ML20062M100
| ML20062M100 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 07/24/1982 |
| From: | VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML20062M088 | List: |
| References | |
| PROC-820724-01, NUDOCS 8208190426 | |
| Download: ML20062M100 (587) | |
Text
{{#Wiki_filter:. O 4 ,.. as % - y um O'N EflP PROC. LIST J l OM 07-22-82 8 "8 y e-s Page 1 of 3 ! - c4 OO ob . -
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o EMERGENCY PLAN IMPLEMENTING PROCEDURES um Ota - 00
,88 cue EPIP NO. Procedure Safety Code Effective Date
- o m j EPIP-1.01 Emergency Manager Controlling Procedure S 07-22-82
.jEPIP-1.02 Response to Unusual Event S 07-22-82 l EPIP-1.03 Response to Alert N T A CONTROLLED S 07-22-82 DOC' % ENT !
EPIP-1.04 Response to Site Emergency , S 07-22-82 ! oJ, L 2 41982 EPIP-1.05 Response to General Emergency NO.< , _ S 07-22-82 , LMt.se nw "
- EPIP-2.01 Notification of State and Local Governments S 07-22-82 l
EPIP-2.02 Notification of NRC r 07-22-82 EPIP-2.03
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VEPCO PRO E R q , ,1 Reports of Offsite Agencies This document ta the prcS:., t 07-22-82 EPIP-3.01 -Callout of Emergency Response Personnel Vir inia Elsetric and Po'*cr L.) i 07-22-82 d is to to returned ubn l
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EPIP-3.02 Activation of Technical Support Center P
-U[t S c 07-22-82 t
U " ' EPIP-3.03 Activation 01 Operational Support Center 07-22-82 f d at. EPIP-3.04 ~f Activation of Emergency Operations Facility S 07-22-82 , EPIP-4.01 Radiological Assessment Director Controlling Procedure S 07-22-82 f EPIP-4.02- Radiation Protection Supervisor Controlling Procedure . S 07-22-82
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EPIP-4.03 ^ Dose Assessment Controlling Procedure S 07-22-82 EPIP-4.04 g ' Emergency Personnel Radiation Exposure S 07-22-82 EPIP-4.05 _ Respiratory Protection S 07-22-82 i
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EPIP PROC. LIST 07-22-82 , Page 2 of 3 EPIP NO. Procedure Safety Code Effective Date EPIP-4.06 Personnel Monitoring and Decontamination S 07-22-82 EPIP-4.07 ' Protective Measures S 07-22-82 EPIP-4.08 Initial Offsite Release Assessment S 07-22-82 .
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EPIP-4.09 Source Term Assessment , S 07-22-82 EPIP-4.10 Determination of X/Q S 07-22-82 EPIP-4.11 Follow-Up Offsite Release Assessment S 07-22-82 . EPIP-4.12 Offsite Environmental Monitoring Instructions S 07-22-82 . EPIP-4.13 Offsite Release Assessment with Environmental Data 'S 07-22-82
'EPIP-4.14 Inplant Monitoring S 07-22-82 EPIP-4.15 Onsite Monitoring S 07-22-82 EPIP-4.16 Offsite Monitoring S 07-22-82 EPIP-4.17 Monitoring of OSC and TSC- S 07-22-82 EPIP-4.18- Monitoring of EOF S 07-22-82 EPIP-4.19 Use of Radios for Health Physics Monitoring- S 07-22-82 EPIP-4.20 Health Physics Actions for Transport of Contaminated Injured Personnel S 07-22-82 EPIP-4.21 Evacuation and Remote Assembly Area Monitoring S 07-22-82 i EPIP-4.22 - Post Accident Sampling of Containment Air S 07-22-82 i ,
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EPIP PROC. LIST j 07-22-82 ' Page 3 of 3 EPIP NO. Procedure Safety Code Effective Date i EPIP-4.23 Post Accident Sampling of Reactor Coolant S , 07-22-82 EPIP-4.24 Gaseous Effluent Sampling During an Emergency S 07.22-82 1 EPIP-4.25 Liquid Effluent Sampling During an Emergency S 07-22-82
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EPIP-4.26 High Level Activity Sample Analysis S 07-22-82 EPIP-5.01 Tranportation of Contamina*_ed Injured Personnel S 07-22-82 ' EPIP-5.02 Search and Rescue S 07-22-82 i i EPIP-5.03 Pers'onnel Accountability S 07-22-82 i EPIP-5.04 Access Control S 07-22-82 EPIP-5.05 Site Evacuation S 07-22-82 EPIP-5.06 Emergency Radiation Exposure Authorization S 07-22-82 l l EPIP-5.07 ' Administration of Radioprotective Drugs S 07-22-82 l t EPIP-5.08 Damage Control Guideline S 07-22-82 l t EPIP-6.01 Re-entry / Recovery Guideline S 07-22-82 l 7 9 f. 1 I I
No. 97887200 ( , VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCEDURE !lTLE REVISION 01 EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE PAGE (With 1 Attachment) 1 of 7 e PURPOSE To initially assess a potential emergency condition and initiate corrective actions. NOT A CONTff0LLED Dnc ..r Off GA mm USER *'""'- NOR , ,ag Shift Supervisor OR_ Station Emergency Manager LATese ntVISauN ENTR Y CONDITIONS rx
) 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
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Supervisor. - VEPCO PROPERTY 21s docu1ent 13 tr..) propu t*, el t'.; Virr!nta E,vetric and Poac : C3. " . ' and Ic to be returned upor. re. . No pernirnton is granted to pc:.
- f' reproddCC. U U C C -' t t 0 .* d:i Oltof t another any las er.:.ar.1on coaub. t .
this doct.raent. { REVISION RECORD REV. 00 PAGE(S): ENTIRE PROCEDURE DATE: 07-02-82 , REV. 01 PAGE(S): ENTIRE PROCEDURE DATE: 07-22-82 ; REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: A REV. PAGE(S): DATE:
) REV. , PAGE(S): DATE:
APPROVAL R$C MMENDED 3 APPROVED T,/^ OA TE '
\ 07-22-82 h CHAlHMANSTA TION NUC AR SAFETY AND OPERA TING COMMITTEE L
f No.97887210 NUMBER PROCEDURE TITLE REVISION
) EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE PAGE 2 of 7 STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 1. INITIATE PROCEDURE:
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 i
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No. 97887210 i NUMBER PRJCEDURE TITLE REVISION EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE PAGE 3 of 7
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 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) GO TO Step 2.e of this in-struction.
- 1) Request Health Physics initiate EPIP-4.01, O Radiological Assessment Director Controlling Procedure, and continue this instruction e) Event-S/G TUBE 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 Procedure, and continue this instruction.
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No 97887210 i NUMBER PROCEDURE TITLE REVISION ( EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE PAGE 4 of 7
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED 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
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O 1) Using index, determine event category AND GO TO proper EAL tab AND
- 2) Evaluate event, deter-mine classification, AND Go To Step 4 of this procedure
- 4. VERIFY CLASSIFICATION:
a) TSC - NOT ACTIVATED a) IF TSC activated, GO TO Step k-b) Notify SRO-On-Call or Super- b) Notify Station Manager or intendent of Operations Asst. Station Manager. c) Verify classification d) If required by Alert, Site, or General Emergency request ' Ci initiation of ADMIN 29.6, Conduct of Operations, Notification L
No. 97887210 NUMBER PROCEDURE TITLE REVISION O. EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE PA GE 5 of 7 ,
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 4. (CONTINUED)
NOTE: Return to Step 2 of this instruction as necesaary during the course of the situation for additional events and
. reclassification.
- 5. VERIFY EALS EXCEEDED:
a) EALS-EXCEEDED a) F EALS NOT exceeded, DO NOT declare an emergency classif-O ication. AND
- 1) Continue appropriate corrective action IAW procedures.
- 2) GO TO Step 7 of this pro-cedure.
b) Assign appropriate individual as interim Emergency Commun-icator c) Direct senior H.P. personnel on site to initiate EPIP-4.01, Radiological Assessment Director Controlling Procedure
- 6. DETERMINE EPIPS:
l a) Event classification - UNUSUAL a) GO TO Step 6.b of this in-EVENT struction. l 1) GO TO EPIP-1.02, Response to Unusual Event L
No. 97887210 NUMBER PROCEDURE TITLE REVISION EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE PAGE 6 of 7
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 6. (CONTINUED) 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) GO TO Step 6.d of this EMERGENCY instruction.
- 1) GO TO EPIP-1.04, Response to Site Energency d) Event classification - GENERAL EMERGENCY
() 1) GO TO EPIP-1.05, Response to General Emergency
- 7. SECURE FROM EVENT:
a) Notify involved station personnel that emergency condition does not exist b) GO TO Step 11,of this instruc-tion
- 8. TERMINATE EMERGENCY:
a) Notify involved station personnel that emergency condition is no longer in effect b) Initiate recovery actions b) IJ[ 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 u
No. 978872:0
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NUMBER PROCEDURE TITLE REVISION EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE PAGE 7 of 7
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 9. TERMINATION NOTIFICATIONS:
a) Initiate termination notifi-cation to counties and state IAW EPIP-2.01, Notification of State and Local Governments b) Initiate termination notifi-cation to NRC IAW EPIP-2.02, Notification of NRC c) ))[ required recovery actions where considered beyond the scope of normal procedures and capabilities in Step 8 GO TO EPIP-6.01 Recovery O and Restortation Guideline
- 10. REPORTING:
a) Verify required reports and notifications IAW EPIP-2.03, Reports to Offsite Agencies
- 11. ADMINISTRATION:
a) Initiate replacement of any used procedures and forms b) Forward completed EPIPs, forms and other applicable records to SNSOC for review . c) ))[ required, deactivate TSC
- 12. TERMINATE EPIP-1.01:
a) COMPLETED BY: DATE: TIME: END u
N3.97887220 NUMBER A TTACHMENT TITLE REWSION EPIP-1.0 01 EMERGENCY ACTION LEVEL TABLE A TTACHMENT PAGE 1 INDEX 1 of 38
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CAUTION: Declaration of the highest emergency class for which an EAL is exceededshall be made.
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I 1 GO TO IF EVENT CATEGORY IS: TAB
- 1. Safety, Shutdown, or Assessment System Event ....................A
- 2. Reactor Coolant System Event ....................................B
- 3. Fuel Failure or Fuel Handling Accident...........................C
- 4. Co n t a inme n t Ev e n t . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . D
- 5. Radioactivity Event..............................................E
- 6. Contaminated Personnel ..........................................F
- 7. Loss of Secondary Cooling........................................G
- 8. El e c t r i c a l Fa i lu r e . . . . . . . . . . . . . . . . . .' . . . . . . . . . . . . . . . . . . . . . . . . . . . . . H
- 9. Fire.............................................................I
- 10. S e cu r i ty Ev e n t . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . J
- 11. Hazard to Station Operation......................................K:
- 12. Natural Events...................................................L
- 13. Miscellaneous Abnormal Events....................................M-m
. , ..-.-.--.~. _ ----- - . . . _ . - . _ _ . - _ - _ - _ _ _ - - - .- _ - -_. _
N3. 97847220
; NUMBER A TTACHMENT TITLE REVISION EPIP-1.0: 01 EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB A) PAGE l 1 SYSTEM SHUTDOWN, OR ASSESSMENT 2 of 38 SYSTEM EVENT 1
j CONDITION / APPLICABILITY INDICATION CLASSIFICATION i Non-transient ECCS i
- 1. Non-spurious ECCS Unusual Event initiation initiation as vali- t dated by Emergency i MODES 1, 2, 3 & 4 Procedures i
- 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 I Operation
- O 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 . Release flow as indicated by rapid RCS cooldown rate
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O MS pressure is GREATER THAN 100 psi below-set point of affected valve.
Ns.97887223 NUMBER A TTACHMENT TITLE REVISION
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EPIP-1.0. - 01 ' O' A TTACHMENT EMERGENCY ACTION LEVEL TABLE PAGE (TAB A) 1 SYSTEM SHUTDOWN, OR ASSESSMENT 3 of 38 SYSTEM EVENT I o 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-S
- 2) Component Cooling 3
- 3) Residual Heat 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 Ojt 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 ,
Ns.91881220 NUMBER A TTACHMENT TITLE REVISION EPIP-1.01 01 O A TTACHMENT "Y^ TAB A PAGE 1 SYSTEM SHUTDOWN, OR ASSESSMENT 4 of 38 S? STEM E" EFT CONDITION INDICATION CLASSIFICATION -
- 7. Failure of the Reactor Condition a) and b) Site Emergency Protection System to exists with c) initiate and complete a required trip while a) RX trip setpoint and at power coincidences-EXCEEDED MODES 1 & 2 AND b) Manual Rx trip-INITIATED AND c) Rx power indication NOT DECREASING
- 8. Indications or alarms Unit (s)'placed it. Mode 3 or Unusual Event on process or effluent lower condition as a re-O parameters required for incident assessment NOT sult of any of the following:
functional in the con-trol room a) Containment Gaseous or Particulate Radiation MODES 1,2,3 & 4 Monitors- NOT OPERABLE AND Backup grab sample capability is inoperable per leak de- - tection T.S.3.4.6.1 0,,R I b) Meteorological monitor-ing instrumentation- LESS THAN minimum required to perform offsite dose calculations per Unit 1 , T.S.3.3.3.4 + S.R c) Post-accident instrument-() f-~s ation-LESS THAN minimum channels allowable per T.S. 3.3.3.6
N3.97887220 NUMBER A TTACHMENT TITLE REVISION EPIP-1.0) 01 O. A TTACHMENT EMERGENCY ACTION LEVEL TABLE (TAB A) PAGE 1 SYSTEM SHUTDOWN, OR ASSESSMENT 5 of 38 SYSTEM EVENT 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 e a unit transient GREATER THAN 1_5,5 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 Emergency trol Rocm with control Rocm with local shutdown NOT established within control NOT established 15 minutes within _1_5, 5 minutes ALL MODES 2
No. 97887220 NUMBER ATTACHMENT TITLE REVISION EPIP-1.0] 01 O A TTACHMENT EMERGENCY ACTION LEVEL TABLE (TAB B) PAGE 1 REACTOR COOLANT SYSTEM EVENT 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 exceeded 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 O MODE 1 RC loops 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 O L.
Ns 97407220 NUMBER A TTACHMENT TITLE REVISION EPIP-1.01 O A TTACHMENT EMERGENCY ACTION LEVEL TABLE (TAB B) 01 PA GE 1 REACTOR COOLANT SYSTEM EVENT 7 of 38 CONDITION / Applicability INDICATION CLASSIFICATION l 4. RCS leak rate requiring Unit in Mode 3 or lo'wer 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 1 gpm 9.R_ b) Identified leakage-GREATER . I THAN 10 gpm 0,,R l c) Controlled leakage from l RCP seals-GREATER THAN 30 gpm TOTAL pR, d) Any pressure boundry leakage
- 5. RCS leak rate exceeds Pressurizer Level cannot Alert l 50 gpm be maintained GREATER THAN l 22% with one(1) Charging /SI MODES 1, 2, 3 & 4 Pump in operation AND RCS inventory balance indi-cates leakage-GREATER THAN
- 5_0_ gpm
- 6. RCS leak rate exceeds EP-2, Loss of Reactor Cool- ' Site Emergency 300 gpm ant, in effect MODES 1, 2 , 3 & 4 AND
's - Pressurizer level can not I
i be maintained.with two (2)
~ or more Charging /SI Pumps .
in operation l
N3.97887220 , NUMBER ' A TTACHMENT TITLE REVISION
,e - - - EPIP-1.01 01 l EMERGENCY ACTION LEVEL TABLE A TTACHMENT PAGE (TAB B) 1 REACTOR COOLANT SYSTEM EVENT 8 of 38 o
CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 7. Primary to Secondary Unit in Mode 3 or lower con- Unusual Event leakage-GREATER THAN dition as a result of 1 gpm actions required by T.S.
3.4.6.2 i 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 Condenser Air Ejector fy! Steam Generator Blowdown Monigor GREATER THAN 1x10 cpm
- 9. Excessive Primary to Unit in Mode 3 or lower 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 i AND Condenser Air Ejector fM! Steam Generator Blowdown Monitor Rgadings-GREATER THAN 1x10 cpm AND Loss of offsite power l indicated by zero volts on l 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
N3.97887220 NUMBER A TTACHMENT TITLE REVISION O EPIP-1.0 A TTACHMENT EHERGENCY ACTION LEVEL TABLE (TAB B) 01 PAGE 1 REACTOR COOLANT SYSTEM EVENT 9 of 38 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 10. (CONTINUED) Condenser Air Ejector Cgt Steam Generator Blowdown MonitorGgEATER THAN 1x10 cpm AND Loss of offsite power indi-cated by zero volts on volt-meters for 4160V Buses D, E
&F
- 11. Loss of 2 of 3 fission Any two of a),b) or c) General Emer-product barriers with exist and the third ,
gency O 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 0R, b) Loss of RCS integrity as indicated by any of the following:
.1) RCS pressure-GREATER THAN 2735 psig O
Ns 97887220 NUMBER A TTACHMENT TITLE REVISION EPIP-1.0: 01 O A TTACHMENT EMERGENCY ACTION LEVEL TABLE (TAB B) PAGE 1 REACTOR COOLANT SYSTEM EVENT 10 of 38 , CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 11. (CONTINUED) 2) EP-2, LOCA, has been implemented
- 3) Containment High Range Area Radiation Monitor
-GgEATERTHAN 10 mR/Hr S
c) Loss of containment inte-grity as indicated by any of the following:
- 1) Containment pressure
-GREATER THAN 6J1 psia and NOT, decreasing
- 2) Loss of containment integrity as defined in T.S. 1.8
- 12. Fuel failure with steam Any two of a),b) or c) General Emer-i 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 1-131
- 2) 5 or more core exit thermocouples
-GRLATER THAN 1200* F f'% SE O
s_ . , -. - , - - - -
Ns.97587220 NUMBER A TTACHMENT TITLE REVISION EPIP-1.01 i O A TTACHMENT EMERGENCY ACTION LEVEL TABLE (TAB B) 01 PAGE 1 REACTOR COOLANT SYSTEM EVENT 11 of 38 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 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 9R_
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 Secondary Coolant, initiated i
1
N s. 97887220 NUMBER A TTACHMENT TITLE REVISION O EPIP-1.0) A TTACHMENT EMERGENCY ACTION LEVEL TABLE (TAB C) 01 PAGE 1 FUEL FAILURE OR FUEL HANDLING ACCIDENT 12 of 38 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 1. Fuel clad damage Unit shutdown required Unusual Event i
indication IAW action statement
.(b) of T.S. 3.4.8.b MODES 1,2,3 & 4 S
High Range Letdown Ra-diation Monitor indica-tion ingreases GREATER THAN 10 cpm within 30, 0 minutes AND remains for at least 15 minutes Ch ()
- 2. Severe Fuel Clad Damage RCS specific activity-GREATER THAN 300.0 Alert uCi/ gram dose equiva-MODES 1,2,3 & 4 lent I-131 E
l High Range Letdown Ra-diation Monitor indica-tion ingreases GREATER ( THAN 10 cpm within i 30, minutes AND remains ( for at least 15, minutes
- 3. Core damage with pos- Condition a) exists with Site Emergency sible. loss of coolable b) geometry a) Fuel clad failure as MODES 1,2,3 & 4 indicated by any of the following:
- 1) RCS Specific activity GREATER THAN M uC1/gra
() dose equivalent I-131
l ns. nensas NUMBER A TTACHMENT TITLE REVISION EPIP-1.0: 01 a O A TTACHMENT EMERGENCY ACTION LEVEL TABLE (TAB C) .PAGE 1 FUEL FAILURE OR FUEL HANDLING ACCIDENT 13 of 38 4 CONDITION / APPLICABILITY INDICATION CiASSIFICATION
- 3. (CONTINUED) 2) High Range Letdown Radiation Monitor indicatiog-GREATER THAN 1x10 cpm i
AND b) Loss of cooling as in-dicated by any of the following:
- 1) 5 confirmed core exit thermocouples
- GREATER THAN 1200* F O ~
- 2) Core DT-ZERO ,
- 3) Core DT - RAPIDLY i DIVERGING l
I l l O .
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Ns.97847220 l NUMBER A TTACHMENT TITLE REVISION EPIP-1.0) 01 O A TTACHMENT EMERGENCY ACTION LEVEL TABLE (TAB C) PAGE 1 FUEL FAILURE OR FUEL HANDLING ACCIDENT 14 of 38 CONDITION? APPLICABILITY INDICATION CLASSIFICATION
- 4. Probable large radio- EP-2, LOCA, has been im- General Emer-activity release ini- plemented AND RCS specific gency ated by LOCA with ECCS activity -GREATER THAN failure. leading to 3000.0 uCi/ gram 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 FW system and General Emer-activity release ini- Condensate System gency tiated by loss of heat Os sink leading to core degredation AND Loss of Auxilary FW System i
- 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 GREATER ALL MODES THAN OR EQUAL TO 2485 psig c) Containment pressure AND temperature -RAPIDLY INCREASING O
I l l
; n,. .n.nn NUMBER A TTACHMENT TITLE REVISION EPIP-1.01
() 01 EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB C) PAGE 1 FUEL FAILURE OR FUEL HANDLING ACCIDENT 15 of 38 p CONDITION / APPLICABILITY INDICATION CLASSIFICATION j 7. Probable large radio- a) Loss of all AC procedures General Emer-activity release init- implemented gency iated by loss of AC - and all feedwater AND ALL MODES
- l b) Turbine Driven Auxilary Feedwater Pump NOT OPERABLE AND c) Restoration of a) or b) i above not likely within 2 hours j 8. Probable large radio- Condition a) and b) exist General Emer-with c) or d).
~ activity release init- gency lated 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-erature-GREATER THAN 190' F AND NOT DECREASING S d) Quench Spray and Recircu- 1 lation Spray Systems- NOT l OPERABLE 1 lO )
, _ - - , , . _ , _ - r .,---
7 - ,
- . . ~ . . - - - - - - - - ,-~ . -
__ _ . - - , - -_. -.~m - _m- - Ns.97887220 NUMBER A TTACHMENT TITLE REVISION EPIP-1.0 01 O EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB C) PAGE 1 FUEL FAILURE OR FUEL HANDLING dCCIDENT 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 I a) Verified accident invol-ALL MODES ving damage to irradiated fuel AND b) Health Physics confirms
! fission product release from fuel i I OR I . 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 level in Rx vessel buildings during refueling -BELOW TOP OF CORE-ALL MODES OR s b) Water level in Spent. Fuel Pit -BELOW TOP OF SPENT FUEL AND i c) Verified damage to irrad-
.iated fuel resulting in readings on Ventilation s VentGaseousMonitgr
-GREATER THAN 1x10 cpm L
r- - - - . w - - - - . + -w,. ---..---.-4--.- -,,,-.,---..3-w . . . - - - . , - - , - -
N 3. 97887220 NUMBER A TTACHMENT TITLE REVISION FDTP-1 01 01 A TTAC# MENT EMERGENCY ACTION LEVEL TABLE PAGE (TAB D) 1 CONTAINMENT EVENT 17 of 38 CONDITION / APPLICABILITY INDICATION %ASSIFICATION
- 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. 3.6.1.1
- 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
^""
O b) Containment pressure
-GREATER THAN 17 psia OR c) Containment temperature
-GREATER THAN 150' F
- 3. High-high Contaitment Condition a) exists with b) Site Emergency radiation, pressure, or c) and temperature 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 0R c) Containment temperature in-O~ dicates-GREATER THAN 200* F
- _ _ _ . . _ . . .. ~ _ - - - _ . . _- - - - _ _ _ . -
N4.97887220 NUMBER A TTAChMENT TITLE REVISION FPTP 1 O 01 A TTAChMENT EMERGENCY ACTION LEVEL TABLE PAGE (TAB D) 1 CONTAINMENT EVENT 1R of 1R CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 4. Extremely high Con- Condition a) exists with b) General Emergency tainment radiation, or c) pressure and temp-perature a) Containment High Range Radiation Monitor -
4 GREATER THAN 10 mR/Hr MODES 1,2,3 & 4 AIO b) Containment pressure
-GREATER THAN 45 psia AND NOT DECREASING OR O
c) Containment temperature
-GREATER THAN 280' F l
0
- . , _ . .. : 7- -- ---- _ __
._- - -- __ -g.,,...., .
Ns,97887220 NUMBER A TTACHMENT TITLE REVISION FPtP-1_01 01 A TTAC# MENT EMERGENCY ACTION LEVEL TABLE PAGE (TAB E) 1 RADIOACTIVITY EVENT 19 of 38 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 1. Effluent release Any of the following Unusual Event GREATER THAN T.S. monitors indicate valid allowable Limit readings above the spec-ified value ALL MODES a) Clarifer Effluent Monit 5-REATERTHAN 2.4x10 cpm b) Vent Stack A Gaseous Monitog-GREATER THAN 3.4x10 cpm -
c) Vent Stack A Parti-p culateMonigor-GREATER V THAN 4.5x10 cpm d) Vent Stack B Gaseous Monitor-GREATER THAN i 1x106 cpm FOR LESS THAN M MINUTES l e) Vent Stack B Particulate Monito{-GREATER THAN 3.8x10 cpm f)AirEjectorMonitorfs)- l GREATER THAN 6.8x10 cpm g)DischargeCanalMongtor-GREATER THAN 6.0x10 cpm h) Process Vent Gaseous 6 Monitor-GREATER THAN 1x10 cpm FOR LESS THAN M MINUTES i) Process Vent Particulate 6 Monitor-GREATER THAN 1X10 cpm FOR LESS THAN M MINUTES
o N3.97887220 NUMBER A TTACHMENT TITLE REVISIO_N FDTP-1 O' 01 A TTAC# MENT EMERGENCY ACTION LEVEL TABLE PAGE (TAB E) 1 RADIOACTIVITY EVENT 20 of 38 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 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-GgEATER THAN 1x10 cpm b) Vent Stack A Gaseous Monitog-GREATERTHAN 3.4x10 cpm c) Vent Stack A Partic-ulatehonitgr-GREATER THAN h5x10 cpm d) Vent Stack B Gaseous Monigor-GREATERTHAN 1x10 cpm FOR GREATER THAN M MINUTES
, e) Vent Stack B Partic-l ulateMonitgr-GREATER THAN 3.8x10 cpm f) Air Ejector Monitorfs)- GREATER THAN 6.8x10 cpm l g)DischargeCanalMonjtor-GREATER THAN 6.0x10 cpm h) Process Vent Gaseous d~ i Monigor-GREATERTHAN l 1x10 cpn FOR GREATER ( , THAN M MINUTES 1 . l i) Process Vent Particulate
\s
- Monigor-GREATERTHAN 1x10 cpm FOR GREATER THAN g MINUTES
- No. 91881220 l
NUMBER A TTACHMENT TITI.E REVISION ! ((() srIe ne A T7AC# MENT a' l EMERGENCY ACTION LEVEL TABLE PAGE ' (TAB E) , 1 RADTOACTTVITY EVENT 21 of 18 o CONDITION / APPLICABILITY INDICATION CLASSIFICATION 3 Projected or actual Valid indications of any Site Emergency site boundary doses of the following exist. of 0.5 Rem to 2 Rem W.B. or 1 Rem to 12 - Rem thyroid expocure a) Any Main Steam Line High Range Monitor ALL MODES GREATER THAN 1.6 mR/hr S b) Ventilation Vent A High Range Mgnitor GREATER THAN 6.5x10 mR/hr in coincidence with Ventilation Vent Gaseous Monitor off' scale high S , c) Ventilation Vent B Bigh Range M nitor GREATER THAN 2 8x10 mR/hr in coincidence with Ventilation Vent Gaseous Monitor off scale high S , d) Process Vent High Range Monitor -GREATER THAN 64,mR/hr S e) Monitoring Team samples indicate doses of from 0.5 to 2.0 Rem W.B. or 1 to 12 Rem thyroid ex-posure at the site bound-a ry . O
N3.97487220 NUMBER A TTACHMENT To LE REVISION rovn_1 n1 ni A TTAC# MENT EMERGENCY ACTION LEVEL TABLE PAGE (TAB E) , I RADIOACTIVITY EVENT 22 of 18 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 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 THAN 2 Rem i posure WHOLE BODY OR 12 Rem ~
THYROID EXPOSURE ALL MODES b) Valid indications of the following exist:
- 1) Any Main Steam Line High Range Monitor
-GREATER THAN 6.4 mR/hr a
- 2) Ventilation Vent A High Range Monitor
_1
-GREATER THAN 2.6x10
=
mR/hr E
- 3) Ventilation Vent B l High Range Monitor j
-GREATE{THAN l 3.2x10 mR/hr M
- 4) Process Vent High Range
-Monitor GREATER THAN 256 mR/hr L
i \w-l l
N3.91887220 NUMBER \ A TTACHMENT TITLE REVISION EPIP-1.0 .- ; 01 O EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB E) PACE 1 RADI0 ACTIVITY EVENT 23 of 38 o CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 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-D
\# ming Area Monitor e) Decontamination Building Area Monitor f) Fuel Pit Bridge Area Monitor g) New Fuel Storage Area Monitor h) Laboratory Area Monitor
- 1) Sample Room Area Monitor O
Ns.91887330 1MBER A TTAC# MENT TITLE REVISION O ppTp_i n ni A TTAC# MENT EMERGENCY ACTION LEVEL TABLE PAGE (TAB F) 1 CONTAMTNATFD PFRCONNFT 76 n f '4R 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 treatment facility ALL MODES 9
/
O
.. . . _ _ . .. . . = . . . _ .
No.97087220 1 l NUMBER A TTACHMENT TITLE REVISION rpip_t n' nt A TTAC# MENT EMERGENCY ACTION LEVEL TABLE PAGE (TAB G) 1 LOSS OF SECONDARY COOLANT 25 of 38 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
, 1. Major Secondary line EP-3, Loss of Secondary 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 Monitor 5
-GREATER THAN 7x10 cp, 0,,R c) Steam Generator Blow-l down Radiation Monitor
-GgEATERTHAN 10 cpm 0,R d) MS Line High Range Radiation Monitor
-CREATER THAN 0.5 mR/hr.
O
N3.97847220 NUMBER A TTACHMENT TITLE REVISION FDTP-1_01 01 A TTACNMENT EMERGENCY ACTION LEVEL. TABLE PAGE (TAB G) 1 LOSS OF SECONDARY COOLANT 26 of 38, CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 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 Secondary 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-down High Range Ra-diation M nit r -G EATER O* THAN 105 cpm c) Condenser Air Ejector RadiationMonitog
-GREATER THAN 10 cpm O_R d) Steam Generator Blow-down Radiation Mgnitor
-GREATER THAN 10 cpm pR, e) MS Line High Range Radiation Monitor
. -GREATER THAN 1.6 mR/hr O
wr y- - - - - - - y- - e _ _ - ._ __a = -_ _ _ ___ _
No.9788 M20 l l NUMBER A TTACHMENT TITLE REVISION l
; EPIP-1.0: 01 ,
EMERGENCY ACTION LEVEL TABLE I A TTACHMENT (TAB H) PAGE 1 ELECTRICAL FAILURE 27 of 38 1 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 pR, Loss of all 34.5KV Reserve Station Service Buses i
- 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 O - Ammeters for 4160V Station Service Buses A,B,& C all indicate-ZERO (0) AMPS l AND Ammeters for 4160V Emergency Buses H and J both indicate-ZERO (0) AMPS
- 3. Loss of off-site 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 l Buses D,E,& F all indi-cate-ZERO (0) AMPS AND .y b) Ammeters for 4160V
() - Station Service Buses A,B & C all indicate-ZERO (0) AMPS AND I _ _ _ .
F N3.97887220 NUMBER A TTACHMENT TITLE REVISION O EPIP-1.0: 01 EMERGENCY ACTION LEVEL TABLE A TTACHMENT PAGE (TAB H) 1 ELECTRICAL FAILURE 28 of 38 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 3. (CONTINUED) c) Ammeters for 4160V Emergency Buses H & 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 AND No light indication avail-able to Reserve Station O 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-THAN 15 minutes GREATER THAN 15 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 1
N3.97887220 NUMBER A TTACHMENT TITLE REVISION ON rnin_1 n' n t_ A TTAC# MENT EMERGENCY ACTION LEVEL TABLE PAGE (TAB I) 1 FTRE 79 nf 1R CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 1. Fire lasting-GREATER Fire within the Station Unusual Event THAN 10 minutes which is not under con-trol within IC[ 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 1,2,3,84 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 T gradation of safety which causes major degrad-systems ation of a safety system l function required for pro-
- MODES 1,2,3 & 4 tection of'the public l
AND Affected systems are caused to be NOT operable as defined by T.S.I.6. and 3.0.5 O
No.97887220
- NUMBER A TTACHMENT TITLE REVISION EPIP-1=g, ni A TTAC# MENT EMERGENCY ACTION LEVEL TABLE PAGE (TAB J) 1 RFCURTTY EVENT 30 of 38 CONDITION / APPLICABILITY INDICATION CLASSIFICATION -
- 1. Security threat, un- Security Shift Supervisor Unusual Event authorized attempted has recommended Shift entry, or attempted Supervisor declare an sabotage Unusual Event IAW. ADM-l 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 O control ALL MODES Supervisor of imminent intrusion into a Vital 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 JHL Shift Supervisor has been-informed of intrusion into
- one or more Vital Areaa l which are occupied OR controlled by an aggressor-O
.,,.,e,-.m . , = - - - - - - - - - .n --
r .- - - -e w - , - ~ - n v -
- = * = - - - - ~ ~ ' ~ - - ' ~ ' ' ~~
No. 97887220 NUMBER A TTACHMENT TITLE REVISION O. EPIP 1.0' AT7'ACNMENT EMERGENCY ACTION LEVEL TABLE PAGE (TAB K) 1 HA7ARD TO STATION OEEEAllON 31 of 38 CONDITIOM/ APPLICABILITY INDICATION CLASSIFICATION
- 1. Aircraft crash or un- Confirmed notification of Unusual Event usual aircraft activity aircraft crash within the site boundary ALL MODES 0,,,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 .
O' 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 i structure or equipment l
ALL MODES 7- , - - -
N3.97887220 NUMBER A TTACHMENT TITI.E REVISION O m.m A TTACHMENT EMERGENCY ACTION LEVEL TABLE
~
PAGE (TAB K) i uivann mn emaminn nprusTTnN 17 of 1R CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 7. Severe explosive damage Explosien 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 S b) ECCS System S c) Main / Auxiliary Feedwater System O 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 which may affect safety of station ALL MODES personnel OJL equipment l
- 9. Entry of toxic or flam- Notification of uncontrolled Alert mable gases or liquids release of toxic 0]L 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 011 flam-vital areas mable agents above life O
threatening or explosive MODE 1,2,3 & 4 limits into Vital Areas AND l
N3.97887220 NUMBER A TTACHMENT TITLE REVISION EPIP-1.0: O A TTACHMENT EMERGENCY AC" ION LEVEL TABLE (TAB K) 01 PAGE 1 - HAZARD TO STATION OPERATION 33 of 38 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 10. (CONTINUED) Any of the following occur:
a) Evacuation of Vital Area required 8 b) Degradation of safety systems rsulting in less of a safety system function required for protection of the public
- 11. Turbine rotating a) Failure of Turbine / Unusual Event O
component failure Generator rotating with no casing equipment resulting penetration in itmediate 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 S
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 sturetures
- 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 O
r
- No.97887220 NUMBER A TTACHMENT TITLE REVISION roto _1 n n1 A TTAC# MENT EMERGENCY ACTION LEVEL TABLE RAGE (TAB L) 1 MATUR AT. EVENT 9 1A nf 1A CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 1. Earthquake detected Confirmed earthquake which Unusual Event acti"ates 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 Sho'ck Annunciator indicate a horieontal motion of-GT,7 TER THAN or EQUAL TO O- 0,,9 g or a vertical moeion 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 motion 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.
O Tornado striking facility Tornado visually detected striking within the Pro-tected Area or Switchyard Alert ALL MODES o
..,a
-- . _ - = . . -- .. .- -
No.97887220 NUMBER A TTACHMENT TITLE REVISION vprp 1 n' n1 A TTACNMENT EMERGENCY ACTION LEVEL TABLE PAGE (TAB L) 1 NATURAL EVENTS 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 73,3 mph
- 7. Extreme winds Sustained extreme winds in Alert excess of 78 mph' caused by MODES 1,2,3 & 4 t
O 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 OR other ~
severe weather condition L f
- 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
.S Low water level in the Lake Anna Reservoir with indi-cated level-LESS THAN 247 feet MSL i
- 10. Flood or low water Flood in the Lake Anna Alert level near design Reservoir with indicated 1-vels level-GREATER THAN 263 feet MSL ALL MODES O, $
1
Ns.97887223 l NUMBER A TTACHMENT TITLE REVISION vpTp_1.n1 01 A TTAC# MENT EMERGENCY ACTION LEVEL TABLE PAGE (TAB L) i NATURAL EVENTS 36 of 38 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 10. (CONTINUED) Low water level in the Lake Anna Reservoir with indi-cated level-LESS THAN 245 i
feet MSL l l 11. Flood or low water Flood in the Lake Anna Site Emergency level above design Reservoir with indicated j levels level-GREATER THAN 280 feet MSL MODES 1,2,3 & 4 E Low water level in the Lake Anna Reservoir with indi-cated level-LESS THAN 244 O feet MSL 1. O l
N3.97487220 m
. = ,
NUMBER A TTACHMENT TITLE REVISION vpip 1 n1 n1 A TTAC# MENT EMERGENCY ACTION LEVEL TABLE PAGE (TAB M) 1 MISCELLANEOUS ABNORMAL EVENTS 37 of 18 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 1. Station conditions Shif t supervisor judgement Unusual Event which warrant increased that any of the following awareness of state and/ exist:
or 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 S b) Unit shutdown is other than a controlled shutdown 0,,,R , c) Unit is in an uncontrolled condition during operation S i d) A condition exists which ' has the potential for-escalation and, therefore, warrants notification
- 2. Station conditions Shift Supervisor / Station ..ert which warrant precau- Emergency M.asger judgement tionary notification to thL 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
N3,97887220 g a 7 NUMBER
- A TTACHMENT TITLE REVISION EPIP-1.0; 01 EMERGENCY ACTION LEVEL TABLE A TTACHMENT ( L'AB M) PAGE 1 MISCELLANEOUS ABNORMAL EVENTS 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 I ALL MODES O
1 l l l O e
N3.97887200 VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCEDURE TITLE REVISION 01 EPIP-1.02 RESPONSE TO UNUSUAL EVENT PAGE (With No Attachments) 1 of 7 PURPOSE
- 1. To provide guidance to the Station Emergency Manager during the pro-gress of a classified UNUSUAL EVENT emergency ~.
NOT A CONTROLLED gy wr.NT USER JUL 2 41982 Station Emergency Manager
E NO:.
LAlt.M ate.Vi$ TON ENTRY CONDITIONS
- 1. Entry From EPIP-1.01, Eriergency Manager Controlling Procedure.
O . VEPCO PROPERTY This document is the property of the Virginia Electric and Power Cottoar.y and is to be returned upon request. No port:iissica la granted to puiO : ... reprcduce, tramit or discione another any inior:r.ation conts: .i this document. I SAFETY Rang REVISION RECORD REV. 00 PAGE(S): Entire Procedure DATE: 07-02-82 REV. 01 PAGE(S): Entire Procedure DATE: 07-22-82 REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: O APPROV L R MMENDED APPROVED < DA TE hV
' CHAIRMANSTA TION NUCLEARSAFETY 07-22-82 I AND OPERATING COMMITTEE
ND.97087210 I NUMBER PROCEDURE TITLE REVISION 01 EPIP-1.02 RESPONSE TO UNUSUAL EVENT PAGE 2 of 7
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTO8TAINED
- 1. INITIATE PROCEDURE:
a) Declare 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. O
- 2. STATE AND LOCAL GOVERNMENT NOTIFICATION:
a) Initiate EPIP-2.01, Notification of State and Local Governments NOTE: Updates of state and local governments should be provided at approximately 15 minute intervals and after significant changes to plant status, radiological data, or meteorological data.
- 3. NRC NOTIFICATION:
a) Initiate EPIP-2.02, Notification of NRC O 1 l L _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
No. 97887210 NUMBER PROCEDURE TITLE REVISION () EPIP-1.02 RESPONSE TO UNUSUAL EVENT PAGE 3 of 7 l l
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 4. CALL OUT OF PERSONNEL:
a) If required, call out appro-priate personnel using Emer-gency Notification List located in the NAPS Tele-phone Directory i NOTE: Call out of rescue and fire personnel is accomplished by AP- 51 , Personnel Injury, and AP- 50, Fire, respectively.
- 5. EVALUATE STATION CONDITIONS:
a) Unit (s) are NOT affected by a) ))[ a unit is affected, evalu-emergency condition ate 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 so conditions so indicate.
indicate
- 6. EVALUATE ONSITE PROTECTIVE MEASURES:
I a) Verify EIPI 4.01, a) Direct Radiological Assess-Radiological Assessment t.'ent Director to initiate Director Controlling EPIP-4.01, Radiological Procedure - ACTIVATED Assessment Director Control-ling Procedure b) Evaluate requirement for limited onsite evacuation
- 1) E required, sound ALERT Alarm and make appropriate announcement using Gai-() Tronics system t
Ns.97887210 NUMBER PROCEDURE TITI.E REVISION () EPIP-1.02 RESPONSE TO UNUSUAL EVENT 01 PAGE 4 of 7
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 6. (CONTINUED) c) Evaluate requirement for accountability
- 1) IJ[ required, initiate EPIP-5.03, Personnel Accounta-bility d) Evaluate requirement for -
radiological protection
- 1) Consult with Radiological Assessment Director
() 2) Initiate protective measures as required
- 7. FOLLOWUP STATE AND LOCAL GOVERNMENT NOTIFICATION:
a) Verify updated Health Physics a) Continue in this procedure dose assessments complete b) Verify timely followup State- b) Initiate EPIP-2.01, Notifi-and local government notific- cation of State and Local ation IAW EPIP-2.01, Notifica- Governments. tion of State and Local i Governments NOTE: Updates to State and local governments should be provided , at approximately 15 minute intervals. l
- 8. FOLLOWUP NRC NOTIFICATION:
a) Verify followup NRC notifi- a) Initiate'EPIP-2.02 cation IAW EPIP-2.02, Notification of NRC. Notificationof NRC O t 4
No. 97887210 NUMBER PROCEDURE TITLE REV/SION s - 01 EPIP-1.02 RESPONSE TO UNUSUAL EVENT PAGE 5 of 7 o
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 9. ADDITIONAL REPORTING:
a) Initiate evaluation of re-porting criteria IAW EPIP-2.03, Reports to Offsite Agencies b) Il[ required, initiate EPIP-2.03, Reports to Offsite Agencies
- 10. CHECK UNIT CONDITIONS:
a) Reactor plants - STABLE a) IF NOT stable confer with Supt. of Operations /SRO-On-Call and initiate further mitigating actions. () 11. CHECK RADIOLOGICAL CONDITIONS: a) Radiological conditions - a) IF NOT stable fMt IMPROVING STABLEfytIMPROVING confer with Supt. of Oper-ations and Radiological Assessment Director. AND Initiate further mitigating actions.
- 12. DAMAGE CONTROL:
a) Damage to Station equip- a) GO TO Step 13,. ment has been verified b) With Superintendent of b) IF NOT available, confer Operations and Superinten- with senior maintenance dent of Maintenance evaluate personnel onsite, extent of damage c) Evaluate following assist-ance requirements () 1) Offsite Technical assistance
' No. 97887210 NUMBER PROCEDURE TITLE REVISION EPIP-1.02 RESPONSE TO UNUSUAL EVENT PAGE 6 of 7
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 12. (CONTINUED)
- 2) Additional personnel
- 3) Material and equipment d) Initiate emergency repairs as required IAW approved station procedures
- 13. VERIFY CLASSIFICATION:
a) Review EPIP-1.01, A* tach- E new event identified or ment 1, Emergency Action Emergency escalated, GO TO Levels, THEN GO TO STEP EPIP-1.01, Emergency Man-13.b ager Controlling Procedure O' AND Step 2_, to identify and reclassify events. i b) Verify no additional events AND have occurred and emergency has NOT escalated Notify Radiological Assess-ment Director.
- 14. CHECK FOR TERMINATION:
a) Verify EALs - NOT EXCEEDED a) E EALs are still exceeded, return to Step 4 or this AND instniction. b) Verify plant condition - b) IF unstable, evaluate and l SAFE AND STABLE return to Step 4_ of this' l instruction. l AND l c) Onsite and offsite response . c) Continue monitoring and re- ! personnel - NOT REQUIRED turn to Step 4_ of this in- ! struction. O
No. 91887210 NUMBER PROCEDURE TITLE REVISION 01 EPIP-1.02 RESPONSE TO UNUSUAL EVENT PAGE 7 of 7
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 15. TERMINATE EPIP-1.02:
a) Close out
- 1) Initiate written summary to offsite authorities within
- 24 hrs
- 2) COMPLETED BY:
DATE: TIME: b) GO TO EPIP-1.01, Emergency Manager Controlling Proce-dure Step 8_ l l 1 I i l END l
No.97887200 VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE O NUMBER PROCEDURE TITLE REVISION 01 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.
NOT A CONTROLLED DOCUMENT JUL 2 41982 USER 99g ,,, . . .HE Station Emergency Manager LATEST HEVISION ENTRY CONDITIONS
- 1. Entry from EPIP-1.01, Emergency Manager Controlling Procedure.
VEPCO PROPERTY This document is tr.e property of * . l Virginia C2watric e d Power Co,' and is to Le roturned upon re- 1 No par:ais;1cn in granted to p.. ; ' reprcdcen, trao it or dt - kncther any !i.:.or.aa tion 00:.2 ) l this dncu.w n*,. f l
##"#kTr..#N## PAGE(S): Entire Procedure DATE: 07-02-82 l REV. 01 PAGE(S): Entire Procedure DATE: 07-22-82 l
REV. PAGE(S): DATE: i REV. PAGE(S): DATE: I REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE:
~) APPROV L RE MENDED APPROVED DA TE
]
07-22-82 1
} ,
CHAIRMAN STA TION NU EAR SAFETY AND GPERA TING COMMITTEE
N3.97887210 NUMBER PROCEDURE TITLE REVISION 01 O EPIP-1.03 RESPONSE TO ALERT PA GE 2 of 12
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 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. O 2. INPLANT NOTIFICATION: a) From'the Control Room, sound the ALERT Alarm b) Make announcement on plant Gai-Tronics system as follows:
- 1) "An ALERT has been declared" l
l 2)."All Emergency Response personnel report. to their assigned stations" l 3) "All visitors and 2000 l series badged personnel report to the Security Building" t
- 4) "All other-personnel A embl A
- .-- r- ,. - - - - - -
No.97887210 1 NUMBER PROCEDURE TITLE REVISION EPIP-1.03 RESPONSE TO ALERT PAGE 3 of 12
- STEP ACTION / EXPECTED 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) 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.
O S L) GO TO Step 7,of this instruction. i r
+,
- e. 4 Ns. sroen to
, NUMBER PROCEDURE TITLE REVISION 01 i O EPIP-1.03 RESPONSE TO ALERT PAGE
) 4 of 12
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED l
l 4
- 6. (CONTINUED) ll, b) Direct Security to activate l Corporate Emergency Response l Team by calling General Office i Security IAW Section 1.2.1 of NAPS Telephone Directory
] . i i i NOTE: Callout of rescue and fire personnel is accomplished by l AP- 51 , Personnel Injury, and AP- 50 , Fire respectively. t
- 7. EVALUATE STATION CONDITIONS:
, a) Unit (s) are NOT affected a) IJ[ a unit is affected, eval-by emergency condition uste safe operation of unaf-
- facted urit.
l 1) Evaluata safety of any , operating unit (s) AND
. 2) Consider unit (s) shutdown Consider unit shutdown if I if emergency conditions conditions so indicate.
so indicate
- 8. VERIFY EMERGENCY CENTERS /
l l FACILITIES: l l a) All emergency centers and a) GO TO Step 9, of this instruc- - . facilities - ACTIVATED tion. o) GO TO Step 12,of this instruction
- 9. VERIFY TSC ESTABLISHED:
a) Check TSC NOT previously a) GO TO Step 10[of this in-activated struction.
~
f i
-. _ _ _ . . - _ ~ . . _ - _ _ .- -. . . ~ _-_- - -- . _ . - _ = . . - _ _ _ -
Ns. 9 78812 3 0 NUMBER PROCEDURE TITLE REVISION 7s 01 () EPIP-1.03 RESPONSE TO ALERT PAGE 5 of 12
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED I
i 9. (CONTINUED) b) Relieve the Shif t Supervisor b) II[ no Shif t Supervisor relief as Station Emergency Manager GO TO Step 10,of this in-struction and return to Step
- 1) BY: 9 when appropriate.
DATE: TIME: c) If desired, relocate Station Emergency Maneser position to TSC d) Announce Station Emergency O 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:
I a) Check OSC NOT previously a) GO TO Step 11,of this in-activated struction. b) Assign appropriate individual i 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) CO TO Step 12,of this in-activated instruction. b) Activate EOF IAW EPIP-3.04, Activation of Emergency C) Operations Facility
_ = _ . _ - _ . , - _ - - - - . - . - . . . - - - - _ - . - - _ . - _ _ - . _ . . -
- m. orserne 4
NUMBER PROCEDURE TITLE REVISION l EPIP-1.0: RESPONSE TO ALERT PAGE 6 of 12
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 12. VERIFY EPIP-4.01:
i a) Assure EPIP-4.01, Radiological a) Direct Health Physics to Assessment Director Controlling initiate EPIP-4.01, Radio- , Procedure - ACTIVATED logical Assessment Director ' l Controlling Procedure,THEN GO TO Step M. b) Check status of EPIP-4.01, 4 Radiological Assessment Director Controlling Procedure c) Verify Onsite Monitoring Team -
- ACTIVATED I
- 13. CHECK RADIOLOGICAL CONDITIONS:
O a) Radiological conditions a) Confer with Radiological STABLE OR_ IMPROVING Assessment Director and Emergency Operations Director AND Initiate appropriate mitiga-ting actions l
- 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 , Initiate appropraite miti-4 gating actions.
- 15. DAMAGE CONTROL:
a) Damage to Station equip-a) GO TO Step 16,.- ment has been verified
i Ns. 97867210 , NUMBER PROCEDURE TITLE REVISION EPIP-1.0 3 RESPONSE TO ALERT PAGE 7 of 12
- STEP ACTION / EXPECTED RESPONSE RESPONSENOT08TAINEO t
- 15. (CONTINUED) b) With Emergency Operations b) IJ[ TSC NOT activated confer i
and Maintenance Directors, , with senior operations and evaluate extent of damage maintenance personnel onsite. c) Evaluate following assist- , ance requirements
- 1) Offsite Tecnnical
- 2) Additional personnel
- 3) Material and Equipment a d) Instruct Emergency Main- d) IJ[ 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 17. evacuation of buildings or areas - REQUIRED t b) Sound AI.ERT 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 EPIP-2.01,
-State / County notification Notification of State and IAW EPIP-2.01, Notification Local Governments.-
of State and Local Govern-ments
- - - - . - , -- .n .-,,,m , .-r,- s -- -- --.- .-, , -- ,,, ,n -, ,,-.e- g v , , ,
N3. 97887210 NUMBER PROCEDURE TITLE REVISION 01 EPIP-1.0 RESPONSE TO ALERT C) 1 PAGE 8 of 12
- STEP ACTION / EXPECTED RESPONSE RESPONSENOT08TAINE0
- 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 C@t greater I s than ji Remthyroid
- 2) Direction of plume travel l
~~ w - ~ ~. m-
N*.97887210 NUMBER PROCEDURE TITLE REVIS. 'N _01 O EPIP-1.03 RESPONSE TO ALERT PAGE 9 of 12 I
- STEP ACTION / EXPECTED RESPONSE RESPONSENOT00TAINE0
- 22. INITIATE SITE EVACUATION:
a) 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
.s of evacuation initiation IAW EPIP-2.02, Notification of NRC
- 24. EMERGENCY EXPOSURE:
a) Evaluation of conditions indi- a) GO TO Step 25. cates authorization of emer-gency radiation exposure limits should be considered b) Implement EPIP-5.06, Emergency Radiation Exposure Authorization
- 25. BLOCKING AGENT:
l a) On recommendation of a) GO TO Step 21 Radiological Assess-ment Director evaluate issuance of Radioiodide blocking agent to onsite personnel if following l exist
- 1) Projected onsite total
- absorbed dose equiva-l lent I-131-GREATER l
THAN 10 Rem
. s No. 97887210 i
NUMBER PROCEDURE TITLE REVISION () 01 EPIP-1.03 RESPONSE TO ALERT PAGE 10 of 12
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 25. (CONTINUED) pR
- 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
- 26. VERIFY EVENTS:
a) Review EPIP-1.01, Attach-ment 1, Emergency Action Levels, and return to this step b) Insure additional events b) Initiate station APs, EPs, l have NOT occurred or EPIPs to address new I events. AND t l Notify Radiological Assess-ment Director
- AND I
Insure initiation of EPIP-2.01, Notification of State and Local Governments and EPIP-2.02, Notification of NRC l s i c) Check that emergency has c) II[ escalated, GO TO EPIP-NOT escalated 1.01, Emergency Manager , Controlling Procedure, ! , Step 6,. i
N:p. 97887210 NUMBER PROCEDURE TITLE REVISION 01 O EPIP-1.03 RESPONSE TO ALERT PAGE 11 of 12
- STEP ACTIONNXPECTED RESPONSE RESPONSENOTOBTAINED
- 27. CHECK FOR TERMINATION:
a) Verify EALS - NOT EXCEEDED a) E EALS are still exceeded, GO TO Step 28. 8 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 30,for termination
- 28. CHECK FOR RECLASSIFICATION:
a) Step 26 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: O' TIME: ( .
'No.97887210 NUMBER PROCEDURE TITLE REVI:10N i
00 EPIP-1.03 RESPONSE TO ALERT i O. PACE 12 of 12 r
- STEP - -' ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED 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 vritten summary -
to offsite authorities within 8 hours O- 2) COMPLETED BY: DATE: TIME: c) GO TO EPIP-1.01, Emergency-Director Controlling Pro-cedure, Step 8_ O -
I. i' ((, .';..... '..,f 'f ' ;. MP.-N:v .h.4.1. ' . N :.Mc 1.~ . . . ; . .
~Y f, 1[.a1. .+'J- * - ' ' . . ~ .
s )+f, No. 97887200 VIRGINIA ELECTRIC AND POWER COMPANY 1 NORTH ANNA POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE O NUMBER PROCEDURE TITLE REVISION 01 EPIP-1.04 RESPONSE TO SITE EMERGENCY PAGE (With No Attachments) 1 of 13 l l PURPOSE .
- 1. To provide guidance to the Station Emergency Manager during the pro-gress of a classified SITE emergency.-
NOT A CONTROLLED DOCtiMENT JUL 241982 USER No.. .sE Station Energency Manager LATt.Si ut. VISION ENTRY CON 0lTIONS
- 1. Entry from EPIP-1.01, Emergency Manager Controlling Procedure.
O VEPCO PROPERTY This docucent is the property of Virginia Bloctric and Power Con: and is ta 'ca returned epon re: .m . . No permission is granted to pif. reproduce. t: c ' it or dir c: lev another at.y in ormation cor.5.. this document.
#'"##N[.gga PAGE(S): Entire Procedure DATE: 07-02-82 REV. 01 PAGE(S): Entire Procedure DATE: 07-22-82 REV. PAGE(S): DATE:
REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: O APPROVAL REC 'MMENDED APPROVED - DA TE s/ 07-22-82 l CHAIRMANSTATIONNUCL ARSAFETY AND OPERA TING COMMITTEE
( N3.97887210 NUMBER PROCE00RE TITI.E REVISION I EPIP-1.04 RESPONSE TO SITE EMERGENCY PAGE 2 of 13
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 1. INITIATE PROCEDURE:
a) Declare 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. O
- 2. INPLANT NOTIFICATION:
a) From the Control Room, sound the ALERT Alarm b) Make announcement on plant Gai-Tronics system as follows:
- 1) "A SITE EMERGENCY has been declared"
- 2) "All Emergency Response personnel report to their assigned stations"
- 3) "All visitors and 2000 series badged personnel report to the Security Building"
- 4) "All other personnel report to their Emer-gency Assembly Areas"
N3.97887210 NUMBER -~ ~ PR lEDURE TITLE REVISION 01 J EPIP-1.04 RESPONSE TO SITE EMERGENCY PA GE 3 of 13 l l
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 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 l l NOTE: Updates to offsite authorities should be provided at l approximately 15 minute intervals and after significant l changes to plant status, radiological data, or meteorological data, j 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. O GO TO Step AND 7 of this instrtiction.
_- - ~ . - . .. .- N3.97887210 NUMBER PROCEDURE TITLE REVISION EPIP-1.04 RESPONSE TO SITE EMERGENCY PAGE 4 of 13
- STEP ACTION / EXPECTED RESPONSE RESPONSE Nt'~0BTAINED
- 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.
4 O 7. EVALUATE STATION CONDITIONS: a) Unit (s) are NOT affected a) IF a unit is affected, eval-by emergency condition uate safe operation of unaf-fected unit. -
; 1) Evaluate safety af any AND operating unit (s)
Consider unit shutdown if
- 2) Consider unit (s) shutdown conditions so indicate.
if emergency conditions l so indicate 1
- 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 g of this i instruction b v l
Ns.97887210 NUMBER PROCEDURE TITI.E REVISION EPIP-1.04 RESPONSE TO SITE EMERGENCY PAGE 5 of 13
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 9. VERIFY TSC ESTABLISHED:
a) Check TSC NOT previously a) GO TO Step IC[ of this in-activated struction. b) Relieve the Shift Supervisor b) IJ[ Shif t Supervisor relief as Station Emergency Manager NOT available GO TO Step 10[ of this instruction and return to Step j[ when appropriate.
- 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 TSO 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 IAW EPIP-3.03, Activation of Operational Support Center O l
r+0.97887210 NUMBER PROCEDURE TITLE REVISION [} V EPIP-1.04 RESPONSE TO SITE EMERGENCY 01 PAGE 6 of 13
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 11. VERIFY EOF ESTABLISHED:
a) Check EOF NOT previously a) GO TO Step 12 of this activated instruction. b) Activate EOF IAW EPIP-3.04, Activation of Emergency Operations Facilicy
- 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 13,. b) Check status of EPIP-4.01, 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 Ojt IMPROVING Assessment Director and Emer-gency Operations Director. AND Initiate appropriate miti-gating actions.
- 14. CHECK UNIT CONDITIONS:
a) Reactor plant (s) - STABLE a) Confer with Emergency Opera-tions Director.
-. .-. _ . . - . .. - . . _ _ = _ _ .=_ .
No.97847210 NUMBER PROCEDUR. TITLE REVISION EPIP-1.0L RESPONSE TO SITE EMERGENCY PAGE 7 of 13
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 14. (CONTINUED)
Initiate appropriate miti-
- gating actions.
- 15. DAMAGE CONTROL:
a) Damage to Station Equip- a) GO TO Step 16. ment has been verified b) With Emergency Operations b) IJ[ TSC NOT manned confer and Maintenance Directors, with senior operations evaluate extent of damage and maintenance personnel onsite. ( c) Evaluate following assist-ance requirements
- 1) Offsite Technical
- 2) Additional personnel
- 3) Material and Equipment d) Instruct Emergency Main- d) Il[ NOT available, initiate tenance Director to ini- interim damage control acti-tiate EPIP-5.08, Damage vitias.
Control
- 16. VERIFY ONSITE CONDITIONS:
i l a) Evaluation indicates limited a) GO TO Step 17 of this in-evacuation of buildings or struction. areas - REQUIRED b) Sound ALERT Alarm and make appropriate announcement using the plant Cai-Tronics system g-~g 17. FOLLOW-UP STATE / COUNTY NOTIFICATION: l a) Verify updated Health Physics dose assessments completed
l N3.97887210
~ NL *BER PROCEDURE TITLE REVISION l 01 EP1P-1.04 RESPONSE TO SITE EMERGENCY PAGE l
8 of 13
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 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 Govern-ments
- 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) Initiate EPIP-5.02, Search IAW EPIP-5.03, Personnel and Rescue. Accountability
- 21. SITE EVACUATION:
() a) Radiological Assessment Director recommends site a) GO TO Step 23,. evacuation
Ns,97847210 NUMBER PROCEDURE TITLE REVISION EPIP-1.04 RESPONSE TO SITE EMERGENCY PAGE 9 of 13
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 21. (CONTINUED) b) Consider the following:
- 1) Onsite dose greater than 1, Rem whole body OJt greater than i Rem thyroid exposure
- 2) Characteristics and direction of the plume
- 3) Contaminntion vs. per-sonnel safety and ex-posure
- 22. INITIATE SITE EVACUATION:
O a) Implement EPIP-5.05, Site . Evacuation
- 23. OFFSITE RECOMMENDATIONS:
a) Radiological Assessment a) GO TO Step 25. 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 lj! Rem thyroid expo-sure
- 2) Characteristics and direction of plume c) GO TO Step 24,and make appropriate recommend-ations to offsite agencies
N3.97887210 NUMBER PROCEDURE TITLE REVISION EPIP-1.0 o RESPONSE TO SITE EMERGENCY PAGE 10 of 13
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 24. EVACUATION / RECOMMENDATION 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
- 25. EMERGENCY EXPOSURE:
a) Evaluation of conditions indi- a) GO TO Step j!i j 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 Radiciodide blocking agent to onsite personnel if following exist , O
, m c- -. - - , . - - -
No. S7447210 NUMBER PROCEDURE TITLE REVISION () EPIP-1.04 RESPONSE TO SITE EMERGENCY PAGE 11 of 13
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 26. (CONTINUED)
- 1) Projected onsite total absorbed dose equiva-lent I-131-GREATER THAN 10 Rem pR,
- 2) Actual onsite total absorbed dose equiv-alent I-131-GREATER THAN 10 Rem b) Direct Radiological Assessment Director to O implement EPIP-5.07, Administration of Radioprotective Drugs
- 27. VERIFY EVENTS:
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. AND Notify Radiological Assess-ment Director. AND Insure initiation of EPIP-2.01, Notification of State and Local Governments and EPIP-2.02, Notification of [U) NRC.
No. 97887210
+
NUMBER PROCEDURE TITLE REVISION EPIP-1.04 RESPONSE TO SITE EMERGENCY PAGE 12 of 13 l
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 27. (CONTINUED) c) Check that emergency has c) IF,F 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 29. b) Verify plant conditions - b) Evaluate conditions and GO TO SAFE AND STABLE Step 7. O - c) Onsite and offsite c) Continue monitoring activi-response personnel - NOT ties and GO TO Step H. REQUIRED d) GO TO Step H 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 3_0,for 0 procedure termination
- 30. TERMINATE EPIP-1.04:
a) Verify Recovery Manager concurrence b) Close out
- 1) Initiate briefing of off-O site authorities at EOF and by phone
No. 97887210
.~
NUMBER PROCEDURE TITLE REVISION EPIP-1.04 RESPONSE TO SITE EMERGENCY PAGE 13 of 13
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 30. (CONTINUED)
- 2) Initiate written summary to offsite authorities within 8 hours
- 3) COMPLETED BY:
DATE: TIME: b) GO TO EPIP-1.01, Emergency 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:
l DATE: TIME: l c) C0 TO EPIP-1.01, Emergency Director Controlling Pro-cedure, Step 8 O l END _ . _ _ _ _ _ - . _ _ ~_ _ -. . _.
l N3.97847200 VIR*lNIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION EMERGENCY PLAN lMPLEMENTING PROCEDURE NUMBER PROCEDURE TITLE REVISION 01 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.
NOT A rONTROL LFO USER DOCUMENf Station Emergency Manager JUL 241982 NON .W ENTRY CONDITIONS Lhit.bi 81cV\btON _ 1. Entry From EPIP-1.01, Emergency Manager Controlling Procedure. VEPCO PROPERTY This document is the property of the Virginia Electric and Power Company and is to be roturned upon req.:est .
!!o permiccion is granted to pain Mi ,
reproduce. trans-it or dicek another iny informat. ion conta f ' this document. - I 1 REVISION RECORO l REV. 00 PAGE(S): Entire Procedure DATE: 07-02-82 REV. 01 PAGE(S): Entire Procedure DATE: 07-22-82 REV. PAGE(S): DATE: REV. PAGE(S): . DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: l O 0 APPROVAL RECOMMENDED APPROVEO DA TE 45#7/ j
/ 07-22-82 q CHAIRMANSTATIONNUCL ARSAFETY
, ANO OPERATING COMMITTEE w
. . No. 9?C87210 NUMBER PROCEDURE TITLE REVISION ; 01 EPIP-1.05 RESPONSE TO GENERAL EMERGENCY 1
O\ PAGE 2 of 21 i. 1
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTQBTAINED i
- 1. INITIATE PROCEDURE:
a) Declare position of Station Emergency Manager I b) BY: DATE: TIME: NOTE: The Shift Supervisor may be relieved as Station Emergency Manager IAW the NAPS Emergency Plan.
< 0 2. INPLANT NOTIFICATION:
a) From the Control Room, i 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 l their assigned stations" -
- 3) "All visitors and 2000 series badges personnel report to the Security Building"
- 4) "All other personnel report to their Emer-gency Assembly Areas" f
l
*
- No 97a37210
\
NUMCER i PROCEDURE TITLE REVISION 01 O EPIP-1.05 RESPONSE TO GENERAL EMERGENCY PAGE 3 of 21 o
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 2. (CONTINUED) c) Repeat Steps 2 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 O 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:
j a) Following conditions have a) GO TO Step 5 of this instruc-been met: tion. l [ 1) RCS specific activity - ! GREATER THAN 3000 uCi/ gram dose equivalent I-131 E l 5 or more core exit thermocouples - GREATER THAN 2000*F
- 2) Containment High Range Radiation Monitgr -
GREATER THAN 10 mR/hr
N3.97887210 NUMBER PROCEDURE TITLE REVISION 01 EPIP-1.05 RESPONSE TO GENERAL EMERGENCY O\ PAGE 4 of 21
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 4. (CONTINUED)
- 3) Containment failure imminent as indicated by pressure - GREATER THAN 60 psia and NOT DECREASING ,
9.R Shif t Supervisor judge-ment that containment failure has occured , b) Determining protective b) Request Radiological Assess-actions: ment Director aid in determi-O 1) Determine wind speed and affected sectors nation of sheltering recom-mendations IAW EPIP-4.01, Radiological Assessment Director Controlling a) ))[ wind speed LESS Procedure. THAN 2.5 mph recom-mend sheltering out to and including Zone 5 in affected sectors AND Recommend evacuation in Zones 6 thru 10 in affected sectors AND Recommend evacuation out to and including Zone 5 in unaffected sectors O
No. 97887210 i 1 l NUMBER PROCEDURE TITLE REVISION 01 i O EPIP-1.05 RESPONSE TO GENERAL EMERGENCY PAGE 5 of 21 e
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOSTAINED
- 4. (CONTINUED) b) IF, 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 g
- 5. CORE MELT AND S/G TUBE RUPTURE WITH STEAM BREAK:
a) Following conditions have a) GO TO Step 6 of this instruc-been met: tion.
- 1) RCS specific activity-GREATER THAN 3000 uC1/ gram dose equivalent I-131 2R 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 O- 100 psig
Ns.97887210 NUMBER PROCEDURE TITLE i REVISION j 01 EPIP-1.05 RESPONSE TO GENERAL EMERGENLi Q PAGE 6 of 21 a
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 5. (CONTINUED) b) Determine protective actions b) Request Radiological Assess-and offsite recommend- ment Director aid in determi-ations'IAW Step 4.b P, age nation of sheltering recom-4 of 21 of this inst ruction, mendations IAW EPIP-4.01, THEN GO TO Step 12. ,'
Radiological Assessment Director Controlling Procedure. c) GO TO Step H
- 6. CORE MELT AND LOCA WITH CONTAINMENT FAILURE LIKELY:
a) Following conditions have a) GO TO Step 7,of this instruc-been met: tion.
- 1) RCS specific activity-GREATER THAN 3000.0 uCi/
g dose equivalent I-131 0,,,R, 5 or more core exit thermocouples-GREATER l THAN 2000*F l
- 2) Containment High Range RadiationMonitgr-GREATER THAN 10 mR/hr
- 3) Containment failure is likely as indicated by l significantly impaired
; ECCS and pressure-GREATER THAN 27.75 psia I
l
No. 97887210 NUMBER PROCEDURE TITLE REVISION 01 O EPIP-1.05 RESPONSE TO GENERAL EMERGENCY PAGE 7 of 21 ' l l
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 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 -
(67
- total) c) GO TO Step 12 O
t O 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 T13 3000.0 uCi/
, e dose equivalent I-131
- AND 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 NOT likely as indicated by pressure - LESS THAN 27.75_ psia AND DECREASING
No. 97887210 NUMBER PROCEDURE TITLE REVISION 01 EPIP-1.05 RESPONSE TO GENERAL EMERGENCY O\ PAGE 8 of 21
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 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 mendations IAW EPIP-4.01, out to and including Radiological Assessment Zone 2 (360') Director Controlling Procedure.
- 2) Evacuation of the popu-lation out to and includ-ing Zone 5 in downwind and adjacent sectors (67h* total)
- 3) Sheltering in Zones 5 out to 10 in downwind and adjacent sectors (67
- total) c) GO TO Step g
- 8. LOW CONTAINMENT ACTIVITY:
a) Following conditions have a) GO TO Step 9_ of this instruc-been met: struction.
- 1) RCS specific activity-GREATER THAN 3000.0 uCi/
grjam dose equivalent I-131 SR 5 or more core exit thermocouples-GREATER THAN 2000*F
- 2) Containment-High Range Radiation Mogitor -
LESS THAN 10 mR/hr O
Ns.97887210 l l NUMBER PROCEDURE TITLE REVISION
- t O EPIP-1.05 RESPONSE TO GENERAL EMERGENCY PAGE 9 of 21 a
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 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 M h)
- 9. S/G TUBE RUPTURE WITH MS SAFETY LIFT LIKELY:
a) Following conditions have a) GO TO Step g of this in-been met: , struction.
- 1) RCS specific activity-GREATER THAN 3000.0 uCi/
l g dose equivalent 1-131 O_R l 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 l 3) Shift Supervisor judgement that lifting of MS sa#ety valve (s) is likely O
. No. 97887210 NUMBER PROCEDURE TITLE REVISION <
01 { EPIP-1.05 RESPONSE TO GENERAL EMERGENCY s
)
PAGE 10 of 21 l
- STEP ACTION! EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 9. (CONTINUED)
I 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 2 (360') Director Controlling Procedure.
- 2) Evacuation of the popu-lation out to and includ-ing Zone 5 in downwind and adjacent sections (67h* total)
O 3) Sheltering in Zones 5 out to 10 in down wind and adjacent sectors (67b' Total) c) GO TO Step 12, ! 10. SIGNIFICANT RELEASE POTENTIAL: a) Any of the following exist: a) GO TO Step 11,of this in-struction.
- 1) Projected site boundry doses exceed 2 Rem wholev body or M Rem thyroid exposure 0,,R l 2) Control of physical security of station lost b) Recommend evacuation within b) Request Radiological Assess-a radius out to and includ- ment Director aid in determi-ing Zone 2 (360') nation of evacuation recom-mendations IAW EPIP-4.01,
(,, ()T Radiological Assessment Director Controlling Procedure, i
N3.97887210 NUMBER PROCEDURE TITLE REVISION 01 O EPIP-1.05 RESPONSE TO GENERAL EMERGENCY PAGE 11 of 21 1
- STEP ACTION / EXPECTED RESPONSE l RESPONSENOT OBTAINED
- 10. (CONTINUED) c) GO TO Step 12,
- 11. MISCELLANEOUS EVENTS:
a) A General Emergency has been declared for any reason other then those specifically men-tioned S.R Shift Supervisor / Emergency Manager judgement indicates actions required to protect O the hedith and safety of the public b) Recommend the following: b) Request Radiological Assess-i ment Director aid in determi-
- 1) Sheltering of the popu- nation of sheltering recom-lation within a radius mendations IAW EPIP-4.01, out to and including Radiological Assessment Zone 2 (360') Director Controlling Procedure 1 2) Sheltering of the popu-lation out to and includ-ing Zone 5 in downwind and adjacent sectors (67
- total) c) GO TO Step 12[
- 12. STATE AND COUNTY NOTIFICATION:
a) Initiate EPIP-2.01, Notification of State and Local Governments j 13. NRC NOTIFICATION: a) Notify NRC Operations Center IAW EPIP-2.02, Notification of NRC
= No.97887210 NUMBER PROCEDURE TITLE REVISION 01 O EPIP-1.05 RESPONSE TO GENERAL EMERGENCY PAGE 12 of 21
- STEP ACTION / EXPECTED RESPONSE RESPONSENOT OBTAINED l
NOTE: Updates to offsite authorities should be provided at approximately 15 minute intervals and af ter significant changes to plant status, radiological data, or meteorological data.
- 14. CALLOUT OF PERSONNEL:
a) Verify Emergency Response a) Direct Security to initiate Personnel - ONSITE EPIP-3.01, Call out of Emer-gency Response personnel. O 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 NOTE: Callout of rescue and fire personnel is accomplished by j AP- 51, Personnel Injury / Overexposure and AP 50 , Fire j respectively. ! 15. EVALUATE STATION CONDITIONS: { l a) Unit (s) are NOT affected a) ))[ a unit is affected, eval-by emergency condition uate safe operation of unaf-fected unit. AND,
N 3. 97887210 NUMBER PROCEDURE TITLE REVISION ,o 01 () EPIP-1.05 RESPONSE TO GENERAL EMERGENCY PA GE 13 of 21 l i r- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED l
- 15. (CONTINUED)
- 1) Evaluate safety of any Consider unit shutdown if operating unit conditions so indicate.
- 2) Consider unit shutdown I if emergency conditions 1 so indicate l i
- 16. VERIFY EMERGENCY CENTERS / FACILITIES:
a) All emergency centers and a) GO 'u. Step 17,of this facilities - ACTIVATED instruction. b) GO TO Step 211 of this instruction
- 17. VERIFY TSC ESTABLISHED:
a) Check TSC NOT previously a) GO TO Step 1E[ of this in-activated struction. b) Relieve the Shif t Supervisor b) Il[ Shif t Supervisor relief as Emergency Manager NOT available GO TO Step IJ[ of this instruction and
- 1) BY: return to Step 12,when appropriate.
DATE: TIME: c) If desired, relocate 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.
ND.97887210 NUMBER PROCEDURE TITLE REVISION EPIP-1.05 RESPONSE TO GENERAL EMERGENCY PAGE 14 of 21
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 18. VERIFY OSC ESTABLISHED:
a) Check OSC NOT previously a) CO TO Step p 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
- 19. VERIFY EOF ESTABLISHED:
a) Check EOF NOT previously a) GO 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, L Radiological Assessment l Director Controlling j Procedure b) Verify onsite Dose Assess-ment Team (s) - ACTIVATED c) Verify offsite dose Assess-ment Team (s) - ACTIVATED i
- 21. CHECK RADIOLOGICAL CONDITIONS:
a) Radiological conditions - a) Confer with Radiological' STABLE 3 IMPROVING Assessment Director-and l Emergency Operations Director. AND x Initiate appropriate miti-gating actions. e
, - , - , - . - -r-w, --- . - - . . . v- w * - t , * - - -
Nh.97887210 NUMBER PROCEDURE TITLE REVISION () 01 EPIP-1.05 RESPONSE TO GENERAL EMERGENCY PAGE 15 of 21 l l
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 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) Damage to station equip- a) GO TO Step 24,. ment has been verified b) With Emergency Operations b) j][ TSC NOT manned confer O and Maintenance Directors, evaluate extent of damage with senior operations and maintenance person-nel onsite. c) Evaluate following assist-ance requirements
- 1) Offsite Technical
- 2) Additional personnel
- 3) Material and Equipment d) Instruct Emergency Mainte- d) j][ 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) GO TO Stepj_j!i of this in-evacuation of buildings or struction. areas - REQUIRED b) Sound ALERT Alarm and make appropriate announcement 1 using the plant Gai-Tronics C/' system
- - -- .-. - .=. .- .__.
I No. 97887210 I l l NUMBER PROCEDURE TITLE REVISION I 01 I EPIP-1.05 RESPONSE TO GENERAL EMERGENCY PAGE 16 of 21
- STEP ACTION / EXPECTED RESPONSE RESPONSENOT OBTAINED
- 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 Govern-ments
- 26. 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.
- 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:
a) All personnel accounted for a) Initiate EPIP-5.02, Search IAW EPIP-5.03, Personnel and Rescue. Accountability (
f N3.97887210 NUMBER l PROCEDURE TITLE REVISION EPIP-1.01 RESPONSE TO GENERAL EMERGENCY PAGE 17 of 21
- STEP ACTION / EXPECTED RESPONSE RESPONSENOT OBTAINED
- 29. SITE EVACUATION:
a) Radiological Assessment a) GO TO' Step 32,. Director recommends site evacuation b) Consider the following:
- 1) Onsite dose greater than 1 Rem whole body 0]t greater than 5, Rem thyroid exposure
- 2) Characteristics and direction of the plume
- 3) Contamination vs. per-O. 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 33,. O. indicates authorization of emergency radiation expo-sure limits should be considered
No. 97887210
; NUMBER PROCE0 LIRE TITLE , REVISION EPIP-1.05 RESPONSE TO GENERAL EMERGENCY PAGE 18 of 21
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 32. (CONTINUED) b) Implement EPIP-5.06, Emergency Radiation Exposure Authorization
- 33. BLOCKING AGENT:
a) On recommendation of a) GO TO Step 34_. Radiological Assess-ment Director evaluate issuance of Radiciodide blocking agent to onsite personnel if following exist: O 1) Projected onsite total absorbed dose equiva-lent I-131-GREATER THAN 10 Ren S.E
- 2) Actual onsite total
! absorbed dose equiv-l alent I-131-GREATER THAN 10 Rem b) Direct Radiological Assessment Director to implement EPIP-5.07, Administration of Radioprotective Drugs
- 34. VERIFY EVENTS:
a) Review EPIP-1.01, Attach-ment 1,' Emergency Action l Levels, AND return to Step 34.b b U
No. 97887210 4 I NUMBER PROCEDURE TITLE REVISION l EPIP-1.05 RESPONSE TO GENERAL EMERGENCY PAGE 19 of 21 l l
- 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.
AND Notify Radiological Assess-ment Director. AND Insure initiation of EPIP-2.01, Notification of State n g 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 -
~-'TO GO Step _35,5
- 2) E condition - DEGRADED -
GO TO Step 4 for reeval-untion of recommendations
- 35. CHECK FOR TERMINATION:
a) Verify EALS - NOT EXCEEDED a) E EALS are still exceeded, GO TO Step 36. 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 H.. REQUIRED d) GO TO Step 38,to terminate
No. 97887210 NUMBER PROCEDURE TITLE REVISION 01 O EPIP-1.05 RESPONSE TO GENERAL EMERGENCY FAGE 20 of 21
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 36. CHECK FOR RECLASSIFICATION:
a) Step M indicates event a) GO TO Step 4 of this in-severity - REDUCED struction. b) Reclassify event and GO TO
. Step E for procedure termination
- 37. TERMINATE EPIP-1.05:
a) Verify Recovery Manager concurrence b) Close out O 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 O ,
- 1) Initiate briefing of offsite authorities at EOF and by phone s .
a
N3.97887210 NUMBER PROCEDURE TITLE REVISION 01 EPIP-1.05 RESPONSE TO GENERAL EMSRGENCY PAGE 21 of 21
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINEO
- 38. (CONTINUED)
- 2) Initiate written summary to offsite authorities within 8_ hours
- 3) COMPLETED BY:
DATE: TIME: c) GO TO EPIP-1.01, Emergency Director Controlling Pro-cedure Step 8_ 1 O END i i ._ _.
- No. 97847200 VIRGINIA ELECTRIC AND POWER COMPANY
,, NORTH ANNA POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE O NUMBER PROCEDURE TITLE REVISION l
\
01 EPIP-2.01 NOTIFICATION OF STATE AND LOCAL GOVERNMENTS l PA GE (k*ith 2 Attachments) 1 of 16 PURPOSE
- 1. To initially notify state and local governments of the declaration of an emergency; AND
- 2. To provide periodic status updates to state and local governments during an emergency; AND .
- 3. To notify state and local governments of any change in emergency status.
USER Emergency Communicator O_R R Station Emergency Manager. rmr a en mm ,, ENTRY CONDITIONS Ong yyy'~ Any one of the following: O 1. Emergency is declared; JUL 341982 No;g ,, g pR LATEs1 niv
- 2. Approximately 15 minutes have passed since last notificat k OR-
- 3. The status of any notification item has changed; OR
- 4. Entry directed by Station Er.:argeEy Manager.
l VEPCO PROPERTY Thia document la the pror er ty ol' , Virginia E4 +:tric and Po.er Co w and is to to returned upon r % c:- No perniccion il granted to poi
- r.
h:* rs ;'rv d a c e , transmit oc dicelese tc j .r. ;t ne r :my ir.rorr.a ti cn cart t .11ria.
. ..a. ..
REVISION RECORD, 1 I l REV. CO PAGE(S): Entire Procedure DATE: 07-02-82 REV. 01 PAGE(S): Entire Procedure DATE: 07-22-82 REV. PAGE(S): DATE: REV. PAGE(S): .DATE: j REV. PAGE(S): DATE: l REV. PAGE(S): DATE: l REV. PAGE(S): DATE: APPROVAL RECO NDED APPROVED - ' - OA TE
- r
- 07-22-82 IRMANSTA TION NUCLEARSAFETY AND OPERA TING COMMITTEE l
, , No. 97887210 NUMBER PROCEDURE TITLE REVISION EPIP-2.01 NOTIFICATION OF STATE AND LOCAL GOVERNMENTS PAGE 2 of 16
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED 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 15 minutes or when there are changes in emergency conditions.
- 1. INITIATE PROCEDURE:
a) INITIATED BY'. TIME: DATE:
- 2. OBTAIN EMERGENCY REPORT FORM:
a) Attachment 1, Report 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 NOTE: 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:
a) IF in Control Room, obtain a) IF NOT, contact Control Room
/ from Met. Panel and request data.
N3.97887210 NUMBER PROCEDURE TITLE REVISION (q / EPIP-2.01 NOTIFICATION OF STATE AND LOCAL GOVERNMENTS 01 LJ PA GE 3 of 16
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 4. (CONTINUED) b) Read wind direction degrees b) IF NOT operable, read Record-from Recorder ZR-MM-101A, er ZR-MM-101C, " Backup Tower
" Main Tower Upper Wind- Wind Direction".
Direction" c) Use wind direction degrees AND Table 1 to determine compass point wind is blowing from TABI.E 1 s COMPASS COMPASS COMPASS POINT (w) DEGREES 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 l 102-124 = ESE 282-3G4 = WNW 462-484 = ESE l 125-146 = SE 305-326 = NW 485-506 = SE l 147-169 = SSE 327-349 = NNW 507-529 = SSE 530-540 = S l d) Record compass point in item 7 of Attachment 1
-- ' -+
No. 97881210 NUMBER -PROCEDURE 1 *LE REVISION O 01 EPIP-2.01 NOTIFICATION OF STATE AND LOCAL GOVERNMENTS PA GE 4 of 16
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 5. DETERMINE WIND SPEED:
a) IF in Control Room, a) IF NOT, contact Control Room obtain from Met. Panel and request data. b) Read wind speed from b) IF NOT operable, read Record-Recorder SR-MM-101A, er SR-MM-101C, " Backup Tower
" Main Tower Upper Wind Speed".
Speed" c) Record wind speed in Item 7 of Attachment 1
- 6. DETERMINE STABILITY CLASS:
O a) IF_ in Control Room, a) IF NOT, contact Control Room () obtain from Met. Panel and request data. b) Read Delta T from Recorder b) IF NOT operable, read Sigma TR-MM-101B, " Main Tower Theta from Recorder ST-MM-101 l Delta T" " Backup Tower Sigma Theta". AND AND Use Table 2 to determine Use Table 3 to determine stability class. stability class. TABLE 2 l DELTA T STABILITY DELTA T STABILITY l (*F) CLASS (*F) CLASS l
-2.0 to -1.4 = A -0.4 to +1.0 = E
-1.4 to -1.2 = B +1.0 to +2.8 = F
-1.2 to -1.1 = C +2.8 to +3.0 = G
-1.1 to -0.4 = D I O l .
U l
No.97887210 NUMBER PROCEDURE TITLE REVISION EPIP-2.01 NOTIFICATION OF STATE AND LOCAL GOVERNMENTS PAGE 5 of 16
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 6. (CONTINUED)
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 - 2.1 to 0 = G 12.5 to 7.5 = D-O c) Record stability class in Item 7 of Attachment 1
- 7. CHECK RADIOACTIVE RELEASE STATUS:
a) Release-HAS OCCURRED a) IF NOT, record "None" in Item 8_ of Attachment 1, pR AND . Release-HAS OCCURRED GO TO Step 11. RR_ Release-IS PROJECTED
- 8. DETERMINE AFFECTED SECTORS:
a) Use wind direction from Item 7,of Attachment 1_ AND Table 4 to determine l O affected sectors \ '% '
N3.97887210 NUMBER PROCEDURE TITLE REVISION EPIP-2.01 NOTIFICATION OF STATE AND LOCAL GOVERNMENTS PAGE 6 of 16
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 8. (CONTINUED)
TABLE 4 COMPASS COMPASS POINT AFFECTED SECTORS POINT AFFECTED SECTORS N Hotel-Juliett-Kilo S Romeo-Alpha-B_ravo NNE J_uliett-Kilo-Lima SSW Alpha-Bravo-Charlie NE Kilo-Lima-M_ike SW B_ravo-C_harlie-D_ elta ENE WSW Lima-M_ike-N_ovemb e r Charlie-D_ elta-Echo E M_ike-November-Papa W Delta-Echo-Foxtrot ESE N_ovember-Papa-guebec 'WNW Echo-Foxtrot-Golf SE P_apa-guebec-R_omeo NW F_oxtrot-Golf-Hotel l SSE Ruebec-R_omeo-Alpha NNW Golf-Hotel-Juliett 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." l 9. 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 !O w
No. 97887210 NUMBER PROCEDURE TITLE REVISION EPIP-2.01 NOTIFICATION OF STATE AND LOCAL GOVERNMENTS PAGE 7 of 16 l
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED NOTE: During the initial stages of an'energency, prior to manning the Technical Support Center (TSC), the Radiological Assess-ment Director will be the senior H.P. member onsite, who will be located in the Control Room or H.P. office. After the TSC is manned, the Radiological Assessment Director will be located in the TSC.
- 10. INFORM RADIOLOGICAL ASSESSMENT DIRECTOR OF MET DATA:
a) Inform Radiological Assessment l Director of:
- 1) Wind direction
- 2) Wind speed
- 3) Stability class
- 11. UPDATE STATUS BOARD:
a) H 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
- 12. RECORD RECO$ MENDED OFFSITE PROTECTIVE ACTIONS:
a) Obtain from statue board a) Obtain from Station Emergency Manager. b) Record in Item 9 of l 1 AttachmentJ_ l I l
N3.97887210 NUMBER PROCEDURE TITLE REVISION 01 EPIP-2.01 NOTIFICATION OF STATE AND LOCAL GOVERNMENTS PA GE 8 of 16 a'
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 13. RECORD REMARKS:
a) Obtain from status board a) Obtain from Station Emergency Manager. b) E there are any remarks, record them in Item 10 of - Attachment 1
- 14. RECORD YOUR NAME AND TITLE:
a) Record in Item 11 of Attachment i
- 15. OBTAIN APPROVAL TO TRANSMIT MESSAGE: .
a) Show completed Attachment 1 to Station Emergency Manager b) Receive approval to transmit
- 16. TRANSMIT MESSAGE TO STATE AND LOCAL GOVERNMENTS:
a) Use Insta-Phone a) IF NOT operable, use normal station telephone. Call following in order listed:
- 1) Louisa County 3* /
- 2) Spotsv1vania County
,r N_
- 3) State.of Virginia
~
for Duty Offi r
- 4) Caroline County j-
, ,g.*
No.97887210 NUMBER-PROCEDURE TITLE REVISION 01
+
EPIP-2.0 . NOTIFICATION OF STATE AND LOCAL GOVERNMENTS PAGE 9 of 16
')
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 5) Orange County
- 6) Hanover County b) Read Attachment 1 exactly as written
. 17. RECORD TIME MESSAGE SENT:
a) Record on bottom of Attach-ment 1
- 18. RETAIN ATTACHMENT:
a) Retain Attachment 1
- 19. INFORM STATION EMERGENCY MANAGER:
a) Inform Station Emergency Manager that message was sent
- 20. VERIFY RELEASE STATUS:
"a) Item 6_ of Attachment a) IF NOT, CO TO Step g.
1 indicates: - l Release-HAS OCCURRED l 0,,,R Release-HAS OCCURRED 0,, R Release-IS PROJECTED
- 21. INFORM STATE THAT REPORT WILL BE SENT:
(
~'-) a) Use State EOC ring down a) IF NOT operable, use normal phone station telephone
N a'. 978 87210 NUMBER PROCEDURE TITLE REVISION 01 EPIP-2.0: NOTIFICATION OF STATE AND LOCAL GOVERNMENTS PAGE 10 of 16
- STEP ACTION / EXPECTED RESPONSE R5S ONSENOT08TAINE0 s
- 21. a (CONTINUED)
AND Call State EOC at .... AND Ask for Duty Officer. i b) Read following =cssage:
- "This is VEPCO North Anna Control Room (or TSC). We will transmit a report of radiological conditions shortly."
c) GO TO Step 2][
- 22. INFORM STATE THAT 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 AND Ask for Duty Officer.
b) Read following message:
"This is VEPCO North Anna Control Room (or TSC).
Since we have no release of
.s radioactive material, we ,( )
will not transmit a report of radiological conditions." c) GO TO Step 3E[
N3.97887210 NUMBER PROCEDURE TITLE REVISION EPIP-2.01 NOTIFICATION OF STATE AND LOCAL GOVERNMENTS PAGE 11 of 16
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINEO
- 23. OBTAIN RADIOLOGICAL REPORT FORM:
a) Attachment 2, Report of a) IF NOT attached to this pro-Radiological Conditions to cedure, obtain from procedure the State, located at the file, back of this procedure NOTE: The initial report of radiological conditions must be trans-mitted to the state as soon as possible following the declar-ation of an emergency involving release of radioactive mater-ial. Follow-up reports should be sent to the state approximately every 15 minutes or when there are changes in radiological O conditions.
- 24. DETERMINE RELEASE DATA:
a) Obtain from status board a) Obtain from Station Emergency Manager. b) Record in Items 1 thru 4 of Attachment 2_ -
- 25. RECORD METEOROLOGICAL DATA:
o a) Obtain wind direction, wind speed, and stability class from most recent Attachment I completed. b) Record in item ,S_ of Attach-ment _2_
- 26. DETERMINE TEMPERATURE:
a) I_F,in Control Room, obtain a) IF NOT, contact Control Room temperature from Recorder and request data. TR-MM-101A, " Main Tower Temperature"
- - .. , . . .._ ._..c _ - . - - - - _ No. 97867210 NUMBER PROCEDURE TITLE REVISION EPIP-2.01 NOTIFICATION OF STATE AND LOCAL GOVERNMENTS PA GE 12 of 16
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED b) Record temperature in Item 6_ of Attachment 2
- 27. DETERMINE PRECIPITATION:
a) Determine AND record pre-cipitation form in Item 6_ of Attachment 2
- 28. INFORM RADIOLOGICAL ASSESSMENT ..
DIRECTOR: ' a) Inform Radiological Assessment Director of temperature 3 D_ precipitation data q O ' h 29. UPDATE STATUS BOARD: a) IF status board being main- a) IF NOT, CO TO next step. ., tained, insure temperature .. ., and precipitation data s . .
+ 2 .,
updated - s
\ i
- 30. RECORD RADIOLOGICAL DATA:
a) Obtain from status board \ a) IF NOT knovn, rec 6rd as$ , { w Tnknown'.' . s N .s s '. OR , k
~
1., Radiological Asses;sment , 13- . C -' Director i s '\ d l , b) Record in Items 7 through ,' h $s T 14 of Attachment 2
- t I_
- 31. RECORD STATION CONDITIONS: N
\
N' ~ s a) Obtain from status board s a) Obtain from Station Energency
\ Manager., '
b) Include status of following:
- 1) Fuel Failure ' "
$3.97887210 NUMBER ,
PROCEDURE TITLE REVISION 01 EPIP-2.01 NOTIFICATION OF STATE AND LOCAL GOVERNMENTS PAGE 13 of 16
~f.
STEP ACTION / EXPECTED RESPONSE AESPONSE NOTOBTAINEO l
- 2) Containment Leakage '
- 3) RCS Integrity c) Record in Item M of Attachment 2_
- 32. RECORD YOUR NAME AND TITLE:
a) Record in Item M of Attachment 2
- 33. OBTAIN APPROVAL TO TRANSMIT MESSAGE:
a) Show completed' Attachment 2 to Station Emergency Manager b) Receive approval to transmit
- 34. TRANSMIT MESSAGE TO STATE:
a) Use ringdown phone to state a) IF NOT operable, use normal EOC station telephone AND o Call state EOC at AND Ask for Duty Officer. b) Read Attachment 2 exactly as written a
- 35. RECORD TIME MESSAGE SENT:
'l a) Record in Item 16 of ~
Attachment 2_
\
N REVISIO PAGE 16 1 4 of TITLE GO VERNMENTS PROCEDURE LOCAL AND 7887210 ST ATE f40.9 OF TION TAINEO NUMBE R NOTIFICA NO T OB
RESPONSE
r EPIP 2.0 ED
RESPONSE
ACTlON/ EXPECT 2: STEP CHMENT ATTA RETAIN chm ent 2, Atta 36 GENCY a) Retain TION EMER STA e gency s ent 47 Em r INFORM Step ' MANAGER: ion was TO 37 rm Stat mes sage ent, GO that a) Infonager TUS: a) IF s Ma Y STA GENC ation 40 EMER rmin Step VERIFY ion of te SENT TO NOT NOT, GO 38 if icate c gen y-a) Not m r a) IF of e s, } IEF: r rive REL ur relief awing: 39 a) IF yo rm follo n pe rfo relief o ur s of
- 1) Briefreyo nt statu curergency ents em chm st Atta vie w la ompleted
- 2) Re 1a nd 2c this pr oc ta ch-edure sfer ompleted atrelief 31 Tr an ur and all cto yo ments co rd r elief:
b) Re Relie ved By: Time : NOT in em. TSC, relobeing: TSC is a) IFTSC when 41 Step OCATION: N L 'N REL
ISC, GO TO
No. 97887210 NUMBER PROCEDURE TITLE REVISION EPIP-2.0: NOTIFICATION OF STATE AND LOCAL GOVERNMENTS PAGE 14 of 16
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 36. RETAIN ATTACHMENT 2:
a) Retain Attachment 2_
- 37. INFORM STATION EMERGENCY MANAGER:
a) Inform Station Emergency Manager that message was sent
- 38. VERIFY EMERGENCY STATUS:
a) Notification of termination a) I_F_ sent, GO TO Step 47. of emergency - NOT SENT
- 39. RELIEF:
a) I_F,your relief arrives, a) IF NOT, GO TO Step ,40. perform following:
- 1) Brief your relief on
. current status of emergency
- 2) Review last Attachments 1 and 2 completed
- 3) Transfer this procedure
- and all completed attach-ments to your relief b) Record relief
Relieved By: l Time: Date:
- 40. RELOCATION:
l a) I_F _F in TSC, GO TO Step 41 a) IF NOT in TSC, relocate to TSC when TSC is being manned i
1 No. 97887210 NUMBER PROCEDURE TITLE REVISION 01 g EPIP-2.01 NOTIFICATION OF STATE AND LOCAL GOVERNMENTS PAGE 15 of 16
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT08TAINE0 AND Station Emergency Manager directs you to relocate to TSC.
- 41. DETERMINE EOF STATUS:
a) Emergency Operations Faci- a) ))[ EOF manned lity (EOF) - NOT MANNED AND EOF has assumed responsibi- . lity for notification of state and local governments, GO TO Step 42.
- 1) GO TO Step 46,
- 42. ASSUME TSC PHONETALKER DUTIES:
a) Man ringdown phone to EOF b) Maintain Emergency Status Board and Radiological Status Board
- 43. MAINTAIN EOF COMMUNICATIONS:
a) Keep EOF updated on emergency status
- 44. OBTAIN METEOROLOGICAL DATA:
a) Approximately every 15 minutes, request undate of meteorological data from the Control Room phonetalker b) Inform EOF AND Radiolo-
.O
(_,) gical Assessment Director of latest meteorological data
No. 97887210 NUMBER PROCEDURE TITLE REVISION 01
, EPIP-2.01 NOTIFICATION OF STATE AND LOCAL GOVERNMENTS PAGE 16 of 16
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED c) Record on status boards
- 45. VERIFY EMERGENCY STATUS:
a) Emergency - NOT TERMINATED a) Emergency - TERMINATED -
- 1) GO TO Step 43 1) GO TO Step 42
- 46. DETERMINE NEED FOR FOLLOW-UP NOTIFICATION:
a) Status of any information a) IF NOT changed, wait approx-on Attachment 1_ or Attach- imately 15 minutes from time ment 2_ - CHANGED last notification form initi-ated, THEN GO TO Step 2.
- 1) GO TO Step 2
- 47. TERMINATE EPIP-2.01: a a) COMPLETED BY:
TIME: DATE: b) Forward all completed EPIPs and attachments to SNSOC for review i l l [ l i 1
- i. _ _. _ __ _
N3.g7887220 4 NUMBER A TTACHMENT TITLE REVISION EPIP-2.01 01 s) REPORT OF EMERGENCY TO STATE AND LOCAL GOVERNMENTS J PA GE A TTACHfENT 1 of 1 MESSAGE:
"This is VEPCO North Anne OControl Room OTSC D EOF. Stendby for a rollait followed by en emergency message. Use e Report of Emergency form to copy thle message." (Conduct a roll <:sti and check the boxes as each party enewers)
O Loules County 0 Virginie State EOC O Orange County O Scotsylvente County 0 Hanover County O Caroline County "The emergency message is as follows:
" Item 1. Emergency etess: O Notification of Unusual Ewnt O Alert 0 $1te Emergency . 9 Deciered at an / /_."
O General Emergency (24 hr. time) (date) O Emergency terminated (If checked.go to item 10)
" Item 2. Assistence requested: O None.
O (no.) Fire Units from . O (no.) Police Units from . O (no.) Rescue Units from . O (Other) .
" Item 3. Emergency response actione underwey: O None.
O Stetton monitoring teams dispetched offsite. N O Station emergency personnel collas in. O (Other)
" Item 4 Evocuation of onsite personnel: C No.
O Yes. Evocuated to .
"ltem 5. Prognosis of situation: O Improving.
O Worsening. O Steele . O (Other) .
" Item 6. Reisese of radioacttw meterial: C Has NOT occurred and is NOT projected.
O Has occurred and is now terminated. O is presently occurring. O Is projected to occur."
" Item 7. Wind direction is from the : Wind somed is MPH. Stability class is .
" Item R. Armes effected are D None.
O Sectore and gone. .
" Item 9. Resommended offsite proesctive actions: O None.
O Shettering in S e c t o r e and Zeems . O Evocustion of sectere med tosse . O (Other) .
~
" Item 10. Romerks: -
~
"1 tem 11. This is I -
(name) (position)
) Pteene acknowledge receipt of thle messege." (Conduct rolloll and check boxes.)
, V O Louise County O Sootsylvania County 0 Virginie State EOC O Hanowr County O Orange County O Caroline County "This is VEPCO North Anne Ocontrol Room QTSC DEOF out et time . (24 hr. timei
No. 97 e 87220 d NUMBER A TTACHMENT TITLE REV/SION EPIP-2.01 01 REPORT OF RADIOLOGICAL CONDITIONS TO THE STATE A TTACHMENT PAGE 2 1 of 1 "This is VEPCO North Anne O Control Room O TSC D EOF. I have a report of *=dMiegical conditions. Use a Reoort of Radiologimi Conditions form to copy this messege. Pteese inform me when you ero ready to copy. Proceed when Informed.) Item 1. Type of rolesse is O airborne,rolessed at elevation of ft. O waterbome. O surfem spill. Item 2. Release O begon et . Ole estimated to begin et . (24 hr. time) (24 hr. time) . Item 3. Release duration C was bra. O is estimated to be bra. Time between reactor shutdown end time of beginning of rolesse O was hrs. 01: not soplicable, Item 4 item 5. Wind direction is from the . Wind speed is MPH. Stability class is . Item 6. Temperoture is
- F. Precipitation form is O None O Rein O Sleet OSnow 0 (Other) .
Item 7. The lodine / Noble Gas Retio is O . O unknown, item 8. Proiected total roleses equivalent Curies of 1131 is O Curies. O unknown. Item 9. Proiected total refesos equivalent Curies of Xe.133 is O curies. D un known. Item 10. Actual does rete et the site boundary is O mR/hr. Dunknown. mR/hr at site boundary, mR/hr et 2 miles, Dunknown, Item 11. Estimated does retes are O mR/hr et 5 miles,and mR/hr et 10 miles. Item 12. Projected totsi integrated Whole Body done is O mR et, site boundary, mR st 2 miles, O unknown. mR st 5 miles,and mR st 10 miles, Pro}ected total integreted Thyroid dose is O mR et site boundary, mR st 2 miles, b unknown, item 13. mR st 5 miles, and mR st 10 miles. 2 O unknown. Item 14 Actual surface redlooctive contaminetton is O DPM /100cm in Zone . Item 15. h conditions are es follows: (Give brief status and cause of emergency. Use back if needed.) Item 16. This is / out at time . (namel _ (position)
*
- N3. 97887200 VIRGINIA ELECTRIC AND POWER COMPANY
, NORTH ANNA POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE O NUMBER PROCEDURE TITLE REVISION 01 EPIP-2.02 NOTIFICATION OF NRC PAGE (With 2 Attachments) 1 of 8 PURPOSE
- 1. To initially notify the NRC of a declaration of an emergency; AND .
- 2. To provide a supplemental status report to the NRC.
NOT A CONTROLLED USER Emergency Communicator OR Station Emergency Manager. re g g4 Nof<, _ ;g ENTRY CONDITIONS
~~ ~ ' ' '~ ~"
Any one of the following: O 1. Emergency is declared; 0,,,g
- 2. Entry directed by Station Emergency Manager. __
, i VEPCO PROPERTY
, , , , ... 1 m. ;m . r u c "-
- . . . . .. . a 0.1 w. e . '
[$ ' p.' ; t n. :1 fG i
.r mt'd tt .
I <r 3
- 3
,, g.
h h , ... z:- .
\ E' n '
_ . ---~'~' I _ _ _ _ _ - k N (( YAGE(S): Entire Procedure DATE: 07-02-82 REV. 01 PAGE(S): Entire Procedure DATE: 07-22-82 REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: O APPROVAL RE MMENDED APPROVED / OA TE
/*
07-22-82 V
}n CHAIRMANSTA TION NU EAR SAFETY
*{
AND OPERA TING COMMITTEE _. , , . -. -- __ - - - - - l
)
so.97es721o NUMBER PROCEDURE TITLE REVISION 01 EPIP-2.02 NOTIFICATION OF NRC O4 PAGE 2 of 8
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: The initial notification to the NRC must be made as soon as possible and in all cases within I hour.
The supplemental report to the NRC should be sent as soon as the information can be collected. As soon as sufficient personnel are available, a continuous open communication channel should be maintained with the NRC.
- 1. INITIATE PROCEDURE:
a) Initiated By: Time: Date:
- 2. OBTAIN INITIAL REPORT FORM:
a) Attachment 1 Initial Re- .a) IF NOT attached, obtain from port of Emergency to the procedure file. NRC, located at back of l this procedure
- 3. COMPLETE FORM:
a) Complete Items 1 thru 17 on Attachment 1_ b) Obtain information from Control Boards or Station l Emergency Manager, as appropriate
- 4. OBTAIN APPROVAL TO TRANSMIT i
MESSAGE: a) Show completed Attachment 1_ to Station Emergency Manager b) Receive approval to transmit
.. .. a
- fe.97887210
. y NUMBER PROCEDURE TITLE REVISION 01
( EPIP-2.0M NOTIFICATION OF NRC , PAGE 3 of 8
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 5. TRANSMIT MESSAGE TO NRC:
a) Use NRC Emergency Notifi- a) IF NOT operable, use com-cation System ringdown mercial telephone phone AND call NRC Operations Center, Bethesda, Maryland at b) Read message section of Attachment 1, exactly as - - written c) Record time message com-pleted in Item lE[ of Attachment 1,
- 6. RETAIN ATTACHMENT:
a) Retain Attachment 1,
- 7. INFORM STATION EMERGENCY MANAGER:
a) Inform Station Emergency Manager that message was sent
- 8. OBTAIN SUPPLEMENTAL REPORI FORM:
a) Attachment 2,, Supplemen- a) IF NOT attached, obtain from tal Report of Emergency procedure tile. to*NRC, located at back of this procedure
- 9. RECORDEMkRbENCYSTATUS }
INFORMATION: a) Complete Section A,, Items 1 thru 3, of Attachmentj[ b) Obtain information from b) Obtain from Station Emergency status board Manager.
, _ , . __~
No[97867210
, 1
)
NUMBER 9 PROCEDURE TITLE REVISION 01 O FPIP-2.02 NOTIFICATION OF NRC PAGE 4 of 8
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED i
- 10. RECORD ACTION TAKEN OR PLANNED:
a) Complete Section B_, Items , 1,and 2, of Attachment 2 b) Obtain information from b) Obtain for Station Emergency status board Manager.
- 11. CHECK RADI0 ACTIVE RELEASE STATUS:
a) Release - RAS OCCURRED a) IF NOT, GO TO Step g . E Release - IS OCCURRING E Release - IS PROJECTED b) Complete Section C_, Items 1 thru 12, of Attachment 2_ c) Obtain information from c) IF NOT known record as status board Tnknown". E Station Emergency Manager
- 12. CHECK PLANT STATUS:
a) Event involves - PLANT a) IF NOT, GO TO Step 3 1_3_. SYSTEM MALFUNCTION s
.y,:m.ma ,
NUMBER PROCEDURE TITLE REVISION O EPIP-2.02 01 PAGE NOTIFICATION OF NRC 4 5 of 8 1 - STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED I
- 12. (CONTINUED) b) Complete Section D_, Items 1 thru 21 of Attachment
_2 c) Obtain information from c) Obtain information from Con-
- status board trol Boards pR, Station Emergency Manager.
- 13. CHECK FIRE STATUS:
a) Event involves - FIRE a) IF NOT, GO TO Step 14. b) Complete Section E Items 1_ thru 3_, of Attachment i c) Obtain information from c) Obtain information from Fire Marshal. Station Emergency Manager, j 14. CHECK CONTAMINATED INJURED PERSONNEL STATUS:
, a) Event involves - TRANSPORT a) IF NOT, GO TO Step g.
OF CONTAMINATED INJURED PERSONNEL TO OFFSITE HOSPITAL b) Complete Section F_, Item 1_, of Attachment 2
- 15. CHECK SECURITY STA'"US:
- a) Event involves - BOMB THREAT a) IF NOT, GO TO Step 15.c.
i b) Complete Secton G,, Items O 1_, 2.a AND 2.b, of Attachment 2
Nd.97887210 . NUMBER PROCEDURE TITLE REVISION 01 j EPIP-2.02 NOTIFICATION OF NRC PAGE 6 of 8
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 15. (CONTINUED) c) Event involves - ACT OF c) IF NOT, GO T0 Step 15.e.
SABnTAGE d) Ccmplete Section G_, Items 1 AND 3.a thru 3.c, of Attachment 2_ e) Event involves - ACTUAL e) IF NOT, GO TO Step 6. OR ATTEMPTED INTRUSION f) Complete Section G_, Items . 1 AND 4.1 thru 4.e
- 16. CHECK HAZARD TO STATION
, OPERATIONS STATUS:
YJ a) Event involves - HAZARD a) IF NOT, GO TO Step E. TO STATION OPERATIONS b) Complete Section H_, Items 1 AND 2 of Attachment 2
- 17. CHECK NATURAL EVENT STATUS:
a) Event involves - NATURAL a) IF NOT, GO TO Step _18,. EVENT b) Complete Section I, Items 1 AND 2, of Attachment 2
- 18. OBTAIN APPROVAL TO TRANSMIT MESSAGE:
a) Show completed Attachment 2 to Station Emergency Manager b) Receive approval to trans-mit
NA 9788F210 NUMBER ROCEDURE TITI.E REVISION 01 EPIP-2.0? NOTIFICATION OF NRC PAGE 7 of 8
~g, 7 STEP ACTIONMXPECTED RESPONSE RESPONS,ENOTOBTAINED
- 19. TRANSMIT MESSAGE TO NRC:
a) Nse NRC Emergency Notifi- a) IF NOT operable, use com-cation System ringdown mercial telephone phone AND call NRC Operations Center, Bachesda, Maryland at b) Read Attachment j[ exactly as, written c) Record time message com-pleted in Section J, Item 1,, of Attachment j2 -
- 20. RETAIN ATTACHMENT:
a) Reta,in Attachment 2,
- 21. INFORM STATION EMERGENCY MANAGER:
a) Inform Station emergency Manager that message was sent
- 22. MAINTAIN C0KHUNICATIONS TO NRC:
a) Provide information as requested by NRC
- 23. VERIFY EMERGENCY STATUS:
a) Notification of termi- a) Ij[ sent, GO TO Step 24,. nation of emergency - NOT SENT
- 1) C0 TO Step 2][
-n 9
L
- Nd.97887210 a
NUMBER PROCEDURE TITLE REVISION 01 O EPIP-2.02 NOTIFICATION OF NRC PAGE 8 of 8
- STEP ACTION /EXPhCTED RESPONSE RESPONSE NOTOBTAINED
- 24. CLOSE DOWN COMMUNICATIONS WITH NRC:
a) Request permission from NRC to close down communication channel with them b) When permission is granted, a) IF NOT granted, remain on secure telephone line until permission is granted, THEN GO TO Step 25.
- 25. TERMINATE EPIP-2.02:
a) Completed By: Time: Date: b) Forward all completed EPIPs and attachments to SNSOC for review. 1 I l ( l l END l - . _ A
-l i
. . i
*l I rp.97887220
~
REVISION NUMBER A TTACHMENT TITLE EPIP - 2.02 01 INITIAL REPORT OF A TTACHMENT ' PAGE EMERGENCT TO TBE NRC 1 , l of 2 l l e This is North Anne Power Station. In accordance with the requiremente of 10 CFR 50.72.1 have en initisi report of en emergency event to tronomit. Pfesse inform me when you are ready to copy. (Proceed when informed.) ,
- 1. The time is . The date is / / . The facility is North Anne Power Station. *I
- 2. My name is .
O Unusual Event C Alert
- 3. The event is cleosified at on /
(astep
/ .
O Site Emergency (24 nr. times Q General Emergency 4 Event description is (check all applicable): O Radiological release event O Conteminated, injured personnel O Natural event O Plant system malfunction O Security incident O (Other) s O Fire Q Hazard to station operation
- 5. Cause of the event was (brief description)
- 6. Unit 1 power level prior to the event was
- Unit 2 power level prior to the event wee 1
- 7. Unit 1 power levet now le %; Unit 2 power level now is %
0 hee NOT C has NOT
- 8. Unit 1 Safety injection occurred; Unit 2 Safety injection occurred, f Q has O hos V
O forced Q forced
- 9. Unit 1 cooling mode is circulation; Unit 2 cooling mode is circulation.
O natures O natural
o
,No.97007123 I
NUMBER A TTACHMENT TITLE REVISION EPIP - 2*02 01 ' INITIAL REPORT OF l A TTACHMENT EMERGENCY TO TBE NRC PAGE 1 2 of 2 O do NOT
~
- 10. We heve incromoed contamination as a result of the event.
Q do - C O do NOT
- 11. We have a relenos of radionedve meterial.
O do D is NOT Q is NOT
- 12. Unit 1 Containtnent isoleted; Unit 2 Containment isolated.
O is O is
- 13. Other problems are (brief description) 14 Unuausi or not understood conditions are (brief description) 1
- 15. We have taken the following actions (check all applicable) 0 Activated company emergency personnet and facilities O Requested offsite law enforcement essestance l
O Diepetched station monitoring teams offelte O None . O Evocuated noneesentiel site personnel O (Other) O Requested offsite Fire Dept. assistence O Requested offsite Rescue Squad seeistena
- 18. We plan to take the following actions (Check all applicable)
C Activate company emergency personnel and facilities O Request offsite law enforcement assistance O Dispatch station monitoring teams offsite O None O Evocueto noneesential site personnel O (Otherl O Request offsite Fire Dept.assistence l l C Request offhte Rescue Squed assistence l i O have l 17. We have notified the State of Virginie and locet governments. We notified the NRC Resident inspector.
) O have NOT v 18. We will transmit a supplemental report shortty. This is North Anne Power Stetton out at time .
(24 hr. time) l l [ -. _
~
_ _ _ a
^ *
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- No. 97887220 NUMBER ~ A TTACHMENT TITLE REVISION 01 EPIP - 2.02 SUPPLEMENTAL REPORT OF A TTACHMENT MGE EMERGENCY TO NRC 2 1 of 5 This is North Anne Power Station. I hows e supplemental report on our emergency event to tronomit. Please Inform me when you are ready to copy. (Proceed when informed.) ,
A. EMERGENCY STATUS .
- 1. The facility is North Anna Power Station. My name le . The time is .
(24 hr. time) O Unusual Event , O Alert
- 2. The event cleosification is O Site Emergency cleosified at time on / / .
(24 hr. time) (dete) O Em O Emergency terminated
- 3. Event description is (checic ell soplienbee)
O Radiological reisees event (if checked, complete Sections 8, C, and J below.) O Pfent system malfunction (if checked, complete Sections 8, D, and J belowJ O Fire (if checked, complete Sections 8, E, and J below.) 7 O Contaminated, injured personnel (If checked, complete Sections 8. F, and J belowJ O Security incident (If checked, complete Sections 8. G, and J below.) O Henard to stodon operation (if checked, complete Sectione 8. H, and J below.) O Netural event ( If checked, complete Sectione 8, I, end J below.) 0 (Other: if checked, briefly describe here and complete Sectione 8 and J be6ow.) i ( B. ACTIONS TAKEN OR Pt.ANNED 1 We have teken the following actions (check eil spoilesbie) O Notified State and faced gowsmmento O Requessed offsite Rescue Squad estistonos O Notified the NRC Residow Inspector O Requested offsite low enforcement assistence O Activated company emergency personnel and facilities O None C Dispeeched station monitoring teams offsite Q (Other) O Evecuoted noneesentiel site personnet O Requested offsite Fire Dept.easistence
- 2. We plan to take the following actions (check oli applicable)
C Notify the NRC Resident inspector O Request offsite low enforcement osaistonos O Activate company emergency personnel end facilities O None O Dispatch station monitoring teams offsite O (Other) e O Evocuote noneesential site personnel C Raquest offsite Fire Dept.essestance v O Request offsite Rescue Squad seeistence l
.. ~_.
G
_ - ____T - _- ' un C
'No.47487223 NUMBER ATTACHMENT TITLE REV/S/0N EPIP - 2.02 01 SUPPLEMENTAL REPORT OF ATTACHMENT EMERGENCT TO NRC PAGE 2 2 of 5 C. RADIOLOGICAL RELEASE STATUS (complete if appelcobiel O has occurred.
~
1 Reisese of redlomettwo meterlate O is presently occurring.
. O le projected to occur.
O liquid.
- 2. The reisees is The rolesse source is . The rolesse point eiewtion is _ ft.
O gaseous. (desertbol O monitored. O was hrs. O NOT monitored. O is sedmetod to be hrs. O microCuries/sec. O Curies. 4 The release rate is The reisees amount is O unknown. O unknown. O NOT present !n the station.
- 5. Eleveted redletion levels are
( i[ O present in the station, with mR/hr in the . t (location) 6 N. O NOT ewecuated any station areas.
- 6. We have Q owecuated from tne .
(location)
- 7. The meteorological conditione are es follows:
- e. Wind direction from the d. Stability ciens is ,
- b. Wind speed is MPH. e. Prodpitation form O none Q rein O sieet Q snow
- c. Temperature is
- F. O(Other)
=
i l 0 mR/hr et 2 mi mR/hr et 5 mi.,and mR/hr et to mi. i
- 8. Estimated present offsite dose retos are ,
l 0 unknown. l n mR/hr et 2 mi-_- mR/hr et 5 ml end mR/hr et 10 mi.
- 9. Projected Jntsysted Whole Body doess em O unknown.
O 2 DFM /100 cm . 10 in pient surface conteminetton is O unknown. O .DFM /100 cm2, O unknown.
,z _to s.cf s .o__ ,s o >-< '-
c% 0 Unknown. l l
=
i
. - . . - - 7 o
* ,No.97847220 NUMBER A TTAC#MENTTITLE EV/S/0N
'd EPIP-2.02 SUPPLEMENTAL REPORT OF A TTAC##ENT M##
EMERGENCY TO NRC 2 3 of 5 O. Pt. ANT STATUS (complete if appelable)
- 1. Unit 1 reactor power fevelis %; Unit 2 reactor power towel is %. .
- 2. Unit 1 Renefor Cooient System preneure is peig; Unit 2 Reactor Cooient System pressure is peig. .
- 3. Unit 17 g is
- F: Unit 2 T is
- F.
O forced circulation with Reector Cooient Pumps running. 4 Unit 1 cooling mode is (no.) O natural circulatloa. O forood circulation with Reactor Cooient Pumps running.
- 5. Unit 2 cooling mode is (no.)
l O naturel circulation. O NOTisoleted. O NOTisolated.
- 6. Unit 1 Containment is Unit 2 Containment is Q lootsted. O lootsted.
l C NOT operating. O NOToperating. , 7 Unit 1 containment sprey systems are Unit 2 containment sprey systems are C operating. O operating, s, l
- F.
- 8. Unit 1 containtnent radiation fewel is mR/hr; pressure is pois; temperature is
- 9. Unit 2 containment radiation level != mR/hr; pressure is pele; temperature is
- F.
O NOTIr.aerted. O NOTinserted.
- 10. Unit 1 control rods are Unit 2 control rods are O NOToperating. O NOT operating.
- 11. Unit 1 Safety iniection System is Unit 2 Safety injection System is O operating. O operating. ,
- 12. Unit 1 S/G towels are % on "A" S/G % on "B" S/G; and % on "C" S/G*
- 13. Unit 2 S/G levels are % on "A" S/G; % on"B" S/G and % on "C" S/G.
O NOTisoleted. O NOTisolated.
-14 Unit 1 S/G's are Unit 2 S/G's are
- 15. Unit 1 feedwater source le . Unit 2 feedwater source is .
O eweitable.
- 16. Normel offsite electrical power is O NOT eweilable.
- 17. Unit 1 safeguards (emergency) bus power supply is for 1H bus and for 1J bus.
L 18. Unit 2 safeguards (emergency) bus power supply is for 2H bus and for 2J bus.
- 19. Diesel generators 01H O 1J O 2H O 2J ere running. Diesel generators 01H O 1J O 2H Q 2J ere loaded.
.- .- ._. - . . _ _ . - . - . - . . - . .._ . -. . . _ .- _ - _ _ _ _ _ _ _N
_ _ _. . -.r e
^
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- No.97847223 1
i " ~ m gyggER - A fACHMENT TITLE REVISION
~
EPIP-2.02 01 SUPPLEMENTAL REPORT A TTACHMENT OF EMERGENCY TO NRC PAGE 2 4 of 5 . 21L. Maior equipment feitures are (briefly describe)
- 21. Mejor busses or Iceds lost are (briefly describel _
E. FIRE STATUS (cornplete if applicable)
- 1. The fire is located at
- 2. The fire is O out O contained O worsening.
O NOT threstoning safety reisted equiprnent. O threatening the following safety reisted equipment: F. CONTAMIN ATED. INJURED PERSONNEL STATUS (complete if appilable) 1 We have transported contaminated, Injured individuele to en offsite hospital. (no.) G. SECURITY INCIDENT STATUS (complete if applicabiel O e bomb threat. (If checked, complete item G.2 boiow)
- 1. The security incident involves O sabotage. (If checked, complete item G.3 below.)
O en intrusion ettempt. (if checked, complete item G.4 below.)
- 2. (Complete for bomb threat incident.)
- e. A search for the bomb was O NOTconducted.
b.
~
The site was O evacuated.
- 3. (Complete for sabotage incident.)
O O did NOT C did NOT (. a. The sabotage g involve radioactive meterial and result in a rolesse. Odid NOT b; The sabotage involve erson or explosives,
- c. The sabotage consisted of
l
. . l
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' No.97887220 REVISION p NUMBER A TTACHMENT' TITLE EPIP - 2.02 SUPPLDENTAL REPORT OF A TTACHMENT EtGRGENCT TO NRC PAGE 2 5 of 5 4 (Complete for intrusion incident.)
O NOT successful.
- a. The intrusion ettempt was O successfvi. -
- b. The intrusion is estimated to have involved " Insiders" and " outsiders".
(no.) (no.)
- c. The furthest point of intrusion ms .
O were NOT CheeNOT
- d. Firearms involved. Control of the station been compromised.
g e O has NOT
- e. Radioactive meterial been rolessed or stolen.
$ H. HAZARD TO STATION OPERATION STATUS (complete if applicable)
O eircraft activity or crash. O trein derailment.
- 1. The heaerd involves O explosion.
O toxic or flammable gas reisess. O miselle impact domego, l
- 2. A brief description of the heterd is C
- 1. N ATUR AL EVENT STATUS (complete if appilcobiel O sorthquake.
O tornado.
- 1. The natural event is a(n) O high sustained wind.
O flood. O low water.
- 2. A brief description of the event is s
J. SIGNOFF i 1 This is the end of this report. This is North Anne Power Stetton out at time (24 hr. timel
'\,
c
- = ~ = ~ - - - - - - - - - - - -
,N3.97887230
. VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION EMERGI JCY PLAN IMPLEMENTING PROCEDURE V NUMBER PROCEDURE TITLE REVISION 01 EPIP-2.03 REPORTS TO OFFSITE AGENCIES PAGE o
(With No Attachments) 1 of 9 PURPOSE
- 1. To ensure that reports to various agencies, which may be required because of the nature of the emergency, are made in a timely manner.
USER Emergency Administrative Director g Station Emergency Manager. ENTRY CONDITIONS NOT A CONTHOLLW Any one of the following: One>"cyr
- 1. An emergency has be declared; EUl 2 4 Jgg
' No.N , LATes agyjgidp]
- 2. Entry is directed by another EPIP.
, VEPCO PROPERTY This doeurcent is the property of thn l Virginia Electric and Power Compa @ and to to be returned upon request-lio pemicaion is granted to pub 11M n .er sny 1 mation cont 91ned *1 l this document. _
~~~
REVISION RECORD REV. 00 PAGE(S): Entire Procedure DATE: 07-02-82 REV. 01 PAGE(S): Entire Procedure DATE: 07-22-82 i REV. PAGE(S): DATE: 1 REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: p/
\_
APPROV RECO ENDED APPROVED DA TE 07-22 -82
/ hv 't^-
i
. CHAIRMANSTATIONNUCLEA SAFETY
^
\
AND GPERA TING COMMITTEE ,
N3.97887210 NUMBER PROCEDURE TITLE REVISION
/7 01 Q EPIP-2.03 REPORTS TO OFFSITE AGENCIES PAGE 2 of 9
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 1. INITIATE PROCEDURE:
a) Initiated By: Time: Date:
- 2. CHECK RADIOLOGICAL STATUS:
a) Release of radioactive a) IF release of radioactive meterials OR abnormal ~ materials OR abnormal radiation exposures - radiation exposures NOT INVOLVED OR THREATENED involved OR threatened, GO TO Step 16,. b d NOTE: The immediate and 24 hour notifications to NRC Region II required below are based on the requirements of 10 CFR 20.402, Reports of Theft or Loss of Licensed Material, and 10 CFR 20.403, Notification of Incidents. These notifications are required to be made in addition to any reports made to the NRC Operations Center or the NRC Resident Inspector.
- 3. CHECK RELEASE STATUS:
a) Release of radioactive a) If release of radioactive materials - HAS OCCURRED materials has NOT occurred OR IS PROJECTED OR been projected, GO TO Step 7_.
- 4. CHECK CONCENTRATION OF RELEASE:
a) Actual OR, projected re- a) IF actual OR projected re-p lease concentration lease concentration (j averaged over 24 hours - averaged over 24 hours NOT GREATER THAN MPC FOR greater than MPC for unre-UNRESTRICTED AREA stricted area, GO TO Step 7,. c
. No.97887219 NUMBER PROCEDURE TITLE REVISION
. 01 PAGE EPIP-2.03 REPORTS TO OFFSITE AGENCIES 3 of 9 '
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: The telephone number for NRC Director, Region II is The address of Region II is:
Nuclear Regulatory Commission, Region II Office of the Executive Director for Operations 101 Marietta Street, Suite 3100 , Atlanta, Georgia 30303
- 5. DETERMINE IMMEDIATE NOTIFI-CATION REQUIREMENT:
a) Concentration of release a) ))[ concentration averaged averaged over 24 hours - over 24 hours NOT g'reater I GREATER THAN 5010 TIMES MPC than 5010 MPC for unre-FOR UNRESTRICTED AREA stricted area, GO TO Step 6,. b) Immediately notify NRC Director, Region II by telephone AND telegraph, mailgram, Olt facsimile
- 6. DETERMINE 24 HOUR NOTIFI-CATON REQUIREMENT:
a) Concentration of release a) Jg[ concentration averaged averaged over 24 hours - over 24 hours NOT greater GREATER THAN 501 TIMES MPC than 501 times MPC for unre-FOR UNRESTRICTED AREA stricted area, GO TO Step 7,. b) Notify NRC Director, Region II~by telephone AND telegraph, , mailgram, OR facsimile . within 24 hours I
- 7. CHECK OVEREXPOSURE STATUS:
a) Overexposures above 10 a) IJ; overexposures above 10 CFR CFR 20 limits - HAVE 20 limits have NOT occurred OCCURED OR ARE LIKELY OR been projected, GO TO Step TO OCCUR 10.
- w. , ,. ..-wwr.,.,,. n w .m n n n , .m - s No:97447210 NUMBER PROCEDURE TITLE- -
REVISION 01 PAGE EPIP-2.0: REPORTS TO OFFSITE AGENCIES 4 of 9 f
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 8. DETERMINE IMMEDIATE NOTIFI-CATION REQUIREMENT:
a) Actual OR_ likely over- a) IF actual OR likely over-exposures - GREATER THAN exposures NOT greater than 25 25 REM WHOLE BODY Rem Whole Body, OR 150 Rem Skin OR 375 Extremities, OR GO TO Step 9. 150 REM SKIN pR 375 EXTREMITIES O b) Immediately notify NRC Director, Region II by telephone AND telegraph, mailgram, O_R, facsimile .
- 9. DETERMINE 24 HOUR NOTIFI-CATION REQUIREMENT:
a) Actual OR likely over- a) IF actual OR likely over-exposures - GREATER THAN exposuras NOT greater than 5 REM WHOLE BODY 5 Rem Whole Body M 30 Rem Skin OR 75' Rem Extremities, OR GO T07tep 10. 30 REM SKIN pR 75 REM EXTREMITIES b) Notify NRC Director, Region II by telephone AND telegraph, ! mailgram, OR facsimile within 24 hours I
- 10. CHECK PROPERTY DAMAGE STATUS:
a) Property - DAMAGED a) IF property NOT damaged, g g Step 3 1_3,. t
,Ns.97887210 NUMBER PROCEDURE TITLE REVISION EPIP-2.03 REPORTS TO OFFSITE AGENCIES PAGE 5 of 9
- STEP ACTION /EXFECTED RESPONSE RESPONSE NOTOBTAINED
- 11. DETERMINE IMMEDIATE NOTIFI-CATION REQUIREMENT:
a) Property damage - a) E property damage does NOT EXCEEDS $201,010 exceed $201,010, GO TO Step L2 - b) Immediately notify NRC Director, Region II by telephone AND telegraph, mailgram, OR facsimile
- 12. DETERMINE 24 HOUR NOTIFI- .
CATION REQUIREMENT: a) Property damage - a) E property damage does NOT O EXCEEDS $2,010 exceed $2,010, GO TO Step M. b) Notify NRC Director, Region II by telephone AND telegraph, ma11 gram OR facsimile within 24 hours
- 13. CHECK STATION OPERATION STATUS:
a) Operation of one E both a) E operation of one O_R both units - LOST units NOT lost, CO TO Step H-
- 14. DETERMINE IMMEDIATE NOTIFI-CATION REQUIREMENT:
a) Operation of one OR both a) E operation of one OR both units - LOST FOR GREATER units NOT for greater than THAN ONE WORKING WEEK one working week, GO TO Step H-b) Immediately notify NRC Director, Region II by telephone AND telegraph, O mailgram, OR facsimile
. . _1
, _ _ - ~ ~ _ . - -
__ -~. _ . _ __
. , . 1 N 3.,978 87210 NUMBER PROCEDURE TITLE REVISION EPIP-2.0 1 REPORTS TO OFFSITE AGENCIES PAGE 6 of 9
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 15. DETERMINE 24 HOUR NOTIFI-CATION REQUIREMENT:
a) Operation of one OR both a) IF Operation of one g both units - LOST FOR ONE DAY units NOT lost from one day OR MORE OR more, GO TO Step M. b) Notify NRC Director Region II by telephone AND telegraph, mailgram, OR facsimile within 24 hours
- 16. CHECK LOSS OR THEFT OF LI-CENSED MATERIAL:
a) Licensed material - LOST O F licensed material NOT lost a) I_F OR STOLEN OR stolen, GO TO Step H.
- 17. DETERMINE IMMEDIATE NOTIFI-CATION REQUIREMENT:
a) Lost OR stolen material - a) IF lost OR stolen licensed PRESENTS SUBSTANTIAL material does NOT present HAZARD TO PERSONS IN UNRE- substantial hazard to per-STRICTED AREAS sons in unrestricted areas, GO TO Step H. b) Immediately notify NRC Director Region II by l telephone AND telegraph, ' mailgram, OR facsimile
- 18. DETERMINE TECH. SPEC. PROMPT i NOTIFICATION REQUIREMENT: t i
! t 4 ' a) any event listed in Speci ' ,a) IF erent das NOT occurred, fication 6.9.1.8 of Tech, GO TO Scep @ . Specs. - HAS OCCURRL'D , i ,' b) Notify NRC Director Region
- A II by telephone AND telegraph, N
! mailgram, OR facsimile , f , . within 24 hours . 2
^
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t I
No. 97847210 NUMBER PROCEDURE TITLE REVISION . O t -- O EPIP-2.03 REPORTS TO OFFSITE AGENCIES PAGE 7 of 9
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAl?tEO NOTE: 10 CFR 20.402, 10 CFR 20.403, and the Technical Specifications require written followup reports to be submitted. Measures should be taken to ensure these reports are prepared and submitted.
- 19. NOTIFY ANI:
a) Within 8 hours, notify the American Nuclear Insurers of the emergency b) Use the telephone number listed in Section 1 of the North Anna Power Station Telephone Directory
- 20. NOTIFY VEPCO INSURANCE DEPT.:
a) Use telephone number listed in Section 1 of North Anna Power Station
- Telephone Directory b) Inform them that ANI has been notified
- 21. VERIFY EMERGENCY STATUS:
i a) Emergency - NOT TER- a) Jg[ emergency terminated, MINATED GO TO Step 23,.
- 22. MONITOR NOTIFICATION EVENTS:
a) ))[ release of radioactive a) IF NOT, continue to monitor materials - OCCURS until emergency terminated, THEN GO TO Step 23. M Release of radioactive materials - INCREASES S L
No.97887210 NUMBER PROCEDURE TITLE REVISION l EPIP-2.03 REPORTS TO OFFSITE AGENCIES PAGE 8 of 9 t
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED i
- 22. (CONTINUED)
Release of radioactive materials - IS PROJECTED H Overexposures - OCCUR S Overexposures - ARE LIKELY S O Loss or theft of licensed material - OCCURS E Event listed in Specifi-cation 6.9.1.8 of Tech. Specs. - OCCURS GO TO Step 2_
- 23. NOTIFY ANI 0F TEliMINATION:
a) Notify American Nuclear Insurers of emergency termination b) Use telephone number l listed in Section 1 of the North Anna Power Station Telephone Directory l l i lO
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l
e- _ - _ . - _ _ -m - . . _ _ . . . - - - - _ _ _ , , - . Pf o. 97887210 NUMBER PROCE00RE TITLE REVISION EPIP-2.03 REPORTS TO OFFSITE AGENCIES PAGE 9 of 9
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 24. TERMINATE EPIP-2.03:
a) Completed By: Time: Date: b) Forward procedure to SNSOC for review. O O -
'L_ ._ _.,.n:c. :'~~ a'.~~ .m~'- " ~ M ~'c-hr
;m -J.-- - ' - - - -
a r - ~ -- ~ Mo.97887200 VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCEDURE TITLE REVISION 01 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.
NOT A CONTROLLLD , Dnr o ryr
!!Il 9 41049 I USER NO Security Team Leader ES1 HEVISION ENTRY CONDITIONS
- 1. Initiation directed by the Station Emergency Manager.
VEPCO PROPERTY This docu :ent is the property of t!..- Vircinia Eir.itric and Power Compan:. and is to be returned upon requesi t;o per:1calon is granted to puu t it I reproduce, t: 4 T: ut or din 1onc . l anoQer any iniormation 70ntal'i.:t: . this docu:aent. , iL J i REVISION RECORD REV. 00 PAGE(S): Entire Procedure DATE: 07-02-82 REV. 01 PAGE(S): Entire Procedure DATE: 07-22-82 REV._ PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: l hO REV. PAGE(S): DATE:
, p APPRO, APPROVED DA TE RfCO, MENDE
, , , 07- 22-82
] , f W CHAIRMANSTA TION UCLEAR SAFETY 0 AND OPERA TING COMMITTEE .
.A 6 No. 97887210 NUMBER PROCEDURE TITLE REVISION O EPIP-3.0. CALLOUT OF EMERGENCY RESPONSE PERSONNEL 01 PAGE 2 of 3 (WITH NO ATTACHMENTS)
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 1. INITIATE PROCEDURE:
a) Initiated By: Time: - Date:
- 2. OBTAIN EMERGENCY PERSONNEL NOTIFICATION LIST:
j 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 i make notifications as rapidly as l 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
[ Health Physics Department l l Operations Department i ~~ ( ,/ Technical Services Dept. l l i ___a
.--a Ns.97887210 NUMBER PROCEDURE TITLE REVISION EPIP-3.0 ;
CALLOUT OF EMERGENCY RESPONSE PERSONNEL PA GE (WITH NO ATTACHMENTS) 3 of 3
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 3. (CONTINUED)
Maintenance Department I Security Department Administrative Services Dept. Training Department Quality Control Department NRC Resident Inspector d) Read messages exactly as T 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 i
- 5. INFORM STATION EMERGENCY MANAGER:
a) Inform Station Emergency Manager that'callout completed
- 6. TERMINATE EPIP-3.01:
a) Completed By: Time: Date: b) Forward EPIP-3.01 to SNSOC for p review
^
END
fo.97887200 VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWEP STATION EMERGENCY PLAN IMPLEMEI flNG PROCEDURE NUMBER PROCEDURE TITLE REVISION 01 EPIP-3.02 ACTIVATION OF TECHNICAL SUPPORT CENTER PAGE (With 9 Attachments) 1 of 6 PURPOSE
- 1. To provide guidance to personnel charged with TSC Activation; AND NOT A CONTROLLED
- 2. To provide guidance to TSC members. DT ' #NT JUL 2 41982
~
USER LATESl REVISION Station Emergency Manager AND TSC personnel ENTRY CON 0lTIONS O 1. Declaration of Alert, Site Emergency or General Emergency; AND .y 8
- 2. Entry from another EPIP; 17 E P C O P R O P E R T' OR Thia duurvnt 1:> the Preieri/ Cf I'#1
..ntric and Po.er Compa:
....,~1r.ia
- 3. Direction of Station Emergency Manager. d iu to ce returned upon re. :er
;,n per :ic 41cn ir granted to ;;, a .h ,
mr it ne Gli 03C '
,.g .g,.3 3 e e ,
in u r ny i m 310' " "' this doct. 1 M.
# N.' 88 PAGE(S): Entire Procedure DATE: 07-02-82 REV. 01 PAGE(S): Entire Procedure DATE: 07-22-82 REV. PAGE(S): DATE:
REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: Y APPRO L OMMENDED APPROVED ' DA TE
, s y v
, , 07-22 -82
{ ___ CHAIRMANSTA TION NUdLEAR SAFETY
~- AND GPERA TING COMMITTEE
Ns,97887210 NUMBER PROCEDURE TITLE REVISION 01 O.r EPIP-3,0: ACTIVATION OF TECHNICAL SUPPORT CENTER PAGE 2 of 6 (WITH 9 ATTACHMENTS)
~
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED NOTE: During normal hours of business, activation of the TSC is the responsibility of the Emergency Administrative Director or his alternate. 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-ment 1 as they arrive b) Maintain accountability c) Notify Station Security of personnel in TSC NOTE: To switch 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
- 2) Carrier LED-RED O
~ No. 97887210 NUMBER PROCEDURE TITLE REVISION
.P-3.01 ACTIVATION OF TECHNICAL SUPPORT CENTER PAGE 3 of 6 (WITH 9 ATTACHMENTS)
- STEP ACTION / EXPECTED RESPONSE RESPONSE N9TOBTAINED
- 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)
- 2) HOLD [BRK)
SIMULTANEOUSLY PUSH [1] O 3> ver1f7 - seri E 1E NOT. eertorm fo11ow1nE a) [ ESC] b) [9]
- w
de.siss7to 1 NUMBER PROCEDURE TITLE REVISION O 01 V EPIP-3.01 ACTIVATION OF TECHNICAL SUPPORT CENTER PAGE 4 of 6 (WITH 9 ATTACHMENTS)
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 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 phones in closet outside Emergency Opera-tions Director's Office b) Connect to jacks on either side of Plant Status Board -
- 5. COMMUNICATION:
a) IJ[ desired, and personnel a) IF NOT, GO TO Step 5.b available, establish com-munication to Control Room via TSC-Control Rm. ringdown phone l b) IJ[ desired, and personnel b) IF NOT, GO TO Step 6; available, establish communications to OSC via PBX phone
- 6. CHECKLISTS:
p) q, a) As each Emergency Manager / Director OR alternate arrives in TSC distribute l appropriate attachment [ l i
rio.97887210 NUMBER PROCEDURE TITLE REVISION ( EPIP-3.01 ACTIVATION OF TECHNICAL SUPPORT CENTER PAGE 5 of 6 (WITH 9 ATTACHMENTS)
- STEP ACTION l EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 6. (CONTINUED)
- 1) Station Emergency Manager Gui'deline, Attachment 2,
- 2) Emergency Operations Director Guideline, Attachment 3,
- 3) Emergency Technical Director Guideline, Attachment 4,
- 4) Emergency Administrative 0- Director Guideline, Attachment 5,
- 5) Emergency Maintenance Director Guideline, Attachment 6
- 6) Radiological Assessment Director Guideline, Attachment 7
- 7) Emergency Communicator ,
Guideline, Attachment 8
- 8) Emergency Procedures Coordinator Guideline, Attachment 9
( 7. VERIFY ACTIVATION: l l a) Required TSC personnel a) IF, required, call out addi-in place tion personnel. GO TO Step 6,,, p 8. TERMINATION Y-, a) TSC deactivated by Station a) DO NOT terminate until l Emergency Manager deactivation complete. 1
Plo. 97887210 NUMBER PROCEDURE TITLE REVISION \ EPIP-3.0 ! ACTIVATION OF TECHNICAL SUPPORT CENTER PAGE 6 of 6 OJITH 9 ATTACHMENTS) STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 8. (CONTINUED) b) Close-out
- 1) COMPLETED BY:
DATE: a TIME: c) Verify Completion of all , Attachments d) Forward EPIP-3.02 and all nine (9) attachments to SNSOC for review 9 O END A
, .N3.97887220 l
l NUMBER A TTACHMENT TITLE REVISION revo_t n- ni A TTAC# MENT TECHNICAL SUPPORT CENTER MANNING PAGE 1 1 of 7 ( - I NOTE: Log personnel as they arrive and leave for accountability purposes. EMERGENCY POSITION PRINCIPLE ALTERNATE Statica 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 O
I po.orseisso l NUMBER A TTACHMENT TITLE REVISION O vpTp 1 n A TTAC# MENT TECHNICAL SUPPORT CENTER MANNING PAGE 01 1 2 of 2 Miscellaneous Personnel ( - O I a O l
- - . - _ ~ . - _..- . - - . ..~ . - .- . .. ___ -_ _ _
, us. ores 722o NUMBER A TTACHMENT TITLE REVISION EPTP-1.0 > of A TTAC# MENT STATION EMERGENCY MANAGER GUI'DELINE PAGE 2 1 of 5 STEP
- ACTION / EXPECTED RESPONSE
- RESPONSE NOT OBTAINED NOTE: This Attachment may be implec:ented by an alternate individual if '
Station Emergency Manager position is NOT located in TSC.
- 1. INITIATE EPIP-3.02, ATTACHMENT 2:
a) BY: DATE: TIME: O 2. EMERGENCY ORGANIZATION: a) Verify response personnel present or enroute:
- 1) Emergency Operations Director
- 2) Emergency Maintenance Director
- 3) Emergency Technical Director
- 4) Emergency Administrative Director *
.5) Radiological Assessement Director
- 6) Emergency Procedures Director
- 7) Emergency Communicator
- 8) OSC Director (at OSC)
'N3.97887220 NUMBER A TTACHMENT TITLE REVISION g FPTP-1.0 '
A1 A TTAC# MENT STATION EMERGENCY MANAGER GUIDELINE PAGE 2 2 of 5 STEP
- ACTION / EXPECTED RESPONSE
- RESPONSE NOT OBTAINED NOTE: Certain 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 emergency
- 2) Notification ci offsite agencies.
- 3) Recommendation of offsite protective measures
- 4) Discontinuance of onsite activities
- 5) Initiation of site evacuation
- 6) Restriction of site access
- 7) Authorization of emergency exposure limits
- 8) Contact of VEPCO management
- 4. OSC:
a) Verify resources with OSC Director
- 1) Fire Brigade
- 2) First Aid Team
. _ . . - - -- g n n u . , - - - . . - , .
N3.97887220 NUMBER A TTACHMENT TITLE REVISION vpip_1.n ni A TTAC# MENT STATION EMERGENCY MANAGER GUIDELINE PAGE 2 3 of 5 STEP
- ACTION / EXPECTED RESPONSE
- RESPONSE NOT OBTAINED
- 4. (CONTINUEb)
- 3) Damage Control Team ,
- 4) Search and Rescue Team
- 5) Standby Operations personnel
- 5. COMMUNICATION:
a) Assure timely notifi-cation of offsite authorities O 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 l , Procedure l
b) Assure development of and l approve additional temporary procedures as required l 7. RELIEF: 1 a) Assure suitable arrangements for timely relief of emergency response personnel through O Emergency Directors l l l I
ryg , ,, n, No.97887223 j i l NUMBER A TTACHMENT TITLE REVISION rpip-1 no of A TTAC# MENT STATION EMERGENCY MANAGER GUIDELINE PAGE 2 4 of 5 STEP
- ACTION / EXPECTED RESPONSE
- RESPONSE NOT OBTAINED
- 7. 7. (CONTINUED)
- 1) Emergency Operations Director
- Operations personnel
- OSC Director
- 2) Emergency Technical Director
- Technical Support Team
- Chemistry Team
- Inst. Technician members
/ of Damage Control Team
- STAS
- 3) Emergency Maintenance Director
- Maintenance Support Team
- Mechanical and Electrical members of Damage Control Team
- 4) Daergency Administrative Director
- Emergency Procedures-Coordinator
- Emergency Communicator
- Administrative Support Team
- Fire Brigade
- First Aid Teau
- Security Team
- Search and Rescue Team ,
- 5) Radiological Assessment
N Director
- Radiation Protection Supervisor
.t
No.97887220 NUMBER A TTACHMENT TITLE REVISION O TDTD_1 A TTAC# MENT n'> STATION EMERGENCY MANAGER CUIDELINE PAGE
? 5 of 5 STEP
- ACTION / EXPECTED RESPONSE
- RESPONSE NOT OBTAINED
- 7. (CONTINUED)
- 5) (CONTINUED)
- 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 l co EPIP-3.02 i o - END
- -- _ . . _ - _ - - .w.-- .
_ _ . - - ~
'Ns,91887220 NUMBER A TTACHMENT TITLE REVISION vpTp 1 n- ni A TTAC# MENT EMERGENCY OPERATIONS DIRECTOR GUIDELINE PAGE 3 1 nf 1 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 Trainee from OSC to act as Coordinator from Admin-TSC-Control Room phonetalker istrative Support Team b) Have phonetalker establish b) ))[ NOT operable use any O communications with Control Room using TSC-Control Room other system operable ring down telephone c) Have phonetalker maintain Plant Status Board d) Update Station Emergency Manager in a timely manner
- 3. OPERATIONAL STATUS:
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 1
No.97887223 4 NUMBER A TTACHMENT TITLE REVISION O FDTD-1.O? A TTAC# MENT EMERGENCY OPERATIONS DIRECTOR GUIDELINE 01 PAGE 3 2 of 3 STEP
- ACTION / EXPECTED RESPONSE
- RESPONSE NOT OBTAINED
- 5. DIRECTION:
a) As required, advise Ojl 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 Director and Operations personnel in OSC
- 2) Control Room personnel
- 3) Emergency Operations Director
- 7. TERMINATE ATTACHMENT 3: _
a) Verify TSC - ___a) IF NOT, return to pre-l)
\s -
DEACTIVATED " ious steps of this attach-ment 3 for reference as required. v
- _ _ - - . . _ , -. _ .m . N3.97887220 NUMBER A TTACHMENT TITLE .REVI ON O
FDTP-1 0: 01 A TTACNMENT EMERGENCY OPERATIONS DIRECTOR GUIDELINE PAGE 3 3 of 3 s 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 O lO l END I i
_m - m ..u w w .. - - - . - - - - - - _2 - . _ . . - :-_<_,- _ g,
. .N3.97887220 NUMBER A TTAC# MENT TITLE REVISION E?!? - 2 . 0 ' 01 A TTAC# MENT EMERGENCY TECHNICAL DIRECTOR GUIDELINE PAGE 4 1 nf 1
. STEP
- ACTION / EXPECTED RESPONSE
- RESPONSE NOT OBTAINED
- 1. INITIATE EPIP-3.02, ATTACHMENT 4:
a) BY: DATE: TIME:
- 2. ORGANIZATION:
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 c) Verify Instrument person-l l nel in OSC
~
l 3. ACTIVITIES: a) Direct the activities of the following:
- 1) Technical Support Team 1
l 2) Chemistry Team O
N9. 97tS1220 NUMBER A TTACHMENT TITLE REVISION O EPIP 3.0: A TTACHMENT EMERGENCY TECHNICAL DIRECTOR GUIDELINE PAGE n1 A 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
() 5.
- 4) Chemistry SUPPORT:
a) Provide technical support to the Station Emergency Manager , 6. PROCEDURES: I a) Assist in the development of any temporary pro-cedures required for con-l ducting emergency actions
- 7. NRC INTERFACE:
a) Interface with NRC and aid in resolution of questions concerning license requirements
- 8. RELIEF:
a) Assure suitable arrange-ments for relief of:
- 1) Technical Support Team
__ _ _. __ _ . _ _ . .m ._ _ _ __ _ -- _ . - _
,N3.97887220 NUMBER A TTACHMENT TITLE REVISION vpTp_1 n' ni A TTAC# MENT EMERGENCY TECHNICAL DIRECTOR GUIDELINE PAGE 4 3 of 3 STEP
- ACTION / EXPECTED RESPONSE
- RESPONSE NOT OBTAINED
- 8. (CONTINUED)
- 2) Chemistry Tc am
- 3) STAS
- 4) Instrumentation mem-bers of Damage Con-trol Team
- 5) Emergency Technical Director
- 9. TERMINATE ATTACHMENT 4:
a) Verify TSC - a) IF NOT, return to previous DEACTIVATED steps of this Attachment-4 for reference as required. b) Close-out
- 1) COMPLETED BY:
DATE: TIME: c) Affix this Attachment 4 to EPIP-3.02 l l < 1 v END i l l-
., . . - =- _ - . . - _ _ _ _ . . _ - - _ _ _ _ - . _ .
Ns.97087220 I. i NUMBER A TTAC# MENT TITLE REVISION FPTP-.1.Go n1 A TTAC# MENT EMERGENCY ADMINISTRATIVE DIRECTOR GUIDELINE PAGE i 1 5 1 of 5 STEP
- ACTION / EXPECTED RESPONSE
- RESPONSE NOT OBTAINED
- 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 l
I b) Verify Security Team l l
- 1) Security Shift Supervisor
- 2) Security Officers
- 3) Security Control System Operator
- 4) Administrative Security Officers
- 3. VERIFY TSC:
O a) H required, assist in , logistics of TSC activation
. , No.97f8722) NUMBER ATTACHMEl . TITLE REVISION O FPTP '4.O? 01 A TTAC# MENT EMERGENCY ADMINISTRATIVE DIRECTOR GUIDELINE PAGE 5 2 of 5 o STEP
- ACTION / EXPECTED RESPONSE
- RESPONSE NOT OBTAINED
- 4. INTERFACE:
a) Advise Station Emergericy Manager on emergency fire protection, security, administration 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 4
i a No.97887223 ' p NUMBER A TTACHMENT TITLE f ) REVISION vpTp 1 n? ! -j, n1 A TTAC# MENT EMERGENCY ADMINISTRATIVE DIRECTOR GUIELINE, ' FAGE
- ?
5 + 3 of 5
. - y 8
,f' ,
STEP
- ACTION / EXPECTED RESPONSE /
- 1RESPO!!S? .- -
NOT JBTAINED -
-g ,
4
- 6. PROCEDURES: ,j a) Assist in the develcomedt' ( (
and review of any tem'- , porary procedures required g '.. for conducting emerge ~ncy [ actions i
/
- 7. COORDINATION: i~~
a) Coordinate acquisition of j equipment, supplies, and /, personnel: , i
,9 i /~ .J
, f
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t < '
., . I l
')
ir 1 ' ' <
- 1) Onsite an.11 ability - , j __
G ; ,;/< ., p
- 2) Offsite thru EU '
/
?t .,,
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i b)RecordonRes.ourceh,/,e I
' i'( / ,
i
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\"
p , Request (Attachmen,t- k , b
./
/ ' i $ _' .) ~' -
Page 5 of 5)Ji
/ .,<-s\.- N/- .'- i\ r i t g :) ^ 1
' . .3, , .\ > >
g c) Assure ticciv f.ollow up on logistical (items
't p 6
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, .t s.
g y g 8.
\.r ' ' aa RELIEFj "p) m5yg 9 c.. T 1
'\ u', ;,
a) Assure suitable at:rs'nge- 6' :( ,
, s *
{,, .. ments for relief of -
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- 1) Administrative Support-
-[ ' b\ \ (1
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Team d ~~ ' .!
'b
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,, Li k \ ,! .'*~ *
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- 2) Security Support Team -
.g [1 ) .
y q _(- , *'(y,
- 3) P.igcrgency Communicator 4 j
." y ) :s ,
/s)EmergencyProcedures J,o ' ' s t# Ii h'j' ,k
, Coordinator j / .
f 4. h '~ , ., q; , ./
\ ;I) ErIrgency Administrative i f,pl-f/
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. Director !
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Ns. 97881220 I NUMBER A TTACHMENT TITLE REVISION EP!p 2.m n1 A TTAC# MENT EMERGENCY ADMINISTRATIVE DIRECTOR GUIDELINE PAGE 9 4 of 5 STEP
- ACTION / EXPECTED RESPONSE
- RESPONSE NOT OBTAINED
- 9. TERMINATE ATTACHMENT 5 a) Verify TSC - a) IF NOT, return to pre-DEACTIVATED vious steps of this Attach-ment 5 for reference as
, required.
b) Close-out
- 1) COMPLETED BY:
. DATE:
TIME: c) Affix this Attachment 5_ to EPIP-3.02 e 'r t 4 f gno I f,; l' ,' N
, Ns.97887220 NUMBER A TTAC# MENT TITLE REVISION 99T9 1_n: 01 A TTAC# MENT EMERGENCY ADMINISTRATIVE DIRECTOR GUIDELINE PAGE 5 5 of 5 RESOURCES REQUEST NAME OF ITEM .
OR SERVICE REQUESTED BY SOURCE INDIVIDUAL O O
i l
, po.s7ss722o l
NUMBER A TTACHMENT TITLE REVISION EPTP-1.0? n1 A TTACNMENT EMERGENCY MAINTENANCE DIRECTOR GUIDELINE 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-tenance personnel in OSC
- 3. ACTIVITIES:
a) Direct activities of:
- 1) Maintenance Support Team
- 2) Damage Control Team (s)
- 4. SUPPORT:
f a) Provide Maintenance Support l to Station Emergency Manager 1 b) Provide timely updates on damage control activities 1 C/ l
,ND. 97 887220 NUMBER A TTAC# MENT TITLE REVISION voro_1 n- m A TTAC# MENT EMERGENCY MAINTENANCE DIRECTOR GUIDELINE PAGE 6 2 of 3 s
STEP
- ACTION / EXPECTED RESPONSE
- RESPONSE NOT OBTAINED
- 5. INTERFACE: '
a) Coordinate activities with other departments via Emergency Directors b) Coordinate 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) l
- 3) Maintenance members of Damage Control Team (s) l
- 4) Emergency Maintenance Director
- 8. TERMINATE ATTACHMENT 6:
a) Verify TSC - DEACTIVATED a) IF,NOT, return to g previous steps of this Attachment 6 for reference i as required. t l
.._ - . . . - -____ . _ _ ~ ,
l , ,Ns.97887220 e NUMBER A TTACHMENT TITLE REVISION FPTP 'l.O? 01 A TTAC# MENT EMERGENCY MAINTENANCE DIRECTOR GUIDELINE PAGE 6 3 of 3 STEP
- ACTION / EXPECTED RESPONSE
- RESPONSE NOT OBTAINED
- 8. (CONTINUED) l b) Close out l
- 1) Completed By:
Date: Time: c) Affix this Attachment 6 to EPIP-3.02 G e O END
_..m,_
, m==__.__~_ . . - - _ _ _ - - . _ _..-,- --
m
.Ns.97887220 NUMBER A TTACHMENT TITLE REVISION FPTP 'l 0:' 01 A TTACNMENT RADIOLOGICAL ASSESSMENT DIRECTOR GUIDELINE 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) IF NOT, initiate EPIP-4.01.
- 3. VERIFY ORGANIZATION:
a) Radiological Assessment Team
- Obtain necessary personnel.
l
- 1) Health Physicist
- 2) Health Physics Technicians b) Offsite Monitoring Teams (2).
c) Radiation Protection Personnel
- 1) Inplant Monitoring Team
- 2) Sample Analysis Team
- 3) Onsite Monitoring Team
- 4. INTERFACE:
a) Coordinate activities with l other departments via Emergency Directors b) Obtain required equipment and supplies via Emergency Admini-strative Director O
NG. 97007220 NUMBER A TTACHMENT TITLE REVISION rorn_, no nt j A TTAC# MENT RADIOLOGICAL ASSESSMENT DIRECTOR GUIDELINE PAGE 7 2 of 4 STEP
- ACTION / EXPECTED RESPONSE
- RESPONSE NOT OBTAINED t
- 5. DIRECTION:
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 Station Emergency Director b) Evaluate emergency exposure criteria c) Provide timely updates on radiological conditions 1
,:,_w.._. w . .-2 --- - - - - - - - -
- u2zane_=.- - - - - -
.N3.97887220 NUMBER A TTACHMENT TITLE REVISION EPID-3 _ n' ni A TTAC# MENT RADIOLOGICAL ASSESSMENT DIRECTOR GUIDELINE PAGE 7 1 of 4 I
l STEP
- ACTION / EXPECTED RESPONSE
- RESPONSE NOT OBTAINED
- 8. PROTECTIVE MEASURES:
a) Evaluate radiological condi-tions and make recommendations 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
- 1) Dose Assessment Teams
- 2) Offsite Monitoring Teams (2)
- 3) Radiation Protection Personnel
- 4) Radiological Assessment l Director I
l t (
_ _ _-. _. _ --m,
, ,Ns.97887220 NUMBER A TTACHMENT TITLE REVISION h vp T p-1. n' A TTACNMENT RADIOLOGICAL ASSESSMENT DIRECTOR GUIDELINE PAGE ni 7 4 of 4 STEP
- ACTION / EXPECTED RESPONSE
- RESPONSE NOT OBTAINED .
- 12. TERMINATE ATTACHMENT 7:
a) Verify TSC - DEACTIVATED a) E NOT, As required, return to previous steps of this Attachment 7 for reference as required b) Close out
- 1) Completed By:
Date: Time: c) Affix this Attachment 7 to EPIP-3.02 b u END
No.97087229 NUMBER A TTACHMENT TITLE REVISION l0 - A TTACNMENT EMERGENCY COMMUNICATOR GUIDELINE
~
PAGE l l R 1 of 2 i STEP
- ACTION / EXPECTED RESPONSE
- RESPONSE NOT OBTAINED
- 1. INITIATE EPIP-3.02, ATTACHMENT 8: ,
a) BY: DATE: TIME: 1 NOTE: Emergency Communicator position moves with that of the Station Emergency Manager.
- 2. VERIFY EOF:
1 a) EOF - NOT ACTIVITATED a) IF ACTIVATED, transmit Essages from TSC/ Control Room to EOF. AND GO TO Step 5 of Attachment 8_. NOTE: dpdates.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
- .-. - . . - - - , , ,- .- . ,. - . . . ~. . , ,. - ._.
N3. 97887220 NUMBER A TTACHMENT TITLE REVISION enrna no M A TTACl[ MENT EMERGENCY COMMUNICATOR GUIDELINE PAGE R 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) E TSC manned maintain the Radiological Status Board J l b) Update Status, Board Data at i 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 l l l O END l
,,m - - -- --
m - e
N3.97887220 NUMBER A TTACHMENT TITLE REVISION !O l A T7AC# MENT EMERGENCY PROCEDURE COORDINATOR GUIDELINE PAGE
~
! 9 1 of 2 STEP
- ACTION / EXPECTED RESPONSE
- RESPONSE NOT OBTAINED l
- l. INITIATE EPIP-3.02, ATTACHMENT 9:
a) BY: DATE: TIME:
- 2. CONTROLLING PROCEDURES:
a) Assist Station Emergency Manager in maintenance of ; controlling procedures b) Assure appropriate pro-j' O cedures are initiated as required i
.c) Track and hold completed procedures until TSC -
deactivation
- 3. LOGISTICS:
a) Verify sufficient EPIPs and attachments available in TSC f b) Procure additional material via Emergency Administrative
' Director
- 4. TERMINATION OF ATTACHMENT 9:
a) Verify TSC - DEACTIVATED a) ))[ NOT. return to previous step of this Attachment 9'for reference as required 7 b) Assist the Station Emergency Manager in collection of all procedures used during the emergency
N3.97887220
; NUMBER A TTACHMENT TITLE REVISION 'O -
A TTAC# MENT EMERGENCY PROCEDURE COORDINATOR GUIDELINE 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 I I ) O
_ , ;u .x_'***'9_ * , ' --- __- -
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s No.97887200 VIRGINIA ELECTRIC AND POWER COMPANY
; NORTH ANNA POWER STATION j EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCEDURE TITLE REVISION 01 EPIP-3.03 ACTIVATION OF OPERATIONAL SUPPORT CENTER PAGE (With 1 Attachment) 1 of 4 PURPOSE
- 1. To provide guidance to personnel charged with activation of the OSC.
NOT A CONTROLLED D O VNT JUL 2 41982 nnu ,, ,,w USER LATEST REVISION Operational Support Center Director ENTRYCONDITIONS
- 1. Declaration of an Alert, Site Emergency or General Emergency; V
AND
- 2. Entry from other EPIPs;
~
n VEPCO PROPERT Y
- 3. Direction of the Station Emergency Manager.
This doc : rent is the property of .he Virginia.Eloctric and Power Company and is to be returned upon reque t.
- No permission is granted to pubil lh.
reproducc. tr . mit or dicclose to another any information containec in
. this document.
I REVISION RECORO REV. 00 PAGE(S): Entire Procedure DATE: 07-02-82 REV. 01 PAGE(S): Entire Procedure DATE: 07-22-82 REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: l REV. PAGE(S): DATE: y~) APPROV RE MENCEO APPROVED
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[h CHAIRMANSTA TION NU EAR SAFETY 07-22 -82 \ '. AND OPERA TING COMMITTEE l -
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1 1 , NUMBER PROCEDURE TITLE REVISION
! k ,' 01 i EPIP-3.03 ACTIVATION OF OPERATIONAL SUPPORT CENTER 2ob' (WITH 1 ATTACHMENT)
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 1. INITIATE EPIP-3.03:
a) BY: DATE: TIME:
- 2. LOCATION:
a) Verify NAPS Maintenance a) Proceed to alternate OSC Bldg. - HABITABLE location in the Emergency Switchgear Room b) Proceed to primary OSC located in the 3rd floor conference room of the Maintenance Bldg.
- 3. COMMUNICATION:
a) Via the dedicated PBX telephone, declare OSC location to Station Emergency Manager
- 4. ACCOUNTABILITY:
a) Maintain a listing of ' personnel as they report ,l i to the OSC l b) Enter names of personnel in appropriate space of EPIP-3.03, Attachment J_ l c) Report names of OSC personnel to Security for accountability
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- No. 97887210 i
1 NUMBER PROCEDURE TITLE l REVISION
, l, / 01 EPIP-3.0 l ACTIVATION OF OPERATIONAL SUPPORT CENTER
- PAGE 3 of 4
, (WITH 1 ATTACHMENT)
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 5. 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) Assure personnel check in J when reporting to OSC b) Assure personnel check out when leaving OSC c) Maintain updated listing of personnel on Attachment 1 for accountability
~
d) 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) GO TO Step 6_ O
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e I No. 97887210 3 NUMBER PROCEDURE TITLE REVISION t L .- 01
; EPIP-3.0 l ACTIVATION OF OPERATIONAL SUPPORT CENTER l PAGE 4 of 4
; (WITH I ATTACINENT)
. - STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 9. TERMINATE EPIP-3.03:
a) On direction of Station Manager deactivate the OSC b) Direct personn'el in OSC to return to normal station organization c) Close out ,
- 1) COMPLETED BY:
DATE: TIME: 9 d) Forward this procedure and attachments to SNSOC for review l l0
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, NUMBER A TTACHMENT TITLE REVISION j voTo-1.01 ni i 4 -j ,
A TTAC# MENT ACTIVATION OF OPERATIONAL SUPPORT CENTER PAGE I I i !
- 1 OSC PERSONNEL LIST 1 of 2 i
j i i l l l OPERATIONS MECHANICAL ELECTRICAL
- 1. :
i 2. I
- 3.
4.
- 5. l i
6. i 7. l 8. 9. 10.
! 11.
12. 13. 14. 15. 16.
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l }y NUMBER A TTACHMENT TITLE REVISION I . FPTP 't 01 n1 1' j A TTACNMENT ACTIVATION OF OPERATIONAL SUPPORT CENTER PAGE l OSC PERSONNEL LIST 2 nf 2 o e
. IST AID TEAM FIRE BRIGADE INSTRUMENT
- 1. .
2. 3. 4. 5.
- 6. ,
7. 8. 9. 10. OTHERS i i
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' wf$.? W e e No. 97887200 *
! VIRGINIA ELECTRIC AND POWER COMPANY q NORTH ANNA POWER STATION
*-; EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCEDURE TITLE REVIS10N 01 EPIP-3.04 ACTIVATION OF EMERGENCY OPERATIONS FACILITY
, PAGE
, (With 1 Attachment), 1 of 4 PURPOSE
- 1. To provide guidance to personnel performing initial activation of EOF.
NOT A CONTROLLED DOC 9 MENT J'JL 2 41982 USER NUd n . i v. Two (2) Security Team members tATESi HEvtStvN ENTRY CONDITIONS
. 1. Declaration of an Alert, Site Emergency or General Emergency; AND
- 2. Direction of the Station Emergency Manager through the on-duty Security Shift Supervisor. -
VEPCO PROPERTY This docurcent is the property of t!w Virginia Electric and Power Company and is to be returred upon request. No permission is granted to pubHot reproduce, t:anm. tit or disclose te another any information contained in this doeur.cnt. . , _J REVISION RECORD REV. 00 PAGE(S): Entire Procedure DATE: 07-02-82 REV. 01 PAGE(S): Entire Procedure DATE: 07-22-82 REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: APPROVAL RE MMENDED APPROVE 0 DA TE g/ 07 22-82
^
4 % CHAIRMANSTATIONNUCL ARSAFETY l AND OPERA TING COMMITTEE
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No. 97887210 NUMBER PROCEDURE TITLE REVISION 01 EPIP-3,0o ACTIVATION OF EMERGENCY OPERATIONS FACILITY PAGE 2 of 4 (WITH 1 ATTACE W ) ? , - STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 1. INITIATE EPIP-3.04:
a) BY: DATE: TIME: = NOTE: This procedure should be performed by two persons. n 2. ENTRANC': E a) Obtain door key to NAPS Visitors Center from Security Shift Supervisor
- 3. AREA SET-UP:
a) Refer to EPIP-3.04, Attachttent i for area locations b) Move and stack auditorium . chairs as required. Dollys provided in Projectica Room c) Obtain tables from Pro-jection Room and place in EOF areas NOTE: Communications equipment designated for the EOF is stored in boxes labeled by area. Equipment plugs and jacks are numbered alike. O __ .= -
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NUMBER PROCEDURE TITLE REVIS N l
~~ '
EPIP-3.0o ACTIVATION OF EMERGENCY OPERATIONS FACILITY PAGE 3 of 4 (WITH 1 ATTACHMENT)
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED ,
- 4. COMMUNICATIONS:
a) Obtain communication equip-ment from metal shelves in-Projection Room b) Connect equipment in appro-priate locations as shown on Attachment 1,, EPIP-3.04 NOTE: Maps and manuals for EOF use are stored in the Proj ection Room.
- 5. STATUS BOARDS:
a) From Projection Room, obtain key to basement door located at West end of Visitors Center b) Locate the three (3) , status boards stored in the basement and place them on tables against the Projection Room wall of the EOF
- 6. SECURITY:
a) Maintain physical control
, of EOF and Visitors Center until relieved by VEPCO Corporate Security per-sonnel
- 1) Entry allowable with 1) Non-VEPCO personnel entry valid VEPCO ID card . allowable by EOF Staff authorization.
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,!4 No. 97847210 t
i i jiQ NUMBER PROCEDURE TITLE REVIS N
' ~'
i EPIP-3.00 ACTIVATION OF EMERCENCY OPERATIONS FACILITY PAGE 4 of 4 (WITH 1 ATTACHMENT)
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 7. TERMINATE:
a) Verify Corporate Security a) IF NOT, GO TO Step 6 personnel have assumed responsibility for EOF Security b) Close out .
- 1) COMPLETED BY: -
DATE: TIME: c) Forward this procedure to / SNSOC for review l i e { t i
\
END
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No. b 78 87220 ,
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)i NUMBER A TTACHMENT TITLE j +
EPIP-3.0 REVISIY1
,. j 2 (' ACTIVATION OF EMERCENCY OPERATIONS FACILITY
. A TTACHMEvT PAGE
- 1 EOF COMMUNICATIONS, NAPS I of 1 i* ,
i: . j
- Proj ection
- Recovery 1
- 9,7.R
- 6, 8 :
Room Manager 5_ g ;
- : Area 6, j Assess =ent g NRC
! 4
- Area j Area
* *Coc=unication 2_
- State ; Support !
Coordinator ,3_ g Area ; Area : Area 7_
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- Enter !
NAPS VISITORS CENTER AUDITORIUM Index . 1,. State OEES dedicated line
- 2. Louisa County dedicated line 3_. Spotsylvania County dedicated line ,
- 4. EOF to TSC
_5. EOF to CERC (OJRP) , _6. NRC line _7_. OPX 8.. Bell
- 9. Station PBX -
10_. Instaphone R. Radiophone w/ portable radios
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- l j no.97sermoo VIRGINIA ELECTRIC AND POWER COMPANY
! NORTH ANNA POWER STATION
'M EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCEDURE TITI.E REVISION 01 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING PROCEDURE PAGE (With 1 Attachment) 1 of 25 s
PURPOSE To initially assess emergency conditions, provide protective measures rec-commendations, establish an emergency organization and direct Health Physics Response to an Emergency. t USER Radiological Assessment Director or Senior Health Physics represen-tation onsite.
.. e A r ONTROi LED ENTRY CONulTIONS pv "NT t 1. Activation by EPIP - 1.01 JUL 2 41982 NOh o .
'E LMr.51 HtNISMN VEPCO PROPERTY l Thia docueent is the prope2 ty of tr Virginis E16ctric and Power Comp ns and is to be roturned upon rer;uect.
No permissian is granted to publish, reproduce, trancait or disclose to another any Information contained in R thic document. REVISION RECORD REV. 00 PAGE(S): Entire Procedure DATE: 07-02-82 REV. 01 PAGE(S): Entire Procedure DATE: 07-22-82 REV. PAGE(S): DATE: l REV. PAGE(S): - DATE: , REV. PAGE(S): DATE: l REV. PAGE(S): DATE: REV. PAGE(S): DATE: APPR APPROVEO l Alf ECOMMENCEO OA TE
// 4 07228:
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, & CHAIRMAN STA TION NUC AR SAFETY '
AND OPERA TING COMMITTEE
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, NUMBER PROCEDURE TITLE REVISION 01 3 -
EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PAGE CONTRCLLING PROCEDURE 2 of 25 1-
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 1. INITIATE PROCEDURE:
a) BY: DATE: TIME:
- 2. CHECK CONDITIONS:
a) The SENIOR HEALTH PHYSICS a) IF TSC IS activated, report individual ONSITE should to the TSC. report to the CONTROL ROOM - if the TSC is NOT activated N .- N 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-c termine the existing PLANT CONDITIONS, EMERGENCY ACTI0t; LEVELS (EAL'S) EXCEEDED , i and the CLASSIFICATION of the EMERGENCY l c) Assume the position of RAD-IOLOGICAL ASSESSMENT DIRECTOR and continue with this instruction 1
- 3. INITIAL ASSESSMENT
. a) Upon CLASSIFICATION of an a) If NO actual OR POTENTIAL EMERGENCY, an INITIAL ASSESS- 0FFSITE RELEASE has oc-l V MENT of offsite release must curred, C0 TO Step M.
l be made l
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NUMBER PROCEDURE TITLE REVIS10N r
' 01 j EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR
.PAGE CONTROLLING PRCCEDURE 3 of 25
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 4. VERIFY EMERGENCY LEVEL a) IF the event is an UNUSUAL a) IF the emergency is an ALERT EVENT, continue with this or GREATER, GO TO Step 6_.
instructicn 4
- 5. EVENT - UNUSUAL EVENT a) If the event is' NOT a RADI-a) I_F,the F event is a RADIO- OLOGICAL RELEASE.GO TO Step LOGICAL RELEASE, ACTIVATE
-14.
EPIP-4.08, Initial Offsite >
, +,
Release Assessment to access O the percent of TECHNICAL SPECIFICATION and return to this Step p' s c:
- 1) E the normal range moni- 1) E monitors indicata GREATER tors are ONSCALE and indi- THAN 1000% TECH SPEC, GO TO cate GREATER THAN 101% TECH Step 6.
SPECS, but LESS THAN 1010% TECH SPECS, OR ' i
~
n !.t Normal! range monitors are , , f 0FFSCALE and indicate LESS , THAN 1010% TECH SPECS RECOMMEND classification of an UNUSUAL EVENT lt g b) REPORT RESULTS 1:nmediately to the Emergency Manager and , g continue with this procedure t c) OBTAIN SAMPLE of the effluent c) hsample can not be OBTAINED release path return to the beginning of this step using station moni-tors to access the release C'}\. ,.,
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- ! EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR 4 i ' <
PAGE CCNTROLLING PROCEDURE
,4 h 1 4 of 25
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STEP ACTION / EXPECTED RESPONSE f RESPONSE NOTOSTAINED f f 4 j , i ,
- 5. (CONTINUED) j
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- II' release terminates, CO TO Step 28,.
d) ANALYZE SAMPLE as per HEALTH ,
.2HYSICS procedure H.P. 3.4.1.3 '
f
,Y e) GO TO Step IS_ for follow up assessment I,('4 '
j h V 6. EVENT - ALERT, SITE OR GENERAL
-f f
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4
./I' a) U the emergency is classified a) IF the event is NOT a RA3IO ,
as an ALERT Q GENERAL EMER- LOGICAL RELEASE, GO YO Step, GENCY J,S_. f _.
.t AND *
, <' j A radiological release has , ,
occurred OR may potentially 4 occur, continue with this procedure 3
/'
- 7. EVENT - CONDITION IV LIMITING ;
FAULTS ,i ., f
~ /':, e a) F the type of Accident is a a) U type of*a'ecident is NOT <
LIMITING FAULT accident, ' a LIMITING FA7LT C0 TO + (LOCA, Steam Generator Tube / Step H. .g 3 Rupture, Main Steam Line Rup- / 1 - ture OR Fuel Handling Acci-dent)7ontinue with this #' 3
')
T irstruction
./
- 8. EVENT - FULL HANDLING ACCIDENT -
,. , 'l ;.&
a) IF Event is a FUEL HAND- a) If EVENT is NOT a ' Fuel Hand-U) I.ING N CIDENT, RECOMMEND 3 ling Accident, GO TO Step 9.' EVACUATION oE the Fuel s g L;-l . ,t "# Building AND/OR affected i i ~ containme nt a-
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is' a NUMBER PROCEDURE TITLE REVISION . , - - ,/) 01 N ,; -( ' EPIP-4.01 RADICLOGICAL ASSESSMENT DIRECTOR ?' ,' i f' ' CONTROLLING PROCEDURE . PAGE 5 of 25 i '/ E i
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT08TAINED
- 8. (CONTINUED) ;
l 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 a
necessary, individuals evacu-ated from the accident area 7, ', d) Activate EPIP 4.08 INITIAL
. OFFSITE RELEASE ASSESSMENT, to
! /- idetermine offsite consequences I ' [,of the acetdent and return to h/ 5chis step
' e) AEPORT RESULTS of the above
, step to the Emergency Manager i
f)fC0 TO Step M
/ 4 9.- EVENT - STEAM GENERATOR TUBE I #
RUPTURE !, , a ) IF,the event is a Steam Gen- a) E the event is NOT a Steam-i i er.ator Tube Rupture REQUEST Generator Tube Rupture GO TO
,/ g[ f th's following INYORMATION Step ~10.
# .' a from the Emergency Manager t/t' .: , , f ':
5 /
- 1) Status of the Air Ejector
{5 divert
- 2) The number of Steam Gen- ,
, erator Relief Valves which have lifted OR_ may poten-tially life I
- 3) E relief valves have
;, j lifted, length of time X valves remained open i ;
- 3. < - . . . . . .
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.. _ a_._:.- - ^r:&_-2 j No. 97887210 4i
- t NUMBER PROCEDURE TITLE REVISION l 01
.a EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PA GE
- CONTROLLING PROCEDURE 6 of 25
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT08TAINED
~9. (CONTINUED)
- 4) Status of main steam supply 4) H AFPT is isolated, re-to the Auxilary Feedwater lease from this pathway Pump Turbine may be disregarded.
NOTE: H the main steam supply from the leaking steam generator has, NOT been isolated, request the Emergency Managsr to initiate isolation of the steam supply.
~
i
- 5) Request placement of operation personnel ir. the Emergency Switchgear Room to report INITIAL readings and any INCREASE B 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 d) RESTRICT ACCESS to the Steam Generator Blowdown Cooler area, Steam Generator Blow-down Lines, Steam Generator Relief Valve area and the . n' O AFrT exhaust area, until a survey confirms no radiological. hazards
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, NUMBER PROCEDURE TITLE REVISION 01 i
EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR
' PAGE CONTROLLING PROCEDURE 7 of 25 f ; - STEP ACTION / EXPECTED RESPONSE RESPONSENOT08TAINED
- 9. (CONTINUED) e) IF, F personnel are available e) IF, F 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 Generator Blowdown and Main
--/ Steam of Affected Unit NOTE: Potential liquid release pathway may occur through the Main Steam Safety Valve.
/
g) GO TO Step N
- 10. EVENT MAIN STEAM LINE RUPTURE a) E a Main Steam Line Rupture a) H event is NOT a Main Steam occurs, obsarve station ven- Line Rupture, GO TO Step E.
tilation monitors
- 1) H 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 the event the accident, GO TO, Sub-step b_.
Os / ACTIVATE EPIP 4.08 Initial Offsite Release Assessment
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s 2 N3.97887210 j' l ie ' hJMBER PROCEDURE TITLE REVIS10N I 01
., EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PAGE CONTROLLING PROCEDURE 8 of 25 i
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 10. (CONTINUED) ,
b) REPORT RESULTS to the Emergency Manager NOTE: IF no initial releases have occurred because of prior primary to secondary leakage, source term may develop inside contain-ment or may result from Main Steam Relief Valve lifting o c) Request from the Emergency Manager the following in-formation and continue with p this instruction
- 1) Location of Steam Break
- 2) Actual or potential lifting of Main Steam Safety Valves
- 3) E valves have lifted.
length of time valve re-mained open ,
- 4) Status of Auxiliary Feed- 4) E Main Steam supply to j water Pump Turbine (iso- the Auxiliary Feedvater
- lation) Pump Turbine has been isolated, no release will l
occur through this pathway
- 5) Monitor Reading on Main Steam Monitors and AFPT l exhaust tonitors 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 Containnent Air AND AND Consider activation once man- , power is available l g EPIP 4.23, Post Accident i j' Sampling of Reactor Coolant l e) GO TO Step 13, i l , - - - - = ---
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- NUMBER Q EPIP-4.01 PROCEDURE TITLE REVISION 01 RADIOLOGICAL ASSESSMENT DIRECTOR
/ AGE 4
CONTROLLING PROCEDURE 9 of 25 4
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTCBTAINED -
- 11. EVENT - LOCA a) E the event is a LOCA, ree- a) E event is NOT a LOCA GO TO ommend EVACUATION of the Step J2.
Auxiliary Building and Safe-guards Building, and RESTRICT entry, until survey confirm no radiological hazards with-in these areas b) Activate EPIP-4.08, Initial b) E _NO,offsite releases have Offsite Release Assessment occurred, continue with this to initially access any instruction offsite release and return to this step D 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 potential for release from the containment building l d) Consider activation of EPIP-4.22, Post Accident Sampling of Reactor Coolant and EPIP-4.23, Post Accident Sampling of Containment Air when man-l power becones available , l e) GO TO Step J3
- 12. EVENT - RADIOLOGICAL RELEASE a) IF the event is a RADIO- a) IF event is NOT a RADIO-LOGICAL RELEASE, continue LOGICAL RELEASE, GO TO with this instruction StepJ5.
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. f's 01 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PAGE CONTROLLING PROCEDURE ,10 of 25 ; - 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 monitor readings
- 13. PROTECTIVE MEASURES a) IF the results from Offsite a) IF results from Offsite Release Assessment are greate.r Release Assessment are less than 50 mr/hr WHOLE BODY OR- than 50 mr/hr WHOLE BODY or
~
250 mF/hr THYROID at the 250 mr'Thr THYROID at the Site Site Boundry, continue with Boundry, GO TO Step M. this instruction b) Obtain from the Emergency b) E no estimate can be given Manager, an ESTIMATE of assume release will last for DURATION of the RELEASE 3 hcurs (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 O 2 :_ ; = = = = = = = = = =
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i ii y NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PAGE CONTROLLING PROCEDURE
- 11 of 25
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 13. (CONTINUED) d) E the Projected Dose is d) E PROJECTED DOSE is LESS GREATER THAN 500 MR WHOLE THAN 500 MR WHOLE EODY BODY E
LESS THAN 1000 MR THYROID GREATER THAN 1000 MR THYROID Inform the Emergency Manager ACTIVATE EPIP 4.07, Protec-that R PROTECTIVE MEASURES tive Measures and return to are required offsite this step AND GO TO substep F I)s 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 15_. MEASURES required 0FFSITE AND The DISTANCE PROTECTIVE MEASURES are required 14 EVENT - INJURED CONTAMINATED INDIVIDUAL a) IF the event is an Injured a) E the event is NOT an In-Contaminated Individual jured Contaminated Indivi-dual GO TO Step g. AND Requires Offsite Medical _ Treatment ACTIVATE EPIP 4.20 HEALTH PHYSICS ACTIONS for TRANS-g' PORTATION of CONTAMINATED INJURED INDIVIDUAL _ . a - . 6 . , =_ . .JJ , _ ' __._ __ : . _ _ _ _ _ _ _ . . ...ja,,,;_,,,_.,._... .
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, 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 or onsite decontamination decenned, GO TO substep 5.
can NOT be used to remove contamination
- 3) Insure a Health Physics individual is available to
( accompany the victim b] 4) Recommend to the Emergency Manager transportation of the victim to MCV
- 5) If the event was initiated 5) IF other EAL'S were exceeded only for contaminated in- GO TO Step M.
jured individual requiring offsite medical treatment AND NO other EAL'S have been Eceeded GO TO Step 3
- 15. FOLLOW-UF ASSESSMENT a) IF TSC is NOT activated a) IF TSC IS activated GO TO 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
.C) Manager
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- 01 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PAGE CONTROLLING PROCEDURE 13 of 25
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 15. (CONTINUED)
NOTE: E conditions require presence in another location, inform the J Emergency Manager and report back to the Control Room af ter completion of task I c) E a Radiological Release c) IF NO release has occured has occured, GO To substep d_.
- 1) OBTAIN if possible SAMFLES 1) E _N_0 0 samples are obtained x, 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 monitor 4.ng and radio analysis f) E the Emergency has terminated f) E the Emergency has NOT GO TO Step g terminated
- 9. R, l IF che TSC is NOT manned, t
Return to Step g AND Repeat sampling and assess-l ment as necessary. l i I
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, 01 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PAGE CONTROLLING PROCEDURE 14 of 25
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 16. VERIFY RELIEF a) When a more Senior Health a) E relief is NOT needed, Physics individual arrives GO TO Step E. -
onsite pR, E relief is needed:
- 1) Brief successor as to the existing plant conditions, offsite release assessment performed b'~ AND Health Physics actions currently underway
- 2) Announce the change of position to the Emergency Manager
- 17. ESTABLISH EMERGENCY ORGANIZATION a) E the Health Physics Emer- a) E Emergency Organization has gency Organization has not been activated, GO TO Step been activated, continue with this procedure H.
I b) Establish the Dose Assessment b) E 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-l able c) Establish the position of c) E manpower is NOT yet avail-Radiation Protection Super- able, continue with this in-visor and assign EPIP-4.02, struction assigning EPIP-4.03 l \ Radiation Protection Super- when manpower becomes avail-i ' visor Controlling Procedure able. l , ;.w, = -- = --- -- w . =: = - + .. - - - - - - - -,
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,j. I NUMBER PROCEDURE TITLE REVISION
( 01 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PAGE CONTROLLING PROCEDURE 15 of 25
- STEP ACTION / EXPECTED RESPONSE RESPONSENOT08fAINED
- 18. OFFSITE ASSESSMENT a) E offsite releases have a) IF, F E offsite releases have occurred, request from the occurred Emergency Manager an indivi-dual to man the Radiation OR l Monitor on the release path-way IF there is NO potential for a release AND GO TO Step p.
Report any increase O_R R decrease in monitor readings b) The following information will be supplied periodical ,0RR upon _ request
- 1) Meteorological Data
- 2) Radiation Monitor System Data
- 3) Sample Analysis Data c) Upon receipt of the above data, complete attachment 1
( i l
- 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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'l No.97887210 l
NUMBER PROCEDURE TITLE REVISION EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PAGE CONTROLLIN
G. PROCEDURE
16 of 25
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTQBTAINEO
- 18. (CONTINUED)
NOTE: The function of plume tracking /offsite monitoring will be the responsibility of the Radiological Assessment Coordinator, upon activation of the EOF
- 1) E EOF is NOT activated and 1) E EOF is activated, GO TO offsite monitoring teams Step E.
are required, request the Radiation Protection Super-visor to ACTIVATE EPIP-4.16, - Offsite Monitoring O, 2) Advise Radiation Protec-tion Supervisor as to the
- 2) I_f, f adequate manpower is NOT available reassess the number of teams required need for Offsite Monitor-ing Teams upon arrival of additional manpower AND GO TO Step E.
- 3) Consult with the Dose l Assessment Team Leader, the
! probable exposure levels that may be received by the j . Offsite Monitoring Teams l 4) E the Whole Body exposure 4) E exposure rates for to the Offsite Teams may Whole Body O_R_ Thyroid will exceed 10 CFR 20 limits not exceed limits, C0 TO ACTIVATE EPIP-4.04, Emer- substep e, gency Exposure Limits E Thyroid exposure is ex-pacted to exceed 10 REM,
- ACTIVATE EPIP 5.07, Admini-l ,
stration of Radioprotective Drugs I
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'% NUMBER PROCEDURE TITLE Rh /ISION 01 EPIP-4.0 L RADIOLOGICAL ASSESSMENT DIRECTOR PAGE
, CONTROLLING PROCEDURE 17 of 25
- 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 Offsite Moni-toring Teams s e) Obtain the latest Offsite e) IF Offsite Release Data is j Release Assessment Data Sheet II6f available, CO TO Step g from the Dose Assessment Team Leader AND Return when data becomes available S
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- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 18. (CONTINUED)
- 1) IJ, the dose rate Offsite 1) E the Dose Rate Offsite is exceeds 50 mr/hr Whole Body Less Than 50 mr/hr Whole -
or 250 mr/hr Thyroid con- Body or 250 mr/hr Thyroid, tinue with this instruction GO TO Step M.
- 19. PROTECTIVE MEASURES 4
a) Obtain from the Emergency Man-ager, and Estimate of 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 Dose Rate (mr/hr) = Projected Dose (mr)
(hours) c) I_f_ f the Projected Dose is c) E Projected Dose is LESS GREATER.THAN MR Whole Body THAN 500 MR Whole Body OR OR GREATER THAN 1000 MR Thyroid LESS THAN 1000 MR Thyroid ACTIVATE EPIP 4.07, Protec- Inform the Emergency Manager tive Measures and return to that E PROTECTIVE MEASURES this Step are required offsite AND GO TO Step p. d) Continue with substep a, through c using dose rates for 2,5, and 10 miles e - 4 e m
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.. : u u . - - O '__1" No.97847210 l,',
3 NUMBER PROCEDURE TITLE REVISION
' 01 EPIP-4.01 1 RADIOLOGICAL ASSESSMENT DIRECTOR PAGE CONTROLLING PROCEDURE 19 of 25
- STEP ACTION / EXPECTED RESPONSE RESPONSENOT OBTAINED 9
l
, 19. (CONTINUED) e) Recommend to the Emergency F 0PROTECTIVE MEASURES e) IF,N0, Manager the PROTECTIVE MEAS- are required, CO TO Step H.
URES required 0FFSITE AND The DISTANCE PROTECTIVE MEASURES are required
- 20. EOF ACTIVATION a) IF EOF is Activated: a) IF EOF has NOT been activated,
- 1) Brief the Radiological O 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 j all Offsite Assessment, I completed to date and the I '~
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 i
data to the EOF 1
- 21. ESTABLISH IN-PLANT MONITORING:
a) Instruct Radiation Projection a) IF,no monitoring is needed, Supervisor to activate EPIP- GO TO substep e_. 4.14. Inplant Monitoring and EPIP-4.15, onsite Monitoring as necessary
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.. NUk ER PROCEl'URE 11TLE REV/SION 1 .1 01 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PAGE CONTROLLING PROCEDURI 20 of 25
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT08TAlfiE0 i
- 21. (CONTINUED) b) Brief Radiation Proj ection Supervisor as to existing plant conditions c) Assist in selecting proper c) IJ[ no monitoring is needed, monitoring and sampling continue with substep e.
areas d) Assist Radiation Projection Supervisor in determining 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 n)nitoring of TSC and EOF
- 1) Based on survey data and plant conditions establish .
routine for surveys of the Emergency Centers I t l NOTE: IF a radiological release has taken place, notify the Radia-l tion Protection Director to resurvey Emergency Centers upon change of plume direction or increase in release, f) Based on survey data, direct the establishment of nev
- l. control points to control the spread of contamination and/
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. -) 01 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PAGE CONTROLLING PROCEDURE 21 of 25
, - STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 22. ENTRANCE - ACCESS CONTROL AREA a) All planned access into Con- a) Il[ entrance is not required
. trolled areas should require GO TO Step 23,.
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 FROTECTION:
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 25,.
- 2) Airborne activity is 2) Maximum permissible con-greater than 0.25 times centration less than or maximum permissible con- equal to 0.25, CO TO Step 25,. 5 centration c) For all essential workers assess respiratory protection as needed per EPIP-4.05 Respiratory Protection and return to this step i
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No.97887210 t ,,/,' NUMBER PROCEDURE TH"LE REVISION 01
; EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PAGE CONTROLLING PROCEDURE 22 of 25 i
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTQBTAINED
{
- 24. LVALUATE 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 assess need for use of radioprotective drugs and return to this step b) Jg[ the actual or projected b) jg[ thyroid exposure will be exposure will be GREATER THAN less than 10 Rem, GO TO Step Ojt EQUAL TO 10 Ram thyroid 25,. (without respiratory protec-tion) recommend administration-of thyroid blocking tablets c) Request approval from the Emergency Manager to Admin-1 ster radioprotective drugs.
' dF 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:
a) Discuss with Dose Assessment Team Leader, the projected or actual whole body and/or thyroid exposure onsite from release of radioactive material b) Determine direction of plume (G) , c) Determine from Emergency s_- Manager the probable duration of release
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No. 97847210
\ NUMBER PROCEDURE TITLE
~~ ~
REVISION 4 s. o1 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PAGE CONTROLLING PROCEDURE 23 of 25 l - STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED i-
- 25. (CONTINUED) d) H actual or projected d) E dose is LESS THAN EVACU-exposure onsite is GREATER ATION LIMITS THAN 1 Rem whole body
~
OR
~
OR g plume is in the direction GREATER THAN 5, Rem Thyroid of the evacuation route, 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 recommendation 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-t body exposure may exceed ance of 10CFR20 exposure l 10CFR20 exposure limits, limits, GO TO Step H. i activate EPIP-4.04, Emergency I Exposure, and return to this l 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 28.
emergency (fire and/or rescue squads)
- 1) Inform Radiation Protection '
Supervisor of their arrival at the Station
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No. 97887210
\
NUMBER
' Vll'-
PROCEDURE TITLE REVISION 01 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PAGe CONTROLLING PROCEDURE 24 of 25
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- l
- 27. (CONTINUED)
- 2) Request dosimetry co'be supplied at the Security building prior to their entrance onsite
- 28. VERIFY EMERGENCY: -
a) Jy[ Emergency condition a) ))[ the Emergency Manager still exists: declares termination of the Emergency, GO TO Step 29.
- 1) Return to Step 16 ind direct the repetition of surveys, radiological sampling and/or dose assessment to determine status of the emergency
- 2) Advise the Emergency Manager 3 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:
1 1
.- _~ ..
No. 978 87210
~
- l. -
k NUMBER PROCEDURE TITLE PEVISION i 01
, EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PAGE CONTROLLING PROCEDURE 25 of 25
- STEP ACTION / EXPECTED RESPONSE RESPONSENOT08TAINE0
'l 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 radsaste 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 3Y: l i DATE: i TIME: i t . END l
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'). ' UMBER A TTACHMENT TITLE REVISION
- EPIP-4.01 01 Ilt RADIOLOGICAL DATA WORKSHEET A TTACHMENT PAGE 1 1 of 1 t
DATE: TIME: UNIT # Meteorological Data: ' WIND DIRECTION (from): , SECTORS AFFECTED: WIND SPEED (mph): PRECIPITATION: STABILITY CLASS: O RADIATION MONITORING SYSTEM DATA: MONITOR CPM OR MR/HR VENT VENT (VG-104) 1 ( VENT VENTB( ) PROCESS VENT (GW-102) AIR EJECTOR (SV-121.122) VENT VENTA (VG~l74) VENT VENTB (VG-175) l PROCESS VENT (GW-173) I f MAIN STEAM ( ) AFPT ( ) i CONT. HIGH RANGE 4 Csl
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- m.nssnoo VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION
- . EMERGENCY PLAN JMPLEMENTING PROCEDURE
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NUMBER PROCEDURE TITLE REVISION 01
~'
EPIP-4.02 RADIATION PROTECTION SUPERVISOR CONTROLLING PROCEDURE ##EE (With No Attachments) 1 of.15 I PURPOSE I 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. ~
. . n ,. ,,mmnem ENTRY CONDITIONS Onc. n4F. tit
' JUL 2 41982 Any one of the following :
N Oil .. .lE
- 1. Emergency classification of alert. N' etc.vlsivN
- 2. Activation by another EPIP.
- 3. Any other time the Radiolog1Fn1 Amnesement Director deems it necessary.
VEPCO PROPERTY This document is the property of it Virginia Eiectric and Power Compnn, and is to be returned upon requesi. RME se ver:21eeic" 2e er # tea te v'd12 - reproduce. tran ett or disclose tr ' another any infori:ation contained S r. i. v...., m.e i. L. .
. 0Y PAGE(S): Entire Procedure n AM . 07-02-82 REV. 01 PAGE(S): Entire Procedure DATE: 07-22-82 REV. PAGE(S): DATE:
REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: APP VA ECOMMENCEO APPROVED DA TE
-u 0 1
f,j W gs CHAIRMANSTA TIONNUCLEAR SAFETY r 07- 22.e2 AND OPERA TING COMMITTEE
No.97887210
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l NUMBER PROCEDue . TITLE RE ISION '.! EPIP-4.02 RADIATION PROTECTION SUPERVISOR I CONTROLLING PROCEDURE PAGE i 2 of 15 I - STEP ACTION / EXPECTED RESPONSE ' RESPONSENOTOBTAINED NOTE: IF Health Physics area becomes uninhabitable, relocate Health Physics staff to the OSC or the Emergency Switchgear Room. t NOTE: Record the sequence of events (i.e., transmission of data, dispersement of teams, etc.) as accurately as time allows, including 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 ac extension 2252 b) Radio b) IF radio does not work or E nnot be found, obtain a
- 1) Obtain a portable radio radio from operations or from health Physics Office security.
l.
- 2) Activate EPIP-4.19, Use of Radios for Health Physics -
Monitoring s -
- 3) Contact the TSC
=
! No.s7sa721o I -l 0\
1 NUMBER
; PROCEDURE TITLE REVISION 01 ,
EPIP-4.02
^! RADIATION PROTECTION SUPERVISCR
- CONTROLLING PROCEDURE PAGE 3 of 15
- STEP ACTION / EXPECTED NESPONSE RESPONSENOTOBTAINED
- 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) E mini =um number of person-personnel onsite (minimum nel are not available, acti-of 14 upon 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 Emargency classification
- 5. ESTABLISH DOSE CONTROL l
a) Insure individual is available a) E individual is stationed at to man dose control station dose control, C0 TO Substep e b) E dose control station be- b) IF dose control is habitable, comes un-inhabitable consider continue with this instruc-relocation to the OSC tiod.
- 1) Place a supply of TLD ribbons in the annealing even to minimize residual dose on ribbons
- 2) The manual TLD reader may -
be remsved to another location Iq.v] l I l l.---._-..-.-..___- .
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. e No. 97847219 k NUMBER PROCEDURE TITLE REVISION
~
t 01 EPIP-4.02 RADIATION PROTECTION SUPERVISOR
.l ####
CONTROLLING PROCEDURE l 4 of'15
- l
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOSTAINED
' Is
- 5. (CONTINUED) 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 I_F,need for inplant monitoring E monitoring teams NOT requir-is determined: ed, GO TO Step 6.
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 suspected to be GREATER THAN 1000 MR/HR
- 1) Only 1 individ'ual must be a H.P. technician e) Advise monitoring team as to the location and surveys required Q
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No.97487210 l i ;Qg \_ NUMBER PROCEDURE TITLE .' REVISION
; s <
01 EPIP-4.02 RADIATION PROTECTION SUPERVISCR s CONTRCLLING PROCEDURE PAGE 5 of 15 i'
?
- STEP ACTION / EXPECTED RESPONSE RESPONSENOT,03TAINE0
~
- 6. (CONTINUED) f) Using infor=ation from the above substep b, determine protective gear required:
- 1) respiraters
- 2) protective. clothing
- 3) dosine ry g) Sug: gest routes of entry that nay reduce exposure <
b) Dispa'tch team (s)
- 1) Upon receipt of survey information, transmit i; data to the Radiologi- > \ \
cal Assessment Director
- 7. ACTIVATE ONSITE MONITOR 1 G i
NOTE: Onsite monitoring teams should ' be dispatched upon Alert classification, as specifiad by Radiological Assessment . Director. - IF need for onsite monitoring IF onsite monitoring NOT re-- is determined: quired, GO TO Step 7. '
;j a) Request from Radiological
- Assessment Director the location of desired moni- ,) N toring and the surveys re-quired <
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- i EPIP-4.02 RADIATION PROTECTION SU ERVISOR CONTROLLING PROCEDURE PAGE <
d' 6 of 15 e n
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED .
n .
- 7. (CONTINI[ED) .
b) Request from the Radiological 4 j Assessment Director assessment ' j of radiological hazards in area of requested surveys / t
; ; -p . .,
- 1) If air samples are required ,
- 1) IF no vehicles are cailm '
vehicle should be obtained able, consider the use of ?, to power portable air , the self-contained bsttarf'
- sampler [ ., powered air samplers. {r
>/ .
I c) If transportation 1s< required assist in obtaining a vehicle -
.. 1) IF,necessary, pequests
, assistance fr,om Radio-logical Assessment , ,
Director i ., f d) Activate EPIP-4.15, Onsite Monitoring . I e) Select 2_ individuals per e) 1 did'$ridual may be dispatch , team only 1 need be a H.P. ed W suspected radiation ' technician le? tis are LESS THAN 1010 l MR/HR. ~ f) Use information from above
;<. y' substep b to determine' pro- i. '
r[1 'M' tective gear required: j L p in
- 1) respirators <"
- n. \
- 2) protective el thing
'b; ,,
7 .
- 3) dosimetry >
p ,, I g) Dispatch monitoring team (s) # h) EsEmblish radio communication h) Continue with this instrut h ' with monitoring team (s) IF tion IF radios arc NOT;; a
' ;' g;
rad,ios are available available. .' l a p
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NUMBER PROCEDURE TITLE REVISl0N l; ' - 01
* -'f EPIP-4.02
, . RADIATION PROTECTION SUPERVISOR l'
, CONTROLLING PROCEDURE
, 7 of 15 ii
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTQBTAINED
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- 7. (CONTINUED)
- 1) Upon receipt of survey results, transmit data to the Radio-logical Assistant Director a
f, 8. ESTABLISH ACCESS CONTROL 1 Based on survey results and/or IF che emergency is NOT radio-l' briefing with the Radiological logical in nature, normal sta-7 i Assessuent Director, establish tion access control will be posittve access control over followed. GO TO Step 8. the Auxiliary Building and/or
, /, other high Radiation Areas i ,, -
b
\ ,
a) Establish access control by:
- 1) Requiring H.P. notifica-tion prior to entry s
- 2) Use of Radiation Work Permits as per Section 2 of the Health Physics Manual b)' Suggested access control
- limits .
- 1) Airborne contamination CONC of 0.25 '
EC i OR
- 2) GREATER THAN 1000 DPM 3 per 100 cm 2 0,,R,
- 3) GREATER THAN 1000 MR/HR
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E NUMBER PROCEDURE TITLE RE ISION l' EPIP-4.02 RADIATION PROTECTION SUPERVISOR ! CONTROLLING PROCEDURE PACE
. 8 of 15 1
- STEP ACTION /EXPE:TED RESPONSE RESPONSE NOTOBTAINED
;i *
.' 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) IF offsite monitoring NOT toring teams required, GO TO Step -9.
- 2) Initial location and number of offsit'e teams required
- 3) Assessment of offsite radiological hazards
- 4) Need to issue radiopro-tective drugs to moni-toring teams b) Activate EPIP-4.16, Offsite Monitoring c) Selecte 2_ individuals per team. Only i 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 O-
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.- No. 91881210
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PROCEDURE TITLE REVISION 01 i? EPIP-4.02 RADIATION PROTECTION SUPERVISOR
,! CONTROLLING PROCEDURE PAGE 9 of 15 .- - STEP ACTION / EXPECTED RESPONSE RESPONSENOTQBTAINED
- 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 classifice. tion IF event is NOT radiological in because of a radiological nature, GO TO Step H.
l event, monitor of emergency I response centers. ai Determine frequency of monitoring based upon:
- 1) spread of contamination from service buildings
- 2) Increase or decrease l of efflue E release ,
No.97847210 li NUMBER PROCEDURE TITLE
, REVISION l.;; s
'- ) 01 EPIP-4.02 RADIATION PROTECTION SUPERVISOR CONTROLLING PROCEDURE PAGE 10 of 15 5 - STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 10. (CONTINUED)
- 3) Increase in emergency classification
- 4) Change in plume direction b) Inform Radiological Assess-ment Director as to the habiltability of the emergency response centers
- 11. CONTAMINATED PERSONNEL a) H station personnel are found a) g no station personnel are O contaminated, assign an indivi-dual to ACTIVATE EPIP-4.09, contaminated, continue with this instruction.
Personnel Monitoring and Decontamination
- 12. CONTAMINATED INJURED PERS0h3EL NOTE: E injury is life threatening, GO TO substep d of this step.
E an individual is injured and E individual is found NOT to be requiring transportation to contaminated, CO TO Step g , offsite hospital, determined to be contaminated as per H.P. procedure 3.1.7.1: a) Review personnel surveys from H.P. procedure 3.1.7.1 b) Insure. decontamination prior
' to transportation, is not pratical p c) Inform Radiological Assessment
('V j. Director of need to transport contaminated personnel
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PROCEDURE TITLE REVIS10N 01 V EPIP-4.02 RADIATION PROTECTION SUPERVISOR
.' CONTROLLING PROCEDURE PAGE 11 of 15
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED l
l
- 12. (CONTINUED) d) Activate EPIP-4.20, H.P.
Actions for Transportation of Contaminated Injured , Individual
- 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 survey instru-ment (s)
NOTE: Upon arrival of ambulance dispatch a technician to issue dosimetry e) Inform Radiological Assess-I ment Director upon departure of ambulance
- 13. EVACUATION MONITORING NOTE: E evacuation alarm sounds without prior notification of pending evacuation, GO TO substep c_ of this step.
E informed by the Radiological IJ, evacuation of the station is g Assessment Director of a pending not eminent, GO TO Step E. ( y evacuation: N _ . _ _ . - . ,v,_ -- ,, .. , , , , ,
No.97847210- . l
, NUMBER PROCEDURE TITLE ~A ISION -
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EPIP-4.02 RADIATION PROTECTION SUPERVISOR CONTROLLING PROCEDURE PACE 12 of 15
'E
- STEP ACTIONNXPECTED RESPONSE RESPONSENOTOBTAINED 9
- 13. (CONTINUED) a) Dispatch onsite monitoring team to the parking lot (s) to determine radiation and contamination levels ,
b) Report results of survey to the Radiological Assessment Director c) Activate EPIP-4.21, Evacu-atic'n and Remote Assembly Area Monitoring 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 i
i a) When notified by Radiological a) Il post accident sampling of
~
l Assessment Director of the containment air and/or i need for a post accident Reactor Coolant NOT required, containment and/or reactor GO TO Step 14. coolant:
- 1) Perform in-plant survey to determine dose rate at sample station
- 2) Inform Radiological Assessment Director results of survey
- 3) Initiate preparation of RWP e,
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No. 97847210 M NUMBER PROCEDURE TITLE RE ISION v y EPIP-4.02 RADIATION PROTECTION SUPERVISOR CONTROLLING PROCEDURE PAGE
; 13 of 15 i
'e STEP
'{ ~
ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED ' :i
'l 14. (CONTINUED)
- 4) Activate EPIP-4.22, Post Accident Sampling of Con-tainment Air and/or EPIP-4.23, Post Accident Sampling of Reactor Coolant
- 5) Supply Health Physics coverage during sampling and sample preparation
- 15. SAMPLE ANALYSIS a) Upon receipt of sample a) E not sample analysis
, p. analysis data from effluent received, GO TO Step 5 1_5,.
. j- sampling, or offsite monitoring, relay the in-formation immediately to the -
Radiological Assessment Director
- 16. ASSESS MANPOWER a) When time allows, determine a) E time is not currently need for relief shift and/or available, assign scheduling an increase in manpower to other H.P. personnel SE Assess at a later time, AND GO TO Step M.
- 1) Discuss with Radiological Assessment Director, the projected duration of emergency
- 2) Determine need for in-creased manpower
. - - - - = .
No.97887210
. l' a ;;%,n NUMBER PROCEDURE TITLE REVISION 4 I i 01 hj EPIP-4.02 RADIATION PROTECTION SUPERVISOR CONTROLLING PROCEDURE PAGE 3, 14 of 15
. - STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 16. (CONTINUED)
- 3) Develop relief schedule i
and/or increased staffing schedule
- 4) Present schedule to Radiological Assessment Director for approval
- 5) E approved, activate 5) I_F,NOT approved, GO TO callout of scheduled Step g.
personnel -
- 6) Upon completion of
.O callout, inform Radio-U logical Assessment Director
- 17. RELIEF OF SHIFT a) E a more senior H.P. indivi- a) a) GO TO Step H.
dual arrives ~or if relief is needed:
- 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) IF, emergency condition still a) Radiological Assessment e::1sts: Director declares termination of Emergency, GO TO Step H.
J O.
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No. 97887210 NUMBER-. ] , PROCEDURE TITLE
.f g a REVISION
' . 01 ie '. m.
I EPIP-4.02 RADIATION PROTECTION SUPERVISOR ' CONTROLLING PROCEDURE PAGE 15 of 15 i .
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED 4
t
- 18. (CONTINUED)
- 1) Return to Step 5 and direct the repetition of surveys and radiological sampling to determine radiological hazards onsite
- 19. TERMINATION OF EMERGENCY 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
- 20. ADMINISTRATION .
a) Forward all completed or parti. ally completed pro-l cedures, notes, sample l results and surveys to
- the Radiological Assess-ment Director l 21. PROCEDURE COMPLETION
a) Completed By: ! Date: 1 1 l Time: 1 END
- c Peo. 97847200 VIRGINIA ELECTRIC AND POWER COMPANY p NORTH ANNA POWER STATION
.}k_ EMERGENCY PLAN IMPLEMENTING PROCEDURE ,! i f- ;
4: NUMBER PROCEDURE TITLE REVISION 01
. EPIP-4.03 DOSE ASSESSMENT CONTROLLING PROCEDURE g> PAGE ] (With 4 Attachments) 1 of 13 PURPOSE Provide Dose Assessment Personnel guidance in calculating percent of Technical Specifications 3 Dose rates and Projected Dose due to radioactive release.
USER Dose Assessment Team Leader 3 Radiological Assessment Director ENTRY CONulTIONS Q Activation by EPIP-4.01, Radiological Assessment Director Controlling Procedure.
' o^J "27* VEPCO PROPERTY This document is the property of the JUL 2 41982 -
virginia sl etric and Power Company g and is to be returned upon request. NOR.. No permicsion is granted to publich, LAItbt i<cytSiuN reproduce, tvansnit or disclose to another any infornation contained in this document.
- REVISION RECORD REV. 00 PAGE(S): Entire Procedure DATE: 07-02-82 REV. 01 PAGE(S): Entire Procedure DATE: 07-22-82 REV. PAGE(S): DATE:
REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: O b Q'( APP CWL JECOMMENCEO j i APPROVED _.- e-
/
- DA TE 07 22 82 1
)
{\ - CHAIRMANSTA TION NUCLEAR SAFETY l AND GPERATING COMMITTEE l
j
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NUMBER PROCEDURE TITLE REVISl0N j 01
,j
,EPIP-4.03 DOSE ASSESSMENT CONTROLLING PROCEDURE 1 PAGE
>t 4
2 of 13
;i
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-{h - STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED 1 .
1, ;
- 1. INITIATE PROCEDURE:
a,) BY: DATE: TIME:
- 2. REQUEST BRIEFING a) Request briefing with the Radiological Assessment '
Director as to the emergency classifications, initial off-site release calcuations and O w current monitor reading and meteorological data
- 3. DETERMINE EMERGENCY CLASSIFI-CATION:
a) IF,the F energency is an UNUSUAL a) IF_'the Emergency is a SITE OR EVENT Q ALERT continue with GENERAL this instruction b) Obtain a SAMPLE from the b) IF 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. ' I c) ACTIVATE EPIP-4.11, Follow-up Offsite Release Assessment d) Obtain from EPIP-4.ll, the PERCENT of TECHNICAL SPECIFI-4 - CATION of the release i l Cb l
~' '~
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; NUMBER ! PROCEDURE TITLE REVISION
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01 EPIP-4.03 DOSE ASSESSMENT CONTROLLING PROCEDURE PAGE 3 of 13 ,
; - STEP ACTIOWEXPECTED RESPONSE RESPONSENOTOSTAINED
- 3. (CONTINUED)
NOTE: Any release GREATER THAN 100% TECH SPECS but LESS THAN 1000% TECH SPECS is a NOTIFICATION OF UNUSUAL EVENT emergency AND Any release GREATER THAN 1000% TECH SPECS but LESSsTHAN 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, CO TO Secp 4_ cation is LESS THAN an ALERT, continue with this instruction. g) REPEAT SAMPLING AND ANALYSIS g) H release has not been until release has been terminated, continue with terminated Substep a through h. h) GO TO Step H
- 4. DETERMINE NEED FOR OFFSITE '
MONITORING l NOTE: A minimum of 2 ' offsite monitoring teams should be dispatched on classification of SITE E GENERAL EMERGENCY. t _ . ~ _ . . , . 2 --
l _ _. 4 No.97847210
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NUMBER PROCEDURE TITLE REVISION l EPIF-4.03 DOSE ASSESSMENT CONTROLLING PROCEDURE __ l PAGE
.' o 4 of 13 y
9 i - STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED t
- 4. (CONTINUED) a) E manpower IS available and a) IF manpower is NOT available, i emergency class.ification is GO TO Step 6.
ALERT E GREATER AND Return to this step when man-power is available.
- 1) Discuss with the Radio-g logical Assessment Director the need for OFFSITE MONI-TORING 1
1 ~ b) IF Offsite Monitoring Teams b) IFF Offsite Monitoring Teams need to be dispatched, review NOT required, GO TO Step 6. the following with the Radio-logical Assessment Director
- 1) Meteorological conditions l
to determine placement of the teams
- 2) Offsite Dose Projection to determine need for protec-tive measures for Offsite Team Members
- 5. ASSIGN RADIOPHONE OPERATOR .
j a) E Offsite Monitoring Team (s) a) E Offsite Teams are NOT to i are to be dispatched, continue be dispatched, GO TO Step 6_. with this instruction b) Request from the Radiological b) IF no individual is avail-Assessment Director to assign able, continue with this an individual to man the instruction, returning to I radiophone and to assist as Step 5_, when an inidividual the Dose Assessment Team is available. ~ Member y .. . _ . _ _ . . . __ -- .- c- ==- s --
_ a I . No.97847210 D NUMBER PROCEDURE TITLE REVISION i{ (g
,e EPIP-4.03 DOSE ASSESSMENT CONTROLLING PROCEDURE 01 PAGE 5 of 13 STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 5. (CONTINUED) c) Brief individual as to the c) IF no individual is avail-initial location of the Ele continue with this monitoring teams instruction.
d) Assign EPIP-4.12, Offsite 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 Relcase 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 i
- 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 Term Assessment, emergency did NOT result from to determine RELEASE RATE actual or potential radio-logical release) GO TO Step
- 1) IF release has occurred 12.
continue with this in-struction. 1) In NO release has occurred
- 2) Determine the TIME since GO TO Substep b_.
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 , O TIME (SECONDS) X RELEASE RATE (Ci/sec) = CURIES
=--_---- ._ a:_ _ - . - - . .
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No.97887210 +" - I 4 m NUMBER PROCEbaRE TITLE -
- REVISION -
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.' EPIP-4.03 DOSE ASSESSMENT CONTROLLING PROCEDURE PAGE j!
6 of 13 S
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED I,
- 6. (CONTINUED)
- 4) Log equivalent CURIES on Attachment 1
- 5) Determine the IODINE to XENON RATIO AND Log on Attachment 1 b) ACTIVATE EPIP-4.I1, Follow-up
-O' Offsite Release Assessment to determine DOSE RATE NOTE: IF wind shift occurs during offsite releases, re-evaluate offsite releases, and log results, using a new form for i
Attachment 2.
- 1) Determine from EPIP-4.ll, the DATE, TIME AND STABILITY CLASS used to i project the dose rate
- 2) Determine SITE BOUNDARY DOSE RATE for WHOLE BODY AND THYROID-from EPIP-4.I1
- 3) Obtain from the Emergency '
Communicator, the PRIMARY SECTOR affected by the , release Q _ _ =
no. snmzo b NUMBER PROCEDURE TITLE RE ISION
- EPIP-4.03 DOSE ASSESSMENT CONTROLLING PROCEDURE PAGE 7 of 13
,l
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 6. (CONTINUED)
- 4) Determine INTECATED DOSE by multiplying the time since the start of the release 3 since previous
- assessment by the DOSE RATE:
TIME (HOURS) x DOSE RATE (MR/HR) = INTEGRATED DOSE
- 5) Determine from Radiological N. Assessment Director, the
( ) estimated DURATION OF U' 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, minutes OR 501 MR/HR for 2 minutes (OR S times these levels .
for thyroid) E 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. O
f No. 978SM10 i1 NUMBER PROCEDURE TITLE REVISION I
! 01 -
EPIP-4.03 DOSE ASSESSMELT CONTROLLING PROCEDURE PAGE 8 of 13
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED -
NOTE: IF the Site Boundary dose rate is GREATER THAN 1000 MR/HR Whole Body or 5000 MR/HR Thyroid 0,,R, The projected dose is GREATER.THAN 2_ REM Whole Body or M REM MR Thyroid, notify the Radiological Assessment Director that a GENERAL EMERGENCY condition exists.
- 8) E monitoring data was used 8) E Sample Analysis Data to evaluate offsite dose,
~
WAS used for Offsite Dose update and revise Offsite Assessment, continue with Dose 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 I.
most. current:
- 1) Stability Class
- 2) Site boundary dose race for Whole Body and Thyroid
- 3) Log data on attachment 5 b) Determine the CONVERSION FACTOR from attachment 3 for distance of 2 miles c) Determine DOSE RATE for 2 miles:
SITE BOUNDARY DOSE RATE X CONVERSION FACTOR = DOSE RATE (MR/HR) (2 MILES) d) Log results on Attachment 4_ i
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. 5
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l NUMBER PROCEDURE TITLE REVISION
~~
[l EPIP-4.0 3 DOSE ASSESSMENT CONTROLLING PROCEDURE
- t PAGE
!? 9 of 13 y
- STEP ACTIONNXPECTED RESPONSE RESPONSENOTb8TAINED l .
- 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 Total Projected Dose
- 8. DOSE RATE, INTEGRATED AND PRO-JECTED DOSE AT OTHER DISTANCES a) E Dose Rates, Integrated and/ a) g 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 than 2, 5, or 10 miles, con- 9.
tinue with this instruction b) ACTIVATE EPIP-4.10 to deter-mine X/Q for:
- 1) Site Boundary
- 2) Distance other than 2, 5 t '
or 10 miles c) Obtain from Step 6_ the Site Boundary Dose Rate d) Determine Dose Rate for dis-tance of interest: SITE BOUNDARY X (X/Q) (distance of interest) = DOSE RATE DOSE RATE (X/Q) (site boundary) (distance of interest) e) Log on attachment 4 _. .: u__ _ . - . - - - . - . . - - - - - , ---m'
. _ . .. ._ . . - . .- - . - . . . . . . - ~ . . . . ..
f no.s7ss7 to a NUMBER TROCEDURE TITLE RE ISION
'~
l EPIP-4.03 DOSE ASSESSMENT CONTROLLING PROCEDURE PAGE 10 of 13
-1 i *' - STEP ACTION (EXPECTED RESPONSE RESPONSENOTOBTAINED
- 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 5_ and log the DATE, TIME, AND SECTOR AFFECTED at the time of the Offsite Assessment AND~ Indicate whether Offsite Assessment was done using a monitor reading or
~
Sample Analysis b) Relay the comp'.eted 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 able, GO 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)
- 2) Determine the TIME of the
... actual measurement
- 3) Determine the DISTANCE from the plant where the reading was taken (miles)
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No. 97887210 Y 1
-l ., NUMBER PROCEDURE TITLE REVISION EPIP-4.03 ' DOSE ASSESSMENT CONTROLLING PROCEDURE PAGE 1 4 11 of 13
- STEP ACTION / EXPECTED RESPONSE RESPONSEN0TOBTAINED
- 10. (CONTINUED)
- 4) Calculate the INITIAL TLME of RELEASE:
TIME OF MEASUREMENT
- DISTANCE = INITIAL RELEASE TLME WIND SPEED c) Obtain from accachment 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) g the Actual and Projected different, - data correlate, GO TO Step
- 1) Notify the Radiological i
Assessment Director as to the difference between Actual and Projected Dose Rates
- 2) Determine which set of data l 1s to be used for dose projections
- 11. ASSESS RELOCATION OF MONITORING I TEAM t a) I_F, Monitoring Teams are in a) IF, Monitoring Teams are not i
the field, review current yet dispatched, GO TO Step meteorological data 3 b) Assess the need to relocate ^ monitoring teams c) IF teams are to be relocated c) IF teams are NOT to be re-Eform the Dose Assessment Ecated, CO TO Step 12. Team Member Assist in relocation of Teams
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' % NUMBER PROCEDURE 17TLE REVlSION (s,~/ ~'
) EPIP-4.03 01 DOSE ASSESSMENT CONTROLLING PROCEDURE
.; PAGE
; 12 of 13 4
i
.- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT08TAINE0 l
- 12. CONTINUE ASSESSMENT:
a) IF EOF is NOT manned a) IF EOF is manned GO TO Step 13. OR Il[ the radiological release OR 011 potential release has NOT IF release OR potential TERMINATED, release has terminated, CO TO Step M. Continue with Step 6 through N
- 13. EOF MANNED i
(O)'g . a) Brief Radiological Assessment
'- Coordinator at the EOF of ALL current offsite Dose Projections and the status and location of Offsite Monitoring Teams l b) Inform the Dose Assessment b) IF radio contact cannot l Team Member to instruct the be established continue Offsite Monitoring Teams to contact with monitoring estabish radid contact with teams, relaying inform-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 -
l received from the Radiological ! Assessment Director
- 1) Meteorological Data
- 2) Monitoring Data
- 3) Sample Analysis Data f5
\,_,4' d) Report readiness to the Radiological Assessment Director and continue with this instruction.
i I -~
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- - - - - - - - . - - - -.-.a . . . . . . . . . . . .., .
e No.97887210 j , NUMBER PROCEDURE TITLE REVISION
-; EPIP-4.03 DOSE ASSESSMENT CONTROLLING PROCEDURE
, PAGE
, ' 13 of 13 6-
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOSTAINEO
; /
i 14. ADMINISTRATION a) Gather all procedures, attach-ments and sample analysis records, AND Present them to the Radio-logical Assessmint Director
- 15. TERMINATE EPIP-4.03 a) Completed By:
O< , Date: Time: e i Om-
..-...... . = - - - = - - --. - -.- -- - -
- - - -- - - - ._ _ _ . ,_.__m ,. , _ , ,
e Peo. 97847220 a NUMBER A TTACHMENT TITLE REVISION r
> ) EPIP-4.03 01
' t[ OFFSITE RELEASE i ATTACHMENT WORKSEEET pAgg
' I 1 of 1 E
?
I/Xe ACTUAL RELEASE PROJECTED RELEASE RATIO . DATE TIME I 131 (ci) Xe-133 (ci) I 131 (ci) Xe 133 (ci) t M i l I e / s 4 1 .
- . = . . . - .
. . = . . . . ~ - - .. . .. . . . . _ _ _ _ .
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No. 97887220
; %, NUMBER 4TTACHMENT TITLE REVISION j -
._ - EPIP-4.03 01 2!
0FFSITE RELEASE A TTACHMENT WORKSBEET PAGE 2 1 of 2 i 1 SITE BOUNDARY - WHOLE BODY L STABILITY INTEGRATED TOTAL PROJECTED 3 DATE TIME SECTOR CLASS DOSE RATE DOSE DOSE o O . 9 Y f __ __-_-_-__e -- enn . , - + - - - -n-. ww -- - > - - -e-m.- =~ e - e ~ r,-- - e o,.y .- --+ ,- -
. M2.97887220
~
NUMBER A TTACHMENT TITLE REVISION i
')
2PI?-4.03 01 0FFSITE RELEASE ATTACHMENT WORKSEEET
' PAGE 2 2 of 2 i
4 SITE BOUNDARY - THYROID STABILITY INTEGRATED TOTAL PROJECTED DATE TIME SECTOR CLASS DOSE RATE DOSE DOSE O s - G
. ::=- - -
-; ; - ;- - -- - ;--- - - = - - - - - - - - - --- = - - _= --
I . - No. 97847220
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NUMBER A TTACHMENT TITLE REVISION EPIP-4.03 01 A TTACNMENT PAGE X/Q MULTIPLICATION FACTOR
! 3 1 of 1 i
-5
! .i j STABILITY CLASS t
i ,i 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 1.58E-1 2.30E-2 4.84E-2 6.78E-2 8.38E-2 9.64E-2 1.36E-1 e 10 8.15E-2 1.21E-2 1.54E-1 2.49E-2 3.47E-2 3.99E-2 5.64E-2 4. I l l
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! 4 1 of 1 if
.I i k 1
1
- DATE TIME SECTOR PROJECTED BY:
MONITOR: I SAMPLE: ' j , a WHOLE BODY - j,
,q.
I SITE BOUNDARY 2 - 5 .10 OTHER DOSE RATE ! INTEGRATED DOSE PROJECTED DOSE 1 THYROID t i SITE BdUND).RY 2 5 10 OTHER DOSE RATE s
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No.97887200 VIRGINIA ELECTRIC AND POWER COMPANY 'q NORTH ANNA POWER STATION
., EMERGENCY PLAN IMPLEMENTING PROCEDURE j
i NUMBER PROCEDURE TITLE REVISION i 01 EPIP-4.04 EMERGENCY PERSONNEL RADIATION EXPOSURE { PAGE (With 3 Attachments) 1 of 6 f i PURPOSE l; o g* I Provide to the Emergency Manager an evalution of the need for authorization of emergency exposure i NOT CONT N ggraENT USER Q Q boil. idt Radiologicsl Assessment Dir,ector NO g ggyh0N ENTRYCONDITIONS i-( .e Any one of the following conditions exist:
- 1. Activation by another EPIP.
- 2. Survey results indicate 10CFR20 quarterly limits may be exceeded.
VEPCO PROPERTY This document is the property of the . Virginia Electric and Power Compry and ic to be returned upon request. No permission is granted to publicle, rep;cduce, tran.5mit or disclose in
- another any information contained in thin M mnont.
REVISION AECORO ~' ' REV. Ob . PAGE(S): Entire Procedure DATE: 07-02-82 REV 01 PAGE(S): Entire Procedure DATE: 07-22-82 REV. J. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. , PAGE(S): DATE: APPR APPROVE 0 AfJECOMMENDEO / /
- OA TE b [ # 07-22-32
/ , CHAIRMANSTA TION NUCLlAR SAFETY f l
) .
AND OPERA TING COMMITTEE
_ . . .__ 9 No. 97847210
,~ O~ NUSIDER PROCEDURE TITLE REVIS10N
'p' Yh. -
, 01
- EPIP-4.04 EMERGENCY PERSONNEL RADIATION EXPOSURE PAGE 2 of 6 i - STEP ACTION / EXPECTED RESPONSE RESPONSENOTO8TAINED
- 1. INITIATE PROCEDURE:
a) Initiated By: Date: Time:
- 2. ASSESS NEED FOR EMERGENCY EXPOSURE:
Ths following are guidelines for acceptable authorization of exposure GREATER 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
. . . . _. E _w . . . - - - -. A + - .h e w . c-
No.ornert:o O ( NUMBER PROCEDURE TITLE REVISION 01 f EPIP-4.04 EMERGENCY PERSONNEL RADIATION EXPOSURE PAGE 3 of 6 ' - STEP ACTION /EXPECTE0 RESPONSE RESPONSEN0T08TAINE0
- 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. p 1) Area radiation monitor V .
- 2) Survey - Activate EPIP-4.14, Inplant Monitoring d) Total dose = d) IF, total dose estimated LESS EXPOSURE TIME X DOSE RATE THAN 3_ Rem, C0 TO Step 12_.
- 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: O
. 4 , _ . ._ _- . . .... . ___.. -_. _ _ . _ _ -
No. sta s72:o N NUMBER PROCEDURE TITLE REVISION 01
- EPIP-4.04 EMERGENCY PERSONNEL RADIATION EXPOSURE PAGE 4 of 6 1
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINEO
- 5. (CONTINUED)
- 1) Attempts to rescue versus total exposure of victim b) Damage repair:
- 1) " Mock-up" or " dry run" prior to entry
- 2) Delay entry to allow for decay and/or venti-lation OR establishment of shielding s 6. RECOMMEND EMERGENCY EXPOSURE:
a) Review with Emergency Man-ager alternatives available b) Insure the individual has b) E 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 authori:ation. b) Insure workers receive:
, 1) Proper protective sf clothing
- 7. ^*~~.- . ~- . '-~~.:.. .. .- " , ..n.~
- . - - - - - - - -:--*~- =
i
. No.97847210 1
NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.04 EMERGENCY PERSONNEL RADIATION EXPOSURE PAGE 5 of 6
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTQBTAINED
- 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 1010 R/Hr
[3
~
e) If possible, direct workers t 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) IF, time permits Review attachment 2. Radiation - Effects Versus Whole Body Exposure, with volunteets
- 9. EMERGENCY EXPOSURE FORM:
a) Complete the emergency worker Radiological Exposure Record on . attachment 3 {
'q
s,. -
--- - 1 -. -.---- :
- Peo. 97887210 i
NUMBER PROCEDURE Tl; E RE ISION
! EPIP-4.04 EMERGENCY PERSONNEL RADIATION EXPOSURE PAGE 6 of 6
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTCBTAINED NOTE: IF 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:
a) IF individual has received 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. PROCEDURECOMPLhTED:
a) COMPLETED BY: DATE: TIME: END O V
.__ __ _ _a 1..,,,.
l .. I_$
., NUMBER A TTACi/ MENT TITLE REVISION l
EFIP-4.04 01 EMERGENCY PERSONNEL RADIATION EXPOSURE A TTACHMENT PAGE 1 EMERGENCY EXPOSURE LIMITS 1 of 1 VEPCO ON-SITE EMERGENCY EXPOSURE LIMITS CLASSIFICATION WHOLE BODY (REM) THYROID (REM) Damage Repair Activity - 25 125 Lifesaving Activity 100
- d
- 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 LLMITS Whole Body 1.25 Rem 3.00 Rem ** l Hands / Feet - 18.75 Rem Skin 7.5 Rem (
** IF 5 (N-18) permits l
i I
no.s7ee72 e i ! 1 NUMBER '
/ TTACHMENT TITLE REVISION
/ EPIP-4.04 01 EMERGENCY PERSONNEL RADIATION EXPOSURE A TTACHMENT PAGE i 2 RADIATION EFFECTS VERSUS WHOLE BODY EXPOSURE 1 of 1 l
l h EX?OSURE EFFECTS 0 rem to 20 rem no" measurable effects 20 rem to 50 rem minor blood changes, cellular damage almost completely repaired. l 50 rem to 100 rem further blood changes, loss of appetite. l , 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 about 50% fatalities in 30 days. 600 rem Virtually all exposed individuals will die. s 4 1 NOTE: The effects shown above are based upon:
- 1. An exposure to the entire body.
- 2. An exposure to an entire population.
- 3. No medical treatment for the victims.
O .
----.~.---:--r_-
t Ns.97047220 D. ' NUMBER A TTACHMENT TITLE REVISION EPIP-4.04 01 4 EMERGENCY PERSONNEL RADIATION EXPOSURE A TTACHMENT PAGE 3 EMERGENCY WORKER RADIOLOGICAL EXPOSLTE RECORD 1 of 1 NAME: AGE: YEARS Last First Mid. Init. 4 Soc. Sec. No.: : Current Quarterly Exposure: rem Authorized Emergency Exposure: rem Authorized by (Emergency Manager): Name: at hours On Date: 19 . 1 SELF-READING DOSIMETER RANGE STARTING READING STOP READING DOSE INTEGRATED BY ROENTGEN R TIME DATE R TIME DATE R DOSE R INIT. i l l i . L TLD BADGE NO. NO. CHECK ( ) DOSE INTEGRATED BY ISSUE READ TIME DATE REM DOSE / REM INIT. O _,y-.. %.. %#..._. .. ., . __ , . , _.
. ~ . . . .
No.97847200 VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STAT lON EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.05 RESPIRATORY PROTECTION PAGE (*='ith 4 Attachments) 1 of 4 PURPOSE Guidance for respirator protection. USER Health Physics personnel ENTRY CONulTIONS Activation by another EPIP. 1 O p g O P fe"qT., i y3h iS .s,3 "" prcSerf[g~[ ,- dy...-entg ,,gt!!C 3, *3a YcF**
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##"###ff\ # .g0 PAGE(S): Entire Procedure DATE: 07-02-82 REV. 01 PAGE(S): Entire Procedure DATE: 07-22-82 REV. PAGE(S).: DATE:
REV. PAGE(S): DATE: REY. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: O A APPR 'VA ECOMMENCEO AFPROVED . / OA TE rAA /X/ l ff, f(JL f - I ~ t CHAIRMANSTATIONNU LEARSAFETY AND OPERA TING COM?JITTEE f
Peo.97887210 7 NUMBER PROCEDURE TITLE REVISION f 01 EPIP-4.05 RESPIRATORY PROTECTION PAGE 2 of 4
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTCBTAINED
- 1. INITIATE PROCEDURE:
a) Initiated By: Date: Time:
- 2. DETERMINE NEED FOR RESPIRATORY PROTECTION Consider use of respiratory protection if entering areas:
a) Where high airborne con-p centrations are suspected j but not verified by coni-toring b) Monitoring indicates air concentration is GREATER THAN 25% of MPC using the relationship of: CONC 1 MPC g c) Nexious gases or oxygen deficient air are present
- 3. SELECT PROPER RESPIRATOR NOTE: Fuel celt situations =ay produce a large amount of beta and/or alpha-emitting contaminants not nor= ally seen by analysis.
a) Assess respiratory haza.rds of area to be entered fx 0
No. 97847210 t NUMBER PROCEDURE TITLE REVISION O EPIP-4.05 RESPIRATORY PROTECTION 01 PAGE 3 of 4
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 3. (CONTINUED) b) Review attachment,1,to determine respirator type c) IF MPC man hours are to c) Continue with this instruc-be recorded for individ- tion.
uals, refer to attachment 2_ and attachment 3
- 4. ISSUANCE a) Issuance will follow normal n Health Physics practices I
U 5. STORED SUPPLIES a) Alternate supply of respira- a) Continue with this instruc-tory equipment may be obtained tion. from:
- 1) North Anna Warehouse
- 2) Surry Power Station
- 6. BOTTLE CHARGING a) Normal bottle charging is a) IF Health Physics area is done in the health physics habitable, GO TO Step 7.
area. Should the area become uninhabitable consider:
- 1) Set up cascade charging
^ system in another location S.E
- 2) Obtain compressed, nermal atmospheric mixture, used
- by firefighters G
No. 91881210 NUMBER PROCEDURE TITLE REVISION 0 EPIP-4.05 RESPIRATORY PROTECTION 01 PAGE ' 4 of 4
- STEP ACTION / EXPECTED RESPONSE RESPONSENCT98TAINED
- 6. (CONTINUED)
P.R
- 3) Charge bottles using portable compressor from <
operations department
- 7. PROCEDURE COMPLETION:
a) COMPLETED BY: DATE: TIME: I 3 . ._J
No. 9 7007220
~
NUMBER A TTACHMENT TITLE REVISION EPIP-4.05 01 RESPIRATORY PROTECTION A TTACHMENT PAGE 1 GUIDANCE FOR RESPIRATORY PROTECTION 1 of 2
~
HAZARDS RECOMMEND USE ACCEPTABLE USE
- 1. Oxygen Deficiency Self contained breathing apparatus with full face, pressure demand respirator
- 2. Radioactive Particulate GREATER THAN OR EQUAL Full face respirator with No respirator BUT TO 0.25 BUT LESS THAN particulate cartridge record MPC-hours CONC 10 I f LESS g N 10 hours /
MFC ""* i O GREATER THAN OR EQUAL TO 10 BUT LESS THAN CONC Atmosphere supplying (airline) with full face respirator Full face respirator with particulate cartridge and 400 I record MPC-hours i LESS g N 10 hour / week GREATER THAN Self contained breathing CONC g apparatus with full 400 I 3pg face, pressure demand i respirator ,
- 3. Radiciodines
$ GREATER THAN OR EQUAL Full face respirator with No respirator but ; TO 0.25 BUT LESS THAN iodine cartridge and record MPC-hours i
CONC recordMPC-hoursLg LESS THAN g) THAN 10 hours / week hours / week 10 I MPC GREATER THAN OR EQUAL Atmosphere supplying Full face respirator TO 10 BUT LESS THAN (airline) with full with iodine car- . face respirator .tridge and record n CONC MPC-hours LESS (' 400 I urs/ t MPC week ({g 9 e w.s%- - . . , = . ... em---=. . . = = _ - - = , - e += +
? O-*.-,.--
e s reo.stee7220 NUMBER A TTACHMENT TITLE REVISION EPIP-4.05 01 RESPIRATORY PROTECTION A TTACHMENT PAGE 1 GUIDANCE FOR RESPIRATORY PROTECTION 2 of 2
- 3. (CONTINUED)
Self contained breaching GREATER THAN apparatus with full CONC face pressure demand i respirator 400 E MPC f
- 4. Unknown Atmosphere Self contained breathing apparatus with full face pressure demand respirator
() A log should be kept to insure no individual normally exceeds 10 MPC-Hours / Week airborne exposure e 2-% e O
^ ^
l
. , i no. naemo l
l l NUMBER A TTACHMENT TITLE REVISION EPIP-4.05 01 RESPIRATORY PROTECTION A TTACHMENT PAGE 2 INSTRUCTIONS FOR USING FORM RPM-11.1 1 of 2
~
- 1. All individuals who enter an airborne radioactivity area must have a current Form RPM-11.1 (see Attachment 3). An entry will be
- recorded on the form for each single entry into an airborne radio-activity area. The form expires only af ter an elapse of 7 days beyond the last entry date.
- 2. Enter on Foru RPM-11.1, individual's name and TI.D number. Enter date and time in/out for each entry.
- 3. In column, ICone./MPC, enter the total sum of uCi/ml/MPC from the air sample log for the airborne area. This does not apply to submersion isotopes. Submersion isotopes will be handled as submersion dose. Samples showing both particulate and radioiodine must be separated into two entries if particulate or particulate-iodine respirators were used. If no respirator, air hood or SCBA was used, then the entry may be inclusive due to identical protec-
. d tion factors.
- 4. To compute stay time multiply 40 by the protection factor used (Respiratory Protection Manual Section 4 Table 1; when no protec-tion is used, protection factor = 1) Multiply this product by (1.0-IMPC Frac.). IMPC Fraction is the fractional sum of the time spent in a radioactive airborne area to the allowed stay time for a seven day period. For the first entry this factor will be zero.
Thereafter, it will be the integrated total MPC fraction for the previous entry. Finally, divide this product by IConc./MPC. ,
- 5. Enter the actual time spent in the airborne radioactive area per entry in column 4 (log time in hours).
I t
- 6. To complete MPC fraction, divide the actual time spent in the i airborne radioactive area by the computed stay time for that area.
Multiply this quotient by (1.0-IMPC Fraction). t
- 7. To complete the incegrated total MPC fraction for each entry, add the MPC fraction to the integrated total MPC fraction of the previous entry. NOTE: Permission must be granted from the HP l' Supervisor or his designee to exceed an integrated total MPC fraction of 0.90 and noted in the remarks column. .
- 8. The integrated total MPC fraction is evaluated for any 7 day I
[si
\d period. Multiple entries made on a single day are considered as a "one day" unit.
l l i
. . . . . . - . .-. . . . - .-. .~ ., ... -.
m.steert2o NUMBER A TTACHMENT TITLE REVISION
~)
4Cs\ EPIP-4.05 01 RESPIRATORY PROTECTION A TTACHMENT PAGE 2 INSTRUCTIONS FOR USING FORM RPM-11.1 2 of 2
~
- 9. When an entry is calculated and represents the "eight day" on a form, then the following applies: calculate the MPC fraction per
- steps 3-6. The integrated total MPC fraction for " day eight" will be found by subtracting the MPC fraction due to " day one" from the integrated total MPC fraction on " day seven" and adding the MPC fraction calculated on " day eight". This represents a shift so that the last entry is always " day seven" ar.d includes all entries made during the preceding six day period.
- 10. In remarks section, note RWP and type of respirator used (if any).
- 11. The evaluation of stay time will be performed by the appropriate Asst. H.P. Supervisor or his designee.
O .d e 0
~. . - - . . . . . . . . . . . , ~ . . . . . .
e No.97047220 NUMBER A TTACHMENT TITLE REVISl0N E P I P -4.05 01 STAYTIME WORKSHEETS A TTACHMENT pAGE 3 1 of 1 et i. E I: 5 i Su
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m.orse7:23 NUMBER A TTACHMENT TITLE REVISION O EPIP-4 OS of A TTAC# MENT RESPIRATORY PROTECTION FACE 4 PROTECTION FACTORS 1 of 1 PROTECTION FACTORS PARTICULATES PARTICULATES DESCRIPTION MODES ONLY CASES & VAPORS
- 1. Air Purifying Respira-tor Fullface with parti- Negative Pressure 50 l culate cannister
]
Fullface with iodine Negative Pressure 50 I cannister
- 2. Atmosphere Supplying l Respirators A. Airline Respira- '
tors ; Fu11 face Continuous flow 2,000 B. SCBA l
' Fullface Pressure demand 10,000 ,
9 d i i
No.97847700 VIRGINIA ELECTRIC AND POWER COMPANY j NORTH ANNA POWER STATION v, EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCEDURE TITLE l REVISION
01 , EPIP-4.06 PERSONNEL MONITORING AND I
DECONTAMINATION #### (With 2 Attachments) 1 of 6 PURPOSE Guidance for decontamination of personnel. NOT A CONTROLLED Doc + n1FNT JUL 2 41982 USER NOR , riE Health Physics Technician LAT:.dl m.vtsoN ENTRYCON0lil0NS O-g 1. Activated by another EPIP. i VEPCO PROPERTY Thia decu rent is the-property M Virginia Ei ntric and Po*er Compt
,nd la to to returned upon re+w.i
.No porrir 41cn is granted to publich, reprcduce, tran rit or disclose to another any in.rol ma t ica contained in t h i a d c c ta u n t. .
1 i SAFETY RE.ATED . l REVIS10N RECORD l REV. 00 PAGE(S): Entire Procedure DATE: 07-02-82 REV. 01 PAGE(S): Entire Procedure DATE: 07-22-82 REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: n.,- REV. APPROVA ECO PAjiE(S): NDED APPROVED , DATE: DA TE J 07-22-82 l [ CHAIRMANSTA TION NUC AR SAFETY AND GPERA TING COMMITTEE l b
No. 978 87210
- i
, NUMBER PROCEDURE TITLE REVISION i
{~~ 01
- j. EPIP-4.06 PERSONNEL MONITORING AND i, DECONTAMINATION pAGE ll 2 of 6
'i
'l i
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED i
', 1. INITIATE PROCEDURE:
a) BY: DATE: TIME:
- 2. OBTAIN MONITORING EQUIPMENT:
a) Obtain an RM-14, with an a) Alternate supply of equipment H.P. 210 probe, from the located in the High Range H.P. office and proceed Calibration Facility located immediately to the Personnel in the Turbine Building. Change Area l
./ 1) E the area is habitable, 1) E 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
-f p\ is injured and requires NOT injured, GO TO Step 4.
first aid: O
= .,. . . - . - - . = - . - . . . . . - - . . . . - . - . . . . . - .-
_ _ - . . . - . _ - - - . - . . - - . . . - ~ . _ _ _ . - - . - . . . - _ - _ - - . - - -. - .
. . ~ . . . . - - - . . . . . L - . -
-*l l *s no.sreest10 I
, >v NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.06 PERSONNEL MONITORING AND DECONTAMINATION PAGE
', 3 of 6 I l
- - STEP ACTION / EXPECTED RESPONSE RESPONSENOT OBTAINEO I
- 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 su vey, 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, CO TO Step .5_.
1
- 1) Have individual clean nose with wet cotton swabs l
- 2) Have individual blow nose frequently
- 3) Record swab reading on Attachment 1 NOTE: Cease decontamination _i_f, f skin becomes reddened OR, bleeding.
NOTE: Obtain permission from Radiation Protection Supervisor to apply potassium permanganate. CL
-e - - . . -~ - * -
, No.97847H0 h NUMBER PROCEDURE TITLE REVIS10N ij '
' 01
;j -
EPIP-4.06 PERSONNEL MONITORING AND ti DECONTAMINATION PAGE l 4 of 6
- STEP ACTION / EXPECTED RESPONSE A
RESPONSE NOTO8TAINED
- 5. DECONTAMINATE:
a) REMOVE contaminated CLOTHING from individual b) E CONTAMINATION problem is WIDESPREAD:
- 1) Shower using soap and water, keeping radie-active material away from body openings
- 2) Dry thoroughly, placing towel in plastic bag or
), contaminated material i barrel
- 3) Repeat survey and log data on Attachment 1,
- 4) E contamination still 4) g TO Step 6 exists repeat showering and surveying, recording survey data on Attach-ment 1
- 5) E contamination still 5) g E Step 6_
exists, select most highly contaminated areas and start decon-tamination for localized areas. c) If contaminated area is c) g TO Substep d. LOCALIZED, isolate the area and perform the following actions. Survey and record data on Attach-ment I after each step
- p. 1) Clean using soap and -
( water
- 2) Apply abrasive soap and water
.- _ . , . _ . - . _ ~ _ . , _ _ _ _ _ _ _
.. -- - . ~ . ~ ..- . . . .
1
. No. 97887210 'l r -
Q ~, . NUMBER PROCEDURE TITLE REVISION 01
]
EPIP-4.06 PERSONNEL MONITORING AND DECONTAMINATION PAGE 4 i 5 of 6 I
- - STEP ACTION / EXPECTED ESPONSE RESPONSE NOTOBTAINED
- 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 contamination is found d) CO TO Substep e.
in EYES or OPEN WOUND: bb V 1) Flush copiously.with water
- 2) Record contamination data on Attachment 1 ,
- 3) Notify Radiation Protec-tion Supervisor e) If contamination is found e) GO, 3 Step 6 in hair:
l 1) Shampoo, isolating face and shoulders
- 2) Consider cutting or shav-ing the affected area if
! contamination cannot be l removed
- 6. CONTAMINATION LIMITS:
a) IF individuals are deconned a) IF individual cannot be i to LESS THAN 100 CPM, above deconned to LESS THAN 50 background, they may be CPM above background contact released Radiation Protection Supervi-sor and request assistance. > - = .
r--- - --- _ . _ _ _ _ _ ___. .. _ _ . _ . . _ . . _ . . . . _ _ _ _ no.sraerano NUMBER PROCEDURE TITLE REVISION EPIP-4.06 PERSONNEL MONITORING AND i DECONTMINATION PAGE 6 of 6
.1 l
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOSTAINED
- 6. (CONTINUED) 1) Individual may be released if contamination is found to be fixed and follow-up
' decontamination and/or dose evaluation is made.
- 7. INTERNAL CONTAMINATION:
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:
l a) Return all completed survey results to the Radiation Protection Supervisor
- 9. PROCEDURE COMPLETION:
a) COMPLETED BY: DATE: TIME: l l
/
'~ ~
7 . _ . __ _ .i._ J-_-.._. _
. - . . . . **~~y . _ , ,
.__ _ . .- - - . - ~ . - .
_) , . , . . . . .. . . z..- . . .. .. .; 4 _ . .. . . . s . . . . - . Poe. 97847220
-l [.
, ) NUMBER A TTACHMENT TITLE REWS10N
; .j- EPIP-4.06 01
! F PERSONNEL DECONTAMINATION RECORD A TTACHMENT PAGE 1 1 of 1 i .
*l
- 1. Individual Contaminaeed:
- 2. TLDi: Date: TIME: RWP#
- 3. Contamination Occurred in (Area):
- 4. While Involved in (Type Work):
l
- 5. Personal Clothing or Equipment Contaminated: YES NO
- 6. Items (List):
- 7. Disposition of above listed items:
- 8. It internal contamination is suspected, the individual should be given a whole body count.
- 9. Internally Contaminated? YES NO IF YES NOTIFY RADIATION CONTROL SUPERVISOR IMMEDIATELY!
- 10. Body Areas Externally Contaminated: I
- 11. Decontamination:
SURVEY INSTRUMENT DECON TIME SKIN AREA & PROBE READING AGENT
- INITIALS i
l l Health Physics Remarks: Health Physics Clearance and Signoff By Date l .. .
.r.-.,.g_.%gaw rme-
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, NUMBE.1 A TTACHMENT TITLE REVt310N EPIP-4.06 01 PERSONNEL SURVEY WORKSHEET A TTACMMENT PAGE ! 2 1 of 1 .l
- 1 I am l ke h $/
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. e No,s7ss7200 8
VIRGIF n ELECTRIC AND POWER 00MPANY
~- -
_ l IRTH ANNA POWER STATION
\f, EMERGENCY PLAN IMPLEMENTIN3 PROCEDURE NUMBER PROCEDURE TITLf REVISION 01.
EPIP-4.07 PROTECTIVE MEASURES
' PAGE (With 5 Attachments) 1 of 7 PURPOSE Supply guidance to Radiological Assessment Director to promptly as'sess projected doses to population of risk and to recoc: mend protective actions to the Emergency Manager.
NOT A CONTROLLED D O C 'H FS'r JUL 2 41982 USER " " " ^ Radiological Assessment Director or Senior Health $yN2cNrNnnel Onsite. ENTRY CONDITIONS Any of the following:
- 1) Activation by EPIP-4.01, Radiological Assessment Director Controlling Procedure.
i VEPCO PROPERTY This document is the property of trie, Virginia Electric and Ponor Co:npziy T l ., and in to be returned upon request.(
- No permis91cn is granted to publish. '
I reproduce. ' tcn : !t or disclosc to another any i ciorria t i'On .cantained . 9 this docu.nent, s
.s ,
REVISION RECORD
- REV. 00 PAGE(S)
- Entire Procedure DATE: 07-02-32 REV. Of PAGE(S): Entire Procedure DATE: ;07-22-82 REV. PAGE(S): DATE:
REV.} PAGE(S): DATE: REV. PAGE(S): 1 DATE: REV. PAGE(S): DATE: REV. ~ PAGE(S): DATE: p ..\ APPROVAL R MMENDED APPROVED - / DA TE i
; [, [ 07- 22-82
/ --
m CHAIRMANSTATIONNUC EARSAFETY AND QPERA TING COMMITTEE
'{ . .
- 7. . . - _ _ . .. _ _ . . . . . _ . . _ .__.-.~s j s j No. 97a 87210 a
\ NUMBER PROCEDURE TITLE MVISION
' ~ O I. -
i EPIP-4.0 t PROTECTIVE MEASURES l PAGE 2 of 7
. ?
- STEP ACTIONNXPECTED RESPONSE RESPONSENOTOBTAINED l
l
- 1. INITIATE PROCEDURE: "
.g a) Initiated By: .
Date: ,, Time: '
~
- 2. PROTECTIVE ACTION GUIDELINES FOR INITIAL ASSESSMENT OR FOR CON-TINUGUS RELEASE a) E, this is an INITIAL ASSESS-MEST OR 1
M . - IF the' radioactive release is J a CONTINUOUS RELEASE Determine che distance, from EPIP-4.03, Dose Assessment Controlling Procedure, which the projected dose exceeds: , j-3-
- 1) 2.0 REM Whole Body OR 12.0 1) IF projected dose is LESS REM Thyroid THAN 2.0 Rem Whole body _0R R 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 TEAN 0.5 Rem Whole Sody 3 1.0 Rem Thyroid, recommend offsite Protective Act-ions, GO TO Step ,5_. V) l'. view PROTECTIVE ACTION -
' IDELINES in Attachment 1 ~
T l c) Atermine.the affected sector l from che E=ergency Communi-cator C). ^ '
- 1) Determine. the current wind ,
direction '% t, 3 l . o , -
-, --. J- - -
l } No. 97887210 l'
\ NUMBER PROCEDURE TITLE REVISION IQ\
>- EPIP-4.07 PROTECTIVE MEASURES 01 PAGE 3 of 7 s
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED e --
- 2. (CONTINUEL)
NOTE: Wind direction is given in the direction the wind is coming FROM.
- 2) Affected sector is 180* ,
from the wind direction
- 3) Review Sector Map in -
Attachment 5_ gg d) Recommend PROTECTIVE ACTIONS t V) for PRIMARY SECTOR (Substep ~c) AND .the two adjacent sectors e) C0 TO Step 5_
- 3. PROTECTIVE ACTION GU'IDELINES FOR A PUFF RELEASE a) H the release is a PUFF a) GO TO Step 5, release 4 9.R .
! Radiological release is probable, but has,NOT yet occurred, continue with this instruction. b) Review EPIP-4.03, Dose Assess-ment Controlling Procedure . l c) IF a review of data from Sub- c) GO TO Step 5 step b indicates OFFSITE EXPOSURE to be GREATER THAN: l . 0.5 REM Whole Body C'L iv l
g .. .s. ...a. , -.- - -- . . - - - . - . -- - . - - - - - . - - - ~ -- - - - - - - - - - - - m i .- b . . No. 97887210 a l' ,. NUMBER PROCEDURE TITLE REVISION O1
. EPIP-4.07 PROTECTIVE MEASUREh PAGE 4 of 7
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 3. (CONTINUED) 9LR 1.0 REM Thyroid n
Continue with this instruction
- 4. CALCULATE NEED FOR EVACUATION '
OR SHELTERING a) Letermine need for EVACUATION OR SHELTERING based on WHOLE BODY EXPOSURE
- 1) Complete Attachment 3,
- 2) Using information f' rom Attachment 3 determine the PROTECTIVE ACTIONS to be recommended from the following:
IF THEN
- 1. Projected dose LECS 1. No action THAN _03 rem
- 2. Saeltering dose LESS 2. Shelter THAN 2.0 rem i 3. Sheltering dose GREATER 3. Evacuate
( THAN 2.0 rem, and Evacu-l. ation dose LESS THAN Sheltering dose
- 4. Sheltering dose GREATER. 4. Shelter i
THAN 2.0 rem, and Evacu-l ation dose GREATER THAN j OR equal to Sheltering' t dose
- O l
i
No. 978 8410
. : H '; '
NUMBER PROCEDURE TITLE REVISION l 01 4 EPIP-4.07 PROTECTIVE MEASURES PAGE 5 of 7 I i I - STEP ACTION / EXPECTED r?ESPONSE RESPONSE NOTOBTAINED
- 4. (CONTINUED) b) Determine EVACUATION OR SHELTERING based on T WROID 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 following: ,
IF THEN
- 1. Projected thyroid dose 1. No ac* ion LESS THAN 1.0 rem
- 2. Sheltering dose GREATER 2. Shelter THAN 1.0 rem but LESS THAN M rem
- 3. Sheltering dose GREATER 3. Evacuate then 12 rem and evacu-
, ation7ose LESS THAN sheltering dose
- 4. Sheltering dose GREATER 4. Shelter THAN 1,2, 2 rem and evacu-ation dose GREATER THAN l M equal to sheltering dose
(' . . . l l
__t-_ <_ -_ . _ - - .. . _ . _ . _ - _ _ . . _ . . . . _ _ _ . _ - No. srasra to
- 3 ~
NUMBER PROCEDURE TITLE REVISIGi; l 01 j EPIP-4.07 PROTECTIVE MEASURES PAGE 6 of 7
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINEO
- 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 For thyroid exposure recom- [s mend sheltering in closed buildings.
.gR, 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 MANiGER a) Provide RECOMMENDATIONS from Step 2 g Step 5,to the Emer-gency Manager b) Review with the Emergency-
- Manager, assumptions made in l
Step 2,OR Step 5. Answer any questions concerning calcu-lations l l 7. RETURN TO CONTROLLING PROCEDURE i
$ a) Upon completion of this pro-t cedure, RETURN to EPIP-4.01, *" Radiological Assessment Direc-tor Controlling Procedure l
l
No. 97047210 l l 3 , NUMBER PR0uEDURE TITLE ~~REVI$10N
- )
,I L
01 EPIP-4.07 PROTECTIVE MEASURES
$ PAGE
; 7 of 7
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 8. PROCEDURE COMPLETION a) COMPLETED BY:
DATE: TIME: E I I i l l l l END 7,__ L ___ . _ . . a - .. . . . - - = _ . _. ,
. - - . . . . .. - . . . - a-_. . . . _ . _ - _. .- ._ ._ . . . . .. ___ __ . _ . _.I No.97887220 NUMBER
('"'r - EPIP-4.0: ATTACHMENT TITLE REVISION 01 STATE OF VIRGINIA A TTACHMENT PAGE 1 PROTECTIVE ACTION GUIDELINES 1 of 1 i i S OFFSITE: PROJECTED DOSE PROTECTIVE ACTIONS
'Less than 0.5 rem whole body OR No protective action necessary IJ[
Less than 1.0 rem thyroid radiological situation is unstable, consider recommendation of citizen - alert. 0.5 - 2.0 rem whole body 0]L Recommend sheltering of public 1.0 - 12.0 rem thyroid Greater than 2.0 rem whole body Ojt Recommend evacuation of affected 12, rem thyroid sectors ONSITE: l l l PROJECTED DOSE PROTECTIVE ACTIONS Less than 1.0 rem whole boay C@t Recommend sheltering Less than 5.0 rem thyroid Greater than 1.0 rem shole body C@t Recommend site evacuation i f Greater than 5.0 rem thyroid l
= - . . . . . .
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k NUMBER A TTAC# MENT TITLE REVISl0N ! 'd . '] EP IP-4.07 01 A TTAC# MENT THYROID EXPOSURE VERSUS IODINE CONCENTRAT EN PAGE 2 l of 1 9a
;; i r 1 . r
; INHALATION
* ' DOSE COMMITMENT n
j 15 REM n 10 REM 2 /
; ,' ,' , 5 REM
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No.97887220 I ,- 4 , NitMBER ~ - < A TTACHMENT TITLE REVISION
>Y' EPIP-4.01 01 EVAUCATION VERSUS SHELTER
, A TTACHMENT PAGE 3 WORKSHEET 1 of 2
- 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 distance or point of interest MR/HR
- 3. Estimation of RELEASE DURATION HOURS
- 4. PROJECTED DOSE = REM 1010
- 5. WIND SPEED MPH'
- 6. PLUME TRAVEL TIME = DISTANCE (miles) EOURS WIND SPEED (mph)
- 7. Time SINCE OR UNTIL, BEGINNING OF RELEASE a) E RELEASE HAS BEGUN:
TIME RELEASE HAS BEEN IN PROGRESS HOURS b) E RELEASE WILL BEGIN: RELEASE WILL START IN HOURS l 8. TIME UNTIL EXPOSURE BEGINS: a) d RELEASE HAS BEGUN: Item 6 - Item 7a HOURS b) IF RELEASE WILL BEGIN: Item 6 + Item 7b, HOURS
- 9. EVACUATION WEATHER CONDITIONS:
NORE\L ADVERSE
- 10. Use distance and weather conditions to obtain ESTIMATED EVACUATION TIME from Ateachment 4 HOURS
~
Peo. 97007220 fb % ' NUMBER A TTACHMENT TITLE REVISION EPIP-4.07 01 EVAUCATION VERSUS SHELTER A TTACHMENT PAGE 3 k'ORKSHEET 2 of 2
- 11. EXPOSURE TIME Evacuation Time - Time until exposure begins HOURS NOTE: E 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 RELEASE DURATION TIME REM
- 14. EVACUATION DOSE:
EVACUATION EXPOSURE PERIOD X DOSE RATE 1000 REM
- 15. SHELTERING DOSE:
PROJECTED DOSE x STRUCTURE SHIELDING FACTOR
- REM l
- NOTE: FOR WHOLE BODY = 0.9 THYROID = 0.65 l
l l i r
\j END
Ns.97887220 NUMBER A TTACHMENT TITLE REVISION ( EPIP-4.0 " 01
; A TTAC# MENT EVACUATION TIMES FOR NORTH ANNA POWER STATION FAGE 4 1 er 1 4
i AREA TIME _ i EVACUATION EVACUATION TIME NORMAL TIME ADVERSE CONDITION CONDITION Total Area ' Within 2-Miles . 2:15 2:15 WITHIN 2-5 MII.ES Louisa Co. 2:15 2:15 Spotsylvania Co. 2:15 2:15 l WITHIN 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 C\ V
~
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~
NUMBER A TTACHMENT TITLE REVISION i \ EPIP-4.07 01
.j NORTH ANNA SECTOR MAP A TTACHMENT PAGE 5 1 of 1 t
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i l VIRGINIA ELECTRIC AND POWER COMPANY
? NORTH ANNA POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE i NUMBER PROCE00RE TITLE REVISION
- 01 EPIP-4.08 .
INITIAL OFFSITE RELEASE ASSESSMENT PACE (With 7 Attachments) 1 of 11 PURPOSE
- 1) Initially assess consequ'ences of offsite releases or potential offsite, releases.
USER Radiological Assessment Director OR Members of Radiological Assessment Team. ENTRY CONDITIONS NOT A GUN t NULLLu DOCUMENT V '
"UL 2 4 82
- 1. Activation from another EPIP.
NO f n . t i' 0, R. LATESI HtvlSIUN
- 2. Entry from other EPIPs E VEPCO PROPERTY
- 3. Direction of the Station Emergency Managenia document is the proper ty 01' the Virginia E19etric and Power Compsny and in to lm returned upon requeat.
tio perah 'ica b: granted to publish. re pr o<iilci, trananit or disclose L.* SAF < another any infor%ation contained D. t his do a.ai.nt. , REVISION RECORD REV. 00 PAGE(S): Entire Procedure - DATE: 07-02-82 REV. 01 PAGE(S): Entire Procedure DATE: 07-22-82 REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: O APPROV 1 RE OMMENCEO APPROVED , _ / i 07-22-82 DA TE
}/
- CHAIRMANSTATIONNUCLE RSAFETY AND OPERA TING COMMITTEE
,--.1-. - -- -.- - .. . .-.- - .
. __.i g
} , . No.97847210 NUMBER PROCEDURE 77TLE REVISION 01 7-s_ EPIP-4.08 INITIAL OFFSITE RELEASE ASSESSMENT PAGE 2 of 11
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED t
- 1. INITIATE PROCEDURE:
a) BY: DATE: TIME:
- 2. DETERMINE EMERGENCY CLASSIFICATION:
a) )); the Emergency is an Unusual a) JJ; a Site Cg! General Emer-Event Cg! Alert, continue with gency, GO TO Step 4. this instruction
- 3. DETERMINE PERCENT g TECHNICAL SPECIFICATION:
\)
NOTE: Evaluation of percent technical specifications in this Step makes assumptions 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) Request from the Emergency Manager, placement of an individual to observe monitor in alarm and report increase or decrease in readings. c) Obtain HIGHEST CPM, above c) IF monitor is offseale OR background, of monitor in not functional, GO TO Step 4 Substep a and log on Attach-ment 1
\s.-
~ . . - ., -
.~. . . . _ . _ . .~ -. -. - - . . .--
e res.97887218
~ '
NUMBER PROCEDURE TITLE - REVI!!DN _ 01 EPIP-4.08 INITIAL OFFSITE RELEASE ASSESSMENT PAGE 3 of 11
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINEO
- 3. (CONTINUED) d) Determine release rate:
- 1) Gaseous 1) Continue with this instruction.
CFM
- 2) Liquid - request the 2) GO 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.
e) Determine the percent Tech-
- e) IF monitor of interest is NOT nical Specification from the listed in the attachments, g the appropriate FIGURE in TO, Step 8_, for follow-up Attachment 2, and log on assessment.
Attachment 1 i,*. NOTE: IF the percent of technical specification is GREATER THAN 100% but LESS THAN 1000%, UNUSUAL EVENT emergency condition exists. S.R H percent technical specifications is GREATER THAN 1000% but LESS THAN 50 MR/HR, ALERT emergency condition exists, i i l ( f) Report results to the _ _ _ l Emergency Manager l O LL - i i
. _ . . ...- -. . . . . . ~ _ . . . - . , ~ . .
r. Po. 97847219
)j 4
NUMBER PROCEDURE TITLE REVISION
.4 01 EPIP-4.08 INITIAL OFFSITE RELEASE ASSESSMENT PAGE 4 of 11
* - STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINEO 1,
t
- 3. (CONTINUED) g) E the percent of Tech Specs g) IF the percent Tech Specs are is GREATER DIAN 1000% , LESS THAN 1000% GO TO Step 8_.
8 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 individzal to observe the monitor in alarm and report increase or decrease in readings b) E release path through b) E NORMAL RANGE MONITORS are PROCESS VENT, VENT VENT OFFSCALE, G_O, 3 Substep c. 3 AIR EJECTOR AND NORMAL RANGE monitors are ONSCALE: NOTE: IF AIR EJECTOR is diverted to containment, NO release from this pathway should be considered. s k j
. . . . , .. - - - , , , - - + ..
m,*tema ,.*%
i _ .. _ _ _ No. 97847210
?
L NUMBER PROCEDURE TITLE REVISION j
;i,
! 01 l EPIP-4.08 INITIAL OFFSITE RELEASE ASSESSMENT PAGE 5 of 11 1
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 4. (CONTINUED)
- 1) Obtain the NUMBER of the MONITOR OF INTEREST and log on Attachment 3:
VENT VENT A (VG-104) 2R VENT VENT B (VG-113) pR PROCESS VENT (GW-102) OR AIR EJECTOR (SV-121,221)
- 2) Obtain the CPM, above background, for MONITOR OF INTEREST CPM
- 3) Obtain, from the Emergency Communicator the STABILITY CLASS AND WIND SPEED STABILITY CLASS l
WIND SPEED
- 4) Obtain CONVERSION FACTOR from Attachment 6, using the Monitor of Interest '
and Stability-Class CONVERSION FACTOR L
-. . . , - . .gy . . . - - y-, - -. . - . , . , , - , , , . , . . . -
.%.- . ,,yw-, , , , . - - - - - - - -.w- , ~,
,, No. 97887210
'il NUMBER _ PROCEDURE TITLE REVISION
} 3 01 i
. .,, EPIP-4.08 INITIAL OFFSITE RELEASE ASSESSMENT i'
PAGE I 6 of 11
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED 4 4. (CONTINUED)
- 5) Determine SITE BOUNDARY DOSE RATE:
CPM X CONVERSION FACTOR MR WIND SPEED "E 1 b) Log MR/HR on Attachmeytt 3
- 7) Go, 3 Step 5_
c) E the release path is c) E HIGH RANGE MONITORS are through the PROCESS VENT NOT onscale, 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_.
l are onseale: I M IF release is through the MAIN STEAM SYSTEM GO TO Substep d_. 1
- 1) Obtain the NUMBER of the '
MONITOR OF INTEREST and ' log on Attachment 3_ PROCESS VENT (RM-GW-173) 0.R VENT VENT A (RM-VG-174) OR t l VENT VENT B (RM-VC-175)
- 2) Obtain from operation the MR/HR of monitor of interest MR/HR
^
- -. ,. - .- .-. .. . - - ' T .- ' .-.. T ::" : - -
1 No.97887210 _
\ NUMBER PROCEDURE TITLE REVISION
' 01 EPIP-4.04 INITIAL OFFSITE RELEASE ASSESSMENT PAGE 7 of 11 k
, - STEP ACTION / EXPECTED RESPONSE RESPONSE NOT08TAINE0
- 4. (CONTINUED)
- 3) Convert MR/HR to pCi/cc using Attachment 5 -
uC1/cc
- 4) Obtain from the Emergency Communicator the STABILITY CLASS and WIND SPEED STABILITY CLASS WIND SPEED b\ 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) CO TO Step 5 l c) IF, release path or potential c) GO O TO Step 5, l release path is through the STEAM SAFETY RELIEF VALVES OR through the AUXILIARY FEED-WATER PUMP TURBINE EXHAUST (AFPT), continue with this instruction 1
l
_ ~~ .-_ _ _ . - ~ _ _ .._ . l No. 97847210 l (D-- NUMBER PROCEDURE TITLE RE ISION t
! EPIP-4.08 INITIAL OFFSITE RELEASE ASSESSMENT s PAGE 8 of 11
+
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINEO
- 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 O, R_
Main Steam Unit #2 RM-MS-270 RM-MS-271 RM-MS-272 9 OR-- Auxil'iary Feedwater Pump Turbine Exhaust (AFPT) . 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 Communicator the STABILITY CLASS AND WIND SPEED
- 3) Obtain from Attachment 6_ the appropriate
,')
CONVERSION FACTOR for the d -- MAIN STEAM monitor and/or the AFPT monitor
i l __, No. C7887210 i ! i 1
'. f]..
NUMBER PROCEDURE TITLE RE ISION
, EPIP-4.08 INITIAL OFFSITE RELEASE ASSESSMENT PAGE 9 of 11 9
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 4. (CONTINUED)
~
- 4) Obtain SITE BOUNDARY DOSE RATE:
MR/HR (MONITOR) X CONVERSION FACTOR , MR WIND SPEED HR NOTE: _IF_ F release is through BOTH the Main Steam AND the Auxiliary Feedwater Pump Turbine Exhaust, the results from both moni-tors are ADDITIVE. O L}. 5) Log MR/HR on Attachment 3_
- 5. DETERMINE SITE BOUNDARY THYROID DOSE RATE a) Initiate EPIP-4.12: OFFSITE ENVIRONMENTAL MONITORING INSTRUCTIONS and continue with this instruction.
- b) Log results on Attachment 4 b) If results utavailable at the present time '
continue with this procedure for whole body dose rate and determine thyroid dose rate when l data becomes available
- 6. DETERMINE DOSE RATE AT 2, 5 AND 10 MILES:
a) Obtain the STABILITY CLASS from Step 4 and SITE BOUNDARY DOSE RATE for Whole Body and Thyroid
) from attachment 3 and 4-d
~ * ^
- l. , _ . - . . . . . . . . - . - - . . :. ~
. _ . _ . - . . . . . - _ - - _ . . ----~--*
Peo. 97887210
- lW . NUMBER PROCEDURE TITLE REVISION
* \ 01 EPIP-4.08 INITIAL OFFSITE RELEASE ASSESSMENT
-{ . PAGE 10 of 11 t
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTCBTAINED
. - 6. (CONTINUED) 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 n NOTE: E site boundary dose rate is GREATER THAN 1.0 REM /HR k' hole Body OR_ S.0 REM /HR Thyroid, notify the Emergency Manager that a GENERAL EMERGENCY condition exists. .
pR E site boundary dose rate is GREATER THAN 50 MR/HR for 30 minutes l
. 500 MR/HR for 2 minutes k' hole body (OR 5 times these levels to
[ the thyroid) l Notify the Emergency Manager that a SITE EMERGENCY condition exists. I a) Report results of attachment 3 OR 4 immediately to the l Emergency Manager l
- v i
. . _ . . . . ~ . . .. .
._.__-. . . - - - - - - . . - . - - - . .-- -. - - - - - - > I l e-No. 97887210 NUMBER PROCEDURE TITI.E REVISION k.I EPIP-4.08 INITIAL OFFSITE RELEASE ASSESSMENT , PAGE
, j 11 of 11 ~ ; i - STEP ACTION / EXPECTED RESPONSE RESPONSENOT08TAINE0 i
- 8. RETURN TO CONTROLLING PROCEDURE a) Upon completion of this pro- ,
cedure, return to EPIP-4.01, Radiological Assessment Director Controlling Procedure
- 9. PROCEDURE COMPLETION:
a) COMPLETED BY: DATE:
, TIME:
l I b V. END
., _ r.._ y ,,_y g-, , - , , , , , --.-e - - - - . . - . ,, --
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j ... i I NUMBER A TTACHMENT TITLE REVISION l'l EPIP-4.08 01 l OFFSITE WHOLE BODY DOSE RATE e A TTACHMENT DATA SHEET PAGE 1 3 1 of 1 i
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No. 97887220 NUMBER A TTACHMENT TITLE REVISION EPIP-4.08 01 j CONVERSION FACTORS A TTACHMENT PAGE 6 1 of 1 CONVERSION FACTORS Stability Class VG-104 VG-113 GW-102 SV-121, 221 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 37)
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 I C \ 1.71 E+2 1.30 E+2 3.69E-1 l Main Auxiliary Feed l Steam Pump Turbine Exhaust A 4.82 E-1 8.53E-1 B - 4.32 E+0 7.65E+0 C 1.57 E+1 '2.77E+1 D 4.63 E+1 8.21E+1 E 9.06 E+1 1.60E+2 F 1.90 E+2 3.37E+2 G 3.66 E+2 6.49E+2
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No. 97887220 i i -
, NUMBER A TTACHMENT TITLE REVISION S EPIP-4.08 01 X/Q MULTIPLICATION FACTOR A TTACHMENT PAGE 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 O
5 1.58E-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-1 2.49E-2 3.47E-2 3.99E-2 5.64E-2 i i I I i t t l l l l v)
._~ .. . - - . _
+
. ?
No. 97 P 87200
, VIRGINIA ELECTRIC AND POWER COMPANY , NORTH ANNA POWER STATION R[j D EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCEDURE TITLE REVISION s 01 EPIP-4.09 SOURCE TERM ASSESSMENT PAGE (With 4 Attachments) 1 of 9 PURPOSE Provide guidance and data to Dose Assessment Team to more accurately predict offsite releases.
NOT A CONTROLLED Dqr. 'P1ENT JUL 2 41982 NR. ng USER LATES'l HEVISION Dose Assessment Team Members. ENTRY CONDITIONS f'] . Upon activation of EPIP-4.03.' Dose Assessment Controlling Procedure. VEPCO PROPERTY This document is the property of the Virginia Electric and Power Comp my and is to be roturned upon requast. No permission is granted to publish. reproducc. tranceit or disclose to another any information contained in i this document. SAFETY,4EIMED BEVISION RECORD REV. 00 PAGE(S): Entire Procedure DATE: 07-02-82 REV. 01 PAGE(S): Entire Procedure DATE: 07-22-82 REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: A APPR VAL EJ0MMEN0E0 APPROVED - DA TE g 07-22-82
'\ l&
CHAIRMANSTATIONNUC EARSAFETY AND GPERA TING COMMITTEE
1 I . 8 No. 97487210 l
.f% NUMBER
, PROCEDURE TITLE REVISION EPIP-4.09 SOURCE TERM ASSESSMENT PAGE 2 of 9 I
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 1. INITIATE PROCEDURE:
a) BY: DATE: TIME:
- 2. SOURCE TERM ASSESSMENT:
a) Source Term (Ci/sec) =ay be obtained from any of the following:
- 1) Normal range STATION
. MONITORS
- 2) SAMPLE EFFLUENT
- 3) SAMPLE of STATION INVENTCRY
- 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 E om a conitor reading, sampling should be done to more accurately' determined the source term-d) Source term will have the
. v{/ UNITS of CURIE /SEC -
e
.e , a v
. . . . .-- - -. .. - - . . . . . - - . . - . . .-.--. . ---...~....-..~.3' s I No. 97851210
~
NUMBER PROCEDURE TITLE REVISION
! , 01 EPIP-4.09 SOURCE TERM ASSESSMENT PAGE 3 of 9
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED e) SOURCE TERM obtained from Containment High Range Monitor OR Containment Sampling is used for analysis following a Loss of Coolant Accident
- 3. SOURCE TERM - NORMAL STATION MONITORS:
NOTE: E MORE THAN ONE effluent pathways are involved in a release, repeat this step for ALL PATHWAYS involved and ADD the results for TOTAL release. O a) SOURCE TERM may be obtained from the following MONITORS: a) E normal range monitors are offseale, 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,.
2
- 3) PROCESS VENT GW-102 E
- 4) CONDENSER AIR EJECTOR SV-121, SV-221 NOTE: CONDENSER AIR EJECTOR may be diverted to containment.
~b) Obtain'the CPM, above
_I- [V background, for monitor of interest ___.)
j No, s7 s s721o 1 m NUMBER PROCEDURE TITLE REVISION 01 f' EPIP-4.09 SOURCE TERM ASSESSMENT PAGE 4 of 9
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 3. (CONTINUED)
- 1) Log the DATE, TIME, MONITOR number and the net CPM of Attachment 1 c) Obtain the FLOW RATE (CFM) effluent pathway d) Obtain CONVERSION FACTOR for monitor of interest:
- 1) VG-104 4.29E-10 OR (q
/
- 2) VG-113 1.73E-11 E
- 3) GW-102 4.29E-10
- 4) SV-121, SV-221 1.10E-6 e) Perform the following calcu-lations to obtain Ci/sec (XE-133 Equivalent)
CPM X CONVERSION FACTOR X CFM = C1/SEC
- 1) Log results on Attachment 1
- 4. SOURCE TERM - SAMPLE EFFLUENTS:
NOTE: E MORE THAN ONE effluent pathway is involved in the release - repeat this step for ALL PATHWAYS involved and ADD the results b\ for a TOTAL release. Q/
'- . s
No. 978 87210 4 s NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.09 SOURCE TERM ASSESSMENT PAGE j 5 of 9 l
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINE0'
- 4. (CONTINUED) a) Request Radiation, Protection a) H 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_
0,,R ,
- 2) PROCESS VENT b)
\j pR
- 3) CONDENSER AIR EJECTOR NOTE: CONDENSER AIR EJECTOR may be diverted to containment, elimi-nating need to assess source term.
i . i b) Have sample analyzed as per normal count room procedures. OR EPIP-4.26 High' Level Ictivity 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 (uci/ml) l lO i
__ . . ~ _ ..
p + == em> 4 weer b 6h No.975872:8 (} NUMBER PROCEDURE 11TLE REVISION 01 EPIP-4.09 SOURCE TERM ASSESSMENT PACE 6 of 9 , - STEP ACTION / EXPECTED RESPONSE RESPONSENOT08TAINED
- 4. (CONTINUED) d) Obtain FLOW RATE of effluent pathway
- 1) Convert CFM to MLS/SEC CFM x 472 =
E e) Calculate SOURCE TERM (Ci/SEC) EQUIVALENT ACTIVITY X FLOW RATE , C1/SEC 1.00 E + 6 b
\s / 5. CORRECT SOURCE TERM FOR MAXIMUM RELEASE:
a) Il sample from Step 4 was a) CO TO Step 10 a grab sample and NOT obtained at maximum release, correct for maximum release
- rate
- 1) Obtain the maximum monitor j reading
- 2) Obtain monitor reading at
! time of sample
- 3) Perform following calcula-tion to obtain MAXIMUM ~
RELEASE RATE: ( . x ape e ease Rate M n to S m le
- 6. -SOURCE TERM - STATION INVENTORY:
a) IF release originated from a a) GO TO Step 1
,- y gas storage tank (ie. Waste
( ) Gas Decay Tank, Volume Control
'd. -
Tank, etc.) sample the ac'tivity remaining in'the tank
No. 978 87210
\ NUMBER PROCEDURE TITLE-
[f
\,
EPIP-4.09 REVISION 01 SOURCE TERM ASSESSMENT PAGE 7 of 9
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTQBTAINED
- 6. (CONTINUED) b) Determine VOLUME of release from the follcwing equation:
PVT gt4 VOLUME = TP g2
- 1) Pg= pressure PRIOR to release
- 2) P 2= pressure AFTER release-N' 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) Vg = design volume of tank
- 4) T g= Temperature prior to .
release (Tg = *F + 459).
- 5) T = temperature after r$ lease (T2 = 'F + 459)_ i
- 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 SCURCE-TERM:
' VOLUME (mls) X EQUIVALENT ACTIVITY 1.01E+6 x Time of Release (Seconds) " '
1
- , - , , , . - , - . - - ., - , ~ +
. - , . . . . . , . . - - . . - - - , . , - . -. - - - - = . -
4 . no..en en t o i ? NUMBER PROCEOURE TITI.E REVISION i 01 EPIP-4.09 SOURCE TERM ASSESSMENT PAGE 8 of 9 , J
- STEP ACTION / EXPECTED RESPONSE RESPONSE NnTOBTAINEO
- 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 percent of ACTIVITY RELEASED TO CON-TAINMENT using Attachment 3,
'r- d) Use information from above Substep b and e 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 e) Determine RELEASE RATE f
- 1) Calculate release rate:
Equivalent CURIES X 4.35 E-8 = Ci/SEC \ . I 8. SOURCE TERM - CONTAINMENT SAMPLE: a) IF LOCA conditions exist, Equest the Radiation. Protection Supervisor to i activate EPIP-4.22, Post. Accident Sampling of Con-tainment Air U, p O a
No.97847210 i NUMBER PROCEDURE TITLE REVISION D 01 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) EQUIVALEN'T CURIES x 2.25E-3 =
Ci/SEC
- 9. SOURCE TERM - ENVIRONMENTAL DATA N a) IF the source term can NOT be a) IF release pathway is
. Etimated from onsite sampling Enitored B able to be' and/or monitor reading, return sampled, GO TO Step H.
to the controlling procedure, obtaining the source term from environ = ental 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: Date: Time: u END
+
, -e
-. .~. . ~ _ . . .._ _ .- _ - - . _ . _ .
e No. 978 87220 5 NUMBER A TTACHMENT TITLE REVISION
, EPIP-4.09 01 MONITOR DATA SHEET A TTACHMENT PA GE 1 1 of I CONVERSION DATE TIME. MONITOR CPM FACTOR CFM Ci/SEC (XE-133) a e
O 4 4 4 i
.4 r
O E o + , "*9" ,
e 4 No. 970 87210
, 'M NUMBER PROCEDURE TITLE REVISION , . EPIP-4.09 01 EQUIVALENT ACTIVITY XE-133 , IMMERSION DOSE 2 1 of 2 , - STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINEO ACTIVITY DOSE EQUIVALENT EQUIVALENT NUCLIDE FACTOR ACTIVITY A B AxB
, KR-83M 5.49E-2 KR-85 5.03E-2 KR-85M 3.55E+0 KR-87 1.78E+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 0-4 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
; I-131 8.57E+0 I-132 5.13E+1
! I-133 1.37E+1 l I-134 5.91E+1 I-135 3.55E+1 I of EQUIVALENT XE-133 =- O V I
,' ~ _ _ , [..._ ~ _ _ -....'
Ns.97887218
.. NUMBER PROCEDURE TITLE REVISION
, EPIP,-4.09 01 EQUIVALENT ACTIVITY I-131 PA GE INHALATION DOSE ,
2 2 of 2
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTCBTAINE0 ACTIVITY DOSE EQUIVALENT EQUIVALENT NUCLIDE uCi/ml or 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 f
I of EQUIVALENT I 131 = uCi/ml or Ci O m v
..-,#, tw e, ..m i ---b 'w-+rw- - * * ' ' "-
1 . . Po,97447220 t m NUMBER A TTACHMENTTITLE ~ - REVISION
}-
V 5' PIP-4*09
~
CONTAINMENT HIGH RANGE MONITOR 01 A TTACHMENT PA GE DOSE RATE VS. TIME 3 1 of 1 7- -- - anu,_.- --ums_ 10 . . .. ---- -- 4 . w- _ 1 .v i m ,r..- ..m,,-
- u Y M & sF. $.. O..p. .N*05 -
- ,5_. :_;.=.$. $'t. W_ .W .j+w 1.,s= =w ',h-t+a=t= n t i-1:1 p ==:t ;_nt
.' ASW_e-
, -. =ps- u- = = -
-82.ap :.2rp= xa u . = _zg-:: _
- . _ - . , .i.s m .x,;--mm_- , - . --
t rwe p y - gg - Ts&=+..-'u-t-4m1a+-p,mO r , _ ; _. _
.: 4'D W % 9pw e m M +.v-4HWW ee ; e +%
di-b g,' bE b5 hk:hN._. . -hih'5b. Nb- nub. i) --bkd.'db. - - - - - -E- --UkdN b--
- E-b-----
_&._h y = _-=
~_=._. __ :=c-._=r.--._-=_.=_::-- -
10 6
+w' ^ -- LOC'A (100
'--- v4 - .
'_T tL M= pELT) -, ';M- ;- "'M' _. -d' s e'_ *2 lSWpp .M.*+b44pv &q
,I %_ :.- _-Q w L_,
-- - a_
- . = - -
=._: y-.: s-4 rW_ --
.: z+-- --
. J yw .
--y4-
,n.=+P,..
,u:
1 n-
-~ .
.1. ---5. :5 ?_i!-i .2 -'.E-1.5 M ! :- 1-~=.---'I'==2.--*- t=-~= 5 = =f- r % #* ii ~+4--' # -
-@~pl UbN M w
]N[kw-4
%h M E--&. E e+C=L514Me--EW* i=- r12EMi'=5T=
NN $AfNN$ 7. wJMmwee)hkd-h"CW E5=2=== rwm %
.i25dE'MM ==iM=E
~
=
--~-:.
__.=N_=_____._z___=.=__.=__.___m._.____:-_=____=_:_=k&.=
=:__
.=_ _ .- - - - -
__.n- z
'm 5 ~
10 * ~+d LOCA (lot FUEL MELT) U-.~;
.i t=w M M
.'Qy *~.-br+_.. - ,_,m,m;;
L-~W*+: :' = V:+ ~- M*'-:=,: =. -_e--..= a %W. % .?~-_- ; %_. m
---=-----=L-.- ~~M--.=. c
==1a
'=.X
+ev--- =.+-
S ' = ^ - ' - - ~- - a
, 14=: li.~_'t - l-6 'd-2: --~E f-E[== _i_5-ji:= _'M= J F;' E-:- ::= - = gu gj .
__'} g : _--_ s t_ FN. WPN,W c -- ,&-Q- 4g+r mm_Wyd)M N
._# M- % -_it t, h, ]JWr*4G_,S. ,9_}MW '.2x '_,
/ g
. - w
.. Pe
=
W M n O d*f M ?L- _,.;,%Mie+M-Mb ^.G*--i ht I .
. : 2:=. :-: st-*f =. tFN.et*2.=T== *=33 : ' ~:Wm'--: - =i:?^ 14P r= -* 1 % c-= ' v '=== \wj .
X==E e-E21=s :=+2ni us=- =i 2=5m=1 z==_
=== ==, == = =. =- = e5.--==_m 2 2 ~==5Lg_=;
- .:_- ;p4= Lg __L y-- _ . . . _
, g _--- - - - _ _ - - ---- . _... ____
s z -% _-- -_ _ _ _ _ . _ _ _ _ _. _ _ _ _ _ as x 4 N m- - -
~
I 2L2==22PMT ~ Enti-IM-E2.2=1 ? - - = M '- A M y n 2=-:=====z=======^==- ==E===--5======= m= =_=.== = E===: =n = . '===L - g , M ... f_W,EMRNppi$ff*"""" Mum *~'*2M - _ :we*M ' s t===_
- i.
=
i- s=g c1= A h t; sr f M [ N M sm+:=r:. _+3 ima-=_t?a_.=-_ =___ .- . LOCA (1001 CLAD TAILURE) - is=+
=y-rnrzz_. :: 2-2::x r _mcr_ x-=.: 2_ _- . _;ghg_y- =-1-_-
~ T_2=7 -W Gr::- - .. - m_ =:- --- - 2 10 =. _. --
._ .._. =-. .m m -a
-_mm gay g n_,r.=
o. 1
'l 'i '. JJ'
_.v
, C 'E 7b
- m. ,w i
L7i-i&'me . MX W 1 JTM E E "- Ed 'r ia o.m ; s u l' EI;.7 - Fa"P' ' ~ . ' .T=% ~T.L= sir -4 . v- r+ 3 ..- 'f=-_@' , -.-i a EE17.' _i -F : - = W5'. _'_f --
, gg_.5Esw+2a =t=27a= .c=; - ---
'==- ==2E+.:sL;-:== = y. E=Et=;=g :
n Wesp- .E =;:==9:-:- == y' I -
.n. .
m , _ . _ _ _u
.m- .:
mm H.]lq 9.f.>..; -
"E .; 3>a_ c3i: n s4 -
e '.Abp L MFi.. B,nc#: " K s.'w.~.'3_ym.- 3. .f_ _y_, Tw y. E'-Ei*.E =. = r ._=g W MEibi.#3- K__15_;
^
-2
?b.tGiE;=~t.--=_==_M_..-.__^=-^~T.-i'-t.
a*----siw=h== s=K -
=--.d_=:*"TE.-:^=
-.:=
2 10 g _-
-,... . . . _ _ -. m .. . . u
,='m ',n.* s.= . .:. '; .-
, ,. _m a w. -
n - - m r , . --
. - ,m n .
- e i _ _u-._._+-
- W" )- ' '
A+%IE.H1 -F W E5Nf. ' i =-
- MA Ofi
- r-.= -W^: 2
'l l
---=-s nW=.t -.=- = === =- ~=
===2:==+ =.=m=:,==.-:- w
=-=-. . - - --.=E+=_=== _ . _. -
--q m r a __
ir
, e.-
-t- .a.
i
.c.-i 1
r 2.r r5m j 2s >
. ._a m a
i e,.
.#m--- .- r e
&,c e .i r ..-aw
'1.
. En,a. 5 -
5 t' h -
, tmP.. -n _=2 n a r1r .
F5E"-T2K' ;= PU_=. z + 6 M EEEJ,f- A._n ; _ Af==..5$.1 __.-. _ -.. . 5_.*..-': ___r _ M.F23Erw g
~50!-M -d'EE A_!rE2M**fti"=%. ---
* ~-~*---;1- "--- . _ _ _ LCCA (12 CLAD FAILURE) Z- - - ~ - -
~~
4, . 1 -x / 10 1 3 4 5 6 7 0 2 tint (Reers)
d s 4
. e ..
I No.97887220 i _ in t ) NUMBER A TTACHMENT TITLE REVISION t V< EPIP-4.09 01 EQUIVALENT CURIES FOR A LOCA ACCIDENT A TTACHMENT PAGE 4 1 of I n _ mn-1,#c,#p...
=.e um 1.- -- ,, ym mg-_.
1.___ _ m s ,#_- n o.m c m & +__. a -.wy_% m= _ym a mar-= f G?! m . EHMMs -3it +i LXR
==_js_gn~
l1*eh=#. i-_ iIfMNit-3
.__a_ = : = . =-g g:__9=
DY"*M_- y:-=d m_=g d y[M. - - M____ so _wn =m.-2 pa j __ur_2: =_= . =:----^----- _ T :- - - .- _;----==_=y=w _ y-\
'm '
10 , 10 , ___
'LOCA (100 UNMNYWg' '--=
', FUgt,Mgt;} "$3
, %'Y5 xi+ ua mn M m ntu st=4 m twM_ &k.w21M
, _ m-awEri r a mg arn .a. ;;;mma_.,.c WG a & R '.3.%'t9-.9.m$. h> W- - -
W_4My
,mI.M b W; r- 6MY4
. .5$T_--;'18_-.Z"
%ep_. - '~-Mi~~ Ti - '
Lm'.--~ 3 Hi .1:itTr"yrg*Q' ; -51' .1_?_-.~--G 'ZI --N ;E ' 5=FI EQMI^i- X%i-Mg
~ .. _ . _ . .. _
7 r: d'-
'r 222 2~'=*ZXZE;_ :_~ ;_E'-M L ._ _
-kGG4. _E=_WMM~fffiEt
~
9 '~ - r 10 e -4. a m - - - - --
$ NM$%d
-- - - , - - - - - - -$ g h ,._ j b874f g LOCA (101 FUEL MILT) !"[t O
- IJ E ric M ang;,n;; 3 a = S m % 4 ,=
a ;au mm = - . m.mm .- (% ., . :s you .a= 2.
\J "
. h_?$_$$$ mm ?wY$_NYWYYW =
wmm '- my PakME ~_Z_Z Z.-~ pm -- - _ __? "__5~Z_'_-'_5_5E_si ' - . ___ _. ;._~_E?_E -_ _- _-__ _ _ ' _ ___.
~
'~
0 10 e e s E l _Tl W7WTl &_. . ; .. c . . '4 , LOCA (11 FUEL MELT) L T,O" h lY(M $5 . I [M$NMuitnsjypgyI.;--. nR2%$ E , ___ . ____ __m G 'CL--'_ .,m ,,_ d ""-_- a;f_ =3 E_; E -~~L-' X . 3i2%i'W3% % lmS3 Y' MMP
~
a 4 N Dw:N5bEbsndbUbHb$5 - _ :: -: "-':--t=_.=:__... n.___ .___ _ _ _ - = ___z.n _____ [WMEhE5NbN LOCA (loot CLAD FAILCRE) - 7 NY35%E_[E-
._ .m Tt U: O m! hh4dirs Le E r i m
m wi= ~ - _3 : r M_E . 2._--a .L 2=2 8 -
- I -
-EtL E-E-L1#E~# :*. =_ 4= #IWw=1r mWM_Em .
-mx v ~s-:~ *_ =
M
~ ^ ^
Z.7~~~~-~ ' . " _ _ _ ' [_ ~_'. a r. E' ' - 1-'C-Eh. - -. _ . - .
~ _ ' _l i._=
6 10
, -- --msi - ,..n -- -m
.m emmy .-% uw .LOCA (11 CLAD TAILU11) .__ . _ . _ e;.
~e %"5 .E.;-i r % ~.; tcW'?N--+++= -
+-= 31+++ = mz =u . _-.:. :=. . . -.
. . : l .
mer -s* == M -WGT.--Z-sbi-=i- at c--C"'- - 95sHOi= E
--~
-=
.:=r__ ~2-_---
.~
~~'~'
* ~
2-~~~~'
^
'L: r-'Tr f%
i 4
'% )' 10 I
O- 1 2 3 &' 5 6 7 T1h! (Rours)
*-geyey- O
._..m_m_ _ _ . - . _ _ _ . . . _ _ _ - _ . m.. .__- . . . .. . . _ ,_. _. . . _ _ . . _ _.m._ _
..-..__.m.__
4 e e ,
! NB.97887224 NUMBER A TTACHMENT TITLE REVISION EPIP-4.09 01 i
EQUIVALENT CURIES I-133 FOR LOCA ACCIDENT A TTACHMENT PAGE 4 2 of 2 NOTE: Within the first 8 hours following LOCA incident, IODINE decay is insignificant . i EQUIVALENT CURIES EVENT I-131 . LOCA 3.51 E+2 (1% Clad Failure) l LOCA 3.85 E+5 (100% Clad Failure) LOCA 5.93 F+5 (1% Fuel Melt) LOCA 5.93 E+6 (10% Fuel Melt) LOCA . 5.93 E+7 (100% Fuel Melt) s r 4 F 4 a
\
V...
- Nb 6 4 4 4 4
* *-W- * - --
v
.... . _ . - .~. . _. . . . _ . _ _ .
No. 97 887200 _ VIRGINIA ELECTF : AND POWER COMPANY NORTH ANr. . POWER STATION sA' <. EMERGENCY PLAN IMPLEMENTING PROCEDURE x . NUMBER PROCEQURE TITLE REVIS!ON
, 01 EPIP-4.10 DETERMINATION OF X/Q
, PAGE (With 5 Attachments) 1 of 5 PURPOSE Determine atmospheric diffusion factor. X/Q. N T A CONikotMD
, DOCllssENT JUL 241992 NOR o,.
r m e. , .. ~~ *HE
. USER ' "'#DUIY Radiological Assessment Director and/or Radiological Assessment Team.
ENTRY CON 0/Tiot!S O~ Activated by offsite dose assessment EPIP. VEPCO PROPERTY This document is the property of 'th.- Virginia Electric and Power Company and la to be returned upon request No perniscion is granted to publich, r<@roduce, tranceit or disclose to-another any information contained iti this docwaent. SAFETY EMD REVISION RCCORD ~ REV. 00 PAGE(S): Entire Procedure DATE: .07-02-82 REV. 01 PAGE(S): Entire Procedure DATE: 07-22-82 REV.. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: p , APP 0}A RECOMMENDED APPROVED . , . , 7 , DA TE
/
g D 07-22-8'2 CHAIRMAN STATION NUCLEAR SAFETY. I AND GPERA TING COMMITTEE 3
No. 97847210 m t N' f, NUMBER PROCEDURE TITLE ~ REVISION
~
01 EPIP-4.10 DETERMINATION OF X/Q PAGE 2 of 5
- STEP ACTION / EXPECTED RESPCNSE RESPONSE fl0T UBTAINED
- 1. INITIATE PROCEDURE:
a) Initiated By: _ Date: _ Time:
- 2. DETERMINE CENTERLINE X/Q AT PREDETERMINED DISTANCE a) IJ; X/Q is for site boundary a) IJ; h/Q is needed for other and/or distance of 0.25 mile distances, GO TO, Step 3,.
increments, continue with this instruction. - ( ,)\ 1) Obtain from the Radio- 1) Obtain information from t logical Assessment the Emergency Communicacor Director: if Radiological Assessment - Director NOT available. Wind Speed AND Stability Class
- 2) Determine distance (mi?es) for which X/Q to be calcu-lated ,
- 3) With Stability Class.
Wind Speed and Distance determine X/Q from Attach-ment 1.
- 4) Correct X/Q from Substep j[ for current wind speed:
^ "* S" WIN PEED (Oph)
(.
\ .I \ _,4 k
no. s re stn e
,n.,.
(N,,/ L' NUMBER PROCEQURE TITLE REVIS10V 01 EPIP-4.10 DETERMINATION OF X/Q 3of$' STEP } ACTION! EXPECTED RESPONSE RESPONSE NOT OBTAINED - NOTE: Dispersion coefficients for stability class C are determined by: coef ficents (stability class F) x 0.6. NOTE: For Stability Class A and distances GREATER THAN 1500 meters, o = 2000, g or Stability Class B and distances CREATER TRAN 5000 meters, og = 2000.
- 3. DETERMINE CENTERLINE X/Q AT ANY DISTANCE a) IJ[ X/Q is required for a a) CO TO Step 4 distance other than calcu-lated by Step 1, continue p_s with this instruction
( ;
\,_) 1) Determine distance re-quired for X/Q (miles)
Convert miles to meters: MILES x 1609 = METERS
- 2) Obtain current WIND 2) Obtain from the Emergency SPEED AND STABILITY CLASS Communicator if Radio-from the Radiological logical Assessment Assessment Director Director NOT available.
Convert vind speed (mph) to meters per second eph x 0.447 =
- 3) With the wind speed (meters /sec) and Stabi-lity Class, determine the dispersion coefficients: .
~
e "~ s i.J' -
\
L - - -. _-
-.___- __ __ __ _ _ - _. __ _ .~ --- . - .
No. o r s e rt t o 1 '; (' NUMBER PROCEDURE TITLE REVISION 01
- EPIP-4.14 DETERMINATION OF X/Q PAGE 4 of 5
- STEP ACTIONiEXPECTED RESPONSE RESPONSE NOT CBTAINED
- 3. (CONTINUED)
Horizontal co~ efficient (cy) use Attachment 2 - e AND Vertical coefficient 1 (cz) use Attachment 3, i
- 4) Determine X/Q by follow-q ing formul.:
X/Q = 1 - sg (3.14 ozo y+ 758) (wind speed)
- 4. DETERMINE X/Q NOT ON CENTER-LINE l a) IF,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 .
4 this instruction
- 1) Determine centerline X/Q
, from Step 2 ,O_R R Step.-3 2). Determine Stability Class
~3) Determine downwind dis-
.tance (miles) for X/Q using Step ,2_ or step 3- -
- 4) Using DISTANCE and STABI- ,
LITY CLASS, determine value-of: 1 2 (c y)2from. Attachment-4_ J
?
.) ,
s n.. m um i t l l' NUMBER - PROCEDL fE TITLE REVISION 01 j EPIP-4.1 ) DETERMINEIION '0F X/Q i PAGE
- 5 of 5 4
1 - STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINEO i j 4. (CONTINUED) j 5) Determine distance y, j y perpendicular to centerline which X/Q is to be calcu- , laced (See Attachment 5) convert y to meters miles x 1609 = meters l i
- 6) Determine X/Q off center-line by the following i
formula: J X/Q centerline X/Q = j exP i '( (2 @Y)3) 7 )
- 5. PROCEDURE COMPLETION:
a) COMPLETED BY: DATE: TIME: } s e a
?
- ' END I
4 4 -,
,s
8 8 N9.97887220 NUMBER A TTACHMENT TITLE REVISION (j- EPIP-4,10 01
^ II###
1 WIND SPEE = PER HOUR 1W2
\
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-4 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
/~'i 2.25 5.90 E 1.30 E-6 1.10 E-5 4.00 E-5 8.80 E-5 2.00 E-4 5.00-E-4 h 2.50
~
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. e 3.00 4.60 E-7 -5. 90 E-7 6.90 E-6 2.60 E-5 5.90 E-5 1.40 E-4 3.50 E-4 3.25. 4.20 E-7 5.60 E-7. 6.00 E-6 ~2.30 E-5 5.30 E-5 1.20 E-4 3.20 E-4 r
3.50 4.00 E-7 5.30 E-7 5.30 E-6 2.00 E-5' 4.80'E-5 1.$6E-4 2.90 E-4 3.75 3.70 E-7 4'.90 E-7. 4.70-E-6 1.80 E-5 4.30 E-5 1.00 E-4 2.70.E-4 4.00 3.50 E-7 4.70 E-7 4.20 E 1.70 E-5 4.00 E-5 9.30 E-5 2.50 E-4 !~ 4;25 3.30 E-7' '4.40'E-7 '3. 80 ,E-6' 1.50 E-5 3.70 E-5 8,.60 E 2.30 E-4 4.50 3.20 E-7 4.20 E-7 3.50 E 1.40-E-5: 3.40 E-5 8.00-E-5 2.10 E-4 i :p 4.75, 3.00 E-7 :4.00 E-7' 3.20 E-6 ' 1.30 E-5 '3.20 E-5 7.40 E-5 -2.00 E-4 I - 5.00 2.90 E-7 3.80 E-7 2.90 E-6 'l~.20 E-5;'2.90 E-5 7.00 E-5; 1.90 E-4 5.25 2.80 E-7 '3.60 E-7 2.70 E-6 l'.10-'E-5 '2.80 E-5 6.50 E-5 1.70'E-4 i- /~'s - 5.50 2.60'E-7-. 3.50 E-7' '2.50 E-6 .1.00 E-5 2.60-E-5 .6.10'E 1.60-E-4 l t )
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i hs.97887220 O NUMBER EPIP-4.10 A TTACHMENT TITLE 3 REVISION og
..X/Q (SEC/M )
A TTAC"fIENT WIND SPEED = 1 MILE PER HOUR 2ofy2 t DISTANCE (MILES) A B C D E F G I 6.00 2.40 E-7 3.20 E-7 2.10 E-6 9.20 E-6 2.30 E-5 5.50 E-5 1.50 E-4 6.25 2.40 E-7 3.10 E-7, 2.00 E-6 8.60 E-6 2.20 E-5 '5.20 E-5 1.40 E-4 i 6.50 2.30 E-7 3.00 E-7 1.90 E-6 8.10 E-6 2.10 E-5 5.00 E-5 1.30 E-4 6.75 2.20 E-7 2.90 E-7 1.80 E-6 7.70 E-6 2.00 E-5 4.h0E-5 1.- 3 0 . E-4 4 . i . 7.00 2.10 E-7 2.80 E-7 1.70 E-6 7.30 E-6 1.90 E-5 4.50 E.-5 1.20 E-4 7.25 2.10 E-7 2.70 E-7 1.60 E-6' 6.90 E-6 '1.80 E-5 4.30 E-5 1.20 E-4 ( 1 7.50 2.00 E-7 2.60 E-7 1.50 E-6 6.60 E-6 1. 70 E--5 4.10 E-5_ 1.10 E-4 7.75 1.90 E-7 2.60 E-7 1.40 E-6. 6'.30 E-6 1.70 E-5 4.00 E-3 1.10 E-4
- 8.00 1.90 E-7 2.50 E-7 '1.3O E-6' 6.00 E-6 1.60 E-SL 3.80 E-5~ 1.00 E-4 8.25 1.80 E-7 2.40 E-7' '1.30 E-6 5.80 E-6 71.'50 E-5 3.70 E-5 .1.00 E-4 h
- 8.50 1.80 E-7 2.40 E-7 1.20 E-6 5.50 E-6 1.50 E 3.50 E-5 9.60 E-5
- 8. 7,5 1.70 E-7 ~ 2.30 E .1. 0 E-6 5.30 E-6 1.40 E-5 -3.40 E-5 9.30 E-5
~
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9.00 1.70 E-7 ~ 2.20 E-7 1.10 E-6 5.10 E-6 1.40 E-5 3.30'E-5 9.00 E-5 9.25 .1.70 E-7 2.20 E-7= 1.00 E-6 4.90 E-6 1.30 E-5 3.20 E-3 8.70 E-5 9.50 1.60 E-7 ,
.2.10 E-7 1.00 E-6 ,4. 70 E-6 .1. 30 E-5 : 3.10 E-5 S.40 E-5 9.75 1.60 E-7 . 2.1YE-7 :9.60 E-7~ 4.50 E-6 1.20 E-5 .3.00 E-5 S.10.E-5
-10.00 1.50 E-7 2.00~E-7 9.20 E-7 4.40 E-6 1.20 E-5 2.90'E-5 -7.90 E-5 9
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- No. 97487200 VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION fN \
EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.l! FOLLOW-UP OFFSITE RELEASE ASSESSMENT PA GE - (With 7 Attachments) 1 of 9 PURPOSE Accurately assess the percent technical specifications OR the offsite whole
, body and thyroid dose rates, using monitor or sample data.
USER Radiological Assessment Director E members of Dose. Assessment Team. ENTRY CON 0lTIONS V 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.
NOT A CONTROLLED or,c ." " " VEP.CO PROPERTY This document is the property of the : JUL 241982 Virginia Electric and Power Company
"' ~ "
- and la to be returned upon request; qg No permiselon la granted to publish,~.
b i k reproduce, transmit or disclose to a,nother any information contained in REVISION RECORO Hab deu = b - REV. 00. PAGE(S): Entire Procedure: DATE: 07-02-82 REV. 01 PAGE(S): Entire Procedure .DATE: 07-22-82 REV. PAGE(S): . DATE: REY. PAGE(S): DATE: REV. PAGE(S): DATE: REV. 'PAGE(S): , DATE: (~%. REV. PAGE(S): . DATE:
.~ , / . - APPROVA R MMENCEO APPROVE 0 . , .,
DA TE
/ -
07 22_s: l {, - CHAIRMAN STA TION NUCLEAR SAFETY AND GPERA TING COMMITTEE = un
N3.97447210 i 1 0 Q, % NUMBER - PROCEDURE TITLE REVISION 01 EPIP-4.I1 FOLLOW-UP OFFSITE RELEASE ASSESSMENT
^'
2 of 9
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINEO
- 1. INITIATE PROCEDURE:
a) Initiated By: Date: Time:
- 2. ASSESSMEhT OF PERCENT TECHNICAL SPECIFICATION a) Determine.the percent of Tech. a) IF the event is a Site OR Specs under UNUSUAL EVENT OR General Emergency, GO TO ALERT Step 3_ for Offsite DOSE RATE calculations.
~
b) IF LIQUID RELEASE b) IF gaseous release, GO TO Substep c_.
- 1) Obtain SMiPLE RESULTS (uci/ml) and log on Attachment 1
- 2) Divide SMiPLE RESULTS (uci/ml) by. respective MPC. Log on Attachment-1
- 3) Sum the results from Sub-step 2,and log on Attach-ment 1
- 4) E sample from Substep 1
- 4) IF sample obtained f rom plant was obtained from dis- system, GO 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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; No. 97847210 NUMBER PROCEDURE TITLE REVISION v
' 01 EPIP-4.11 FOLLOW-UP OFFSITE RELEASE ASSESSMENT PAGE 3 of 9 1
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOSTAINED
- 2. (CONTINUED)
- 6) Obtain the number of
- CIRCULATING WATER PUMPS running.
- 7) Obtain the GPM of the release from Operations
- 8) Determine the 7. Tech Spec:
Substeo 3 X GPM X 4.19 E-4
.# of Circulating Water Pumps " *. * *
- 9) GO TO Step 7 c) IF, CASEOUS ' RELEASE
- 1) Obtain SAMPLE RESULTS and-log activity on Attachment 2
- 2) Determine percent Tech Specs 2) GO TO Step 3,.
for NOBLE GASES from~ equation 1, Attachment 2
- 3) Determine percent Tech Specs,
.for SKIN DOSE from equation 2,. Attachment 2 4)' Determine percent Tech Specs for RADI0 IODINE AND for PARTICULATES with halflives GREATER THAN 8 DAYS by sunuaing the activity (uci/ml) '
and using equation 3 on-Attachment 2 l- 5)LGO TO Step [ X k - v%+t-~ .. .mm ,e+=, - r- .yme e p aa. % ,esee -w & rN----.e,e - , E- g ww * .5 4 -- # --~+.
, .- . , ,,-a
I No. 97887210
.JD
' ;/
NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.11 FOLLOW-UP OFFSITE RELEASE ASSESSMENT PAGE 4 of 9
- STEP ACTIONNXPECTED RESPON!E RESPONSENOTOBTAINED
- 3. DETERMINE OFFSITE DOSE WITH ,
, NORMAL RANGE MONITORS a) Determine Offsite Dose vich a),GO TO Step 6_ E sample Normal Range Monitor 2 sample analysis of release ,I_S, S analysis is NOT available available. .
b) E release is through the b) GO TO Step 4 E monitors are Ventilation System OR, OFFSCALE Air Ejector 0R, AND
~" Release is through the MAIN Any of the following monitors STEAM
% are ONSCALE, continue with this instruction:
- 1) VENT VENT A (VG-104)
P_R.
- 2) VENT VENT B (VG-113) 0.LR
- 3) PROCESS VENT (CW-102) pR_
- 4) AIR EJECTOR (SV-121, 221) c) Obtain the following infor-mation and log on Attachment 3
- 1) DATE, TIME, AND MONITOR of interest .x
- 2) CPM of monitor of interest .
frcm Radiological Assessment Director Nf
.- ~a-. ,-,-._.m . . . ~ _ .-- - *
, ,. :- _. - - r-- - - --- --
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j . e* No.97847210
<] NUMBER PROCEDURE TITLE REVISION i
01 EPIP-4.11 FOLLOW-UP OFFSITE RELEASE ASSESSMENT PAGE 5 of 9
- STEP ACTION / EXPECTED RESPONSE RESPONSENOT OBTAINED
- 3. (CONTINUED)
- 3) FLOW RATE (CFM)
- 4) Obtain X/Q for site boun-dary from EPIP-4.10, Decemination of X/Q d) Obtain the CONVERSION FACTOR for monitor of interest and log on Attachment 3 MONITOR CONVERSION FACTOR
- 1) VG-104 1.80 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 CPM X CFM X (X/Q) X CONVERSION FACTOR = l l 1) Log results on Attachment ,3_ f) GO TO STEP 6
- 4. DETERMINE OFFSITE DOSE WITH PROCESS OR VENT VENT HIGH RANGE MONITORS a) E release is through the a) IF sample analysis p avail-Process Vent OR Vent Vent able, GO TO Step 6_.
m
, i i i
-~
.I No.97887210 i
NUMBER ~~
~ PROCEDURE Ti . E REVISION 01 EPIP-4.11 FOLLOW-UP OFFSITE RELEASE ASSESSMENT PAGE s
6 of 9
- STEP ACTIONMXPECTED RESPONSE RESPONSENOTOBTAINEO
- 4. (CONTINUED)
AND _OR High Range Monitors are on H release is through the scale Main Steam, GO TO Step 5. AND ,01 Sample Analysis is not yet If, monitors are not onscale available, GO TO Step 7 Continue with this instruction
, b) Fill in the DATE, TIME AND f 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. n. v 4 to obtain MR/HR _ ~ ~. . - -
. _ - _ . _= - ____:_-_______
,_ _ _ . , . . . _. _. . . . . . - . .- - -- -- - - - - - - - - - - ~ + - - --
1 No.97887210 1 I NUMBER PROCEDURE TITLE REVISION k" 01 EPIP-4.11 FOLLOW-UP OFFSITE RELEASE ASSESSMENT PACE 7 of 9
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 5. (CONTINUED) uC1/cc X CRf X (X/Q) X CONVERSION FACTdR =
g) GO TO' Step 6
- 5. DETERMINE OFFSITE DOSES WITH-MAIN STEAM OR 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) IF MAIN STEAM SAFETY 1) IF no valve has lifted, VALVE lifts OR may project release using only potentially lift, deter- one valve.
mine the' NUMBER OF VALVES LIFTED from Radiological' - Assessment Director AND the FLOW RATE as follows: i 8 NUMBER OF VALVES LIFTED x 2.62 = m /sec
- 2) IF the AUXILIARY FEED PUMP 2) IF main steam to the
! TURBINE,has NOT been turbine is isolated, isolated determine FLOW' no release is likely RATE from following: through this pathway. L Continue with this step.- UNIT #1 = 4.216 m3 /sec t UNIT #2 = 3.967 m3 /sec i t e e
u -. . - . .- . - . - t ' No.97887214 ~. l ' NUMBER PROCEDURE TlnE REVISION ,f {
' N(P . j J'
EPIP-4.11 FOLLOW-UP OFFSITE RELEASE ASSESSMENT 01 PAGE 8 of 9 k l - STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED i
- 5. (CONTINUED) d) Decemine the DOSE CONVERSION FACTOR from Attachment 7 and -
log on Attachment 6 e) Determine the X/Q for S$.te Boundary from EPIP-4.10 Determination of X/Q and log Attachment 6 f) Perform the following calculation to determine MR/HR: h Dose MR _,/ MR/HR (Monitor) x Flow Rate (cc/SEC) x Conversionx,(X/Q)={. Factor
- 6. DETERMINE OFFSITE DOSE RATE FROM SAMPLE RESULTS a) Obtain EQUIVALENT ACTIVITY (C1/SEC) for I-131 and Xe-133 from EPIP-4.09, Source Term.
Assessment b) Determine X/Q for Site Boundary from EPIP-4.10. Determination of X/Q i c) Determine DOSE RATE
\
- 1) THYROID Ci/SEC x X/Q x 1.85 E + 9 = MR/HR 5
- 2) WHOLE BODY Ci/SEC x X/Q x 4.20 E + 4 = MR/HR u .:
e e e
=4 P. . pf@ . *
.*MG p g . .c e s. . ~ ms 9 -w?'G* M a eW W'* d eM -- *W - - - - -
~'
t n . . = . . . ns. esen21e NUMBER PROCEDURE TlnE REVISION
\ ,
01 EPIP-4.11 FOLLOW-UP OFFSITE RELEASE ASSESSMENT PAGE 9 of 9 1 1
- - STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED 1
- 7. RETURN TO CONTROLLING PROCEDURE:
a) Upon completion of this procedure' RETURN to EPIP-4.03, Dose Assessment Controlling Procedure
- 8. PROCEDURE COMPLETION:
a) Completed By: Date: Time END h a
\
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; No.97887224
! a f
NUMBER A TTACHMENT TITLE REVISION j' ... EPIP-4.11 01
% TECH SPEC LIQUID A TTACHMENT PAGE 1 . WORKSHEET 1 of 1 i
t ISOTOPE (khIfmkf1 UNRESTRICTED-MPC p H-3 3.01.E-3 KR-85 4.01 E-5 KR-85m 4.01 E-5 KR-87 4.01 E-5 KR-80 4.01 E-5 Xe-131m 4.01 E-5 Xe-133 4.01 E-5 Xe-133m 4.01 E-5
. Xe-135 4.01 E-5 MN-54 1.01 E-4 l
MN-56 1.01 E-4
.\
Re-59 5.01 E-5
, Co-58 9.01 E-5 Co-60 3.0L E-5 CR-Sl 2.01 E-3
- ZR-95 6.01 E-5 Mo-99 4.01 E-5 Ru-109 1.01 E-5 Te-132 2.01 E-5 i Cs-134 9.01 E-6
! Cs-136 6.01 E-5 Cs-137 2.01 E-5 BA-140 2.01 E-5 CE-144 1.01 E-5 I-131 ' 3.01 E-7 I-132 8.01 E-6 I-133 1.01 E-6 I-134 2.01 E-5 I-135 4.01 E-6 g (uci/ml)i , MPCi l i vu
. .. ~. . -._ . ._. . . _ . . .
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! Ns.97887220
.?
NUMBER A TTACHMENT TITLE REVISION \
\ '\ EPIP-4.1; 01 }' ._ . - l % TECH SPEC GASEOUS ATTACHMENT PAGE j 2 WORKSHEET 1 of 1 .l t
DOSE FACTORS ISOTOPE ACTIVITY (uCi/mL) Ki Li Ni KR-83M 6.40 E-5 0.01 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 6.01 E+0 s 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 ' 4.01 E-1 3.01 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 O Xe-137 1.01 E-1 1.60 E+1 1.10 E-1 Xe-138 2.01 E+0 5.40 E+0 2.10 E+0 l
- 1. (E (uci/ml)1 (ki)] (CFM) (9.44 E-2) = % T.S. WHOLE BODY DOSE l
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- 3. I (uci/ml) (CFM) (1.94 E+4) = % I.S. RADIODINES AND PARTICULATES o
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no. orasnoo VIRGINIA ELECTRIC AND POWER COMPANY N' 'ITH ANNA POWER STATION EMERGENCN ?LAN IMPLEMENTING PROCEDURE .
; l NUMBER PROCECURE TITLE REVISION 01
'l i EPIP-4.12 0FPSITE ENVIRONMENTAL MONITORING INSTRUCTIONS PACE
}
(With 3 Attachments) 1 of 7 i PURPOSE Provide guidance to the Dose Assessment Team or the Radiological Assessment Director to direct the Offsite Monitoring Teams to properly 1) confirm radiological release, 2) track release and, 3) determine radiological composition of release. NOT i. CONTROLLED Dori na rNT . USER v UL d 4 19W Dose Assessment Team Members. NO,i ,,q . LATESI HtVISION ENTRY CONDITIONS f Any one of the following: l 1. Release of radioactive materials with a Site or General Emergency l condition and E0P is NOT activated. -
- 2. Any other time which the Radiologi. cal Assessment Director deems it .
necessary. VEPCO PROPERTY
' This document is the property of the Virginia Elvetric and Power Comp;n3 and la to be roturned upon roquesL.
No parmission la granted to publish, reproduce. tranwit or disclose to another any information contained in this document. N ."88 PAGE(S): Entire Procedure DATE: 07-02-82 REV. 01 PAGE(S): Entire Procedure DATE: 07-22-82 REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: O a An A,,R0vE0 - - OA rE a03 ReCOMMEN0e0 g;f 07- 22-82 h ,
//
L CHAIRMANSTA TIONNUCLEAR SAFETY { ANO OPERA TING COMMITTEE
, =~-
9 . .
no. orsertio i NUMBER PROCEDURE TITLE RE ISION 8'l EPIP-4.12 0FFSITE ENVIRONMENTAL MONITORING 4 1 INSTRUCTIONS PAGE b 2 of 7 i i, l i - STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED 4 ! I
'i 1
- 1. INITIATE PROCEDURE:
a) BY:
! DATE: ,
TIME:
- 2. ACTIVATION UPON SITE OR GENERAL EMERGENCY:
a) The procedure is applicable a) IF EOF is activated and moni-upon radioactive release and toring teams in the field, declaration of SITE or turn over control of the GENERAL EMERGENCY monitoring teams to the Radiological Assessment OR Coordinator Whenever Radiological Assess- 1) BRIEF Radiological ment Director deems it necessary , Assessment Coordinator
, as to the current AND location of the monitor- .
ing teams and data The EOF is NOT MANNED gathered to, date
- 2) Inform Monitoring Teams in the field that they are to RECEIVE INSTRUC-l TIONS and REPORT all DATA to the Radiological Assessment Coordinator at the EOF
- 3) GO TO Step 13.
l l , i f
..o i
7.- -.
. e No.97887210 1
1
) NUMBER PROCEDURE TITLE REVIS10N 01 EPIP-4.12 0FFSITE ENVIRONMENTAL MONITORING INSTRUCTIONS PAGE
,i 3 of 7 i
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTQBTAINED E
I
! 3. REVIEW PROJECTED DATA:
j a) Review the projected release data b) Obtain from the Radiological
?
Assessment Director the current meteorological conditions:
- 1) Wind Speed '
2)' Wind Direction
- 3) Stability Class
- 4. ASSESS MONITORING NEEDS:
a) Initially only ONE monitor- a) Staff monitoring teams as ing team may be available manpower becomes available GO TO Step b,
- 1) Use first monitoring ceam
! to initially CONFIRM THE l RELEASE THE DIRECTION AND RADIOLOGICAL COMPOSITION b) Minimum of TWO monitoring' teams is desirable
- 1) Locate one team NEAR SITE and the other downwind at <
l a DISTANCE FROM PLANT l
- 5. ASSESS MONITORING ACTIONS:
a) Purpose of 0FFSITE MONITORING
- 1) Initially CONFIRM offsite release
- 2) TRACK direction of the p!
%./
. PLUME
[ l l
. -***m.. _m w .*,me.e ., .e~ -% ,. ._e.,m,. . - - , , .- ., m.-.,- -.
. _ _ _ _ _ _ _ _ _ _ = _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ . _ .
,l
~
No. orsenso h- NUMBER PROCEDURE TITLE REVIS10N j 01 EPIP-4.12 0FFSITE ENVIRONMENTAL MONITORING INSTRUCTIONS pAGE 4 of 7 4
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTO8TAINED 5 (CONTINUED) j
) { 3) Determine radiological COMPOSITION of the plume
- 6. ESTABLISH RADIO CONTACT:
/
a) Activate EPIP-4.19, Use of a) H radio communications are Radios for Health Physics NOT able to be established Monitoring to establish - request assistance from the radio consnunication with , Radiological Assessment team using the RADIOPHONE Director AND Dispatch Teams instructing Os ' i them to use a pub)tc tele-phone to relay results to the TSC b) Instruct team to report all data to the TSC until , instructed otherwise
. c) Give monitoring teams the TSC telephone number in case of radio failure
- 7. ESTABLISH MONITORING LOCATION:
i
- a) A number'of PRESELECTED a) IF maximum plume concentra-MONITORING LOCATIONS have tion is NOT at preselected been established around monitoring locations, GO To the statica (see Attachment Subs,tep b, 1 and 2)
- 1) These points can be used l -
initially to locate l monitoring teams b) Monitoring at LOCATIONS
. OTHER THAN PRESELECTED can be identified using .
\d Attachment 1, -
r -- -
- _, , _ :^. , ~ - - - -
._._ ' ~~
No. 97887210 NUMBER PROCEDURE TITLE REVIS/CN EPIP-4.12 0FFSITE ENVIRONMENTAL MONITORING INSTRUCTIONS PACE 5 of 7
'l
_l - STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED ' t
! 7. (CONTINUED)
I 1) Location can be specified by use of SECTOR DESIGNA-TION and DISTANCE (MILES) (ie. a distance of ,2_ MILES NORTH of the plant would be A-2)
', c) Locate team (s) downwind
- 1) Wind direction from Step 3, indicates direction wind is coming FROM
- 8. CONFIRMATION:
4 a) Direct First Monitoring Team
~
to the sector, nearsite, which is affected by plume b) Obtain the following data and/or samples, if appro-priate
- 1) Maximum dose rate (MR/ER)
- 2) Air sample - particulate, iodine and gas
- 3) Soil Sample c) HAVE initial confirmatory samples RETURNED to the Security Building (D
N_s
.._ _ _ .mu. ~ .. -
- c. w as . --- -w- -me-- -~~ - ~~ ~ ~ > - - * ~ ~ - ~ ~ * -
j __ _ _ _ _ - _ _ _ _ _ . No. s7s en to I
~'
NUMBER PROCEDURE TITLE REVISION s 01 EPIP-4.12 0FFSITE ENVIRONMENTAL MONITORING INSTRUCTIONS PAGE I 6 of 7
'l
- STEP ACTION / EXPECTED RESPONSE I
' RESPONSENOTO8TAINED
.I
; 8. (CONTINUED)
J
- 1) Air sample should be immediately analyzed to determine Iodine / Noble
(:as ratio
, 9. FLUME TRACKING:
a) Plume monitoring should continue, obtaining at a minimum, the dose rate at , centerline of the plume b) Unexpected readings may
/, result from plume rise, looping or cloud meander
- 1) Have team travel down-wind a distance until plume is located c) Review the applicability of Attachment 3,, concerning plume width
! 10. FIXED ENVIRONMENTAL SAMPLERS AND TLD'S: a) Fixed air samplers and TLD's provide good information on the TOTAL release. Collection of these samples may provide best information after termination of release
- 11. ADDITIONAL SAMPLING:
a) Additional sampling for determination of chronic exposure pathways is not i normally within the scope l q']' of INITIAL EMERGENCY RES-I PONSE I
._ _ . . _ . . _ _ - _ -u- '
, No. 97887210
. i
,' NUMBER ~
~
~
PROCEDURE TITLE REVIS10N 01
,. EPIP-4.12 0FFSITE ENVIRONMENTAL MONITORING INSTRUCTIONS PAOE 7 of 7
- STEP ACTIONNXPECTEC RESPONSE RESPONSE NOT OBTAINED l 11. (CONTINUED)
.} b) Upon RECOVERY phase of'the
; Emergency, direct monitoring teams to obtain milk, water .
, and crop samples as appro-priate
- 12. CONTINDE MONITORING:
a) Continue Step 7 through M until: ,
- 1) EOF MANNED, GO TO Step 2
. () ,
- 2) Relear1 TERMINATED, GO-TO Step M OR
- 3) If monitoring data becomes *
, available, ACTIVATE EPIP-4.13 Offsite Release Assessment i with Environmental Data 1
- 13. PROCEDURE COMPLETION:
a) COMPLETED BY: DATE: TIME:
~
e j- ~ END
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**No.97087220 3
, . NUMBEl ATTACHMENT TITLE REVISION
) EPI?-4.12 01 i
LOCATION OF PRESELECTED ' A T;'4CNMENT SAMPLE LOCATIONS FAGE 2 1 of 2 l} * '; i
- s q
l Sector A
- 1. Intersection of Route 601 and Hailey Mill Road (643)
- 2. Approximately 1 mile from intersection of Routes 208 and 655 on Route 655 e
Sector B
- 1. Good Hope Church Intersection of Routes 208 and 601
- 2. Bethal Church on Route 208 Sector C
- 1. Approximately 4 miles from Good Hope Church on Route 601 East
- 2. On Route 713 approximately h mile from intersection of Routes 713 and 601 Sector D
- 1. 3/4 mile on Route 601 from intersection of Routes 601 and 614 Sector E ,
- 1. Intersection of Routes 614 and 601 at Lewistown
- 2. 3/4 South on Route 614 from intersection of Routes 601 and 614 Sector G
- 1. Ils mile on Route 614 from the intersection of Routes 614 and 652 Sector H
- 1. Intersection of Routes 614 and 652 in Sector H i
Sector J
- 1. Intersection of Routes 614 and 652 in Sector J - .
i Sector T
- 1. 1 mile East on Route 652 from intersection of Route 701 and 652 Sector L 5
- 1. Laurel Hill Church, approximately mile from intersection of Routes 701 and'652
+ -
- b
, No. 97887220 F, . !
\ NUMBER A TTACHMENT TITLE . REVISION
,' EPIP-4.12 01 LOCATION OF PRESELECTED A TTAC# MENT SAMPLE LOCATIONS PAGE l 2 , 2 of 2
'i l
i I I l* Sector M l 1. Intersection of Route 642 and C&O Railroad approximately I , mile from intersection of Routes 701 and 652 l Sector N l 1. Trailer Park on Route 652 approxicataly 3/4 mile from intersection of Route 701 and 652
- 2. Route 685 North approximately \ mile from intersection of Rotces 652 and 685 l
Sector P Ov
- 1. Route 685 North approximately Ik mile from intersection of Routes 652 and 685
- 2. Edgewood Church approximately 1 3/4 miles from the intersection of Routes 652 and 701 l =
Sector Q .
- 1. Route 208 East approximately 1 mile from the intersection of Routes 685 and 208
- 2. Route 208 East approximately 2 miles from intersection of Routes 685 and 208 Sector R ,
- 1. Route 608 East approxi.ately m h mile from intersection of Routes 655 and 208
- 2. Interser". ion of Routes 655 and 208
+
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*t No.97887220 f.'
b F ,) NUMBER EPIP-4.12 A TTAC# MENT TITLE REVISION 01 FACTORS CONTROLLING THE AREA
'; A TTAC# MENT AFFECTED BY A RELEASE PAGE 3 1 of 2 I
i 4 I i The area a release cloud may affect is dependent on the atmospheric stability . I class and the wind speed and direction, among other variables such as preci-pitation and the terrain. From a practical standpoint only stability class, which affects the " width" of the affected area, and wind speed and direction which affects the length and direction of the area, will be considered. The width of an affected area as a function of stability class and distance from the release point is illustrated by the following table. The table lists the different stability classes and lists the width of an area in feet which will contain a certain percent of the maximum calculated concentrations (or doses). The percentages considered are 90, 50 and 10%. The distances are 1 and 2 miles from a release point. These tables may be used as guide-lines on what to tell the monitoring team to expect, such as in stability class F they are looking for a small area of rapidly increasing concentra-tions if the cloud is approached from the side.
,r 3 '
Area Width - Feet Stability Percent of Class Maximum 1 Mile Distance 2 Mile Distance 90 878 1632 A 50 2256 4195 10 4109 7641 90 653 1227 B 50 1676 3152 10 3053 5741 90 472 887 I C 50 1213 2279 l 10 2209 4152 90 319 595 D 50 819 1530 l 10 1492 ,2787 90 235 433 E 50 603 1112 10 1098 2027 l 90 161 299 F 50 414 768 l v) f^ 10 754 1399 i l
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b No. 9788/220 l . t; i NUMBER A TTAC# MENT TITLE -- - REVISION ( EPIP-4.12 01
-l FACTORS CONTROLLING THE AREA A TTACNMENT
' AFFECTED BY A RELEASE FAGE 3 2 of 2
'1 1 4 Area Width - Feet Stability Percent of Class Maximum 1 Mile Distance - 2 Mile Distance 90 97 179 G 50 249 460 10 453 843 Wind speed affects the area by the fact that higher wind speeds cause the cloud to arrive sooner, but the concentrations are reduced. The affected area will be downwind of the release point, if the direction is variable, the area with the highest average downwind direction will be affected the greatest.
O[, k , O e m u)
) _ _ _ _ . _ _ _ . . . _ . _ . . _ . . _ . . _ . . _ . . _ _ . _ _ _ _ _ _ _ _ . _ _ _ . . __. . _. .
No.97887200
'l VIRGINIA ELECTRIC AND POWER COMPANY ,
L NORTH ANNA POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE { NUMBER PROCEDURE TITLE REVISION i 01 i EPIP-4.13 0FFSITE RELEASE ASSESSMENT WITH ENVIRONMENTAL DATA PAGE (With 4 Attachments) 6 PURPOSE Confirm onsite dose projections or decemine source term, using Environmental Monitoring data. l USER Radiological Assessment Director or Members of Dose Assessment Team. ENTRYCONDITIONS
- s. - Any of the following: ,
l 1) Activation by EPIP-4.03, Dose Assessment Controlling Procedure.
- 2) Activation by EPIP-4.12, Offsite Environmental Monitoring Instructions.
I NOT A CONTROLLED mc wNr VEPCO PROPERTY This docunent is the property of the l M 2 4 1982 Virginia Electric and Power Company NORn 'E and is to be returned upon request. No permicolon is granted to publich, h i
' reproduce. - trancnit or disclose to another any inforn:ation contained in this document.
REVISION RECORO REV. 01 PAGE(S): Entire Procedure DATE: 07-22-82 REV. PAGE(S) DATE: REV. PAGE(S) DATE: , REV. PAGE(S) DATE: l REV. PAGE(S) - DATE: REV. PAGE(S) DATE: REY. PAGE(S) DATE: O / A 0A ' RECOMMENDED APPROVED DA TE i n . 1 07-22-82 l
% CHAIRMANSTA TION NUCLEAR SAFETY AND OPERA TING COMMITTEE
------------'-------m
, No. 97847210 l
NUMBER PROCEDURE TITLE REV S ON i EPIP-4.13 0FFSITE RELEASE ASSESSMENT WITH ENVIRONMENTAL DATA PAGE
,l . I 2 of 7 4, -
_l Yl - STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED , l
-l.
i : 1. INITIATE PROCEDURE: a) Initiated By: Date: -
. Time:
- 2. USE OF ENVIRONMEVIAL DATA:
a) Offsite Environmental Data may be used for:
- 1) Confirm dose projection OR O '
- 2) If onsite release data from monitors and/or sample analysis is NOT
- 2) If onsite release data from monitors and/or sample analysis I_S,S available a Source Term available DO NOT (C1/SEC) may be determined estimate Source Term from environmental data
- 3. " CONFIRM DOSE PROJECTIONS:
a) Use offsite dose rate measure- a) If Source Term (Ci/SEC) ment to CONFIRM projected dose calculations are needed rate using Environmental Data, GO TO Step 8 OR Establish Real Time Dose Rate Offsite b) Insure measurements O_RR samples ~ b) If measurements are NOT taken are from centerline of taken from centerline of the plume the plume. GO TO Step 6, c) DOSE RATES may be obtained from:
- 1) Direct Measurements
- 2) Sample Analysis Data
....----%. . .. I.- , " . . .
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! No.s7:s7:to h NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.13 0FFSITE RZLEASE ASSESSMENT WITH ENVIRONMENTAL DATA PACE
, 3 of 7 i -
STEP l ACTION /lXPECTED RESPONSE RESPONSE NOT08TAINED I I NOTE: Sample analysis data of environmental sample should be used, when available, versus_ field analysis in determining 0FFSITE DOSE RATE.
- 4. DETERMINE WHOLE BODY OFFSITE DOSE RATE FROM DIRECT RADIATION READINGS:
a) Obtain from the monitoring a) If DOSE RATES are NOT from teams the centerline DOSE the centerline, GO TO Step 6 RATE
- 1) Log DATE, TIME, LOCATION, and DOSE RATE on Attachme6e N
b) The DOSE RATE from substep a_ may be considered the Whole Body Dose Rate c) Log DOSE RATE on Attachment 1
- 5. DETERMINE THYROID OFFSITE DOSE RATE FROM SAMPLE ANALYSIS:
a) Determine Offsite Dose Rate to a) If data from air sample is NOT the THYROID by using data from yet available, continue with air sample taken at centerline Step 6 until data is available of the plume l OR l l If sample is NOT taken at I centerline of the plume, GO TO l Step 6_ b) If sample data is given in b) If sample data is given in i COUNTS PER MINUTE obtain the uCi/mL, GO TO Substep c BACKGROUND COUNTS PER MINUTE l from the monitoring team (s) - 1 7 ( i x,_7 l
No.97887210 4 i l q l$ NUMBER PROCEDURE TITLE REVISION EPIP-4.13 0FFSITE RELEASE ASSESSMENT WITH ENVIRONMENTAL DATA PAGE
.j ;
.t I
t - STEP ACTION / EXPECTED RESPONSE - RESPONSE NOT08TAINED 1
; 1) Determine the NET COUNTS PER
'. MINUTE: -
SAMPLE (CPM) - BACKGROUND (CPM) = NET (CPM) l
- 2) Refer to Attachment 2 to ~ 2) If Net CPM is too large to determine Equivalent I-131 locate on the Attachmen::,
activity in uCi/mL divide the CPM by a power of i 10 to get on the graph, then Eltiply the activity (uci/mL) by the same power of 10, c) Determine Thyroid Dose Rate: ACTIVITY (uCi/ml) x 1.85 E+9 = MR/HR I O d) Log the DATE, TIME, LOCATION, and DOSE RATE on Attachment 1,,
- 6. OFF-CENTERLINE DOSE RATES: .
I a) If Dose Rates from Step ,5_ and a) If dose rates from Step 5 and Step 6_ were taken off-center- Step 6 are taken from the line, activate EPIP-4.10. centerline, GO TO Step ,7,. Determination of X/Q and return , to this step after determining
- 1) X/Q at the pe7endicular distance from unple location, on the centerline of plume
- 2) X/Q of the sample location b) Determine Estimated Centerline Dose Rate:
X/Q (Centerline) x Dose Rate (MR/HR) = DOSE RATE MR/HR X/Q (Sample Location) , c) Log the DATE TIME, LOCATION and DOSE RATE on Attachment 1,
- 1) Note in the Remarks Column that the sample was taken off centerline l
l.
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)
NUMBER PROCEDURE TITLE REVISION
/ 01
EPIP-4.13 .
OFFSITE RELEASE ASSESSMENT
'WITH ENVIRONMENTAL DATA PACE
, , 5 of 7 e
1 i
- STEP , ACTION / EXPECTED RESPONSE RESPONSENOT 08TAINE0 l 7. TRANSMIT DATA:
a) Upon completion of Attachment 1_, relay the Attachment to the Dose Assessment Team Leader.
- 8. DETERMINE SOURCE TERM: (Ci/SEC) a) Use Offsite Data to determine a) If Source Term data is NOT the Source Term (Ci/SEC) of the required, C0 TO Step g
. release b) Insure measurements or samples b) If data is NOT from the taken are from the centerline centerline of the, plume, of the plume GO TO Step 6 to estimate centerline data and return to this step c) Source Term may be estimated by:
- 1) Direct Measurements .
- 2) Sample Analysis Data
- 9. DETERMINE SOURCE TERM FROM DIRECT MEASUREMENTS:
a) Obtain centerline Dose Rate a) If Dose Rate measurements measurements are NOT from centerline od the plume, GO TO Step 6,to estimate centerline data and return to this step
. 1) Log the LOCATION, TIME and DOSE RATE on Attachment 3 I
- 2) Obtain the current Wind Speed and Stability Class b
u
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e. No. 97847210 4 i t 6
;N p NUMBER prs EDURE TITLE REVISION f .
~ 01 EPIP-4.13 0FFSITE RELEASE ASSESSMENT i WITH ENVIRONMENTAL DATA PAGE j 6 of 7
\ I 1
e
'f 7 STEP ACTION / EXPECTED RESPONSE RES!0NSENOTO8TAINED i
j b) ' Determine the CONVERSION FACTOR from Attachment 4 using the center-line DISTANCE from the planc 9 c) Determine the RELEASE RATE of EQUIVALENT XE-133 (CilSEC): MR/HR x 3.05 E-5 x WIND SPEED x CONVERSION FACTOR = Ci/SEC d) Log results on Attachments 3_
- 10. DETERMINE SOURCE TERM FROM SAMPLE ANALYSIS: -
O NOTE: This step may be used for Iodine samples taken in the field or Iodin a t and Gas samples returned to the' station for analysis, i ! a) Insure sample data is from a) If sample data is not from centerline of the plume centerline of plume, GO TO Step 6 to estimate centerline . data Tuse uCi/mi instead of data rate) and return to this step-b) Obtain uCi/ml measurements at b) If sample data received in sample location COUNTS PER MINUTE, GO TO Step 5, Substep b,.co determine activity uC1/ml) and return to this step l l 1) Log LOCATION, TIME and ACTIVITY on Attachment 3_
- 2) Obtain the current Wind Speed and Stability Class I
! O c) Obtain the CONVERSION FACTOR from l V, " Attachmeist 4_ using the centerline I DISTANCE from the plant e
- m___.____- m.. -
No. 973 e MIO f. f h NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.13 0FFSITE RELEASE ASSESSMENT
, WITH ENVIRONMENTAL DATA PAGE 1 7 of 7
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED l
d) DETERMINE THE RELEASE RATE ACTIVITY X WIND SPEED X CONVERSION FACTOR = Ci/SEC NOTE: Ci/SEC determined in Step 9,and Step 10, represent a release at some time PRIOR to the field measurement. ,To determine actual release time: TIME OF RELEASE = TIME OF MEASUREMENT - DISTANCE FROM PLANT WIND SPEED 1 Th- 11. TRANSMIT DATA:
)
~
i a) Upon completion of Attachment 3, I inform Dose Assessment Team Leader I of results l .
- 12. CONTINUED ASSESSMENT:
a) Relocate monitoring teams on a) If teams are to remain in the the advise of the Dose Assess- same location, GO TO Substep b ment Team Leader b) Return to Step 3 and repeat b) If the emergency has terminate <l assessment if the emergency or if the EOF has been manned, has NOT terminated or if the GO TO Step 1_3,3 , EOF is NOT manned
- 13. ADMINISTRATION:
a) Return all procedures and l Offsite data to the Radio-logical Assessment Director
- 14. PROCEDURE COMPLETION:
l l a) Completed By: l , Date: - Time: l (v }, END e . , - . - . . .,--%w..-. %w. we m . - = = - - . . . ---
~_ , . . -- a _- -.
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- _ _j No.97087220 Y
i _
' NUMBER A TTACHMENT TITLE REVISION
'}l' v.,, EPIP-4.13 01
}
0FFSITE ENVIRONMENTAL DATA SHEET ( - A TTACHMENT PAGE
*1 1 1 of 1 e
i s I s i i ! % DATE TIME LOCATION 1 WHOLE BODY THYROID DOSE RATE DOSE RATE (ar/hr) . ar/hr e REMARKS: l [
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