessment -
Director Guideline, Attachment 1. H
- 7) Emergency Communicator Guideline, Attachment 8_,
.LR
- 8) Emergency Procedures Coordinator Guideline, - - - . - . _ - - -
Attachment 9, 10 l r ,
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No. 97887210 NUMBER PROCEDURE TITLE REVISION 03 EPIP-3.02 ACTIVATION OF TECHNICAL SUPPORT CENTER PAGE (WITH 10 ATTACEMENTS) 6 of 6
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 7. VERIFY ACTIVATION:
a) Required TSC personnel a) E required, call out addi-in place tion personnel. GO TO Step
- 8. TERMINATION a) TSC deactivated by Station a) DO NOT terminate until Emergency Manager deactivation complete, b) Close-out
- 1) COMPLETED BY:
DATE: ILE: c) Verify Completion of all Attachments d) Forward EPIP-3.02 and all nine (9) attachments to SNSOC for review i 1 i END 1 l l p-. .* *-m e.
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No. 978 ~7220 NUMBER A TTACHMENT TITLE REVISION EPIP-3.02 03 TECHNICAL SUPPORT CENTER MANNING A TTACHMENT PAGE 1 1 of 2 NOTE: Log perscanel as they arrive and leave for accountability purposes. EMERGENCY POSITION PRINCIPLN ALTERNATE Station Emergency Manager Emergency Operations Director Emergency Technical Director Emergency Maintenance Director - Emergency Administrative Director Radiological Assessment Director Emergency Communicator Emergency Procedures Coordinator ADDITIONAL PERSONNEL Maintenance Support Team Administrative Support Team Technical Support Team Radiological Assessment Team
. l l
No. 97887223 NUMBER A TTACHMENT TITLE REVISION l EPIP-3.02 03 -
, TECHNICAL SUPPORT CENTER MANNING ATTACHMENT PAGE 1 2 of 2 l
.l Miscellaneous Personnel
)
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m.G.ua. ' V.a w as.-c . . _ . ... & . - aL a- . ; a . - :. . ._ reo.e7ee72:a NUMBER A TTACHMENT TITLE REVISION EPIP-3.02 03 STATION EMERGENCY MANAGER GUIDELINE A TTACHMENT PAGE 2 1 of 5 STEP
- ACTION / EXPECTED RESPONSE
- RESPONSE NOT OBTAINED NOTE: This Attachment may be implemented by an alternate individual if Station Emergency Manager position is NOT located in TSC.
- 1. INITIATE EPIP-3.02, ATTACHMENT 2:
a) BY: DATE: TLE:
- 2. EMERGENCY ORGANIZATION:
a) Verify response personnel present or enroute:
- 1) Emergency Operations Director
. 2) Emergency Maintenance .
Director
- 3) Emergency fechnical Director
- 4) Emergency Administrative Director
- 5) Radiological Assessement . . . . - ...
- 6) Emergency Procedures Director
- 7) Emergency Communicator
- 8) OSC Director (at OSC) 4 - +y e -- e.. p w-.
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wJ -A.. . . ._ba . _. -- A. . . - No.97087220 NUMBER A TTACHMENT TITLE REVISION EPIP-3.02 03 STATION EMERGENCY MANAGER GUIDELINE A TTACHMENT PAGE 2 2 of 5 STEP
- ACTION / EXPECTED RESPONSE
- RESPONSE NOT OBTAINED NOTE: Cartain decisions are the sole responsibility of the Station Emergency Manager and the authority to make these decisions shall NOT be delegated.
=
- 3. AUTHORITY:
a) The following decisions shall NOT be delegated:
- 1) Clasification of emergeacy
- 2) Notification of offsite '
s agencies.
- 3) Recommendation of offsite protective measures
- 4) Discontinuance of onsite activities
- 5) Initiation of site evacuacion *
- 6) Restriction of site access
- 7) Authorization of emergency exposure limits
- 8) Contact of VEPC0 management
- 4. OSC: .
a) Ver'ify resources with OSC Director
- 1) Fire Brigade
- 2) First' Aid Team e
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l NUMBER ATTACHMENT TITLE REVISION EPIP-3.02 03 STATION EMERGENCY MANAGER GUIDELINE A TTACHMENT PAGE 2 3 of 5 STEP
- ACTION / EXPECTED RESPONSE
- RESPONSE NOT OBTAINED
- 4. (CONTINUED)
- 3) Damage Control Team
- 4) Search and Rescue Team
- 5) Standby Operations personnel
- 5. COMMUNICATION: ,
a) Assure timely notifi-cation of offsite - authorities NOTE: Actions of procedures may be modified, during emergency conditions, only at the discretion of the Station Emergency Manager.
- 6. DIRECTION:
a) Assure direction of the emergency is conducted IAW EPIP-1.01, Emergency Manager Controlling
. Procedure b) Assure development of and approve additional temporary procedures as required
- 7. RELIEF:
a) Assure suitable arrangements for timely relief of emergency response personnel through Emergency Directors d .
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a -~ .:----a .a ~ a.. . -- - - - - - - - - - l l No. 81887tto l l l NUMBER A TTACHMENT TITLE REVISION EPIP-3.02 03 , i STATION EMERGENCY MANAGER GUIDELINE I A TTACHMENT PAGE j 2 4 of 5 STEP
- ACTION / EXPECTED RESPONSE
- RESPONSE NOT OBTAINED
- 7. (CONTINLTD) t
- 1) Emergency Operations Director
- Operations personnel
- OSC Director
- 2) Emergency Technical Director
- Technical Support Team
- Chemistry Team
- STAS
- 3) Emergency Maintenance Director
- Maintenance Support Team
- Mechanical and Electrical members of Damage Control Team
-Inst. Technician Members of Damage Control Team
- 4) Emergency Administrative Director
- Emergency Procedures Coordinator
- Emergency Communicator
- Administrative Support Team
- Fire Brigade
- First Aid. Team
- Security Team
- Search and Rescue Team
- 5) Radiological Assessment Director
- Radiation Protection j Supervisor _.
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No.97887220 NUMBER ATTACHMENT TITLE REVISION EPIP-3.02 03 STATION EMERGENCY MANAGER GUIDELINE A TTACHMENT PAGE 2 5 of 5 STEP
- ACTION / EXPECTED RESPONSE
- RESPONSE NOT OBTAINED
- 7. (CONTINUED)
- 5) (CONfINUED)
- In Plant Monitoring Team
- Sample Analysis Team
- Personnel Monitoring and Decon Team *
- Onsite Monitoring Team
- Dose Assessment Team
- Offsite Monitoring Teams
- Evacuation Monitoring Teams
- 8. TERMINATE ATTACHMENT 2:
a) Verify TSC - a) IF NOT, return to pre-DEACTIVATED vious steps of this Attach-ment 2 for reference as required. b) Close-out
- 1) COMPLETED BY:
DATE: TIME: c) Affix this Attachment 2 to EPIP-3.02 l 1 i
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No.97887220 NUMBER A TTACHMENT TITLE REVISION ' EPIP-3.02 03 EMERGENCY OPERATIONS DIRECTOR GUIDELINE ATTACHMENT PAGE 3 1 of 3 STEP
- ACTION / EXPECTED RESPONSE
- RESPONSE NOT OBTAINED
- 1. INITIATE EPIP-3.02, ATTACHMENT 3:
a) BY: DATE: . TIME:
- 2. COMMUNICATIONS:
a)'Obtain Control Room Operator a) Obtain Nuclear Training f Trainee from OSC to act as Coordinator from Admin-TSC-Control Room phonetalker istrative Supil ort Team
^
b) Have phonetal r establish b) E NOT operable use any connunications with Control other system operable Room using TSC-Control Room ring down telephone c) Have phonetalker maintain i Plant Status Board d) Update Station Emergency Manager in a rimely manner
- 3. OPERATIONAL STATUSi a) As required, obtain opera-tional status from Control Room personnel
- 4. SUPPORT:
a) Verify availability of opera-tions personnel in OSC b) As required, request addi-tional personnel to support operational activities c) As required, request material AND equipment via Emergency ; Administrative Director .,/ t l 8 usi $ es e a -e .we m--* - w-m soumWe .6qhg *y w
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- ACTION / EXPECTED RESPONSE
- RESPONSE NOT OBTAINED
- 5. DIRECTION:
a) As required, advise OR direct Control Room Personnel in the mitigation of operational events b) As required,' provide status change information and operational recommen-dations to the Station Emergency Manager c) Assure proper usage of station procedures by Operations personnel d) Evaluate safety status of any unaffected units e) Assist in the development of any temporary proced-ures required for con-ducting emergency actions
- 6. RELIEF:
a) Assure suitable arrange-ments for relief of:
- 1) OSC Directc c and Operations personnel in OSC
- 2) Control Room personnel
- 3) Emergency Operations Director
- 7. TERMINATE ATTACHMENT 3:
a) Verify TSC - a) E NOT, return to pre-DEACTIVATED vious steps of this attach-ment 3 for reference as required.
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No. 97017220 NUMBER A TTACHMENT TITLE REVISION EPIP-3.02 03 EMERGENCY OPERATIONS DIRECTOR GUIDELINE A TTACHMENT PAGE 3 3 of 3 STEP
- ACTION / EXPECTED RESPONSE
- RESPONSE NOT OBTAINED
- 7. (CONTINUED) b) Close-out
- 1) COMPLETED BY:
DATE: TIME: c) Affix this Attachment 3 to EPIP-3.02 , U 4 l l l END ,
)
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I \ A.,:,: M 41 ;.u.ua & ss a u m a awa- = < ' Yw._- .. . 6 - - ... . _ l No.97887220 l l [ NUMBER ATTACHMENT TITLE REVISION l EPIP-3.02 03 t , EMERGENCY TECHNICAL DIRECTOR GUIDELINE l ATTACHMENT PAGE l 4 1 of 3 STEP
- ACTION / EXPECTED RESPONSE
- RESPONSE NOT OBTAINED
- 1. INITIATE EPIP-3.02, ATTACHMENT 4:
a) BY: DATE: TIME:
- 2. CRGANIZATION:
a) Verify Technical Support *0btain necessary personnel Team:
- 1) Engineering Supervisor
- 2) STA
- 3) Reactor Engineer
- 4) Engineer (Mechanical) _
- 5) Engineer (Electrical) b) Verify Chemistry Team
- 3. ACTIVITIES:
a) Direct the activities of the following:
- 1) Technical Support Team
- 2) Chemistry Team
9 - u ,. ..c ,. _ .m- . u-_ , , , _,, ___ _, __m_,___,_ ._ no. n s e sso NUMBER A TTACHMENT TITLE REVISION EPIP-3.02 03 EMERGENCY TECHNICAL DIRECTOR GUIDELINE A TTACHMENT. PAGE 4 2 of 3 STEP
- ACTION / EXPECTED RESPONSE
- RESPONSE NOT OBTAINED
- 4. ENGINEERING ANALYSIS:
a) Analyze and aid in de-velopment of solutions to problems in the fol-lowing areas of exper-tise:
- 1) Engineering
- 2) Reactor Physics
- 3) Instrumentation and Control
- 4) Chemistry
- 5. SUPPORT:
a) Provide technical support to the Station Emergency Manager
, 6. PROCEDURES:
a) Assist'in the development of any temporary pro-cedures required for con-ducting emergency actions ! 7. NRC INTERFACE: a) Interface with NRC and aid in resolution of questions concerning license requirements .
- 8. RELIEF:
i a) Assure suitable arrange-ments for relief of: l l
- 1) Technical Support Team )
i 4
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No. 9784722) l NUMBER A TTACHMENT TITLE REVISICN EPIP-3.02 03 EMERGENCY TECHNICAL DIRECTOR GUIDELINE A TTACHMENT PAGE 4 3 of 3 STEP
- ACTION / EXPECTED RESPONSE
- RESPONSE NOT OBTAINED
- 8. (CONTINUED)
- 2) Chemistry Team
- 3) STAS
- 4) Emergency Technical Director
- 9. TERMINATE ATTACHMENT 4:
a) Verify TSC - a) E NOT, return to DC-ACTIVATED previous steps of this Attachment 4 for refe-rence as required. b) Close-out
- 1) COMPLETED BY:
DATE: TIME: . c) Affix this Attachment 4 to EPIP-3.02 l l l 1 EE j i l
No.97887220 NUMBER A TTACHMENT TITLE REVISION EPIP-3.02 03 EMERGENCY ADMINISTRATIVE DIRECTOR GUIDELINE A TTACHMENT PAGE l 1 5 1 of 5 STEP
- ACTION / EXPECTED RESPONSE
- RESPONSE NOT OBTAINED l
1
- 1. INITIATE EPIP-3.02, ATTACHMENT 5:
a) BY: DATE: TIME:
- 2. ORGANIZATION a) Verify Administrative *0btain necessary personnel.
Support Team
- 1) Security Supervisor
- 2) QC Supervisor OR Engineer
- 3) Nuclear Training Coordinator
- 4) Fire Marshal
- 5) Clerks b) Verify Security Team
- 1) Security Shift Supervisor
- 2) Security Officers
- 3) Security Control System Operator
- 4) Administrative Security Officers
- 3. VERIFY TSC:
a) E required, assist in logistics of TSC activation
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- ACTION / EXPECTED RESPONSE -
- RESPONSE NOT OBTAINED
- 4. INTERFACE:
a) Advise Station Emergency Manager on emergency fire protection, security, ade.inistration and logis-tical support b) Verify Emergency Communicator-IAW EPIP-3.02, Attachment 7 c) Verify Emergency Procedures Coordinator IAW EPIP-3.02, Attachment 6_
- 5. DIRECTION:
a) Provide clerical and records support b) Assure TSC accountability IAW EPIP-3.02 c) Direct Security Team on the following: ,
- 1) Personnel account-ability
- 2) Access control
- 3) Station security
- 4) EOF actuation
- 5) Maintain liaison with local law enforcement agencies d) Provide QA review of procedures I
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No.97447220 NUMBER A TTACHMENT TITLE REVISION EPIP-3.02 03 EMERGENCY ADMINISTRATIVE DIRECTOR GUIDELINE A TTACHMENT PAGE 5 3 of 5 STEP
- ACTION / EXPECTED RESPONSE
- RESPONSE NOT OBTAINED
- 6. PROCEDURES:
l a) Assist in the development and review of any tem-porary procedures required for conducting emergency actions
- 7. COORDINATION:
a) Co7rdinate acquisition of equfpment, supplies, and g personnel: ,
- 1) Onsite availability 4
- 2) Offsite thru EOF
- l Record on Resource b) .
Request (Attachment 5, ~ t
)
l Page 5 of 5) c) Assure timely follow up i on logistical items
- 8. RELIEF:
i
; a) Assure suitable arrange-ments for relief of:
....._ ' . .. . 1) Administrative Support . _ .
l \ - Team 1 . _. ..
- 2) Security Support Team l
- 3) Emergency Communicator
- 4) Emergency Procedures
. Coordinator
- 5) Emergency Administrative _ . - __ -__
Director ) 1 _% ea e o e i-,..ae
- 4 a-as *gp **** * *e* *= = = * * * ' * % "'
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- ACTION / EXPECTED RESPONSE
- RESPONSE NOT OBTAINED
- 9. TERMINATE ATTACILMENT 5 a) Verify TSC - a) IF NOT, return to pre-DEACTIVATED vious steps of this Attach-ment 5 fot reference as required.
b) Close-out
- 1) COMPLETED BY:
DATE: TIME: c) Affix this Attachtunt 5 to EPIP-3.02 A 1 4
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No. 97847220 I NUMBER A TTACHMENT TITLE REVISION EPIP-3.02 03 EMERGENCY MAINTENANCE DIRECTOR GUIDELINE A TTACHMENT PAGE 6 1 of 3 STEP
- ACTION / EXPECTED RESPONSE
- RESPONSE NOT OBTAINED
- 1. INITIATE EPIP-3.02, ATTACHMENT 6:
a) BY: DATE: TIME:
- 2. VERIFY ORGANIZATION:
a) Maintenance Support Team *0btain necessary personnel.
- 1) Supervisor Maintenance Services
- 2) Mechanical Supervisor
- 3) Stores Supervisor /
Storekeeper
- 4) Electrical Supervisor b) Verify availability of Main-ter..ance personnel in OSC c) Verify instrument personnel in OSC
- 3. ACTIVITIES:
a) Direct activities of:
- 1) Maintenance Support Team
- 2) Damage Control Team (s)
- 4. SUPPORT:
a) Provide Maintenance Support to Station Emergency Manager b) Provide timely updates on damage control activities
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No.97447220 j NUMBER A TTACHMENT TITI.E REVISION EPIP-3.02 03 EMERGENCY MAINTENANCE DIRECTOR GUIDELINE l A TTACHMENT PAGE 6 2 of 3 STEP
- ACTION / EXPECTED RESPONSE
- RESPONSE NOT OBTAINED
- 5. INTERFACE:
a) Coordinate activities with other departments via Emergency Directors b) Coordir. ate acquisition of equipment, supplies and personnel through the Emergency Administrative Director c) Assure timely follow up ,
- 6. PROCEDURES:
a) Assist in the development , and review of any temporary procedures required for conducting emergency actions
- 7. RELIEF:
a) Assure suitable arrangements for relief of:
- 1) Emergency Support Team
- 2) Damage Control Team (s)
- 3) Maintenance members of Damage Control Team (s)
- 4) Instrumentation members of Damage Control Room
- 5) Emergency Maintenance Director
- 8. TERMINATE ATTACHMENT 6:
a) Verify TSC - DEACTIVATED a) IF NOT, return to ) previous steps of this / Attachment 6 for reference as required. 4 i .
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-*L-No.97087220 NUMBER A TTACHMENT TITLE REVISION EPIP-3.02 03 EMERGENCY MAINTENANCE 'sIRECTOR GUIDELINE A TTACHMENT PAGE 6 3 of 3 STEP
- ACTION / EXPECTED RESPONSE
- RESPONSE NOT OBTAINED
- 8. (CONTINUED) b) Close out
- 1) Completed By:
Date: Time: c) Affix this Attachment 6 to EPIP-3.02 D d
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z m -.s: a- .u. No.97847220 NUMBER A TTACHMENT TITLE REVISION EPIP-3.02 03 RADIOLOGICAL ASSESSMENT DIRECTOR GUIDELINE A TTACHMENT PAGE 7 1 of 4 STEP
- ACTION / EXPECTED RESPONSE
- RESPONSE NOT OBTAINED
- 1. INITIATE EPIP-3.02, ATTACHMENT 7:
a) BY: DATE: TIME:
- 2. VERIFY EPIP-4.01:
. a) EPIP-4.01 - INITIATED a) E NOT, initiate EPIP-4.01.
- 3. VERIFY ORGANIZATION:
a) Radiological Assessment Team
- Obtain necessary personnel.
- 1) Health Physicist ,
- 2) Health Physics Technicians b) Offsite Monitoring Teams (2) c) Radiation Protection Personnel I
- 1) Inplant Monitoring Team
- 2) Sample Analysis Team
- 3) Onsite Monitoring Team
- 4. INTERFACE:
a) Coordinate activities with other departments via Emergency Directors b) Obtain required equipment and supplies via Emergency Admini-strative Director
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- ACTION / EXPECTED RESPONSE
- RESPONSE NOT OBTAINED
- 5. DIRECTION:
m a) Direct activities of the following ,
- 1) Radiological Protection Supervisor ,
- 2) Dose Assessment Team b) Until EOF manned direct following
- 1) Offsite Monitoring Teams
- 2) Evacuation Monitoring Teams c) When EOF manned direct Dose Assessment Team Leader to report to Radiological Assessment Coordinator
- 6. CHECK RELEASES:
a) Obtain status of releases from-process monitors where possible b) Evaluate offsite dose assess-ment information
- 7. SUPPORT:
a) Provide radiological advice to i Station Emergency Director I b) Evaluate emergency exposure criteria c) Provide timely updates on radiologicar conditions l l l - __-. 3
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No.97tS7220 l NUNCER A TTACHMENT TITLE REVISION EPIP-3.02 03 RADIOLOGICAL ASSESSMENT DIRECTOR GUIDELINE A TTACHMENT PAGE 7 3 of 4 STEP
- ACTION / EXPECTED RESPONSE
- RESPONSE NOT OBTAINED
- 8. PROTECTIVE MEASURES:
a) Evaluate radiological condi-tions and make recounnendations for onsite and offsite protec-tive actions to Station Emergency Manager
- 9. DAMAGE CONTROL:
a) Provide RWPs required for damage control , activities
- 10. PROCEDURES:
a) Assist in the development ) of any temporary procedures required for conducting emergency actions
- 11. RELIEF:
a) Assure suitable arrangements for relief of:
- 1) Dose Assessment Teams.
- 2) Offsite Monitoring Teams (2)
- 3) Radiation Protection Personnel
- 4) Radiological Assessment Director s
i
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1 No. 97447220 NUMBER A TTACHMENT TITLE REVISION RADIOLOGICAL ASSESSMENT DIRECTOR GUIDELINE A TTACHMENT PAGE 7 4 of 4 STEP
- ACTION / EXPECTED RESPONSE
- RESPONSE NOT OBTAINED
- 12. TERMINATE ATTACHMENT 7:
a) Verify TSC - DEACTIVATED a) IJF NOT, As required, return to previous steps of this Attachment 7 for reference as required b) Close out
- 1) Complaced By:
Date: Time: c) Affix this Attachment 7 to EPIP-3.02 4 E
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- A TTACHMENT TITLE REVISION EPIP-3.02 03 EMERGENCY COMMUNICATOR GUID"LINE A TTACHMENT PAGE 8 1 of 2 STEP
- ACTION / EXPECTED RESPONSE
- RESPONSE NOT OBTAINED
- 1. INITIATE EPIP-3.02. ATTACHMENT 8:
a) BY: DATE: TLE: NOTE: Emergency Conununicator position moves with that of the Station Emergency Manager.
- 2. VERIFY EOF:
a) EOF - NOT ACTIVITATED a) IF ACTIVATED transmit Essages from TSC/ Control . Room to EOF. AND GO TO Step 5 of Attachment 8_. NOTE: Updates to state and local governments should be made at approx-imately 15 minutes intervals and after significant changes of plant status, radiological data, or meteorological data.
- 3. STATE AND COUNTY NOTIFICATION:
a) Under direction of the Station Emergency Manager, transmit messages IAW EPIP-2.01, Notification of State and Local Governments i _,/ __ _ _ _ _________-___----J
! .n v.:,.: O ...a:n.z%$lxe-Ai&=%.:- ~ u e ~ ~ - v i s s u ~ - %- '-e -- :-A u= o A u =%': s..:?- no.orse72 o NUMBER A TTACHMENT TITLE REVISION EPIP-3.02 03 EMERGENCY COMMUNICATOR GUIDELINE A TTACHMENT PAGE 8 2 of 2 STEP
- ACTION / EXPECTED RESPONSE
- RESPONSE NOT OBTAINED
- 4. NRC NOTIFICATION:
a) Under direction of the Station Emergency Manager, transmit messages IAW EPIP-2.02, Notification of NRC
- 5. VERIFY TSC:
a) IF TSC manned maintain the Ediological Status Board b) Update Status Board Data at 15 minute intervals
- 6. TERMINATE ATTACHMENT 8:
a) Verify TSC - DEACTIVATED a) GO TO Step 2 of Attachment 8. b) Close out
- 1) Completed By:
Date: Time: c) Affix this Attachment 8_ to EPIP-3.02
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No. 97887220 NUMBER A TTACHMENT TITLE REVISION EPIP-3.02 03 EMERGENCY PROCEDURE COORDINATOR GUIDELINE A TTACHMENT PAGE 9 1 of 2 STEP
- ACTION / EXPECTED RESPONSE
- RESPONSE NOT OBTAINED
- 1. INITIATE EPIP-3.02, ATTACHMENT 9:
a) BY: DATE: _ TLE:
- 2. CONTROLLING PROCEDURES:
a) Assist Station Emergency Manager in maintenance of controlling procedures b) Assure appropriate pro-cedures are initiated as required c) Track and hold completed procedures until TSC deactivation
- 3. LOGISTICS:
a) Verify sufficient EPIPs and attachments available in TSC b) Procure additional material via Emergency Administrative Director
- 4. TERMINATION OF ATTACHMENT 9:
a) Verify TSC - DEACTIVATED a) g NOT, return to previous step of this Attachment 9 for reference as required, b) Assist the Station Emergency _ Manager in collection of all procedures used during the emergency l
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No.97b87220 NUMBER ATTACHMENT TITLE REVISION EPIP-3.02 03 EMERGENCY PROCEDURE COORDINATOR GUIDELINE A TTACHMENT PAGE 9 2 of 2 STEP
- ACTION / EXPECTED RESPONSE
- RESPONSE NOT OBTAINED
- 4. (CONTINUED) c) Verify appropriate signatures on procedure and attachments d) Verify procedures properly completed e) Close out
- 1) Completed By:
Date: Time: f) Affix this Attachment 9 to EPIP-3.02 v
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No. 97887330 ......^ NUMBER A TTACNMENTi1TLE REVISION EPIP-3.02 03 EMERGENCY FACILITY PHONE NUMBERS A TTACHMENT PAGE 10 1 of 1 Emergency Work Area: CONTROL ROOM PBX NUMBER: Unit No. 1 Control Room Operator 2512 Unic No. 1 Shift Supervisor 2511 Unit No. 2 Control Room Operator 2522 Unic No. 2 Shift Supervisor 2521 TECHNICAL SUPPORT CCTTER Station Emergency Manager 2914 Health Physics 2252 Technical Services 2263 Operations 2301 Maintenance 2254 1 NRC 2316 OPERATIONAL SUPPORT CDITER Primary OSC 2746 Alternate OSC 2797 EMERCENCY OPERATIONS FACILITY Recovery Manager 2166 SECURITY Secondary Alarm Station (SAS) 2221 Central Alarm Station (CAS) 2249 Shift Supervisor 2224 l OTHER VEPC0 NUMBERS l'
- Vepco Information (Visitot) Center 2919 l-
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h Ed.< ' s > :2.;,y_Q,_ pa%D W[WGMNIRS%r.ct@.wwhy4Pi:% , #gf2d M-Ypse; };v3;7 No. 97887200 VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCEDURE TITLE REVISION 04 EPIP-3.03 ACTIVATION OF OPERATIONAL SUPPORT CENTER PAGE (WITH'3 ATTACHMENTS) 1 of 4 PURPOSE l
- 1. To provide guidance to personnel charged with activation of the OSC.
l l USER Operational Support Center Director i I ENTRYCON0lTIONS
- 1. Declaration of an Alert, Site Emergency or General Emergency; AND
- 2. Entry from other EPIPs; SE
- 3. Direction of the Station Emergency Manager. .
S AFETY 3 ELATED REVISION RECORO REV. 00 PAGE(S): Entire Procedure DATE: 07-02-82 REV. 01 PAGE(S): Entire Procedure DATE: 07-22-82 REV. 02 PAGE(S): Entire Procedure DATE: 09-01-82 REV. 03 PAGE(S): Entire Procedure DATE: 03-09-83 REV. 04 PAGE(S): Entire Procedure DATE: 05-24-83 REV. PAGE(S): DATE: REV. PAGE(S): DATE: APPROVAL REC MENCEO APPROVED DA TE 05-24-83 AIR ANSTATIONNUCiEARSAFETY . ANO OPERATING ~ COMMITTEE- - - - - ---~-
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A a , No. 97887210 NUMBER PROCEDURE TITI.E REVISION 04 EPIP-3.03 ACTIVATION OF OPERATIONAL SUPPORT CENTER r PAGE (WITH 3 ATTACHMENTS) 2 of 4 l l
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED l
l 1. INITIATE EPIP'-3.03: l l a) BY: DATE: TIME:
- 2. LOCATION:
, a) Verify NAPS Maintenance a) Prbceed to alternate OSC ! Bldg. - HABITABLE location in the Emergency l Switchgear Room, Unit One l b) Proceed to primary OSC side, located in the 3rd floor - l conference room of the . Maintenance Bldg. l
. 3. COMMUNICATION:
- l l a) Via the dedicated PBX l telephone, declare OSC
( location to Station i Emerger.cy Manager b) Refer to Attachment 3_, for Emergency Facility l Phone Numbers
- 4. ACCOUNTABILITY:
a) Maintain a listing of personnel as they report to the OSC b) Enter names of personnel in appropriate space of EPIP-3.03, Attachment I c) Report names of OSC personnel to Security for accountability @WMh & M9 et
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ru.97es7sto NUMBER PROCEDURE TITLE REVISION 04 EPIP-3.03 ACTIVATION OF OPERATIONAL SUPPORT CENTER PAGE ('elITH 3 ATTACHMENTS) 3 of 4
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED S. NOTIFICATION:
a) Notify the Station Emergency Manager of OSC activation and relay . the following:
- 1) Number of personnel in each classification
- 2) Supervisors / Foremen present
- 6. PERSONNEL: _
a) Review Attachment 2 - Operational Support Center Director Guideline b) Assure personnel check in when reporting to OSC c) Assure personnel check out when leaving OSC d) Maintain updated listing of personnel on Attachment I for accountability e) Notify Station Emergency Manager on significant manning changes
- 7. DISPATCHING:
a) Dispatch members as re-quired by Station Emergency Manager or his designee
- 8. STATUS: .
a) Verify emergency status in a) IF NOT in effect, GO TO Step effect 9. b) CO TO Step 6 4
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n.--. an_ . ~ . . - . . _ . . + .... .. - ... .. .. .. . . ......s-.u. No. 9788 P210 ' NUMBER PROCEDURE TITLE REVISION 04 EPIP-3.03 ACTIVATION OF OPERATIONAL SUPPORT CENTER PAGE (WITH 3 ATTACHMENTS) 4 of 4
- STEP ACTION / EXPECTED RESPONSE RESPONSENOT08TAINE0
- 9. TERMINATE EPIP-3.03:
a) On direction of Station Manager deactivate the OSC b) Direct personnel in OSC to return to normal station organization , c) Close out
- 1) COMPLETED BY:
DATE: TIME: d) Forward this procedure and attachments to SNSOC for review 4 e.w a . s. . l Q . _. -..-...--- - ---. ~ ~ - - - - - - - - - - - ~ ~ - - - - ~ - - ~*
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no.orea n so i NtiMBER A TTACHMENT TITLE REVISION EPIP-3.03 04 ACTIVATION OF OPERATIONAL SUPPORT CENTER ~ ATTACHMENT PAGE 1 OSC PERSONNEL LIST 1 of 2 OPERATIONS MECHANICAL ELECTRICAL 1. 2. 3. 4. 5. 6. , 7. 8. 9. 10.
- 11.
l 12. 13. 14. 15. j 16. i l 1 l
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Peo. 97447220 , NUMBER A TTACHMENT TITLE REVISION EPIP-3.03 04
~
ACTIVATION OF OPERATIONAL SUPPORT CENTER ATTACHMENT OSC PERSONNEL LIST PAGE 1 2 of 2 i i f i f h IST AID TEAM ~ FIRE BRIGADE INSTRU}DLNT l 1. 2. 3. 4. S. 6. l l 7. , 8.
- 9. -
10. l OTHERS l 1 I D i 1 l
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', m . - No. 97847220 l l NUMBER ATTACHMENT TITLE REVISION , EPIP-3. 03- 04 OPERATIONAL SUPPORT CENTER DIRECTOR GUIDELINE A TTACHMENT PAGE 2 1 of 2 STEP
- Action / Expected Response
- Response Not Obtained
- 1. Initiate EPIP-3.03, Attachment 2 a) By:
Date: Time:
- 2. Verify Organization:
a) Fire Team b) First Aid Team c) Damage Control Teams d) Search and Rescue Team e) Standby Operations Personnel
- 3. Responsibility:
a) Delegate teams listed in Step 2 as requested by the Station Manager or his - designee
- 4. Support: - -
a) Provide timely updates on damage control activities to the Station Manager or his designee
.~ - - 4
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i no. memo l l NUMBER ATTACHMENT TITLE REVISION EPIP-3.03 04 OPERATIONAL SUPPORT CENTER DIRECTOR GUIDELINE A TTACHMENT PAGE 2 2 of 2 o (Continued) STEP
- Action / Expected Response
- Response Not Obtained
- 5. Terminate Attachment 2:
a) Verify OSC - De-activated a) If not, return to previous Steps of this Attachment for reference as required. ! b) Close-out I
- 1. Completed By
Date: Time: c) Affix this Attachment 2 to EPIP-3.03. l l i l e - - - - - - ~w - ,
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., NUMBER A TTACHMENT TITLE REVISION EPIP-3.03 04 DERGENCY FACILITY PHONE NUMBERS A TTACHMENT PAGE 3 1 of 1 Emergency Work Area:
CONTROL ROOM PBX NUMBER: Unit No. 1 Control Room Operator 2512 Unic No. 1 Shift Supervisor 2511 Unit No. 2 Control Room Operator 2522
" tit No. 2 shift Supervisor 2521 -
TECHNICAL SUPPORT CENTER Station Emergency Manager 2914 Health Physics . 2252 Technical Services 2263 Operations 2301 Maintenance 2254 NRC 2316 OPERATIONAL SUPPORT CENTER Primary OSC 2746 Alternate OSC 2797 EMERGENCY OPERATIONS FACILITY Recovery Manager 2166 SECURITY Secondary Alarm Station (SAS) 2221 Central Alarm Station (CAS) 2249 Shift Supervisor 2224 OTHER VEPCO NUMBERS Vepco Information (Visitor) Center 2919 i ( ( 4 8 i
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No.s7sarzoc VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCEDURE TITLE REVISION 04 EPIP-3.04 ACTIVATION OF EMERGENCY OPERATIONS FACILITY PAGE (With 4 Attachments) 1 of 6 PURPOSE
- 1. To provide guidance to personnel performing initial activatibn of EOF.
I USER Two (2) Security Team members ENTRY CONDITIONS
- 1. Declaration of an Alerr, Site Emergency or General Emergency;
- l AND l
- 2. Direction of the Station Emergency Manager through the on-duty Security Shift Supervisor.
SAFSTY 3 ELATED REVISION RECORO REV. 00 PAGE(S): Entire Procedure DATE: 07-02-82 REV. 01 PAGE(S): Entire Procedure DATE: 07-22-82 REV. 02 PAGE(S): Entire Procedure DATE: 09-01-82 REV. 03 PACE (S): Entire Procedure DATE: 03-09-83 REV. 04 PAGE(S): Entire Procedure -... DATE: 05-24-83 REV. PAGE(S): DATE: REV. PAGE(S): DATE: APPROVAL RECOMMEN O APPROVE 0 DA T.E
* /" 05-29-E 3 CHAIRMANSTA TION NUCLEARSAFETY AND OPERA TING COMMITTEE . .~.-- - . ~ . . - . . . - . L.
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[ - No.97887210 \ NUNDER PROCEDURE TITLE REVISION 04 EPIP-3.04 ACTIVATION OF EMERGENCY OPERATIONS FACILITY
- PAGE (WITH 4 ATTACIDfENTS) 2 of 6
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 1. INITIATE EPIP-3.04:
a) BY: DATE: TIME: NOTE: This procedure should be performed by two persons.
. 2. ENTRANCE:
a) Obtain door key to NAPS Training Building Simulator. Maintenance Area and SRAC office from Security Shift Supervisor
- 3. AREA SET-UP:
a) Refer to EPIP-3.04, ! Attachment 1 and 2 for ~ area locations b) Locate the three (3) status boards stored in the SRAC office and place in the
'RAC/RM console area.
NOTE: Maps, manuals, badges, plug-in phone and other emergency supplies are stored in the SRAC office.
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. 04 EPIP-3.04 ACTIVATION OF EMERGENCY OPERATIONS FACILITY PAGE (WITH 4 ATTACHMENTS) 3 of 6
- STEP ACTION / EXPECTED RESPONSE RESPOVSENOTOBTAINED
- 4. COMMUNICATIONS: .
a) Remove phone for security use from emergency supply cabinet in SRAC office and place on wall at entrance to simulator hallway, b) Refer to Attachment 3 for Emergency Facility Phone Numbers.
- 5. SECURITY:
a) Maintain physical control of EOF and Visitors Center until relieved by VEPCO Corporate Security per-sonnel and allow entry to:
- 1) VEPCO EOF Team Members w'ho possess a VEPCO ID with the initials " CERT" affixed to the back, or who are listed in the CERP Manual
- 2) VEPCO employee with Valid ID and approved for access by the Recovery Manager or his designee i 3) Visitors who have positive ID stating both the individ- - . . - - . - . _ . -_. _ . .
ual and organization repre-I sented, and who are listed in CERP Manual or are approved for access by the Recovery Manager or his designee. This shall include repre-( sentatives of federal state and local agencies. l _. _ . . _ _ . . .. . . . . ._.__- . . _ . . . . . . l l 1
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x- , - _. . ..a - x .. No.97847213 NUMBER PROCEDURE TITLE REVISION 04 EPIP-3.04 ACTIVATION OF. EMERGENCY OPERATIONS FACILITY l PAGE l (WITH 4 ATTACEMENTS) 4 of 6 l
- STEP ACT10N/EXPECTE0 RESPONSE RESPONSEN0TOBTAINED a) There will be no re-quirement for visitors to be escorted unless '-
deemed appropriate by the Recovery Manager, his designee or the EOF 3ecurity Supervisor.
- 4) Those individuals who do not meet the above criteria but are approved for access by the Recovery Manager B) Personnel Badging:
- 1) Af ter personnel identification and authorization have been verified, each person will be issued an " EOF Security Identification Badge" that is to be displayed on the person (in the chest area) at all times while in EOF.
- 2) Badge Issuance
.1. Vepco Employees (All) - white colored background (100-199)
- 2. Federal Agency Personnel - blue colored background (200-299)
- 3. State Agency Personnel - green colored background (300-399)
- 4. Local Agency Personnel - yellow colored background (400-499)
- 5. Miscellaneous Persocnel - red colored background (500-599)
{ l 6. PERSONNEL ACCOUNTABILITY
- a) Prior to a person's initial entry to the EOF, security l personnel will record on the " EOF Access Log" (Attachment 4) the following
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. l No.97887210 4,s NUMBER PROCEDURE TITLE REVISION i 04 EPIP-3.04 ACTIVATION OF EMERGENCY OPERATIONS FACILITY PAGE (WITH 4 ATTACEMENTS) 5 of 6
- STEP ACTION / EXPECTED RESPONSE RESP 2NSENOTOBTAINED --
- 1. Badge number issued.
- 2. Name of individual.
- 3. Social Security Number of individual.
1 4. Company / organization represented. - (Vepco, include department)
- 5. Access authorized by (if applicable).
- 6. Whether escort is required.
- 7. Time of entry.
b) Prior to exiting the EOF, all personnel will be required to surrender their," EOF Security Identification Badge" and security personnel will record the time of exit on the " EOF Access Log."
! c) Re-entry to the EOF will require that all personnel request their previously assigned badge number for that day and, if requested by security personnel, produce positive identification. Security personnel will then record the time of re-entry on the " EOF Access Log."
d) Access authorizations and badge number assignments will be valid through 2400 on the day received. Personnel may retain their assigned badge if staying beyond 2400, e) EOF Access Register will be closed-out at 2400 each day (real , time). Personnel staying in the EOF after 2400 will be
- transferred by security to the new log.
f) .n iidicion to the above, all entry and exit to and from the F4 <11~,. be in accordance with established Health Physics
- 4. .) procedures, l
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___ __a ___,3 _ , , _ . , , . , ...a t, No.97887210 NUMBER PROCEDURE TITLE REVISION 04 EPIP-3.04 ACTIVATION OF EMERGENCY OPERATIONS FACILITY PAGE (WITH 4 ATTACHMENTS) 6 of 6
- STEP ACTIONtEXPECTED RESPONSE RESPONSENOTOBTAINED
- 7. TERMINATE:
a) Verify Corporate Security a) IF NOT, GO TO Step 5, personnel have assumed responsibility for EOF Security b) Close out
- 1) COMPLETED BY:
DATE: TIME: c) Forward this procedure to SNSOC for review e m
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NUMBER A TTACHMENT TITLE REVISION EPIP-3.04 04 EMERGENCY OPERATIONS FACILITY ATTACHMENT PAGE 3 WORK AREAS 1 of 1 EMERGENCY WORK AREA: CONTROL ROOM: , PBX NUMBER: Unit No. 1 Control Room Operator 2512 Utiit No.1 Shif t Supervisor 2511 Unit No. 2 Control Room Operator 2522 Unit No. 2 Shift Supervisor 2521 TECHNICAL SUPPORT ' CENTER Station Emergency Manager . 2914 Health Physics 2252 Technical Services 2263 Operations 2301 I Maintenance 2254 NRC - 2316 i OPERATIONAL SUPPORT CENTER Primary OSC 2746 Alternate OSC 2797 EMERGENCY OPERATIONS FACILITY , Recovery Manager 2166 SECURITY j Secondary Alarm Station (SAS) 2221 j Central Alarm Station (CAS) 2249 i Shift Supervisor 2224 OTHER VEPCO NUMBERS s Vepco Information (Visitor) Center 2919
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- No. 97887220 --
I 1 7 . NUMBER A TTACHMENT TITLE REVISION l EPIP-3.04 04 EMERGENCY OPERATIONS FACILITY ATTACHMENT PAGE 4 EOF ACCESS LOG 1 of 1 1 d - d5 i ! l . g.. F T y E 2 5 , l 5 : R 6 E l
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PURPOSE To inicially assess emergency conditions, provide protective measures ree-commendations, establish an emergency organization and direct Health Physics Response to an Emergency. l USER Radiological Assessment Director or Senior Health Physics represen-tation onsite. ENTRY CONDITIONS
- 1. Activation by EPIP - 1.01 i
REVISION RECORO REV. 00 PAGE(S): Entire Procedure DATE: 07-02-82 REV. 01 PAGE(S): Entire Procedure DATE: 07-22-82 REV. 02 PAGE(S): Entire Procedure DATE: 09-01-82 REV. 03 PAGE(5): Entire Procedure DATE: 05-24-83 REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: APPROVAL RECOMMENDED APPROVE 0 OA TE
.f / f 05-24-83
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j CHAIRMANSTATI0h NUCLEARSAFETY AND OPERATING COMMITTEE .
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N3.97847210 * ' NUMBER PROCEDURE TITLE REVISION 03 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PAGE CONTROLLING PROCEDURE 2 of 25 fSTEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
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- 1. INITIATE PROCEDURE:
a) BY: DATE:
- TIME
- 2. CHECK CONDITIONS:
a) The SENIOR HEALTH PHYSICS a) IF,TSC IS, activated, repo*rt individual ONSITE should to the TSC. report to the CONTROL ROOM if the TSC is NOT activated NOTE: During the INITIAL stages of the EMERGENCY the SHIFT SUPERVISOR may assume the position of EMERGENCY MANAGER b) Request BRIEFING with the Emergency Manager to de-termine the existing PLANT CONDITIONS, EMERGENCY ACTION LEVELS (EAL'S) EXCEEDED and the CLASSIFICATION of the EMERGENCY c) Assume the position of RAD-10 LOGICAL ASSESSMENT DIRECTOR and continue with this instruction
- 3. INITIAL ASSESSMENT l a) Upon CLASSIFICATION of an a) If NO actual OR POTENTIAL l
EMERGENCY, an INITIAL ASSESS- 0FFSITE RELEASE has oc-l
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MENT of offsite release must curred, GO TO Step 14. , i - -- be made l_ _._... _. . _ . _ . . _ l _ , .-..s.,.-... ...~..,-r- . . . . . . . . . -- ew
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- N3.97887219 NUMBER PROCEDURE TITLE REVISION 03 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PAGE CONTROLLING PROCEDURE 3 of 25
- STEP --
ACTION / EXPECTED R.*!?ONSE
- RESPONSENOTOBTAINED
- 4. VERIFY EMERGENCY LEVEL a) IF the event is an UNUSUAL a) IF the emergency is an ALERT EVENT, continue with this or GREATER, CO TO Stg 6.
instruction
- 5. EVENT - UNUSUAL EVENT a) If the event is NOT a RADI-a) IF the event is a RADIO- OLOGICAL RELEASE GO TO Step LOGICAL RELEASE, ACTIVATE 14.
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EPIP-4.08, Initial Offsite Release Assessment to access the percent of TECHNICAL SPECIFICATION and return to this Step
- 1) IF,the F normal range moni- 1) IF, normal range monitors tors are ONSCALE and indi- indicate GREATER THM or cate GREATER THAN or EQUAL EQUAL TO 1000% TECH SPEC, TO 100% TECH SPECS, but GO TO Step 6_.
LESS THAN 1000% TECH SPECS, SR, Normal range monitors are OFFSCALE and indicate LESS THAN 1000% TECH SPECS CONFIRM classification . - - - .- -. _ _ . - _ of an UNUSUAL EVENT
- b) REPORT RESULTS immediately to the !mergency Manager and cont;nue with this procedure c) OBTAIN SAMPLE of the effluent c) IF sample cannot be OBTAINED release path return to the beginning of this step using station moni- . -. -
tors to access the release I
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- STEP ACTION / EXPECTED RESPONSE RESPONSENOT08TAINE0
- 5. (CONTINUED)
SR E release terminates, GO TO Step 28.
. d) ANALYZE SAMPLE as per HEALTH PHYSICS procedure H.P. 3.4.1.3 e) Go TO Step J,5 5 for follou up assessment
- 6. EVENT - ALERT SITE OR GENERAL -
a) E the emergency is classified a) E the event is NOT a RADIO-as an ALERT, SITE OR GENERAL LOGICAL RELEASE, GO TO Step EMERGENCY E. AND A radiological release has occurred ,0_R R may potentially occur, continue with this procedure
- 7. EVENT - CONDITION IV LIMITING FAULTS a) E the type of Accident is a a) E type of accident is NOT LIMITING FAULT accident, a LIMITING FAULT GO TO (LOCA, Steam Generator Tube Step M.
Rupture, Main Steam Line Rup-l ture E Fuel Handling Acci- ! dent) continue with this ( instruction i I 8. EVENT - FUEL HANDLING ACCIDENT a) IF Event is a FUEL HAND- a) If EVENT is NOT a Fuel Hand-ENG ACCIDENT, RECOMMEND ling Accident, CO TO Step 9. EVACUATION of the Fuel Building AND/OR affected containment 4
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. s No.9784?210 NUMBER PROCEDURE TITLE REVISION 03 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PAGE CONTROLLING PROCEDURE 5 of 25
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED s.
- 8. (CONTINUED) b) RESTRICT ACCESS until radio-logical assessment can be ,
made c) ASSIGN EPIP-4.06 . PERSONNEL c) Continue with this instruc-MONITORING AND DECONTAMINATION tion if individuals found to the Health Physics staff to non-contaminated. monitor and decontaminate, as necessary, individuals evacu-ated from the accident area d) Activate EPIP 4.08. INITIAL OFFSITE RELEASE ASSESSMENT, to determine offsite consequences of the accident and return to this step e) REPORT RESULTS of the above step to the Emergency Manager f) GO TO Step M
- 9. EVENT - STEAM GENERATOR TUBE RUPTURE a) E the event is a Steam Gen- a) H the event is NOT a Steam erator Tube Rupture REQUEST Generator Tube Rupture GO TO the following INFORMATION Step 3 from the Emergency Manager
- 1) Status of the Air Ejector divert
- 2) The, number of Steam Gen-erstor Relief Valves which have lifted OR may poten-tially lift
- 3) IF relief valves have lifted, length of time valves remained open
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No.97847219 NUMBER PROCEDURE TITLE REVISION 03 EPIP-4.01' RADIOLOGICAL ASSESSMENT DIRECTOR
, PAGE CONTROLLING PROCEDURE 6 of 25
- STEP ACTIONMXPECTED RESPONSE RESPONSENOTOBTAINED
- 9. (CONTINUED) ,
- 4) Status of main steam supply 4) E AFPT is isolated, re-to the Aux 11ary Feedwater lease from this pathway Pump Turbine may be disregarded.
. NOTE: I_F,the =ain steam supply from the leaking steam generator has NOT been isolated, request the Emergency Manager to initiate isolation of the' steam supply.
- 5) Request placement of operation personnel in the Emergency Switchgear Room to report INITIAL readings and any INCREASE OR_ DE-CREASE in the MAIN STEAM MONITORS and the AFPT ex-haust monitors
- 6) Request current Steam Gen-erator Blowdown pathway b) ACTIVATE EPIP 4.08. Initial Offsite Release Assessment and return to this Step c) REPORT RESULTS of the above step to the Emergency Manager s*dum d) RESTRICT ACCESS to the Steam Generator Blowdown Cooler -.. -
_ area, Steam Generator Blow- - - - - . - down Line's, Steam Generator Relief Valve area and the AFPT exhaust area, until a survey confirms no radiological -.-. hazards -
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;::,6L& -.s J g g;s_r" % 32 hk:: ~::= a u:n K .. , imp _ l<_. *~ ._ x _ gas z .:w _ l_ u No. 97387210 NUMBER PROCEDURE TITLE REVISION 03 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PACE CONTROLLING PROCEDURE 7 of 25
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED I
- 9. (CONTINUED) e) E personnel are available e) E personnel are NOT avail-consider ACTIVATION of EPIP- able, consider sampling upon 4.23, Post Accident Sampling arrival of additional man-of Reactor Coolant, to assess power core damage. AND continue with this instruc-tion f) Consider sampling of Steam '
Genarator Blowdown and Main Steam of Affected Unit NOTE: Potential liquid release pathway may occur through the Main Steam Safety Valve. g) GO TO Step E
- 10. EVENT MAIN STEAM LINE RUPTURE a) E a Main Steam Line Rupture a) IF, event is NOT a Main Steam occurs, observe station ven- Line Rupture, GO TO Step 11,. 1 tilation monitors
- 1) E station monitors have 1) E station monitors DO NOT indicated a release indicate a release OR OR E there was primary to IF there was NO primary to secondary leakage PRIOR to secondary leakage PRIOR to l the event the accident, GO TO Sub-l' step ~b.
ACTIVATE EPIP 4.08, ~ Initial Offsite Release Assessment
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ww -.4- - -...s w- s-.a i No. 97887219 NUM86R PROCEDURE TITLE REVISION 03 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PAGE CONTROLLING PROCEDURE 8 of 25 l
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTO8TAINED
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- 10. (CONTINUED) b) REPORT RESULTS to the l Emergency Manager l NOTE: E no initial releases have occurred because of prior primary l co secondary leakage, source term may develop inside contain-ment or may result from Main Steam Relief Valve lifting c) Request from the Emergency
. Manager the following in-
. formation and continue with '
this inntruction t
- 1) Location of Steam Break
- 2) Actual or potential lifting of Main Steam Safety Valves
- 3) IF valves have lifted, length of time valve re-mained open ,
t 4) Status of Auxiliary Feed- 4) E Main Steam supply to l water Pump Turbine (iso- the Auxiliary Feedwater lation) Pump Turbine has been ! isolated, no release will , occur through this pathway 5)' Monitor Reading on Main Steam Monitors and AFPT exhaust monitors d) E manpower is available, d) E manpower is NOT available consider ACTIVATION of EPIP- continue with this procedure 4.22, Post Accident Sampling of Containment Air AND AND Consider activation once man-power is available EPIP 4.23, Post Accident Sampling of Reactor Coolant e) GO TO Step g - g e4 $- ,_ eW 6h@ m'4%**
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a N, , . m , s .;_ . .:: .Q: ^ +1. 2 -. G; '; [ . i . . Peo. 97487210 NUMBER PROCEDURE TITLE REVISION 03 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PAGE CONTROLLING PROCEDURE 9 of 25
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 11. EVENT - LOCA a) E the event is a LOCA, rec- a) H event is NOT a LOCA CO TO ommend EVACUATION of the Step M.
Auxiliary Building and Safe-guards Building, and RESTRICT entry, until survey confirm no radiological hazards with-in these arcas b) Activate EPIP-4.08. Initial b) E N0_ offsite releases have Offsite Release Assessment occurred, continue with this to initially access any instruction offsite release and return to this step c) REPORT RESULTS of the above . Step to the Emergency Manager NOTE: LOCA accident may not initially result in large release, but may produce a large source with a potencial for release from the containment building d) Consider activation of EPIP- d) If manpower is not available, 4.23, Post Accident Sampling continue with this instruct-of Reactor Coolant and EPIP- ion and consider activation 4,22, Post Accident Sampling once manpower is available. of Containment Air when man-power becomes available e) GO TO Step g , 12. EVENT - RADIOLOGICAL RELEASE i a) E the event is a RADIO- a) H event is NOT_a RADIO-LOGICAL RELEASE, continue LOGICAL RELEASE, CO TO with this instruction Step H. l - . .
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- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 12. (CONTINUED) b) ACTIVATE EPIP-4.08, Initial '
Offsite Release Assessment to initially assess offsite releases c) REPORT RESULTS of the above step to Emergency Manager d) REQUEST from the Emergency Manager placement of an in-dividual at the monitor of release pathway to report increase or decrease in ronitor readings
- 13. PROTECTIVE MEASURES a) U the results from Offsite a) U results from Offsite Release Assessment are greater Release Assessment are less than or equal to 50 mR/hr WHOLE-chan 50 mR/hr WHOLE BODY or BODY OR 250 mR/hr THYROID at the 250 m7R hr THYROID at the Site Site Boundary, continue with Boundary, GO TO Step H.
this instruct 1,on b) Obtain from the Emergency b) IF no estimate can be given Manager, an ESTIMATE of assume release will last for DURATION of the RELEASE - 3 hours (hours) c) Determine Projected Dose
- 1) Use the following formula to determine site boundry dose for Whole Body and Thyroid Duration of Release X Site Boundary (mR/hr) = Projected Dose (mR) .
(hours) Dose Rate i ) @ We n. $ $e e , F ppp E$9- a % @ _ _ _ _ m._ _
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No. 97847210 NUMBER PROCEDURE TITLE REVISl0N 03 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PAGE CONTROLLING PROCEDURE 11 of 25
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 13. (CONTINUED) d) E the Projected Dose is d) E PROJECTED DOSE is LESS GREATER THAN OR EQUAL TO THAN 500 mR WHOLE BODY 500 mR WHOLE BODY OR
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OR LESS THAN 1000 mR THYROID GREATER THAN OR EQUAL TO 1000 mR THYROID Inform the Emergency Manager ACTIVATE EPIP 4.07, Protec~ that NO PROTECTIVE MEASURES tive Measures and return to arerRuiredoffsite this step AND GO TO Step M e) Continue with substep a through d,using the dose rate for 2,5 and 10 miles f) Recommend to the Emergency f) E E PROTECTIVE MEASURES are Manager the PROTECTIVE required, GO TO Step M. MEASURES required.0FFSITE AND The DISTANCE PROTECTIVE l MEASURES are required
- 14. EVENT - INJURED CONTAMLNATED ~ ~ ~
INDIVIDUAL , a) g the event is an Injured a) E the event is NOT an In-Contaminated Individual jured Contaminated Indivi- _ dual GO TO Step J5;. 5 AND i I Requires Offsite Medical Treatment ACTIVATE EPIP 4.20 HEALTH PHYSICS ACTIONS for TRANS-PORTATION of CONTAMINATED ~ INJURED INDIVIDUAL M
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tu *.e Luir .s.w .s _ : msnwa .'.ra L - 2:-45 m: ' No. 97887210 NUMBER PROCEDURE TITLE REVISION 03 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PAGE CONTROLLING PROCEDURE 12 of 25
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 14. (CONTINUED)
- 1) Review survey to confirm personnel contamination NOTE: First Aid considerations must be given priority over decontamination of individual
- 2) Insure clothing removal and/ 2) E individual can be l or onsite decontamination deconned, CO To substep 5_.
can NOT be used to remove contamination
- 3) Insure a Health Physics individual is available to accompany the victim
- 4) Recommend to the Emergency
- l Manager transportation of t
the victim to MCV l l 5) If the event was initiated 5) IF other EAL'S were exceeded only for contaminated in- GO TO Step 15. jured individual requiring offsite medical treatment ! AND NO other EAL'S have been Eceeded CO TO Step 3
- 15. FOLLOW-UP ASSESSMENT a) IF TSC is NOT activated a) IF TSC IS activated CO-TO
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continue with this in- Step 17 ---- struction b) One member of the Health Physics group should re-main in the control room to assist the Emergency --
- Manager
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No. 97847210 NUMBER PROCEDURE TITLE REVISION 03 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PAGE CONTROLLING PROCEDURE 13 of 25
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 15. (CONTINUED)
NOTE: E conditions require presence in another location, inform the ' Emergency Manager and report back to the Control Room after completion of task c) E a Radiological Release c) E NO release has occurred has occurred, GO TO stbatep d_.
- 1) OBTAIN if possible SAMPLES 1) E No samples are obtained of the effluent continue with this in-struction using Monitor readings for follow-up assessment
- 2) As time allows, ACTIVATE EPIP-4.03, DOSE ASSESSMENT Controlling Procedure d) Insure dose control individual is available to supply dosi-metry e) Provide. Health Physics coverage as needed, for damage control teams, access control, person-nel monitoring and radio analysis f) E the Emergency has terminated f) E the Emergency has NOT GO TO Step 28 terminated -
pR, E the TSC is NOT manned. Return to Step M i AND Repeat sampling and assess-ment as necessary. - - - - - -
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No. 97447213 NUNDER PROCEDURE TITLE REVISION 03 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PAGE CONTROLLING PROCEDURE 14 of 25
- STEP ACTIDM/ EXPECTED RESPONSE RESP 0MENOTOBTAINED j
- 16. VERIFY RELIEF ,
a) When a more Senior Health a) IF, ,F relief is NOT needed, Physics individual arrives Go TO Step E. onsite , 3 - I_F, relief is needed: l ~
- 1) Brief successor as to the existing plant conditions, offsite release assessment performed AND Health Physics actions currently underway l 2) Announce the change of l position to the Emergency l Manager
- 17. ESTABLISH EMERGENCY ORGANIZATION a) g the Health Physics Emer- a) IF Emergency Organization has gency Organization has not been activated, GO TO Step '
been activated, continue with g. this procedure b) Establish the Dose Assessment b) g manpower is NOT yet avail-ment Team and assign EPIP-4.03, able, continue with this in-Dose Assessment Controlling struction assigning EPIP-4.03 Procedure when manpower becomes avail-able
- c) Establish the position of c) I,F, F manpower is NOT yet avail-Radiatton Protection Super- able, continue with this in-visor and assign E?IP-4.02, struction assigning EPIP-4.03 Radiation Protection Super- when manpower becomes avail-visor Controlling Procedure able. ,
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L_ u.CL ' - wi.,. J - c. rm. 2 No. 97847210 NUMBER PROCEDURE TITLE REVISION 03 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PAGE CONTROLLING PROCEDURE 15 of 25
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 18. OFFSITE ASSESSMENT a) E offsite releases have 0 offsite releases have a) E _N_0 occurred, request from the occurred Emergency Manager an indivi-dual to man the Radiation -
OR Monitor on the release path-way IF there is NO potential for a release AND 0 GO TO Step 20,. Report any increase E decrease in monitor readings b) The following information will be supplied periodical g upon request
- 1) Meteorological Data
- 2) Radiation Monitor System Data
- 3) Sample Analysis Data -
c) Upon receipt of the above data, complete attachment i
- 1) Give attachment 1 to the Dose Assessment Team d) Evaluate the need for OFF-
, SITE MONITORING TEAMS with the Dose Assessment Team Leader NOTE: During a Site or General Emergency a minimum of two monitoring teams should be dispatched for Offsite Monitoring.
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NUMBER PROCEDURE TITLE REVISION 03 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PAGE CONTROLLING PROCEDURE 16 of 25
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTO8TAINED
- 18. (CONTINUED)
NOTE: The funct' ion of plume tracking /offsite monitoring will be the responsibility of the Radiological Assessment Coordinator, opon activation of the EOF
- 1) H EOF is NOT activated and 1) I_FF EOF is activated, GO TO offaite monito, ring teams Step E.
are required, request the Radiation Protection Super-visor to ACTIVATE EPIP-4.16, Offsite Monitoring
- 2) Advise Radiation Protec- 2) _I_f, f adequate manpower is tion Supervisor as to the NOT available reassess the number of teams required need for Offsite Monitor-ing Teams upon arrival of additional manpower AND GO TO Step 20.
- 3) Consult with the Dose
- Assessment Team Leader, the probable exposure levels that may be received by the Offsite Monitoring Teams
- 4) E the Whole Body exposure 4) H exposure rates for to the Offsite Teams may Whole Body OR Thyroid will exceed 10 CFR 20 limits not exceed Haits GO TO ACTIVATE EPIP-4.04, Emer- substep e_ of Step 18.
gency Exposure Limits 3 E Thyroid exposure is ex-pected to exceed 10 REM, ACTIVATE EPIP 5.07 Admini-l stration of Radioprotective i . Drugs s
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NUMBER PROCEDURE TITLE REVISION 03 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PAGE CONTROLLING PROCEDURE. 17 of 25 l
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 18. CONTINUED)
- 5) Inform the Radiation Protection Supervisor of protective clothing and respiratory protection required for Offsite Teams
- 6) Assist the Dose Assessment Team Leader as to the placement of Off. site Moni-toring Teams e) Obtain the latest Offsite e) E Offsite Release Data is Release Assessment Data Sheet NOT available, GO TO Step g from the Dose Assessment Team Leader AND
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Return when data becomes available
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No. 97887210 NUMBER PROCEDURE TITLE REVISION 03 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PAGE j CONTROLLING PROCEDURE 18 of 25 1
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTQBTAINED
- 18. (CONTINUED)
- 1) IF the dose rate Offsite is 1) IF the Dose Race Offsite is greater than or equal to Less Than 50 mR/hr Whole 50 mR/hr Whole Body or 250 Body or 250 mR/hr Thyroid, mR/hr Thyroid continue with GO TO Step M.
this instruction.
- 19. PROTECTIVE MEASURES a) Obtain from the Emergency Man-ager, an Estimate of the DURATION of the RELEASE (hours) b) Determine Projection Dose
- 1) Use the following for-mula to determine site
')
boundry dose for Whole . Body or Thyroid Duration of Release X Site Boundary Dose Rate (mR/hr) = Projected Dose (mR) (hours) c) f the Projected Dose is c) IF Projected Dose is LESS GREATER THAN OT EQUAL TO 500mR _THAN 500 mR Whole Body Whole Body OR OR GREATER THAN OR EQUAL TO LESS THAN 1000 mR Thyroid 1000 mR Thyroid ! ACTIVATE EPIP 4.07, Protec- Inform the Emergency Manager tive Measures and return to that NO PROTECTIVE MEASURES this Step arerRuiredoffsite AND
- GO TO Step Q.
l I i d) Continue with substep a through c_ using dose rates for 2.5, and 10 miles s J
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~ NUMBER PROCEDURE TITLE REVISION 03 EPIP-4.01 RADIOLOGICAL ASS'ESSMENT DIRECTOR PAGE CONTROLLING PROCEDURE 19 of 25 i
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 19. (CONTINUED) e) Recommend to the Emergency e) E NJ PROTECTIVE MEASURES Manager the PROTECTIVE MEAS- are required, GO TO Step H. l URES required 0FFSITE AND The DISTANCE PROTECTIVE MEASURES are required
- 20. EOF ACTIVATION a) E EOF is Activated: a) E EOF has NUT been activated.
GO TO , Step 21. I
- 1) Brief the Radiological Assessment Coordinator as to the existing plant condi-tions, offsite dose projec-tions and current Health Physics actions underway
- 2) Inform Dose Assessment Team Leader to brief Radiological Assessment Coordinator on all Offsite Assessment. -
completed to date and the status and location of off-site monitoring teams. !
- 3) Insure an individual remains '
available in the Radio-logical Assessment area to transmit meteorological, monitor and sample analysis data to the EOF
- 21. ESTABLISH IN-PLANT MONITORING:
a) Instruct Radiation Projection a)Nnomonitoringisneeded, Supervisor to activate EPIP- GO TO substep e_. 4.14, Inplant Monitoring and EPIP-4.15, onsite Monitoring as necessary
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- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 21. (CONTINUED) b) Brief Radiation Projection Supervisor as to existing ,
plant conditions c) Assist in selecting proper c) F no monitoring is needed, monitoring and sampling continue with substep e. areas
~
d) Assist Radiation Protection Supervisor in determining i proper protective gear and _ _. dosimetry. Aid in developing any special precautions necessary for in-plant monitoring ; e) Request from the Radiation Protection Supervisor tech-nical assistance in esta-blishing initial and peri-odic monitoring of TSC and EOF
- 1) Based on survey data and plant conditions establish -
routine for surveys of the Emergency Centers NOTE: IF a radiological release has taken place, notify the Radia-tion Protection Supervisor to resurvey Emergency Centers upon change of plume direction or increaae in release. f) Based on survey data, direct, the establishment of new control points to control the ! spread of contamination and/ or limit exposure )
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No. 97847210 NUMBER PROCEDURE TITLE REVISION 03 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PAGE CONTROLLING PROCEDURE 21 of 25
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 22. ENTRANCE - ACCESS CONTROL AREA a) All planned access into Con- a) IJF entrance is not required trolled areas should require GO TO Step E.
an evaluation of Radiological Hazards prior to entrance b) Assist Emergency Manager in obtaining Health Physics coverage, if necessary c) Consult with the Radiation Protection Supervisor as to the entrance requirements
- 1) Request initiation of a Radiation Work Permit as per the Health Physics Manual for entrance
- 23. RESPIRATORY PROTECTION:
a) Assess results of air sampling b) Recommend evacuation of all non-essential personnel in areas that:
- 1) High airborne activity is 1) Airborne contamination is expected but not measured not suspected, GO TO Step 2_5,. 5
- 2) Airborne activity is 2) Maximum permissible con-greater than 0.25 times centration less than or tuaximum permissible con- equal to 0.25 MFC, GO TO Step centration _255,.
c) For all essential workers assess respiratory protection as needed per EPIP-4.05 Respiratory Protection and return to this step am6**%*e=== s=m e 4. -% e ,ee% -w g , 3 e
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No. 978!7210 NUMBER PROCEDURE TITI.E REVISION 03 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PAGE CONTROLLING PROCEDURE 22 of 25
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 24. DETERMINE THE NECD FOR RADI0 PROTECTIVE DRUGS:
NOTE: Administration of Potassium Iodide Tablets is preferably done prior to exposure, although administration of the drug within 2 hours is considered acceptable a) Activate EPIP 5.07, Admini-stration of Radioprotective
. Drugs to asaass need for use of radioprotective drugs and return co-this step b) H the actual or projected b) E thyroid exposure will be exposure will be GREATER THAN less than 10 Rem GO TO Step 3 EQUAL TO 10 Rem thyroid 21 (without respiratory protec-tion) recommend administration of thyroid blocking tablets c) Request approval from the Emergency Manager to Admin- ,
ister radioprotective drugs, d) Supply of tablets is located d) Alternate supply located at at North Anna Medical Surry Power Station Facilities
- 25. ONSITE EVACUATION OF NON-ESSENTIAL PERSONNEL:
I a) Discuss with Dose Assessment Team Leader, the projected or actual whole body and/or i thyroid exposure onsite from release of radioactive material b) Determino direction of plume c) Determine from Emergency i Manager the probable duration - of release 8
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WCo m' 1 % Awarheggh . . . " .ED .l M-E 2 ' a ' ' 1 s-- 4 e .oreersio NUNDER PROCEDURE TITLE REVISION 03 i EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PAGE CONTROLLING PROCEDURE 23 of 25 STEP . ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED s 25. (CONTINUED) d) I_F, F actual or projected d) E dose is LESS THAN EVACU-exposure onsite is GREATER ATION LIMITS THAN OR EQUAL TO 1, Rem whole body OR
~
_OR E plume is in the direction GREATER THAN OR EQUAL TO ~5 of the evacuation route, Rem Thyroid consider sheltering of non-AND essential workers Plume is NOT in the direction of the evacuation route RECOMMEND EVACUATION of all
. non-essential personnel -
e) Report recoassendation to the Emergency Manager
- 26. EMERGENCY EXPOSURE TO RADIATION WORKERS:
a) Prior to entry into a high a) H entry into high radiation . radiation areas, where whole areas will not cause exceed-body exposure may exceed ance of 10CFR20 exposure 10CFR20 exposure limits, limits GO TO Step H. activate EPIP-4.04, Emergency Personnel Radiation Exposure, and return to this procedure
- 27. DOSIMETRY FOR OFFSITE ASSISTANCE a) IF Offsite Assistance is a) IF Offsite Assistance is NOT required to mitigate the required, GO TO Step g. ~
emergency (fire and/or rescue squads)
- 1) Inform Radiation Protection Supervisor of their arrival 4 at the Station l
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- STEP ACTION / EXPECTED RESPONSE RESPONSENOTO8TAINED
- 27. (CONTINUED)
- 2) Request dosimetry to be supplied at the Security building prior to their entrancs onsite
- 28. VERIFY EMERGENCY:
a) E Emergency condition a) E the Emergency Manager still exists: declares termination of the Emergency, GO TO Step g.
- 1) Return to Step M and direct the repetition of surveys, radiological sampling and/or dose assessment to determine status of the emergency
- 2) Advise the Emergency Manager and the Radiation Protection Supervisor as to the in-creasing or decreasing trends of Emergency
- 29. EVENT TERMINATION:
a) Termination of Emergency de-clared by Emergency Manager 1} Notify Radiation Protection Supervisor and Radiation Assessment Coordinator of termination of Emergency
- 2) Evaluate further use of
~
monitoring team (s) for data collection
- 3) Request review of recovery phase with the Emergency Manager and consider the following:
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No. 97847210 NUMBER PROCEDURE TITLE REVISION f 03 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PAGE CONTROLLING PROCEDURE 25 of 25
- STEP ACTION /EXPECTE0 RESPONSE RESPONSEN0T08TAINE0
- 29. (CONTINUED) a) Access control to out-side contaminated areas b) Return to normal access control, areas through-out site c) Assistance for deconta-mination effort. Health Physics support person-nel and radwaste pack-aging and disposal
- 30. ADMINISTRATION:
a) Initiate replacement of procedure and/or emergency equipment if necessary b) Forward completed proce-dures, release calculations and survey results to the Emergency Manager
- 31. TERMINATE EPIP-4.01: .
a) COMPLETED BY: DATE: TIME:
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- -- '--;a- - - L ' L Poe. 97847320 NUNMR A TTACHMENT TITLE REVISION EPIP-4.01 03 RADIOLOGICAL DATA WORKSHEET A TTACHNENT PAGE 1 1 of 1 DATE: TIME: UNIT f -
a Meteorological Data:_ WIND DIRECTION (from): SECTORS AFFECTED: ,
. WIND SPEED (mph):
PRECIPITATION: STABILITY CLASS: RADIATION MONITORING SYSTEM DATA: MONITOR CPM OR MR/MR VENT VENTA (VG-104) VENT VENTB( PROCESS VENT (GW-102) AIR EJECTOR (SV-121.122) VENT VENT (VG-174) VENT VENTB (VG-175) PROCESS VENT (GW-173) MAIN STEAM ( ) AFPT ( ) CONT. HIGH RANGE _
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o ** Peo. 97f 47200 VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION _. EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCEDURE TITLE REVISION 03 EPIP-4.02 RADIATION PROTECTION SUPERVISOR PACE CONTROLLING PROCEDURE (With No Attachments) 1 of 16 PURPOSE To assist Radiological Assessment Director in establishment of radiation protection program during an emergency and dispatching monitoring teams. USER Assistant Health Physics Supervisor. Health Physicist or Health Physics Technician. ENTRY CONDITIONS Any one of the following :
- 1. Emergency classification of alect.
- 2. Activation by another EPIP.
- 3. Any other time 'the Radiological Assessment Director deems it necessary.
SAFETY RELATED
~ ~
REVISION RECORO REV. 00 PAGE(S): Entire Procedure DATE: 07-02-82 REV. 01 PAGE(S): Entire Procedure DATE: 07-22-82 REv. 02 PAGE(S): Entire Procedure DATE: 09-01-82 , REV. 03 PAGE(S): Entire Procedure DATE: 05-24-83 I REV. PACE (S): DATE: REV. PAGE(S): DATE: ) REV. PAGE(S): DATE: I l APPROVAL RECC ENDE0 APPROVED OA TE l [ 05-24-83 1
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No. 97867210 i ' NUMBER PROCEDURE TITLE REVISION _ 03 EPIP-4.02 RADIATION PROTECTION SUPERVISOR CONTROLLING PROCEDURE PAGE 2 of 16
- STEP ACTION / EXPECTED RESPONSE RESPONSENOT08TAINE0 NOTE: H Health Physics area becomes' uninhabitable, relocate Health Physics staff to the OSC or the Emergency Switchgear Room.
NOTE: Record the sequence of events (i.e., transmission of data,
' dispersement of teams, etc.) as accurately as time allows, incigding time of event and initials.
- 1. INITIATE PROCEDURE:
, a) Initiated By:
Date: Time:
- 2. ESTABLISH COMMUNICATION Upon activation of the TSC, establish communication by:
a) Telephone
- 1) Locate a telephone in work area
- 2) Call the TSC at extension
! 2252 b) Radio b) E radio does not work or cannot be found, obtain a
- 1) Obtain a portable radio radio from operations or from health Physics Office security.
i
- 2) Activate EPIP-4.19. Use of Radios for Health Physics Monitoring l 3) Contact the TSC l
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NUMBER PROCEDURE TITLE REVISION , i 03 l EPIP-4.02 RADIATION PROTECTION SUPERVISOR CONTROLLING PROCEDURE PAGE 3 of 16
- STEP At: TION / EXPECTED RESPONSE RESPONSENOT08TAINiD
- 3. PERFORM ACCOUNTABILITY a) Perform accountability as per EPIP 5.03, Personnel Accountability b) Report Health Physics readiness to the Radio-logical Assessment Director
. 1) Report the number of H.P. 1) F minimum number of person-personnel onsite (minimum nel are not available, acti-of 1,4,upon 4 Alert classifi- vate callout of the H.P. per-cation) sonnel, as necessary.
- 4. DETERMINE PLANT STATUS a) Request briefing with the Radiological Assessment Director as to the plant-status, assistance re-quired and Emergency classification 5 '. ESTABLISH DOSE CONTROL a) Insure individual is available a) IJF individual is stationed at to man dose control station dose control, GO TO Substep c b) IF dose control station be- b) IT dose control is habitable, comes uninhabitable consider continue with this instruc-relocation to the OSC tion.. - .--
- 1) Place a supply of TLD i ribbons in the annealing oven to minimize residual dose on ribbons
- 2) The uanual TLD reader may be removed to another
- location 4- _ .. .L .. .- - - . - _ . . , -- - - - - - - -- ---------1 .m~ ~ _% -
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re.. ornins - NUMBER PROCEDURE TITLE REVISION 03 EPIP-4.02 RADIATION PROTECTION SUPERVISOR CONTROLLING PROCEDURE PACE 4 of 16
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTORTAINED
- 5. (CONTINUED) s c) Request dose control indivi-dual to maintain exposure records and issue dosimetry as per H.P. procedures, H.P.
3.1.1 and H.P. 3.1.2
- 6. ACTIVATE INPLANT MONITORING IF,need for inplant monitoring IF monitoring teams NOT requir-is determined: ed. GO TO Step 1 a) Request from Radiological Assessment Director:
- 1) Location of required monitoring
- 2) Type of surveys required b) Request assessment of poss -
ible Radiological hazards in in area of requested surveys
'c) Activate EPIP-4.14, Inplant Monitoring d) Select 2 individuals if enter-ing an area suspectsd to be GREATER THAN or EQUAL TO 1,000 0 mR/HR
- 1) Only 1 individual must be a I.P. technician l
e) Advise monitoring team as to the location and surveys required v .-
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. NUMBER PROCEDURE TITI.E REVISION 03 EPIP-4.02 RADIATION PROTECTION SUPERVISOR CONTROLLING PROCEDURE PAGE 5 of 16
- STEP ACTION /EXPECTE0 RESPONSE - RESPONSEN0TORTAINED
- 6. (CONTINUED) f) Using information from the above substep b, determine protective gear required:
- 1) respirators
- 2) protective clothing
- 3) dosimetry j g) Suggest routes of entry that may reduce exposure h) Dispatch team (s)
- 1) Upon receipt of survey information, transmit data to the Radiologi-cal Assessment Director
- 7. ACTIVATE ONSITE MONITORING NOTE: Onsite monitoring teams should b'e' dispatched upon Alert c'.assification, as specified by Radiological Assessment Director.
IF need for onsite monitoring ,IJ,onsite monitoring NOT re-is determined: quired CO TO Step 8. a) Request from Radiological Assessment Director the location of desired moni-toring and the surveys re-quired i l l l I *1
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_ . _ . . , ~ a _ __ . a . n.. ,. _ . . . . , _. - No.97847210 ' NUMBER PROCEDURE TITLE REVISION I 03 EPIP-4.02 " RADIATION PROTECTION SUPERVISOR CONTROLLING PROCEDURE PACE 6 of 16
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTO8TAINED I
- 7. (CONTINUED) b) Request from the Radiological Assessment Director an evalua-
. tion of radiological hazards in area of requested surveys
- 1) If air samples are required 1) E no vehicles are avail-vehicle should be obtained able, consider the use of to pt.wer portable air the self-contained battery sampler powered air samplers, c) If transportation is required assist in obtaining a vehicle
- 1) IF,,necessary, request assistance from Radio-logical Assessment Director d) Activate EPIP-4.15, Onsite -
Monitoring e) Select 2_ individuals per e) 1 individual may be dispatch-team only I need be a H.P. ed if suspected radiation technician levels are LESS THAN 1000 mR/HR. f) Use information from above substep b_ to determine pro-tactive gear required: b
- 1) respirators
- 2) protective clothing
- 3) dosimetry g) Dispatch monitoring team (s) h) Establish radio communication h) Continue with this instruc- ,
with monitoring team (s) IF- tion IF radios are NOT radios are availabla available.
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i No. 97827210 NUMBER PROCEDURE TITLE - REVISION ! / 03 EPIP-4.02 RADIATION PROTECTION SUPERVISOR CONTROLLING PROCEDURE PAGE 7 of 16
- STEP ACTION / EXPECTED RESPONSE
- RESPONSENOTO8TAINED
- 7. (CONTINUED)
- 1) Upon receipt of survey results, transmit data to the Radio-logical Assistant Director
- 8. ESTABLISH ACCESS CONTROL Based on survey results and/or E the emergency is NOT radio-briefing with the Radiological logical in nature, normal sta-Assessment Director, establish tion access control will be positive access control over followed. GO TO Step 9.
. the Auxiliary Building and/or other high Radiation Areas a) Establish access control by:
- 1) Requiring H.P. notifica-tion prior to entry
- 2) Use of Radiation Work Permits as per Section 2 of the Health Physics Manual b) Suggested access control limits
- 1) Airborne contamination CONC i
of 0.25 g i _OR
- 2) CREATER THAN or EQUAL TO 1000 DPM per 100 ca z OR 1 I
- 3) CREATER THAN or EQUAL TO i 1000 mR/HR
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t Peo.97847213 NUMBER PROCEDURE TITLE REVISION 03 EPIP-4.02 RADIATION PROTECTION SUPERVISOR CONTROLLING PROCEDURE PAGE 8 of 16
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 9. ACTIVATE OFFSITE MONITORING NOTE: Offsite Monitoring Team (s) should be dispatched upon classifi-cation of Site or General Emergency, as specified by the Radiological Assessment Director.
a) Review with the Radiological Assessment Director:
- 1) Need for Offsite Moni- 1) E offsite monitoring NOT toring teams required, GO TO Step M.
- 2) Initial location and
. number of offsite teams required
- 3) Assessment of offsite radiological hazards
- 4) Need to issue radiopro-tective drugs to moni-toring teams b) Activate EPIP-4.16, Of fsite Monitoring c) Select 2_ individuals per team. Only 1,need be a H.P. technician d) Assist in obtaining a vehicle
- 1) Health Physics truck -
- 2) Station Manager's car e) Assign an emergency kit, located at the station's Medical Center
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.EPIP-4.02 RADIATION PROTECTION SUPERVISOR CONTROLLING PROCEDURE PAGE 9 of 16
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 9. (CONTINUED)
- 1) Assign a battery powered air sampler .
- 2) Assign RM-14 with H.P.
210 probe
- 3) Record number of Emer-gency kits issued f) Brief team on the initial
, location they are to report g) Review protective gear re-quired:
- 1) Respirator and/or radio-protective drugs
- 2) Protective clothing
- 3) Dosimetry h) Dispatch Monitoring team
- 10. ACTIVATE TSC/OSC/ EOF MONITORING Upon Alert classification E event is NOT radiological in because of a radiological nature, GO TO Step M.
event, monitor emergency response centers. a) Determine frequency of monitoring based upon:
- 1) spread of contamination ~~
from service buildings
- 2) Increase or decrease of efflueE release
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w ._ _ , .e . %._.s_ .an_ . _ No. MSSM10 i NUntBER PROCEDURE TITLE REVISION ., 03 ( EPIP-4.02 RADIATION PROTECTION SUPERVISOR CONTROLLING PROCEDURE PAGE 10 of 16 i l
- STEP
] ACTIONNXPECTED RESPONSE RESPONSENOTODTAINED
- 10. (CONTINUED) l
- 3) Increase in emergency classification
- 4) Change in plume direction
, b) Assign:
- 1) EPIP-4.17, Monitoring of OSC and TSC AND
~ '
- 2) EPIP-4.18, Monitoring of EOF i NOTE: Health Physics personnel should begin monitoring of the EOF l within 60 minutes following an ALERT classification.
c) Inform Radiological issess-ment Director as to the
- habitability of the emergency response centers
- 11. CONTAMINATED PERSONNEL a) E station personnel are found a) E no station personnel are contaminated, assign an indivi- contaminated, continue with dual to ACTIVATE EPIP-4.06, this instruction.
Personnel Monitoring and Decontamination
- 12. CONTAMINATED INJURED PERSONNEL NOTE: E injury is life threatening, GO TO substep d of this step.
t j H an individual is injured and
- E individual is found NOT to be j requiring transportation to contaminated, GO TO Step M.
[ offsite hospital, detcrained to be contaminated as per H.P. procedure 3.1.7.1: _ I r
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No.97887210 NUMBER PROCEDURE TITLE
/ ,' REVISION 03 EPIP-4.02 RADIATION PROTECTION SUPERVISOR CONTROLLING PROCEDURE PAGE 11 of 16
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 12. (CONTINUED) a) Review personnel surveys from H.P. procedure 3.1.7.1 b) Insure decontamination prior to transportation, is not pratical c) Inform Radiological Assessment Director of need to transport contaminated personnel d) Activate EPIP-4.20, Health Physics Actions for Transport-ation of Contaminated Injured i Individual l
- 1) Select a technician to accompany victim
- 2) Supply technician with copy of EPIP-4.20 Health Physics Actions for Trans-portation of Contaminated Injured Individual
- 3) Supply technician with portable surt,ey instru-ment (s)
NOTE: Upon arrival of ambulance dispatch a technician to issue dosimetry e) Inform Radiological Assess-ment Director upon departure of ambulance 9 m #
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No. 97847210 NUMBER PROCEDURE TITLE REVISION 03 EPIP-4.02 RADIATION PROTECTION SUPERVISOR CONTROLLING PROCEDURE PAGE 12 of 16
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTO8TAINED l
- 13. EVACUATION MONITORING NOTE: E evacuation alarm sounds without prior notification of pending evacuation, CO T0 substep ,c_ of this step.
IF, F informed by the Radiological E evacuation of the station is Assessment Director of a pending not eminent, CO TO Step ,1_4,. 4 ( i evacuation 1
. I a) Consider dispatching onsite monitoring team to the parking loc (s) to determine radiation and contamination levels , ';
b) Report results of survey to the Radiological Assessment Director c) Activate EPIP-4.21 Evacu-ation and Remote Assembly Area Monitoring , i d) Assist in obtaining trans-portation of monitoring team g arrange transport-ation with security e) Inform Radiological Assess-ment Director when team is dispatched
- 14. POST ACCIDENT SAMPLING a) When notified by Radiological a) E post accident sampling of Assessment Director of the containment air and/or need for a post accident Reactor Coolant NOT required, containment and/or reactor GO TO Step M. ,
coolant: 3 1
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7 .._, _ .. -_ No.97$$7210
,, - ~ . NUMBER PROCEDURE TITLE REVISION
- 03 EPIP-4.02 RADIATION PROTECTION SUPERVISOR CONTROLLING PROCEDURE PAGE 13 of 16
- STEP ACTION / EXPECTED RES*0NSE RESPONSENOTOBTAINED
- 14. (CONTINUED)
- 1) Perform in-plant survey to determine dose rate at sample station
- 2) Inform Radiological Assessment Director results of survey
- 3) Initiate prsparation of RWP
- 4) Activate EPIP-4.22, Post Accident Sampling of Con-tainment Air and/or EPIP-
. ,4.23, Post Accident Sampling of Reactor Coolant
- 5) Activate EPIP-4.25, liquid ,
effluent sampling during an emergency as necessary.
- 6) Supply Health Physics coverage during sampling and sample preparation
- 15. SAMPLE ANALYSIS a) Upon receipt of sample a) F not sample analysis analysis data from effluent received, GO TO Step 16,.
sampling, or offsite monitoring, relay the in-formation innaediately to the Radiological Assessment Director
- 16. ASSESS MANPOWER a) When time allows, determine a) IF time is not currently need for relief shift and/or Wailable, assign scheduling an increase in manpower- to other H.P. personnel 1
l l l
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_w. ._ u.. sraerno NUMBER PROCEDURE TITLE REVISION . 03 EPIP-4.02 RADIATION PROTECTION SUPERVISOR CONTROLLING PROCEDURE PAGE 14 of 16
- STEP ACTION / EXPECTED RESPONSE RESPONSENOT08TAINED
- 16. (CONTINUED) pR Assess at a later time, AND GO TO Step E.
- 1) Discuss with Radiological Assessment Director, the ,
projected duration of emergency
- 2) Determine need for in-creased manpower '
- 3) Develop relief schedule and/or increased staffing schedule
- 4) Present schedule to Radiological Assessment.
Director for approval
- 5) E approved, activate '5) IJF, NOT approved, GO TO callout of scheduled Step E.
personnel
- 6) Upon completion of callout, inform Radio-logical Assessment Director
- 17. RELIEF OF SHIFT a) E a more senior H.P. indivi- a) a) GO TO Step E.
dual arrives ~or if relief is needed:
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- STEP ACTIONNXPECTED RESPONSE RESPONSENOTORTAINED
- 17. (CONTINUED)
- 1) Brief successor as to the plant conditions and Health Physics actions underway
- 2) Announce change of pos-ition to the Radiological Assessment Director
- 3) Remain with new super-visor for approximately 30 minutes
- 18. CONTINUE ASSESSMENT a) E emargency condition still a) Radiological Assessment exists: Director declares termination of Emergency, CO TO Step g.
- 1) Return to Step 5 and direct the repetition ci surveys and radiological sampling to determine radiological hazards onsite
- 19. TERMINATION OF D.ERGENCY a) Inform Health Physics staff as to termination of emergency b) Maintain access control c) Review Recovery actions with Radiological Assess-ment Director d) Replace all procedures and equipment used during the emergency l
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- STEP ACTION / EXPECTED RESPONSE RESPONSENOT08TAINE0
- 20. ADMINISTRATION a) Forward all completed or partially completed pro-cedures, notes, sample results and surveys to the Radiological Assess-ment Director
- 21. PROCEDURE COMPLETION:
, a) Completed By:
Date: Time: END -
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! EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCEDURE TITLE REVISION 03 EPIP-4.03 DOSE ASSESSMENT CONTROLLING PROCEDURE PAGE (With 4 Attachments) 1 of 13 PURPOSE Provide Dose Assessment Personnel guidance in calculating percent of Technical Specifications OR Dose Rates and Projected Dose due to radioactive release. USER Dose Assessment Team Leader OR Radiological Assessment Director ENTRY CONDITIONS Activation by EPIP-4.01, Radiological Assessment Director Controlling Procedure. SAFETY RELATED REVISION RECORO REV. 00 PAGE(S): Entire Procedure DATE: 07-02-82 REV. 01 PAGE(S): Entire Procedure DATE: 07-22-82 REV. 02 PAGE(S): Entire Procedure DATE: 09-01-82 REV. 03 PAGE(S): Entire Procedute DATE: 05-24-83 REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: APP VAL RECOM. 7:0E0 APPROVE 0 OA TE j 05-24-83 D
~ CHAIRMANSTA TION NUCLEAR SAFETY . . . . . _ _ _ . _ . . - . .
AND OPERA TING COMMITTEE
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- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 1. INITIATE PROCEDURE:
a) BY: s DATE: TIME:
- 2. REQUEST BRIEFING a) Request briefing with the Radiological Assessment Director as to the emergency classifications, initial off-site release calculations and current monitor reading and meteorological data
- 3. DETERMINE EMERGENCY CLASSIFI-CATION:
a) E the emergency is an UNUSUAL a) E the Emergency is a SITE 3 EVENT OR ALERT continue with GENERAL GO TO Step 4. this instruction b) Obtain a SAMPLE from the b) E a sample is not available, effluent pathway continue with this instruc-tion using monitor readings to assess the release, until sample results become avail-able. c) ACTIVATE EPIP-4.11, Follow-up Offsite Release Assessment d) Obtain from EPIP-4.11, the PEACENT of TECHNICAL SPECIFI-CATION of the release
1- -
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NUMBER PROCEDURE TITLE REVISION 03 EPIP-4.03 DOSE ASSESSMENT CONTROLLING PROCEDURE PAGE 3 of 13 STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 3. (CONTINUED)
NOTE: Any release GREATER THAN OR EQUAL TO 100% TECH SPECS but LESS THAN 1000% TECH SPECS is a NOTIFICATION OF UNUSUAL EVENT emergency AND Any release GREATER THAN OR EQUAL TO 1000% TECH SPECS but LESS THAN 50 mR/HR at the site boundary is an ALERT emergency. e) REPORT RESULTS to the Radio-logical Assessment Director f) E emergency classification f) E the emergency classifi-is an ALERT, GO TO Step 4_ cation is LESS THAN an ALERT, continue with this instruction. g) E release has terminated. g) E release has not been E E Step 14,. 4 terminated, continue with Substep a through 8.
- 4. DETERMINE NEED FOR OFFSITE MONITORLNG NOTE: A minimum of 2 offsite monitoring tieams should be dispatched ~
~
on classification of SITE OR GENERAL EMERGENCY.
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- STEP ACTIONiEXPECTED RESP 0AfSE RESPONSENOTOBTAINED
- 4. (CONTINUED)
~. a) F manpower IS available and a) IF manpower is NOT available, emergency classification is GO TO Step 6.
ALERT OR GREATER AND Return to this step when man-power is available.
- 1) Discuss with the Radio-logical Assessment Director the need for OFFSITE MONI-TORING b) IF,Offsite F Monitoring Teams b) IF Offsite Monitoring Teams need to be dispatched, review NOT required, CO TO Step 6.'
the following with the Radio-logical Assessment Director
- 1) Meteorological conditions to determine placement of the teams
- 2) Offsite Dose Projection to detemine need for prote:-
tive measures for Offsite Team Members
- 5. ASSIGN RADIOPHONE OPERATOR a) F Offsite Monitoring Team (s) a) I_F,Offsite F Teams are NOT to are to be dispatched, continue be dispatched GO TO Step 6.,
with this instruction b) Request from the Radiological b) IF, F no individual is avail-Assessment Director to assign able, continue with this , . _ , . an individual to man the instruction, returning to radiophone and to assist as Step 5, when an inidividual the Dose Assessment Team is available. Member
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NUMBER PROCEDURE TITLE REVISION 03 EPIP-4.03 DOSE ASSESSMENT CONTROLLING PROCEDURE PAGE 5 of 13
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTORTAINED
- 5. (CONTINUED) c) Brief individual as to the c) IF no individual is avail-initial location of the Ele continue with this acnitoring teams instruction..
d) Assign EPIP-4.12, offaite d) IF no team member is avail-Environmental Monitoring able ACTIVATE the EPIP's and Instructions , and return to this step EPIP-4.13. Offsite Release Assessment with Environmental Data, to the team member requesting ACTIVATION of the above EPIP's
- 1) Assist, as necessary, establishment of communi-cations and the placement of the teams at desired location
- 6. OFFSITE DOSE ASSESSMENT a) IF OFFSITE DOSE ASSESSMENT a) IF OFFSITE DOSE ASSESSMENT E required ACTIVATE EPIP- E NOT required (i.e.
4.09, Source Tera Assessment, emergency did NOT result from to determine SOURCE TERM actual or potential radio-logical release) CD TO Step
- 1) IF release has occurred 12.
Entinua kith this in- ~ struction. 1) If NO release has occurred CO E Substep ~b.
- 2) Determine the TIME since the start of the release .
OR since the previous assessment and convert to seconds
- 3) Perform the following cal-culation to determine the equivalent curies of I-131 and Xe-133 released TIME (SECONDS) X SOURCE TERM (Ci/sec) = CURIES
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No. 97847210 , NUMBER PROCEDURE TITLE REVISION 03 EPIP-4.03 DOSE nSSESSMENT CONTROLLING PROCEDURE PAGE 6 of 13
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
. 6. (CONTINUED)
- 4) Lcg equivalent CURIES on Attachment i .
- 5) Determine the IODINE to XENON RATIO AND Log on Attachment 1 b) ACTIVATE EPIP-4.11, Follow-up Offsite Release Assessment to determine DOSE RATE NOTE: IF wind shift occurs during offsite releases, re-evaluate of fsite releases, and log results, using a new form for Attachment 2, E?IP-4.11.
- 1) Determiste fror. EPIP-4.11, the DATE TIME AND STABILITY CLASS used to project the dose rate
- 2) Determine SITE BOUNDARY DOSE RATE for WHOLE BODY AND THYROID from EPIP-4.11
- 3) Obtain from the Emergency Communicator, the PRLMY SECTOR affected by the release 5
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N 3. 97847210 NUMBER PROCEDURE TITLE REVIS10?: 03 EPIP-4.03 DOSE ASSESSMENT CONTROLLING PROCEDURE PAGE 7 of 13
- STEP ACTION / EXPECTED RESPONSE RESPONSENOT08TAINED
- 6. (CONTINUED) l
- l
- 4) Determine INTEGRATED DOSE by multiplying the time l i
since the start of the l release OR since previous assessment by the DOSE RATE: TIME (HOURS) x DOSE RATE (mR/HR) = INTEGRATED DOSE
- 5) Determine from Radiological Assessment Director, the estimated DURATION OF RELEASE (HOURS)
- 6) Determine the TOTAL PROJECTED DOSE:
DURATION OF RELEASE X DOSE RATE + INTEGRATED DOSE = TOTAL PROJECTED DOSE (mR)
- 7) Log results on Attachment 2 NOTE: IF Site Boundary Dose Rate is 50 mR/HR Whole Body for 30 Enutes OR 500 mR/HR for 2 minutTs (OR 5 times these leveTs" for thyro'Td) -
0,R The projected dose is 0.5 to 2.0 REM Whole Body OR 1.0 to 12 REM Thyroid, notify the Radiological Assessment Director that a SITE EMERGENCY condition exists. 3
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No. 97847210 NUMBER PROCEDURE TITLE REVISION 03 EPIP-4.03 DOSE ASSESSMENT CONTROLLING PROCEDURE PAGE 8 of 13 l I
- STEP ACTICN/ EXPECTED RESPONSE . RESPONSENOT08TAINED 1 1
NOTE: IF the Site Boundary dose rate is GREATER THAN OR EQUAL TO 1000 mR/HR Whole Body or 5000 mR/HR Thyroid pR The projected dose is GREATER THAN OR EQUAL TO 2 REM Whole Body or 12 REM Thyroid, notify the Radiological Assessment l Director that a GENERAL, EMERGENCY condition exists. ; l
- 8) IFF monitoring data was used 8) IF,F Sample Analysis Data l to evaluate offsite dose, WAS used for Offsite Dose update and revise Offsite Assessment, continue with Dese Assessment when Sample this instruction.
Analysis Data becomes available
- 7. DETERMINE OFFSITE DOSE RATE.
INTEGRATED AND TOTAL PROJECTED DOSE AT 2, 5 AND 10 MILES a) Determine from Step 6 the ' most current:
- 1) Stability Class
- 2) Site boundary dose rate for Whole Body and Thyroid
- 3) Log data on attachment 4
- b) Determine the MULTIPLICATION l FACTOR from attachment 3,for distance of 2 miles l
c) Determine DOSE RATE for 2 ~ miles: SITE BOUNDARY DOSE RATE X MULTIPLICATION FACTOR = DOSE RATE (mR/HR) (2 MILES) i l d) Log results on Attachment 4, l l i
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,, No.97847219 q
. NUMBER PROCEDURE TITLE REVISION 03 EPIP-4.03 DOSE ASSESSMENT CONTROLLING PROCEDURE
~, PAGE 9 of 13
- STEF ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 7. (CONTINUED) e) Repeat Substep b,through d_
- for distances of 5 and 10 ,
miles AND Continue with this instruction f) Repeat Substep a_ through e for the Integrated Dose and for the )*otal Projected Dose
,i *
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' 8.
DOSE RATE. INTEGRATED AND PRO-I % ' JECTED DOSE AT OTHER DISTANCES. I a) E Dose Rates, Integrated and/ a) E data is NOT requested or Projected Doses are re- at distances other than 2
, quested at distances other 5, or 10 miles, GO TO Step
(> 5 than 2, 5. or 10 miles, con- 9. tinue with this instruction b) ACTIVATE EPIP-4.10 to deter-mine X/Q for:
- j 1) Site Boundary
- 2) Distance other than 2, 5 or 10 miles c) Obtain from Step 6 the Site Boundary Dose Rate
{ 1
- d) Determine Dose Rate for dis-
.. tance of 'aterast:
- g ,
SITE BOUNDARY g (X/Q) (distance of interest) = DOSE RATE DOSE RATE (X/Q) (site boundary) '(distance of interest) (-
~
1 e) Log on attachment i i l'
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no. nenno NUMBER PROCEDURE TITLE REVISION 03 EPIP-4.03 DOSE ASSESSMENT CONTROLLING PROCEDURE PAGE 10 of 13
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 8. (CONTINUED) f) Repeat Substep a_ through e_
using Site Boundary Integrated Dose and Total Projected Dose *
. 9. RELAY DATA TO RADIOLOGICAL ASSESSMENT DIRECTOR:
a) Complete Attachment 4_ and log the DATE TIME, AND SECTOR AFFECTED at the time of the Offsite Assessment AND Indicate whether Offsite Assessment was done using a monito_r reading or Sample Analysis b) Relay the completed attachment 4 to the Radiological Assess-ment Director
- 10. COMPARE PROJECTED TO ACTUAL OFFSITE DOSE a) Obtain from the Dose Assess- a) IF Offsite Data is NOT avail-ment Team Member the current E le, CO TO Step 11.
Offsite Monitoring Data b) Correct the Actual Dose Rates from the Offsite Monitoring Teams for the initial release time:
- 1) Obtain the wind speed from the Radiological Assessment Director (mph) 9
- 2) Determine the TIME of the actual measurement
- 3) Determine the DISTANCE from the plant where the reading was taken (miles) e
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m.orse m s NUntBER { _ PROCEDURE TITLE REVISION 03 EPIP-4.03 DOSE ASSESSMENT CONTROLLING PROCEDURE PAGE 11 of 13
- STEP ACTION / EXPECTED RESPONSE RESPONSENOT08TAINED 10.- (CONTINUED)
- 4) Calculate the INITIAL TIME of RELEASE:
TIME OF MEASUREMENT - DISTANCE = INITIAL RELEASE TIME WIND SPEED c) Obtain from attachment 2, the Projected Dose Race at the distance and time specified in the above Substep b d) Compare dose rates from above Substep a and c e) E data is significantly a) E the Actual and Projected different, data correlate, CO TO Step
.Lt.-
- 1) Notify the Radiological Assessment Director as to the difference between Actual and Projected Dose
, Rates
- 2) Determine which set of data is to be used for dose proj ections
- 11. ASSESS RELOCATION OF MONITORING TEAM a) E Monitoring Teams are in a) E Monitoring Teams are not the field, review current yet dispatched, GO TO Step meteorological data H. -
b) Assess the need to relocate monitoring teams c) IF teams are to be relocated c) IF teams are NOT to be re-Inform the Dose Assessment lEcated, GO TO Step M. Team Member Assist in relocation of Teams i
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r...nuw _... No. 97847210 NUMBER PROCEDURE TITLE REVISION 03 EPIP-4.03 DOSE ASSESSMENT CONTROLLING PROCEDURE PAGE 12 of 13
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 12. CONTINUE ASSESSMDIT:
a) IF EOF is NOT manned a) IF EOF is manned GO TO Step 3 1,3,. OR JF the radiological release OR OR,potencial release has NOT IF release OR potential TERMINATED, release has terminated, GO TO Step 4 1_4,. Continue with Step 6 through 3I
- 13. EOF MANNED a) Brief Radiological Assessment Coordinator at the EOF of ALL current offsite Dose Projections and the status and location of Offsite Monitoring Teams b) Inform the Dose Assessment b) IF radio contact cannot Team Member to instruct the E established maintain Offsite Monitoring Teams to contact with monitoring estabish radio contact with teams, relaying infor:r,-
the EOF ation from the teams to the EOF c) Instruct the Dose Assessment Team Member to maintain contact with the EOF relaying __ _ the following information _ . received from the Radiological Assessment Director __ _ _ __ [~
~
- 1) Meteorological Data [_ " _'
- 2) Monitoring Data . _' .T. _ . b- .
- 3) Sample Analysis Data d) Report readiness to the . _ _ _ . . . , _ _ _ _ _ _.
Radiological Assessment ' Director and continue with ,__ _ _ _ .. . this instruction. _. . . . . . . _j
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)
PAGE 13 of 13
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 14. ADMINISTRATION a) Gather all procedures, attach-ments and sample analysis records.
AND Present them to the Radio-logical Assessment Director
- 15. TERMINATE EPIP-4.03 a) Completed By:
, .Date:
Time: e w 4 l
)
END . _ . l I Il4
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~ MUMBER A TTACHMENT TITLE REVISION EPIP-4.03 03 0FFSITE RELEASE A TTACHMENT WORKSHEET PAGE 2 1 of 2 SITE BOUNDARY - WHOLE BODY STABILITY INTEGRATED TOTAL PROJECTED DATE TIME SECTOR CLASS DOSE RATE DOSE DOSE i
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No.97867200 VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION
- EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCEDURE TITLE REVISION 03 EPIP-4.04 EMERGENCY PERSONNEL RADIATION EXPOSLTE PAGE (With 3 Attachments) 1 of 6 PURPOSE Provide to the Emergency Manager an evalution of the need for authorization of emergency exposure USER
, Radiological Assessment Director ENTRY CONDITIONS 1
1 Any one of the following conditions exist: l
- 1. Activation by another EPIP.
- 2. Survey results indicate 10CFR20 quarterly limits may be exceeded.
SAFETY 3 ELATED REVISION RECORO REY. 00 PAGE(S): Entire Procedure DATE: 07-02-82 REV 01 PAGE(S): Entire Procedure DATE: 07-22-82 REV. 02 PAGE(S): Entire Procedure DATE: 09-01-82 REV. 03 PAGE(S): Entire Procedure DATE: 05-24-82 REV. PAGE(S): DATE: REV. PAGE(S): DATE: er" escerei-nATv. APPRO LRECOMM CEO APPROVED DA TE
.M 05-24-83 CHAIRMAN STA TION NUCLEAR SAFETY AND OPERA TING COMMITTEE .
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- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 1. INITIATE PROCEDURE:
' a) Initiated By:
Date: Time:
- 2. ASSESS NEED FOR EMERGENCY EXPOSURE:
The following are guidelines for acceptable authorization of exposure CREATER THAN 10CFR20 quarterly limits (see attachment 1) a) Lifesaving
- 1) Search, rescue and re-moval of injured
- 2) Perform first aid
- 3) Entry to correct con-dicions that could, if unrepaired, result in onsite or offsite injury b) Damage repair or corrective actions
- 1) Save valuable equipment ,
- 2) Limit offsite releases
- 3. ASSESS ESTIMATED DOSE:
a) Request from Emergency , Manager, destination of . emergency workers t
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- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 3. (CONTINUED) b) Determine length of expos-ure time c) Assess dose rate by one of the following:
NOTE: Minimize exposure to monitoring personnel while obtaining sufficient data to estimate exposure.
- 1) Area radiation monitor
- 2) Survey - Activate EPIP-4.14, Inplant Monitoring d) Total dose = d) IF total dose estimated LESS EXPOSURE TIME I DOSE RATE ~THAN 3_ Rem, GO TO Step M.
- 4. INSURE ACTIVATION:
a) Notify Emergency Manager to activate EPIP-5.06, Emer-gency Radiation Exposure Limits
- 5. REVIEW EMERGENCY DOSE LLMITS:
a) Review attachment 1 for emergency exposure limits
- 6. ASSESS NEED FOR IMMEDIATE ACTION:
Consider the following prior to authorization: a) Lifesaving actions: ! e a egq . Aa . y . ggg4m & M e m+ ee-wp p .W -M**W=- N Mh
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740.97887210 NUMBER PROCEDURE TITLE REVISION 03 EPIP-4.04 EMERGENCY PERSONNEL RADIATION EXPOSURE PAGE 4 of 6
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 5. (CONTINUED)
- 1) Attempts to rescue versus total exposure of victim b) Damage repair:
- 1) " Mock-up" cr " dry run" prior to entry
- 2) Delay entry to' allow for decay and/or venti-lation OR establishment of shieTding
- 6. RECOMMEND EMERGENCY EXPOSURE:
a) Review with Emergency Man-ager alternatives available b) Insure the individual has b) IF individual previously re-NOT received a once in a ceived emergency exposure, lifetime exposure deny authorization. c) Submit recommendation to the Emergency Manager *
- 7. PROTECTIVE ACTIONS:
a) Entry requires Radiation Work Permit NOTE: Emergency Manager may, at his discretion, wave requirements for Radiation Work Permit prior to entry and give verbal authorization. _ . _ b) Insure workers receive:
- 1) Proper protective i clothing
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- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT08TAINED
- 7. (CONTINUED)
- 2) Dosimetry capable of measuring expected dose
- 3) Respiratory protection, if necessary
- 4) Instrumentation capa-ble of reading radia-tion levels of up to 1000 R/Hr c) If possible, direct workers to route of entry of lowest exposure NOTE: Unless considered necessary, monitoring personnel should not remain in high exposure area.
d) Provide Health Physics coverage
- 8. REVIEW EXPOSURE EFFECTS:
a) H time permits, Review attachment 2, Radiation l Effects Versus Whole Body Exposure, with volunteers
- 9. EMERGENCY EXPOSURE FORM:
a) Complete the emergency worker Radiological Exposure Record on attachment 3
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- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED NOTE: _I_F, F the authorized emergency exposure, or a large portion of exposure is received, the dose may be considered a once in a life time dose and individual shall be excluded from further emergency exposure.
- 10. FOLLOW UP ASSESSMENT:
IF individual has received a) TREATER THAN 25 Rem, "recom-mend" evacuation to MCV for further assessment
- 11. ADMINISTRATION a) Complete attachment 3 b) Forward copy of attachment 3_ to Station Emergency Manager c) Place the original attach-ment 3 in individual's dose control file
- 12. RETURN TO CONTROLLING PROCEDURE a) Upon completion of this proced-ure return to the controlling proceduce
- 13. PROCEDURE COMPLETED:
a) COMPLETED BY: DATE: TIME: END e** -m ,e m
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NUMBER A TTACHMiNT TITLE REVISION EPIP-4.04 03 EMERGENCY PERSONNEL RADIATION EXPOSURE A TTACHMENT PAGE 1 EMERGENCY EXPOSURE LIMITS 1 of 1 VEPCO ON-SITE EMERGENCY EXPOSURE LLMITS . CLASSIFICATION WHOLE BODY (REM) THYROID (R3) Damage Repair Activity 25 125 Lifesaving Activity 100
- No limit given in extreme case because loss of thyroid may be acceptable to save a life. This may not be necessary if respirators and/or blocking agents are available for rescue personnel.
NRC 10CFR20 QUARTERLY LIMITS Whole Body 1.25 Rem 3.00 Rem ** Hands / Feet 18.75 Rem Skin 7.5 Rem
** IF 5 (N-18) permits l
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? , ,_ _ - - - -. __ L :, ,-_ a., _ _ _ _ _ _ _. _ _ . _ Pee. 97887220 - NUMRER A TTACHMENT TITLE REVISION EPIP-4.04 03 EMERGENCY PERSONNEL RADIATION EXPOSURE A TTACHMENT PAGE 2 1ADIATION EFFECTS VERSUS 120LE BODY EXPOSURE 1 of 1 EXPOSURE EFFECTS 0 rem to 20 rem no measurable effects , 20 rem to 50 rem minor blood changes, cellular damage almost completely repaired. 50 rem to 100 rem further blood changes, loss of appetite, fatigue, no disability. 100 rem to 300 rem illness occurs: nausea, vomiting, diarrhea, skin reddening, loss of hair, complete recovery in~most cases, although a few fatalities. 300 rem to 400 rem severe illness. 450 rem a' bout 50% fatalities in 30 days. 600 rem Virtually all exposed individuals will die. NOTE: The effects shown above are based upon:
- 1. An acute exposure to the entire body.
- 2. An acute exposure to an entire population.
- 3. No medical treatment for the victims.
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-. MUMBER A TTACHMENT TITLE REVISION EPIP-4.04 03 EMERGENCY PERSONNEL RADIATION EIPOSURE A TTACHMENT PAGE 3 EMERGENCY WORKER RADIOLOGICAL EXPOSLTE RECORD 1 of 1 NAME: AGE: YEARS Last First Mid. Init.
Soc. Sec. No.:* : Current Quarterly Exposure: rem Authorized Emergency Exposure: rem Authorized by (Emergency Manager): Name: at hours On Date: 19 . SELF-READING DOSIMETER RANGE STARTING READING STOP READING DOSE INTEGRATED BY ROENTGEN R TIME DATE R TIME DATE R DOSE R INIT. l TLD BADGE NO. NO. i CHECK ( ) DOSE INTEGRATED BY ISSUE READ TIME DATE REM DOSE / REM INIT. . _ . , . , _ i l t l REMARKS: I l l l
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No.97087200 VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCEDURE TITLE REVISION 03 EPIP-4.06 PERSONNEL MONITORING AND PAGE DECONTAMINATION (With 2 Attachments) 1 of 6 PURPOSE Provide guidance for decontamination of personnel. USER Health Physics Technician ENTRY CONulTIONS
- 1. Activated by another EPIP.
SAFETY RELATED
^ ~~
REVISION RECORO REV. 00 PAGE(S): Entire Procedure DATE: 07-02-82 REV. 01 l
. _ PAGE(S): Entire Procedure DATE: 07-22-82 l REV. 02 PAGE(S): Entire Procedure DATE: 09-01-82 l REV. 03 PAGE(S): Entire Procedure DATE: 05-24-83 l REV. PAGE(S): DATE:
REV. PAGE(S): DATE: O rt1. Pacef94 DATT. APPRO Al RECOM DED APPROVED DA TE S 05-24-83 .._ CHAIRMANSTA TION NUCLEAR SAFETY
- - . . .~. T. . -.^.^.L-y
- / AND OPERA TING COMMITTEE ~~ ~~~ ~~. - .11
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w. No. 97847210 NUMBER PROCEDURE TITLE REVISION 03 EPIP-4.06 PERSONNEL MONITORING AND DECONTAMINATION PAGE 2 of 6
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 1. INITIATE PROCEDURE:
a) BY: DATE: TIME:
- 2. OBTAIN MONITORING EQUIPMENT:
a) Obtain an RM-14, with an H.P. 210 probe, from the Health Physics instrument locker and proceed immedi-ately to the Personnel Change Area
- 1) IF the area is habitable, 1) IF area is uninhabitable, all contaminated indivi- request assistance from duals will be deconned the Radiation Protection there Supervisor for relocation AND Have contaminated indivi-dual remove contaminated clothing and don clean protective clothing (paper suit, gloves, booties,'
etc.) to minimize spread of contamination.
- 2) IF a large number of individuals are suspected of being contaminated, the laundry should be used to handle the over- --
flow
- 3. CONTAMINATED PERSONNEL WITH INJURIES:
a) IF contaminated individual a) IF contaminated individual is is injured and requires NOT injured, CO TO Step 4. first aid: g g3m e .* %p rme e % M $ - O
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NUMBER PROCEDURE TITLE REVISION 0,3 EPIP-4.06 PERSONNEL MONITORING AND DECONTAMINATION PAGE 3 of 6
- STEP ACTIONMXPECTED RESPONSE RESPONSE NOTOBTAINED
- 3. (CONTINUED)
- 1) Perform follow-up first-aid and decontamination in the H.P. laundry facility, if appropriate
- 2) Perform as much decontam-ination as medical status permits
- 4. PERFORM SURVEY:
a) Perform initial survey, documenting results on Attachments 1 and 2
- 1) Pay particular attention to the nose and mouth area to determine possible in-ternal contamination b) IF internal contamination is a) IF internal contamination is suspected, note on Attachment NOT suspected, GO TO Step 5,.
1
- 1) Have individual clean nose with wet cotton swabs
- 2) Have individual blev j nose frequently l...- . . .. . .
l 3) Record sv.1b reading on l Attachment i - NOTE: Cease decontamination if skin becomes reddened OR bleeding. , NOTE: Obtain permission from Radiation Prctection Supervisor to ! apply potassium permanganate. i _. . .. - . - - - - - ~ - - - - ~ .-. . . . . - . ---
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Pee. 97847210 NUMBER PROCEDURE TITLE REVISION 03 EPIP-4.06 PERSONNEL MONITORING AND DECONTAMINATION PAGE 4 of 6
- STEP ACTION / EXPECTED RES!0NSE RESPONSE NOTO8TAINED
- 5. DECONTAMINATE:
a) REMOVE contaminated CLOTHING from individual b) IF_ CONTAMINATION problem is _ WIDESPREAD: LJ Shower using soap and water, keeping radio-active material away from body openings
- 2) Dry thoroughly, placing towel in plastic bag or contaminated material barrel
- 3) Repeat survey and log data on Attachment 1
- 4) IF contamination still 4) CO TO Step 6_
exists repeat showering and surveying, recording survey data on Attach-ment 1
- 5) IJ_ contamination still 5) E E Step 6_
exists, select most highly contaminated areas and start decon-tamination for localized areas ., c) If contaminated area is c) GO TO Substep d. LOCALIZED, isolate the area and perform the following actions. Survey and record data on Attach-ment 1 after each step
- 1) Clean using soap and water
- 2) Apply abrasive soap and water
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.- STEF ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 5. (CONTINUED)
- 3) Apply a mixture of 50%
CORNMEAL and 50 DETER-
' GENT PASTE and scrub with brush
- 4) As a last resort, apply potassium permanganate solution, rinse and apply freshly prepared sodium bisulfite solution d) IF contamit.ation is found d) GO TO Substep e_.
in EYES or OPEN L'0UND:
- 1) Flush copiously with water
- 2) Record contamination data on Attachment 1
- 3) Notify Radiation Protec-tion Supervisor e) If contamination is found e) g E Step 6 in hair:
- 1) Shampoo, isolating face and shoulders
- 2) Consider cutting or shav-ing the affected area if contamination cannot be removed
- 6. CONTAMINATION LIMITS
- 1 a) IF individuals are deconned a) IF individual cannot be to as low as reasonably deconned to background, i achievable, below 100 CPM contact Radiation Protection '
above background, they may Supervisor prior to releasing be released. the individual.- 7 , g , ... . - . ,j
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No.97887210 NUMBER PROCE00RE TITLE REVISION 03 EPIP-4.06 PERSONNEL MONITORING AND DECONTAMINATION PAGE 6 of 6
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 6. (CONTINUED) 1) Individual may be released if contamination is found to be fixed (< 0.1 mR/hr) andfollow-ufdecontamina-tion and/or dose evaluation is made. Contact the Rad-iation Protection Super-visor prior to releasing the individual.
~
- 7. INTERNAL CONTAMINATI0N:
a) Individuals suspected of a) IF whole body counter is in-internal contamination operable, use Surry Power should be evaluated follow- Station counter. ing normal station H.P. procedure 3.1.3.4, Whole Body Counter Operation
- 8. ADMINISTRATION:
a) Return all completed survey results to the Radiation Protection Supervisor
- 9. PROCEDURE COMPLETION:
a) COMPLETED BY: DATE: TIME: END WEh , g
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- no.oreenso NUMBER A TTAC# MENT TITLE REVISION RPTP-la_06 03 ATTAC# MENT PERSONNEL DECONTAMINATION RECORD FAGE 1 1 of 1
- 1. Individual Contaminated:
- 2. TLDf: Date: TIME: RWPi
- 3. Contamination Occurred in (Area):
- 4. While Involved in (Type Work):
. 5. Personal Clothing or Equipment Contaminated: YES NO
- 6. Items (List):
- 7. Disposition of above listed items:
- 8. If internal contamination is suspected, the individual should be given a whole body count.
- 9. Internally Contaminated? YES NO -
l IT YES NOTIFY RADIATION PROTECTION SUPERVISOR IMMEDIATELY!
- 10. Body Areas Externally Contaminated:
- 11. Decontanination:
SURVEY INSTRUMENT DECON TIME SKIN AREA & PROBE READING AGENT INITIALS t Health Physics Remarks: Health Physics Clearance and Signoff By Date N' 4 m' N $ ' ]N $ N. Mh gb% ,, g4 ) $#4g,g g$4N g,
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Peo. 97847200 VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION
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EMERGENCY PLAN IMPLEMENTING PROCEDURE l NUMBER PROCSOURE TITLE REVISION 03 EPIP-4.07 PROTECTIVE MEASURES PAGE (With 5 Attachments) 1 of 7 PURPOSE Supply guidance to Radiological Assessment Director to promptly assess projected doses to population of risk and to recommend protective actions to the Emergency Manager. USER Radiological Assessment Director or Senior Health Physics Personnel Onsite. ENTRY CONDITIONS Any of the following:
- 1) Activation by EPIP-4.01, Radiological Assessment Director Controlling Procedure.
{ -. REVISION RECORO REV. 00 PAGE(S): Entire Procedure - DATE: 07-02-82 - ' - ~ REV. 01 PAGE(S): Entire Procedure DATE: 07-22-82
- - - REV. 0 2 PAGE(S): Entire Procedure - -DATE:--09-01-82 - - - - -
REV. 03 PAGE(S): Entire Procedure DATE: 05-24-83 REV. PAGE(3): -- DATE: - - - - - - - - ~ ~ REV. PAGE(S): DATE: REV. PAGE(S): DATE: APPROVAL RECO 1ENCEO APPROVED OA TE
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- f. NUMSER PROCE00RE TITLE REVISION
, 03 EPIP-4.07 PROTECTIVE MEASURES PAGE 2 of 7 Q1 ' ,
7 F ~ STE! ACTION / EXPECTED RESPONSE RESPONSENOTO8TAINED , t 4
.' 1. INITIATE PROCEDURE:
,a) Initiated By:
i Date: , 4' -' f Time:
- 2. PROTECTIVE ACTION GUIDELINES FOR INITIAL ASSESSMENT OR FOR CON-TINUOUS RELEASE a) IF this is an INITIAL ASSESS-MENT E
E the radioactive release ia a CONTINUOUS RELEASE Determine the distance, from - EPIP-4.03, Dose Assessment Controlling Procedure, at which the projected dose exceeds:
- 1) 2.0 REM Whole Body OR 12.0'
- 1) IF projected dose is LESS
- REM Thyroid THAN 2.0 Rem Whole bcdy OR 12.0 Rem Thyroid, continue AND/OR with this instruction.
, 2) 0.5 REM Whole Body OR 1.0 2) IF projected dose is LESS REM Thyroid TRAN 0.5 Rea Whole Body 3 1.0 Rea Thyroid, recommend offsite Protective Act- [ t ions, GO TO Step 5. ,
, 4
'h b). Review PROTECTIVE ACTION GUIDELINES in Attachment 1
\' '
i'c)= Determine the affected sector ei ' i f ,e ' from the Emergency Communi- ' ly \ citor , j ['
- II ' termine the current wind t, J
direction ( L q \.3 z,r3e.' '
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- PAGE 3 of 7
~ STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOSTAINED
- 2. (CONTINUED)
NOTE: Wind direction is given in the direction the wind is coming FROM.
- 2) Affected sector is 1530' from the wind direction
- 3) Review Sector Map in Attachment 5_
d) Reconumend PROTECTIVE ACTIONS for PRIMARY SECTOR (Substep c)
' AND the two adjacent sectors e) CO TO Step 5
- 3. PROTECTIVE ACTION GUIDELINES FOR A PUFF RELEASE a) F the release is a PUFF a) GO TO Step 5
- release S.R, Radiological release is probable, but has NOT yet occurred, continue with this instruction. . . _ _ _ . _. . . . .. _ _ .
b) Review EPIP-4.03, Dose Assess-ment Controlling Procedure c) IF a review of data from Sub- c) GO TO Step 5_ step b_ indicates OFFSITE EXPOSURE to be GREATER THAN OR EQUAL TO 0.5 REM Whole Body
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- STEP ACTION / EXPECTED RESPONSE RESPONSENOTORTAINED
- 3. (CONTINUED)
E 1.0 REM Thyroid
~
Continue with this instruction
- 4. CALCULATE L'EED FOR EVACUATION OR SHELTERING a) Determine need fo'r EVACUATION OR SHELTERING based on WHOLE EDY EXPOSURE
- 1) Complete Attachment 3
- 2) Using information from Attachment 3 determine the PROTECTIVE ACTIONS to be reconenended from the following:
IF THEN
- 1. Projected dose LESS~ 1. No action THAN 0.5 rem
- 2. Sheltering dose,LESS 2. Shelter THAN 2.0 rea
- 3. Sheltering dose GREATER 3. Evacuate i
THAN OR EQUAL TO M , rem, I and Evacuation dose LESS i THAN Sheltering dose i
- 4. Sheltering dose GREATER 4. Shelter I
THAN OR EQUAL TO 2.0 rem, f and Evacuation dose GREAT-l ER THAN 3 equal to Shelt-ering dose
, , 4 M
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No. 97ser210 NUMBER PROCEDURE TITLE REVISION 03 EPIP-4.07 PROTECTIVE MEASURES PAGE 5 of 7 l
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTORTAINED l 4. (CONTINUED) l b) Determine EVACUATION OR SHELTERING based on TIiYROID .
EXPOSURE
- 1) Complete Attachment 3_ using THYROID EXPOSURE RATE AND 0.65 for STRUCTURE SHELTERING FACTOR
(
- 2) Using information from Attachment 3 determine PROTECTIVE ACTIONS to be RECOMMENDED from the I following:
1 E WB
- 1. Projected thyroid dose 1. No action l
LESS THAN 1.0 rem-
- 2. Sheltering dose GREATER 2. Shelter THAN OR EQUAL TO 1.0 rem but LESS THAN -12 rem
- 3. Sheltering dose GREATER 3. Evacuate than OR EQUAL TO 12 rea .
and evacuation dose LESS ' THAN sheltering dose l
- 4. Sheltering dose GREATER 4. Shelter ~~ ~
THAN OR EQUAL TO M rem
'~~
and evacuation dose GREAT- ' ER THAN O_R, equal to shelt-ering dose
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No. 9704F210 NUMBER PROCEDURE TITLE . REVISION 03 EPIP-4.07 PROTECTIVE MEASURES PAGE 6 of 7
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTQBTAINED
- 5. DETERMINE NEED FOR PROTECTIVE ACTION ONSITE a) Review survey and air sampling data with the Radiation Pro-tection Supervisor
, b) E the whole body dose rate b) E onsite Protective Action exceeds 1 REM /HR in occupied Guidelines are NOT exceeded, areas of the plant recommend evacuation to low radiation area OR l
For thyroid exposure recom-mend sheltering in closed buildings. , OR , E projected thyroid exposure may exceed 5 REM (see attach-ment 2,): Recommend evacuation of onsite personnel NOT required for emergency response
- 6. BRIEF EMERGENCY MANAGER a) Provide RECOMMENDATIONS from l Step 2 OR Step 5 to the Emer-gency Manager b) Review with the Emergency -
Manager, assumptions made in Step 2_ E Step 5. Answer any questions concerning calcu-lations 7. RETURN TO CONTROLLING PROCEDURE l l a) Upon completion of this pro-cedure RETURN to EPIP-4.01, i Radiological Assessment Direc-cor Controlling Procedure _ _ . _ . . _ ~ . . _ . . . . . . . .;
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, NUMBER PROCEDURE TITLE REVISION 03 EPIP-4.07 PROTECTIVE MEASURES PAGE 7 of 7
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 8. PROCEDURE COMPLETION a) COMPLETED BY: -
DATE: TIME: G 6 END w_.._.._..- _ _._. -..
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NUMBER A TTACHMENT TITLE REVISION EPIP-4.07 03 STATE OF VIRGINIA A TTACHMENT PAGE 1 PROTECTIVE ACTION GUIDELINES 1 of 1 OFFSITE: PROJECTED DOSE PROTECTIVE ACTIONS Less than 0.5 rem whole body. ,0_R R No protective action necessary E Less chan 1.0 rem thyroid radiological situation is unstable, consider recommendation of citizen
. alert.
0.5 - 2.0 rem whole body O_R, - Recommend sheltering of public 1.0 - 12.0 rem thyroid
' Greater than or equal,to 2.0 rem Recommend evacuation of affected whole body 3 3 rem thyroid sectors ONSITE:
PROJECTED DOSE PROTECTIVE ACTIONS
/
Less than 1.0 rem whole body 3 Recommend sheltering Less than 5.0 rem thyroid Greater than or equal to 1.0 rem Reconenend site evacuation whole body OR Greater than 5.0 rem thyroid
)
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No. 97887220 NUMBER A TTACHMENT TITLE REVISION EPIP-4.07 03 THYROID EXPOSURE A TTACHMENT VERSUS PAGE 2 IODINE CONCENTRATION 1 of 1 l
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m .oreersse NUMBER A TTACHMENT TITLE REVISION EPIP-4.07 03 EVAUCATION VERSUS SHELTER A TTACHMENT PAGE 3 WORKSHEET 1 of 2 i
- 1. Determine approximate DISTANCE to POINT OF INTEREST MILES NOTE: Use furthest distance in which protective action guidelines for sheltering have been exceeded.
- 2. Calculate DOSE RATE at d'istance or point of interest mR/HR
- 3. Estimation of RELEASE DURATION HOURS
- 4. PROJECTED DOSE = DOSE RATE X RELEASE DURATION 1000
- 5. WIND SPEED MPH
- 6. PLUME TRAVEL TIME = DISTANCE (miles)* HOURS WIND SPEED (mph)
- 7. Time SINCE OR UNTIL, BEGINNING OF RELEASE a) IF RELEASE HAS BEGUN: .
TIME RELEASE HAS BEEN IN PROGRESS HOURS i b) IF, RELEASE WILL BEGIN: RELEASE WILL START IN HOURS
- 8. TIME UNTIL EXPOSURE BEGINS:
l l a) IF RELEASE HAS BEGUN: l E en.6 - Item _7a HOURS b) IF RELEASE WILL BEGIN: E en 6 + Item 7b HOURS
- 9. EVACUATION WEATHER CONDITIONS:
NORMAL ADVERSE
- 10. Use distance and weather conditions to obtain ESTIMATED .,
EVACUATION TIME from Attachment 4 # HOURS-1 13 4 $$ g ., 4 Se g S -- m>ee 6peM M 4 -4@w en G c.. - .m,. _. ~ y .w. , _y.g.-._ , y __ g .., _
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e._& . _ I. _ _ _ _ . .fw_ _._1;__. No. 97847220 NUMBER A TTACHMENT TITLE REVISION EPIP-4.07 03 EVAUCATION VERSUS SHELTER A TTACHMENT ppgg 3 WORKSHEET 2 of 2 l l s_ 11. EXPOSURE TIME Evacuation Time - Time until exposure begins HOURS NOTE: H time until exposure begins is longer than Evacuation time, enter ZERO HOURS
- 12. EVACUATION EXPOSURE PERIOD:
Smaller of either exposure time or Release Duration Time HOURS
- 13. PROJECTED DOSE REM
- 14. EVACUATION DOSE:
EVACUATION EXPOSURE PERIOD X DOSE RATE , 1000 REM
- 15. SHELTERING DOSE:
l PROJECTED DOSE x STRUCTURE SHIELDING FACTOR
- RE!!
- NOTE: FOR WHOLE BODY = 0.9 THYROID = 0.65 END
= .- . --- -- . . . _ . . . . . _ ___i
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NUMBER A TTACHMENT TITLE REVISION EPTP-4.0/ 0'l A TTAe WENT EVACUATION TIMES FOR NORTH ANNA POWER STATION PAGE 4 1 of 1 AREA TIME, EVACUATION EVACUATION TIME NORMAL TIME ADVERSE CONDITION CCNDITION Total Area Within 2-Miles 2:15 2:15 WITHIN 2-5 MILES Louisa-Co. 2:15 2:15 Spotsylvania Co. 2:15 2:15 WIMIN 5-10 MILES Louisa Co. 2:45 3:30 Orange Co. 2:15 2:15 Hanover Co. 2:15 2:15 Caroline Co. 2:15 2:15 Spotsylvania Co. 2:45 3:30
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' No. 97887220 NUMBER A TTACHMENT TITLE REVISION 1:'p T D-4 . 0 7 01 A TTAC#WENT NORTH ANNA SECTOR MAP PAGE 5 1 of i m
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esa. oreanos VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCEDURE TITLE REVISION 03 EPIP-4.08 INITIAL OFFSITE RELEASE ASSESSMENT PACE (With 8 Attachments) 1 of 11 PURPOSE i Initially assess consequences of offsite releases or potential offsite i releases. } USER 1 l Radiological Assessment Director OR Members of Dose Assessment Team. I i ENTRY CONDITIONS
- 1. Activation from another EPIP, 8
- 2. Entry from other EPIPs 3
- 3. Direction of the Station Emergency Manager.
SAFETY RELATED REVISION RECORO REV. 00 PAGE(S): Entire Procedure DATE: 07-02-82 REV. 01 PAGE(S): Entire Procedure DATE: 07-22-82 REV. 02 PAGE(S): Entire Procedure DATE: 09-01-82 REV. 03 PAGE(S): Entire Procedure DATE: 05-24-83 REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: APPR Al R MMENDEO APPROVE 0 QA TE g 05-24-83
'l , CHAIRMAN STA TION NUCLEAR SAFETY AND CPERA TING COMMITTEE- - -- - - - - - - - ~ ~ - - - - "
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No. 97847210 NUMBER PROCEDURE TITLE REVISION 03 EPIP-4.08 INITIAL OFFSITE RELEASE ASSESSMENT PAGE 2 of 11
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 1. INITIATE PROCEDURE:
a) ' BY: DATE: TIME:
- 2. DETERMINE EMERGENCY CLASSIFICATION:
a) E the Emergency is an Unusual a) E a Site E General Emer-Event 3 Alert, continue with gency, GO TO Step 4. this instruction
- 3. DETERMINE PERCENT TECHNICAL SPECIFICATION:
NOTE: Evaluation of percent technical specifications in this Step makes conservative assumpcions about flow rate, isotopic mixture and detector response. Further analysis upon completion of this procedure will be necessary to quantify release. a) Obtain from operations the number of the monitor in alarm and log on Attachment 1 , b) Requesc from the Emergency l Manager, placement of an j individual to observe monitor l in alarm and report increase l or decrease in readings. _ c) Obtain HIGHEST CPM, above c) IF monitor is offscale OR background, of monitor in not functional GO E Step 4_. Substep a,and log on Attach-ment 1 m = a m
~~ mwdl.gf.,gx :n *:mL T~* z w ~ E ~: . .&:. a: '
. . , . - ='x No. 97487210 NUMBER PROCEDURE TITLE REVISION 03 EPIP-4.08 INITIAL OFFSITE RELEASE ASSESSMENT PAGE 3 of 11
- STEP ACTIONNXPECTED RESPONSE RESPONSENOTO8TAINED
- 3. (CONTINUED) d) Determine release rate:
- 1) Gaseous 1) Continue with this instruction.
CFM
- 2) Liquid - request the 2) CO,,, TO, Substep e_.
number of circulating water pumps running NOTE: E more than one monitor is in alarm, the TOTAL percent Tech Spec will be the SUM of the percent from EACH monitor. DO,NOT sum per cent from liquid monitors and gaseous monitors together. Liquid releases must be totaled separately from gaseous releases e) Determine the percent' Tech-
- e) E monitor of interest is NOT nical Specification from the listed in the attachments, ~Go the appropriate FIGURE in TO_ Step 8_, for follow-up Attachment 2_, and log on assessment.
Attachment 1,, NOTE: E the percent of technical specification is GREATER THAN OR -- EQUAL TO 100% but LESS TRAN 1000%, UNUSUAL EVENT emergency condition exists. O,,,R, E percent technical specifications is GREATER THAN OR EQUAL TO 1000% but LESS THAN 50 mR/HR, ALERT emergency condition exists. f) Report results to the Emergency Manager
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m x. . , w .1 . c_.~ .g ._ w.uw.- - .. ~ _ _ No. 97087210 NUMBER PROCEDURE TITLE REVISION
~
03 EPIP-4.08 INITIAL OFFSITE RELEASE ASSESSMENT PAGE 4 of 11
- STEP ACTION /EXPECTE0 RESPONSE REiPONSENGT08TAINE0
- 3. (CONTINUED) g) E the percent of Tech Specs g) E the percent Tech Specs are is GREATER THAN OR EQUAL TO LESS THAN 1000% Go TO Step 8,.
1000% gR, E site boundary ' DOSE RATE is requested, continue with this instruction
- 4. DETERMINE SITE BOUNDARY WHOLE BODY DOSE RATE:
a) Request from the Emergency Manager, placement of an individual to observe the monitor in alarm and report increase or decrease in readings . b) H release path through b) E NORMAL RANGE MONITORS are ! PROCESS VENT, VENT VENT OFFSCALE, GO E Substep c. ! OR AIR EJECTOR AND 1 l NORMAL RANGE monitors are l ONSCALE: i l l NOTE: IF AIR EJECTOR is diverted to containment, NO release from l this pathway should be considered. l ee&m O
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c . No. 97867210 NUMBER PROCEDURE TITLE REVISION 03 EPIP-4.08 INITIAL OFFSITE RELEASE ASSESSMENT PAGE 5 of 11
- STEP ACTION /EXPECTEU RESPONSE RESPONSENOTOBTAINED
- 4. (CONTINUED)
- 1) Obtain the NUMBER of the MONITOR OF INTEREST and log on Attachment 3_:
VENT VENT A (VG-104) l E VENT VENT B (VG-113) , E PROCESS VENT (GW-102) 4 3 AIR EJECTOR (SV-121,221)
- 2) Obtain the CPM, abova background, for MONITOR OF INTEREST CPM
- 3) Obtain, from the Emergency Communicator the STABILITY CLASS AND WIND SPEED STABILITY CLASS WIND SPEED
- 4) Obtain CONVERSION FACTOR from Attachment 6 using the Monitor of Interest and Stability Class CONVERSION FACTOR W4 4habmm * **=h m.... _ .
w --w--= =. :--w :s- - - - < ~
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c- - es .oresnio NUMBER PROCEDURE TITLE REVISION 03 EPIF-4.08 INITIAL OFFSITE RELEASE ASSESSMENT PAGE 6 of 11
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 4. (CONTINUED)
- 5) Determine SITE BOUNDARY DOSE RATE:
CPM X CONVERSION FACTOR , mR WIND SPEED HR
- 6) Log mR/HR on Attachment 3
- 7) Go,T_0. 0 Step 5 c) E the release path is c) E HIGH RANGE MONITORS are through the PROCESS VENT NOT onseale, recommend OR VENT VENT and normal emergency classification of range monitors are OFFSCALE UNUSUAL EVENT and GO TO and the high range monitoring Step 8,.
are onscale: 3 E release is through the MAIN STEAM SYSTEM CO TO Substep d_.
- 1) Obtain the hUMBER of the MONITOR OF INTEREST and log on Attachment 3_
PROCESS VENT (RM-GW-173) l OR l VENT VENT A (RM-VG-174) E VENT VINT B (RM-VG-175)
- 2) Obtain from operation the mR/HR of monitor of interest mR/HR
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No. s7es7:10 NUMBER PROCEDURE TITLE REVISION 03 EPIP-4.08 INITIAL OFFSITE RELEASE ASSESSMENT PACE 7 of 11
- STEP ACTION / EXPECTED RESPONSE RESPONSEN0TOBTAINED
- 4. (CONTINUED)
- 3) Convert mR/HR to pCi/cc using Attachment 5, UCi/cc
- 4) Obtain from the Emergency Communicator the STABILITY CLASS and WIND SPEED 1
STABILITY CLASS WIND SPEED
- 5) Using Stability Class and Monitor of Interest obtain the CONVERSION FACTOR from Attachment 6 CONVERSION FACTOR
- 6) Determine SITE BOUNDARY DOSE RATE uCi/cc X CONVERSION FACTOR mR WIND SPEED *E
- 7) Log mR/HR on Attachment 3
- 8) g 3 Step 5 d) H release path or potential c) g 3 Step 5 release path is through the _ . _
STEAM SAFETY RELIEF VALVES g through the AUXILIARY FEED- _. WATER PUMP TURBINE EXHAUST (AFFT), continue with this instruction - l i I
-..-}.
1
Qgqp3: ygQ,,ye -: ' . a_: _ = . .N . . .a ~_ %;; _, . . g a_.u:u e - - _ , .~. --- .. - L. P60.97947211 NUMBER PROCEDURE TITLE REVISION 03 EPIP-4.08 INITIAL OFFSITE RELEASE ASSESSMENT PAGE 8 of 11
- STEP ACTION l EXPECTED RESPONSE RESPONSENOTO8TAINED
- 4. (CONTINUED)
- 1) Obtain from Emergency ,
Manager, the mR/HR of monitor in alarm - Main Steam Unit #1 RM-MS-170 RM-MS-171 RM-MS-172 Main Steam Unit #2 RM-MS-270 . RM-MS-271 RM-MS-272 OR AuxilTa'ry Feec'. water Pump Turbine Exhaust (AF?T) RM-MS-176 RM-MS-276 NOTE: If Auxiliary Feedwater Pump is isolated, no release is assumed from this pathway.
- 2) Obtain from the Emergency l Communicator the STABILITY
- l CLASS AND WIND SPEED ,
- 3) Obtain from Attachment 6,the appropriate CONVERSION FACTOR for the MAIN STEAM monitor and/or the AFPT monitor l
l
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Peo.steerste 1 NUMBER PROCEDURE TITLE REVISION 03 EPIP-4.08 INITIAL OFFSITE RELEASE ASSESSMENT PAGE 9 of 11
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 4. (CONTINUED)
- 4) Obtain SITE BOUNDARY DOSE RATE:
i mR/HR (MONITOR) X CONVERSION FACTOR , mR WIND SPEED HR NOTE: IF release is through BOTH the Main Steam AND the Auxiliary Feedwater Pump Turbine Exhaust, the results from both moni-tors are ADDITIVE.
- 5) Log mR/HR on Attachment 3_
- 5. DETERMINE SITE EOUNDARY THYROID DOSE RATE a) Determine SITE BOUNDARY WHOLE
! BODY DOSE RATE f rom Attachment
-3.
b) Determine CONVERSION FACTOR versus type of accident listed - in Attachment 8. c) Multiply to determine SITE BOUNDARY THYROID DOSE RATE. Step a x Step b = mR/HR d) Log results on Attachment 4
- 6. DETERMINE DOSE RATE AT 2, 5 "- --
AND 10 MILES: ~ " ' " - a) Obtain the STABILITY CLASS from Step 4 and SITE BOUNDARY DOSE RATE Tor whole Body and Thyroid from attachment 3 and 4 _.-4 l
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I e .steenio l NUMBER PROCEDURE TITLE REVISION 03 EPIP-4.08 INITIAL OFFSITE RELEASE ASSESSMENT PAGE 10 of 11
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTODTAINED
- 6. (C0yINUED) b) Use Attachment 7 to deter-mine the MULTIPLICATION FACTOR c) Perform calculations to determine the 2. 5 and 10 mile DOSE RATE:
DOSE RATE X MULTIPLICATION FACTOR = d) Log on Attachment 3 or 4
- 7. , REPORT RESULTS NOTE: E site boundary dose rate is GREATER THAN OR EQUAL TO 1.0 REM /HR Whole BodyROR 5.0 REM /HR Thyroid, notify the Emergency Manager that a GENERAL EMERGENCY condition exists.
9.R_ E site boundary dose rate is GREATER THAN OR EQUAL TO 50 mR/HR for 30 minutes 500 mR/HR for 2 minutes Whole body (OR 5 times these levels to the thyroid) Notify the Emergency Manager that a SITE EMERGENCY condition exists. a) Report results of attachment -- -- - - . 3 OR 4 inanediately to the Emergency Manager - - r - .
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. eso. orsente NUMBER PROCEDURE TITLE REVISION 03 EPIP-4.08 INITIAL OFFSITE RELEASE ASSESSMENT PAGE 11 of 11
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 8. RETURN TO CONTROLLING PROCEDURE a) Upon completion of this pro-cedure, return to EPIP-4.01, l Radiological Assessment l Director Controlling Procedure 1
- 9. PROCEDURE COMPLETION: I a) COMPLETED BY:
DATE: TIME: 0 1 1 l l G e
.------..------9
_____ __-______________AA.____ _s.--mmt_ _ . _ _ _ _ _ _ _
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r-No.97017330 NUMMR A TTACHMENT TITLE REVISION EPIP-4.08 03
% TECHNICAL SPECIFICATION DATA SHEET -
ATTACHMENT FAGE I L of 1 MONITOR NET COUNT PER MINUTE % TECH. SPECS s D I W
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No.97807220 NUMBER A TTACHMENT TITLE REVISION l EPIP-4.08 03 INITIAL OFFSITE RELEASE A TTACHMENT ASSESSMENT PAGE 2 VENT VENT A (VG 104) 1 of 6 s. s
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'A 4.65E-6 1.47E-7 1.03E-8 2.12E-6 ,
B , 4.17E-5 1.32E-6 9.22E-8 1.90E-5 C 1.51E-4 4.78E-6 3.34E-7 6.88E-5 D 4.48E-4 1.41E-5 9.89E-7 2.04E-4 E 8.75E-4 2.76E-5 1.93E-6 3.98E-4 F 1.84E-3 5.80E-5 4.06E-6 8.35E-4 G 3.54E-3 1.12E-4 7.83E-6 1.61E-3 VG-174 VG-175 GW-173 High Range High Range High Range Vent Vent A Vent Vent B process Vent,
, A 2.25 E-1 1.70 E-1 4.85E-4 B 2.01 E+0 1.53 E+0 4.34E-3 C 7.30 E+0 5.54 E+0 1.57E-2 D 2.16 E+1 1.64 E+1 4.66E-2 E 4.22 E+1 3.20 E+1 9.11E-2 F 8.86 E+1 6.72 E+1 1.91E-1
.G 1.71 E+2 1.30 E+2 3.69E-1 i
, Main Auxiliary Feed Steam Pump Turbine Exhaust A 4.82 E-1 8.53E-1 l B 4.32 E+0 7.65E+0 l C 1.57 E+1 2.77E+1 D 4.63 E+1 8.21E+1 E 9.06 E+1 1.60E+2 i F 1.90 E+2 3.37E+2 i G 3.66 E+2 6.49E+2 l l .
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7 1 of 1 STABILITY CLASS Distance A B C D E F G Miles 2 3.59E-1 1.09E-1 2.34E-1 2.71E-1 2.89E-1 3.31E-1 4.14E-1 5 1.5bE-1 2.30E-2 4.84E-2 6.78E-2 8.38E-2 9.64E-2 1.36E-1 10 8.15E-2 1.21E-2 1.54E-2 2.49E-2 3.47E-2 3.99E-2 5.64E-2 1 i
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- 1. LOCA 0.5 27
. 1.0 32 1.5 36 2.0 41 2.5 46 3.0 ,
51 3.5 57 4.0 62 4.5 69 5.0 75 6.5 98 8.0 123 10.0 158 12.5 209 15.0 258 24.0 389 48.0 707 72.0 758 i
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No.97887223 NUMBER A TTACHMENT TITLE REVISION EPIP-4.08 03 A TTAC# MENT THYDOID DOSE CONVERSION FACTORS PAGE 8 2 of 2 FILTERED ACCIDENT (CHARCOAL) UNFILTERED
- 2. Primary Gas Release 6.46 E + 0 6.46 E + 1
- 3. Steam Generator Tube Rupture 2.09 E + 2
- 4. Fuel Handling Accident 5.37 E + 2 9.30 E + 3
- 5. Waste Gas Decay Tank 5.37 E - 3 5.37 E - 2
- 6. Main Steam Line Break (with prior primary to secondary leakage) 3.50 E v 1 3.50 E + 2 O
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/ he. ores 720o VIRGINIA ELECTRIC AND POWER COMPANY l NORTH ANNA POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCEDURE TITLE REVISION 03 EPIP-4.09 SOURCE TERM ASSESSMENT PAGE (With 4 Attachments) 1 of 9 l PURPOSE _ Provide guidance and data to Dose Assessment Team to more accurately predict offsite releases. USER Dome Assessment Team Members. ENTRY CONDITIONS Upon activation of EPIP-4.03, Dose Assessment Controlling Procedure. {h REVISION RECORO REV. 00 PAGE(S): Entire Procedure DATE: 07-02-82 REV. 01 PAGE(S): Entire. Procedure DATE: 07-22-82 REV. 02 PAGE(S): Entire Procedure DATE: 09-01-82 REV. 03 PAGE(S): Entire Procedure DATE: 05-24-83 REV. PAGE',S) : DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: APPROVAL RE MENDED APPROVE 0 CA TE q 05-25-83 CHAIR.AN STA TION NUCLEAR SAFETY _ _ > ,N00,ER,,,NOca ,,,E - .. . _ ..
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No.97847210 NUMBER PROCEDURE TITLE REVISl0N 03 EPIP-4.09 SOURCE TERM ASSESSMENT PAGE 2 of 9
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 1. INITIATE PROCEDURE:
a) BY: DATE: TIME:
- 2. SOURCE TERM ASSESSMENT:
a) Source Term (C1/sec) may
. be obtained from any of the following:
- 1) Normal range STATION MONITORS
- 2) SAMPLE EFFLUENT
- 3) SAMPLE of STATION INVENTORY
- 4) CONTAINMENT PERSONNEL HATCH MONITOR
- 5) SAMPLE of CONTAINMENT AIR
- 6) ENVIRONMENTAL SAMPLE DATA b) SOURCE TERM based on MONITOR readings should be used only for INITIAL assessment and to establish TRENDS c) IF source term is obtained from a monitor reading, sampling should be done to more accurately determine the source term d) Source term will have the ~'
UNITS of CURIE /SEC 8
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. NUMBER PROCEDURE TITLE REVISION 03 EPIP-4.09 SOURCE TERM ASSESSMENT PAGE 3 of 9
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED e) SOURCE TERM obtained from Containment High Range Monitor
,0_R R Containment Sampling is used for analysis following a Loss of Coolant Accident
- 3. SOURCE TERM - NORMAL STATION MONITORS:
NOTE: E MORE THAN ONE effluent pathway is involved in a release, repeat this step for ALL PATHWAYS involved and ADD the results for TOTAL release. a) SOURCE TERM may be obtained a) E normal range monitors are from the following MONITORS: offscale, GO TO Step 4_.
- 1) VENT VENT A VG-104 OR OR IF release pathway is through the main steam system, GO TO
, 2) VENT VENT B VG-113 Step _10,.
OR
- 3) PROCESS VENT GW-102 OR
- 4) CONDENSER AIR EJECTOR
_ . - "~' SV-121. SV-221 NOTE: CONDENSER AIR EJECTOR may be diverted to containment. b) Obtain the CPM, above
~ - ~ ~ ~ ' - ~ ~~ - ~ ~ ' ' ' - '
background, for monitor ~ ~ ~ ~ ~ ~ ~ of interest l l 2._.. ... _ _ . . . . . . . _ - . . . - . . . . . - . - . . _ . . . - - . .-
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Peo. 97847210 NUMBER PROCEDURE TITI.E REVISION 03 EPIP-4.09 SOURCE TERM ASSESSMENT PAGE 4 of 9
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOSTAINED
- 3. (CONTINUED)
- 1) Log the DATE, TIME, MONITOR number and the net CPM of Attachment I c) Obtain the FLOW RATE (CMI) effluent pathway d) Obtain CONVERSION. FACTOR for monitor of interest:
- 1) VG-104 4.29E-10 E
- 2) VG-113 1.75E-11 E
- 3) GW-102 4.29E-10 E
- 4) SV-121, SV-221 1.10E-6 e) Perform the following calcu-lations to obtain Ci/see (Xe-133 Equivalent)
CPM X CONVERSION FACTOR I CFM = C1/SEC
- 1) Log results on Attachme e
- 4. SOURCE TERM - SAMPLE EFFLUENTS:
NOTE: I_F, F MORE THAN ONE af fluent pathway is involvad in the release, repeat this step for ALL PATHWAYS involved and ADD the results for a TOTAL release. e W L______ ____ _ _ - _ _ _ _ _ _ _- _ __
. :. _ .w - -..u.---.- ..: 4. ~~ * ~ su :2 - '
No.97887210 NUMBER PROCEDURE TITLE REVISION 03 EPIP-4.09 SOURCE TERM ASSESSMENT PAGE 5 of 9
- STEP ACTION / EXPECTED RESPONSE RESPONSENOT08TAINED
- 4. ~(CONTINUED) a) Request Radiation Protection a) E sampling not required, Supervisor to activate EPIP- Go TO Step 5.
4.24, Gaseous Effluent Sampling During an Emergency, to obtain a sample of one of the following:
- 1) VENT VENT A OR VENT VENT B_
E
- 2) PROCESS VENT E .
- 3) CONDENSER AIR EJECTOR NOTE: CONDENSER AIR EJECTOR may be diverted to containment, elimi-nating need to assess source term.
b) Have sample analyzed as per normal count room procedures OR EPIP-4.26. High Level Activity Sample Analysis
- 1) Log results of the analysis on Attachment 2 c) Perform calculations on Attachment 2 to obtain EQUIVALENT ACTIVITY I-131 OR Xe-133 (uC1/ml) --
i 1 l.-. _ _ ~ - ..... _ - - - - - - - - - - - - - . . - - - - - - --- - - l j _ _
No. 97047213 NUMBER PROCEDURE TITLE REVISION 03 EPIP-4.09 SOURCE TELM ASSESSMENT PAGE 6 of 9
- STEP ACTIONNXPECTED RESPONSE RESPONSFNOTOBTAINED
- 4. (CONTINUED) d) Obtain FLOW ~ RATE of effluent pathway
- 1) Convert CFM to MLS/SEC CFMx472=hg e) Calculate SOURCE TERM (C1/SEC)
EQUIVALENT ACTIVITY X FLOW RATE , Ci/SEC 1.00 E + 6
- 5. CORRECT SOURCE TERM FOR MAXIMUM RELEASE:
a) E sample from Step 4 was a) GO TO Step E a grab sample and NOT obtained at maximum release, correct for maximum source ters:
- 1) Obtain the maximum monitor .
reading
- 2) Obtain monitor reading at time of sample
- 3) Perform following calcula-tion to obtain MAXIMUM RELEASE RATE:
Mn r S mple x S urce Term = Maximum /SEC
- 6. SOURCE TERM - STATION INVENTORY:
a) E release originated from a a) g g Step 7 gas storage tank (ie. Waste Gas Decay Tank, Volume Control Tank, etc.) sample the activity + remaining in the tank 4 oa. t y .* '- j.. , " t * .4-*-;,p, f4 , ~. Q,., a [,,,,
~~ " . . . . .
l .C.s u A i AL.,-. . . .- . ~ J a .... w. - . %' l4'.' L O%.l '** -.
-ia -. ..: - - ~.~W-~.
Peo. 97887210 NUMBER PROCE00RE TITLE REVISION 03 EPIP-4.09 SOURCE TERM ASSESSMENT PAGE 7 of 9
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 6. (CONTINUED) b) Determine VOLUME of release from the following equation:
VOLUME = 1I2T 12
- 1) Pg= pressure PRIOR to
. release
- 2) P2 " Pressure AFTER release NOTE: Error in calculation of VOLUME of gas may result due to water level in tank. IF tank has water in it, subtract volume occu-pied by the water from the design volume of the tank.
- 3) V = design volume of tank 1
- 4) T g= Temperature prior to release (Tg = *F + 459)
- 5) T
- temperature after 2
release (T2 = *F + 459)
- 6) Convert volume of release ft x 2.832E+4 - MLS c) Convert activity determined from above Substep a_ to.
EQUIVALENT I-131 and/or Xe-133 ACTIVITY using Attachment 2
- ~
d) Perform the following calcu-lations to determine SOURCE TERM: VOLUME (mis) X EQUIVALENT ACTIVITY = C1/SEC 1.00E+6 x Time of Release (Seconds)
. ~ . _ _ _ . _ . . . . . _ _ . . _ . -- - .. . ;
-p g , . - ,
.--..[N
f - [._ . _[_ _ _ . _
~ ~-
a _ _, m __. _ a -._ No. 97947210 NUMBER PROCEDURE TITLE REVISION 03 EPIP-4.09 SOURCE TERM ASSESSMENT PAGE 8 of 9
~ STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 7. SOURCE TERM - CONTAINMENT PERSONNEL HATCH MONITOR:
a) E LOCA conditions exist a) GO TO Step 9. obtain the DOSE RATE (mR/hr) from Containment High Range Monitor of affected unit b) Obtain length of TIME (HOURS) since SHUTDOWN of. UNIT c) Determine the extent of fuel damage using Attachment 3, d) Use information from above Substep b and c and attach-ment 4 to determine equivalent curies I-131 and Xe-133, available for release NOTE: E rupture of containment is imminent, consider ALL activity in Substep d_, available for release. e) Determine RELEASE RATE
- 1) Calculate release rate:
Equivalent CURIES X 4.35 E-8 = Ci/SEC
- 8. SOURCE TERM - CONTAINMENT SAMPLE:
a) IF LOCA conditions exist, Equest the Radiation - ~ ~ Protection Supervisor to activate EPIP-4.22. Post ~~ ~~ ' Accident Sampling of Con-
~~ ~
tainment Air ' g g eee 4 -m a bW - 4 mh, gag 4 . w-i e6w
~
c --
. ,:_n -- - . . - . . . A: '
"r*- &:2 ' '
-u No.97047219
~
NUMBER PROCEDURE TITLE REVISION 03 - EPIP-4.09 SOURCE TERM ASSESSMENT PAGE 9 of 9
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 8. (CONTINUED) b) Convert the results of the analysis of the Containment Air Sample to EQUIVALENT I-131 and Xe-133 activity (uci/ml), using Attachment 2_
c) Determine RELEASE RATE:
- 1) EQUIVALENT CURIES x 2.25E-3 = C1/SEC
- 9. SOURCE TERM - ENVIRCNMENTAL DATA a) IF the source term can NOT be a) IF, release pathway is estimated from onsite sampling monitored OR,able to be and/or monitor reading, return sampled, GO TO Step H.
to the controlling procedure, obtaining the source term from environmental monitoring data
- 10. RETURN TO CONTROLLING PROCEDURE a) Upon completion of this ~
procedure, RETURN TO EPIP-4.03 Dose Assessment Controlling Procedure
- 11. PROCEDURE COMPLETION:
a) Completed By: 1 Date: I j Time: BP .
. . . . ._ 1 1
s._... END ._ _ _ . _ . . . _ . _ _ . _ , _ _ _ _ _ . _ . . _ 1 I
.r - - -+ e- r--.-
no.oreersso 4 NUMBER A TTACHMENT TITLE REVISION EPIP-4.09 03
- MONITOR DATA SHEET ATTACHMENT PAGE 1 ~1 of 1 f
l. CONVERSION DATE TIME MONITOR CPM FACTOR CFM Ci/SEC (Xe-133) e 4 o S m 0 9 k r 'l s I
- . . . - , m. . . - . _ . . .m. -_ _.- . ...
... , a. . . .u. . . . . .
. . . _ .c: 3m ts e': '.
.- , e
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- s. . . . k .. .J -- . -- . - . . L-- ~L.L..JL.~ : *L '--- :
Peo.97887220 NUMBER A TTACHMENT TITLE REVISION EPIP-4.09 03 1 EQUIVALENT ACTIVITY Xe-133 A TTACHMENT IMtERSION DOSE PAGE 2 1 of 2 ACTIVITY DOSE EQUIVALENT EQUIVALENT NUCLIDE uCi/ml or Ci FACTOR ACTIVITY A B AxB KR-83M 5.49E-2 KR-85 5.03E-2 KR-85M 3.55E+0' KR-87 1. 78 E+ 1 KR-88 4.56E+1 KR-89 4.20E+1 XE-131M 4.30E-1 XE-133 1.00E+0 XE-133M 9.09E-1 XE-135 5.57E+0 XE-135M 9.74E+0 XE-137 4.12E+0 XE-138 2.54E+1 I-130 4.79E+1 T-131 8.57E+0 l I-132 5.13E+1 I-133 1.37E+1 I-134 5.91E+1 1-135 3.55E+1 E of EQUIVALENT XE-133 = _ _ ew.. w. . m-.. ,...wew *' - * * * " ** * **"* *' '"*""h **
- h 8-
- Wmpae ewe 6 g *. h 64..
~ ' " ^
'er -
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Pee. 97687220 NUMBER ATTACHMENT TITLE REVISION EPIP-4.09 03 EQUIVALElrI ACTIVITY'I-131 A TTACHMENT INEALATION DOSE PAGE 2 2 of 2 ACTIVITY DOSE EQUIVALENT EQUIVALENT NUCLIDZ uC1/ml er Ci FACTOR ACTIVITY A B AxB I-130 1.14E-1 I-131 . 1.00E+0 I-132 1.19E-2 I-133 2.37E-1 I-134 3.12E-3 I-135 4.87E-2 E of EQUIVALENT I-131 = uCi/ml or Ci
- . 4. . %
5
. = +.,
~
.en . . ~ . . .. .. : . w :. . .
. . . . . . ... . ., . . ~ . . . . . .
-N@.97887223 NUMBER A TTACHMENT TITLE REVISION EPIP-4.09 03 PERSONNEL HATCH MONITOR A TTAC# MENT DOSE RATE (MR/HR) VERSUS TIME PAGE I 3 1 of 1 g7 t' n T en . un - r' t- . e no g
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t No. 97887220 NUMBER A TTACHMENT TITI.E REVISION EPIP-4.09 03 EQUIVALENT CURIES Xe-133 FOR LOCA ACCIDENT A TTACHMENT PAGE 4 1 of 2 lOhVA NT URI F RA e AA forNT g
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M a No. 97!87220 NUMBER A MCHMENT TITLE ggy,,,g, EPIP-4.09 Q ENT CURIES I-131 FOR LOCA ACCIDENT ATTACNMENT ppgg 4 , 2 of 2 NOTE: Within the first 8 hours following LOCA incident, IODINE decay is insignificant. EQUIVALENT CURIES EVENT I-131 LOCA 3.52 E+2 (1% Clad Failure) LOCA 3.85 E+5 (100% Clad Failure) LOCA 5.93 E+5 (1% Fuel Hele) LOCA 5.93 E+6 (10% Fuel Mele) LOCA 5.93 E+7 (100% Fuel Mele) _. .. **h
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,-._ _ .' g _ 2 .. . . .z :.. . : . . _ _ .e ...t. . _ . . . .. . . _ . m . a. :. ._ , . . . a .
# No.97847200 1",
'~
VIRGINIA ELECTRIC AND POWER COMPANY - . NORTH ANNA PdWER STATION ' 4 ^'
~ ',,
EMERGENCY PLAN IMPLEMENTING PROCEDURE l l NUMBER PRGCEDUFF (??lV :~ ' REVISION .
- . . '03 EPIP-4.10 DETERMINATION OF X/Q PAGE (With 5.Attaquents)' . t of 5 PURPOSE
. _ . _ .~.
1- - s Determine atmospheric diffusion factor, X/Q. '
.- '.f -
~
s_ - _ ~' i USER ~ m-s, s
., ,m .
Radiological Assessment Director ond/or Dose Assessment Team. ' r _- - ENTRY CON 0lTIONS , 4 s , Activated by EPIP-4.03, Dose Asatssment Con'folling' t Procedure
.~ ne L
N FEW RELMED E , n. _ , s_ _ s REVISION RECORD -< " ' REV. 00 REV. 01 PAGE(S): Entire Procedure PAGE(S): Entire Procedure
- J 'i-. ,
- ,DATE: 02-82
.DAT! 07-22-82 DQ
- REV. 02 9 ,
PAGE(S): Entire Procedure --
~DATE: 09-0 M 2 REV. 03 PAGE(S): Entire Procedure DATE: 0544-B'3 "
REV. PAGE(S): -; ' '
~
DATE: , REV. PAGE(S): ~ DATE: .- REV. PAGE(S): , DATE:, n _h_ APPROVAL RECOMMENDEO APPR0bi DA TE W - 05-24-83 , R,( ~CHAl MANSTATIONNUCLEARSAFETY ANO QPERA TING COMMITTEE
$_tg, 9-
,3 _ 7 _ . . _ . , . _ _ . . . .....;.
x
m- ' ' ' . 466.w. .' 4 --
. ._ M a-. '. m. - . -.C ~A....dws; - --
Peo. 97tS7210 * - e NUMBEt' PROCEDURE T;TLE REVIS10N
~
03 EPIP-4.10 DETERMINATION OF X/Q-PAGE 2 of 5 ( . _=
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 1. INITIATE PROCEDURE:
s a) Initiated By: Date: Time:
- 2. DETERMINE CENTERLINE X/Q AT PREDETERMINED DISTANCE n
a) E X/Q is for site boundary a) E X/Q is needed for other and/or distance of 0.25 mile distances, GO TO, Step 3.
*~ increments,' continue with
,. , , this instruction.
' -C ' 1) Obtain from the Radio- 1) Obtain information from D, '
s logical Assessment the Emergency Communicator Director: if Padiological Assessment Director NOT available.
.f .
. Wind Speed
.v
-; " AND Stability Class -
, , ss -
.' 2) Determine distance (miles) for which X/Q is to be '
calculated
- 3) With Stability Class,
, Wind Speed and Distance
, determine X/Q from Attach-
'. ment 1. -
~. -
, < _ ,/ . u- 4) Correct X/Q from Substep 3,for current vind speed:
"s r s,?
X/o
,- Actual X/Q = WIND SPEED (mph)
A
,~
t 'y A
+ % .
e
' ' ~
w . e. ,y- - .* v. t I k (p. .. . . . . . .. .._.. ._. .. . . . _ . . . . - - . . . . . . . - . . - - - - . .
, .p , , .
+
Akp ' f .. Ly ._ _ _ L.
^ '
- . -i
-.~s-+~ L M U ~ '-* . G A C i..' S - 4 "
- f: ) ,
/ _ See. 9701721I ,
,f /
7 s ?
~ NUNitER , PROCEDURE Tl?LE REVISION e . . .
, ?
03 _ _1 i r - ' EPIP-4.10 DETE.RMINATION ClT K/Q PAGE 3 of 5
<r - - STEP , ~
- ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED NOTE: Dispersion coefficients for stability class G are ' determined
~
by: coefficents (stability class F,) x 0.6. NOTE: For Stability Class A and distances GREATER TRAN 1500 meters.
- ~'o g = 2000. -
or Stability Class B and distaneos GREATER THAN 5000 meters,
. - 'e Z
= 2000.
, / ,.
- 3. ' / UEIERMlNE CENTERLINE X/Q AT W DISTANCE l / I a) IT X/,Q is required for a a) GO'.TO Step 4. -
distance other than calcu-laced by Step 1. contir.ue with this instruction,
+
- 1) Determine distanci rt-
, quired for X/Q (miles)
Convert miles to meters: i
, 1
- MILES x 1609 - METERS
/ 2)'Obtain current WIND
- 2) Obtain from the Emergency
' SPED AND STABILIT'l CLASS Communicator if Radio-
, from the Radiclogical logical Assessment Assessment Director ,
Director NOT available. e , Convert wind speed s
.! (uph) to meters per /
, second .
s
/ _ / r ,
,,I, Qg
,e l
- 1 'a ph x 0.447 = >
1 c s i sec i :
')-'
- 3) With the wind speed '
l (meters /sec) and Stabi-
~
lity Class, determine the v k dispersion coefficients: V! j I , LB \ ! g a (' 1
- 9 ! ,
),l t
! 4 d
., g ., . =,p. O.-= a+ . - * *
- ee =*e, =%- +*a -**- ***w . ee e e ang -
'i: $ - -
l
.-a.:. -
- : a .a a. =- - :" ~
- = '
.a- ~ : - :- . .. u ;
\
l reo. neenn NUMBER PROCEDURE TITLE REVISION 03 EPIP-4.10 DETEPRINATION OF X/Q PAGE 4 of 5
- STEP ACTION / EXPECTED RESPCNSE l RESPONSENOTOBTAINED
- 3. (CONTINUED)
Horizontal coefficient (cy) use Attachment 2
~
AND ' Vertical coefficient (cz) use Attachment 3
- 4) Determine X/Q'ty follow-ing formttla:
X/Q = 1 (3.14 a e + 758) (wind speed m/Sec) z y
- 4. DETERMINE X/Q NOT ON CENTER-LINE a) E X/Q is required for dis- a) E off-centerline X/Q NOT tances off the centerline of required, CO TO Step 5_.
the plume, continue with this instruction
- 1) Determine downwind distance (miles) for X/Q using Step 2, or Step 3_.
- 2) Determine Stability Class
- 3) Determine centerline X/Q from Step 2 or Step 3.
l
- 4) Using DISTANCE and STABI-LITY CLASS, determine value
! of: 1 2 (oY)2 from Attachment 4 i i l '. _ . . . ? s .. . . - - . . . . . . . . . . - - - - . . ~ . . . . - ~ . . . - . . . . - . . E' ,
^ - --
^ ~
c & ank:Gi s ys.*. M u. ._ s; gig. - ': a-- u. - ~ ,2 _ : :. s , _ ._
- x2 ..= w.-.2. . ..
No. C7447210 NUMBER PROCEDURE TITLE REVISION 03 EPIP-4.10 DETERMINATION OF X/Q PAGE
~
$ oE $
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED . .
- 4. (CONTINUED)
- 5) Determine distance y, perpendicular to centerline which X/Q is to be calcu- .
lated (See Attachment 5_) convert y to meters siles x 1609 = meters
- 6) Determine X/Q off center-line by the following formula:
gjg , X/Q centerline e 2 ( (p,y),) y ) S. PROCEDURE COMPLETION: a) COMPLETED BY: DATE: TIME: 8
~ g g ~. , :.. 7-_ , , , a-. . . -
,__ : .= __
No.97007220 NUNCER A TTACHMENT TITLE REVIS10N EPIP-4.10 03 A TTACHMENT KlQ (SEC/M') PAGE 1 WIND SPEED = 1 MILE PER HOUR 1 of 2 DISTANCE (MILES) . A B C D E F G Site Boundary 1.84 E-6 1.65 E-5 5.98 E-5 1.77 E-4 .3.46 E-4 7.26 E-4' 1.40 E-3 1.00 1.25 E-6 1.10 E-5 4.50 E-5 1.40 E-4 2.80 E-4 5.90 E 1.20 E-3 1.25 1.00 E-6 6.30 E-6 3.10 E-5 9.80 E-5 2.00 E-4 4.50 E-4 9.80 E-4 1.50 8.50 E-7 3.90 E-6 2.20 E-5 7.40 E-5 1.60 E-4 3.50 E-4 8.00 E-4 1.75 7.40 E-7 2.60 E-6 1.70 E-5 5.90 E-5 1.30 E-4 2.80 E-4 6.80 E-4 2.00 6.60 E-7 1.80 E-6 1.40 E-5 4.80 E-5 1.00 E-4 2.40 E-4 5.80 E-4 2.25 5.90 E-7 1.30 E-6 1.10 E-5 4.00 E-5 8.80 E-5 2.00 E-4 5.00 E-4
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l NUMBER PROCEDURE TITLE REVISION 03 EPIP-4.11 FOLLOW-UP OFFSITE RELEASE ASSESSMENT PAGE (With 8 Attachments) 1 of 9 . PURPOSE i Accurately assess the percent technical specifications OR the offsite whole body and thyroid dose rates, using ronitor or sample data. USER Radiological Assessment Director OR Rmembers of Dose Assessment Team. ENTRY CONDITIONS = Any of the following:
- 1) Activation by EPIP-4.01, Radiological Assessment Director Controlling Procedure.
- 2) Activation by EPIP-4.03, Dose Assessment Controlling Procedure.
SAFETY RELApup-
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REVISION RECORD REV. 00 PAGE(S): Entire Procedure DATE: 07-02-82 REV. 01 PAGE(S): Entire Procedure DATE: 07-22-82 REV. 02 PAGE(S): Entire Procedure DATE: 09-01-82 REV. 03 PAGE(S): Entire Procedure DATE: 05-24-83 REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV, PAGE(S): DATE: APPROVAL RECO ENDEO APPROVED DA TE j 05-24-83 Cf CHAIRMANSTA TION NUCLEAR SAFETY AND OPERA TING COMMITTEE l -
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- STEP ACTION / EXPECTED RESPONSE RESPCAfSE NOT08TAINE0
- 1. INITIATE PROCEDURE:
a) Initiated By: Date: Time:
- 2. ASSESSMENT OF PERCENT TECHNICAL SPECIFICATION a) Detarmine the percent of Tech. a) IF the event is a Site OR
, _ Specs under UNUSUAL EVENT g General Emergency, GO TO ALERT Step 3 for Offsite DOSE RATE calculations.
b) IF LIOUID RELEASE b) IF gaseous release, GO TO Substep c.
- 1) Obtain SAMPLE RESULTS (uci/ml) and log on Attachment 1
- 2) Divide SAMPLE RESULTS (pC1/ml) by respective MPC. Log on Attachment 1
- 3) Sum the results from Sub-step 2_ and log on Attach-ment 1
- 4) IF, sample from Substep 1
- 4) IF sample obtained from plant was obtained from dis- system, CO TO Substep 6_.
charge canal, determine the percent Tech Specs by: Substep 3 x 100 = % Tech Spec
- 5) GO To Step 7
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1 No.97887258 NUMBER PROCEDURE TITLE REVISION m i EPIP-4.11 FOLLOW-UP OFFSITE RELEASE ASSESSMENT PAGE I 1 3 of 9
- STEP ACTION / EXPECTED RESPONSE RESPONSENOT ORTAINED
- 2. (CONTINUED) .
- 6) Obtain the number of '
CIRCULATING WATER PUMPS running.
- 7) Obtain the GPM of the release from Operations
- 8) Determine the % Tech Spect -
Substep 3 X GPM X 4.19 E-4
# of Circulating Water Pumps " *, ** *
- 9) Go TO Step 1 c) IF GASEOUS RELEASE
- 1) Obtain SAMPLE RESULTS and log activity on Attachment 2
- 2) Determine percent Tech Specs 2) GO TO Step 3_.
for NOBLE CASES from equation 1. Attachment 2
- 3) Determine percent Tech Specs for SKIN DOSE from equation -
- 2. Attachment 2
- 4) Determine percent Tech Specs for IULnI0 IODINE AND for PARTICULATES with halflives GREATER THAN 8 DAYS by summing the activity (uCi/ml) and using equation 3 on
. Attachment 2 ~
- 5) C0 TO Step 1 l
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- NUMBER PROCEDURE TITLE REVISION 03 EPIP-4.11 FOLLOW-UP OFFSITE RELEASE ASSESSMENT PAGE 4 of 9
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 3. D'ETERMINE OFFSITE DOSE WITH NORMAL RANGE MONITORS a) Determine Offsite Dose with a) GO TO Step 6_ E sample Normal Range Monitor E sample analysis of release IS analysis is NOT available available.
b) E release is through the b) GO TO Step 4_ E monitors are Ventilation System E OFFSCALE Air Ejector AND E Release is through the MAIN Any of the following monitors STEAM are ONSCALE, continue with this instruction:
- 1) VENT VENT A (VG-104)
E
- 2) VENT VENT B (VG-113)
~
E
- 3) PROCESS VENT (GW-102)
OR
- 4) AIR EJECTOR (SV-121, 221) c) Obtain the following infor-mation and log on Attachment 3
- 1) DATE. TIME, AND MONITOR of interest
- 2) CPM of monitor of interest from Radiological Assessment Director e
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NUMBER PROCEDURE TITLE REVISION m EPIP-4.11 FOLLOW-UP OFFSITE RELEASE ASSESSMENT PAGE 5 of 9
~
~ STEP ACTION / EXPECTED RESPONSE RESPONSENOT08TAINE0 ~
- 3. (CONTINUED) .
- 3) FLOW RATE (CFM)
- 4) Obtain X/Q for site boun-dary from EPIP-4.10, Determination of X/Q .
d) Obtain the CONVERSION FACTOR for monitor of interest and log on Attachment 3 MONITOR CONVERSION FACTOR
- 1) VG-104 1.E0 E-5
- 2) VG-113 7.33 E-7
- 3) GW-102 1.80 E-5
- 4) SV-121, 221 -
4.61 E-2 e) Perform the following calcu-lation to determine mR/HR CPMXCFMX(X/Q)XCONVERSIONFACTOR=h
- 1) Log results on Attachment 3_
, f) CO TO STEP 6_
- 4. DETERMINE OFFSITE DOSE WITH PROCESS OR VENT VENT HIGH RANGE MONITORS a) E release is through the a) E sample analysis e avail-Process Vent g Vent Vent able, GO TO Step 6_.
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L* - * ' ~ - No. 97867210 NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.11 FOLLOW-UP OFFSITE RELEASE ASSESSMENT PAGE 6 of 9
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTO8TAINED
- 4. (CONTINUED)
AND OR High Range Monitors are on H release is through the scale Main Steam, GO TO Step 5. AND OR Sample Analysis is not yet g monitors are not onseale available, GO TO Step 7 Continue with this instruction b) Fill in the DATE, TIME AND MONITOR of interest on Attachment 4 c) Obtain the mR/HR on monitors from Radiological Assessment Director
. 1) Convert mR/HR to uCi/cc using Attachment 5.
- 2) Log uCi/cc on Attachment 4 d) Obtain the FLOW RATE OF RELEASE (CFM)
- 1) Log on Attachment 4_
e) Obtain X/Q FOR Site Boundary from EPIP-4.10, Determination of X/Q
- 1) Log on Attachment 4 f) Perform the following calculation on Attachment
- 4 to obtain mR/HR l -
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- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED..
- 4. (CONTINUED) -
pCi/cc X CFM X (X/Q) X 8.50E-1 = g) CO TO Step 6 I 1
- 5. DETERMINE OFFSITE DOSES WITH '
MAIN STEAM E AFPT MONITORS a) Log DATE, TIME, AND MONITOR of interest on Attachment 6, b) Obtain mR/HR and log on Attachment 6 c) Obtain FLOW RATE
- 1) E MAIN STEAM SAFETY 1) E no valve has lifted, VALVE lif ts OR may p,roject release using only potentially lift, deter- one valve.
mine the NUMBER OF VALVES LIFTED from Radiological Assessment Director AND the FLOW RATE as follows: ' t NUMBER OF VALVES LIFTED x 2.62 = m8 /sec ,
- 2) E the AUXILIARY FEED PUMP 2) E main steam to the TURBINE has NOT been turbine is isolated, isolated determine FLOW no release is likely RATE from following: through this pathway.
Continue with this step. UNIT #1 = 3.967 m8 /sec UNIT #2 = 4.216 m8 /sec
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- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 5. (CONTINUED) d) Determine the DOSE CONVERSION FACTOR from Attachment 7 and log on Attachment 6 e) Determine the X/Q for Site Boundary from EPIP-4.10 Determination of X/Q and log on Attachment 6 f) Perform the following calculation to determine mR/HR:
Dose mR mR/HR (Monitor) x Flow Rate (m /SEC) x Conversionx(X/Q)={
""U #
- 6. DETERMINE THYROID 00SE RATE a) Determine the WHOLE BODY DOSE RATE (mR/HR from Step 3 Step 4 or Step 5_.
b) Determine CONVERSION FACTOR versus type of accident listed on Attachment 8. j c) Multipy to determine THYROID DOSE RATE i Step a_ x Step b,= mR/HR l I
- 7. DETERMINE OFFSITE DOSE RATE FROM
~
SAMPLE RESULTS . l a) Obtain EQUIVALENT ACTIVITY (Ci/SEC) for I-131 and Xe-133 from EPIP-4.09, Source Term j Assessmer.t b) Determine X/Q for Site Boundary l from EPIP-4.10, Determination of X/Q
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- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTQBTAINEO . .
c) Determine DOSE RATE
- 1) THYROID (EQUIVALENT I-131)
Ci/SEC x X/Q x 1.85 E + 9 = mR/HR
- 2) WHOLE BODY (EQUIVALENT Xe-133)
Ci/SEC x X/Q x 4.20 E + 4 = mR/HR
- 8. RETURN TO CONTROLLING PROCEDURE:
a) Upon completion of this procedure RETURN to EPIP-4.03, Dose Assessment Controlling Procedure
- 9. PROCEDURE COMPLETION:
a) Completed By: Date: Time END
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rui.orsertzo NUMBER A TTACHMENT TITLE REVISION EPIP-4.11 . 03
% TECH SPEC LIQUID A TTACHMENT PAGE 1 k'ORY, SHEET 1 of 1 ISOTOPE (bbkIN UN2ESTRICTED-MDC H-3 ""'
3.00 E-3 Kr-85 4.00 E-5 Kr-85m 4.00 E-5 Kr-87 4.00 E-5 Kr-88 4.00 E-5 ' Xe-131m 4.00 E-5 Xe-133 4.00 E-5 Xe-133m 4.00 E-5 Xe-135 4.00 E-5 Mn-54 1.00 E-4 Mn-56 - 1.00 E-4 Fe-59 5.00 E-5 Co-58 9.00 E-5 Co-60 3.00 E-5 Cr-51 2.00 E-3 7.r-95 6.00 E-5 Mo-99 4.00 E-5 Ru-103 1.00 E-5 Te-132 2.00 E-5 Cs-134 9.00 E-6 - Cs-136 6.00 E-5 Cs-137 2.00 E-5 Ba-140 2.00 E-5 Ce-144 1.00 E-5 I-131 3.00 E-7 I-132 8.00 E-6 I-133 1.00 E-6 I-134' 2.00 E-5 I-135 4.00 E-6 g (uCi/ml)1 , MPCi . e
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A TTACHMENT TITLE REVISION ') EPIP-4.11 03
% TECH SPEC GASEOUS A TTACHMENT PAGE 2 WORKSHEET 1 of 1 DOSE FACTORS ISOTOPE ACTIVITY (uCi/ml) Ki Li Ni Kr-83M 6.40 E-5 0.00 E+0 3.40 E-3 Kr-85M 7.50 E-1 1.90 E+0 7.80 E-1 Kr-85 9.10 E-3 1.80 E+0 9.70 E-3 Kr-87 2.20 E+0 1.30 E+1 2.40 E+0 Kr-88 5.70 E+0 3.10 E+0 6.00 E+0 Kr-89 7.20 E-1 1.30 E+1 7.60 E-1 Xe-131M 2.70 E-1 6.20 E-1 3,40 E-1 Xe-133M 2.10 E-1 1.30 E+0 2.80 E-1 Xe-133 2.40 E-1 4.00 E-1 3.00 E-1 Xe-135M 8.70 E-1 9.30 E-1 9.30 E-1 Xe-135 1.10 E+0 2.40 E+0 1.20 E+0 Xe-137 1.00 E-1 1.60 E+1 1.10 E-1 Xe-138 2.00 E+0 5.40 E+0 2.10 E+0
- 1. I [(uCi/ml)1 (ki)] (CFM) (9.44 E-2) = % T.S. WHOLE BODY DOSE
- 2. I [(uci/ml)1 (L1 + 1.1 Ni)) (CFM) (1.56 E-2) = % T.S. SKIN DOSE
- 3. I (uci/ml) (CFM) (1.94 E+4) = % T.S. RADIOIODINES AND PARTICULATES i
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- NUMBER A TTAC# MENT TITLE MVISION EPIP-4.I1 03 FOLLOW-UP OFFSITE RELEASE ASSESSMENT A TTAC# MENT MAIN STEAM AND AFFT MONITOR FACE 6 WORKSHEET 1 of 1 DOSE mR/HR FLOW CONVERSION DATE TIME MONITOR (MONITOR) CC/SEC FACTOR X/Q mR/HR l
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