ML20071L591
| ML20071L591 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 07/29/1982 |
| From: | Joshua Wilson VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML18139C023 | List: |
| References | |
| PROC-820729-01, NUDOCS 8209220395 | |
| Download: ML20071L591 (615) | |
Text
{{#Wiki_filter:. No. 978872 30 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE O A ) V NUMBER PROCEDURE TITLE REVISION 00 EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE PAGE (With 1 Attachment) 1 of 8 PURPOSE To initially assess a potential emergency condition and initiate corrective actions. USER Shift Supervisor or Station Emergency Manager ENTRY CONDITIONS Q Any one of the following :
- 1. Another station procedure directs initiation of this procedure 0,,,R
- 2. A potential emergency condition is reported to the Shift Supervisor.
REVISION RECORD REV. 00 PAGE(S): ENTIRE PROCEDURE DATEUUL 2 S 1982 REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: APPROVAL RECOMMENDED APPROVED OA TE
/ 5MA-RAIRMAN STA TION NUCLEAR SAFETY UUL 2 0 W AND OPERA TING COMMITTEE 8209220395 820907 i PDR ADOCK 05000280 '
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No. 97847210 NUMBER PRGCEDURE TITL E REVISION b
- 00
*- EPIP-1.01 CMERGENCY MANAGER CONTROLLING PROCEDURE PAGE 2 of 8
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 1. INITIATE PROCEDURE:
. a) BY: DATE: TIME: NOTE: Continue through this and all further instructions unless otherwise directed to hold, i t
- 2. IDENTIFY EVENT:
O
\-
a) Event-TRANSPGRT OF CONTAMI- a) GO TO Step 2b t of this in-NATED INJURED PERSONNEL struction. 4 i
- 1) Initiate EPIP-5.01 Transport of Contami-nated Injured Personnel
- 2) Verify initiation of i EPIP-4.20. H.P. Actions i for Transport of Injured i Contaminated Personnel
- 3) Continue this instruction i
l b) Event-RADIATION RELEASE b) GO TO Step 2ctof this in- . struction.
- 1) Request Health Physics initiate EPIP-4.01, Radiological Assess-ment Director Controlling Procedure, and continue
- this instruction l
~ c) Event-FUEL HANDLING INCIDENT c) GO TO Step 2d of this in-struction. l i
No,97847210
~
NUMBER PROCEDURE TITLE REVISION O- EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE 00 PAGE - 3 of 8
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINEO
- 2. (CONTINUED)
- 1) Request llealth Physics initiate EPlP-4.01, Radiological Assessment Director Controlling
! Procedure, and continue this instruction
+ d) Event-SECONDARY RELEASE d) GO TO Step 2e of this in-struction.
- 1) Reques*. Health Physics i initiate EPIP-4.01, Radiological Assessment
{ Director Controlling Procedure, and continue this instruction i i e) Event-S/G TUBE RUPTURE e) C0 TO Step 2f,of this in-struction. i 1) Request llealth Physics ! initiate EPIP-4.01, , Radiological Assessment Director Controlling l 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.
O U
+
ru. n e sn so NUMBEff PROCEDURE TITLE REVISION 00 EPIP-1.01
- C$ EMERGENCY MANAGER CONTROLLING PROCEDURE PAGE 4 of 8 STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINEO CAUTION: Declaration of the highest emergency class for which an EAL is exceeded shall be made.
~
- 3. ASSESSMENT AND CLASSIFICATION:
a) Refer to EPIP 1.01, Attachment 1 Emergency Action Levels, index
- 1) Using index, determine event O category AND GO TO proper EAL tab AND
- 2) Evaluate event, deter-mine classification, AND GO TO Step 4 of this procedure
- 4. NOTIFICATION AND VERIFICATION:
a) TSC - NOT ACTIVATED a) Il[ TSC activated, CO TO Step 6,. b) Notify Operations Personnel
- 1) Superintendent of Operations G. Kane Attemot contact via' beeper
('_
+-emaw -wabA
_..._d O- .
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NUMBER PROCEDURE TITLE REVISION A 00 EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE PA GE . 5 of 8
- STEP ACTION / EXPECTED RESPONSE RESPONSENOT OBTAINED .
4 (CONTINUED)
- 2) SRO-On-Call S. Stevens .
Attempt contact via beeper S.E
.t. Peterson ,,
Attempt contact via beeper c) Verify classification d) H required by Alert, Site - C/' """'""""' " "*""'"' """'**""'- ~ ' request initiation of Standing - - ' Order 21 ' NOTE: Return to Step 2_ of this instruction as necessary during-the course of the situation for additional events and reclassification. , s v
- 5. VERIFY EALS EXCEEDED:
a) Assure EALs - EXCEEDED a) E EALs N0?qexceeded, DO NOT declare anremergency classification. . , _AN.D_ . . .
- 1) Continue appropriate- ,
7 _ correc)iveactio,dTnW g prc,cecures.- - '
."' .1 ,
, 2)-Go TO, Step 7 of thle- +
-procedure. .
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No. 9788 7210 NUMBER PROCEDURE TITLE REVISION ( 00
\
EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE 6 of 8
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 5. (CONTINUED) b) IF required, assign appropriate individual as interim Emergency Commun-icator c) IjF required, direct senior H.P.
personnel on site to initiate EPIP-4.01, Radiological Assessment Director Controlling Procedure
- 6. DETEm4INE EPIPS:
a) Event classification - UNUSUAL a) GO TO Step 6b,of this in-EVENT struction. C'a 1) GO TO EPIP-1.02, Response to Unusual Event b) Event classification - ALERT b) GO TO Step 6ci of this instruction.
- 1) GO TO EPIP-1.03, Response to Alert c) Event classification - SITE c) GO TO Step 6ji of this EMERGENCY instruction.
i
- 1) GO TO EPIP-1.04, Response to Site Emergency 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 u l s,
No.97887210
,,, NUMBER PROCEDURET1TLE REVISION
/ 00 EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE PAGE 7 of 8
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 7. (CONTINUED) b) GO TO Step ll,of this instruc-tion
- 8. TERMINATION NOTIFICATIONS:
a) Initiate termination notifi-cation to state and local governments IAW EPIP-2.01, Notification of State and Local Governments b) Initiate termination notifi-cation to NRC IAW EPIP-2.02, p~ Notification of NRC
\- / 9. REPORTING:
a) Verify required reports and notifications IAW EPIP-2.03, Reports to Offsite Agencies
- 10. RECOVERY ACTIONS:
a) Notify involved station personnel of emergency te rmination b) Initiate recovery actions b) II[ required recovery actions e IAW established station are determined to be beyond procedures and capabilities the scope of established procedures and capabilities GO TO EPIP-6.01, Reentry / Recovery Guidelines
- 11. ADMINISTRATION:
a) Notify Coordinator Emergency Planning to assure replacement of controlled EPIPs. I a
No 97887210 NUMBER PROCEDURE TITI.E REVISION 00 EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE PAGE 8 of 8
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 11. (CONTINUED) b) Forward completed EPIPs, forms and other applicable records to SNSOC for review c) IF, required, deactivate station emergency response facilities and personnel
- 12. TERMINATE EPIP-1.01:
a) COMPLETED BY: DATE: TIME: END
No.91897220 NUMBER A TTACHMENT TITLE REVISION
.h EPIP-1.01 00 s_ / EMERGENCY ACTION LEVEL TABLE A TTACHMENT PAGE 1 INDEX 1 of 39
******************************************************w*****r ************
CAUTION: Declaration of the highest emergency class for which an EAL is exceeded shall be made. 4 GO TO IF EVENT CATEGORY IS: TAB
- 1. Safety, Shutdown, or Assessment System Event ....................A s,
s,,) 2. Reactor Coolant System Event ....................................B
- 3. Fuel Failure or Fuel Handling Accident...........................C
- 4. Containment Event................................................D
- 5. Radioactivity Event..............................................E l
- 6. Contaminated Personnel ..........................................F
- 7. Loss of Secondary Cooling........................................G
! 8. Electrical Failure...............................................H l l
- 9. Fire.............................................................I I
I 10. Security Event...................................................J
- 11. Hazard to Station Operation......................................K
- 12. Natural Eventt ..................................................L l
, 13. Miscellaneous Abnormal Events....................................M l
\
l a l i 1
no siner220 NUMBER A TTACHMENT TITLE REVISION 0 EPIP-1.01 A TTACHMENT EMERGENCY ACTION LEVEL TABLE (TAB A) 00 PAGE 1 SAFETY, SHUTDOWN, OR ASSESSMENT SYSTEM EVENT 2 of 39 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 1. Non-transient ECCS Non-spurious ECCS Unusual Event initiation initiation as vali-dated by Emergency ABOVE CSD CONDITION Procedures
- 2. Non compliance with Unit (s) placed in HSD 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 POWER & HSB noncompliance with T.S.
Limiting Conditions for
. Operation
- 3. Loss of Function needed Total loss of the following: Site Emergency for unit HSD condition a) Charging /SI System ABOVE ISD CONDITION SE b) Main feedwater AND Auxiliary Feedwater Systems Systems
- 4. Loss of function need- a) Total loss of Sec- Alert ed for unit CSD con- ondary System cool-r dicion ing capability l
l l CSD b) Total loss of any of l the following systems:
- 1) Service Water SE
- 2) Component Cooling O n
- 3) Residual Heat Removal l
No. 91881220 m NUMBER A TTACHMENT TITLE REVISION EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB A) PAGE 1 SAFETY, SHUTDOWN, OR ASSESSMENT SYSTEM EVENT 3 of 39 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 5. 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 CONDITIO"S by accoustical or tem-perature monitoring equipment AND RCS pressure-LESS THAN i 1600 psig
- 5) Main Steam Excessive Steam Generator Safety, PORV, or Decay Heat Release flow as indicated by rapid RCS cooldown rate AND MS pressure is GREATER THAN 100 psi below set point of affected valve.
l
- 6. Failure of the Reactor Condition a) and b) Site Emergency Protection System to exists with c) l initiate and complete l
a requited trip while a) RX trip setpoint and at power coincidences - EXCEEDED POWER & HSB AND b) Manual Rx trip - INITIATED LJ ' AND Rx power indication-NOT DECREASING
No. 91887tt0 NUMBER A TTACHMENT TITLE REVISION f~h y EPIP-1.01 00 EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB A) PAGE I SAFETY, SHUTDOWN, OR ASSESSMENT SYSTEM EVENT 4 of 39 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 7. Failure of the Reactor a) Manual Ojt Automatic Rx Alert Protection System to trip - INITIATED complete a trip which takes the Rx Suberitcal AND
. POWER & HSB b) Intermediate Range Mo-nitor indicating-ZERO or POSITIVE SUR
- 8. Indications or alarms Unit placed in HSD or Unusual Event on process or effluent lower condition as a re-parameters required for sult of any of the following:
g-~x incident assessment NOT () functional in the con-trol room a) Containment Gaseous or Particulate Radiation AB0VE CSD CONDITION Monitors- NOT OPERABLE AND Backup grab sample capability - NOT AVAILABLE SE b) Meteorological monitor-ing instrumentation- LESS THAN minimum required to perform offsite dose calculations SE c) Post-accident instrument-ation-LESS'THAN minimum channels allowable per TS Table 3.7-6 h
two. 9788722C NUMBER A TTACHMENT TITLE REVISION
. EPIP-1.01 00 I
EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB A) PAGE I SAFETY, SHUTDOWN, OR ASSESSMENT SYSTEM EVENT 5 of 39 4 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 9. Loss of communications Complete failure of the Unusual Event capability following:
ALL CONDITIONS a) Station PBX phone system L AND b) Station Gai-Tronics system AND , c) Station UHF radio system
- 10. 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 i than 15 minutes during loss of unit computer for
- a unit transient GREATER THAN 15 minutes POWER & HSB AND Unit operational transient -
IN PROGRESS
- 11. 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 i POWER & HSB i
i
- 12. Evacuation of Main Con- Evacuation of the Control Site Emergency trol Room with control Room with local shutdown NOT established within control NOT established 15 minutes within 15 minutes ALL CONDITIONS
- 13. Evacuation of Main Con- Evacuation of the Control Alert trol Room required Room with shut down control ,
i estabifahed within 15 min-i ALL CONDITIONS utes
Pto. 97887220 NUMBER A TTACHMENT TITLE REVISION O EPIP-1.01 A TTACHMENT EMERGENCY ACTION LEVEL TABLE (TAB B) 00 PAGE 1 REACTOR COOLANT SYSTEM EVENT 6 of 39 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 1. Safety Limit-RCS Limits of T.S. Fig. Unusual Event Temperature / Pressure 2.1 EXCEEDED curve exceeded POWER & HSB
- 2. RCS overpressure 2735 psig RCS Unusual Event Pressure limit-EXCEEDED ALL CONDITIONS
- 3. Rx overpower 118% Rx thermal. Unusual Event power limit -
b\ POWER EXCEEDED LJ
- 4. RCS Irsk rate exceeds EP-2, Loss of Reactor Site Emergency 300 gpm Coolant - IMPLEMENTED AB0VE CSD CONDITION AD l Pressurizer level can not be maintained with two (2) or more Charging /SI Pumps in operation
- 5. RCS leak rate exceeds Unit in HSD cr lower cond- Alert 1 50 gpm ition as a ' result of actions required IAW AP-16, ABOVE CSD CONDITION Excessive Primary Plant Leakage AND RCS inventory balance indi-cates leakage-GREATER THAN 50_ gpm l
i
9tc. 978 81220 NUMBER A TTACHMENT TITLE REVISION EPIP-1.01 00 EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB B) PAGE 1 REACTOR COOLANT SYSTEM EVENT 7 of 39 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 6. RCS leak rate requiring Unit in HSD or lower Unusual Event plant shutdown IAW as a result of any T.S. 3.1.C of the following:
POWER & HSB a) Unidentified RCS leakage-GREATER THAN 1 gpm pR b) Identified leakage-GREATER THAN ,10_ gpm SE O c) Non-isolable fault of RCS pressure boundary
- 7. RCP locked rotor All the following Alert leading to fuel dam- exist:
age a) Flow in one or more POWER RC loops - LESS THAN 90% AND b) RCP trip caused by Phase Overcurrent Relay - ACTUATION AND c) High Range Letdown Radiation Monitor indication increases 5 to-GREATER THAN 5x10 cpm O
No. 97887220 NUMBER A TTACHMENT TITLE REVISION EPIP-1.01 00 O' A TTACHMENT EMERGENCY ACTION LEVEL TABLE
- (TAB B) PAGE 1 REACTOR COOLANT SYSTEM EVENT 8 of 39 CONDITION /
APPLICABILITY INDICATION CLASSIFICATION
- 8. Gross Primary to EP-4 Steam Generator Tube Site Emergency Secondary leakage with Rupture - IMPLEMENTED with loss of offsite power SI in progress ABOVE CSD CONDITION AND Condenser Air Ejector Exhaust - DIVERT to Containment AND Loss of offsite power indi-cated by zero volts on volt-ON meters for 4160V Buses D, E
&F
- 9. Excee41ve Primary to Unit in HSD or lower Alert ,
l Secondary leakage with condition as a result of . loss of offsite power actions required by T.S. 3.1.C.6 l ABOVE CSD CONDITION l AND l Loss of offsite power indicated by zero volts on voltmeters for 4160V buses D, E & F. O , v --. , ,v.- -- v- , . - - . - -
No. 97867210 REVISION (- NUMBER EPIP-1.01 PROCEDURE TITLE Q EMERGENCY ACTION LEVEL TABLE 00
, PAGE (TAB B) 1 REACTOR COOLANT SYSTEM EVENT 9 of 39
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CONDITION /
APPLICABILITY INDICATION CLASSIFICATION
- 10. Gross Primary to EP-4, Steam Generator Tube Alert Secondary leakage Rupture - IMPLEMENTED with SI in progress .
AB0VE CSD CONDITION AND Condenser Air Ejector Exhaust - DIVERT to Containment
- 11. Primary to Secondary Unit in HSD or lower con- Unusual Event leakage-GREATER THAN dition as a result of 1 gpm actions required by T.S.
(()S 3.1.C.6 AB0VE CSD CONDITION
- 12. Loss of 2 of 3 fission Any two of a),b) or c) General Emer-product barriers with exist and the third gency potential loss of 3rd is imminent barrier a) Fuel clad integrity fail-ALL CONDITIONS ure as indicated by any of the following:
- 1) RCS specific activ:'.ty -
GREATER THAN OR EQUAL TO 300.0 uCi/ gram dose equivalent I-131.
- 2) 5 or more core exit
, thermocouples reading-GREATER THAN 1200*F pR
- b) Loss of RCS integrity as l ((s) indicated by any of the following
i
No. 97887220 p NUMBER EPIP-1.01 A TTACHMENT TITLE REVISION 00 ('e) 4 EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB B) PAGE 1 REACTOR COOLANT SYSTEM EVENT 10 of 39 F CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 12. (CONTINUED)
- 1) RCS pressure has exceeded 2735 psig
- 2) EP-2, Loss of Reactor Coolant - IMPLEMENTED
- 3) Outside Containment High Range Gamma Radiation Monitor rgading-GREATER THAN 2x10 mR/hr pR, ID c) Loss of containment inte-
-/ grity as indicated by any of the following:
- 1) Containment pressure -
GREATER THAN 60 psia AND NOT DECREASING
- 2) Loss of containment I
integrity as defined in T.S. 1.0.H t 13. Fuel failure with steam Any two of a),b) or c) General Emer-l generator tube rupture exists and the third is gency I imminent ALL CONDITIONS a) Fuel clad integrity failure as indicated by any of the following:
- 1) RCS specific activity-GREATER THAN 300 uCi/
gram dose equivalent I-131
No. 97887220 NUMBER A TTACHMENT TITLE REVISION EPIP-1.01 00 A TTACHMENT
^ #
PAGE (TAB B) 1 REACTOR COOLANT SYSTEM EVENT 11 of 39 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 13. (CONTINUED)
- 2) 5 or more core exit thermocouples indi-cate-GREATER THAN 1200'F b) S/G tube rupture as indicated by both of the following:
- 1) RSC Low Pressure ,
SI - INITIATED
- 2) EP-4, Steam Generator Tube Rupture, -
IMPLEMENTED i i 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 -
IMPLEMENTED
so.orss72 o NUMBER A TTACHMENT TITLE REVISION O EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 00 ATTACHMENT (TAB'C) PAGE 1 FUEL FAILURE OR FUEL HANDLING ACCIDENT 12 of 39 I CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 1. Core damage with pos- Condition a) exists with Site Emergency sible loss of coolable b) geometry a) Fuel clad failure as ABOVE CSD CONDITION indicated by any of the following:
- 1) RCS Specific activity - GREATER THAN 6f[ uCi/ gram dose equivalent I-131
,2) High Range Letdown Radiation Monitor O. indicatiog-GREATER t
THAN 1x10 cpm AND b) Loss of cooling as in-dicated by any of the following: , 1) 5 confirmed core exit thermocouples - l GREATER THAN 1200*F
- 2) Core DT-ZERO
- 3) Core DT - RAPIDLY DIVERGING i 2. Severe Fuel Clad RCS specific activity - Alert Damage GREATER THAN 300.0 uCi/ gram dose equiva-l ABOVE CSD CONDITION lent I-131 OR O
1 l
- .. . _ . . . . - _ _ . . - . - ~ - - .
two.97687220 NUMBER A TTACHMENT TITLE REWSION EPIP-1.01 00
## " * ^ # U" # PAGE . A TTACHMENT (TAB C) 1 FUEL FAILURE OR FUEL HANDLING' ACCIDENT' 13 of 39
. CONDITION / ACCOUNTABILITY INDICATION CLASSIFICATION 4
- 2. (CONTINUED)
High Range Letdown Ra-diation Monitor indica-tion incrgases GREATER THAN 5x10 cpm within 30, minutes AND remains for at least 15 minutes
! 3. Fuel clad damage Unit shutdown required Unusual Event indication IAW action statement TS 3.4.8.b ABOVE CSD CONDITION QR
) :ligh Rang, Letdown Ra-diation Monitor indica-tion ingreases GREATER THAN 10 cpm within 30 minutes AND remains Er at least 15 minutes
- 4. Probable large radio- EP-2, Loss of Reactor General Emer-activity release ini- Coolant, - IMPLEMENTED, gency ated by LOCA with ECCS AND RCS specific failure leading to activity - GREATER core degredation THAN 300.0 uCi/ gram dose equivavent I-131 ABOVE CSL CONDITION AND ,
High or Low Head ECCS flow - NOT being delivered to the core
No.97887220
, NUMBER A TTACHMENT TITLE REVISION
) EPIP-1.01 00 EfERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB C) PAGE 1 FUEL FAILURE OR FUEL HANDLING ACCIDENT 14 of 39 CONDITION /
APPLICABILITY INDICATION CLASSIFICATION
- 5. Probable large radio- Loss of Main FW system and General Emer-activity release ini- Condensate System gency tiated by loss of heat sink leading to core AND degredation Loss of Auxilary FW System
\BOVE CSD CONDITION AND RHR System - NOT OPERABLE 6.
Probable large radio- Condition a) exists with General Emer-7- activity release ini- b) or c) gency t tiated by failure of
\
protection system to a) Rx nuclear power af ter bring Rx suberitical a trip remains-GREATER and causing core de- THAN 52' gredation b) RCS pressure - GREATER ABOVE CSD CONDITION THAN 2485 psig AND NOT decreasing c) Containment pressure and temperature are RAPIDLY INCREASING
- 7. Probable large radio- a) ECA-2, Loss of All ac General Emer-activity release init- Power - IMPLEMENTED isted by loss of AC and all feedwater AND ABOVE CSD CONDITION b) Turbine Driven Auxilary Feedwater Pump NOT OPERABLE AND
\
c) Restoration of a) or b)
-M above not likely within 2 hours
Peo. 97 8872 3 8 NUMBER PROCEDURE TITLE REVlSION EPIP-1.01 00 EMERGENCY ACTION LEVEL TABLE PAGE (TAB C) 1 FUEL FAILURE OR FUEL HANDLING ACCIDENT 15 of 39
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CONDITION /
APPLICABILITY INDICATION CLASSIFICATION
- 8. Probable large radio- Condition a) and b) exist Ge..eral Emer-activity release init- with c) or d) ger:y iated by LOCA with loss of ECCS and containment a) EP-2, Loss of Reactor cooling Coolant - IMPLEMENTED ABOVE CSD CONDITION AND b) High {gt Low Head ECCS flow NOT being delivered to the core AND ,
\
c) Containment RS sump temp-erature-GREATER THAN 190*F AND NOT DECREASING SE d) Containment Spray and Recir-culation Spray Systems- NOT OPERABLE
- 9. Major fuel damage Conditions a) or b) exist Site Emergency accident with radio- with c) acitvity release to containment or fuel a) Water level in Rx vessel buildings during refueling - BELOW TOP OF CORE ALL CONDITIONS SE b) Water level in Spent Fuel Pit verified - BELOW TOP OF SPENT FUEL j D U ^*"
~ , , - - - ,
No. 974 87220 r NUMBER A TTACHMENT TITLE REVISION EPIP-1.01 00 EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB C) PA GE 1 FUEL FAILURE OR FUEL HANDLING ACCIDENT 16 of 39 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 9. (CONTINUED) c) Verified damage to irrad-isted fuel resulting in readings on Ventilation VentGaseousMonigor-GREATER THAN 1x10 cpm
- 10. Fuel damage accident Condition a) exists with Alert with release of radio- b) or c) activity to containment O or fuel buildings ALL CONDITIONS a) Verified accident invol-ving damage to irradiated fuel AND b) Health Physics confirms fission product release from fuel 9.E c) Readings on the Ventilation VentGaseousMonigor-GREATER THAN 1x10 cpm i
I L
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hI ho.97487220 NUMBER A TTACHMENT TITLE REVISION O. EPIP-1.01 EMERCENCY ACTION LEVEL TABLE 00 A TTACHMENT (TAS D) PAGE 1 CONTAINMENT EVENT 17 of 39 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 1. Extremely high Con- Condition a) exists with General Emergency tainment radiation, b) or c) pressure and temp-pe ra t*2 re a) Outside Containment High Range Radiation Mgnitor -
GREATER TilAN 5x10 mR/hr AB0VE CSD CONDITION AND
, b) Containment pressure -
GREATER THAN 4_5, 5 psia AND is NOT decreasing O c) Containment temperature - GREATER THAN 280*F
- 2. High-high Containment Condition a) exists with Site Emergency radiation, pressure, b) or c) and temperature a) Outside Containment liigh Range Radiation Mgnitor -
! AB0VE CSD CONDITION GREATER THAN 2x10 mR/hr AND b) Containment pressure - GREATER THAN 23.0 psia and is NOT decreasing N i i c) Containment temperature - GREATER TilAN 200*F f3 Q! k
No. 918 81220 0 NUMBER EPIP-1.01 A TTACHMENT TITLE CHERGENCY ACTION LEVEL TABLE REVISION 00 A TTACHMENT (TAB D) PAGE 1 CONTAINMENT EVENT 18 of 39 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 3. High-high Containment Condition a) exists with Alert radiation, pressure b) or c) and temperature a) Outside Containment High ABOVE CSD CONDITION Range Radiation g Monitor -
GREATER THAN 10 mR/hr AND b) Containment pressure - GREATER THAN 17.7 psia O c) Containment temperature - GREATER THAN 150*F
- 4. Loss of Containment Unit has been placed in Unusual Event integrity HSD or lower condition due to a loss of con-I# tainment integrity as ABOVE CSD CONDITION defined by T.S.1.0.H and prescribed by T.S.
3.8.A l l \ l
-'N l (J
No.97867220
"% NUMBER A TTACHMENT TITLE REVISION EPIP-1.01 00 EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB E) PAGE 1 RADIOACTIVITY EVENT 19 of 39 CONDITION /
APPLICABILITY INDICATION CLASSIFICATION
- 1. Projected or actual a) Confirmed Health Physics General Emerg-site boundary doses assessments of site bound- ency exceed 2 R6m W.B. or ary actual or projected 12 Rem thyroid ex- doses indicate-GREATER posure THAN 2[ Rem whole body or 12[ Ree thyroid exposure ALL CONDITIONS SE b) Valid indications of the following exist:
- 1) Any Main Steam Line CI High Range Monitor indicates-G5 EATER TRAN 1.5x10 mR/hr 1
SE
- 2) Ventilation Vent High Range Monitor indicates-GgEATER TRAN 4.0x10 mR/hr EE
- 3) Process Vent High Range
+ ' Monitor indicates 3 GREATER THAN 2.7x10 mR/hr
- w. , ---..s n-e.. e y - .r-r,r-7-- - w -w-
no.orsertto NUMBER A TTACHMENT TITLE REVISION O' EPIP-1.01 EMERCENCY ACTION LEVEL TABLE 00 A TTACHMENT (TAB E) pAgg 1 RADIOACTIVITY EVENT 20 of 39 CONDITION / APPLICABIIITY INDICATION CLASSIFICATION
- 2. 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 exposure a) Any Main Steam Line High RangeMonitorindicages-ALL CONDITIONS GREATER THAN 7.5x10 mR/hr 2 b) Ventilation Vent High RangeMonitorindicages-GREATER THAN 2.0x10 [~ mR/hr in coincidence
\v} with Ventilation Vent Gaseous Monitor off scale hip,h i OR c) Process Vent High Range Monitorind{ cates-GREATER THAN 1.4x10 mR/hr S
d) Monitoring Team samples indicate doses of from j 0.5 to 2.0 Rem W.B. or l , I to 12 Rem thyroid ex-j posure at the site bound-ary l G i
No,97887220 3 NUMBER A TTACHMENT TITLE R[ VISION EMERGENCY ACTION LEVEL TABLE
~
A TTACHMENT (TAB E) PAGE 1 RADIOACTIVITY EVENT 21 of 39 CONDITION / 4 APPLICABILITY INDICATION CLASSIFICATION
- 3. 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 material a) Control Room Area Monitor b) Auxiliary Building Control ALL CONDITIONS Area Monitor c) Auxiliary Building Drum-f-~g ming Area Menitor d) Decontamination Building Area Monitor
, e) Fuel Pit Bridge Area Monitor f) New Fuel Storage Area Monitor g) Laboratory Area Monitor h) Sample Room Area Monitor 1 j. O
.. ,- ~ . - . - - - .
No. 97887220
% NUMBER A TTACHMENT TITLE REVISION EPIP-1.01 00 DiERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB E) PAGE 1 RADIOACTIVITY EVENT 22 of 39 f
i CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 4. Effluent Release Any of the following Alert
- GREATER THAN 10 monitors indicate TIMES T.S. instan- valid readings above j taneous allow- the specified values able limits ALL CONDITIONS a) Ventilation Vent Gaseous Monitog-GREATERTHAN 2.5x10 cpm b) Air Ejector Monitgr -
GREATER THAN 1x10 cpm AND Air Ejector exhaust NOT diverting to containment ! c)DischargeCanalMongtor-GREATER THAN 1.3x10 d) Process Vent Gaseous Monigor-GREATERTHAN 1x10 cpm for GREATER THAN M minutes 0) v
No.91887220 NUMBER A TTACHMENT TlHE REVISION ('} Q EPIP-1.01 00 EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB E) PAGE 1 RADIOACTIVITY EVENT 23 of 39 CONDITION / APPLICABILITY INDICATION CLASSIFICATION-
- 5. Effluent release Any of the following Unusual Event GREATER THAN T.S. monitors indicate valid allowable Limit readings above the spec-ified value J ALL CONDITIONS a) Ventilation Vent Gaseous Monitog-GREATER THAN 2.5x10 cpm b) Air Ejector Monitor -
5 GREATER THAN 3.5x10 cpm
/"N AND Air Ejector exhaust -
NOT diverting to contain-ment c)DischargeCanalMon{ tor-GREATER THAN 1.3x10 d) Process Vent Gaseous
, Monigor-GREATERTHAN 1x10 cpm for LESS THAN l
M minutes i a
Peo. 978 87220 NUMBER A TTACHMENT TITLE REVISION 0 EPIP-1.01 A TTACHMENT EMERGENCY ACTION LEVEL TABLE (TAB F) 00 PACE I CONTAMINATED PERSONNEL 24 of 39 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 CONDITIONS i
v 4 e ? 1 i
^* >;
s . ? No.97887220
,, ' N [s[ 't r ,, 's I
? b _k 3 ;
NUMBER A TTACHUEA T TITLE REVISION , (m EPIP-1.01 EMERGENCY ACTIOS LEVEL TABLE h _i 0 0. ._
~#
E. b' 1 A TTACHMENT ' (T AB G)' , PAGE 1 LOSS OF SECONDARY, COOLANT -25 of 39 , s
>_ _4+.- ,
. 1
^
~ [, . ',.
elw CONDITION /- APPLICABILITY INDICATION CLASSIFICATION
- 1. Major Secondary line Conditions a) and b) exist Site Emergency break with signif- wich' c), d) or e) icant Primary to ,
Secondary leakage and a) EP-3, Loss of Secondary fuel damage indicated _Cootant - IMPLEMENTED AND i varified non-spurious , ABOVE CSD CONDITION - 9 s'. - s AND i. g L-b) RCS specific activity - GEEATER THAN 300 uCi/
;Q[ r [k gram OR Letdown High R.inge Radiation Monitor -
#e b)
SREATER THAN,10 cpm s. AND . y c) Condenser Air Ejector Radiation Monitgr - , . .
,y y GREATER THAN 10 cpm '
.ye , ~, (
O_R, { , [' d)-Steam Generator Blow- -O'. downRadiationgonitor- ', YO GREATER THAN 10 cpm f 0.3 -
, j,
\ 6 e) MS Line High Rar.ge Radiation Monitor _,, '
GREATER THAN 7.5x10 '
~
mR/hr - 3 0 . O a
, _ - - y - -r_--
- -,w - - - . . . - . . . - ,. s._
no. sre e nso
-?; '
NUMBER A TTACHMENT TITLE REVISION ("'%[ LPIP-1.01 00 EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB G) PAGE 1 LOSS OF SECONDARY COOLANT 26 of 39 x -. CONDITION / a APPLICABILITY INDICATION CLASSIFICATION
,. 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. - IMPLEMENTED AND verified to be non-ABOVE CSD CONDITION spurious
.- AND
, b) Condenser Air Ejector
- Radiation Monitor -
0
-~g i GREATER TilAN 1x10 cpm OR c) Steam Generator Blow-downRadiationgonitor-GREATER THAN 10 cpm i
SE d) MS Line High Range
'i Radiation Monitor -
, GREATER TilAN 0.5 mR/hr
- 3. Major Secondary line EP-3, Loss of Secondary Unusual Event break Coolant. - IMPLEMENTED AND verified non-spurious ABOVE CSD CONDITION
- s
No. 97S S1220 NUMBER A TTACHMENT TITLE REVISION 0 EPIP-1.01 A TTACHMENT EMERGENCYACTIONLgVELTABLE (TAB H) 00 PAGE 1 ELECTRICAL FAILURE 27 of 39 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 CONDITIONS pR Loss of all 34.5KV Reserve Station Service Buses
- 2. Loss of off-site and The following conditions Site Emergency on-site AC power for exist for a period -
! more than 15 minutes GREATER THAN H minutes ALL CONDITIONS a) Ammeters for 4160V Reserve Station Service Buses D,E,& F all - ZERO (0) AMPS AND b) Ammeters for 4160V . Station Service Buses ! A,B & C all ZERO (0) AMPS AND c) Ammeters for 4160V Emergency Buses H & J both - ZERO (0) AMPS i
- 3. Loss of all off-site Ammeters for 4160V Reserve Alert and on-site AC power Station Service Buses D, E,
& F all - ZERO (0) AMPS i ALL CONDITIONS
^""
- O
- -- _ - ~ - --
i No. tis e rtto (" NUMBER A TTACHMENT TITLE REVISION EPIP-1.01 00 EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB H) PAGE 1 ELECTRICAL FAILURE 28 of 39 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 3. (CONTINUED)
Ammeters for 4160V Station Service Buses A,B,& C all - ZERO (0) AMPS AND i Ammeters for 4160V Emergency Buses H and J both - ZERO (0) AMPS
- 4. Loss of all on-site The following conditions Site Emergency DC power for-GREATER exist for a period -
THAN 15 minutes GREATER THAN 15, minutes ALL CONDITIONS a) All Station Battery volt-I meters - ZERO (0) VOLTS c AND b) No light indication available to Reserve Station Service Breakers ISD1, 15El and 15F1 I i
- 5. Loss of all on-site All Station Battery volt- Alert
- DC power meters - ZERO (0) VOLTS I
ALL CONDITIONS AND l No light indication avail-able to Reserve Station Service Breakers 15D1,15El O and 15F1
No.97887220 l NUMBER A TTACHMENT TITLE REVISION EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAD I) PAGE 1 FIRE 29 of 39 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 1. Fire resulting in de- Fire within the Station Site Emergency gradation of safety which causes major degrad-systems ation of a safety system function required for pro-ABOVE CSD CONDITION tection of the public AND Affected systems are caused to be NOT operable as defined by T.S.I.0.D and 3.02 O 2. Fire potentially affect- Fire within the Station ing station safety sys- which has potential for Alert tems causing a safety system NOT to be operable as defined by T.S.I.0.D AB0VE CSD CONDITION and 3.0.2
- 3. Fire lasting-GREATER Fire within the Station Unusual Event THAN 10 minutes which is not under con-trol within 10 minutes ALL CONDITIONS after fire fighting efforts begin O
LJ i
,~ _ _ . - -- . . . _ . _
no. on ento NUMBER A TTACHMENT TITLE REVISION O EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 00 A TTACHMENT (TAB J) PAGE 1 SECURITY EVENT 30 of 39 i CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 1. Loss of Station Shif t Supervisor has been General Emer-physical control informed that the security gency force has been neutralized ALL CONDITIONS by attack, resulting in loss of physical control of station SE i
Shif t Supervisor has been I informed of intrusion into one or more Vital Areas i which are occupied OR controlled by an aggressor
- 2. Imminent loss of Security Shif t Supervisor Site Emergency physical Station has notified the Shift control Supervisor of imminent intrusion into a Vital ALL CONDITIONS Area
- 3. Ongoing Security com- Security Shif t Supervisor Alert
! promise has notified the' Shift Supervisor of a confirmed ALL CONDITIONS unneutralized intrusion into the Protected Area l l 4. Bomb potentially Shif t Supervisor notifi- Alert l affecting station cation of a verified bomb { safety systems discovered on OR near a safety related system l ALL CONDITIONS + f'
eto.97eS1220 NUMBER A TTACHMENT TITLE REVISION O, EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 00 A TTACHMENT (TAB J) PAGE 1 SECURITY EVENT 31 of 39 C0hTITION/ APPLICABILITY INDICATION CLASSIFICATION
- 5. Security threat, un- Security Shift Supervisor Unusual Event authorized attempted has recommended Shift entry, or <ttempted Supervisor declare an sabotage Unusual Event IAW SEC-24 ALL CONDITIONS
- 6. Bomb threat or Shift Supervisor notifi- Unusual Event discovery cation of a bona fide bomb n
V ALL CONDITIONS threat OR-Shift Supervisor notifi-cation of bomb discovery within the Protected Area i O
No.97887220
- NUMBER A TTACHMENT TITLE REVISION I
O) ~EPIP-1.01 00 (~~/ EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB K) PAGE 1 HAZARD TO STATION OPERATION 32 of 39 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 1. Aircraft damage to Aircraft crash which affects Site Emergency vital plant systems vital structures by impact or fire ABOVE CSD CONDITION 2.
Aircraft crash on the Aircraft crash within the Alert facility Protected Area ALL CONDITIONS OR, Aircraft crash in Station Switchyard
\~ / 3. Aircraft crash or un- Confirmed notification of Unusual Event
. usual aircraft activity aircraft crash within the site boundary ALL CONDITIONS pR Unusual aircraft activity in the vicinity of the site as determined by the Shift Supervisor AND/OR Security Shift Supervisor
- 4. Severe explosive damage Explosion which results in Site Emergency severe degradation of any systems required for safe AB0VE CSD CONDITION shutdown:
I O
No. 91887tt0 s- NUMBER A TTACHMENT TITLE REVlSION (m j V EPIP-1.01 00 EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB K) PAGE 1 HAZARD TO STATION OPERATION 33 of 39 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 5. Explosion damage to Unplanned explosion result- Alert
- facility ing in damage to plant structure or equipment ALL CONDITIONS
- 6. Onsite explosion Confirmed report of un- Unusual Event planned explosion onsite ALL CONDITIONS
- 7. Entry of toxic or flam- Notification of uncontrolled Site Emergency mable gases into plant release of toxic OR flam-vital areas mable agents above life O ABOVE CSD CONDITION threatening or explosive limits into Vital Areas AND Any of the following occur:
a) Evacuation of Vital Area required OR b) Degradation of safety systems resulting in loss of a safety system function required for protection of the public
- 8. Entry of toxic or flam- Notification of uncontrolled Alert mable gases or liquids release of toxic OR flam-into plant facility mable agent which cause:
a) Evacuation of personnel from plant areas ALL CONDITIONS AND
\- / b) Safety related equipment is rendered inoperable
. . _. .= .. -
No. 91S S1220 NUMBER A TTACHMENT TITLE REVISION EPIP-1.01 00 EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB K) PA GE 1 HAZARD TO STATION OPERATION 34 of 39 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 9. 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 CONDITIONS personnel OR equipment
- 10. Severe missile damage Missile iapact causing Site Emergency to safety systems severe degradation of safety systems required for unit ABOVE CSD CONDITION shutdown O
O
- 11. Missile damage to a) Notification of missile Alert 4 safety related impact causing damage equipment or to safety related equip-structures ment or structures i
i ABOVE CSD CONDITION i 12. Turbine failure a) Failure of Turbine / Alert with penetration Generator rotating equip-ment resulting in casing POWER penetration Q G. i
No.97887220 NUMBER A TTACHMENT TITLE REVISION lm) EPIP-1.01 00
\/ EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB L) PAGE I NATURAL EVENTS 35 of 39 CONDITION /
APPLICABILITY INDICATION CLASSIFICATION
- 1. Earthquake greater Earthquake which activates Site Emergency than DBE levels the Event Alarm on the Strong Motion Accelerograph ABOVE CSD CONDITION AND AP-37, Seismic Event, calculations indicate horizontal motion of 0.15g 0FL GREATER pR I'^ Safety related systems are
\s - significantly degraded by earthquake
- 2. Earthquake greater Confirmed earthquake which Alert than OBE levels activates Event Alarm on the Strong Motion Accel-
/.L CONDITIONS erograph AND AP-37, Seismic Event, calculations indicate horizontal motion of 0.07g OR GREATER 9_R Safety related equipment is rendered inoperable by earthquake
- 3. Earthquake detected Confirmed earthquake which Unusual Event activates the Event Alarm ALL CONDITIONS on the Strong Motion
[~
\,__ )) Accelerograph
No. 918 81220 y NUMBER A TTACHMENT TITLE REVISION EPIP-1.01 00 EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB L) PAGE 1 NATURAL EVENTS -36 of 39 CONDITION / APPLICABILITY INDICATION CLASSIFICATION 4 Tornado striking Tornado visually detected Alert facility striking within the Pro-tected Area or Switchyard ALL CONDITIONS
- 5. Tornado onsite Tornado visually detected Unusual Event onsite ALL CONDITIONS
- 6. Severe winds Sustained severe winds in. Site Emergency (s - excess of 100 mph caused by AB0VE CSD CONDITION Hurricane, Tornado Oft other severe weather condition
- 7. Extreme winds Sustained extreme winds in Alert excess of 8f) mph caused by ABOVE CSD CONDITION Hurricane OR other severe weather conditions
- 8. High winds Any of the following: Unusual Event ALL CONDITIONS a) System Operator notifi-cation of Hurricane watch for Surry County SR-b) Sustained wind speed onsite measured OR
, projected to be in ex-cess of 73 mph
No. 97887220 NUMBER A TTACHMENT TITLE REVISION
! 0 EPIP-1.01 A TTACHMENT EMERGENCY ACTION LEVEL TABLE (TAB L) 00 PAGE 1 -NATURAL EVENTS 37 of 39 CONDITION /
APPLICABILITY INDICATION CLASSIFICATION
- 9. Flood or low Nater Flood in the James River Site Emergency level above design with indicated level -
levels GREATER THAN +27 feet MSL ALL CONDITIONS OR Low water level in the James River with indicated level - LESS THAN -9, feet MSL as indicated by loss of Emergency SW Pump suction
- 10. Flood or low water Flood in the James River Alert level near design with indicated level -
levels GREATER THAN +21 feet MSL ALL CONDITIONS SE Low water level in the Surry Power Station intake canal with indicated level - LESS THAN _18, feet AND DECREASING
- 11. Flood or low Flood in the James River Unusual Event
[ water level with indicated level - GREATER THAN +12 feet MSL l ALL CONDITIONS f SE Low water level in the Surry Power Station intake
- canal with indicated level-LESS THAN 18 feet AND NOT
! INCREASING ~~ l l 1 \ G
No. 918 81220 NUMBER A TTACHMENT TITLE REVISION
. EPIP-1.01 00
\'s EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB M) PAGE 1 MISCELLANEOUS ABNORMAL EVENTS 38 of 39
~ CONDITION /
APPLICABILITY INDICATION CLASSIFICATION
- 1. Any major internal or Shift Supervisor / Station General Emer-external events which Emergency Manager judge- gency singlely or in combin- ment ation cause massive damage to station fa-cilities ALL CONDITIONS
- 2. Station conditions Shift Supervisor / Station. Site Emergency which warrant activation Emergency Manager judgement of emergency facilities j monitoring teams or pre-
cautionary notification to the near-site public ALL CONDITIONS
- 3. Station conditions Shift Supervisor / Station Alert which warrant precau- Emergency Manager judgement tionary notification to the near-site public ALL CONDITIONS
- 4. 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 CONDIT0NS a) Unit (s) placed in a HSD or lower condition as a result of noncompliance 4 with T.S. Limiting Con-dition for Operation O .
=
4
No. ore srazo I- NUMBER A TTACHMENT TITLE REVISION EPIP-1.01 00 EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB M) PAGE 1 MISCELLANEOUS ABNORMAL EVENTS 39 of 39 r i I CONDITION / , APPLICABILITY INDICATION CLASSIFICATION l l 4 (CONTINUED) b) Unit shutdown is other , than a controlled shutdown i c) Unit is in an uncontrolled condition during operation 2 d) A condition exists which has the potential for i escalation and, therefore. I warrants notification l i f i 4 i E f
- O f
1
~-
'.o.97487230 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCEOURE TITLE REVISION 00 EPIP-1.02 RESPONSE TO UNUSUAL EVENT PAGE (With No Attachments) 1 of 7 PURPOSE To provide guidance to the Station Emergency Manager during the progress of a classified UNUSUAL EVENT emergency.
USER Station Emergency Manager ENTRY CONulTIONS
- 1. Entry From EPIP-1.01, Emergency Manager Controlling Procedure.
i l l l REVISION RECORO REV. 00 PAGE(S): Entire Procedure DATE:JUL 2 91982 REV. PAGE(S): DATE: I REY. PAGE(S): DATE: l REV. PAGE(S): DATE: i REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: APPROVAL RECOMMENDED A ROVED DA TE U j
/, Wbs ~ OULO 8
[CdAIRMANSTA TION NUCLEAR SAFETY Q AND OPERA TING COMA *lTTEE l t
Pso. 97 887210 NUMBER PROCEDURE TITLE REVISION O \~ l EPIP-1.02 RESPONSE TO UNUSUAL EVENT 00 PAGE 2 of 7
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 1. INITIATE PROCEDURE:
a) Declare position of Station Emergency Manager b) BY: DATE: TIME: NGTE: The Shift Supervisor may be relieved as Station Emergency Manager LAW the SPS Emergency Plan.
- 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 30 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, Attachment 1
- 4. CALL OUT OF PERSONNEL:
a) If required, call out appropriate personnel using Emergency ()/ s-- Personnel Notification List, Attachment 1, EPIP-3,01, Call-Out of Emergency Response Personnel
Peo. 97887219 NUMBER PROCEDURE TITLE REVISION A < - 00 t
\~- EPIP-1.02 RESPONSE TO UNUSUAL EVENT PAGE 3 of 7
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 5. EVALUATE STATION CONDITIONS:
a) Unit (s) are NOT affected by a) IF a unit is affected, emergency condition evaluate safe operation of unaffected unit.
- 1) Evaluate safety of any operating unit (s) AND
- 2) Consider unit (s) shutdown Consider unit shutdown if if emergency conditions so conditicns so indicate.
indicate
- 6. EVALUATE ONSITE PROTECTIVE MEASURES:
n a) Verify EPIP-4.01, a) Direct activation of [/x-- Radiological Assessment EPIP-4.01, Radiological' 3 Director Controlling Assessment Director i Procedure activated Controlling Procedure b) Evaluate requirement for limited onsite evacuation
- 1) IF, required, sound EMER-GENCY Alarm and make'appro-priate announcement using Gai-Tronics system c) Evaluate requirement for accountability
- 1) I_F, required, direct security to initiate EPIP-5.03, Personnel i Accountability d) Evaluate requirement for radiological protection
- 1) Consult with Radiological Assessment Director
A s Pto. 97887210 NUMBER PROCEDURE TITLE REVISION 00 EPIP-1.02 RESPONSE TO UNUSUAL EVENT PAGE 4 of 7
- STEP -
ACTIONiEXPECTED RESPONSE RESPONSE NOTOBTAINED
- 6. (CONTINUED)
- 2) Initiate protective measures as required
- 7. FOLLOW-UP SIATE AND LOCAL GOVERNMENT NOTIFICATION:
a) Verify updated Health a) Continue in this procedure Physics dose assessments complete b) Verify timely follow-up b) Direct initiation of gg notification IAW EPIP-2.01, Notification ( I EPIP-2.01, of State and Local Notification of State and Governments. Local Governments NOTE: Updates to state and local governments should be provided at approximately 30 minute intervals. i
- 6. FOLLOW-UP NRC NOTIFICATION:
f a) Verify follow-up NRC notifi- a) Direct initiation of i IAW EPIP-2.02, Notification EPIP-2.02 Notification of of NRC, Attachment 2 NRC.
- 9. ADDITIONAL REPORTING:
j a) Initiate evaluation of re-porting criteria IAW EPIP-2.03, Reports to Offsite Agencies b) IF, required, initiate EPIP-2.03, Reports to Offsite Agencies
- - - - .. . ~ - -
No. 97887210 NUMBER PROCEDURE TH"LE' REVISION O g 00 EPIP-1.02 RESPONSE TO UNUSUAL EVENT PAGE 5 of 7
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 10. CHECK RADIOLOGICAL CONDITIF;S: '
a) Radiological conditions - a) IF NOT stable OR improving STABLE OR IMPROVING confer with Superintendent of Operations and Radio-logical Assessment Director. AND Initiate further mitigating actions.
- 11. CHECK UNIT CONDITIONS:
a) Reactor plants - STABLE a) IF NOT stable confer with fg Supt. of Operations /SRO-On-( Call 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 availiable, confer Operations and Superinten- with senior maintenance dent of Maintenance evaluate personnel onsite, evaluate extent of damage c) Evaluate following assist-ance requirements
- 1) Offsite Technical
- 2) Additional personnel
- 3) Material and Equipnent d) Initiate emergency repairs as required IAW approved Station Procedures D
o
No, 974872 3 0
, NUMBER PROCEDURE TITLE REVISION h
V EPIP-1.02 RESPONSE TO UNUSUAL EVENT 00 ' PAGE 6 of 7
- STEP ACTION / EXPECTED RESPONSE ---
RESPONSE NOT OBTAINED l
- 13. VERIFY CLASSIFICATION:
a) Review EPIP-1.01, Attach-.
- E ner event identified or ment 1 Emergency Action emergency escalated, GO TO Level, TPEN, GO TO Step Step M of this procedure.
13.b AND b) Verify no additional events Notify Radiological Astess-have occurred and emergency ment Director. has NOT escalated
- 14. CHECK FOR TERMINATION:
a) Verify EALs - NOT EXCEEDED .a) IF EALs are still exceeded, 5 turn to Step 4_ or this
\/ AND instruction.
b) Verify plant condition - b) E unstable, evaluate and SAFE AND STABLE return to Step 4_.of this instruction. AND c) Onsite and offsite response c) Continue monitoring and re-personnel - NOT REQUIRED turn.to Step 4_ of this in-l struction. ?
- 15. EMERGENCY TERMINATION:
a) Close-Out
- 1) Initiate written summary to offsite authorities within
! 24 hours
- 2) COMPLETED BY:
DATE: TIME: m I l
-._-___ ., - ~ - . , . . _ - - .. - _ . . _ _ ,
No. 9788721C NUMBER PROCEDURE TITLE REVISION 00 k/ EPIP-1.02 RESPONSE TO UNUSUAL EVENT PAGE 7 of 7
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 15. (CONTINUED) b) GO TO EPIP-1.01, Emergency Manager Controlling Proce-dure Step 8_
- 16. TERMINATE EPIP-1.02:
a) Close-Out
- 1) Initiate written summary to offsite authorities within 24 hours
- 2) COMPLETED LY:
(n DATE: TIME: b) GO TO EPIP-1.01, Emergency Manager Controlling Procedure Step 4_ l
Peo. 97887230 VIRGINI A ELECTRIC AND POWER COMPANY SURRY POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE O V. NUMBER PROCEDURE TITLE REVISION 00 EPIP-1.03 RESPONSE TO ALERT PACE (With No Attachments) 1 of 12 PURPOSE To provide guidance to the Station Emergency Manager during the progress of a classified ALERT emergency. USER Station Emergency Manager ENTRYCONDITIONS
- 1. Entry from EPIP-1.01, Emergency Manager Controllinc Procedure.
'J REVISION RECORO REV. 00 PAGE(S): Entire Procedure DATE:JUL 2 9 1982 REV. PAGE(S): DATE:
l REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: , APPROVAL RECOMMENDED APPROVED DA TE
/ , UL 2 9 1932
/ CHAIRMAN stall 0N NUCLEAR SAFETY AND OPERA TING COMMITTEE
- , - .- .- .-,--,.,e., - - - , ~ - --w. - ,,,-
ho.97887219 NUMBER PROCEDURE TITLE REVISION (b' ) 00 EPIP-1.03 RESPONSE TO ALERT PAGE 2 of 12
- STEP ACTION / EXPECTED RE:PONSE l 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 SPS Emergency Plan.
- 2. INPLANT TOTIFICATION:
a) Make announcement on station Gai-Tronics system as follows:
- 1) "An ALERT has been declared"
- 2) "All Emergency Response personnel report to their assigned stations" r
b) Repeat Step 2.a. THEN continue this instruction
- 3. CALLOUT OF PERSONNEL:
a) Verify Emergency Response a) Direct Security to initiate Personnel - ONSITE EPIP-3.01, call out of Emergency Response Personnel. AND
No.91851210 NUMBER PROCEDURE TITLE REVISION i O EPIP-1.03 RESPONSE TO ALERT 00 PAGE 3 of 12
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 3. (CONTINUED)
CO TO Step 4 of this instruction, b) Direct Security to activate , Corporate Emergency Response Team by calling General Of fice Security IAW Attachment 1, EPIP-3.01, Call-Out of Emergency Response Personnel l 4. STATE AND LOCAL GOVERNMENT NOTIFICATION: a) Initiate EPIP-2.01, (s s-Notification of State and Local Governments NOTE: Updates to state and local governments should be provided at approximately 30 minute- intervals and after significant changes to plant status, radiological data, or meteorological data. ! 5. NRC NOTIFICATION: a) Initiate EPIP-2.02, Notification of NRC, Attachment 1
- 6. EVALUATE STATION CONDITIONS:
I a) Unit (s) are NOT affected a) Il[ a unit is affected, by emergency condition evaluate safe operation of unaffected unit.
- 1) Evaluate safety of any operating unit (s) AND
- 2) Consider unit (s) shutdown Consider unit shutdown if if emergency conditions conditions so indicate.
Ox-- so indicate
No. 978 8722 0 NUMBER PROCEDURE T1TLE REVISION EPIP-1.03 RESPONSE TO ALERT PAGE 4 of 12
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINEO
- 7. VERIFY OFIERGENCY CENTERS /
FACILITIES: a) All emergency centers and a) GO TO Step 8 of this facilities - ACTIVATED instruction, b) GO TO Step 11 of this instruction
- 8. VERIFY TSC ESTABLISHED:
a) Check TSC NOT previously a) GO TO Step 9,of this in-activated struction, b) Relieve the Shift Supervisor b) j][ no Shift Supervisor as Station Emergency Manager relief GO TO Step 9, and return to Step 8,, ( when appropriate.
- 1) BY:
DATE: TIME: i c) If desired, relocate Station Emergency Manager position to TSC ! d) Announce Station Emergency Manager name and location to offsite authoritfes I c) Verify TSC - ACTIVATED e) Initiate activation of TSC l IAW EPIP-3.02, Activation I of Technical Support Center.
- 9. VERIFY OSC ESTABLISHED
a) Check OSC NOT previously a) CO TO Step 10 of this in-I activated struction. O 1 l I _ - . _ . _ - . . .,y _. , .-, _._,_e - , -
No.97887230 NUMBER PROCEDURE TITLE REVISION 00 N- ' EPIP-1.03 RESPONSE TO ALERT PAGE 5 of 12
- STEP ACTION! EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 9. (CONTINUED) b) Direct on-duty mechanical foreman to assume position of interim OSC Director c) Direct activation of OSC IAW EPIP-3.03, Activation of Operational Support Center
- 10. VERIFY EOF ESTABLISHED:
a) Check EOF NOT previously a) GO TO Step 11,of this in-activated instruction. [ \ b) Direct Security to activate EOF IAW EPIP-3.04, Activation of Emergency Operations Facility
- 11. 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 12,. b) Check status of EPIP-4.01, Radiological Assessment Director Controlling Procedure c) Verify Onsite Monitoring Team - ACTIVATED
- 12. CHECK RADIOLOGICAL CONDITIONS:
4 a) Radiological conditions - a) Confer with Radiological STABLE Of[ IMPROVING Assessment Director and Emergency Operations 1 Director
No. 97887210 NUMBER PROCEDURE 11TLE REVISION ( i 00
\- EPIP-1.03 RESPONSE TO ALERT PA GE 6 of 12
- STEP ' ACTION / EXPECTED RESPONSE RESPONSE NOTDETAINEO
- 12. (CONTINUED)
AND Initiate approprinte mitigating actions
- 13. CllECK UNIT CONDITIONS:
a) Reactor plants - STABLE a) )); TSC activated confer with Emergency Operations Director, IJ,NOT confer with SRO-On-Call. AND Initiate appropraite miti-I T' gating actions. 14 DAMAGE CONTROL: a) Damage to Station equip- a) GO TO Step 15,. ment has been verified b) With Emergency Operations b) IF TSC NOT activated confer and Maintenance Directors, with senior operations and evaluate extent of damage maintenance personnel onsite, c) Evaluate following assist-ance requirements
- 1) Offsite Technical
- 2) Additional personnel
- 3) Material and Equipment d) Direct Emergency Maintenance d) JJ[ NOT available, initiate Director to initiate interim damage control ac-EPIP-5.08, Damage Control tivities.
d4,, b. Peo. 97867214 ' 5 NUMBER PROCEDURE TITLE REVI510h x 00 EPIP-1.03 RESPONSE TO ALERT PAGE 7 of 12 s b %
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OCTAINEO s
- 15. EVALUATE ONSITE CONDITIONS: -
2, a) Evaluate requirement for accountability or limited , on site evacuation b) E required, direct Control b) 'IF accountability or Room personnel to sound the evacuation NOT required, ' j EMERGENCY Alarm GO TO St'op H. - c) If accountability required, c) E only limited on' cite make announcement on station evacuation required, make ' Gai-Tronics system as follows: appropriate' announcement using station Gab-Tronics ;
"All personnel not responding system.
to the emergency report to - your Emergency Assembly Area" , d) Repeat Step 15.b and 15.c
~
THEN continue with this , instruction _
- 16. INITIATE ACCOUNTABILITY:
-/
a) IF required, direct Security to initiate EPIP-5.03, . Personnel Accountability
- 17. FOLLOW-UP STATE AND LOCAL W GOVERNMENT NOTIFICATION:
a) Verify updated Health Physics dose assessments complete
~
b) Verify timely follow-up b) Initiate EPIP-2.01, state and local government - Notification of Stat.e and notification IAW EPIP-2.01, Local Governments. Notification of State and Local Governments ' l l l p b 9 -,w---ye oev = .-,i -, --r -
-_.a4
, no.orsar:
NUMBER PROCEDURE TITLE REVISION 00 EPIP-1.03 RESPONSE TO ALERT PAGE 8 of 12 f STEP ACTIONiEXPECTEC AESPONSE RESPONSE NOT OSTAINED NOTE: Updates to state and local governments should be provided at approximately 30 minute intervals. 4
- 18. FOLLOW-UP NRC NOTIFICATION:
4 a) Verify follow-up NRC a) Initiate EPIP-2.02, notification IAW, EPIP-2.02, Notification of NRC. Notification of NRC, Attachment 2
' 19 . ADDITIONAL REPORTING:
a) Direct the Emergency Administrative Director to evaluate reporting I I 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) IF, accountability taken, a) Direct initiation of verify all personnel EPIP-5.02 Search and accounted for IAW EPIP-5.03, Rescue. Personnel Accountability
- 21. SITE EVACUATION:
a) Radiological Assessment a) GO T3 Step 24. Director recommends Site evacuation b) Consider the following:
- 1) Onsite dose GREATER THAN l_ Rem whole body OR_ GREATER THAN 5, Rem Thyroid
~
( 2) Direction of plume travel
No.91SS7210 NUMBER PROCEDURE TITLE REVISION [ l 00 (s_/ EPIP-1.03 RESPONSE TO ALERT PA GE
, 9 of 12
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 22. INITIATE SITE EVACUATION:
a) Initiate EPIP-5.05, Site Evacuation
- 23. EVACUATION NOTIFICATIONS:
a) Notify state and local govern-ments 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 O
- 24. DIERGENCY 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:
a) On recommendation of a) GO TO Step 25. Radiological Assess-ment Director evaluate issuance of Radiciodide blocking agent to onsite personnel if following exist
- 1) Projected onsite total absorbed dose equiva-lent I-131-GREATER THAN 10 Rem Ci
, 4 \ss[
. _ _- . . - . . _ - . _ _. . _ - _ . -. _ ~ . - .
No. 978 8 7210 NUMBER PROCEDURE TITLE REVISION O EPIP-1.03 RESPONSE TO ALERT 00 PAGE 10 of 12 1
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 1
- 25. (CONTINUED) 2R
- 2) Actual onsite total absorbed dose equiv-alent I-131-GREATER THAN 10 Rem b) Direct Radiological Assessment Director to initiate EPIP-5.07, Administration of Radioprotective Drugs
- 26. VERIFY EVENTS:
a) Review EPIP-1.01, Attach-ment 1, Emergency Action Levels THEN, GO TO Step 26.b b) Insure additional events b) Initiate station APs, EPs, have NOT occurred or EPIPs to address new events. AND Notify Radiological Assess-ment Director AND Insure initiation of EPIP-2.01, Notification of State 1 and Local Governments and EPIP-2.02, Notification of NRC c) Check that emergency has c) Il[ escalated, GO TO Step 2j[ NOT escalated of this procedure. O
Peo. 9 745 7210 NUMBER PROCE00RE TITLE REVISION 00 EPIP-1.03 RESPONSE TO ALERT PAGE j 11 of 12 0
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 27. CHECK FOR TERMINATION:
3 a) Verify EALS - NOT EXCEEDED a) IF,EALS F are still exceeded, i CO TO Step 28. AND b) Verify plant conditions - b) Evaluate conditions and SAFE AND STABLE C0 TO Step 6_. AND , c) Onsite and offsite response c) Continue monitoring activi-personnel - NOT REQUIRED ties and GO TO Step 28. d) C0 TO Step 30 for termination
- 28. CHECK FOR RECLASSIFICATION:
a) Step M indicates event a) GO TO Step 6_ of this in-severity - REDUCED struction, b) Reclassify event and CO TO Step H for procedure termination
- 29. TERMINATE EPIP-1.03:
a) Verify Recovery Manager i concurrence IF EOF I activated b) Close-Out
- 1) Initiate written summary to offsite authorities within 8 hours i
.I
- 2) COMPLETED BY:
l DATE: TIME:
Peo. 97847210 NUMBER PROCEDURE TITLE REVISION O EPIP-1.03 RESPONSE TO ALERT 00 PAGE 12 of 12
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OPTAINED J
l
- 29. (CONTINUED) c) GO TO EPIP-1.01, Emergency Manager Controlling Pro-cedure, Step 4_
- 30. EMERGENCY TERMINATION:
a) Verify Recovery Manager concurrence U EOF activated b) Close-Out
- 1) Initiate written summary to offsite authorities within 8, hours
- 2) COMPLETED BY:
DATE: TIME: c) GO TO EPIP-1.01, Emergency Director Controlling Pro-cedure, Step 8_ END i
,___v ..-- - ,_ _.e. .
.. v-r- --w--
Peo.97887230 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCEDURE TITLE REVISION - 00 EPIP-1.04 RESPONSE TO SITE EMERGENCY PAGE
.(With No Attachments) 1 of 13 PURPOSE
- 1. To provide guidance to the Station Emergency Manager during the pro-gress of a classified SITE emergency.
USER Station Emergency Manager ENTRY CONulTIONS O 1. Entry from EPIP-1.01, Emergency Manager Controlling Procedure. J! I REVISION RECORD REV. 00 PAGE(S): Entire Procedure DATEdVL 2 91982 REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: l REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. 'PAGE(S): DATE: I ' APPROVAL RECOAfAfENDED APPROVED DA TE l s l'm'& (LdAn
. HAIR & FAN STA TION NUCLEAR SA FETY NL E U W AND OPERA TING COAfAf/TTEE i
( -
No.97887230 NUMBER PROCEDURE TITLE REVISION 00 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 SPS Emergency Plan.
- 2. INPLANT NOTIFICATION:
a) From the Control Room, sound the EMERGENCY Alarm b) Make announcement on station Gai-Tronics system as follows:
- 1) "A SITE EMERGENCY has been declared"
- 2) "All Emergency Response personnel report to their assigned stations" l 3) "All other personnel report to their Emer-gency Assembly Areas" c) Repeat Steps 2.a and 2.b, j THEN continue this in-i struction t
O l 1 I . - . , , . , . - , . - , . . _ . . .- - _--, . - - . , - - - . . . , , . - . .- - - .- --
No,97887210 NUMBER PROCEDURE TITLE REVISION EPIP-1.04 RESPONSE TO SITE EMERGENCY , PAGE 3 of 13
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 3. ONSITE ACCOUNTABILITY:
a) Direct Security to initiate
- Notify Security Shift EPIP-5.03, Personnel Account- Supervisor via PBX-#346 ability b) Direct Security to initiate EPIP-5.04, Access Control
- 4. CALLOUT OF PERSONNEL:
a) Verify Emergency Response a) Direct Security to initiate Personnel - ONSITE EPIP-3,01, Call out of Emer-gency Response Personnel. GO TO Step 7 of this instruction. b) Direct Security to activate Corporate Emergency Response Team by calling General Office Security IAU Attach-ment 1. EPIP-3.01, call-out of Emergency Response Per-sonnel
- 5. STATE AND LOCAL GOVERNMENT NOTIFICATION:
a) Initiate EPIP-2.01, Notification of State and Local Governments NOTE: Updates to state and local governments should be provided at approximately 30 minute intervals and after significant changes to plant status, radiological data, or meteorological data. O
No. 97887210 i NUMBER PROCEOURE TITLE REVISION O 00 EPIP-1.04 RESPONSE TO SITE EMERGENCY PAGE 4 of 13
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED l
l
- 6. NRC NOTIFICATION:
a) Initiate EPIP-2.02, Notification of NRC, Attachment 1
- 7. EVALUATE STATION CONDITIONS:
a) Unit (s) are NOT affected a) E a unit is affected, eval-by emergency condition uste safe operation of unaf-fected unit.
- 1) Evaluate safety of and operating unit (s) AND
- 2) Consider unit (s) shutdown Consider unit shutdown if if emergency conditions conditions so indicate.
(Y so indicate
- 8. VERIFY D1ERGENCY CENTERS /
FACILITIES: i a) All emergency centers and a) GO TO Step 9_ of this instruc-facilities - ACTIVATED tion. b) GO TO Step H of this instruction i
- 9. VERIFY TSC ESTABLISHED:
a) Check TSC NOT previously a) GO TO Step 10,of this in-activated struction. b) Relieve the Shift Supervisor b) E Shift Supervisor relief as Station Emergency Manager NOT available GO TO Step M of this instruction, and
- 1) BY: return to Step 9,, when appropriate.
DATE: TIME:
No. 97847210 NUMBER PROCEDURE TITLE REVISION 00 EPIP-1.04 RESPONSE TO SITE EMERGENCY PAGE 5 of 13
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 9. (CONTINUED) c) If desired, relocate Station Emergency Manager position to TSC d) Announce Sation Emergency Manager name and location to offsite authorities e) Verify TSC - ACTIVATED e) Initiate activation of TSC IAW EPIP-3.02, Activation of Technical Support Center.
- 10. VERIFY OSC ESTABLISHED:
a) Check OSC NOT previously a) GO TO Step 11 of this in-C'))
. activated struction, b) Direct on-duty mechanical foreman to assume position of interim OSC Director c) Direct activation of OSC IAW EPIP-3.03, Activation of Oper-ational Support Center
- 11. VERIFY EOF ESTABLISHED:
a) Check EOF NOT previously a) GO TO Step 12 of this activated instruction, b) Direct Security to activate EOF IAW EPIP-3.04, Activation of Emergency Operations Facility l 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 (s GO TO Step 13,.
No. 978 872 3 0 NUMBER PROCEDURE TITLE REVISION EPIP-1.04 RESPONSE TO SITE EMERGENCY PAGE 6 of 13
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 12. (CONTINUED) b) Check status of EPIP-4.01, Radiological Assessment Director Controlling Procedure c) Verify Onsite Monitoring Team - ACTIVATED
- 13. CHECK RADIOLOGICAL CONDITIONS:
i a) Radiological conditions - a) Confer with Radiological STABLE OR IMPROVING Assessment Director and Emergency Operations Director AND Initiate appropriate miti-gating actions.
- 14. CHECK UNIT CONDITIONS:
a) Reactor plant (s) - STABLE a) ))[ TSC activated, confer with Emergency Operations Director.
))[ NOT, confer with SRO-On-Call.
AND Initiate appropriate citi-gating actions.
- 15. DAMAGE CONTROL:
a) Damage to station equip- a) CO TO Step 16. ment has been verified b) With Emergency Operations b) ))[ TSC NOT manned confer and Maintenance Directors, with senior operations evaluate extent of damage and maintenance personnel
/ onsite.
1
No. 974 87210 NUMBER PROCEDURE TITLE REVISION EPIP-1.04 RESPONSE TO SITE EMERGENCY PAGE 7 of 13
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 15. (CONTINUED) c) Evaluate following assist-ance requirements
- 1) Offsite Technical
- 2) Additional personnel
- 3) Material and Equipment d) Direct Emergency Main- d) IJ[ NOT available, initiate tenance Director to init- interim damage control acti-iate EPIP-5.08, Damage vities.
Control
- 16. VERIFY ONSITE CONDITIONS:
[O) a) Evaluation indicates limited a) GO TO Step 17 of this in-evacuation of buildings or struction, areas - REQUIRED b) Sound EMERGENCY Alarm and make appropriate announcement using the station Gai-Tronics system
- 17. FOLLOW-UP STATE AND LOCAL GOVERNMENT NOTIFICATION:
a) Verify updated Health Physics dose assessments completed b) Verify timely follow-up b) Initiate EPIP-2.01, state and local government Notification of State and notification IAW EPIP-2.01, Local Governments. Notification of State and Local Governments NOTE: Updates to state and local governments should be provided at approximately 30 minute intervals.
ho.9785721C NJMBER PROCEDURE TITLE REVISION
- f') 00 V EPIP-1.04 RESPONSE TO SITE EMERGENCY PAGE 8 of 10
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 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, Attachment 2
- 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) Direct initiation of EPIP-5.02, IAW EPIP-5.03, Personnel Search and Rescue. Accountability
- 21. SITE EVACUATION:
a) Radiological Assessment a) CO TO Step 21 Director recommends site evacuation b) Consider the following:
- 1) Onsite dose GREATER THAN J_ Rem whole body OR GREATER
- TRAN 5, Rem thyroid exposure
- 2) Characteristics and direction of the plume l 3) Contamination vs. per-I sonnel safety and ex-Posure
~. .
l
~ - _. .. - ._. . - . .
No. 978 87230 NUMBER PROCEDURE 17TLE REVISION 00 4 EPIP-1.04 RESPONSE TO SITE EMERGENCY PAGE 9 of 13
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 22. INITIATE SITE EVACUATION:
a) Implement EPIP-5.0.' , 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 boundary doses of 0.5 Rem to 2 Rem whole body, OR 1 Rem to O)
\m, 12, Rem thyroid expo-sure
- 2) Characteristics and direction of plume c) C0 TO Step 24 and make appropriate recommend-ations to offsite agencies
- 24. EVACUATION / RECOMMENDATION NOTIFICATIONS:
a) Notify state and local governments 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 O av ~w.r
Peo.97887210 NUMBER PROCEDURE TITLE REvlSION EPIP-1.04 RESPONSE TO SITE EMERGENCY PAGE 10 of 13 4
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 25. EMERGENCY EXPOSURE:
a) Evaluation of conditions indi- a) GO TO Step 26, cates authorization of emer-gency radiaiton exposure limits should be considered b) Implement EPIP-5.06, Emergency Radiation Exposure Authorization
- 26. BLOCKING AGENT:
a) On recommendation of a) GO TO Step 27. Radiological Assess-ment Director evaluate (,, [)\ issuance of Radioiodide blocking agent to onsite personnel if following exist
; 1) Projected onsite total ; absorbed dose equiva-lent I-131-GREATER TRAN 10 Rem 9.R_
- 2) Actual onsite total absorbed dose equiv-i alent I-131-GREATER THAN _10 Rem b) Direct Radiological Assessment Director to implement EPIP-5.07, Administration of Radioprotective Drugs O
No. 97487210 NUMBER PROCEDURE TITL E REVISION
, O 00
\-- EPIP-1.04 RESPCNSE TO SITE EMERGENCY - - -
, PAGE 11 of 13
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTGSTAINEO
- 27. VERIFY EVENTS:
a) Review EPIP-1.01, Attach-ment 1 Emergency Action Levels. THEN, GO TO Step 27.b b) Insure additional b) Initiate station APs, EPs, events have NOT occurred or EPlPs to address new events. AND Notify Radiological Assess-cent Director.
/T AND l
O Insure initiation of EPIP-2.01, Notification of State and Local Governments and EPIP-2.02, Notification of NRC. c) Check that emergency has c) Jg[ escalated, GO TO Step jf) NOT escalated of this procedure
- 28. CHECK FOR TERMINATION:
a) Verify EALs - NOT EXCEEDED a) ))[ EALs are still exceeded, GO TO Step 29,. AND b) Verify plant conditions - b) Evaluate conditions and GO TO SAFE AND STABLE Step 7. AND c) Onsite and offsite response c) Continue monitoring activi-personnel - NOT REQUIRED ties and GO TO Step 29. O
a F.c.97887210 NUMBER PROCEDURE TITLE REVISION O 00 b EPIP-1.04 RESPONSE TO SITE EMERGENCY P3GE 12 of 13
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 28. (CONTINUED) d) Go To Step 31 for termination I
- 29. CHECK FOR RECLASSIEICATION:
a) Step 2 indicates event a) GO TO Step 7 of this in-severity - REDUCED struction. b) Reclassify event and GO TO Step 30 for procedure termination
- 30. TERMINATE EPIP-1.04:
a) Verify Recovery Manager concurrence IF, EOF activated b) Close-Out
- 1) Initiate briefing of off-site authorities at EOF and by phone
- 2) Initiate written summary to offsite authorities within 8_ hours
- 3) COMPLETED BY:
DATE: TIME:
- c) GO TO EPIP-1.01, Emergency Manager Controlling Pro-cedure, Step 4 -
v i
Peo. 978 87219 NUMBER PROCEDURE TITLE REVISION 00 O EPIP-1.04 RESPOSSE TO SITE EMERGENCY PAGE 13 of 13 .i
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 31. EMERGENCY TERMINATION' -
a) Verify Recovery Manager concurrence IF_ EOF activated 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:
V DATE: TIME: c) GO TO EPIP-1.01, Emergency Director Controlling Pro-cedure, Step B END G
; Peo.97487210 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE O NUMBER PROCEDURE TITLE REVISION
-00 EPIP-1.05 RESPONSE TO GENERAL EMERGENCY PAGE (With 1 Attachment) 1 of 22 PURPOSE c
- 1. To provide guidance to the Station Emergency Manager during the pro-gress of a classified GENERAL emergency.
USER Station Emergency Manager ENTR Y CONDITIONS O 1. Entry From EPIP-1.01, Emergency Manager Controlling Procedure. l l REVISION RECORD REV. 00 PAGE(S): Entire Procedure DATE:JUL2 91982 REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: APPROVAL RECOMMENCE 0 A ROVED DA TE y);h
= /
hl).se f CHAIRMANSTATIONNUCLEARSAFETY Jut 2 s rm AND QPERA TING COMMITTEE - r
Peo.97887210 ~ l i NUMBER PROCEDURE TITLE REVISION 00 1 EPIP-1.05 RESPONSE TO GENERAL DIERGENCY PAGE 2 of 22
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED ;
l 1. INITIATE PROCEDLTE: a) Declare position of Station 4 Emergency Manager b) BY: DATE: TIME: NOTE: The Shift Supervisor may be relieved as Station Emergency Manager IAW the SPS Emergency Plan. -l
- 2. INPLANT NOTIFICATION:
a) From the Control Room, I sound the EMERGENCY Alarm b) Make announcement on station i Gai-Tronics system as follows:
- 1) "A GENERAL EMERGENCY has been declared"
- 2) "All Emergency Response personnel report to their assigned stations"
- 3) "All other personnel report to their Emer-gency Assembly Areas" c) Repeat Steps 2.a and 2.b, THEN continue this in-struction
No. 978 87t:0 NUMBER PROCEDURE TITLE REVISION 00 EPIP-1.05 RESPONSE TO GENERAL EMERGE!;CY PAGE 3 of 22
- STEP ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED
- 3. ONSITE ACCOUNTABILITY:
a) Direct Security to initiate
- Notify Security Shift EPIP-5.03, Personnel Account- Supervisor via PBX-#346 ability b) Direct Security to initiate EPIP-5.04, Access Control .-
- 4. CALLOUT OF PERSONNEL:
a) Verify Emergency Response a) Direct Security to initiate Personnel - ONSITE EPIP-3.01, Call out of Emer-gency Response personnel. AND 4 N-- GO TO Step 5,of this instruction b) Direct Security to activate Corporate Emergency Response Team by calling General Office Security IAW Attachment 1 EPIP-3.01, Callout of Emergency Response Personnel NOTE: The following Steps 5 thru 12 determine the offsite protective actions to be recommended for various General Emergency situa-tions. Refer to Attachment 1 for affected zones and sectors.
- 5. CORE MELT AND LOCA WITH CONTAINMENT FAILURE IMMINENT OR OCCURING:
a) Following conditions have a) GO TO Step 6,of this been met: instruction.
- 1) RCS specific activity -
CREATER THAN 3000 uCi/ gram f) m dose equivalent I-131
No. 97447210 NUMBER PROCEDURE TITLE REVISION 00 EPIP-1.05 RESPONSE TO GENERAL EMERGENCY PAGE 4 of 22
- STEP ACTION /E7PECTED RESPONSE RESPONSE NOT OBTAINED
- 5. (CONTINUED)
RE 5 cr more core exit
- thermocouples - GREATER THAN 2000*F
- 2) Outside Containment High Range Radiation Monitor -
2 GREATER THAN 5x10 mR/hr
- 3) Containment failure imminent as indicated by pressure - GREATER THAN 60 psia NOT DECREASING SE Shift Supervisor judge-ment that containment
, failure has occurred b) Determining protective b) Request Radiological Assess-actions: ment Director aid in determi-nation of sheltering recom-
- 1) Determine wind speed and mendations IAW EPIP-4.01, affected sectors Radiological Assessment Director Controlling a) I_F, wind speed LESS Procedure.
THAN 2.5 mph recommend sheltering out to, and including Zone-5 in affected sectors AND Recommend evacuation in Zones 6 thru 10 in affected sectors D) 6 v
No,97887210 NUMBER PROCEDURE TITLE REVISION EPIP-1.05 RESPONSE TO GENERAL EMERGENCY PAGE 5 of 22
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
}
- 5. (CONTINUED)
AND Recommend evacuation out to and including Zone 5 in unaffected sectors 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 13,
- 6. CORE MELT AND S/G TUBE RUPTURE WITH STEAM BREAK:
a) Following conditions have a) GO TO Step 7 of this been met: instruction.
- 1) RCS specific activity-GREATER THAN 3000 uCi/ gram dose equivalent I-131 1
SE 5 or more core exit thermocouples-GREATER THAN 2000*F
- 2) S/G tube rupture flow --
greater than capacity of l ,Q two (2) Charging /SI Pumps
\ )
No. 97887210 NUMBER PROCEDURE TITLE REVISION h, 00
\~ / EPIP-1.05 RESPONSE TO GENERAL EMERGENCY
- PAGE 6 of 22
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 6. (CONTINUED)
- 3) Major S/G Secondary depressurization as indicated by MS header to line DP - GREATER THAN 100 psid pR Shif t Supervisor judgement that large steam break -
IN PROGRESS b) Determining protective b) Request Radiological actions: Assessment Director aid in [ determination of shel-
\d } tering recommendations IAW
- 1) Determine wind speed and EPIP-4.01, Radiological affected sectors Assessment Director Controlling-Procedure.
a) IF, wind speed LESS THAN 2.5 mph recommend 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 b'^4 V
. No,97887210 NUMBER PROCEDURE TITLE REVISION EPIP-1.05 RESPONSE TO GENERAL EMERGENCY FAGE 7 of 22
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 6. (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 ~13 O 7. CORE MELT AND LOCA WITH CONTAINMENT FAILURE LIKELY:
a) Following conditions have a) GO TO Step 8,of this been met: instruction.
- 1) RCS specific activity-GREATER THAN 3000 uCi/
gram dose equivalent I-131 OR l l 5 or more core exit j thermocouples-GREATER I THAN 2000*F
- 2) Containment High Range Rsdiation Monitor -
- GREATER THAN 5x10 2 I
i
ho.97887230 NUMBER PROCEDURE TITLE REVISION EPIP-1.05 RESPONSE TO GENERAL EMERGENCY PAGE 8 of 22
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 7. (CONTINUED)
- 3) Containment failure is likely as indicated by significantly impaired Engineered Safeguards Systems AND pressure -
GREATEk THAN 23.0 psia b) Recommend the following: b) Request Radiological Assessment Director aid in
- 1) Evacuation of the popu- determination of evacuation lation within a radius recommendations IAW out to and including EPIP-4.01, Radiological
. Zone 5 (360') Assessment 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 lj[
- 8. CORE MELT AND LOCA WITH CONTAINMENT FAILURE NOT LIKELY:
a) Following conditions have a) GO TO Step 9 of this been met: instruction.
- 1) RCS specific activity-GREATER THAN 3000 uCi/
gram dose equivalent I-131 i AND 5 or more core exit thermocouples-GREATER THAN 2000*F (#' b) i
No.97887210 NUMBER PROCEDURE TITLE REVISION [,,.V) 00 EPIP-1.05 RESPONSE TO GENERAL EMERGENCY PAGE 9 of 22
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 8. (CONTINUED)
- 2) Containment High Range Radiation Monitor -
GREATER THAN 5x10 2 i
- 3) Containment failure is NOT likely as indicated by pressure - LESS THAN 23.0 psia AND DECREASING b) Recommend *.he following: b) Request Radiological Assessment Director aid in
- 1) Evacuation of the popu- determination of evacuation lation within a radius recommendations IAW
,s out to and including EPIP-4.01, Radiological e i Zone 2 (360*) Assessment Director s/ Controlling Procedure.
- 2) Evacuation of the popu-lation cut 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 (67h* total) i c) GO TO Step 13,
- 9. CORE MELT AND S/G TUBE RUPTURE WITH MS SAFETY LIFT LIKELY:
a) Following conditions have a) GO TO Step 11,of this been met: instruction.
- 1) RCS specific activity-GREATER THAN 3000 uCi/
gram dose equivalent I-131 h G
e No.97887210 '- NUMBER PROCEDURE TITLE REVISION
-00 EPIP-1.05 RESPONSE TO GENERAL EMERGENCY PAGE 10 of.22 t - STEP ACTION / EXPECTED RESPONSE RESPDNSENOTOBTAINED
- 9. (CONTINUED) 5 or more core exit thermocouples -
GREATER THAN 2000*F
- 2) S/G tube rupture flow greater than the capacity 1 of one (1) Charging /SI
; Pump i
- 3. Shift Supervisor judgement ,
that lifting of MS safety valve (s) likely b) Recommend the following: b) Request Radiological Assessment Director aid in l 1) Evacuation of the popu- determination of evacuation lation within a radius recommendations IAW EPIP-out to and including 4.01 Radiological Assessment Zone 2 (360*) Director Controlling Procedure. 1
- 2) Evacuation of the popu-lation out to and includ-1 ing Zone 5 in downwind and adjacent sections ,
- (67
- total) .,
- 3) Sheltering in Zones 5 out to 10 in down wind
~
and adjacent sectors 1 (67
- Total) -
c) Go TO Step 13,
- 10. CORE MELT WITH LbW CONTAINMENT ACTIVITY: -
i a) Following conditions have a) GO TO Step 1C; of thic been met: instruction. -1 i e [ s
No. 978 87218 NUMBER PROCEDURE 77TLE REVISION A
-- EPIP-1.05 RESPONSE TO GENERAL EMERGENCY PAGE 11 of 22
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 10. (CONTINUED)
- 1) RCS specific activity-GREATER THAN 3000 uCi/
gram dose equivalent I-131 pR 5 or more core exit the rmocouples-GREATER THAN 2000*F
- 2) Containment High Range Radiation Mo LESS THAN 10,gitormR/hr -
[~} 3) Containment pressure-s_ - LESS THAN 17.7 psia AND NOT INCREASING b) Recommend evacuation within b) Request Radiological a radius out to aad including Assessment Director aid in Zone 2 (360*) determination of evacuation recommendations IAW EPIP-4.01 Radiological Assessment Director Controlling Procedure c) GO TO Step 13,
- 11. SIGNIFICANT RELEASE POTENTIAL:
a) Any of the following exist: a) GO TO Step 12,of this instruction.
- 1) Projected Site Boundary doses exceed 2 Rem whole-body or 12 Rem thyroid exposure pR
- 2) Loss of physical control -
of the station O O
ho.97887230 NUMBER PROCEDURE TITLE REVISION EPIP-1.05 RESPONSE TO GENERAL EMERGENCY PAGE 12 of 22
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 11. (CONTINUED) b) Recommend evacuation within b) Request Radiological a radius out to and includ- Assessment Director aid in ing Zone 2 (360*) determination of evacuation recommendations IAW EPIP-4.01, Radiological Assessment Director Controlling Procedure.
c) GO TO Step 13,
- 12. MISCELLANEOUS EVENTS:
a) A General Emergency has been cg declared based on loss of 2 ( ) of 3 fission product barriers with loss of the third imminent O_R, Station Emergency Manager judgement indicates actions required to protect the health and safety of the public b) Recommend the following: b) Request Radiological Assessment Director aid in
- 1) Sheltering of the popu- determination of sheltering lation within a radius Recommendations IAW out to and including EPIP-4.01, Radiological Zone 2 (360*) Assessment Director Controlling Procedure
- 2) Sheltering of the popu-lation out to and includ-ing Zone 5 in downwind and adjacent sectors (67
- total) c) GO TO Step 13,
,.s)
Peo. 978 87218 NUMBER PROCEDURE TITLE REVISION 00 [ s-)/ m EPIP-1.05 RESPONSE TO GENERAL EMERGENCY PAGE 13 of 22
- STEP ACTION / EXPECTED PESPONSE RESPONSE NOT OBTAINED
- 13. STATE AND LOCAL GOVERNMENT NOTIFICATION:
a) Initiate EPIP-2.01, Notification of State and Local Governments NOTE: Updates to state and local governments should be provided at approximately 30 minute intervals and after significant changes to plant status, radiological data, or meteorological data.
- 14. NRC NOTIFICATION:
0 t I (_ e a) Notify NRC Operation: Center IAW EPIP-2.02, Notification of NRC
- 15. EVALUATE STATION CONDITIONS:
a) Unit (s) are NOT affected a) Il[ a unit is affected, eval-by emergency condition uate safe operation of unaf-fected unit.
- 1) Evaluate safety of any operating unit AND
- 2) Consider unit shutdown Consider unit shutdown if if emergency conditions conditions so indicate, so indicate
- 16. VERIFY EMERCENCY CENTERS / FACILITIES:
a) All emergency centers and a) GO TO Step 17,of this facilities - ACTIVATED instruction. b) GO TO Step 20 of this - instruction m
No.97867219 NUMBER PROCEDURE TITLE REV/SION v EPIP-1.05 RESPONSE TO GENERAL EMERGENCY 00 PA GE 14 of 22
- STEP ACTION / EXPECTED RESPONSE ' RESPONSE NOT OBTAINED
- 17. VERIFY TSC ESTAELISHED:
a) Check TSC NOT previously a) GO TO Step 18 of this in-activated struction. b) Relieve the Shift Supervisor b) IF_ Shift Supervisor relief as Emergency Manager NOT available GO TO Step 18, of this instruction and
- 1) BY: return to Step 1],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 EPIF-3.02, Activation of Technical Support Center.
- 18. VERIFY OSC ESTABLISHED:
a) Check OSC NOT previously a) GO TO Step 19,of this in-activated struction, b) Direct on-duty mechanical foreman to assume position of interim OSC Director c) Direct activation of 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 in-activated instruction 7~
No. 97 t &7219 NUMBER PROCEDURE TITLE REVISION Q 00 EPIP-1.05 RESPONSE TO GENERAL EMERGENCY PA GE 15 of 22
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 19. (CONTINUED) b) Direct Security to activate EOF IAW EPIP-3.04, Activation of Emergency Operations Facility
- 20. VERIFY EPIP-4.01:
a) Check status of EPIP-4.01, Radiological Assessment Director Controlling Procedure b) Verify Onsite Monitoring Team - ACTIVATED
'~'
c) Verify Offsite Monitoring Team (s) - ACTIVATED
- 21. CHECK RADIOLOGICAL CONDITIONS:
a) Radiological conditions - a) Confer with Radiological STABLE OFi DECREASING Assessment Director and Emergency Operations Director. AND Initiate appropriate miti-gating actions.
- 22. CHECK UNIT CONDITIONS:
a) Reactor plant (s) - STABLE a) ))[ TSC activated confer with Emergency Operations Director. ))[ NOT, confer with SRO On-Call, AND Initiate appropriate miti-gating actions. i b> t_- l l l - - _ - _ . . , . _ __
No. 97887219 NUMBER PROCEDURE TITLE REVlSION l [,,~
] 00 EPIP-1.05 RESPONSE TO GENERAL EMERGENCY -
PAGE 16 of 22
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 23. DAMAGE CONTROL:
a) Damage to station equip- a) GO TO Step 24. ment has been verified b) With Emergency Operations b) IF,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) Direct Emergency Mainte- d) Il[ NOT available, initiate nance Director te initiate interim damage control ac-EPIP-5.08, Damage Control tivities.
- 24. VERIFY ONSITE CONDITIONS:
a) Evaluation indicates limited a) GO TO Step 25 of this in-evacuatien of buildings or struction, areas - REQUIRED b) Sound EMERGENCY Alarm and make appropriate announcement using the plant Gai-Tronics system
- 25. FOLLOW-UP STATE AND LOCAL GOVERNMENT NOTIFICATION:
a) Verify updated Health Physics dose assessments completed b) Verify timely follow-up b) Initiate EPIP-2.01, State and local government Notification of State and 7-- notification IAW EPIP-2.01, Local Governments. ( 'j Notification of State and Local Governments 1
l No,97887219 NUMBER PROCEDURE TITLE O REVISION EPIP-1.05 RESPONSE TO GENERAL EMERGENCY PAGE 17 of 22 J l
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINEO NOTE: Updates to state and local governments should be provided at approximately 30 minute intervals.
- 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
- 27. ADDITIONAL REPORTING:
a) Direct the Emergency Administrative Director to evaluate reporting criteria IAW EPIP-2.03, J Reports to Offsite Agencies i b) Initiate reporting require-j ments of EPIP-2.03, Reports to Offsite Agencies
- 28. VERIFY ACCOUNTABILITY:
a) All personnel accounted for a) Direct initiation of IAW EPIP-5.03, Personnel EPIP-5.02, Search and Accountability Rescue
- 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]L greater than 5, Rem thyroid exposure
- 2) Characteristics and direction of the plume t
7 e i
, - - - ,,----er- ,;,,, e --.,_,w , ,---,.,m.-
No. 97887210
,-, NUMBER PROCEDURE 11TLE REVISION
(] EPIP-1.05 RESPONSE TO CENERAL EMERGENCY 00 PAGE 18 of 22
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 29. (CONTINUED)
- 3) Contamination vs. per-sonnel safety and ex-posure
- 30. INITIATE SITE EVACUATION:
a) Initiate EPIP-5.05, Site Evacuation
- 31. EVACUATION / REC 0KMENDATION NOTIFICATIONS:
}
a) Notify state and local governments of evacuation 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. ! indicates authorization of emergency radiation expo-sure limits should be considered b) Implement EPIP-5.06, Emergency Radiation Exposure Authorization b,
\~ >
No.97887214 NUMBER PROCEDURE Ti1LE REVISION
, 00
/ EPIP-1.05 RESPONSE TO GENERAL EMERGENCY PAGE 19 of 22
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 33. BLOCKING AGENT:
a) On recommendation of a) GO TO Step 34. Radiological Assess-ment Director evaluate issuance of Radioiodide blocking agent to onsite personnel if following exist:
- 1) Projected onsite total absorbed dose equiva-lent I-131-GREATER THAN 10 Rem OR Ns ./ 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
- 34. VERIFY EVENTS:
a) Review EPIP-1.01, Attach-ment 1, Emergency Action Levels, THEN GO TO Step 34.b b) Insure additional b) Initiate station APs, EPs, events have NOT occurred or EPIPs to address new events. AND __ - Notify Radiological Assess-
, ment Director.
Peo. 97887214 NUMBER PROCEDURE TITLE REV/SION O 00 s_s EPIP-1.05 RESPONSE TO GENERAL EMERGENCY PAGE 20 of 22
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINEO
- 34. (CONTINUED)
AND Insure initiation of EPIP-2.01, Notification of State and Local Governments and EPIP-2.02, Notification of NRC. c) Check emergency conditions- c) GO TO Step 5,to verify CHANGED recommendations. i
- 1) Il[ condition - IMPROVED -
GO TO Step 31
- 2) IF condition - DEGRADED -
[} (/ G6 TO Step 5,for reeval-uation of recommendations
- 35. CHECK FOR TERMINATION:
a) Verify EALs - NOT EXCEEDED a) IF EALs are still exceeded, GO TO Step 36. AND b) Verify plant conditions - b) Evaluate conditions and GO TO SAFE AND STABLE Step 5. AND c) Onsite and offsite response c) Continue monitoring activi-personnel - NOT REQUIRED ties and GO TO Step 36. d) GO TO Step 38 to terminate
- 36. CHECK FOR RECLASSIFICATION:
a) Step 34, indicates event a) GO TO Step 5 of this in-l severity - REDUCED struction, b) Reclassify event and GO TO Step 37 for procedure termiEtion
I No.97887210 NUMBER PRCCEDURE TITLE REVlSION [ 00 \m / EPIP-1.05 RESPONSE TO GENERAL EMERGENCY PAGE 21 of 22
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 37. TERMINATE EPIP-1.05:
a) Verify Recovery Manager concurrence ))[ EOF activated b) Close out
- 1) Initiate briefing of off-site authorities at EOF and by phone
- 2) Initiate written summary to offsite authorities within 8, hours
{} v
- 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 concurrenceJ][ EOF activated b) Cleae-Out
- 1) 'nitiate briefing of offsite authorities at EOF and by phone
- 2) Initiate written summary to offsite authorities within E[ hours O
O
No. 978 87219 NUMBER PROCEDURE TITLE REVISION
% 00 I
EPIP-1.05 RESPONSE TO GENERAL EMERGENCY PAGE 22 of 22
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 38. (CONTINUED)
- 3) COMPLETED BY:
- DATE
TIME: i c) GO TO EPIP-1.01, Emergency Director Controlling Pro-cedure Step 8, O i l L I i END i t l l l I._..,__, , , . . -, _ , - _ _ . . , _ , _ _ . - - . . ~ _ _ - . . , _ . _ , _ - _ . _ - _... , _ . _ , , . > . . . . . - . _ . . . , . _ _ , - - - - - . . , . - - - - -
NUMBER A TTACHMENT TITLE REVISION EPIP-1.05 00 O.- % SURRY SECTOR MAP A TTACHMENT PA GE 1 1 of 1
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, No.97687230 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE O
NUMBER PROCEOURE TITLE REVISION 00 l EPIP-2.01 NOTIFICATION OF STATE AND LOCAL GOVERNMENTS PAGE i (With 2 Attachments) 1 of 17 i 4 PURPOSE i 1. To initially notify state and local governments of the declaration of an emergency; n'D
- 2. To provide periodic status updates to state and local governments i during an emergency; g
- 3. To notify state and local governments of any change in emergency
{ status. } USER Emergency Communicator or Station Emergency Manager. t ENTRY CONDITIONS l Any one of the following: l 1. Emergency is declared; I 6
- 2. Approximately 30 minutes have passed since last notification; E
- 3. The status of any notification item has changed; 0,g
- 4. Entry directed by Station Emergency Manager.
I i l l l REVISION RECORD REV. 00 PAGE(S): Entire Procedure DATE:JUL 2 91982 i REV. PAGE(S): DATE:
- REV. PAGE(S)
- DATE:
l REV. PAGE(S): DATE: REV. PAGE(S): DATE: ! REV. PAGE(S): DATE: REV. PAGE(S): DATE: I
- APPROVAL RECOMVENCEO A C' PROVE 0 DA TE
/ N g4
/ / CHAIRVAN STA TION NUCLEAR SAFETY JUL 2 S 1992
, J. * .
- ANO OPERA TING COMMITTEE i
i
.-,,,,-n--,- n,- ,n--- -. ,---,-.. -,.- .-. - , ------ n,., n ,,-----,--.--n - - - , - - , - + - - - . . - , - , - - - -
e.o. ste snie NUMBER PROCEDURE TITLE REVISION
) 00 EPIP-2.01 NOTIFICATION OF STATE AND LOCAL GOVERNY.ENTS PAGE 2 of 17
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: The initial notification 'of an emergency must be made within 15 minutes following declaration of the emergency.
Follow-up -reports of emergency conditions should be sent approximately every 30 minutes or when there are changes in emergency conditions.
~
- 1. INITIATE PROCEDURE:
a) INITIATED BY: TIME: DATE:
- 2. OBTAIN EMERGENCY REPORT FORM:
V a) At tachtaent 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 i status board Manager. b) Record in Items 1 thru 6_ of Attachment J_ j NOTE: Wind direction is always given as the compass point, NOT the degrees, the wind is blowing f rom. Example: Wind direction t is from the East North East (ENE). 1
- 4. DETERMINE WIND DIRECTION:
I a) E in Control Room, obtain a) IF NOT, contact Control Room from Met. Panel and request data. ts l I
No. 97887210 NUMBER . PROCEDURE TITLE REVISION O\ 00 Q ) EPIP-2.01 NOTIFICATION OF STATE AND LOCAL GOVERNMENTS PAGE 3 of 17
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 4. (CONTINUED) b) Read wind direction degrees b) IF NOT operable, read "CH.A from "CH.A - Wind Direction Wind Direction Backup" Upper" recorder. recorder.
c) Use wind direction degrees AND Table 1 to determine compass point wind is blowing from TABLE 1 () ( j DEGREES COMPASS POINT DEGREES COMPASS POINT DEGREES COMPASS POINT 0-11 = N 170-191 - S 350-371 = N 12-34 = NNE 192-214 = SSW 372-394 = NNE 35-56 = NE 215-236 = SW 395-416 = NE 57-79 = ENE 237-259 = WSW 417-439 = ENE 80-101 = E 260-281 = W 440-461 = E 102-124 = ESE 282-304 = WNW 462-484 = ESE 125-146 = SE 305-326 = NW 485-506 = SE 147-169 = SSE 327-349 = NNW 507-529 = SSE 530-540 = S d) Record compass point in item 7 of Attachment 1
\
- Peo. 9 7 8 8 7219 NUMBER PROCEDURE TITLE REVISION v) EPIP-2.01 NOTIFICATION OF STATE AND LOCAL GOVERNMENTS 00 PACE 4 of 17
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINEO l
- 5. DETERMINE WIND SPEED:
a) I_F,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 "CH.A -
"CH.A - Wisd Speed Wind Speed Backup" recorder.
Upper" recorder c) Record wind speed in Item 7 of Attachment 1
- 6. DETERMINE STABILITY CLASS:
O a) I_F,in F Control Room, obtain from Met. Panel a) IF NOT, contact Control Room and request data. b) Read Delta T from "CH.A - b) IF NOT operable, read Sigma Delta T Upper / Lower" "CH.B - Sigma Theta" recorder recorder. 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 (*F) CLASS (*F) CLASS
-2.0 to -1.2 = A -0.3 to +1.0 = E l
-1.2 to -1.1 - B +1.0 to +2.5 = F
-1.1 to -1.0 = C +2.5 to +3.0 = G
-1.0 to -0.3 = D m
Peo. 978 8723 6 NUMBER PROCEDURE TITLE REVISION Q 00 EPIP-2.01 NOTIFICATION OF STATE AND LOCAL GOVERhMENTS PA GE 5 of 17
- 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 s 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, OR AND Release - IS OCCURRING GO TO Step 1. 0,, R Release - IS PROJECTED
- 8. DETERMINE AFFECTED SECTORS:
a) Use wind direction from Item 7 of Attachment 1 AhT b G
ho.97887210 NUMBER PROCEDURE TITLE REVISION O EPIP-2.01 NOTIFICATION OF STATE AND LOCAL GOVERNMENTS FACE 6 of 17
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 8. (CONTINUED)
Table 4 to determine affected sectors TABLE 4 COMPASS COMPASS POINT AFFECTED SECTORS POINT AFFECTED SECTORS N Hotel-fuliett-Kilo S Romeo-Alpha-Bravo NNE duliett-Kilo-L_ima SSW Alpha-Bravo-Charlie NE K_ilo-L_ima-Mike SW Bravo-Charlie-Delta ENE L_ima-Mike-November WSW Charlie-D_ elta-E_cho E Mike-November-Papa W Delta-Echo-Foxtrot ESE November-P_apa-guebec WNW Echo-Foxtrot-Gulf SE Papa-guebec-Romeo NW Foxtro t-G_ulf-H_ot el SSE quebec-R_omeo-Alpha NNW Gulf-Hotel-J_uliett NOTE: Affected Sectors and Zones are recorded using alphanumeric designations. Example: The affected Sectors and Zones are B1 and 2, C1 and 2, and D1 and 2.
- 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-cent I b wJ
No. 97857210 NUMBER PROCEDURE TITLE REVISION 00 EPIP-2.01 NOTIFICATION OF STATE AND LOCAL GOVERNMENTS PAGE 7 of 17
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED NOTE: During the initial stages of an emergency, 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 Director of:
- 1) Wind direction
() w/
- 2) Wind speed
- 3) Stability class
- 11. UPDATE STATUS BCaRD:
a) IF status board is being a) IF NOT, GO TO next step. maintained, insure following updated: i 1) Wind direction
- 2) Wind speed
- 3) Stability class
- 4) Affected sectors
- 12. RECORD REC 0tTMENDED OFFSITE PROTECTIVE ACTIONS:
I ! a) Obtain from status board a) Obtain from Station Emergency Manager. b) Record in Item 9,of ( Attachment 1 l i
Pos.97887219 NUMBER PROCEDURE TITLE REVISION 00 EPIP-2.01 NOTIFICATION OF STATE AND LOCAL COVERNMENTS PA GE o 8 of 17
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 13. RECORD REMARKS:
a) Obtain from status board a) Obtain from Station Emergency Manager, b) IF there are any remarks, record them in Item H of . Attachment 1
- 14. RECORD YOUR NAME AND TITLE:
a) Record in Item _11 of Attachment 1
- 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) Surry County. j
- 2) James City County
- 3) State of Virginia
~ .____.-
Ask for Duty Officer
- 4) Isle of Wight
_ j- .
/
Ns.97867216 NUMBER PROCEDURE TITLE REVISION 00 O EPIP-2.01 NOTIFICATION OF STATE AND LOCAL GOVERNMENTS
~
. PA GE 9 of 17
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 16. (CONTINUED)
- 5) Williamsburg
- 6) Newport News ,
- 7) Yor'k County ,
b) Read Attachment 1 exactly as written
- 17. RECORD TIME MESSAGE SENT:
a) Record on bottom of Attach-ment 1
- 18. RETAIN ATTACIIMENT:
a) Retain Attachment 1
- 19. INFORM STATION EMERGENCY MANAGER:
a) Inform Station Emergency Manager that message sent
- 20. VERIFY RELEASE STATUS:
a) Item 6_ of Attachment a) IF NE , GO TO Step H. 1 indicates: _ Release - HAS OCCURRED pR,
. Release - IS OCCURRING S.R_
O
NL 97887214 NUMBER PROCEDURE TITLE REVISION O EPIP-2.01 NOTIFICATION OF STATE AND LOCAL COVERNMENTS 00 RAGE 10 of 17
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 20. (CONTINUED)
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 AND Call State EOC at O ino Ask for Duty Officer, b) Read following message:
"This is VEPCO Surry Control Room (or TSC) . We will transmit a report of radiological conditions shortly."
c) CO TO Step 23
- 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
~ . ., j
'N _ _
AND
No. 978 87218 NUMBER PROCEDURE TITLE REV/SION 00 EPIP-2.01 NOTIFICATION OF STATE AND LOCAL GOVERNMENTS PAGE 11 of 17
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 22. (CONTINUED)
Ask for Duty Officer. b) Read following message:
"This is VEPC0 Surry Control Room (or TSC).
Since we have no release of radioactive material, we will not transmit a report of radiological conditions." c) GO TO Step 38
- 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 30 minutes or when there are changes in radiological conditions.
- 24. DETERMINE RELEASE DATA:
a) Obtain from status board a) Obtain from Station Emergency Manager. b) Record in Items I thru 4 of Attachment 2 b J
No.97887210 NUMBER PROCEDURE TITLE REVISION O) t V 00 EPIP-2.01 NOTIFICATION OF STATE AND LOCAL GOVERNMENTS PA GE 12 of 17
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED l
- 25. RECORD METEOROLOGICAL DATA:
a) Obtain wind direction, wind speed, and stability class from most recent Attachment I completed b) Record in item 5,of Attach-ment 2
- 26. DETERMINE TEMPERATURE:
a) IF in Control Room, obtain a) IF NOT, contact Control Room temperature from "CH.A - and request data. Temperature" recorder ( i i b) Record temperature in Item
\~- 6,of Attachment 2,
- 27. DETERMINE PRECIPITATION:
a) Determine AND record pre-cipitation from in Item 6,of Attachment 2
- 28. INFORM RADIOLOGICAL ASSESSMENT DIRECTOR:
a) Inform Radiological Assess-ment Director of tempera-ture AND precipitation data
- 29. UPDATE STATUS BOARD:
a) IJ[ status board being main- a) IF NOT, GO TO next step, tained, insure temperature and precipitation data updated b d
h No. 978 572 3 0 NUMBER PROCEDURE TITLE REVISION O w' EPIP-2.01 NOTIFICATION OF STATE AND LOCAL GOVERNMENTS FAGE 13 of 17
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 30. RECORD RADIOLOGICAL DATA:
a) Obtain from status board a) IF NOT known, record as
" unknown."
0R, Radiological Assessment Director b) Record in Items 7 through 14 of Attachment 2
- 31. RECORD STATION CONDITIONS:
a) Obtain from status board a) Obtain from Station Emergency Manager. I U) b) Include status of following:
- 1) Fuel Failure
- 2) Containment Leakage
- 3) RCS Integrity c) Record in Item 15 of Attachment 2,
- 32. RECORD YOUR NAME AND TITLE:
a) Record in Item 16, of Attachment 2,
- 33. OBTAIN APPROVAL TO TRANSMIT MESSAGE:
a) Show completed Attachment 2,to Station Emergency Manager b) Receive approval to transmit b U 1
[ , m .nisarmte NUMBER PROCEDURE TITLE REVISION
,h 00
() EPIP-2.01 NOTIFICATION OF STATE AND LOCAL GOVERNMENTS PACE 14 of 17
- STEP ACTION / EXPECTED RESPONSE RESPONSE NO T OBTA. 'IED
- 34. TRANSMIT MESSAGE TO STATE:
a) Use ringdown phone to state a) IF NOT operable, use normal EOC station telephone AND Call state EOC at AND Ask for Duty Officer. b) Read Attachment 2 exactly as written r 1 s
- 35. RECORD TIME MESSAGE SENT:
a) Record in Item M of Attachment 2_
- 36. RETAIN ATTACHMENT:
a) Retain Attachment 2
- 37. INFORM STATION EMERGENCY MANAGER:
a) Inform Station Emergency Manager that message sent
- 38. VERIFY EMERGENCY STATUS:
a) Notification of termination a) IF_ F sent, GO TO Step 47. of emergency - NOT SENT
- 39. RELIEF: .
a) IF your relief arrives, a) IF NOT, C0 TO Step 40, perform following* p; )
,__ - . - . _ - . . _ _ . _ _ . - . . - _ . . _ _ - . . _ ~ .
Peo.97887219 NUMBER PROCEDURE TITLE REVISION O ' 00 EPIP-2.01 NOTIFICATION OF STATE AND LOCAL GOVERNMENTS PAGE I 15 of 17
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 39. (CONTINUED)
- 1) Brief your relief on current status of emergency i
- 2) Review last Attachments 1 and 2 completed l 3) Transfer this procedure and all completed attach-
] ments to your relief b) Record relief: Relieved By: i i - Time: Date: '
=,
- 40. RELOCATION: ,
a) F in TSC, GO TO Step 4l a) IF NOT in TSC, relocate'to-TSC when TSC is being mantied I ., l # Station Emergency Manager directs you to relocate to TSC.
- 41. DETERMINE EOF STATUS:
- a) Emergency Operations Faci- a) IF EOF manned lity (EOF) - NOT MANNED l -1AND l 1) GO TO Step 46 l
EOF has assumed responsibi-lity for_nctification of state and local governments, GO TO Step ~42. O
/
~
ho.978t?219 NUMBER PROCEDURE TITLE REVISION 00 EPIP-2.01 NOTIFICATION OF STATE AND LOCAL GOVERNMENTS PAGE 16 of 17
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINEO
- 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 30 minutes, request update of meteorological data from the Control Room phonetalker b) Inform EOF AND Radiolo-gical Assessment Director of latest meteorological data 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 E.
- 46. DETERMINE NEED FOR FOLLOW-UP NOTIFICATION:
O o - I
9 Peo.97887219 K NUMBER PROCEDURE TITLE REVISION
/) --
EPIP-2.01 NOTIFICATION OF STATE AND LOCAL GOVEFEMENTS PAGE 17 of 17
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 46. (CONTINUED) a) Status of any information a) IF NOT changed, wait approx-on Attachment 1 or Attach- imately 30 minutes from time ment 2_ - CHANGED last notification form initi-ated, THEN GO TO Step 2.
- 1) GO TO Step 2.
I
- 47. TERMINA!L EPIP-2.01:
a) COMPLETED BY: TIME: DATE: s b) Forward all completed EPIPs and attachments to SNSCC for review END l0 I l t
l l j Peo.9788722c i
, NUMBER A TTACHMENT TITLE REVISION i ) EPIP-2.01 REPORT OF EMERGENCY TO 00 g
A TTACHMENT STATE AND LOCAL GOVEFa*MENTS FACE 1 1 of 1 MESSAGE:
"Th6s is VEPCO surry DConirol Roorn OT5C D EOP. Stoney for a revoli fonovved try en emergency messese. Use a Report of Energency form to sosry me messess " 4Corusuct a rouell and cmsco t*e bones as each party enesser J O Surry County D virginie state soc 0 williamsburg D York County 0 James City County D Isle of Wight County D liewport Neve "The onwegsacy encenage la es foltouse:
" Item 1. E. vergency caess: O Nottfication of Unueuel Eient C Alert O Site Emergency Deciered et an / /_."
D General Emergency (24 hr. amel (detel D Emergency isrminated (if checked, so to item 101
" Stem 2. Assistence rooverted: D None.
D (no.) Fire Units from . D (no.lPol.co Units from . D (no.1 Rescue Units from . O 10eerl ."
" Stem 3. Errorgoney response actions undersey D None, D Stet on man:toring seems dispetched offeite.
p D Stetton emergency personnel coiled in, (dl D (Oewel
" stem 4 Evocustion of onsite personnel: D No.
D Yes. Encuoted to ."
- Item 5. Prtgnosis of situation: D Improving.
O Worsening. O simo6e . O 10eer)
*ltem 6. Retesse of redRective erwiertet: D Has NOT occurred and is NOT pr4ected.
O Has occurred and is nous term 6neted. O is presentry securring. O la projected to oesur." ,
" Item 7, wnd direction is from ee - : gend speed is MPH. Stabitity stems is ."
" Item 8. Areas effected are D None.
D 8estere and semea _.
" Item 9. Rosommenced offshe protsethe actions: D None.
O Shelte% In Settere med Essee . O Eveo6mson of Sestore end genes , O lother) .a "Iten 10. marrorks:
/
" Item 11. This is leemoon)
(nomel
*Pienne acknoweedge receipt of mis massess " IConduct ronen#1 and check beseeJ 0 sorry couerr D virstate state toc D v111tensburg D fork c m ty a
. . . . ,t, . _ t, e .. . .f ut. t -, , e. ,.r - .
"This is VEPCO Surr7 DControl Room DT3C DEOF out et time G4 hr.t6mel
No. 978 87220 NUMBER A TTACHMENT Tl!LE REVIS/0N EPIP-2.01 REPORT OF RADIOLOGICAL 00 A TTACHMENT CONDITIONS TO THE STATE PAGE 2 1 of 1 "This is VEPCO surry C Controd Room D T3C D EOF. I have e report o' redio6ogical condtfons. Lhe e Pleport of Radiosoew constions form to copy thle mesmose. Piemme inform me when you are remov to copy. Proosed vAen informed.) ham 1. Type of rweme is O serbome,reisesed et elevetson of ft. O seistbome. O surfem will. Nom 2. Re6amme D began et . Oh eeurreted to tegen et . Q4 hr.ume) Q4 hr. ume) item 3. Rotesse durocon D vise hrs. O is satir wted to be hrs. hem 4 Time between reactor shutdown and tirne of beginntr>g of release Q eues hrs. Dis not mooliamble. item 5. Mnd direction is from the . Wind speed is MPH. Stabi!!ty r.:es:Is . Item 8. Temperetvre b
- F. Precipitetion form is D None O P A D $4eet OSnow 0 (Oew) .
hem 7. The ladineMoble Gas Retle is D . O unknoum.
' Projected total reisses eaulveient Curies of 1131 is O Curies. O unknoum.
ttom 8. Item 9. Preiseted total ro6eese eeuhelent Curies of Ko.133 is O Curles. D unknoum. ftern 10. Actuel dose rete et the site boundary is O mR/hr. Dunknown, item 11. Estimated does rotes are O mR Ar et site boundery, mR/hr et 2 miles. D unknown. mR At et 5 miles, and mR/hr et t o miles, imm 12. Proiseted total iniepeted Whole Body due is D mm st, site boundery, mm et 2 miles. O unknovan, mR et 6 miles, and mR et 10 miles. Item 13. Projected totet integreted Thyroid done is O mR st site boundary, mR st 2 miles, b unknown. M et 5 miiss, and mR et to miles. l 2 O unknovan, item 14 Actuel surfeos radioective conismination is D DPM /100am in Zone . item 15. Destion conditions are es follones: (Give brief sistus and snuse of emergency. Use back if needed.) i 1
) 'J team IL Tids k / out et smo .
iname), (postoon)
et.97647230 v VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE -
, NUMBER PROCEDURE TITLE REVISION 00 EPIP-2.02 NOTIFICATION OF NRC PACE (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.
USER Emergency Communicator O_R R Station Emergency Manager. ENTR Y CONDITIONS Any one of the following:
- 1. Emergency is declared; a
- 2. Entry directed by Station Emergency Manager.
REVISION RECORD REV. 00 PAGE(S): Entire Procedure DATE:JUL 2 9 1982 REV. PAGE(S): DATE: REV. PAGE(S): DATE: , REV. PAGE{S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: APPROVAL RECOMMENDEO APPROVED DA TE
/"
/
.h 5W HAIRMAN STA TIONNUCLEAR SAFETY JUL2 S 1982 AND OPERA TING COMMITTEE
No.97887210 l 4 NUMBER PROCEDURE TITLE REVISION 00 , EPIP-2.02 NOTIFICATION OF NRC 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 1 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: 7\ f t Date: V
- 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 this procedure
- 3. COMPLETE FORM:
a) Complete Items 1 thru 17 on Attachment 1 l b) Obtain information from l Control Boards or Station l Emergency Manager, as l appropriate
- 4. OBTAIN APPROVAL TO TRANSMIT MESSAGE:
a) Show completed Attachment I to Station Emergency Manager l l l
No.97887210 NUMBER PROCEDURE TITLE REVISION O 00
*Q EPIP-2.02 NOTIFICATION OF NRC PAGE 3 of 8
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 4. (CONTINUED) b) Receive approval to transmit
- 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 1-202-951-0550. 1 (~ 1, b) Read message section of Attachment 1 exactly as written c) Record time message com-pleted in Item 18,of Attachment 1,
- 6. RETAIN ATTACHMENT:
a) Retain Attachment 1
- 7. INFORM STATION EMERGENCY MANAGER:
a) Inform Station Emergency Manager that message sent
- 8. OBTAIN SUPPLEMENTAL REPORT FORM:
a) Attachment 2,, Supplemen- a) IF NOT attached, obtain tal Report of Emergency from procedure file, to NRC, located at back of this procedure a i I
me.s7:s721e NUMBER PROCEDURE TITLE REVISION
\
00 EPIP-2.02 NOTIFICATION OF NRC PA GE 4 of 8
- STEP ACTIOWEXPECTED RESPONSE RESPONSE NOT OBTAINED
- 9. RECORD EMERGENCY STATUS INFORMATION:
a) Complete Section A. Items 1 thru 3_, of Attachment 2 b) Obtain information from b) Obtain from Station status board Emergency Manager.
- 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 Emergency Manger.
- 11. CHECK RADI0 ACTIVE RELEASE STATUS:
a) Release - HAS OCCURRED a) IF NOT, GO TO Step H. 8 Release - IS OCCURRING OR Release - IS PROJECTED b) Complete Section C, Items 1 thru 12, of Attachment l l c) Obtain information from c) IF NOT known, record as status board " unknown." l I l n Station Emergency j Manager
Pto. 97887210 NUMBER PROCEDURE TITLE REVISION 00 EPIP-2.02 NOTIFICATION OF NRC FAGE 5 of 8
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 12. CHECK PLANT STATUS:
a) Event involves - PLANT a) IF NOT, GO TO Step 13. SYSTEM MALFUNCTION 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. i b) Complete Section E Items 1 thru 3_, of Attachment 2 c) Obtain information from c) Obtain information from f Fire Marshal Station Emergency Manager. i 14. CHECK CONTAMINATED INJURED PERSONNEL STATUS: a) Event involves - TRANSPORT a) IF NOT, GO TO Step 15. OF CONTAMINATED INJURED PERSONNEL TO OFFSITE HOSPITAL i
- b) Complete Section F, Item 1, of Attachment 2
- 15. CHECK SECURITY STATUS:
l
-s g a) Event involves - BOMB THREAT a) IF NOT, GO TO Step 15.c.
U 1 i
No. 978 87210 NUMBER PROCEDURE TITLE REVISION
' 00 EPIP-2.02 NOTIFICATION OF NRC PAGE 6 of 8
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 15. (CONTINUED) b) Complete Secton G Items 1 1, 2.a AND 2.h, of Attachment 2_
c) Event involves - ACT OF c) IF NOT, GO TO Step 15.e. SABOTAGE d) Complete Section G_, Items 1 AND 3.a thru 3.c of Attachment 2 e) Event involves - ACTUAL e) IF NOT, GO TO Step 16. OR ATTEMPTED INTRUSION f) Complete Section G_, Items 1 AND 4.1 thru 4.e, of Attachment 2_
- 16. CEECK HAZARD TO STATION OPERATIONS STATUS:
a) Event involves - HAZARD a) IF NOT, GO TO Step H. TO STATION OPERATIONS b) Complete Section H_, Items 1 AND 2_, of Attachment 2_
- 17. CHECK NATURAL EVENT STATUS:
i a) Event involves - NATURAL a) IF NOT, GO TO Step 18,. EVENT b) Complete Section I, Items 1 AND 2_, of Attachment 2_ l 18. OBTAIN APPROVAL TO TRANSMIT MESSAGE: a) Show completed Attachment 2 to Station Emergency D iianager i l
No. 97887213 NUMBER PROCEDURE TH'LE REVISION O 00 EPIP-2.02 NOTIFICATION OF NRC PAGE 7 of 8
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 18. (CONTINUED) b) Receive approval to trans-mit
- 19. TRANSMIT MESSAGE TO NRC:
a) Use NRC Emergency Notifi- a) IF NOT operable, use com-cation System ringdown merical telephone phone AND call NRC Operations Center, Bethesda, Maryland at 1-202-951-0550. f-~s b) Read Attachment 2, exactly as written c) Record time message com-pleted in Section J,, Item 1, of Attachment 2,
- 20. RETAIN ATTACHMENT:
a) Retain Attachment 2
- 21. INFORM STATION EMERGENCY MANAGER:
a) Inform Station Emergency Manager that message sent
- 22. MAINTAIN COMMUNICATIONS TO NRC:
a) Provide information as requested by NRC
- 23. VERIFY EMERGENCY STATUS:
a) Notification of termi- a) II[ sent, GO TO Step 24. nation of emergency - NOT SENT LJ
Peo. 978 87216 I NUMBER PROCEDURE TITLE REVISION 00 EFIP-2.02 NOTIFICATION OF NRC PAGE 8 of 8
- STEP ACTIOMEXPECTED RESPONSE RESPONSE NOTOBTAINED
- 23. (CONTINUED)
- 1) GO TO Step H
- 24. CLOSE D0k'N COMMUNICATIONS k'ITH NRC:
a) Request permission from NRC to close down communication channel with them b) k' hen permission is granted, a) IF NOT granted, remain on secure telephone line until permission is granted, THEN GO TO Step M.
'5. TERMINATE EPIP-2.02: )
a) Completed By: Time: Date: b) Forward all completed EPIPs and attachments to SNSOC for l review I l 4 END J
Peo. 978 4 7220 m NUMBER A TTACHMENT T/TLE REVISION EPIP-2.02 INITIAL REPORT OF 00 A TTACHMENT PAGE 1 1 of 2 This is Surr7 Power Stetion. In accordonce with the requirements of 10 CFR 50.72. I have en Initial rooort of an emergenw went to trenamit. Pienne inform me when you ers ready to copy. (Proceed vde informed.)
- 1. The time is . The date is / I . The facility is Surry Power Stettor..
- 2. My name is .
O Unusual Event C Alert
- 3. The event is ciensified et on / / .
C Site Emeqpency (24 nr. time toete) C General Emergency 4 Event description is (check til soolicso6e): C Radiological rolesse event C Contaminated. Injured personnel C Natural event C P! ant system malfuncdon C Securityincident C (Other) C Fire C Hazard to station operation
- 5. Cause of the event vens (bMef descrtodont l
- 6. Unit 1 power level prior to the event was % Unit 2 power levet prior to the event was E
- 7. Unit 1 power lowf now is W Unit 2 power low! now is E C has NOT C has NOT
- 8. Unit 1 Safety injection occurred: Unit 2 Safety injection occurred.
O has C hee i
\ C forced C forced
- 9. Unit 1 cooling mode is circuladon: Unit 2 cooling mode is circulation.
O notural C natural l
No. 978 87220 NUMBER A TTACHMENT TITLE REVISION Q EPIP-2.02 INITIAL REPORT OF EMERGENCY TO THE NRC 00 A TTACHMENT PAGE 1 2 of 2 O do NOT
- 10. We have increased contamination as a result of the event.
O do - O do NOT
- 11. We have e relance of radioecttve rneterial.
O do OkNOT C k NOT
- 12. Unit 1 Containtnent holsted: Unit 2 Ccetainment tsolated.
O is O is
- 13. Other problems are (brief descrtWon) h Unusael or not unoerstood conditions are bnef description)
[d 14
- 15. We have taken the following actions (check all applicable)
O Activated company emergency personnel and fecilities C Requested offsite low enforcement easietence O Oiapetched station rnonitoring teams offsite O None O Evacuated nonessential site personnel O (Other) O Requested offsite Firs Dept ensistence O Requested offste Rescue Saued semistence
- 18. We plan to take the following actions (Check all applicable)
D Activate company emergency personnel and facilities O Request offs!te law enforcement assistence O Dispatch station monitoring teems offsite D None O Evecuato noneamential site personnel D (Other) O Request offsite Ftro Oopt.senstence O Request offhte Rescue Squed seestance O have
- 17. We have notified the State of Virginie end local governments. We notified the NRO Resident inspector.
O teve NOT
~
- 18. We vdll transmit a supplemental report shortty. This is Surry Power Station out et time .
(2e hr. time) l
No.97887220 NUMBER A TTACHMENT TITLE REVISION 0% Q EPIP-2.02 SUPPLDENTAL REPORT OF DERGENCY TO NRC 00 p, gg A TTACHMENT 2 1 of 5 This is Surry Power Station. I how a supplemer tel report on our emergency event to transmit. Please inform me when you ers ready to copy. (Proceed when informed.) A. EM E AGEN0Y STATUS
- 1. The facility is Surry Power Station. My norne is . The time is .
(24 hr. time) ( O Unuouel Event C Alert
- 2. The event classification is C Site Ernergency classified at time on / / .
(24 hr. time) (cete) C Emergency terminated
- 3. Event deactlptun is (check all applicablel O Radiological release event (if checked, complets Sections B, C, and J belowJ O Plant system malfunedon (if checked, complete Sections B, D, and J belowJ Q Fire (if checked, complete Sections B, E, and J below.)
O Contaminated, injured personnel (if checked, complete Sections B, F, and J below.) C Security incident (if cf.acked, complete Sections B. G, and J below.) l Q Hazard to stadon operation (if checked, complete Seedons B, H,and J belowJ f D Natural ownt ( If checked, complete Seedons B,I, and J below.) 0 (Other; if checked, briefty describe here and complete Sectior.s B and J belowJ B. ACTIONS TAKEN OR PLANNED 1 We have taken the following actions (check all appilomble) l O Requested offsite Rescue Squad estistence ! O Notified State and local gowromonts O Notified the NRC Residere. Inspector D Requested offsite few enforcement essetence O Activated company emergency personnel and facilities D None D Dispatched station monitoring teams offsite Q (Other) O Evneusted noneesential site personnel D Requested offsite Fire Dept.assistonos
- 2. We plan to take the following actions (check o!! applicable)
D Notify the NRC ResWnt inspector C Request offsite law enforcement assistonos O Activote corr.peny emergency personnel and facilities D None O Dispetch stetton monitoring tsems offette O (Other) O Evacuate nonessential site personnel C Request offsite Fire Dept. sesistence O Request offsite Rescue Squed assistence l
Peo. 97 4 0 722C NUMBER A TTACHMENT TITLE REVISION j EPIP-2.02 SUFPLEMENTAL REPORT OF 00 A TTACHMENT PAGE 2 2 of 5 C. MP1QJ.OQtCAL PELEASE STATUS foonetrte if appilastHe) O has occurred.
- 1. Retesse of radioacthe meterials Q le presently occurring.
O is projected to occur. O ikruid. . The re' eses point eiewtion is ft.
- 2. The retenee is The row sourse le O goesous, icleocribel D rnonttored. O vues hrs.
O NOT monitored. O la estimated to be hrs. O microcuries/sec. O Curtes. 4 The re+eese rete is TN reense amount le O NOT present in the station. C1 1 J
- 5. Elevated redation levels are D present in the station, wtth rnR/hr in the .
\_ / Docetioni O NOT ewecuated any station eress.
- 6. We have D eh from ttie .
(locetton)
- 7. The rnsteorological conditions ero es follows:
- a. Wind direction from the d. Stability cises is .
- b. Mnd eosed is MPH. e. Prodottation form D none D retn D s6eet D stow
- c. Tempereture is ' F. D(Other!
O mR/hr et 2 mi mR/hr et 5 trd and mR/hr et to mi.
- 8. Estirneted preser.t offsite does retos are D unknosen.
f1 mm/hr et 2 mi.: mRthe et 5 mi and mRthe et 10 mi.
- 9. Projected Integreted whole Body doses are D unknoven.
O DFM A00 ern2 ,
- 10. IrMdant sortece contem6netson le D unknown.
l 2 D. DFM n00 cm .
- 11. Oneite surfoce contam6 nation D unknoesn.
O DFM /100 em2 , i
] 12. Offitte surface contaminetton is O unknousn. \
[ l l
Peo. 9 78 87220 NUMBER A TTACHMENT T/TLE REVISION EPIP-2.02 SUPPLEMENTAL PIPORT OF 00 A TTACHMENT PA GE 2 3 of 5 i D. PLANT STATUS (cornplete if applicatW)
- 1. Unit i reactor power lowei is %* Unit 2 reactor power level is % .
Unit 1 Reector Coo 6ent Svstem preneure is pois: Unit 2 Reector Cooient System prwesure is psis. 2.
- 3. Unit 1 T g is
- F: Unit 2 "*gis
- F.
O forced druletion with Reector Cooient Purnps running. 4 Unit 1 cooling mode is (no.) O forced circulation with Reector Cootent Pumps running.
- 5. Unit 2 cooling mode is (no.)
O NOTisoleted. O NOTisolated.
- 6. Unit 1 Containtnent is Unit 2 Containment is O NOT operating. O NOT opereting.
- 7. Unit 1 containment morey systorm are Unit 2 containment sprey systems ero C opereting. O operating.
N v
- 8. Unit 1 conteinment radiation lent is mR/hr; pressure is psie: temperature is
- F.
- 9. Unit 2 containment radiation level k mR/hr; preneure is psia; temperature is 'F.
O NOTInserted. O NOTinserted.
- 10. Unit 1 controf rods are Unit 2 control rods are C inserted. O inserted.
O NOT opereting. O NOT operating.
- 11. Unit 1 Safety inject'on System is Unit 2 Safety injection System is C operstmg. O operating.
- 12. Unit 1 S/G levels are % on "A" S/G: % on "B" S/G: and % on "C" S/G:
- 13. Unit 2 S/G lowo4e are % on "A" S/G: % on"B" S/G: and % on "C" S/G.
O NOT lasisted. O NOTisoleted.
- 14. Unit 1 S/G's are Unit 2 S/G's ero
- 15. Unit 1 feedenter source is . Unit 2 feedvetor source is .
O entiable.
- 16. Normal offsite electrical power is O NOT eveliable.
- 17. Unit 1 safegwds (amorgencyl bus power supply le for 1H bus and for 1J bus.
Unit 2 safeerde (emergencyl bus power supply la for 2H bus and for 2J bus, 18. s
- 19. Diamet generetors O cc 1 D 2:c 2 O cc 3 are running. Dienet generetorsD cc 1 D nc 2 O cc 3 ore icoded.
Pio,g7887220 NUMBER A TTACHMENT TITLE REVISION d EPIP-2.02 SUPPLDENTAL REPORT OF 00 EMERGENCY TO NRC A TTACHMENT PA GE 2 4 of 5
& Major equipment fellures are Qv6efly describe)
- 21. Mejor busses or tonos lost are (briefly describe)
E. FtRE STATUS (complete if applicable)
- 1. The fire is located et
- 2. The fire is Q out O contewied C worsening.
/m
/ Q) C NOT threatening asfety reteted oovipment. O throetesing the following safety seleted equipment: F. CONTAMIN ATED. INJURED PERSONNEL STARIS (complete if apolicable)
- 1. We have transported con sminated. injured indMduals to en offsite hospital.
(no.) G. SECURITY INClDENT STATUS (complete if applicable) C e bomb threat. (if checked, complete item G.2 below) 1 The security incident invoNes O esbotage. Ilf checked, complete item G.3 below.) . O en intrusion atiempt. (if checked, complete item G.4 below.)
- 2. (Complete for bomb threat incident.)
O conducted. Results of the search wLre .
- a. A search for the bomb was C NOT conducted.
D NOT evecuated,
- b. The site was O evacuated
- 3. (Complete for sabotage incident.)
C' O did NOT C did NOT
- a. The sabotage involve radioactive material and result in a rolesse.
[ Odad NOT b; The sabotage ' volve eroon or explosivos. e Odid
- c. The sabotage consasted of .
1 Peo.97887220 NUMBER A TTACHMENT TITLE REVISION x EPIP-2.02 SUPPLEMD'TAL REPORT OF 00 f EMERGENCY TO NRC p, gg A TTACHMENT 2 5 of 5 4 (complete for intrusion incident.) O NOT succeerful. -
- e. The intrusion ettempt ves "inswers" and " outsiders".
- b. The intrusion is estimated to have invoeved (no.)
(no.1
- c. The furthest point of intrusion was O were NOT C has NOT been compromised.
- d. Firearms involved. Control of the station g e 0 hee NOT
- e. Radioactive rnsterial been role. sed or stolen.
H AZAR D TO ST ATION OPER ATION STATUS (complete if applicable) h H. G O eircraft activity or crash.
- 1. The hetard involvee 3 explosion.
O toxic or fiammable oss row. O mostle impact Osmage.
- 2. A brief description of the hazard is
- 1. N ATUA AL EVENT STATUS (comp 4ste If appilosble) i
' C earthquake. 0 tomedo. l
- 1. The naturel event is a(n) O high susteined udnd.
O flood. O low veier.
- 2. A brief description of the event is O J. SIGNOFF 1 This k the end of this report. This in Surry Power Stedon aut et time (24 hr. time)
'4:,.97887230 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE (J huMBER PROCEDURE TITLE REVISION 4 ! 00 EPIP-2.03 REPORTS TO OFFSITE AGENCIES PAGE (With No Attachments) 1 of 8 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 OR Station Emergency Manager. ENTR Y CONDITIONS
- 1. An emergency has be declared; a
- 2. Entry is directed by another EPIP.
I i I r { REVISION RECORD REV. 00 PAGE(S): Entire Procedure DATE:JUL 2 9 1982 REV. PAGE(S): DATE: , REV. PAGE(S): DATE: REV. PAGE(S): DATE: ! REV. PAGE(S): DATE: ! REV. PAGE(S): DATE: REV. PAGE(S): DATE: APPROVAL RECOMMENDED APPROVED CA TE
// / , f 5L JUL 2 9 G82
/' ' ' / lHAIRMANSTA TION NUCLEAR SAFETY AND OPERA TING COMMITTEE t
No. 9788723 0 NUMBER PROCEDURE TITL.E REVISION EPIP-2.03 REPORTS TO OFFSITE AGENCIES P4GE 2 of 8
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 1. INITIATE PROCEDURE:
a) Initiated By: Time: Date:
- 2. CHECK RADIOLOGICAL STATUS:
a) Release of radioactive a) IF release of radioactive materials OR abnormal materials OR abnormal radiation exposures - radiation exposures NOT INVOLVED OR THREATENED involved OR threatened, [)
\, /
GO TO Step 16. 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 l reports made to the NRC Operations Center or the NRC Resident Inspector.
- 3. CHECK RELEASE STATUS:
a) Release of radioactive a) Il[ 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- [ lease concentration lease concentration , \s 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. l.
No.e7ssn:o NUMBER PROCEDURE TITLE REVlSION 00 EPIP-2.03 REPORTS TO OFFSITE AGENCIES PAGE 3 of 8
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINEO NOTE: The telephone number for NRC Director, Region II is (404) 222-4503. 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) IF concentration averaged averaged over 24 hours - over 24 hours NOT greater GREATER THAN 5000 TIMES MFC than 5000 MFC for unre-FOR UNRESTRICTED AREA stricted area, GO TO Step 6,. 1 g b) Immediately notify NRC Director, Region II by telephone AND telegraph, mailgram, OR_ facsmile
- 6. DETERMINE 24 HOUR NOTIFI-i CATON REQUIREMENT:
a) Concentration of release a) II[ concentration averaged averaged over 24 hours - over 24 hours NOT greater GREATER THAN 500 TIMES MPC than 500 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
- 7. CHECK OVEREXPOSURE STATUS:
a) Overexposures above 10 a) IF overexposures above 10 CFR CFR 20 limits - HAVE 20 limits have NOT occurred OCCURED OR ARE LIKELY OR been projected, CO TO Step TO OCCUR 10,. D O
he.97887218 NUMBER PROCEDURE TITLE REVISION O EPIP-2.03 REPORTS TO OFFSITE AGENCIES 00 PAGE 4 of 6
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINEO
- 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, Cgt 150 Rem Skin Cgt 375 Extremities, OR GO TO Step 9,. 150 REM SKIN SE 375 EXTREMITIES b) Immediately notify NRC Director, Region II by telephone AND telegraph, mailgram QR facsimile
- 9. DETERMINE 24 HOUR NOTIFI-CATION REQUIREMENT:
a) Actual Cgt likely over- a) IF actual OR likely over-exposures - GREATER THAN exposures NOT greater than 5 REM WHOLE BODY 5 Rem Whole Body Cgt 30 Rem Skin Cgt 75 Rem Extremities, pR GO TO Step 10. l 30 REM SKIN SE 75 REM EXTREMITIES b) Notify NRC Director, Region II by telephone AND telegraph, mailgram, OR facsimile within i 24 hours
- 10. CHECK PROPERTY DAMAGE STATUS:
a) Property - DAMAGED a) II[ property NOT damaged, GO, l
\ Tg Step M.
i s_ > l l
too.97887219 NUMBER PROCEDURE TITLE REVISION 00 EPIP-2.03 REPORTS TO OFFSITE ACENCIES PACE 5 of 8
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 11. DETERMINE IMMEDIATE NOTIFI-CATION REQUIREMENT: ,
a) Property damage - a) IF property-damage does NOT EXCEEDS $200,000 exceed $200,000, GO TO Step .
.I. 2,.
b) Immediately notify NRC Director, Region II by telephone AND telegraph, mailgram, Cg! facsimile
- 12. DETERMINE 24 HOUR NOTIFI-CATION REQUIREMENT:
a) Property damage . a) IF property damage does NOT EXCEEDS $2,000 exceed $2,000, GO TO Step 13,. (N , ( ,) b) Notify NRC Director, Region II by telephone AND telegraph, mailgram Cg! facsimile within 24 hours
- 13. CHECK STATION OPERATION STATUS:
a) Operation of one OR both a) IF operation of one OR both units - LOST units NOT Jost, GO TO Step
.I $.-
- 14. DETERMINE IMMEDIATE NOTIFI-CATION REQUIREMENT:
a) Operation of one OR both a) IF operation of one OR both units - LOST FOR GREATER units NOT lost for greater THAN ONE WORKING WEEK than one working week, GO TO Step 15,. b) Immediately notify NRC Director, Region II by telephone AND telegraph, mailgram, Og facsimile O
No. 978 8723 0 NUMBER PROCEDURE TITLE REVISION 00 EP1P-2.03 REPORTS TO OFFSITE AGENCIES PACE ] , 6 of 8
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OSTAINED
- 15. DETERMINE 24 HOUR NOTIFI-CATION REQUIREMENT: .
a) Operation of one OR both a) IF operation of one OR both units - LOST FOR ONE DAY units NOT lost for one day {gt MORE Cgt more, GO TO Step 16,. b) Notify NRC Director, Region II by telephone AND telegraph, mailgram, fyl facsimile within 24 hours
- 16. CHECK LOSS OR THEFT OF LI-CENSED MATERIAL:
a) Licensed material - LOST a) Jg[ licensed material NOT lost OR STOLEN OR stolen, GO TO Step 18,. Os 17. DETERMINE IMMEDIATE NOTIFI-CATION REQUIREMENT: a) Lost OR stolen material - a) IF lost OR stolen licensed PRESENTS SUBSTANIIAL material does NOT present HAZARD TO PERSONS IN UNRE- substantial hazard to per-STRICTED ARFAS sons in unrestricted areas, GO TO Step 18. b) Immediately notify NRC Director, Region II by telephone AND telegraph, mailgram,fytfacsimile , 18. DETERMINE TECH. SPEC. PROMPT NOTIFICATION REQUIREMENT: l l a) Any event listed in Speci- a) IF event has NOT cccurred, fication 6.6.2.a of Tech. GO TO Step 19. Specs. - HAS OCCURRED b) Notify NRC Director, Region II by telephone AND telegraph, ma11 gram,fyt facsimile within 24 hours s-l t l
No. 97 0 8 7214 NUMBER PROCE00RE TITLE REVISION EPIP-2.03 REPORTS TO 0FFSITE AGENCIES PAGE 7 of 8 2
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: 10 CFR 20.402, 10 CFR 20.403, and the Technical Specifications require written follewup reports to be submitted. Measures f ,
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) The telephone number for ANI is (203) 677-7305
- 20. NOTIFY VEPC0 INSURANCE DEPT.:
I T a) Call the VEPCO Insurance V Dept, at 771-4004 b) Inform them that ANI has been notified
- 21. VERIFY EMERGENCY STATUS:
a) Emergency - NOT TER- a) IF, emergency terminated, MINATED GO TO Step 23;.
- 22. MONITOR NOTIFICATION EVENTS:
a) Il[ release of radioactive a) IF NOT, continue to monitor materials - OCCURS until emergency terminated, THEN GO TO Step 23. SE Release of radioactive materials - INCREASES SE Release of radioactive materials - IS PROJECTED
- i, sJ .
No. 97887219 NUMBER PROCEDURE TITLE REVlSION 00 EPIP-2.03 REPORTS TO OFFSITE AGENCIES PAGE 8 of 8 STEP ACTION / EXPECTED RESPONSE RESPONSENOT OBTAINE0 l
- 22. (CONTINUED)
~
M Overexposures - OCCUR S Overexposures - ARE LIKELY Loss or theft of licensed material - OCCURS S ( Event listed in Specif1-cation 6.6.2.a of Tech. Specs. - OCCURS GO TO Step 2,
- 23. NOTIFY ANI 0F TERMINATION:
a) Notify American Nuclear Insurers of emergency , termination b) Use telephone number
- listed in Step 19.b
- 24. TERMINATE EPIP-2.03:
a) Completed By: Time: Date: b) Forward procedure to SNSOC for review END I
,_y- - , , . -
w- -,
-- . _ --+_ -_,s. - . - - .
ht.97881230 e l VIRGINlA ELECTRIC AND POWER COMPANY Je.- SURRY POWER STATION ' f EMERGENCY PLAN IMPLEMENTING PROCEDURE .j < (- NUMBER PROCEDURE TITLE REVISIUN' . 00 EPIP-3.01 CALLOUT OF EMERGENCY RESPONSE PERSONNEL pggg (k'ith 1 Attachment). t
.1 of 3 J
y.
~: ;
PURPOSE
'. . . _~
. .=
- 1. To callout station: AND corporate emergency' responhe persennel if . they are not already at their normal work locations. -
s USER Security Team Leader OR Station Emergency Manager
, n ENTR Y CONDITIONS
- 1. Initiation directed by the Station Emergency' Manager' .
/
REVISION RECORO REV. 00 PAGE(S): Entire Procede, DATEdVL 2 91982 7 REV. PAGE(S): '
.DATE:
REV. PAGE(S): DATE: - REV. PAGE(S): DATE: REV. "~ PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: APPROVAL RECOMMENDEO APPROVED ~ CA TE -
/ '
osc~ - ,. d . YH .. CHAIRMAN STA TION NUCLEAR SAFETY AND OPER$ilNG COMMITTEE
' N o. 9 7887210 I
NUMBER PROCEDURE TITLE REVISICN O 00 EPIP-3.01 CALLOUT OF EMERGENCY RESPONSE PERSONNEL PA GE 2 of 3
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED ^~ '
- 1. _ --INITIATE PROCEDURE:
,e) Initiated By:
f Time: Date:
- 2. OBTAIN EMERGENCY PERSONNEL NOTIFICATION LIST.
a) Attachm'ent 1 of this procedure
- 3. NOTIFY EMERGENCY RESPONSE PERSONNEL:
a) Use all available tele-
~ -
phones and Security personnel to make the notification as rapidly as possible b), Notify, in order, the individuals listed in the Attachment until at least one individual is reached in each department c) Transmit the message indi-cated for that department, verify the message has been understood, and then move to next department d) Read messages exactly as written in Attachment 1 of this procedure
No.910812:0 i NUMBER' PROCEDURE TITLE REVISION
.00
. EPIP-3.01 CALLOUT OF EMERGE!;CY RESPONSE PERSONNEL ; PA GE
-3 of 3
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED -
! 4. RECORD TIME CALLOUT COMPLETED: ! a) .Callout of above departments completed at (time) . 5. INFORM STATION EMERGENCY MANAGER TI!!E CALLOUT COMPLETED: i
- 6. Tete!INAlt, EPIt'-3.01:
a) Close-Out
- 1) COMPLETED BY:
TIME: DATE: i l l l END O
no. ns e nte NUMBER A TTACHMENT TITLE REVISION EMERGENCY PERSONNEL N TIFICATION LIST A TTACHMENT PAGE 1 1 of 6
'l. INSTRUCTIONS TO SECURITY: Use all available security personnel and telephone lines to make the following notifications as rapidly as possible. Notify, in order, the individuals listed below until at least one individual in each department has been notified. When each individual is reached, transmit the message indicated for that department, verify the message has been understood, and then move to the next department.
- 2. GENERAL OFFICE SECURITY (Richmond)
MESSAGE: "This is Security at Surry Power Station. An emergency has been declared at Surry Power Station. Commence the callout of the. Corporate Emergency Response Team in accordance with the Corporate Emergency Response Plan." NAME EXT. TELEPHONE NUHBER General Office Security
?
- 3. STATICN MANAGEMENT RESSAGE: "This is Security at Surry Power Station. This message is to inform you that an emergency has been declared at the station."
NAME EXT. TELEPHONE UUMBER ! J. L. Wilson . i R. F. Saunders i ! _ G. E. Kane lO c
^
i
no.tras122e NUMBER A TTACHMENT TITLE REvlSION EPIP-3.01 00 O A TTACHMENT EMERGENCY PERSONNEL NOTIFICATION LIST PAGE 1 2 of 6
- 4. HEALTH PHYSICS DEPARTMENT MESSAGE: "This is Security at Surry Power Station. An emergency has been declared. Commence callout of emergency response personnel in your department in accordance with your departmental emergency notification list.
NAME EXT. TELEPHONE NUMBER S. P. Larver f I P. P. Nottingham Barry Garber j I Dean Densmore /
- 5. TECHNICAL SERVICES DEPARTMENT Message: "This is Security at Surry Power Station. An emergency has been declared. Commence callout of emergency response personnel in your department in accordance with your departmental emergency notification list."
NAME EXT. TELEPHONE NUMBER D. A. Christian e Eugene Grecheck Douglas Rickeard Larry Curfman John Horhutz George Pitonyak , l Rick Dailey ' Tom Swindell Larry Miller
\
No.97887228 NUMBER A TTACHMENT TITLE REVISION EPIP-3.01 00 A TTACHMENT PAGE
, 1 3 of 6
- 6. MAINTENANCE DEPARTMENT MESSAGE: "This is Security at Surry Power Station. An emergency has been declared. Commence callout of emergency response personnel in your department in accordance with your departmental emergency notification list."
NAME EXT. TELEPHONE NUMBER H. W. Kibler l Jerry Oliver l 1 John Patrick ! Dick Mudd
- 7. SECURITY LEPARTMENT MESSAGE: "This is Security at Surry Power Station. This message is to inform you that an emergency has been declared at the station."
NAME EXT. TELEPHONE NUMBER Otto Wegman i H. J. Van Dyke
. B. B. McDuffie
,/
- - -~
D .
Fwo.97887220 NUMBER A TTACHMENT TITLE - REVISION EPIP-3.01 00-EMERGENCY PERSONNEL NOTIFICATION LIST
, A TTACHMENT PAGE 1 4-of 6
- 8. ADMINISTRATIVE SERVICES DEPARTMENT MESSAGE: "This is Security at Surry Power Station. An emergency has been declared. Commence callout of emergency response personnel in your department in accordance with your departmental emergency notification list."
NAME EXT. TELEPHONE NUMBER-W. R. Runner E. P. DeWandel F. M. Cox I l Luther Farinholt Carl'Winecoff i 7
- 9. QUALITY CONTROL DEPARTMENT MESSAGE: "This is Security at Surry Power Station. An emergency has been declared. Commence callout of emergency response l personnel in your department in accordance with your departmental emergency notification list."
l NAME EXT. TELEPHONE NUMBER Richard Driscoll , . Frank Rentz . Dean Grady f
, Bill Earl r
~%
, ~ O
No.91631220 NUMBER A TTACHMENT TITLE REVISION EPIP-3.01 00 EMERGENCY PERSONNEL NOTIFICATION LIST A TTACHMENT PAGE
> 1 5 of 6
- 10. TRAINING DEPARTMENT MESSAGE: "This is Security at Surry Power Station. An emergency has been declared. Commence callout of emergency _ response personnel in your department . accordance with your departmental emergency notification list."
NAME EXT. TELEPHONE NUMBER Larry Edmonds
- 0. A. Vogtsberger H. McCallum L. Gardner
- 11. NRC MESSAGE: "This is Security at Surry Power Station. This message is to inform you that an emergency has been declared at the station."
4 d ! NAME EXT. TELEPHONE NUMBER i i Don Burke i , i Mike Davis
- 12. TERMINATE ATTACHMENT 1
- - ,
I j a) Close-Out I
- 1) COMPLETED BY:
DATE:
, ,, TIME:
No.07:3722o A UMBER A TTACHMENT TITLE REVISION
') EPIP-3.01 00
'd EMERGENCY PERSONNEL NOTIFICATION LIST A TTACHMENT PAGE 1 6 of 6
- 12. (CONTINUED) b) Affix this Attachment to EPIP-3.01 O
o Eh3 v
*v3,97887230 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE O
V -NUMBER PROCEDURE TITLE REVISION 00 EPIP-3.02 ACTIVATION OF TECHNICAL SUPPORT CENTER PACE (With 10 Attachments) 1 of 8 PURPOSE
- 1. To provide guidance to personnel charged with TSC Activation.
- 2. To provide guidance to TSC members.
USER Emergency Administrative Director OR Available TSC Personnel ENTRY CONDITIONS
- 1. Declaration of Alert, Site Emergency or General Emergency; AND
- 2. Entry from another EPIP; 0R,
- 3. Direction of Station Emergency Manager.
l REVISION RECORO l REV. 00 PAGE(S): Entire Procedure DATEdVL 2 91982
- REV. PAGE(S)
- DATE:
. REV. PAGE(S): DATE: REV. PAGE(S): DATE: ' l REV. PAGE(S): DATE: l REV. PAGE(S): DATE:
- REV. PAGE(S)
- DATE:
APPROVAL RECOMMENCEO APPROVE 0 DA TE f, g/ [ 3^ CHAIRMAN STA TION NUCLEAR SAFETY JUL 2 6 1982 AND OPERA TING COMMITTEE
. , m-Peo.97887210 NUMBER PROCEOURE TITLE REV/SION 00 EPIP-3.02 ACTIVATION OF TECHNICAL
^O
, SUPPORT CENTER
! 2 of b
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINEO l
NOTE: During normal hours of business, activation of the TSC is the responsibility of the Emergency Administrative Director. If callout of personnel is required, the first member to report should implement this instruction. , 1. INITIATE PROCECURE: a) BY: DATE: TIME:
- 2. ACCOUNTABILITY:
I ) a) Log TSC personnel on
-/ Attachment 1 as they arrive b) Maintain accountability c) Notify Station Security of personnel 2n TSC i NOTE: Two individuals are required to move TSC equipment.
- 3. TSC EQUIPMENT:
i a) Obtain key to Coordinator Emergency Planning Office from Security b) Deliver TSC " Materials Kit" in Coordinator Emergency Planning Office closet to TSC c) Obtain table from Unit P2 Computer Rocm i 4 s- d) Set-up TSC IAW Attachment j 10
No.97887210 t NUMBER . PROCEDURE TITLE REVISION 00 EPIP-3.02 ACTIVATION OF TECHNICAL SUPPORT CENTER #46f ' 3 of 8 ]
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
?
.3. (CONTINUED)
- 1) Tables (3)
- 2) Easels (3)
. 3) Status Boards (3) ; 4) 6 buttom Ringdown Phones i
from Relief Office (2). .I j 5) licadphones (2) e) Initiate TSC " log"
- 4. C0mfUNICAT10N:
j a) Uncoil telephone cables from above drop ceiling and lower $ .b) Connect 6 button Rindown i- Phones to cables i c) IF, desired, and personnel available, stablish com-munication to Main Control i l Room via Ringdown Phone or Station PBX d) IF desited, and personnel [ available, establish j communication to OSC via 1 Ringdown Phone or Station PBX
- 5. CHECKLISTS:
i ! a) As each Emergency Manager / Director OR alternate i arrives in TSC distribute appropriate attachment $ s
No.s7ss721o NUMBER PROCEDURE 17TLE REVISION C; EPIP-3.02 ACTIVATION OF TECRNICAL 00 SUPPORT CENTER #A6E 4 of 8 .
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED d
- 5. (CONTINUED)
- 1) Station Emergency Manager Guideline, Attachment 2
- 2) Emergency Operations Director Guideline, Attachment 3
- 3) Emergency Technical Director Guideline,
- l Attachment 4 4
- 4) Emergency Administrative Director Guideline, Attachment 5
[v)
- 5) Emergency Maintenance Director Guideline, Attachment 6
- 6) Radiological Assessment Director Guideline, Attachment 7
- 7) Emergency Communicator Guideline, Attachment 8 I
- 8) Emergency Procedures l Coordinator Guideline, Attachment 9 i NOTE: The following Steps 6 thru 12 describe steps required to set-up TSC printers for operation (4 required).
I IF Control Room printer fails due to electronic failure {g[ paper fault, the TSC printer will stop, also, f) v
/XX/ is convention for a key stroke.
t
-.~ - . .- - , - . . , ,
No. 97887210 j l NUMBER PROCEDURE TITLE REVISION i 00 l \ EPIP-3.02 ACTIVATION OF TECHNICAL , j SUPPORT CENTER #A6E j 5 of 8 ! - STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINEO
- 6. VERIFY SPITCH POSITIONS:
a) Front of printer:
- 1) 0FF LINE
[ Black Bkg]
- 2) ANL ~
[ White Bkg]
- 3) 300
[ Black Bkg]
- 4) PSX/FDX
[ White Bkg] 5)'ALF [ White Bkg]
- 6) 1200
[ktite Bkg] b) Rear of printer: _;
- 1) PARITY SWITCll
{0dd] 7
- 2) BAUD RATE SWITCH
[1200]
- 3) XMIT CLOCK SWITCH
[ Centered]
- 7. ENERGIZE PRINTER:
j a) Verify the following:
- 1) Power on Light - ON
- 2) XMIT Light - ON 1
. . _ ._ . _ . . , _ _ _ . _ _ _ _ . , _ . . _ . . _ . . . . _ _ _ _ _ _ _ . . _ _ _ , .,_-,,.,_..,__._____,.,___.-...,z.- _ _ . - . . . . _ _ - - _ .
No. 978 57210 NUMBER PROCEOURE TITLE REVlSION O EPIP-3.02 ACTIVATION OF TECHNICAL 00 PA GE SUPPORT CENTER 6 of 8
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: The following key pad sequences are to be entered on right side of printer.
- 8. PROTOCOL SET-UP:
a) / ESC /,/9/,/3/ b) / ESC /,/8/,/0/ c) / ESC /,/9/,/1/ d) / ESC /,/8/,/7/ e) / ESC /,/8/,/2/ j (
- 9. PRINT SIZE SET-UP:
a) / ESC /,/7/,/4/ b) / ESC /,/7/,/7/
- 10. HORIZONTAL MARGINS:
a) Roll paper to top of a sheet, with preforations dividing print head in half l b) Enter the following Keypad sequences: 4 1) / ESC /,/5/,/3/,/0/,
/6/,/6/
- 2) / ESC /,/5/,/4/,/0/,
- /0/,/0/
- 3) ESC /,/5/,/5/,/0/,
/5/,/7/
() I
- 4) /FF/
l l
t,o.97547210 A UMBER PROCEDURE TITLE REVISION s \s - EPIP-3.02 ACTIVATION OF TECHNICAL SUPPORT CENTER E46E 7 of 8
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAlflEO
- 10. (CONTINUED) c) Verify paper advance d) Set paper to print one-inch below top of sheet
- 11. STORE INFORMATION IN MEMORY:
a) / ESC /,/9/,/8/
- 12. PLACE ON LINE:
,_s a) At printer front, depress
( On Line/Off Line Switch \m -) to - ON LINE [ White Bkg) NOTE: Printers will now operate in parallel to those in the Control Room.
- 13. VERIFY MONITORING:
a) Verify H. P. monitoring equipment operating
- 14. VERIFY ACTIVATION:
a) Required TSC personnel a) IF required, call out in place additional personnel. C0 TO Step 12.
- 15. TERMINATE EPIP-3.02:
a) TSC deactivated by Station a) DO NOT terminate until Emergency Manager deactivation complete. b) Close-out
- 1) COMPLETED BY:
e i DATE: LJ TIME:
N o. 97487210 4 NUMBER PROCEDURE T1TLE REVIS10N
' O' EPIP-3.02 ACTIVATION OF TEC11NICAL FA6f SUPPORT CENTER 8 of 8
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED i
- 15. (CONTINUED) c) Verify completion of all attachments 1
i d) Forward Procedure EPIP-3.02 and all ten (10) attachments to SNSOC for review e) Return TSC equipment to appropriate storage locations
\s-
No. 918 87220 NUMBER A TTACHMENT TITLE REVISION EPIP-3.02 00 TECHNICAL SUPPORT CENTER MANNING
. ATTACHMENT PAGE 1- 1 of 2 NOTE: Log personnel name and time of arrival for accountability purposes, i
- EMERGENCY POSITION PRINCIPLE ALTERNATE Station Emergency Manager Emergency Operations Director Emergency Technical Director Emergency Maintenance Director i Emergency Administrative Director Radiological Assessment Director Emergency Communicator Emergency Procedures Coordinator ADDITIONAL PERSONNEL i
Maintenance Support Team Administrative Support Team 6 Technical Support Team Radiological Assessment Team. i k r
.- .. . . - . . . , , _. ,._.__._____._-..,___.-._-...-_._,,,,_m..- . . . . , , - . . . - , - -,-, u
s no. oresnzo 1
- NUMBER A TTACHMENT TITLE REVISION
., EPIP-3.02 00 TECHNICAL SUPPORT CENTER MANNING
' PAGE A TTACHMENT
'l- 2 of 2
- Miscellaneous Personnel l
r i j 2 2 a 4 e t I i i -l l l l l i l l l l 4 i l' I..._..--..,_._..,__._,,______.._,_.,_._-._.___._.._.___.....__.._.._..____.~___._,..._._.-_..___.-.
No.97887220 NUMBER A TTACHMENT TITLE REVISION EPIP-3.02 00
* ^GE O *U IU A TTACHMENT pAgg 2 1 of 4 STEP
- ACTION / EXPECTED RESPONSE RESPONSE NOT OSTAINED NOTE: This Attachment may be implemented by an alternate alternate individual the Station Emergency Manager position is NOT located in TSC.
- 1. INITIATE EPIP-3.02, ATTACHMENT.2:
a) BY: DATE: TIME:
- 2. EMERGENCY ORGANIZATION:
a) Check with Security (PBX-and verify response personnel or alternates present or enroute:
- 1) Emergency Operations Director
- 2) Emergency Maintenance j Director l 3) Emergency Technical l Director i 4) Emergency Administrative Director
, 5) Radiological Assessement Director ,
- 6) Emergency Procedures Coordinator
- 7) Emergency Ccemunicator
- 8) OSC Director tat OSC)
. -. . . _ . = - . . . . . - . -. -.- . - . - . . _
; n...,.. m s NUMBER A TTACHMENT TITLE REVISION EPIP-3.02 00 A TTACHMENT
'" " PAGE
! 2 2 of.4 i i. i' ! STEP
- ACTION / EXPECTED RESPONSE
- RESPONSE NOT OBTAINED f
i 4 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:
e ; a) The following decisions shall NOT be delegated j 1) Clasification of. J emergency i
- 2) Notification of offsite l
agencies and recommen-dation of protective } measures prior to EOF i activation ! 3) Discontinue onsite i activities i j 4) Order. site evacuation l l
- 5) Restrict site access
! 6) Authorize emergency l exposure limits
- 7) Contact VEPCO management i
I 4. OSC: l a) Verify resources with OSC i Director i
- 1) Fire Brigade
- 2) First Aid Team i
i- . I !
+
l I
40.97887220
,- m NUMBER A TTACHMENT TITLE REVISION
(\' ) EPIP-3.02 00 STATION EMERGENCY M/JAGER GUIDELINE A TTACHMEN T PA GE 2 3 of 4 STEP
- ACTION / EXPECTED RESPONSE
- RESPONSE NOT OBTAINED
- 4. (CONTINUED)
- 3) Damage Control Team
- 4) Search and Rescre Team
- 5. COMMUNICATION:
a) Assure timely notifi-cation of offsite authorities r\ I
'-- NOTE: Actions of procedures may be modified, during emergency conditions, only at the discretion of the Station Emergency Manager.
- 6. DIRECTION:
a) Assure direction of the Emergency is conducted IAW EPIP-1.01, Emergency Manager Controlling Procedure b) Assure development of and approve additional temporary procedures as required
- 7. RELIEF:
a) Assure suitable arrangements for timely relief of emergency response personnel through Emergency Administrative Director 7~ ( ) v
, - . . - = , _ . . . .- . , . . . . . _ . . _ - . . . _ - ., . _ _ ,
No.97887220 i
! .. NUMBER . A TTACHMENT TITLE REVISION .
EPIP-3.02 00 k STATION EMERGENCY MANAGER GUIDELINE. k A TTACHMENT PA GE
-2 4 of 4 j 1
1 1 STEP
- ACTION / EXPECTED RESPONSE
- RESPONSE NOT OBTAINED I
; 8. TERMINATE ATTACHMENT 2:
a) Verify TSC - DEACTIVATED a) Return.to previous steps
, of this Attachment 2.for 8
OR reference 1 Personnel - RELIEVED
, b) Close-out 4 1) COMPLETED BY:
- i. .
DATE:
- i. TIME:
i c) Affix this Attachment 2 to EPIP-3.02 l-4 9 0 J s 4 i 1 END d I
- . ~ . - . _ _ _ _ _ . .-- . - - - . . - - . - . - . .
No. 9138722C NUMBER A TTACHMENT TITLE REVISION , EPIP-3.02 u00
-- EMERGENCY OPERATIONS DIRECTOR GUIDELINE i A TTACHMENT PAGE 3 1 of 3 l STEP
- ACTION / EXPECTED RESPONSE
- RESPONSE NOT OBTAINED 2
l 1. INITIATE EPIP-3,02, ATTACHMENT 3: a) BY: DATE: TIME: I
- 2. COMMUNICATIONS:
a) Obtain operator from Emergency a) Obtain Nuc. Training Coord-Switchgear Room inator from Administrative Director O k_-
% b) Establish communications b) Establish communications to from TSC to Main Control Control Room via available Room via Ringdown Phone means 4
, c) Update Station Emergency Manager in a timely manner d) Insure status boards i maintained i
- 3. VERIFY:
l a) 11[ required, obtain opera-l tional status from Control Room personnel ! 4. SUPPORT: I a) Verify availability of opera-tions personnel in OSC b) As requirei, request addi-tional personnel to support operational activities ns-m c) As required, request material and equipment via Emergency Administrative Director i i
No.s7ss722e NUMBEA A TTACHMENT 77TLE REVlSION (Oj V EPIP-3.02 E!ERGENCY OPERATICUS DIRECTCE GUIDELINE 00 A TTACHMENT PAGE 3 2 of 3 I STEP
- ACTICN/ EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 5. DIRECTION:
i a) As required, advise or direct !' Control hocm Personnel in the mitigation of operational events b) As required, provide status change information and operational recommen-dations to the Station Emergency Manager g c) Assure proper usage of ! N' Station procedures by l Operations perscnnel , d) Evaluate safety status ! of any unaffected units e) Assist in the development of any temporary proced-l urcs required for con-ducting emergency actions I
- 6. RELIEF:
a) Assure suitable arrange-ments for relief of: , 1) Supplemental OperatioF personnel )
- 2) On-duty Operatons personnel
- 3) Emergency Operations Director position i
4 m-gw-=..y s- +- 7 y >w.9mm+ y q,: ,, ,,-_e , _f,,,,e p ..y-.-mww._-,_. .., ..-_%_--.mw ,y --%r.. 4-,--,,--.e m --.
]: ~...... m o I NUMBER A TTACHk cNT TITLE REVISION
}
EPIP-3.02 -00 EMERGENCY CPERATIONS DIRECTOR GUIDELINE. A TTACHMENT PA GE
- 3- 3 ef 3 L
STEP
- ACTION /EXPECTEL RESPONSE RESPONSE NOT OBTAINED
! 7. ' TERMINATE ATTACHMENT 3: I J a) Verify TSC - DEACTIVATED a) Return to previous steps of this Attachment 3 for 1 OR reference. j Personnel - RELIEVED i b) Close-out 4
- 1) COMPLETED BY
DATE:
' TIME:
c) Affix this Attachment 3 . to EPIP-3.02 i 3 l l r END
~
4 No 97887229 i NUMBER A TTACHMENT TITLE REVISION EPIP-3.02 00 A TTACHMENT PAGE 4 1 of 3 STEP
- ACTION / EXPECTED RESPONSE
- FISPONSE NCT OBTAINED
'{ ) 1. INITIATE EPIP-3.02, ATTACHMENT 4: a) BY: DATE: i. TIP2: (
- 2. ORGANIZATION:
a) Verify Technical Support *Obtain necessary personnel
- Team:
O Ij s 1) Engineering Supervisor
- 2) SES Engineer
( 3) Reactor Engineer i I g
- 4) Engineer (Mechanical)
- 5) Engineer (Electrical) b) Verify Chemistry Team c) Verify Instrument person-nel in OSC
- 3. ACTIVITIES:
a) Direct the activities of I the following:
- 1) Technical Support Team
- 2) Chemistry Team O
l
- - _ _ _ . _ . _ - - - _ _ _ . _ _ _ _ . _ . . . _ _ _ _ _ - - - _ _ . _ . . . _ , . ~ _ . . - . - _ , _ . .
4
- No. 918 01220 4
NUMBER A TTACHMENT TITLE REVISION O EPIP-3.02 A TTACHMENT EMERGENCY TECilNICAL DIRECTOR GUIDELINES 00 PAGE 4 2 of 3 STEP
- ACTION / EXPECTED RESPONSE
- RESPONSE NOT OBTAINED
, 4. ENGINEERING ANALYSIS:
a) Analyze and aid in de-1 . velopment of solutions to problems in the fol-lowing areas of exper- ' l tise:
- 1) Engineering-
- 2) Reactor Physics
- 3) Instrumentation and Control 4
- 4) Chemistry
- 5. SUPPORT:
a) Provide Technical Support to the Station Emergency 1 Manager f 6. PROCEDURES: 1 a) Assist in the development i of any temporary pro-cedures required for con-ducting emergency actions
- 7. NRC INTERFACE:
i 2 ! a) Interface with NRC and I aid in resolution of ! questions concerning license requirements l
- 8. RELIEF:
f a) Assure suitable arrange-l (s ments for relief of:
- 1) Technical Support Team
N2. o rsa nto NUMBER A TTACHAfENT TITL E REVISION [ EPIP-3.02 00 (m, EMERGENCY TECHNICAL DIRECTOR Gt'IDELINES A TTACHMENT PAGE 4 3 cf 3 STEP
- ACTION / EXPECTED RESPONSE
- RESPONSE NOT OBTAINED
- 8. (CONTINUED)
- 2) Chemistry Team
- 3) On-Duty STA
- 4) Instrumentation Mem-bers of OSC
- 5) Emergency Technical Director Position
- 9. TERMINATE ATTACHMENT 4:
s_,- a) Verify TSC - DEACTIVATED a) Return to previous steps of this Attachment 4 for {g! reference. Personnel - RELIEVED b) Close-out
- 1) COMPLETED BY:
DATE: TIME: c) Affix this Attachment 4 to EPIP-3.02 END
'h v
ree.s7s 72:e NUMEER A TTACHMENT TlTL E REVISION
/ \ EPIP-3.02 00 EMERGENCY ADMINISTFATIVE D! RECT 0F GUIDEI,INES A TTACHMENT PAGE 5 1 of 5 STEP
- ACTION / EXPECTED PLSPCHSE RESPONSE NOT CBTAINED
- 1. INITIATE EPIP-3.02, ATTACliMENT 5:
a) BY: DATE: TIME:
- 2. ORGANIZATION:
a) Verify Administrative *Cbtain necessary personnel. Support Team (~N s
\._,) 1) Security Supervisor
- 2) QC Supervisor CR QC Engineer
- 3) Nuclear Training Coordinator
- 4) Fire Marshall
- 5) Clerks
- 6) Safety Supervisor b) Verify Security Team
- 1) Security Shift Supervisor
- 2) Security Officers
- 3) Security Control System Operator
- 4) Administrative Security
/ ') Officers \v J W -- .- _ _ _ _ _ . _ _ . _ _ _ _
No. 9 74 0 7220 NUAfBER A TTACHAfENT TITLE REVISION [ ~') EPIP-3.02 00 \- / EMERGENCY ADMINISTRATIVE DIRECTOR GUIDELINES A TTACHAfENT PAGE 5 2 of S
- RESPONSE NOT OBTAINED STEP
- ACTION / EXPECTED RESPONSE
- 3. VERIFY TSC:
a) IF required, assist in logistics of TSC activation 4 INTERFACE: a) Advise Static' Emergency Manager on Fire Protection. Security Administration. Logistical Support, and First Aid O s_/ b) Verify Emergency Communi-cator IAW EPIP-3.02, Attachment 8 c) Verify Emergency Procedures Coordinator IAW EPIP-3.02, Attachment 9
- 5. DIRECTION:
a) Provide clerical and records support
- 1) Maintain TSC log -
b) Assure TSC accountability c) Direct Security Team on the following:
- 1) Personnel Account-ability
- 2) Access Control
/T 3) Station Security~ V
__. __. _ _ _ __ . . _ _ _ . __ . . _ . . - _ . . .. - . _ _ = _ - . . - - _ _ _ _ - _ _ _ _ _ - - _
! No. 97447220 j
~
NUMBER A TTACHMENT TITLE REVISION l- EPIP-3.02 ~00 l EMERGENCY ADMINISTRATIVE DIRECTOR GUIDELINES A TTACHMENT PAGE 5 3 of 5 i 1 STEP
- ACTION / EXPECTED RESPONSE
- RESPONSE NOT OETAINED
; 5. (CONTINUED)
- 4) EOF Actuation f
, 5) Maintain liaison with ! local law enforcement agencies , 6. PROCEDURES:
1 l a) Assist in the development and review of any tem-l porary procedures required l for conducting emergency i actions j 7. COORDINATION: l a) Coordinate acquisition of j
- equipment, supplies, and l personnel
i 1 Onsite availability i 2) Offsite thru EOF b) Record on Resource Request (Attachment 5 Page 5 of 5) c) Assure timely follow up
- on logistical items i
! 8. REL1EF: I a) Assure suitable arrange-ments for relief of:
- 1) Administrative Support Team I
l
no.orss1220
,._ NUMBER A TTACHMENT TITLE REVISION / EPIP-3.02 00 (s_-) EMERGENCY ADMINISTRATIVE DIRECTOR Gt'IDELINES A TTACHMENT PA GE 5 4 of 5 STEP
- ACTION / EXPECTED RESPONSE
- RESPONSE NOT OBTAINED
- 8. (CONTINUED)
- 2) Security Support Team
- 3) Emergency Communicator
- 4) Energency Procedures Coordinator
- 5) Postion of Administrative Director b) Via Emergency Directors, assure
/}
relief of Emergency Response s._/ Personnel
- 9. TERMINATE ATTACHMENT 5:
a) Verify TSC - DEACTIVATED a) Return to previous steps of this Attachment 5 for OR reference. Personnel - RELIEVED b) Close-out
- 1) COMPLETED BY:
DATE: TIME: c) Affix this Attachment 5 to EPIP-3.02 1 .O END lG i l
No.91587220 hukfBER A TTACHATENT TITLE REVISION [~~'T EPIP-a.02 00
'(j EERCENCY ADMINISTRATIVE DIRECTOR GUIDELINES A TTACHAfENT PA GE 5 5 of 5 RESOURCES REQUEST NAME OF ITEM OR SERVICE REQUESTED BY SOURCE INDIVIDUAL (s) \
v I , v
No,97887220 ['y NUMBER A TTACHMENT TITLE REVISION t , EPIP-3.02 00
EMERGENCY MAINTENANCE DIRECTOR CUIDELINE A TTACHMENT PA GE 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 *Obtain necessary personnel. 7-~x 1) Supervisor Maintenance Se rvice s (d)
~
- 2) Supervisor Mechanical Maintenance
- 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 Leaders
- 4. SUPPORT:
a) Provide maintenance support to Station Emergency Manager r> ( ) b) Provide timely updates on damage control activities
l No. 97887220 f NUMBER A TTACHMENT TITLE REVISION t EPIP-3.02 00 EMERGENCY MAINTENANCE DIRECTOR GUIDELINE A TTACHMENT PAGE 6 2 of 3 4 1 i : STEP
- ACTION / EXPECTED RESPONSE
- RESPONSE NOT OBTAINED f
- 5. INTERFACE:
a) Coordinate activities with other departments via Emergency Directors b) Coordinate acquisition of equipment, supplies and personnel through the Emergency Administrative Director 1 l , c) Assure timely follow up i
- 6. PROCEDURES:
a) Assist in the development
- and review of temporary procedures required for conducting emergency actions .
- 7. RELIEF:
a) Assure suitable arrangements , for relief of: i
- 1) Maintenance Support Team i
- 2) Damage Control Teas i
Leaders i
- 3) Maintenance Members of l Damage Control Team
- 4) Position of Emergency Maintenance Director
- 8. TERMINATE ATTACEMENT 6:
- a) Verify TSC - DEACTIVATED a) Return to previous steps of this Attachment 6 for Ojt reference.
Personnel - RELIEVED l-
. . . . ., _ _ . . _ _ _ . _ _ . . _ _ _ . _ _ . . _ _ . _ . - . . . _ . - m. . .._ . _ . . _
No.97887220 l i, , NUMBER A TTACHMENT TITLE REVISION l EPIP-3.02 00 EMERGENCY MAINTENANCE DIRECTOR GUIDELINE A TTACHMENT PA GE 6 3 of 3 i i i i STEP
- ACTION / EXPECTED RESPONSE
- RESPONSE NOT OBTAINED 3 .- 8. (CONTINUED) i b) close out
- 1) Completed By:
Date: Time: i c) Affix this Attachment 6 to ! EPIP-3.02 l i t
+
l I l i l END i v r
, ~ . . - - . , . . ~ , - ---..y 7,-- - , , - . - ,. , . - . ,, , , , . ,,.,.,_,,...,-_m. . .4 .,.. ,y ., . -, ._ . . , - * . . - - . - . - . =-- -
no.usenso NUMBER A T7ACHMENT 11TLE REV/S10N (' EPIP-3.02 00 ( ,, RADIOLOGICAL ASSESSMENT DIRECTOR GUIDELINE A T7ACHMENT 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) Check EPIP-4.01 - INITIATED /'~'T 3. VERIFY ORGANIZATION: U a) Dose Assessnent Team
- Obtain necessary personnel
- 1) Health Physicist
- 2) Health Physics Technicians b) Offsite Monitoring Teams (2) c) Radiation Protection Personnel
- 1) Inplant Monitoring Team
- 2) Saeple Analysis Team
- 3) Onsite Monitoring Team
- 4. INTERFACE:
a) Coordinate activities with other departments via Emergency Directors b) Obtain required equipment and supplies via Emergency Admini-("~'s strative Director
.)
. - - .- - - .. . - - _ _ - - - , _ - - _ . . . ~ . -- - - . - , . ..
No,9188 7220
. NUMBER A TTACHMENT TITLE REVISION l EPIP-3.02 00 L RADIOLOGICAL ASSESSMENT DIRECTOR GUIDELINE i'
A TTACHMENT PAGE 7 2 of 4 i I STEP '* ACTION / EXPECTED RESPONSE
- RESPONSE NOT OBTAINED
! 5. DIRECTION: 1 i a) Direct activities of the following:
- 1) Radiation Protection i Supervisor i
- 2) Dose Assessment Team l
- 3) Evacuation Monitoring Team b) Until EOF manned direct
- following:
i
- 1) Offsite Mc-itoring Teams c) When EOF manned, direct Dose Assessment Team Leader to
! establish liaison with EOF Radiological Assessment Coordinator
- 6. CHECK RELEASES:
a) Obtain status of releases from process monitors where possible b) Evaluate offsite dose assess-ment information l 7. SUPPORT:
'a) Provide radiological advice to Station Emergency Manager ! b) Evaluate emergency exposure , criteria i
i gg c) Provide timely updates on (,;/ radiological conditions l l
i- , No.91ss1220 s NUMBER A TTACHMENT TITLE REVISION
} EPIP-3.02 00 RADIOLOGICAL ASSESSMENT DIRECTOR GUIDELINE A TTACHMENT PAGE
-7 3 of 4 STEP
- ACTION / EXPECTED RESPONSE
- RESPONSE NOT OBTAINED j 8. PROTECTIVE MEASURES:
I 4 a) Evaluate radiological condi-tions and make recommendations for onsite and offsite protec-1 tive actions to Station Emergency Manager i 9. DAMAGE CONTROL: . a) Provide radiological pro-i tection for damage control activities i 10. PROCEDURES: a) Assist in the development j of any temporary procedures required for conducting emergency actions , 11. . RELIEF:
- a) Assure suitable arrangements i for relief of
- 1) Dose Assessment Teams i
l
- 2) Onsite Monitoring Team l
l 3) Offsite Monitoring Teams (2) i l 4) Radiation Protection l Personnel 1
- 5) Position of Radiological Assessment Director
/O
(_ / .
+&y w -+-w -c- m--, ,- -- .+r - - .-- -,-,,-----+m, ,- ,we-w-e s-+-es_- w -- v--y.-- - , - - - -,p, -
+
. _ . - - - _ ._ - _ . . . . ~ . . . ~ . _
No.97887220 (" t NUMBER EPIP-3.02 A TTACHMENT TITLE REVISION 00 RADIOLOGICAL ASSESSMENT DIRECTOR GUIDELINE A TTACHMENT PAGE 7 4 of 4 a j STEP
- ACTION / EXPECTED RESPONSE
- RESPONSE NOT OBTAINED
; 12. TERMINATE ATTACHMENT 7:
a) Verify TSC DEACTIVATED a) Return to previous steps
- of this Attachment 7 for reference.
OR, Personnel - RELIEVED b) Close out i
- 1) Completed By:
Date: Time: c) Affix this Attachment 7 to EPIP-3.02 I 4
.wy -
.m--
._~-..c.... .__ ._ .-
No. 91881220
% NUMBER A TTACHMENT TITLE - REVISION EPIP-3.02 00 EMERGENCY COMMUNICATOR GUIDELINE A TTACHMENT ' PA GE 8 1 of 2 l
. STEP
- ACTION / EXPECTED RESPONSE
- RESPONSE NOT OBTAINED 4
- 1. INITIATE EPIP-3.02, ATTACRMENT 8:
[! a) BY: DATE: t , TIME: NOTE: Emergency Communicator position moves with that of the Station Emergency Manager. I
- 2. VERIFY EOF:
i a) EOF - NOT ACTIVITATED a) IF, ACTIVATED, transmit
- messages from TSC/ Control 4 Room to EOF.
! AND i GO TO Step 4 of Attachment 8. NOTE: Updates to state and local governments should be made at approximately 30 minute 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, 7- g Notification of State and t J Local Governments V l w m,
-pvs,a-- , - e. m o -- - oen e-m-- --e. e n,---, y- -
No,97887220 NUMBER A TTACHMENT TITLE REvlSION [8i EPIP-3.02 00 EMERGENCY COMMUNICATOR GUIDELINE A TTACHMENT PAGE 8 2 of 2 STEP
- ACTION / EXPECTED RESPONSE
- RESPONSE NOT OBTAINED
- 4. NRC NOTIFICATION:
a) Under direction of the Station Emergency Manager, transcit messages IAk' EPIP-2.02, Notification of NRC
- 5. STATUS BOARDS:
a) IF EOF manned, maintain Energency Status Board AND the Radio-
-~ logical Status Board J \~ / b) Update Status Boards as data changes
- 6. TERMINATE ATTACHMENT 8:
a) Verify TSC - DEACTIVATED a) As required, GO TO Step 2 of Attachment 8. QR Personnel - RELIEVED b) Close at
- 1) Completed By:
Date: Time: i c) Affix this Attachment 8 to EPIP-3.02 (~'8 e j' N END
. - - . . - . . . - . __ ~ . _. .-. .. . ~ . . . .
i No. 9 74 8722C l NUMBER A TTACHMENT TITLE REVISION j ^
, EPIP-3.02 00
! EMERGENCY PROCEDURE COOPSINATOR GUIDELINE , A TTACHMENT PAGE r 9 1 of 2 i i i STEP
- ACTION / EXPECTED RESPCNSE RESPCNSE NOT OBTAINED 1
- 1. INITIATE EPIP-3.02, ATTACHMENT 9:
a) BY: 4 DATE: j TIKE:
- 2. CONTROLLING PROCEDUPIS:
.i a) Assist Station Emergency i Manager controlling procedures b) Assure appropriate pro-cedures are initiated as required c) Track and hold completed l procedures until TSC 4 deactivation i d) Verify Q.A. review of procedures
- 3. LOGISTICSt
.a) Verify sufficient EPIPs and attachments available b) Procure additional material via Emergency Administrative Director a
- 4. TERMINATION OF ATTACHMENT 9:
j a) Assist the Station Emergency Manager in collection of all
. procedures used during the emergency
. _ _ _ . . . . . _ _ . _ . _ _ _ _ _ _m ... _ _ _ _ . . _ , _ _ _ . - . .. _ . - . . . . - - , _ _ _ . ._
i No. 97887220 , NUMBER A TTACHMENT TITLE REVISION EPIP-3.02 00
] E.v2RGENCY PEOCEDUPI COCPDINATOR GUIDELINE l A TTACHWENT PAGE 9 2 of 2 l
STEP
- ACTION / EXPECTED PISPONSE RESPONSE NOT CBTAINED i
j
- 4. (CCNTINUED)
, b) Verify appropriate signatures ! on procedure and attachments c) Verify procedures properly completed d) Verify TSC - DEACTIVATED d) Return to previous steps. of this Attachment 9 for O_R
-reference, i
Personnel - RELIEVED 1 e) Close-Out
- 1) Completed By:
Date: Time: f) Affix this Attachment 9 to EPIP-3.02 s END _ _ _ . _ . . ~ _ ..- _ _ _ _ _ _ - . . _ . , , . _ , _ _ . _ _ _ _ _ . . _, _ _ _ _ _ , _ _ ,
us.neenso REVISION
,Q NUMBER A TTACHMENT TITLE EPIP-3.02 00 ATTACHMENT TSC SETUP PLAN PAGE 1
10 1 0F 1 HP ENGINEERING O h7C 1 A m
. T
.A TABLE B L
E STATUS BOARDS l
/
i PIANT STAT TYPE. 1 0
.c.97as7sse VIRGINI A ELECTRIC AND POWER COMPANY SURRY POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE fm\
V NUAfBER PROCEDURE TITLE REVISION
-00 EPIP-3.03 ACTIVATION OF OPERATIONAL SUPPORT CENTER FACE (With 1 Attachment) 1 of 4 PURPOSE
- 1. To_ provide guidance to personnel charged with activation of the OSC.
l USER Operational Support / :nter Director ENTRY CONDITIONS C\
- 1. Declaration of an Alert, Site Emergency or General Emergency; AND
- 2. Entry from other EPIPs; pR
- 3. Direction of the Station Emergency Manager.
i REVISION RECORO REV. 00 PAGE(S): Entire Procedure DATE:JUL 2 9 1982 REV. PAGE(S): DATE: 1 REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: i REV. PAGE(S): DATE: REV. PAGE(S): DATE: APPROVAL REC 0AfAfENDED A 0 PROVED DA TE f[. CHAIRATAN STA TION NUCLEAR SAFETY AND GPERA TING COAfA!!TTEE JUL 2 91382
; No. e7ss 72:e
' NUMBER PROCEDURE TITLE REVISION
/
00 k-) u EPIP-3.03 ACTIVATION OT OPERATIONAL SUPPORT CENTER AA GE 2 of 4
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 1. INITIATE EPIP-3.03:
a) BY: DATE: TIME:
- 2. LOCATION:
a) Verify SPS 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 CSC location to Station Emergency Manager
- 4. ACCOUNTABILITY:
i I a) Maintain a listing of i personnel as they report to the OSC l b) Enter names of personnel in appropriate space on EPIP-3.03, Attachment 1 , c) Report names of OSC l personnel to Security for accountability i
- 5. EMERGENCY K1T:
a) Verify emergency kit in a) IJ[ NOT, dispatch personnel OSC to Station Control Room to s obtain White Emergency Kit for delivery to OSC.
. - ... . - - ~ ~ - _ - . - ~ - . . .-- -.
No. 978 87218 NUMBER PROCEDURE TITLE REVISION ' 00 ( EPIP-3.03 ACTIVATION OF OPERATIONAL PAGE l SUPPORT CENTER 3 of 4 i
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 6. NOTIFICATION:
a) Notify the Station Emergency Manager of OSC activation and relay the following: i
~ 1) Number of personnel in each classification
- 2) Supervisors / Foremen present
- 7. PERSONNEL:
1 I a) Assure personnel check in i 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
- 8. DISPATCHING:
a) Dispatch personnel as re-quired by Station Emergency Manager or his designees
- 9. STATUS:
a) Verify emergency status in a) IJ[ emergency NOT in effect effect GO TO Step 10. 4 b) GO TO Step 7 O . t
-- ,, ---- - - - - , - , , - ,- g a , ,wg - .--..n.. .-- - . . - - -- --
----me--- - - -
I No.s7ss72:e NUMBER PROCEDURE TITLE REVISION m 1 . 00
, EPIP-3.03 ACTIVATION OF OPERATIONAL PAGE SUPPORT. CENTER 4 of.4
' - STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 10. TERMINATE EPIP-3.03:
a) On direction of Station Manager deactivate the OSC b) Direct personnel in OSC to return to normal station organization c) Close-Out i
- 1) COMPLETED BY:
DATE:
. TIME:
d) Forward EPIP-3.03 with all attachments to SNSOC for review 4 1 1 1 END O)
No.97837220 rem /0N E P- 3 . 0.,
' 00 ACTIVATION OF OPERATIONAL SUPPORT CENTER f A TTACH4fENT PAGE g OSC PERSONNEL LIST 1 og 2 i
ELECTRICAL MECilANICAL i 1. I h 2. s 1 3. 4. i S. 6. I 7. 8. 9. 4 10. I 11. i 12, 4 13. 14. 4 l 15. 16. + t 1 i V
No. 978872.to I
' NUMBER REVISION A TTACHMENT TITLE EPIP-3.02 00 ACTIVATION OF OPERATIONAL SL'PPORT CENTER A TTACHMENT PAGE 1 OSC PERSONNEL LIST 2 of 2 1
9 , IST AID TEAM FIRE BRIGADE INSTRUMENT 4
, 1.
1 4 2. 3. 4.
- 5. ,
I 6.
., 7.
8. 9. 10. 3 OTHERS t I 't l p i
N:.97se7230 VIRGINI A ELECTRIC AND POWER COMPANY SURRY POWER STATION
,g EMERGENCY PLAN IMPLEMENTING PROCEDURE hum 9ER PROCEDURE TITLE REVISION 00 EPIP-3.04 ACTIVATION OF D!ERGENCY OPERATIONS FACILITY PAGE (With No Attachments) 1 of 3 4
PURPOSE
- 1. To provide guidance to personnel performing initial activation of EOF.
- USER One (1) Security Team member ENTRY CON 0lTIONS
- 1. Declaration of an Alert, Site Emergency or General Emergency; AND
- 2. Direction of the Station Emergercy Manager through the on-duty Security Shift Supervisor.
1 I REVISION RECORD REV. 00 PAGE(S): Entire Procedure DATEdUl2 S 1992 REV. PAGE(S): DATE: REV. PAGE(S): DATE: i REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: i REV. PAGE(S): DATE: l APPROVAL RECOMMENDED APPROVED DA TE
/ % JUL 2 91982 CHAIRMA?iSTA TION NUCLEAR SAFETY AND OPERA TING COMMITTEE l
. ~ . ....-.. - .- . _ , . . - . _ . _. , . . . . . . . . _ _ .
d No.9788721C NUMBER PROCEDURE TITLE REVISION (\ s#,m) 00 EPIP-3.04 ACTIVATION OF EMERGENCY GPERATICUS FACILITY PAGE 2 of 3 l
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINEO
- 1. INITIATE EPIP-3.04:
a) BY: DATE: TIME:
- 2. ENTRANCE:
a) Obtain door key card to SPS simulator building from Security Shift
. Supervisor
- 3. MATERIALS:
a) Obtain key to Coordinator Emergency Planning office from Security Shift Super-
- visor I
l b) Locate EOF " Materials Kit" in Coordinator Emergency Planning office closet
- 1) Easels (3)
- 2) Status Boards (3)
- 3) Boxes marked EOF 4 c) Deliver materials to simulator room in Simulator Building
., 4. SECURITY: a) Maintain physical control of EOF and Simulator Build-ing until relieved by Vepco Corporate Security personnel O i i
-, _ ,,,..% .. . ,_:,_.,..r _ , . . , , ,.m. -.. , , _ . . _ , , . - , - - , _ . , . _ . , -
he.97887210 E NUMBER PROCEOURE TITLE REVISION f CD EPIP-3.04 ACTIVATIO!1 OF EMERGE! ICY OPEFATIO:iS FACILITY PAGE 3 of 3
- STEh .~ ACTION / EXPECTED RESPONSE RESPONSE NOT CBTAINED 3 5. TEFJ4INATE EPIP-3.04:
i j a) Verify Corporate Security personnel have assumed the l watch
- b) Close out
- 1) COMPLETED BY:
DATE: TIME: ! c) Forward this procedure to-SNSOC for review i i i f i I END 1 f l
w msnu VIRGIN! A ELECTRIC AND POWER COMPANY SURRY POWER STATION EMERGENCY PLAN IMOLEMENTING PROCEDURE I ) touMBER PROCECURE TITLE REVISION 00 EPIP-5.01 TRANSPORTATION OF CONTAMINATED I!UURED PERSONNEL PAGE (With No Attachments) 1 of 4 lURPOSE To provide actions to be taken when contaminated injured person (s) require transport to an offsite medicci facility. USER Shift Supervisor or Station Emergency Manager. ENTRY CONDITIONS [,m Any one of the following conditions exist:
\_
- l. Activation by another EPIP; pR
- 2. Contaminated injured person (s) requiring of f site medical treatment; OR
- 3. Any titie deemed necessary by Shift Supervisor or Station Emergency Manager.
l l l REVIS105 RECORD ( REV. 00 PAGE(S): Entire Procedure DATEdVL 2 91932 REV. PAGE(S): DATE: l REV. VAGE(S): DATE: l REV. PAGt(s): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: AFPROVAL RECOMAtENCEO APPROVE 0 OA TE
\v ' \ / ':
- 5MA 1
l 'h ' l Cg!RAtAN STA TION NUCLEAR SAFETY JUL 2 91982 AND OPERA TING CD', tat / TTEE l s l l l
- . _- = ,
no.s7as m o NUMBER PROCED J ;E TITLE REVISION O 00 Q) EPIP-5.01 TRANSPORTATION OF l0NTAMININATED INJURED PE:tSONNEL FACE 2 of 4 1
- STEP ACTION / EXPECTED RESPONSE R(SPONSE NOTOBTAINED
- 1. = INITIATE EPIP-5.01: .
a) BY: i DATE: TIME: # 4 ca 2. VERIFY PERSONNEL CONTAMINATED ' INJURED: a) Assure HP-3.1.7.1, Personnel _ a) Direct Health, Physics'to Injury-ACTIVATED initiate HP-3'l.7.1. . .
- Personnel Injury, then GO TO Step 3.
O. .o
- 3. VERIFY AMBULANCE: , ,e <
a) Insure First-Aid Team ~$)Verifyoffsiterescue '
~;
Member obtains ambulance personnel notif.ied if - key from Security onsite ambulance'NOT availa_ie ,
.i
+
b) Insure ambulance is brought . ( , to required location ,
- 4. INITIATE EPIP-4.20, H.P.
Actions For Transport of ,' ; j Contaninated Injured Per- , I s onnel -- .._ ? i ( NOTE: Do not notify Medical, College of Virginia (MCV), of l contaminated injured personnel being transtgreed 6' until ambulance has left the site.
- 5. INITIATE MCV-VEPCO RADIA- /
l l. O TION EMERGENCY PLAN: j u. s _ s' "
' ~'
f , - q f
, ' e-4 l
L.. "
No. 57 8 67210 NUMBER PROCEDURE TITLE REVISION pg 00 (' ) EPIP-5.01 TRANSPORTATION OF CONTA'11NINATED INJURED PERSONNEL FACE 3 of 4 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 5. (CONTINUED) a) Major radiation emergency- a) H minor radiation emergency-GREATER TRAN 10 victims LESS THAN 10, victims call cali
- AND b) Provide MCV following GO TO Step 5.b.
information e
- 1) Time of accident
- 2) Number of victims
- 3) Severity of injuries (3
(_) 4) Number of neutron irradiated victims
- 5) Estimate of dose receivcd by victims
- 6) Estimated time of arrival at MCV i
- 6. NOTIFICATION:
Initiate EPIP-2.01, Notifi-4 cation of State and Local Governments t
- 7. TERMINATE EPIP-5.01:
a) Close-Out
- 1) COMPLETED BY:
DATE: TIME: _ (% a ,
\
l l , eso. 97847210 i NUMBER PROCEDURE TITLE REVISION 00 ! EPIP-5.01 TPANSPORTATION OF CONTAMININATED l INJURED PERSONNEL FAGE 4 of-4 I
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED i
- 7. (CONTINUED) i i
, b) Forward EPIP-5.01 to SNSOC for review f l f f J d k a J f 4 I END f f v e -m +, m- - - *~e e- emm- w ev-ve-m,,=-----er, m.,e-g--ywe-.- -----,w_--
"5.978t7220 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION e
n i EMERGENCY PLAN IMPLEMENTING PROCEDURE
,]
fiUMafR PROCEDURE TITLE REVISION 00 EPIP-5.02 SEARCli AND RESCUE gjgg (k'ith No Attachments) I of 5 PURPOSE To insure that search and rescue operations are performed. USER Search and Rescue Team. ENTR Y CONDITIONS
/m '
(w, ) Any one of the following conditions exist:
- 1. Activation by another EPIP; 2R j 2. EPIP-5.03, Personnel Accountability has been initiated and all I personnel within the protected area are not accounted for; OR i
l
- 3. Any time deemed necessary by the Station Emergency Manager.
l l l l REVISION RECORD REV. 00 PAGE(S): Entire Procedure DATE3UL 2 0 1932 l REV. PAGE(S): DATE: l REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: A ( \ APPROVAL RECO&tStENCEO APPROVED DA TE LJ i \ CHAIRMAN STA TION NUCLEA R SAFETY dJ' L 2 S 1982 A ?.'O OPERA TING COA 1AtlTTEE
no.ssesnse NUMBER PROCEDURE TITLE REVISION 00 EPIP-5.02 SEARCH AND RESCUE PME 2 of 5
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
~
- 1. INITIATE EPIP-5.02:
a) BY: DATE: TIME: i 2. VERIFY ACCOUNTABILITY COMPLETED: a) Alert, Site or General a) IF Alert, Site or General Emergency has been declared Emergency NOT declared CO TO i Step _2C.
- b) Obtain results of account-ability from Station Emergency Manager c) Determine number of missing personnel-i d) Attempt to identify last known location of missing
( individual (s)
- 3. ASSESS liAZARDS:
a) Determine radiological hazards b) Determine other hazards
- 1) Toxic gases
- 2) High pressure steam
- 3) Structural damage
- 4) Electrical
- 5) Natural events l
No.97867210 NUMBER PROCEDURE TITLE REVISION (en V EPIP-5.02 SEARCH AND RESCUE 00 PAGE 3 of 5
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED i
- 4. OBTAIN THE FOLLOWING EQUIP-MENT PRIOR TO BEGINNING SEARCH AND RESCUE:
a) Appropriate protective clothing b) Appropriate respiratory protection c) Appropriate personal dosimet ry d) Appropriate radiation survey meter e) First aid kit
- 5. ESTABLISH AND MAINTAIN COM-MUNICATIONS WITH STATION EMERGENCY MANAGER
- 6. LOCATE MISSING PERSONNEL:
a) Preplan routes b) Perform Search and Rescue actions l I l CAUTION: Exercise care not to aggravate any injury. Radiological conditions are considered secondary to immediate medical treatment of severe injury unless acute radiation hazard for casualty exceeds injury hazard. I l l l L.
No.97887210 NUMBER PROCEDURE TITLE REV/SION O 00
\~ 2 EPIP-5.02 SEARCP. AND RESCUE PAGE 4 of 5
- STEP ACTIOh!EXPECTEC RESPONSE RESPONSE NOTOBTAINED
- 8. ADMINISTER FIRST AID:
a) IJ[ required, administer First Aid IAW normal First Aid practice
- 1) Insure breathing
- 2) Insure stoppage of exces-sive bleeding
- 3) Request First Aid Team
- 9. REMOVE INJURED PERSONNEL TO SAFE AREA:
- 10. REPORT TO STATION EMERGENCY MANAGER:
a) Name of individual (s) b) Badge number of indivi-dual (s) c) TLD number of individual (s) d) Location individual (s) e) Condition of individual (s)
- 11. VERIFY ALL PERSONNEL ACCOUNTED FOR:
a) Contact Station Emergency Manager b) All personnel accounted for b) GO TO Step 2.c i o 1 i
No. 97887210 NUMBER PROCEDURE TITLE REVISION . 00 EPIP-5.02 SEARCH AND RESCUE FACE
] 5 of 5 ~
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 12. TERMINATE EPIP-5.02:
a) Close-Out
- 1) COMPLETED BY:
DATE: TIME: 3 o i I l l f END i I i I L -- - - - - . . _ _ _ _ ,_ .
' ' ~ ~ ~ ~ ~ ' ' * - . _ _ _ , _ _ . _ _ _ _ . _ _ , _
, _ . . .s . . . , _ . . - _ _ _.
P.% 97887230 l VIRGINIA ELECTRIC AND POWER COMPANY l SURRY POWER STATION
- EMERGENCY PLAN IMPLEMENTING PROCEDURE O NUMBER PROCEDURE TITLE REVISION
, 00 EPIP-5.03 PERSCNNEL ACCOUNTABILITY PAGE r
- -(With 1 Attachment) 1.'of - 7
~
i PURPOSE
- 1. To determine the personnel who are inside the protected area and.
unaccounted for within 30 minutes following declaration of Site Emergency, or General Emergency. 1 { 2. To provide a' periodically updated list of all personnel inside the protected area. USER Security Team Leader. k ENTRY CONulTIONS i Any one of the following:
- 1. Activation by another EPIP; OR i
. 2. Declaration of a Site Emergency, or General Emergency; I 9.R, i 3. Any time deemed necessary by the Station Emergency Manager. 1 i J l
- REVISION RECORD
! REV. 00 PAGE (S) : Entire Procedure DATE: { REV. PAGE(S): DATE:
; REV. PAGE (S) : DATE:
l REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: l REV. PAGE (S) : DATE: APPROVAL RECOMMENCEO APPROVEO DA TE CHAIRS.*AN STA TION NUCLEAR SAFETY } AND OPERA TING COMMITTEE a
-. . . . , - , ~ . , , - - - . _ _ . - - , - . . , - . _ - . . - - _ . - -. _ - . _ - . - - . . - - - - - _ . - _ , _- - - . _ . .
No.97887210 NUMBER PROCEDURE TITLE REVISION
) 00 EPIP-5.03 PERSONNEL ACCOUNTABILITY PA GE 2 of 7
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 1. INITIATE EPIP-5.03:
a) INITIATED BY: TIME: - DATE:
- 2. VERIFY EVACUATION STATUS:
; a) Evacuation - NOT ORDERED a) H evacuation ordered, GO TO Step H.
1 NOTE: Each Emergency Assembly Area will have an Emergency Assembly Area Leader. This person will be a supervisor or other N cognizant person normally working in the Emergency Assembly Area. , Each Emergency Assembly Area Leader will immediately take !. steps to determine who is missing from their Emergency Assembly Area that should be there, and who is present that should not be there. I Each Emergency Assembly Area Leader will record the above information and forward it to Security.
- 3. INITIATE ACCOUNTABILITY WITHOUT I EVACUATION:
a) Make announcement on station Gai-Tronics system as follows: 1 i
- 1) " Emergency Assembly Aren Leaders - TAKE ACCOUNT-ABILITY"
- 2) " Emergency Assembly Area l Leaders call extension (s)
- (give numbers) and report
! O results of accountability"
No. 9786 7210 NUMBER PROCEDURE TITLE REVISION EPIP-5.03 PERSONNEL ACCOUNTABILIn* PAGE 3 of 7
- STEP ACTION / EXPECTED RESPONSE RESPONSENOT OBTAINED
- 3. (CONTINUED)'
b) Repeat Step 3.a. THEN con-tinue with this instruction
- 4. CALL MPP:
a) Use station PBX -
- b) Instruct them to' perform.
accountability c) Instruct them to report results to extension (give number)
- 5. CALL TRAINING CENTER:
a) Use station PBY b) Instruct them to perform accountability c) Instruct them to report results to extension (give number)
- 6. RECORD RESULTS:
a) As accountability results arrive, record on Attach-ment 1, Personnel Account-ability Form
- 7. BALANCE RESULTS:
a) Balance Column 1 against
. Column 2
- 1) Strike names appearing in both columns.
't
No.97887230 NUMBER PROCEDURE TITLE REVISION O
' --- EPIP-5.03 PERSONNEL ACCOUNTABILITY PAGE 4 of 7
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED l
- 8. PERFORM COMPUTER SEARCH:
a) Check names remaining in a) IF, computer is inoperable, Column 1.that have not perform manual search on been marked through to badge rack of the names determine if they are remaining in Column 1 to within the Protected Area determine if they are with-in the Protected Area. Also check visitor log and visitor rack.
- 9. FORWARD LIST:
a) Forward list of personnel a) IJ[ TSC NOT canned, forward indicated missing within results to Station Emerg-r ps the Protected Area to the ency Manager in Control Emergency Administrative Room, (s- ') Director in the TSC b) C0 TO Step 16,
- 10. INITIATE ACCOUNTABILITY WITH EVACUATION:
a) As personnel evacuate collect security badges b) Remind evacuating personnel to keep pocket dosimeters and TLD's c) Concurrent with evacuation process security badges AND Return to appropriate rack positions i
- 11. INPLANT NOTIFICATION:
a) Make announcement an station Gai-Tronics system as follows:
No. 97687210 i NUMBER PROCEDURE ilTLE REVISJON ^ O 00
-- EPIP-5.03 PERSONNEL ACCOUNTABILITY PA GE -
'5 of 7 1
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAlflE0
- 11. (CONTINUED)
- 1) " Emergency response center leaders perform account-ability"
- 2) " Emergency response center leaders call-extension (give number)-
and report results of accountability" b) Repeat Step ll.a. THEN continue with this instruction
- 12. RECORD RESULTS:
a) Record names as account-ability results arrive
- 13. PERFORM COMPUTER SEARCH:
f a) Verify badges processed a) IF,NOT, process badges. < b) Obtain names of all b) IF, computer is. inoperable, personnel within the perform manual search on Protected Area from badge racks to obtain computer names of all personnel within the Protected Area.
- 14. BALANCE THE LIST:
a) Check the names from Step M with computer list and highlight names of all personnel missing within the Protected Area
ho.978672:0 NUMBER PROCEDURE TITLE REVISION 4 (g . 00
\w- EPIP-5.03 PERSONNEL ACCOUNTABILITY PAGE j 6 of 7
- STtP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 15. FORWARD LIST:
i a) Forward list'of all a) ))[ TSC NOT manned, forward . personnel within the lists to Station Emergency Protected Area to Manager in Control Room. 1 Emergency Administrative Director in TSC b) Forward list of all personnel within the Protected Area indicated missing to Emergency Administrative Director in TSC
- 16. RUN COMPUTER LISTINGS:
[ a) Produce a list of all a) IF computer is inoperable,
\-- personnel with the perform manual logging of Protected Area all personnel 0, R, As directed by Emergency ; Administrative Director
- 17. VERIFY EMERGENCY STATUS:
a) Emergency - NOT terminated a) ))[ terminated, GO TO Step
~~~18.
I b) GO TO Step 16,
- 18. TERMINATE EPIP-5.03:
I a) Close-Out
- 1) COMPLETED BY:
TIME: DATE: t
. - - - . .. - . - - - . .. - - -. .-~ = . - - ,
J No. 97487210 NUMBER PROCEDURE TITLE REVISION 00 i EPIP-5.03 PERSONNEL ACCOUNTABILITY PAGE ! 7 of 7 i STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED l 18. (CONTINUED) b) Forward EPIP-5.03 with all attachments to SNSOC for ? review 4 i END 1 2
- - - . . . . - e-,--.,---,,- - -
,,--.n.n-.,-, - . . - - - , , , - , - . , _ , - . - - , , , - ---,,,w -
- . -,.~,. . ----
f40.97847220
,m NUMBER A TTACHMENT TITLE REVISION l ) 00 EPIP-5.03 PERSONNEL ACCOUNTABILITY A TTACHMENT PAGE 1 1 of 3 Column 1 - those missing Column 2 - those present ASSEMBLY AREA from their assembly area that should not be here (Name) (Name and Badge No.)
ADMINISTRATION BLDG: Station Management Pront Office Admin. Xerox Trailer Procedures Trailer Projects Personnel Westinghouse Start-up Personnel p SECURITY: t Security Dept. Visitors (non-Vepco) CPTS Safety Purchasing Emerg. Planning TRAINING AUDITORIUM: Training Department Students NUS WAREHOUSE: Warehouse Personnel ENVIRONMENTAL LAB: Environmental Dept. Drawing Update Dept. Performance Engrs. STA V) Q.C. Trailers NDT
No. 97887220 .i
/ NUMBER A TTACHMENT TITLE REVISION I 00 EPTP-5.03 PERSONNEL ACCOUNTABILITY A TTACHMENT PA GE 1 2 cf 3 Column 1 - those missing Column 2 - those present ASSEMBLY AREA from their assembly area that should not be here 4
(Name) (Name and Badge No.)' ! SOUTH ANNEX:
- Engineers Q. C. Department Reproductions Station Records Medical Department k'.' B. Count Room i
INSTRUMENT CAL LAB: s Instrument Cal Lab
'-- Personnel CONTROL ROOM:
- Operations Dept.
INSTRUMENT SHOP: Instrument Dept. HEALTH PHYSICS OFFICE: H.P. Department Dose Control i CHEMISTRY LAB: Chemistry Dept. I' OLD ELECTRIC SHOP:
\ Maintenance Services i
-. , . - . - - .- , _ ~
4 No. 315 87220 NUMBER A TTACHMENT TITLE REVISION
\ 00 EPIP-5.03 PERSONNEL ACCOUNTABILITY A TTACHMENT PAGE 1 3 of 3 i
i 1 4 Column 1 - those missing Column'2 - those present
- ASSEMBLY AREA from their assembly area that.should'not be here (Name) (Name and Badge No.)
CONDENSATE POLISHING: Operations Dept. Tool Room i ISt Floor NEW MACHINE SHOP: Mechanical Maintenance Electrical Maintenance Weld Shop i
#1 TURBINE BLDG. BASEMENT:
Non VEPCO Construction i STORER0OM: Storeroom Personnel Fire Marshal and Staff MPP l l i k l I I l . - _ - - . ._. .- .- - _ ._
rio,97887230 l VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCEOURE TITLE REVISION 00 EPIP-5.04 ACCESS CONTROL PACE (With 2 Attachments) 1 of 4 , PURPOSE To insure that under emergency conditions only personnel with an emergency response function-have access to the site. i r I USER Security Team Leaders.
~
ENTRY CONDITIONS
- 'N J Any one of the following
- 1. Activation by another EPIP; l
P.R
- 2. Any time deemed necessary by the Station Emergency Manager; REVISION RECORO REV. 00 PAGE(S): Entire Procedure DATE J* UL 2 0 1982 REV. PAGE(S): DATE:
REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: REY. PAGE(S): DATE: { APPROVAL RECOMMENCEO APPROVED DA TE
- d. *
'HAIRMAN STA TION NUCLEAR SAFETY JUL 2 S 1NE AND OPERA TING COMMITTEE 1 _ . -. ._ - . - - . .-.
too. 9788 7210 NUMBER PROCEDURE TITLE REVISION
~' EPIP-5.04 ACCESS CONTROL PAGE 2 of 4
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 1. INITIATE EPIP-5.04:
a) INITIATED BY: TIME: DATE:
- 2. VERIFY EVACUATION STATUS:
i a) Evacuation - ORDERED a) IF Evacuation NOT ordered, GO TO Step 5.
- 3. MAN MOTORIZED GATES:
a) Open motorized gate 1 and
\ gate 3 if required b) Collect security badges as personnel evacuate c) Remind evacuating person-nel to keep their pocket dosimeters and TLDs
- 4. CONTROL TRAFFIC:
a) Dispatch Security personnel control b) Dispatch Security person- b) Dispatch Security personnel nel to intersection of to Entrance to Hog Island Rt. 650 and Rt. 617 with gate with EPIP-5.04, Attach-EPIP-5.04, Attachment 1, ment 2. Security Duties at Security Duties at Roadblock Alternate Remote Assembly Area (Hog Island). c) Request Surry County Sheriff set-up roadblock O
No.97867210 NUMBER PROCEDURE TITLE REVISION 00 G. EPIP-5.04 ACCESS CONTROL
\) PAGE 3 of 4 STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 4. (CONTINUED)
- 1) Station PBX - 1) Use Security radio link 9E NOTE: No Security personnel are to evacuate the site unless directed by the Station Emergency Manager, except security confidential clerk and security administrative assistant.
O 5. NOTIFY VISITORS: a) Notify visttors site is. a) IF, visitors have an closed and they must leave emergency response function have Station Emergency Manager authorize them.
- 6. EXPEDITE MOVEMENT OF EMERGENCY VEHICLES AND PERSONNEL:
a) Quickly move emergency _ response vehicles and personnel to the area where emergency exists b) Assist H.P. personnel in distribution of dosimetry to emergency response visitors - c) Allow H.P. monitoring personnel quick access to offsite and onsite areas O l I
- - -n . . _ . - -
4 N o, 97887210
, NUMBER PROCEDURE TITLE REVISION i
fi V EPIP-5.04 ACCESS CONTRCL 00 PAGE
! 4 of 4
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 7. VERIFY EMERGENCY:
- a) Alert, Site Emergency or a) IF,NOT, GO TO Step 8_,
General Emergency - EXISTS AND b) GO TO Step 2 of this procedure Avait instructions.from Station Emergency Manager
- 8. TERMINATE EPIP-5.04:
- a) Close-Out
- 1) COMPLETED BY:
DATE: TIME: i b) Forward EPIP-5.04, with all attachments to SNSOC for review i, t l END O f
No. 97887320 p NUMBER EPIP-5.0; A TTACHMENT TITLE REVISION ( 00 SECURITY DUTIES AT ROADBLOCK A TTACHMENT . PA GE 1 1 of.2
- 1. VERIFY ROADBLOCK REQUESTED:
~
a) Check with Security Shift a) If required, check with Supervisor to see if road- Station Emergency Manager. block was requested from LLEA at intersection of Rt. 650 and Rt. 617
- 2. PROCEED TO ROADBLOCK:
a) Proceed to intersection of Rt. 650 and Rt. 617
- 3. AID IN CONTROLLING TRAFFIC:
a) Assist LLEA in controlling j road block - I b) Release evacuees after H.P. monitors and-clears them. i c) Keep intersection and Rt. 650 passable for emergency response personnel 4 4. IDENTIFY EMERGENCY RESPONSE PERSONNEL: i a) By personal recognition b) By VEPCO identification c) State identification d) NRC identification i i e) Fire or rescue affiliation i i yw --
, . - - - - -,,,,,,,-,,,,,a -
, -- ,e ---
---,-m-s,,-- , , , - - w-- - ,--
No. 918S7 tC NUMBER A TTACHMENT TITLE REVISION O' EPIP-5.04 SECURITY DUTIES AT ROADBLOCK 00 A TTACHMENT PA GE 1 2 of 2 NOTE: Access to the station is to be limited.to those individuals responding in accordance with the Emergency Plan i.e., Surry Power Station employees, Vepco corporate personnel, local fire or rescue units and personnel, URC employees and State employees.
- 5. DETAIN PERSONNEL WITH NO IDENTIFICATION:
a) IF, doubt exists pertaining to identity and response purpose of an individual:
- 1) Do not allow passage through roadblock
- 2) Seek authorization i to proceed from the Station Emergency Manager in the TSC or Control Room
- 6. TERMINATE ATTACle!ENT 1:
a) Close Out
- 1) COMPLETED BY:
l DATE: TIME: b) Affix this Attachment 1 to EPIP-5.04 l i END
- O I
l
. . . - . . - - - . - , . . . - . . - . _ - . - - . - . . - - _ - - . - - . ~ .---
No. 97887220 REVISION
~
NUMBER A TTACHMENT TITLE EPIP-5.02 00 SECURITY DUTIES AT ALTERNATE A TTACHMENT RDIOTE ASSEMBLY AREA (HOG ISLAND) PAGE 2 1 of 2
- 1. VERIFY EVACUATION ORDERED TO H0G ISLAND:
a) Verify with Security Shift a) IF required, check with Supervisor Station Emergency Manager
- 2. ENTRANCE TO HOG ISLAND GATE:
a) Obtain keys to Hog Island gate from. Security Shift Supervisor b) Take bolt cutters in the event keys do not work
- 3. DIRECT TRAFFIC TO H0G ISLAND:
a) Direct traffic from station site AND b) Construction site
- 4. EVACUATION TO HOG ISLAND:
a) Insure orderly evacuation to Hog Island by the j following:
- 1) Evacuees continue to end of road l 2) Evacuees do not block l the road i
- 3) Evacuees remain in vehicles for further instruction O
No. 97887220 NUMBER A TTACHMENT TITL E . REVISION EPIP-5.04 00 O- SECURITY DUTIES AT ALTERNATE i A TTACHMENT REMOTE ASSDiBLY AREA (HOG ISLAND) PAGE 2 2 of 2 i
- 5. DETAIN EVACUEES:
a) For Health Physics Monitoring b) For further instructions from l' Security Shift Supervisor / Station Emergency Manager
- 6. TERMINATE ATTACHMENT 2:
a) Close Out . 1) COMPLETED BY: DATE: TIME: b) Affix this Attachment 2 to EPIP-5.04 i i f, 4 END
! D) s %s i
i 1 1
-._. - ,- , _ _ ..__... ._ ....~- -, _ _ . ___ _ - ,,_ ... _ .._ ___...- _ .___.--.-._- _ _ -,. .- ,,.-... ..,.._...=___ ..-__. _
, No.97487230 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION
% EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCEDURE TITif REVISION 00
< EPIP-5.05 SITE EVACUATION PACE
- (With No Attachments) 1 of 5' PURPOSE
. Insure steps are.taken to provide for a quick and orderly cvacuation. l l USER Station Emergency Manager OR Emergency Administrative Director.
. ENTRY CONDITIONS
- 4 Any one of the following conditions exist
- 1. Activation by another EPIP; SE
- 2. Upon determining evacuation is imminent; 0g
- 3. At any time deemed necessary by the Station Emergency Manager.
REVISION RECORO REV 00 PAGE(S): Entire Procedure DATE yL2 9 22 l , REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: APPROVAL RECOMMENDEC AFPROVED DA TE
~/.g/* '/
tand-'HAIRMAN STA TION NUCLEAR SAFETY JUL 2 91982 ANd OPERA TING COMMITTEE -
,, - - r r - -,
No. 978 87210 NUMBER PROCEDURE TITLE REVISION
.+ 00 EPIP-5.05 SITE EVACUATION PAGE 2 of 5
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 1. INITIATE EPIP-5.05:
a) BY: TIME: DATE:
- 2. DETERMINE WIND DIRECTION:
a) E wind from NNW, N, or NNE use alternate remote assembly area (Hog Island) b) II[ wind from any other compass direction, use O primary remote assembly area (Rt. 650 and 617)
- 3. NOTIFY STATION SECURITY:
a) Notify Security Shift a) Use Gai-Tronics. Supervisor by Station PBX - - b) Advise that evacuation is about to be ordered c) Advise which assembly area to be used d) Verify EPIP-5.04, Access Control has been activated
- 4. NOTIFY MPP:
a) Notify MPP Security by Station PBX - . f* b) Inform evacuation ordered
- c) Advise .,hich assembly area is
- s. to be used f
i
<" ,e No. o res tn o _ ,, f f
-.s -
NUMBER PRCCEDURE TITLE REVISION f s. 00 EPIP-5.05 (v) SITE EVA;I@TInN
/ PAGE
> '~ 3 of 5
- STEP -
C' , ACTION / EXPECTED RESPON:E RCSPONSE NOT OBTAINED
/ ~
- 5. CALL TRAINING CENTER:
a) Notify training personnel - , . . , by Station PBX - , - - , b) Inform evacuation ordered c) Advise which assembly area is to be used
- 6. INPLANT NOTIFICATION: ,
a) Verify primary remote assembly a) IF NOT, GO TO Step 1 area to be used (Rt. 650 & 617) (' b ,' Sound Emergency Alann ' ' V) c) Make announcement on station Gai-Tronics as follows: ' ~
- 1) " Personnel NOT responding to emergency evacuate the g station"
- 2) " Turn in security badge, keep pocket dosimeter and TLD" '
- 3) " Proceed to intersection of Routes 650 and 617"
- 4) " Remain in vehicle for l
further instructions" , j d) Repeat Steps 6,THEN, CO TO-i Stepj[
- 7. INPLANT NOTIFICATION:
a) Verify alternate remote assembly area to be used (Hog Island) b) Sound Emergency Alarm { a
- . _ - - - _ . . _ = _. - .~.- .-_-
d
, so'.tsse m o NUMBER PROCEDURE TITLE REVISION 00 6 EPIP-5.05 SITE EVACUATION a PAGE 4 of 5
- STEP ACTION (EXPECTED RESPONSE RESPONSE NOTOBTAlt/E0 1
.i
- 7. (CONTINUED) f~ c) Make announcement on station
. . - Gai-Tronics system as !
I - follows:
- 1) " Personnel NOT responding to emergency evacuate the station"
- 2) " Turn in security badge, keep pocket dosimeters and TLD"
- 3) " Proceed on Rt. 650 to
- Hog Island Wildlife l O Management Area"
[! V _ l 4) " Continue to end of road"
- 5) " Remain in vehicle for further instructions"
, d) Repeat Step 7, THEN continue l with this instruction t I 8. VERIFY EPIP-4.21: I a) -Verify EPIP-4.21 Evacuation
~ Remote Assembly Area Monitoring -
ACTIVATED
- 1) Check with Radiological l Assessment Director
( 9. TERMINATE EPIP-5.05: a) Close-Out
- 1) COMPLETED BY: ,.
1 TIME: DATE: s
-.-..,,wy. ~m_ _ ,. -%--
_- . . - . . -. . . . - _ . . - . . . _ . _ -- - - . . - - . _ . - - . . . ~ _ - ~ . ~ - . . . . _ - - _ . . . , .. t ) No, 978 47210
?
l NUMBER FROCEDURE TITLE REVISION 00 EPIP-5.05 SITE EVACUATION PA GE 5 of 5 i l
- STEP ACTIOWEXPECTED RESPONSE RESPONSE NOT OBTAINED I l > < 9. (CONTINUED) 1 b) Forward EPIP-5.05 to SNSOC '
for review i F t -l
) f
- l t
i r I 1 i i l 1 i i i 6 END I N
. )
..~. - . _ , _ _ _ . - , , . , ~ . _ . . . _ . . . . _ _ _ . . . _ . _ _ . _ _ . _ . . . . . , , _ , _ _ _ _ _ _ _ . _ , . . . . . _ _ , _ _ . , , _ - . , . _ , , . . _ . . _ _ _ . ,
. 978t7230 VIRGINi A ELECTRIC AND PO'.* ER COMPANY SURRY POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE U A us!BER PROCECURE TITLE REVISION 00 EPIP-5.06 EMERGENCY RADIATION EXPOSURE AUTHORIZATION PA CE (k'ith No Attachments) 1 of 6 PURPCSE Provide guidance for authori::stion of emergency radiation exposure.
USER Station Emergency Manager ENTR Y CONDITIONS V Any one of the following conditions exist:
- 1. Activation by another EPIP; pR
- 2. Lifesaving activity during an emergency which may result in exposure in excess of 10CFR20 quarterly limits; pR
- 3. Saving valuable equipment OR_ limiting of fsite releases which may result in exposure in excess of 10CFR20 quarterly limits.
REVISION RECORD REV. 00 PAGE(S): Entire Procedure DATE: EL 28E REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: ! \ AP?ROVAL RECO.s!\ FENDED APPRO VED DA TE
/y/j' &
lh n CHAIR.tfAN STA TION NUCLEA R SA FETY S L U 0 1982 AND OPERA TING cot!.tflTTEE
he.97887218 NUMBER PROCEDURE TITLE REVISION ( ) 00 \s / EPIP-5.06 EMERGENCY RADIATION EXPOSURE AUTl!ORIZATIOS PAGE 2 of 6
- STEP ACTIOWEXPECTED RESPONSE RESPONSE NOT OBTAINED
- 1. INITIATE PROCEDURE:
a) INITIATED BY: DATE: TIME: NOTE: The follocing describes criteria considered for lifesaving and facility protective actions.
- 2. CLASSIFY EMERGENCY EXPOSURE:
( ) a) Lifesaving \s /
- 1) Search and Rescue, First-Aid, and rer. oval of injured, where there is reasonable expectation that an individual is alive within affected area.
- 2) Entry to correct con-ditions which, if left uncorrected, could re-sult in onsite or off-site injury b) Damage control or corrective actions which:
- 1) Save valuabic equipment
- 2) Limit offsite releases
- 3. DETERMINE EXPOSURE:
a) Activate EPIP-4.04, Emer-gency Personnel Radiation ( ) Exposure LI
No. 978 8 7219 i l NUMBER PROCEOURE TITLE REVlSION , 00 EPIP-5.06 EMERGESCY RADIATION EXPOSURE AUTHORIZATION PACE 3 of 6
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINEO 1
- 3. (CONTINUED) i b) Supply Radiological Assess-
, ment Director with information i about location and length of time of exposure l i c) Request Radiological Assess-ment Director evaluate planned exposure 1 4 EXPOSURE LIMITS: a) Lifesaving
- 1) Whole Body 5 Rem
- 2) Thyroid - unlimited b) Damage Control
- 1) Whole Body - 25, Rem
- 2. Thyroid - 125 Rem
- 5. AUTHORIZATION:
a) Review recommendation of Radiological Assessment Director b) Authorize Emergency expo- b) IF emergency exposure is not sure authorized, GO TO Step 10L. c) Complete Attachment 3 of EPIP-4.04, Emer-gency Personnel Rad-iation Exposure, by signing and recording allowable dose
No. 97 0 8 7218 NUMBER PROCEDURE TITLE REVISION ) EPIP-5.06 EMERGENCY RADIATION EXPOSURE AUTHORIZATION 00 PACE 4 of 6 -
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: The following should be considered as guidance in selecting individuals for emergency exposures.
- 6. SELECTION CRITERIA:
a) Personnel should be volunteers or profes-sional rescue personnel (i.e., fire fighters, first aid and rescue personnel) b) Volunteers should be in good physical health c) Volunteers should be broadly familiar with probable consequences of exposure d) Women capable of repro- - duction should not take-part e) Volunteers should be above the age of 45, whenever possible f) Internal exposure should be minimized by use of respiratory protection g) Exposure shall be limited to a once in a lifetime dose NOTE: Emergency Manager may wave need for RWP if situation warrants immediate action. Verbal authorization must be given.
No. 978 E72:0 NUWBER PROCEDURE TITLE . REVIS10N O 00
\-- EPIP-5.06 EMERGENCY RADIATION EXPOSURE AUTHORIZATION .PAGE 5 of 6 i
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED T
1
- 7. INITIATE RWP:
a) Direct Radiological Assess-4 ment Director to complete Radiation Work Permit
- 8. REVIEW EMERGENCY ACTION:
l a) Emergency Manager and i Radiological Assessment Director shall review with individual receiving emergency exposure, the following:
- 1) Possible effects of ex-i posure
- 2) Expected dose rates
- 3) Stay time
- 4) Requirements of RWP
- 9. FOLLOW-UP ASSESSMENT:
a) IF' exposure GREATER THAN 2 25L Rem, arrange for transport to MCV for follow-up assessment
- 10. TERMINATE EPIP-5.06:
a) Close-Out
- 1) COMPLETED BY:
DATE: TIME: O (.
ho.97887219 NUMBER PROCEDURE TITLE REVISION 00 h(/ EPIP-5.06 EMERGENCY FjOIATION EXPOSURE AUTHORIZATION PA GE 6 of 6
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 10. (CONTINUED) b) Forward EPIP-5.06 to SNSOC for review O
I I i l l l END i ) il l
i
*.c,976 8 72 30 -
VIRGINlA ELECTRIC AND POWER COMPANY SURRY POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE i NUMBER PROCEOURE TITLE REVISION ' 00 EPIP-5.07 ADMINISTRATION OF RADI0 PROTECTIVE DRUGS PA CE (With 2 Attachments) 1 of 4 PURPOSE i To administer, with proper authorization..radioprotective drugs. USER Radiological Assessment Director or Senior Health Physics personnel onsite. ENTRY CONDITIONS i Any one of the following conditions exist:
- 1. Activation by another EPIP;
' OR . 2. Survey results indicate inhalation dose may have exceeded.10. Rem;
- 3. Entry into high airborno activity area where inhalation dose may exceed-j 10 Rem.
l REVISION RECORO REV. 00 PAGE(S): Entire Procedure DATEnlUL2 9 E2 REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: i -REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: APPROVAL REC 0tfMENDED APPROVED DA TE
//
AIRMAN STA TION NUCLEAR SAFETY gg g 9 yy AND OPERA TING COMMITTEE
reo.97ss m e NUMBER PROCEDURE TITLE REVISION ( EPIP-5.07 ADMINISTRATION OF RADI0 PROTECTIVE DRUGS PAGE 2 of 4
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 1. INITIATE PROCEDURE:
a) INITIATED BY: DATE: TIME:
- 2. AUTHORIZATION:
a) Review data from EPIP-4.01 with the Station Emergency Manager b) Request approval for use of radioprotective drugs from O Station Emergency Manager
- 3. OBTAIN MEDICAL ADVICE:
a) Contact VEPCO Medical a) Il[ :nedical approval is NOT Director available within 30 minutes administer the KI tablets. office -
- home -
beeper - , CAUTION: Potassium iodide should not be used by people allergic to iodine. i I , ([S) 1
, . . , < - , ., - , .-. . . _ . , - . - , ,. e . , - - - , , , .-.--4 - ,
No.ofes721e ; NUMBER PROCEDURE TITLE REVISION i 00 EPIP-5.07 ADMINISTRATION OF RADI0 PROTECTIVE DRUGS PAGE 3 of 4
- - STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 4. REVIEW USE OF DRUG:
a) Review with affected individual effects of drugs per Attachment 2 NOTE: Administration of radioprotective drugs is perferably done prior to exposure, although administration within 2 hours after exposure is considered acceptable.
- 5. DOSAGE:
4 () a) Review directions for dosage as per Attachment 2 , 6. LOCATION: , i a) A supply of drugs is located in Surry H.P. Office Emergency Kit b) Alternate supply located at North Anna Medical Facility l
- 7. ADMINISTRATION:
a) Complete Attachment 3 b) Issue radioprotective drugs to affected individual i
- 8. . FOLLOW-UP ACTION:
a) Perform follow-up assessment NOT prior to 24 hours after exposure IAW the following: k 1
.~---,,-p. , , , ~
.,~.-q - , -a . , , ,,,n, ., . - - - n, , - . . . .
No. 978 87210 NUMBER PROCEDURE TITLE REVISION 00
\ EPIP-5.07 ADMINISTRATION OF RADI0 PROTECTIVE DRUGS PAGE 1
4 of 4
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 8. (COSTINUED)
- 1) Procedure llP-3.1.1.4, Personnel Dosimetrv-i Bioassy, Whole body Counter Operation T
pR_
- 2) Procedure llP-3.1.1.6, Personnel Dosimetry-i Operation of the ND/ APT Bionssy, Whole Body Counting Chair
- 9. TERMINATE EPIP-5.07:
i a) Close-Out
- 1) COMPLETED BY:
DATE: TIME: b) Forward EPIP-5.07 with all attachments to SNSOC for review I END O o
ho,97tS7220 p NUMBER A TTACHMENT TITLE REVISION ( ) EPIP-5.07 00 V ADMINISTPaTION OF RADI0 PROTECTIVE DRUGS A TTACHMENT PA GE 1 DOSAGE AND SIDE EFFECTS 1 of 1 CAUTION: Potassium Iodide should not be used by people allergic to Icdine. Keep out of reach of children. In case of overdose or allergic reaction, contact a physician or public health authority. DIRECTIONS FOR USE ADULTS : One (1) tablet once a day. Take tablet for not more than 10 days.
%' SIDE EFFECTS Usually, side effects happen when people take higher doses for a long period of time. Do not take more than the recommended dose nor for for longer than the recommended time you are told. Side effects are unlikely due to low doses over n short periods of time.
Possible side ef fects are skin rashes, swelling of salivary glands, and
" iodism" (metallic taste, burning of mouth and throat, sore teeth and gums, symptoms of head cold, and sometimes stomach upset and diarrhea).
A few people have an allergic reaction with more serious symptoms. These could be fever and joint pains, or swelling of parts of the f ace and body and at times, severe shortness of breath requiring immediate medical attention. Taking of iodide may rarely cause overactivity of the thyroid gland, undcractivity of the thyroid gland, or enlargement of the thyroid gland (goiter). k' HAT TO DO IF SIDE EFFECTS OCCUR
- h If side effects are severe or if you have an allergic reaction, stop taking s2 Potassium Iodide and call a doctor.
No. 9 78 8 7220
/8 NUMBER A TTACHA!ENT TITLE REvlSION
( ) EPIP-5.07 00 AD:!INISTRATION OF RADI0 PROTECTIVE DRUCS A TTACHMENT PA GE 2 POTASSIt". IODIDE ISSUE REPORT 1 of 1 TIME OF TIME OF INITIAL NAME SS NUMBER EXPOSURE KI DOSE ISSUED BY ('s,
'NJ
\ l ! V l I i
*c.97887230 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE k'J A UMBER PRCCEDURE TITLE REVISION 00 EPIP-5.0S DAMAGE CONTROL GUIDELINE PA CE (With 2 Attachments) 1 of 11 PURPOSE
- 1) To provide guidance to the Emergency Maintenance Director and Damage Control Team Leader during progress of an emergency.
- 2) To define and evaluate tasks.
USER Emergency Maintenance Director ENTRY CONDITIONS / \ U 1. Declaration of an Alert, Site Emergency or General Emergency; AND
- 2. Entry from other EP1Ps; 9.E
- 3. Direction of the Station Emergency Manager.
REVISION RECORD REV. 00 PAGE(S): Entire Procedure DATE:JUL 2 91332 REV. PAGE(S): DATE: REV. PAGE(S): DATE: REY. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: p APPROVAL RECOMMENDED APPROVED DA TE j/ SA JUL 2 019 2
/* lHAIRMAN STA TION NUCLEAR SA FETY AND OPERA TING COMMITTEE
i No. 978 87210 NUMBER PROCEDURE TITLE REVISION 00 EPIP-5.08 DAMAGE CONTROL GUIDELINE PAGE 2 of 11
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
.1. INITIATE EPIP-5.08: '
a) BY: DATE: TIME:
- 2. ASSESSMENT.AND REPAIR:
l a) With Station Emergency Manager identify and evaluate assessment and repair requirements s b) Verify if any of the b) GO TO Step 3;. following exist: l 1) Damage to equipment or systems
- 2) Loss of electrical j supply i
- 3) Loss of control func-tion
- 4) Loss of indication 1
- 5) Any other condition
- specified by Station Emergency Manager.
c) Determine practicality and c) IJ[ NOT practical or feasible,
- feasibility of assessment GO TO Step 3,.
l or repair efforts i 3. CONTAMINATION CONTROL: l a) With Station Emergency Manager, identify and evaluate contamination control requirements { } n . . . . , - , - - , . - - .. - - . . . . - . - - - . - - . - , .
Pto.97887210 NUMBER PROCE00RE TITLE REVISION
,r y I ) 00
'N_/ EPIP-5.08 D/JIAGE CONTROL GUIDELINE PA GE 3 of 11
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 3. (CONTINUED) b) Verify if any of the b) GO TO Step 4_.
following are required for contamination control
- 1) Isolation of systems or components
- 2) Manual containment isolation
- 3) Isolation of severely contaminated rooms or buildings, including 7- access, piping and
( ) ventilation
'% J
- 4) Radiological clean-up
- 5) Pumping of spills to radwaste system
- 6) Any other condition specified by Station Emergency Manager c) Determine practicality and c) IF NOT practical or feasible, feasibility of contamination GO TO Step 4.
control efforts
- 4. MODIFICATIONS:
a) With Station Emergency Manager, identify and evaluate modification requirements for systems and structures b) Verify if any of the b) GO TO Step 5_. following are required (w C/
No. 97887210 NUMBER PROCEDURE TITLE REVISION 00 05 EPIP-5.08 DAMAGE CONTROL GUIDELINE PAGE 4 of 11
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 4. (CONTINUED)
- 1) Emergency changes to existing systems
- 2) Changes to setpoints or controls
- 3) Alterations to liquid or gaseous flow paths
- 4) Temporary shielding
- 5) Additions or altera-tions to radwaste systems
,,, i e \m,/ 6) Temporary or altered electrical systems
- 7) Any other condition specified by Station Emergency Manager c) Determine practicality and c) IF NOT practical or feasible, feasibility of modifications GO TO Step 5,.
- 5. RADb'ASTE CONSIDERATIONS:
a) Check radwaste conditions i j b) IJ; RCS spill outside con-l tainment, suggest evaluation ! of chemical addition for radiciodide control c) IJ[ required, evaluate con-tingencies for dealing with radwaste exceeding capacity l of plant radwaste system 4 - - - -
No. 97 8 87210 NUMBER PROCEDURE TITLE REVISION 00 O'-. EPIP-5.08 DAMAGE CONTROL GUIDELINE PAGE 5 of 11
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 6. PERSONNEL:
a) Assess availability and expertise of onsite sup-port personnel b) II[ required, request additional station personnel, 0]( offsite
~
personnel via corporate 4 channels
- 7. COORDINATION:
a) Determine need for support c- from other departments
\- I b) Coordinate activities with Emergency Directors in TSC 2
NOTE: More than one corrective action may. be attempted simultaneously. . 8. SET PRIORITY: a) Confer with Station Emer- , gency Manager to determine i priority of actions l ! b) List all feasible tasks in order of priority on EPIP-5.08, Attachment I l l 9. NOTIFICATION OF TEAN LEADERS: t I a) Call OSC and request de- ! sired Damage Control Team
,,. Leaders report to TSC t
i l l l . . , , . - - - . . - _ ,, , _ - . . _ , .__ _ __ - ,_ - _.. . _ _
. -- _ - _ - - . . - . - _ - .. .. . .=. .. .. . - -___.. . - ... . _ . . .
J mo.orsante NUMBER PROCEDURE TITLE REVISION 00 EPIP-5.08 DAMAGE CONTROL GUIDELINE PAGE 6 of 11
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 4
i
- 9. (CONTINUED)
- b) Assign task responsibility
! to Damage Control Team Leaders based on expertise
)' and personnel availability
- 10. VERIFY EQUIPMENT:
a) Identify special tools and equipment required 1
. AND .
! l r Identify sources, procure r s materials and send to OSC l- 11. OFFSITE ASSISTANCE: a) Determine need for offsite assistance
- 1) NSSS Vendor 1
- 2) A & E Vendor
- 3) Corporate l 4) Other organizations identified in Sect 5.3, Augmentation of Onsite Emergency Organization q of SPS Emergency Plan b) Request required assistance from EOF via Emergency Administrative Director
- 12. NON-RADIOLOGICAL HAZARDS:
a) Identify non-radiological haz-ards involved with each task i T a
% y .
_ - - - , - - - . _ _ _. ,,.,%, - ~ - - _ - - _ , , , , -, - - - - - , - m. .--- --- - , ,-- ,c ..-,,w.,.- , -
No. 97 8 47210 NUMBER PROCEDURE TITLE REVISION 7-( l 00
\- ' EPIP-5.08 DAMAGE CONTROL GUIDELINE PACE 7 of 11
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT CBTAINED
- 12. (CONTINUED)
- 1) Toxic gases
- 2) High pressure steam
- 3) Structural damage
- 4) Electrical
- 5) Natural events b) Locate protective clothing and equipment fM
( ) c) Forward material to OSC Ns/
- 13. RADIOLOGICAL HAZARDS:
a) Identify radiological hazards involved with each task b) Via Radiological Assess-ment Director, request a special RWP for each task c) Evaluate requirement for continuous Health Physics coverage and request as required d) Insure availability of protective clothing, equipment dosimetry and survey instrumentation s v l
No,97887230 NUMBER PROCEDURE TITLE REVISION 00 EPIP-5.08 DAMAGE CONTROL CUIDELINE PAGE 8 of 11
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 13. (CONTINUED) e) IF required, request authorization of emergency radiation exposure limits IAW EPIP-5.06, Emergency Radiation Exposure Author-ization
- 14. DETERMINE ROUTES:
a) Using identified hazards, define acceptable ingress and egress routes for each task
/
kh/ s b) Describe routes on Pg. 1, Attachment 2, of EPIP-5.08 c) IF desired, provide maps and affix to EPIP-5.08, Attachment 2 NOTE: During conduct of emergency measures, temporary procedures may be approved by the Station Emergency Manager. SNSOC and QA review should be obtained when appropriate.
- 15. PROCEDURES:
a) Review, modify or write procedures to be used for each task b) Obtain Station Emergency Manager approval
- 16. COMMUNICATIONS:
a) Determine comtunication requirements
No. 978 87210 I i NUMBER PROCEDURE TITLE REV/SION
) EPIP-5.08 DAMAGE CONTROL GUIDELINE 00 PAGE 9 of 11
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
}
- 17. DOCUME!;TATION:
a) For each task, complete a a separate Pg. 1. Attachment 2 of EPIP-5.08 i 18. TEAM LEADER BRIEFING:
) ; a) Forward EPIP-5.08 Attach-ment 2 for each task to designated Damage Control Team Leader (s) for action b) Brief Damage Control Team Leaders as to scope of assigned tasks and i
established priorities c) Direct Damage Control Team Leader (s) to proceed to OSC for assembly and briefing of Damage Control Group (s) 1 19. UPDATE STATION EMERGENCY MANAGER: I f a) IF, applicable, update
- Station Emergency Manger on following
- 1) Assessment results
- 2) Repair actions
- 3) "ontamination control j actions 1
- 4) Modification actions
( b) Verify new tasks have NOT b) GO TO Step 8,for assessment l developed of priority. l
. - - - . ~ . . . . . - -
No,s7ss721e l NUMBER ' PROCEDURE TITLE REVISION O' EPIP-5.08 D/0! AGE CONTROL GUIDELINE 00 PAGE 10 of 11 i 1 e
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED t
i
- 20. VERIFY PROGRESS: -
1 . a) Check with Damage Control a) Insure timely contact with !' Team Leader (s) to assess Damage Control Teat Leader (s) status of tasks b) Update Attachment 1 c) F IF,a significant change or c) GO TO Step 21 difficulty has occurred. . C0 TO Step H IF,all tasks completed. l- GO TO Step H f
- 21. VERIFY TSC:
; a) Check TSC - ACTIVATED a) IF NOT, GO TO Step M.
, b) CO TO Step H [ I
- 22. TED11NATE EPIP-5.08:
a) Instruct Damage Control l Leader (s) to return to normal station organ-ization b) I_F, applicable, confer with Station Manager on restoration actions c) Collect, verify comple-tion of, and affix all copies of EPIP-5.08, Attachment 2 (
No. 978 $7210 NUMBER PROCEDURE TITLE REVISION O EPIP-5.08 DAMAGE CONTROL GUIDELINE 00 PAGE 11 of 11
- STEP -
ACTION /EXPTCTED RESPONSE RESPONSE NOT OSTAINED
- 22. (CONTINUED) d) Close-Out
- 1) COMPLETED BY:
DATE: TIME: e) Forward EPIP-5.08, with all attachments to SNSOC for review l l END O 1
.. -_-.- = .___ _-_ _ . -
P40.97887220 NUMBER A TTACHMENT TITLE REVICION
. EPIP-5.0f 00 EQUIPMENT DAMAGE AND REPAIR LOG A TTACHMENT PAGE 1 1 of 1 i.
SYSTEM, TASKS TASK COMPONENT, TO BE ASSIGNED TO: ACTIONS NUMBER OR STRUCTURE PERFORMED (LEADER) PERFORMED j - i f T emmune h r j l s l i s
~
i 4-
- - . , , . _ , . , _ , _ , , ,y m....-- - , . , ,,,,,...m
No.s7as7220 s- ~ s NUMBER A TTACHMENT TITLE REVISION ( ) EPIP-5.03 00
'V DAMAGE CONTROL TEAM LEADER GUIDELINE A TTACHMEN T PA GE 2 1 of 5 DAMAGE CONTROL TEAM LEADER GUIDE SHEET j 1. Task Number:
- 2. Task
Description:
- 3. Team Leader:
- 4. Group Leader:
- 5. Group Members:
- 6. Special Tools fs
( or Equipment:
\J )
- 7. Protective Gear '
or Dosimetry: 8; Proce2ures:
- 9. Approvals: Emergency Maintenance Director Station Emergency Manager l 10.' Actions Performed:
l l l II. Review QA Representative SNSOC Chairman 1 1 1
/
,,-~\ )
(u_, ) o f
i No.97487220 , l NUMBER A TTACHMENT TITL E REVISION [ i EPIP-5.08 00 CI DAMAGE CONTROL TEA!! LEADER~'CL'. DELI'NE - A TTACHMENT '
- PAGE 2 y 2 of' 5 e
- 1. INITIATE EPIP-5.08, ATTACIDIENT 2: .-
~~
a) BY: 1 DATE: TIME:
/
NOTE: Damage Control Group members are NOT designated. prior to initiation of this procedure. They are selected based on availability and required expertise. I i )
'V 2. PERSONNEL: ,
a) Select Damage Control ', Group members based on task and allowable dosage .'
~
b) Enter information on ' Pg. 1, Attachment 2 , of EPIP-5.08 c) Assemble group members for briefing
- 3. LOGISTICS:
a) Refer to Pg 1 of - this Attachment'E b) Acquire procedures, " drawing, schematics, tools, Rb'Ps as required - for group's task
/ I (v!7. ..
e
to.97887220 j' NUMBER A TTACHMENT TITLE REVISION (x L/ l' EPIP-5.0E 00 DAMAGE CONTROL TEAM LEADER GUIDELINE A TTACHMENT PAGE
. 2 3 of 5
/
_ 3. (CONTINUED) c) Assure all Damage Control Group cembers are properly outfitted with protective gear d) IF, required, assure H.P. coverage
~
- 4. BRIEFING:
a) Brief group members:
- 1) Task objectives
/m (x/ ) 2) Routes on ingress and egress
- 3) Specific assignments
- 5. COMMUNICATION:
a) Establish communications with group using appro-priate means NOTE: Follow appte,ed procedures during progress of task. Any deviations must be approved by the Station Emergency Manager via the Emergency Maintenance Director.
- 6. TFAINING:
a) Based on the task urgency, confer with Emergency Maintenance Director on l dry-run requirement for ALARA considerations f,_ s_- i l*. O
No 97887220 NUMBER A TTACHMENT TITLE REVISION EPIP-5.08 00 i g\d') DAMAGE CONTROL TEAM LEADER GUIDELINE i A TTACHMENT PAGE 2 4 of 5
- 7. ASSESSMENT
a) ))[ required, dispatch group to assess task requirements b) On receipt of assessment results:
- 1) Obtain parts, addi-tional tools or per-sonnel, as required
- 8. REPORT:
a) Report assessment results to Emergency Maintenance
\
Director and confer if significant deviation from expected
- 9. PERFORMANCE OF TASK:
t a) Direct task performance ! b) Maintain communication i c) Evaluate status d) Forward status to Emer- ! gency Maintenance Direc-I tor on significant changes
- 10. EXPOSURE:
l a) Verify exposures of per-l' sonnel performing task l b) ))[ required, request evaluation of emergency radiation exposure limits l by Station Emergency Manager via Emergency Maintenance Director f { I
No. 978 8 7220 m NUMBER EPIP-5.0E A TTACHMENT TITLE REVISION 00 ( )
,/ % DAL\GE CONTROL TEAM LEADER GUIDELINE A TTACHMENT PAGE 2 5 of 5
- 11. TERMINATE EPIP-5.08, ATTACIbiENT 2:
a) Verify task complete a) CO TO Step 9. b) Complete Step 10,on 0 Pg. 1 of this Attachment 2 c) Close out
- 1) COMPLETED BY:
DATE: TIME: A (%/ ) d) Forward this Attachment 2 to Emergency Maintenance Director f ( m,
)
END
-_ ~ _ . . . , .
No. 978 8 72 30 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE t NUMBER PROCEDURE TITLE REVISION 00 EPIP-6.01 RE-ENTRY / RECOVERY GUIDELINE gjgg (With No Attachments) 1 of 6 PURPOSE
- 1. To provide guidance to the Station Emergency Manager and the recovery organization to return the plant to a normal mode.
i USER Station Emergency Manager 4 ENTRY CONDITIONS
- 1. EPIP-1.01 after Alert, Site or General Emergency has existed.
REVISION RECORO REV. 00 PAGE(S): Entire Procedure DATE4E 2 8 S2 REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE:
- REV. PAGE(S): DATE:
REV. PAGE(S): DATE: REV. PAGE(S): DATE: APPROVAL RECOMMENDEO APPROVED DA TE
- j.,,y 4 ?una n
{ ,:HAIRMANSTA TION NUCLEAR SAFETY vn S , ,,,,
\f AND OPERA TING COMMITTEE
. _ . . - _ - . . _ . . . . ,_m.. . . _ _ m __ . __ . .
No. 9788 7210 4 NUMBER PROCEDURE TITLE REVISION 00 i - - EPIP-6.01 RE-ENTRY / RECOVERY GUIDELINE , PAGE 2 of 6
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINEO
- i. ,
- 1. INITIATE PROCEDURE:
i' a) BY: DATE:
- TIME
- 2. ' VERIFY CONDlTIONS:
a) Station parameters indicate
- CO TO EPIP-1.01, Emer-
- no potential or actual emer- gency Manager Controlling i gency exists Procedure Step 3 for re-assessment.
b) Station radioactivity releases are controllable AND permiss- [{
%.J able levels are NOT exceeded l c) Station is capable of sustained i safe / stable condition Note: Recovery organization members are NOT designated prior to initiation of this procedure. They are selected based on
- availability and. required. expertise.
1 . f 3. DEVELOP INITIAL RECOVERY PLAN: i a) With Recovery Manager and appro-i priate advisors, prepare an initial recovery plan which ) includes: I
- 1) Identification of any immed-
! iate area reentrys required i
- 2) Identification of any immedi-l ate repairs required
' 3) Identification of immediate , modifications required i h
No.stss72:e NUMBER PROCE00RE 77TLE REVISION 00 O-' s EPIP-6.01 RE-ENTRY / RECOVERY GUIDELINE PAGE 3 of 6 STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINEO
- 3. (CONTINUED)
- 4) Identification of immediate mate. rial and personnel re-sources required
- 5) Development of an initial schedule for performing the above tasks
- 6) Development of the initial recovery organization
- 4. NOTIFY RECOVERY PERSONNEL:
a) Inform the members of the initial recovery organiza-tion of their function and work schedule (
- 5. TERMINATE EPIP-1.01 a) GO TO EPIP-1.01, Step 11, for termination, THEN Gjl H Step 6 of this pro-cedure-
- 6. VERIFY REENTRY:
a) 1][ reentry of areas included a) IF NOT, GO TO Step 8,. in initial recovery plan, C0 TO Step 7 Note: Following termination of the emergency, emergency exposure limits are no longer authorized and normal exposure limits are back in effect.
- 7. DEVELOP REENTRY PROCEDURES:
a) Initiate development of re-entry procedures, considering the following:
No. 9788 7210 NUMBER PROCEDURE TITLE . REVISION EPIP-6.01 RE-ENTRY / RECOVERY GUIDELINE' PA GE 4 of 6
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAlt/ED
- 7. (CONTINUED)
- 1) Reentry, area radiation levels
- 2) Exposure levels of recovery personnel
- 3) Survey requirements
- 4) Survey team composition
- 5) Need for additional per-sonnel
- 6) Protective measures i
- 7) RWPs
- 8) ALARA b) Receive required procedure approvals AND implement 4
- 8. VERIFY REPAIRS:
- I a) IF repairs included in initial a) IF NOT, GO TO Step M.
i recovery plan, GO TO Step 9
- 9. DEVELOP REPAIR PROCEDURES:
a) Initiate development of re-pair procedures, considering the following:
- 1) Applicability of existing procedures I
- 2) Exposure limits f
l t 3) Exposure levels of recovery personnel I-
_ ~ ._ . __ . .__ ._ . _ _ . No. 97 8872 20 NUMBER PROCEOURE TITLE REVISION 00
\- EPIP-6.01 RE-ENTRY / RECOVERY GUIDELINE PAGE 5 of 6
- STEP ACTION /EXPECTEO RESPONSE RESPONSEN0TOBTAINEO
- 9. (COSTINUED)
- 4) Need for additional materials
; and personnel
- 5) RWPs
- 6) ALARA
! b) Receive required procedure , approvals AND. implement repairs
- 10. VERIFY MODIFICATIONS:
a) IJ; modifications identified a) IF NOT, GO TO Step 12. in initial recovery plan,
,, GO TO Step 11, w' 11. DEVELOP MODIFICATIONS:
a) Initiate development of DCs, MRs, njg jumper requests, con-sidering the following: ?,
- 1) Nuclear safety implica-tions
- 2) 50.59 review requirements
, 3) Tech. Spec. implications i
- 4) ALARA b) Receive required approvals
, AND implement modifications l
- 12. VERIFY RECOVERY STATUS:
I a) Affected unit (s) - a) IF NOT, GO TO Step 13. CAPABLE OF NORMAL OPERATION i
- 1) GO TO Step 14 O
i
No.97887210 NUMBER - PROCEOURE TITLE REVISION 00 v ~EPIP-6.01 RE-ENTRY / RECOVERY GUIDELINE PAGE 6 of 6
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINEO ,,
- 13. DEVELOP LONG TERM RECOVERY PLAN:
a) With Recovery Manager and appropriate advisors, de-velop a long term recovery plan which includes:
- 1) The recovery organization
- 2) Administrative controls during recovery
- 3) Tasks to be accomplished
- 4) Task schedule
- 14. TERMINATE EPIP-6.01:
, a) Completed By:
Time: Date: ! b) Forward this procedure to SNSOC for review l l l END I
Veoco y VIRGINIA ELECTRIC AND POWER COMPANY [ Surry Power Station {\j P. O. Box 315
- Surry, Virginia 23883-0315 July 29, 1982 Director, Safety Evaluation &
Control Eth Flocr; OJ RP; Richmond Volumes 1, 2 and 3 SURRY POWER STATION EMERGENCY PLMJ IMPLEMENTING PROCEDURES Enclosed is a revised edition of the Surry Power Station Emergency Plan Implementing Procedures, dated: July 29, 1982. Please destroy your previous edition. of the Surry Power Station Emergency Plan Implementing Procedures and replace it with the attached. n U E. P. DeWandel Records Management Supervisor EPD: mag Enclosure i 4 1 v) f 1
No. 97487230 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE O
\
NUMBER PROCEDURE TITLE REVISION 00 EPIP-4.01 RADIOLOGICAL ASSESSMEtiT DIRECTOR PAGE CONTROLLI!iG PROCEDURE (With 2 Attachment) 1 of 30 PURPOSE To initially assess emergency conditions, provide protective measures recommendations, establish an emergency organization and direct Health Physics Response to an Emergency. USER Radiological Ausessment Director or Senior Health Physics represen-tative onsite. ENTRY CONDITIONS
- 1. Activation by EPIP - 1.01
\
(/
'u ,
i l l l l l REVISION RECORD . REV. 00 PAGE(S): Entire Procedure DATEdVL 2 91!82 l REV. PAGE (S) : DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: [ REV. PAGE(S): DATE: l REV. PAGE(S): DATE: REV. PAGE(S): DAT2: 1 APPROVAL RECOMMENDED APPROVED DA TE l b ' 54% l ,Z JUL 2 9 1992 I
* '^=
CHAIRMAN STA TION NUCLEAR SAFETY AND OPERA TING COMMITTEE
No. 97887210 NUMBER PROCEDURE TITLE REVISION EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING PROCEDURE PAGE 2 of 30 1
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 1. INITIATE PROCEDURE:
a) BY: DATE: TIME: NOTE: During the initial stages of the emergency the Shift Supervisor may assume the position of Emergency Manager.
- 2. CHECK CONDITIONS:
[ a) The Senior Health Physics a) IF TSC is activated, report (_j individual onsite should to the TSC. report to the Control Room E the TSC is NOT ac'ivatad b) Request briefing with Emergency Manager to determine:
- 1) Existing Plant Conditions
. 2) Emergency Action Levels (EALs) exceeded
- 3) Classification of emergency c) Assume the position of Radio-logical Assessment Director
- 3. INITIAL ASSESSMEITI:
a) IP an offsite release has a) If no actual OR potential occurred: offsite release has ment occurred GO TO Step 15. b) Request alternate on-shift technician to obtain, if possible, a sample of the effluent
No. 97887210 NUMBER PROCEDURE TITLE REVISION O 00 I EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING PROCEDURE PAGE 3 of 30
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 4. VERIFY EMERGENCY LEVEL:
a) E the event - UNUSUAL a) F the event is ALERT IF EVENT, continue with this or GREATER, GO TO Step 6. instruction
- 5. EVENT - UNUSUAL EVENT:
a) IF, radiological release - a) IF the event is NOT radio-continue logical release GO TO Step LS-b) Initiate EPIP-4.08 , Initial Offsite Release Assessment to assess percent Tech Spec Limit wj no Return to Step 5.c c) Assess percent Tech Spec:
- 1) IF normal range monitors 1) E normal range monitors indicate LESS THAN 100% GREATER THAN E EQUAL l
Tech Spec, inform Emergency TO 100% Tech Spec, GO TO Manager initial results Step 5.e.2. indicate LESS THAN UNUSUAL EVENT A!O GO TO Step 5.e
- 2) E normal range monitors 2) IF normal range monitors are onscale and indicate indicate GREATER THAN I GREATER THAN 100% Tech 1000% Tech Spec, GO TO Spec, but LESS THAN 1000% Step 6_.
Tech Spec O
No. 97887210 NUMBER PROCEDURE TITLE REVISION
) 00
\/ EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING PROCEDURE PAGE 4 of 30
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED 5 CONTINUED)
Normal range monitors are offscale and indicate LESS THAN 1000% Tech Spec
- 3) Confirm classification of an UNUSUAL EVENT d) Report percent Tech Specs and Site Boundary dose rate to the Emergency Manager e) Obtain sample (s) of the e) E sample CANNOT be effluent release path obtained GO TO Step M.
O V f) Have sa::tple(s) analyzed as per Health Physics procedure, H. P. i 3.4.1.3 l g) GO TO Step 16,for follow up l assessment i ( 6. EVENT - ALERT, SITE OR GENERAL: a) IF the emergency is classified a) IF the event is NOT a as an ALERT, SITE, OR GENERAL radiological release, EMERGENCY GO TO Step M. AND Radiological release has occurred g may potentially occur, continue with this l procedure
- 7. EVENT - CONDITION IV LIMITING FAULTS:
a) IF event - Limiting Fault a) IF, accident is NCfr a Accident: Limiting Fault, GO TO Step 12. I
. , , - , , .e-,, , _ . _ . , -
940.97887210 NUMBER . PROCEDURE TITLE REVISION O 00 k/# EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR
#AOf CONTROLLING PROCEDURE 5 of 30
- STEP ACTIONEXPECTED RESPONSE RESPONSENOTOBTAINED
- 7. (CONTINUED)
- 1) LOCA - GO TO Step 11
- 2) Steam Generator Tube Rupture - GO TO Step 9_
- 3) Main Steam Line Rupture -
GO TO Step 10 0, R
- 4) Fuel Handling Accident -
C GO TO Step 8_
- 8. EVENT - FUEL HANDLING ACCIDENT:
a) E event - Fuel Handling accident:
- 1) Recommend evacuation of Fuel Building AND/OR Affected containment Building AND l
l 2) Restrict access until radiological assessment can be made b) Assign EPIP-4.06, Personnel b) E individual'found non-Monitoring and Decontamination contaminated, continue to monitor and decontaminate, with this instruction. as necessary, individuals evac-
, uated from accident area V
1
No 97887210 NUMBER PROCEDURE TITI.E REVISION 00 d EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR FA68 CONTROLLING PROCEDURE 6 of 30
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINEO
- 8. (CONTINUED) c) Initiate EPIP-4.08, Initial Offsite Release Assessment, to assess offsite releases AND Return to Step 8.d d) Report results of above step to Emergency Manager e) GO TO Step 3
- 9. EVENT - STEAM GENERATOR TUBE RUPTURE:
%J
- a) E event - Steam Generator a) IF event is NOT Steam
! Tube Rupture, request the Generator Tube Rupture, following from Emergency GO TO Step _10 Manager:
- 1) Status of Air Ejector divert
- 2) Number of Steam Generator Relief Valves lifted, pR Valves which may potentially I lift
- 3) IF relief valves lifted, length of time valves remained open
- 4) Status of main steam supply to the Auxilary Feedwater l
Pump Turbine i ! 5) Current Steam Generator Blowdown pathway
No. 978872:0 NUMBER PROCEDURE TITLE REVlSION h\ 00 V EPIP-4.01 RADIOLOGICAL ASSESSMEITT DIRECTOR PAGE CONTROLLING PROCEDURE 7 of 30
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINEO
- 9. (CONTINUED) b) IF Air Ejector diverted to b) ))[ Air Ejector did NOT containment divert to containment AND OR Individuals are in affected IF NO individuals are in containment: affected containment:
- 1) Request immediate evacu- 1) Continue with this ation of containment instruction.
c) IF nain steam supply to c) IF main steam supply to Auxiliary Feedwater Pump AFWPT isolated, release Turbine has NOT been from this pathway may be isolated: disregarded.
- 1) Request Emergency Manager 1) GO TO Step 9.d.
l initiate isolation of main steam supply, of affected generator, to Auxiliary Feedwater Pump Turbine i d) Request placement of oper-ations personnel in Emergency Switchgear Room to report:
- 1) Initial readings AND l 2) Increase or decrease in i
Main Steam and AFWPT exhaust monitors e) Initiate EPIP 4.08, Initial Offsite Release Assessment: 1
- 1) Determine offsite dose rate
No. 91881210 NUMBER PROCEDURE TITLE REVISION [j'\ ( EPIP-4.Ol RADIOLOGICAL ASSESSMENT DIRECTOR 00 PACE CONTROLLING PROCEDURE 8 of 30
- STEP ACTION / EXPECT l0 RESPONSE RESPONSE NOTOBTAlt/E0
- 9. (CONTINUED)
AND
- 2) GO TO Step 9.f of this instruction f) Report results of the above step to Emergency Manager g) Restrict access, until survey (s) confirm no radiological hazards:
- 1) Steam Generator Blowdown Cooler area
- 2) Steam Generator Blowdown y/ Lines
- 3) Steam Generator relief valve area
- 4) Auxiliary Feedwater Pump Turbine exhaust area
- 5) Condensate Polishing Building h) _IF personnel are available h) IF personnel are NOT avail-consider initiation of EPIP- able, consider sampling 4.23, Post Accident Sampling upon arrival of additional g Reactor Coolant, to manpower assess core damage AND Continue with this instru-ction.
- 1) Consider sampling of Steam Generator Blowdown and Main Steams of affected unit j) Potential liquid release pathway may occur through the Main Steam Safety Valve.
b
Pfo. 97887210 NUMBER PROCEDURE TITLE REVlSION 00 {Nj] EPIP-4.01 RADIOLOGICAL ASSESSMEITI DIRECTOR CONTROLLING PROCEDURE PAGE 9 of 30
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 9. (CONTINUED) k) GO TO Step 13
- 10. EVENT MAIN STEAM LINE RUPTURE:
a) E Main Steam Line Rupture a) IF event is NOT a Pain occurs, review station ven- Steam Line Rupture, GO TO tilation monitors Step 11.
- 1) IF station monitors have 1) IF station monitors indicated a release, DO NOT indicate a re-initiate EPIP-4.08, lease, GO TO Step 10.b.
Initial Offsite Release Assessment
}
m./
- 2) Assess offsite dose rate
- 3) Return to Step 10.b b) Report results to the Emergency Manager c) IF NO initial release has occurred, source term may develop:
- 1) Inside containment pR
, 2) From Main Steam Relief ! Valve Lift d) Request following information from the Emergency Manager:
- 1) Location of Steam Break
- 2) Actual or potential lifting of Main Steam Safety Valves
Ns.97867213 NUMBER PROCEDURE TITLE REVISION O 00 b EPIP-4.01 RADIOLOGICAL ASSESSMFliT DIRECTOR
^'
CONTROLLING PROCEDURE r*10 of 30
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 10. (CONTINUED)
- 3) IF, valves have lifted, length of time valve remained open
- 4) Status of Auxiliary Feed- 4) IF Main Steam supply water Pump Turbine (iso- to the Auxiliary Feed-lation) water Pump Turbine has been isolated, no release will occur through this
- 5) Monitor Reading on Main pathway.
Steam Monitors and AFWPT exhaust monitors e) ~~IF manpower is available: e) IF manpower is NOT available
) 1) Consider initiation of continue with this procedure EPIP-4.22, Post Accident AND Sampling of Containment Air Consider initiation once manpower is available.
AND
~
- 2) EPIP-4.23, Post Accident Sampling of Reactor Coolant f) GO TO Step 13, 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.
- 11. EVENT - LOCA a) IF event - LOCA: a) IF NOT LOCA, GO TO Step
- 1) Evacuate Auxiliary Building and Safeguards Building
No. 97887210 NUMBER PROCEDURE TITLE REVISION O 00 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR - CONTROLLING PROCEDURE PAGE 11 of 30
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 11. (CONTINUED)
AND
- 2) Restrict entry until survey (s) confirm no radiological hazzards b) IF offsite release has b) IF NO offsite release has occurred, initiate EPIP-4.08, occurred, GO TO Step ll.d.
Initial Offsite Release Assessment
- 1) Assess offsite release AND
\j 2) Return to Step 11.c c) Report results of above step to Emergency Manager d) IF manpower is available, d) M manpower NOT available:
consider initiation of following: 1) Continue with this instruction.
- 1) EPIP-4.22, Post Accident Sampling of Containment Air AND
- 2) EIPI-4.23, Post Accident Sampling of Reactor Coolant
) e) GO TO Step M
- 12. EVENT - RADIOLOGICAL RELEASE:
a) IF event - Radiological a) F event is NOT a Radio-IF Release, continue with this logical Release, GO TO instruction Step M. b (
- m. . mms NUMBER A TTACHNENT TITLE REVISION RADIOLOGICAL ASSESSMENT DIRECTOR d II ####
CONTROLLING PROCEDURE 12 of 30 s
- 12. (CONTINUED) i b) Initiate EPIP-4.08, Initial Offsite Release Assessment:
- 1) Assess offsite release Ah3
, 2) Return to Step 12.c f c) Report resulta, of above
, step to Emergency Manager d) Request the Emergency i Manager place an in-
' dividual at monitor of --
interest AND Report increase or decrease in reading
- 13. VERIFY OFFSITE DOSE RATE:
a) IF results of offsite release a) IF results of offsite assessment at the Site release assessment at Site Boundary: Boundary:
- 1) GREATER THAN OR EQUAL TO 1) LESS THAN 50 mR/hr 50 mR/hr Whole Body Whole Body OR OR GREATER THAN OR EQUAL TO LESS THAN 250 mR/hr 250 mR/hr Thyroid Thyroid
- 2) Continue with this 2) GO TO Step H.
instruction O
No.97887210 NUMBER PROCEDURE TITLE REVISION EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING PROCEDURE PAGE 13 of 30
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINEO
- 14. PRCTECTIVE MEASURES:
a) Obtain an estimate of a) E no estimate can be duration of release (hours) given, assume 3, hours. from Emergency Manager b) Use Site Boundary, 2, 5, and b) F 2, 5, and 10 mile dose IF 10 mile Whole Body and- rate were NOT calculated, Thyroid dose rates from: use dose rate at the distances calculated.
- 1) EPIP-4.08, E initial assessment 1) GO TO Step 14.b.2.
OR,
- 2) EPIP-4.03, IF follow-
/ up assessmeE c) Determine projected dose:
DURATION OF RELEASE x DOSE RATE = PROJECTED DOSE (hours) (mR/hr) (mR)
- 1) Repeat above calculation for all dose rates given i in Step 14.b d) E projected dose - d) I_F projected dose -
GREATER THAN g EQUAL TO LESS THAN 500 mR Whole 500 mR Whole Body Body OR OR GREATER THAN g EQUAL TO LESS THAN 1000 mR Thyroid 1000 Thyroid
- 1) Initiate EPIP-4.07, 1) Inform Emergency Man-Protective Measure ager y protective measure required O
LJ l
No. 97887210 NUMBER PROCEDURE TITLE REVISION 00 V) EPIP-4.01 RADIOLOGICAL ASSES 3 MENT DIRECTOR CONTROLLING PROCEDURE PAGE 14 of 30
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 14. (CONTINUED)
AND AND
- 2) Determine protective 2) GO TO NOTE prior to measures for distances, Step 15.
which projected dose equals or exceeds the above dose
- 3) Return to Stcp 14.e e) Recommend to the Emergency e) IF NO protective measures Managers required, GO TO NOTE prior to Step 15.
O 1) Protective measures re-V quired offsite AND
- 2) Distance protective measures required i
l NOTE: First Aid considerations must be given priority over decontamination of individual. 15- EVENT - INJURED CONTAMINATED INDIVIDUAL: a) IF the event is an Injured a) F the event ic NOT an In-IF Contaminated Individual, jured Contaminated Indivi-dual, GO TO Step 16. AND Requires Offsite Medical l Treatment: l O l l l l l
No. 97887210 NUMBER PROCEDURE TITLE REVISION 2 00
,_j EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING PROCEDURE PAGE 15 of 30
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 15. (CONTINUED) 4
- 1) Initiate EPIP-4.20, Health Physics Actions for Trans-portation of Contaminated Injured Individual
- 2) Review personnel contami-nation survey (s) to confirm personnel contamination b) Insure clothing removal and/ b) E individual deconned, or onsite decontamination GO TO Step 15.e.
can NOT be used to remove contamination fi
\._,,/
c) Insure a Health Physics individual is available to accompany the victim d) Reconnend to Emergency Manager transportation of victim to MCV e) IF the event initiated e) IF other EALs were only for contaminated in- exceeded GO TO Step 16. jured individual requiring offsite medical treatment, AND O other EALs exceeded: N_O
- 1) GO TO Step 30
- 16. FOLLOW-UP ASSESSMENT:
a) IF TSC NCfr activated a) IF TSC IS activated GO TO continue with this in- Step 18. struction O
' .s 1
l F No. 97887210 8 i NUMBER PROCEDURE TITLE REVISION O 00 / h EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING PROCEDURE PAGE 16 of 30
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 16. (CONTINUED) b) One member of Health Physics group should remain in the '
control room to assist the Emergency Manager s c) E conditions require c) Continue with this instru-presence in another location: ction.
- 1) Inforn Emergency Manacer +
AND , s s.
- 2) Report to Control Room s immediately upon completion 3 O of task b d) IF a radiological release has d) IF NO release has occurred:
occurred: ,
- 1) GO TO Step 16.g. (
- 1) Continue with this instru-ction i e) Obtain samples of the effluent e) IF MO samples can be ob-tained >
- 1) Analyze samples as per nomal Health Physics ,
- 1) Continue with this procedure instruction '
AND AND
- 2) E sample activity is high, '2) jrse monitoring readings assign EPIP-4.26, High Level '/ for follow-up assess-Activity Sample Analysis iment I -
\> w ,'
f) -IF time allows: f) -IF time is NOT available,s ; s I
- 1) Initiate EPIP-4.03, Dose 1) GO TC' Step 16.g , .
Assessment Controlling Procedure AND
]
. ! g GJ '
'I
e Pto. 97887210 ,
' ^
\
NUMBER PROCEOURE TITLE REVISION m 00 s EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING PROCEDURE PAGE 17 of 30
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 16. (CONTINUED)
AND 2) Return to Step 16.f, when time becomes avail-
- 2) 'tetura to Step 16.g able g) Insure c ase control individual is avai1 @le to supply dosimetry
, h) Frovide H.P. coverage, as needed, for; i
- 1) Can. age Control Teams
's OR
] !
- 2) Access cor ,
~ ,/ .
-OR/
i
- 3) Personnel monitoring I
OR
- 4) Sample'~ analysis ,
- 1) IF the emergency has 1) E the emergency has NOT terminated GO TO Step H terminated GO TO Step 16.j s
j) IF TSC IS manned, GO TO j)~ E the TSC is NOT manned: Step 17
'~
n ' q 1) Obtain latest dose rate
-s
- 2) Return to Step p A'ID
- 3) Repeat sampling and assessment, as necess-ary n .% }.p) ,
s h t { r ' *\ w--v. ' a - - . , . 4 -- .3
-.s., --.._~_
} - a
. e.o.orss721o +
r' t / ' NUMBER i '?ROCEDURE TITLE
/") - .
REVIS. ION 00' V EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR
~~ '
? ACE CONTROLLING PROCEDURE ,
18 of 30
- STEP ACTION / EXPECTED RESPONSE RESPCNSENOTOBTAINEO
- 17. VERIFY RELIEF:
, a) When a more Senior Health a) IF F relief is NOT needed, Physics individual arrives GO TO Step 18. .; onsite 4_j ' QR , . E relief is needed: ,
- 1) Brief successor as to existing plant conditions i AND
, 2) Offsite release assessment AND
- 3) H. P. actions currently undcrvay b) Announce the change of position to the Emergency Manager
- 18. ESTABLISH EMERGENCY ORGANIZATION:
a) IF the H. P. emergency a) E emergency organization organization NOT activated, E activated, GO TO NOTE' continue with this procedure prior to Step H. b) IF manpower is available: b) E manpower is NOT avail-able, continue with this
- 1) Establish the Dose Assess- instruction, assigning ment Team EPIP-4.03, when manpower becomes available.
AND l
- 2) Assign EPIP-4.03, Dose Assess-O ment Controlling Procedure
_ _ . ~ . - _ ._. ._. _
. , -. ~_
No. 97887210 NUMBER PROCEDURE TITLE REVISION N- , 00 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING PROCEDURE PAGE
< 19 of 30
.~ -
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINEO
- 18. (CONTINUED) c) E:*ablish position of c) E manpower is NOT yet Radiation Protection Super- available, continue with visor and assign EPIP-4.02, instruction assigning Radiation Protection Super- EPIP-4.02 when manpower visor Controlling becomes available.
g: During a SITE of GENERAL emergency, a minimum of two
. monitoring teams should be dispatched for offsite monitoring.
i
\
NOTE: The function of plume tracking /offsite monitoring will be the responsibility of the Radiological Assessment Coordinator, upon activation of EOF. D '
- '19. ASSESS NEED FOR OFFSITE
, MONITORING:
4 a) Evaluate need for offsite a) E offsite monitoring NOT monitoring with Dose Assess- required, GO TO Step 22 ment Team Leader
\l '
l b) IF EOF NOT activated: b) IF EOF activated, GO TO Step 22. , 1) Request Radiation Pro-tection Supervisor to initiate EPIP-4.16, Offsite Monitoring
/
c) Evaluate need of protective l measures for offsite teams l d) E Whole Body exposure may d) E Whole Body will NOT exceed 10CFR20 quarterly exceed 10CFR20 limits, limits: GO TO Step 19.e.
- 1) Initiate EPIP-4.04, Emergency Exposure Limits b\
lG l l l
ha.sfes72 e NUMBER PROCEDURE TITLE REVISION (' 00 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING PROCEDURE
^'
20 of 30
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 19. (CONTINUED)
AND
- 2) Return to Step 19.e e) E Thyroid exposure exceeds e) IF Thyroid exposure will 10 REM (refer to Attachment NOT exceed 10 REM, GO TO 2): Step 19.f.
- 1) Initiate EPIP-5.07, Admini-stration of Radioprotective Drugs AND Return to Step 19.f f) Inform Radiation Protection Supervisor:
- 1) Number of monitoring teams 1) E adequate manpower NCfr required available, GO TO Step E.
AND
- 2) Protective clothing required AND i
- 3) Respiratory protection required l g) Assist Dose Assessment Team in placement of offsite .
monitoring teams.
- 20. OFFSITE ASSESSMENT:
I a) IF offsite releases occurs a) IF NO offsite releases have occurred
- 1) Request Emergency Manager l place individual at monitor OR O of interest l
e.a.stee71e NUMBER PROCEDURE TITLE REVISION h (/ EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR 00 PAGE CONTROLLING PROCEDURE 21 of 30
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 20. (CONTINUED)
IF there is NO potential for a release AND
- 2) Report increase or 1) GO TO Step 22.
decreasein monitor readings b) The following information will be supplied periodically OR upon request:
- 1) Meteorological data
[)) Q.,
- 2) Radiation Monitor System data
- 3) Sample Analysis data c) Upon receipt of above data: c) IF no data received, GO TO Step 20.d.
- 1) Complete Attachment 1 l 2) Give Attachment I to the Dose Assessment Team -
i l d) Obtain latest offsite Release d) F data not available, GO TO Assessment Data Sheet from Step 22. Dose Assessment Team i
- 21. VERIFY OFFSITE DOSE RATE:
I a) IF Site Boundary dose rates a) IF, Site Boundary dose rate:
- 1) GREATER THAN OR EQUAL TO 1) LESS THAN 50 mR/hr 50 mR/hr Whole Body Whole Body
[ _OR _OR l O L
N D. U S S 7M G NUMBER PROCEDURE TITLE REVISION O EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING PROCEDURE 00 PAGE 22 of 30
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 21. (CONTINUED)
- 2) GREATER THAN OR EQUAL TO 2) LESS THAN 250 mR/hr 250 mR/hr Thyroid Thyroid b) Return to Step M b) GO TO Step 22.
- 22. EOF ACTIVATION:
i a) IF EOF activated, continue a) IF EOF NOT activated, with this instruction GO 10 Step _2_3, 3 b) Brief Radiological Assess-ment Coordinator:
- 1) Existing plant conditions D
AND
- 2) Current offsite dose pro-jections AND
- 3) H.P. actions underway c) Inform Dose Assessment Team Leader to brief Radiological Assessment Coordinator:
I
- 1) Offsite dose assessment
( AND
- 2) Status and location of off-l site monitoring teams
! d) Insure individual remains in ! radiological assessment area to transmit to EOF: l 0
No. 97837210 NUMsER PROCEDURE TITLE REVISION i 00 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING PROCEDURE PAGE 23 of 30
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 22. (CONTINUED)
- 1) Meteorological data AND
- 2) Monitor data AND
- 3) Sample analysis data
- 23. ESTABLISH IN-PLANT MONITORING:
a) Brief Radiation Protection Supervisor as to existing plant conditions b) Assist in selecting proper b) IF NO monitoring is monitoring and sampling needed GO TO Step 23.e. areas J) Instruct Radiation Protection Supervisor to initiate EPIP-4.14, Inplant Monitoring AND EPIP-4.15, Onsite Monitoring, as necessary d) Assist Radiation Protection Supervisor in:
- 1) Determining protective gear
- 2) Dosimetry AND
- 3) Developing special precautions, as necessary, for inplant and
(~ onsite monitoring teams.
No. 9 7887210 NUMBER PROCEDURE TITLE REVISION O, 00 EPIP-4.01 liDIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING PROCEDURE FAGE 24 of 30
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 23. (CONTINUED) e) Request from Radiation Protection Supervisor establishing initial and periodic monitoring of TSC and EOF 11 Based on survey data and plant conditions establish routine for surveys of the Emergency Centers f) IF a radiological release has f) GO TO Step 23.g.
occurred A change in plume direction OR increase in release has taken place
- 1) Notify Radiation Protection Supervisor Alm
- 2) Request survey of emergency centers g) Based on survey data, direct the establishment of new control points:
- 1) Control spread of contami-nation AND/OR
- 2) Limit exposure V
_ _ - - - _ -- a
Ns. ores 721e NUMBER PROCEDURE TITLE REVISION 00 v EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PACE CONTROLLING PROCEDURE 25 of 30
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT08TAINE0
- 24. ENTRANCE - ACCESS CONTROL AREA: '
a) Entrance into access a) IJ, entrance is not required controlled areas should GO TO Step M. require 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 D 1) If necessary, request [V initiation of a Radiation Work Permit, as per the Health Physics Manual
- 25. RESPIRATORY PROTECTION: $
a) Assess results of air sampling b) Recommend evacuation of all non-essential personnel in areas that:
- 1) High airborne activity is 1) E Airborne contamination expected but not measured NOT suspected, GO TO Step E.
- 2) Airborne activity is 2) E activity is LESS GREATER THAN 0.25 times R EQUAL TO 0.25 THAN O_R maximum permissible maximum permissible concentration. concentration GO TO Step E.
c) Assess need for respiratory protection, as per EPIP-4.05 - Respiratory Protection and h g return to Step 26
No. 97887210 NUMBER PROCEDURE TITLE REVISION EPIP-4.01 RADIOIDGICAL ASSESSMENT DIRECTOR PA GE CONTROLLING PROCEDURE 26 of 30 F
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 26. DETERMINE NEED FOR RADIOPROTACTIVE DRUGS:
a) Determine, from survey results, concentration of radiciodine (uCi/ml) b) Determine actual or projected length of exposure time (hours) c) F IF,repiratory protection c) E respirator NOT worn, was worn, determine pro- use protection factor of tection factor: 1.
- 1) Refer to EPIP-4.05,
^
T Respirator Protection, Attachment 3, to determine protection factor d) Determine actual concen-tration: Step 2.a Step 2.c
= /d e) With data from Step 2.b and Step 2.d, use Attachment 2 --
to determine iodine dose committment f) IF actual OR projected f) _IF, Thyroid exposure is exposure will be GREATER LESS THAN p Rem: THAN OR EQUAL TO 10 Rem Thyroid 1) GO TO Step 27.
- 1) Request approval from Emergency Manager to administer radio-frotective drugs b
U
No. 97887210 NUMBER PROCEDURE TITLE REVISION EPIN4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING PROCEDURE PAGE 27 of 30
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 26. (CCNTINUED) g) Il approval is granted:
- 1) Initiate EPIP-5.07, Administration of Radio-protective Drugs h) Supply of tablets is located h) Alternate supply located in H.P. Office Emergency Kit at North Anna Power Station
- 27. ONSITE EVACUATION OF NON-ESSENTIAL PERSONNEL:
a) Determine with Dose Assessment
} Team Leader, the projected or ,j actual exposure, onsite, from release of radioactive material b) Determine direction of plume c) Determine from Fmergency Manager duration of release d) IF actual or projected d) E dose is LESS THAN evacu-exposure onsite: ation limits
- 1) GREATER THAN OR EQUAL TO O2 1 Rem Whole Body IF_ plume is in the direction AND/OR of the evacuation route:
- 2) GREATER THAN OR EQUAL TO 1) Consider sheltering of 5_ Rem Thyroid non-essential workers AND AND
- 3) Plume is NOT in the direction 2) GO TO Step M.
of the evacuation route, con-tinue with this instruction v'
t.o. steen t e NUMBER PROCEDURE TITLE REVISION
) EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR 00 PAGE CONTROLLING PROCEDURE 28 of 30
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 27. (CONTINUED) e) Recommend evacuation of all non-essential personnel f) Report recomendation to the Emergency Manager
- 28. ASSESS EXPOSURE TO EMERGENCY RADIATION WORKERS:
a) Prior to entry into a High Radiation areas, access possible exposure levels b) E Whole Body exposure b) E entry into high T exceeds 10CFR20 quarterly radiation area will NOT exceed exposure limits:
- 1) Initiate EPIP-4.04, 1) GO TO Step 2_9.9 Emergency Exposure AND
- 2) Return to Step 29
- 29. DOSIMETRY FOR OFFSITE ASSISTANCE:
a) IF offsite assistance is a) IF offsite assistance is required to mitigate NOT required, GO TO Step emergency (fire and/or 3_0. rescue squads)
- 1) Inform Radiation Protection Supervisor of arrival
- 2) Request dosimetry to be supplied at Security Building prior to entrance onsite
No. 97887230 NUMBER FROCEDURE TITLE REVlSION I h 00 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING PROCEDURE PAGE 29 of 30
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 30. VERIFY EMERGENCY:
a) IF emergency condition still a) IF Emergency Manager exists, continue with this declares termination of instruction emergency GO TO Step 31,. b) Return to Step 17,and direct repetition:
- 1) Survey (s)
AND/OR
- 2) Radiological sampling AND/OR
(_m
- 3) Offsite dose assessment c) Advise the Emergency Manager and the Radiation Protection l
Supervisor as to tha increasing or decreasing trenis of I Emergency
- 31. EVENT TERMINATION:
a) Termination of emergency de-clared by Emergency Manager l
- 1) Notify Radiation Protection Supervisor and Radiation Assessment Coordinator of termination of emergency
- 2) Evaluate further use of l monitoring team (s) for data collection b) Request review of recovery phase with the Emergency Manager and consider the
[~') following: V
No. 97887210 NUMBER PROCEDURE TITLE REVISION O \ 00 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING PROCEDURE PAGE 30 of 30
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 31. (CONTINUED)
- 1) Access control to out-side contaminated areas
- 2) Return to normal access control, areas through-out site
- 3) Assistance for deconta-mination effort, Health Physics support person-nel and radwaste pack-aging and disposal
- 32. ADMINISTRATION:
rm a) Initiate replacement of procedure and/or emergency equipment if necessary b) Forward completed proce-dure (s) , release calculations and survey results to the Emergency Manager
- 33. TERMINATE EPIP-4.01:
a) COMPLETED BY: DATE: TIME: Elm O
. Ns.97487220 NUMBER A TTACHMENT TITLE REVISION EPIP-4.03 00 n(/ RADIOLOGICAL DATA WORKSHEET A TTACHMENT PAGE 1 1 of 1 DATE: TIME: UNIT #
i Meteorological Data: WIND DIRECTION (from): SECTORS AFFECTED: WIND SPEED (mph): PRECIPITATION: STABILITY CLASS: RADIATION MONITORING SYSTEM DATA: n MONITOR CPM OR MR/HR VENT VENT (VG-104) PROCESS VENT (GW-102) AIR EJECTOR (SV-111, 211) l VENT VENT (VG-123) PROCESS VENT (GW-122) MAIN STEAM ( ) AFWPT ( ) CONT. HIGH RANGE G-
740.97!87224 NUMBER A TTACHMENT TITLE REVISION (m) ( EPIP-4.01 00 N/ THYROID EXPOSURE vs. IODINE CONCENTRATION A TTACHMENT PAGE 2 1 of 1 l1 10 3. . .
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I-131 "' I "-I - 41 .'i : i j r -2 .i"-.- .-- - *'p - i f ,.-- - e f . .-- p.'- - - , - 4 7 (uci/ml) - ng=i=-1=1- L.--.sd_:
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" t- ~ : / .- ---t f = 45 4 +3- ;f -M--n =: .y-; . . - -r. r- =- - .:, = -;
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No. 978872 30 VIRGINIA ELECTF;IC AND POWER COMPANY SURRY POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE e i NUMBER PROCEDURE TITLE REVISION 00 EPIP-4.02 RADIATION PROTECTION SUPERVISOR PAGE CONTROLLING PROCEDURE (With No Attachments) 1 of 16 PURPOSE To assist Radiological Assessment Director in establishment of radiatios. protection program during an emergency and dispatching monitoring teams. USER Assistant Health Physics Supervisor, Health Physicist or Health Physics Technician. ENTRY CON 0lTIONS Any one of the following : 0) \g 1. Emergency classification of ALERT.
- 2. Activation by another EPIP.
- 3. Any other time the Radiological Assessment Director deems it necessary.
REVISION RECORD REV. PAGE(S): DATE:JUL 2 9 1962 REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: APPROVAL RECOMMENDED APPROVED DA TE _/ [ JUL 2 i M
. ?e -
CQMANSTA TION NUCLEAR SAFETY AND OPERA TING COMMITTEE
too.s7satrio I NUMBER PROCEDURE TITIE REVISION
. EPIP-4.02 00
< RADIATION PROTECTION SUPERVISOR CONTROLLING PROCEDURE PAGE 2 of 16
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
)
NOTE: I_F, Health Physics area becomes uninhabitable, relocate Health Physics staff to the OSC or.the Emercency Switchgear Room.
- 1. INITIATE PROCEDURE:
a) Initiated By: Date: Time:
- 2. ESTABLISH COMMUNICATION:
Upon activation of the TSC, O- establish communication by: a) Telephone
- 1) Locate a telephone in H.P. office
- 2) Call the TSC at extension
/
b) Radio b) IJ[ radio does not work or cannot be found, obtain a
- 1) Obtain a portable radio radio from operations or from Health Physics Office security.
- 2) Initiate EPIP-4.19, Use of Radios for Health Physics Monitoring
- 3) Contact the TSC
- 3. PERFORM ACCOUNTABILITY:
a) Perform accountability as e per EPIP 5.03, Personnel Accountability
No.97as7210 NUMBER PROCEDURE TITLE REVISION (, EPIP-4.02 00 v RADIATION PROTECTION SUPERVISOR CONTROLLING PROCEDURE PAGE 3 of 16
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 3. (CONTINUED) b) Report Health Physics readiness to the Radio-logical Assessment Director
- 1) Report the number of H.P.
personnel onsite
- 4. DETERMINE PLANT STATUS:
a) Request briefing with Radiological Assessment Director as to: j 1) Emergency classification v
- 2) Plant status
- 3) Assistance required
- 5. ESTABLISH DOSE CONTRCL:
a) Insure individual is avail-able at dose control station b) IF_ dose control station be- b) E dose control is habitable, comes uninhabitable consider GO TO Step 4.c. relocation to the OSC: l
- 1) Insure adequate supply of
[ I dosimeters are available AND i l 2) Relocate, if necessary, j dosimetry processing equip-ment l c) Request dose control indivi-l dual to maintain exposure O records and issue dosimetry l h as per normal H. P. procedures l
No. 97887230 NUMBER PROCEDURE TITLE REVISION EPIP-4.02 00 RADIATION PROTECTION SUPERVISOR CONTROLLING PROCEDURE PAGE 4 of 16
- STEP - ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 6. ACTIVATE INPLANT MONITORING:
IF need for inplant monitoring IF inplant monitoring tec;ms NOT determined: required, GO TO NOTE prior to Step 6. a) Request from Radiological Assessnent 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 m
\
c) Assign EPIP-4.14, Inplant Monitoring
- 1) Select 2, individuals
- 2) Only 1 individual must be a H.P. technician t d) Advise monitoring team as
! to the location and surveys required e) Determine protective gear required:
- 1) Respirators
- 2) Protective clothing
- 3) Dosimetry f) Suggest routes of entry that may reduce exposure i
No. 97847210 NUMBER PROCEDURE TITLE REVISION [ EPIP-4.02 00 v RADIATIOli PROTECTION SUPERVISOR CONTROLLING PROCEDURE FAGE 5 of 16
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED -
- 6. (CONTINUED) g) Consider use of portable g) IF NO radios are available radios for Inplant Monitor- GO TO Step 6.h.
ing Teams h) Dispatch team (s) i) Upon receipt of survey information, transmit data to the Radiologi-cal Assessment Director NOTE: Onsite monitoring teams should be dispatched upon Alert (^'h classification, as specified by Radiological Assessment (,,/ Director.
- 7. ACTIVATE ONSITE MONITORING:
IF need for onsite monitoring IF onsite monitoring NOT re-is determined: quired, GO TO Step 7 l a) Request from Radiological Assessment Director the location of desired moni-toring and the surveys re-quired b) Request from the Radiological Assessment Director assessment l of radiological hazards in area of requested surveys
- 1) F air samples required, obtain vehicle to power portable air sampler c) If transportation is required assist in obtaining a vehicle (OuJ
No. 978 87210 NUMBER PROCEDURE TITLE REVISION 19 EPIP-4.02 00 h RADIATION PROTECTION SUPERVISOR CONTROLLING PROCEDURE FA6E 6 of'16
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED --
- 7. (CONTINUED)
- 1) _IF F necessary, request assistance from Radio-logical Assessment Director d) Assign EPIP-4.15, Onsite Monitoring e) Select 2 individuals per team only l_ need be a H.P.
technician f) Determine protective gear required: N.
- 1) Respirators
- 2) Protective clothing
- 3) Dosimetry g) Dispatch monitoring team (s) h) I_F radios are available, h) Continue with this in-establish radio communication struction IF radios.NOT monitoring team (s) available.
- 1) Upon receipt of survey results, transmit data to Radiological Assessment Director
- 8. ESTABLISH ACCESS CONTROL:
a) Based on survey (s) and/or a) I_F F emergency NOT radiological briefing with Radiological in nature: Assessment Director concern-ing radiological event: 1) Normal station access control to be followed (v\
Peo. 97887210 NUMBER PROCEDURE TITLE REVISION
-s -
) EPIP-4.02 00 PADIATION PROTECTION SUPERVISOR CONTROLLING PROCEDURE FA6E 7 of 16
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINEO
- 8. (CONTINUED)
AND
- 2) GO TO Step 8.
- 1) Establish access control over Auxiliary Building and/or other high radiation or high airborne areas b) Suggested access control limits:
- 1) Airborne contamination GREATER THAN l
s 0.25 E CONCi MPCi SE
- 2) GREATER THAN 1000 dpm per 100 cma S.E l 3) GREATER THAN 1000 mR/hr i
j c) Establish access control by:
- 1) Requiring H.P. notifica-tion prior to entry AND/OR
- 2) Use of Radiation Work Permits as per Section 2 i
of the Health Physics Manual l O. V l
No, 97847210 NUMBER PROCEDURE TITI.E REVISION EPIP-4.02 00 O- RADIATION PROTECTION SUPERVISOR CONTROLLING PROCEDURE FA6E 8 of 16
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED NOTE: Offsite Monitoring Team (s) should be dispatched spon classification of SITE or GENERAL emergency, as specified by the Radiological Assessment Director.
- 9. ACTIVATE OFFSITE MONITORING:
a) Review with Radiological Assessment Director:
- 1) Need for offsite moni- 1) E offsite monitoring toring teams NOT required, GO TO Step 9-
- 2) Initial location and number of offsite teams required
( )4 3) Assessment of offsite radiological hazards b) Assign EPIP-4.16, Offsite Monitoring c) Select 2 individuals per team: l 1) Only 1,need be a H.P. technician d) Assist in obtaining a vehicle
- 1) Health Physics truck
, 2) Station Manager's car i l
- 3) Assistant Managers car
- 4) Superintendent Operations car l
O i l
No.97887210 NUMBER PROCEDURE TH'LE REVISION
\ EPIP-4.02 00 RADIATION FROTECTION SUPERVISOR CONTROLLING PROCEDURE PAGE 9 of 16
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 9. (CONTINUED) e) Assign an emergency kit:
- 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 reporting location g) Review protective gear (x required:
- 1) Respirator gear
- 2) Protective clothing
- 3) Dosimetry h) Dispatch monitoring team
- 10. INITIATE TSC/OSC/ EOF MONITORING:
a) Upon ALERT emergency establish I monitoring of emergency response centers b) Determine frequency of l monitoring based upon:
- 1) Spread of contamination from service buildings
! 2) Increase oft decrease of effluent release I l b s/s 1
Pto. 97887210 NUMBER PROCEDURE TITLE REVISION O EPIP-4.02 00 RADIATION PROTECTION SUPERVISOR CONTROLLING PROCEDURE PACE 10 of 16
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 10. (CONTINUED)
- 3) Increase in emergency classification
- 4) Change in plume direction c) Assign
- 1) EPIP-4.17, Monitoring of OSC and TSC AND
- 2) EPIP-4.18, Monitoring of EOF d) Inform Rad ological Assess-ment Director as to the habitability of emergency response centers
- 11. CONTAMINATED PERSONNEL:
a) E station personnel found a) IF no station personnel contaminated: found contaminated, GO TO Step H.
- 1) Assign EPIP-4.06, Personnel Monitoring and Decontamination AND
- 2) Report results to Radiological Assessment Director NOTE: IF injury is life threatening, GO TO Step ll.d.
O v
Peo. 9788723 0 NUMBER PROCEDURE TITLE REVISION EPIP-4.02 00 ss RADIATION PROTECTION SUPERVISCR CONTROLLING PROCEDURE PAGE 11 of 16
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 12. CONTAMINATED INJURED PERSONNEL:
E an individual is injured IF individual is NOT found to be and requires transportation contaminated, GO TO Step H. offsite: a) Review personnel survey (s) b) Insure decontamination prior to transportation NOT practical c) Inform Radiological Assessment Director of need to transport contaminated personnel d) Assign EPIP-4.20, H.P. \.s Actions for Transportation of Contaminated Injured Individual
- 1) Select a technician to accompany victim
- 2) Supply technician with copy of EPIP-4.20
- 3) Supply technician with portable survey instru-ment (s) e) Upon arrival of ambulance, dispatch a technician to issue dosimetry f) Inform Radiological Assess-ment Director upos departure of ambulance
- 13. EVACUATION MONITORING:
a) IF evacuation alarm sounds a) Continue with this instruc-
^- Ethout prior notification tion.
of pending evacuation, GO TO Step 12.d
t No. 97087210 NUMBER PROCEDURE TITLE REVISION
) EPIP-4.02 00 Nd RADIATION PROTECTION SUPERVISOR CONTROLLING PROCEDURE E46f 12 of 16 7
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 13. (CONTINUED) b) )); informed by the Radio- b) )); evacuation of the station logical Assessment Director is not eminent, GO TO Step of a pending evacuation 13.
- 1) Dispatch, if necessary, onsite monitoring team to the parking lot (s) to determine radiation and contamination levels <
ec) Report results of survey to the R1diological Assessment ? Director - d) Assign EPIP-4.21, Evacu-f' ation and Remote Assembly Area Monitoring e) Assist in obtaining trans-portation of team OR arrange transportation with security f) Inform Radiological Assess-ment Director when team dispatched
- 14. POST ACCIDENT SAMPLING:
a) )); notified by Radiological a) ))[ post accident sampling Assessment Director of need Containment Air and/or for post accident contain- Reactor Coolant NOT required, ment and/or reactor coolant GO TO Step 14. sample:
- 1) Perform in-plant survey to determine dose rate at sample station
- 2) Inform Radiological
['h \m-Assessment Director results of survey
- y. - . -
/ .; > r 1
No. o re s7220 i (s c z (!I ' + ll. NbMJift , PROCEDURE TITLE REVISION
$2IP-4'.0$ s 00 d -
RADIATION PROTECTICh SUPERVISCR t, CONTROLLING PROC.2DURL , FACE 1 i
- i. 13 of 16 is \ )
Y ( l z_ \
' - ACTIONfEAPECCD RESPONSE STEP .f- ,
(( - RESPONSENOT CBTAINED 6 / 'J
+
1
\, x
- 14. . (CONTINUED).
e '
\ .
- 3) Initiiate preparation ofs RWP
- 4) Assign EPIP-4.22, M Accident Sampling of Centain-ment Air , ,;
i t AND/OR , EPIP-4.22, Post Accident [ , Sampling of Reactor Coolant i
- 5) Supply Health Physics I: overage during sampling and sample preparation tv
- 15. SAMPLE ANALYSIS:
a) Upon receipt of sample a) IF sample analysis data NOT analysis data requested by received, GO TO Step M. Radiological Director 4 AND OR Report analysis to Radio-Receipt of abnormal or logical Assessment Director unexpected analysis data when available. s
- 1) Report results it: mediately to the Radiologiral Assess- ,
ment Director i 16. ASSESS !GNPOWER: a) When time all ws, determine a) E time is not currently need for relief shift and/or available, assign scheduling increase in manpower to other H.P. personnel l - l \ Assess at a later time, I 'h 1 l ((
%d
)
i l
No. 978 ??210 NUMBER PROCEDURE TITLE REVISION EPIP-4.02 00 V RADIATION PROTECTION SUPERVISOR CONTROLLING PROCEDURE PAGE 14 of 16 f STEP ACTION /EXFECTED RESPONSE RESPONSE NOT OBTAINED
- 16. (CONTINUED)
AND
'GO TO Step 16.
- 1) Discuss with Radiological Assessment Director, pro-jected duration of emergency
- 2) Determine need for in-creased manpower
- 3) Develop relief schedule and/or increased staffing schedule i
h 4) Present schedule to Radiological Assessment Director for approval
- 5) IP approved, activate 5) E NOT approved, GO TO callout of scheduled Step 16.
personnel
- 6) Upon completion of callout, inform Radio-logical Assessment Director
- 17. RELIEF OF SHIFT:
a) E a more senior H.P. a) GO TO Step 17. individual M relief arrives:
- 1) Brief successor as to the plant conditions AND Health Physics actions underway a
v
Ns.97887210 NUMBER PROCEDURE TITLE REVISION
/-~ EPIP-4.02 00 RADIATION PROTECTION SUPERVISOR CONTROLLING PROCEDURE
^'
15 of 16
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 17. (CONTINUED)
- 2) Announce change of pos-ition to the Radiological Assessment Director
- 3) Remain with new Super-visor for approximately 30 minutes
- 38. CONTINUE ASSESSMENT:
a) IF emergency condition still a) IF Radiological Assessment exists: Director declares termina-tion of Emergency, GO TO I h Step ~18~ A- 1) Return to Step 4,
- 2) Direct repetition of survey (s) and sampling, as necessary, 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 v I l
. _ _ - ,a;
No. 97887210 NUMBER PROCEDURE TITLE REVISION EPIP-4.02 00 Q RADIATION PROTECTION SUPERVISOR PAGE CONTROLLING PROCEDURE 16 of 16
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 20. ADMINISTRATION:
a) Forward all completed or partially completed pro-cedures, notes, sample results and surveys to the Radiological Assess-ment Director
- 21. TERMINATE EPIP-4.02:
a) Completed By: Date: Time: O END O
No.97887230 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCEDURE TITLE REVISION 00 EPIP-4.03 DOSE ASSESSMENT CONTROLLING PROCEDURE PAGE (With 4 Attachments) 1 of 11 PURPOSE Provide Dose Assessment Personnel guidance in calculating percent of Technical Specifications _OR dose rates and projected dose, due to radioactive release. USER Dose Assessment Team Leader OR Radiological Assessment Director ENTRYCONDITIONS 4 p Activation by EPIP-4.01, Radiological Assessment Director Controlling () Procedure. I l l 1 REVIS10N RECORD l REV. 00 PAGE(S): Entire Procedure DATE: JUL 2 9 1982 REV. PAGE(S): DATE:
-REV. PAGE(S): DATE:
REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: l REV. PAGE(S): DATE: APPROVAL RECOMMENDEO APPROVED DA TE
. dr -
M s g_ JUL 2 9 1982 C A RMANSTATIONNUCLEARSAFETY AND OPERA TING COMMITTEE
Ns.s7ss721e NUMBER PROCEDURE TITLE REVISION 00 EPIP-4.03 DOSE ASSESSMENT CONTROLLING PROCEDURE PAGE 2 of 17
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
(
- l. INITIATE PROCEDURE:
a) BY: DATE: TIME:
- 2. REQUEST BRIEFING:
a) Request briefing with the Radiological Assessment Director as to:
- 1) Emergency classification
- 2) Initial offsite release O5 calculations
- 3) Current monitor readings
- 4) Current meteorological data
- 3. DETERMINE EMERGENCY CLASSIFICATION:
a) IF the emergency is an a) IF the emergency is a SITE UNUSUAL EVENT O_R, R ALERT: or GENERAL:
- 1) Continue with this instru- 1) GO TO Step 4_.
crion b) Obtain a sample from the b) IF a sample NOT available: effluent pathway
- 1) Use a monitor reading to assess release
- 2) Initiate EPIP-4.08, Initial Offsite Assess-ment
- 3) Assess percent Tech Spec AND
- m. siss721e NUMBER PROCEDURE TITLE REVISION 00 O. -
EPIP-4.03 DOSE ASSESSMENT CONTROLLING PROCEDURE - PAGE 3 of 17 ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED f STEP
- 3. (CONTINUED)
- 4) Return to Step 3,of this procedure c) Initiate EPIP-4.13, Follow-up Offsite Release Assessment
- 1) Assess percent of Tech Spec AND
- 2) Return to Step 3.d d) IF percent of Tech Spec d) IP percent of Tech Spec
[O. I1mit LESS THAN 1004: E mit GREATER THAN 1004:
- 1) GO TO Step E 1) GO TO Step 3.e.
e) E percent of Tech Spec e) IF percent of Tech Spec LESS THAN 10004: GREATER THAN 1000%:
- 1) Confirm / Recommend UNUSUAL 1) Confirm / Recommend an EVENT emergency ALERT emergency l
- 2) GO TO Step 3.f f) Report results to Radiological Assecsment Di'.ector g) If, emergency - ALERT g) IF emergency - UNUSUAL EVENT
- 1) GO TO Step NOTE prior to Step 4, 1) GO TO Step 3.h h) IP release NOT terminated h) E release terminated:
- 1) Repeat Step 3.a thru Step 3.h 1) GO TO Step E.
ND.97887213 NUMBER PROCEDURE TITLE REVISION p- 00 h EPIP-4.03 DOSE ASSESSMENT CONTROIIING PROCED.URE F E 4 of 17
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTCBTAINED NOTE: A minimum of 2 offsite monitoring teams should be dispatched on classification of SITE OR GENERAL emergency.
- 4. DETERMINE NEED FOR OFFSITE MONITORING:
a) IF manpower is available a) E manpower NOT available: 9.E I_F teams have already been dispatched: ( 1) Discuss with the Radio- 1) GO TO NOTE prior to Step t logical Assessment Director 6 the need for offsite monitoring b) E Offsite Monitoring Teams b) IF Offsite Monitoring Teams to be dispatched, review NOT required, GO TO NOTE the following with the Radio- prior to Step 6_ logical Assessment Director:
- 1) Meteorological conditions
- 2) Offsite Dose Projection
- 5. ASSIGN RADIOPHONE OPERATOR a) Request from the Radiological a) IF no individual is avail-Assessment Director to assign: able:
- 1) Individual to man the 1) GO TO Step 3.c radiophone AND Assist as Dose Assessment team member O-
Po.978t?213 NUMBER PROCEDURE TITLE REVISION 00 Oi EPIP-4.03 DOSE ASSESSMENT CONTROLLING PROCEDURE PAGE 5 of 17
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 5. (CONTINUED)
~
b) Brief Dose Assessment Team member on initial location of mor.itoring teams c) Initiate or Assign EPIP-4.12, Offsite Environmental Monitoring Instructions, AND EPIP-4.13, Offsite Release Assessment with Environmental Data, \ v
- 1) Assist, as necessary, establishment of communi-cations and the placement of the teams at desired location NOTE: If wind shift occurs during offsite releases, re-evaluate offsite releases, and log results, using a new form for Attachment 2.
- 6. OFFSITE DOSE ASSESSMENT:
a) IF offsite dose assessment a) IF offsite dose assessment required: NOT required (i.e., emer gency did NOT result frot
- 1) Initiate EPIP-4.09, source actual or potential radio-Term Assessment active release)
- 2) Determine source term m
(C1/sec) 1) GO TO Step 15.
No. 97887213 NUMBER PROCEDURE TITLE REVISION O EPIP-4.03 DOSE ASSESSPINT CONTROLLING PROCEDURE 00 PAGE 6 of 17
- STEP ACTION / EXPECTED RESPONSE .
RESPONSE NOTOBTAINED
- 6. (CONTINUED)
- 3) Return to Step 6.b b) Log on Attachment 1 c) Determine time (seconds) since start of release from the Emergency Communicator O_R Since previous assessment, from Attachment 1
- 1) Perform following to O
Q determine equivalent curies I-131 and Xe-133, released: TIME (seconds) x r7 LEASE RATE (Ci/sec) = CURIES
- 2) Iog equivalent curies on Attachment 1
- 3) Determine iodine - xenon ratio AND
- 4) Log on Attachment 1 l d) Initiate EPIP-4.10, X/Q Deter-mination and obtain:
l l 1) X/Q at Site Boundary
- 2) Stability class
[
- 3) Wind Speed (mph) _
AND __ O
- 4) Log on Attachment 2 l
N3.97187219 NUMBER PROCEDURE TITLE REVISION O 00 h EPIP-4.03 DOSE ASSESSMENT CONTROLLING PROCEDURE PAGE 7 of 17
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 6. (CONTINUED) e) Initiate EPIP-4.11, Follow-up Offsite Release Assessment and obtain:
- 1) Site Boundary dose rate -
Whole Body and Thyroid AND
- 2) Return to Step 6.e.3 of of this procedure
- 3) Log date, time and dose rate on Attachment 2
[ (,j 7. DETERMINE INTEGRATED DOSE: a) Obtain time from Step 6.b:
- 1) Convert time to hours b) Perform the following:
TIME x DOSE RATE + Previous = INTEGRATED (hours) (mR/hr) Integrated Dose DOSE c) Log on Attachment 2 l
- 8. DETERMINE TOTAL PROJECTED DOSE:
l a) Obtain from Radiological a) Assume 3, hours Assessment Director IF NO estimate is given
- 1) Estimated duration of l release (hours) from current period of time b) Obtain projected dose rate Whole Body and Thyroid from y Step 6.e.
No.9788721e NUMBER PROCEDURE TITLE REVISION 00 EPIP-4.03 DOSE ASSESSMENT CONTROLLING PROCEDURE PAGE 8 of 17
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED 8.
(CONTINUED) c) Determine projected dose Whole Body and Thyroid: DURATION RELEASE x DOSE RATE + INTEGRATED DOSE = TOTAL PROJECTED DOSE
- 1) Log results on Attachment 2.
- 9. DETERMINE OFFSITE DOSE RATE, INTEGRATED AND TOTAL PROJECTED DOSE AT 2, 5 AND 10 MILES
( a) Obtain from Step 6,the i m st current: ! 1) Stability class l 2) Site Boundary dose rate - Whole Body and Thyroid AND
- 3) Log dose rate on Attachment l
- 4 l
b) Determine the conversion l factor from Attachment 3 , l for distance of 2, 5_ and H miles c) Determine dose rate for 2, 5 and 10 miles SITE BOUNDARY DOSE RATE x CONVERSION FACTOR = DOSE RATE (mR/hr) d) Log results on Attachment 4 l D2 V
l Ns.97ss721e l NUMBER PROCEDURE TITLE REVISION 00 O EPIP-4.03 DOSE ASSESSMENT CONTROLLING PROCEDURE P E I 9 of 17
- STEP ACTION / EXPECTED RESPONS.~ RESPONSE NOT08TAINE0 ,
- 9. (CONTINUED) e) Repeat Steps 9.a thru 9.e for:
- 1) Irtegrated dose AND
- 2) Total projected dose f) Determine plume arrival time:
- 1) Determine current wind speed (mph) from Step 6.d U 2) Determine arrival time for 2, 5 and 10 miles by the following:
CURRENT TIME OF DAY + DISTANCE (2, 5 or 10 Miles) = TIME OF WIND SPEED (mph) ARRIVAL
- 3) Log on Attachment 4
- 10. DOSE RATE, INTEGRATED AND PRO-JECTED DOSE AT OTHER DISTANCES a) IJF dose rates, integrated and/ a) E data is NOT requested or Projected Doses - re- at distances other than 2, quested at distances other 5 or 10 miles, GO TO Step than 2, 5, or 10 miles: H.
j b) Initiate EPIP-4.10 to determine X/Q for:
- 1) Site Boundary
- 2) Distance ether than 2, 5, or 10 miles
- 3) Return to Step 11.c
No. 97887210 NUMBER PROCEDU
- TITLE REVISION 00 EPIP-4.03 DOSE ASSESSMENT CONTROLL.NG PROCF"JRE PAGE 10 of 17
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED 10.
~
(CONTINUED) c) Obtain from Step 6_ the. Site Utandary Dose Rate d) Determine dose rate for dis-tance of interest: , SITE BOUNDARY X/Q (distance of interest) DOSE RATE DOSE RATE X/Q (site boundary) Idistanceofinterest) e) Log on Attachment 4 f) Repeat Steps 10.a thru 10.e ('y using Site Boundary Integrated Dose and Total Projected Dose g) Determine plume arrival time:
- 1) Determine current wind speed (mph) from Step 6.d.
- 2) Determine arrival time for distance other than 2, 5 OR 10 miles by the following:
l l CURRENT TIME OF DAY + DISTANCE = TIME OF l WIND SPEED (mph) ARRIVAL
- 3) Log on Attachment 4.
- 11. DETERMINE DISTANCE FOR PROTECTIVE MEASURES a) _IF, Site Boundary projected dose a) IF Site Boundary projected is GREATER THAN 0.5 Rem Whole dose is LESS THAN g Body EQUAL TO 0.5 Rem Whole l Body v
No.97487233 NUMBER PROCEDURE TITLE REVISION 00 EPIP-4.03 DOSE ASSESSMENT CONTROLLING PROCEDURE PAGE 11 of 17
- STEP ACTION / EXPECTED RESPONSE RESPONSENOT OBTAINED
- 11. (CONTINUED)
AND/OR OR GREATER THAN 1.0 Rem Thyroid: LESS THAN OR EQUAL TO 1.0 Rem Thyroid
- 1) Continue with this instruction 1) GO TO Step 12.
b) Obtain from Attachment 2:
- 1) X/Q at Site Boundary
- 2) Wind Speed
- 3) Stability Class d
AND
- 4) The projected dose, Whole Body and Thyroid, at the Site Boundary c) E Site Boundary Whole Body c) GO TO Step 11.d dose GREATER THAN 0.5 Rem:
+
- 1) Determine of interest X/Q* at distance X/Q* = 500mR x X/Q at Site Boundary x Wind Speed Site Boundary Dose (Whole Body)
- 2) Refer to EPIP 4.10, Attach-ment 1 AND
- 3) Determine approximate distance (miles)
- 4) Log distance for Site Emergency on Attachment 4
(%-)
ro.e7ss72 e NUMBER PROCEDURE TITI.E REVISION 00 EPIP-4.03 DOSE ASSESSMENT CONTROLLING PROCEDURE PAGE 12 of 17
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 11. (CONTINUED)
- 0) E Site Boundary Thyroid dose d) g T_O O Step 11.e GREATER THAN 1.O Rem:
- 1) Determine of interest:
X/Q* at distance X/Q* = 1000 mR x X/Q at Site Boundary x Wind Speed Site Boundary Dose (Thyroid) j 2) Refer to EPIP 4.10, Attach-ment 1 s M b 3) Determine approximate distances (miles) , 4) Log distance for Site Emergency on Attachment 4. e) IF Site Boundary whole Body e) GO TO Step ll.f. dose is GREATER THAN 2.0 , Rem:
- 1) Determine of interest:
X/Q* at distance X/Q* = 2000 mR x X/Q at Site Boundary x Wind Speed Site Boundary Dose
- 2) Refer to EPIP-4.10, Attach-ment 1 AND
- 3) Determine approximate distance (miles)
- 4) Log distance for General Emergency on Attachment 4 l
--,-n- - -
-9v--- -w,a , e-,- -
,me m --,<y me - , - - , , , ,-g -,,,,yy.w-,-vm.,---- ew --
N4.97!87219 NUMBER PROCEDURE TITI.E REVISION 00 EPIP-4.03 DOSE ASSESSMENT CONTROLLING PROCEDURE PAGE 13 of 17
- STEP ACTION / EXPECTED RESPONSE RESPONSENOT OBTAINED
~
- 11. (CONTINUED) f) IF, Site Boundary Thyroid f) GO TO Step 12 dose GREATER THAN 12.0 Rem:
- 1) Determine X/Q for distance of interests x/Q* = 12,000 mR x X/Q at Site Boundary x Wind Speed Site Boundary Dose
- 2) Refer to EPIP-4.10, Attach-ment 1 AND
- 3) Determine approximate w/ distance (miles)
- 4) Log distance for General Emergency on Attach ment 4 l 12. RELAY DATA TO RADIOLOGICAL ASSESSMENT DIRECTOR:
a) Complete Attachment 4 with:
- 1) Date
- 2) Time
- 3) Sector affected AND b) Indicate whether Offsite Assessment was done using a monitor reading or sample analysis c) Relay the completed Attachment 4 to the Radiological Assess-ment Director I
---r- - . - -. - _, -_ ,
No.s7ss721e NUMBER PROCEDURE TITLE REVISION
) 00 w/ EPIP-4.03 DOSE ASSESSMENT CONTROLLING PROCEDURE PAGE 14 of 17
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED 13 ASSESS RELOCATION OF MONITORING '
TEAMS (S): a) E Monitoring team (s) are a) IF monitoring team (s) are in the field, review data NOT in the field, GO TO from Attachment 4 Step 15. b) Select a specified distance, dose rate and time from Attachment 4 c) Relocate Monitoring Team (s) to distance specified in Step 13.b and have team relay reading at time of plume arrival
- 1) Inform Dose Assessment Team Member AND
- 2) Assist in relocation of teams
- 14. COMPARE PROJECTED TO ACTUAL OFFSITE DOSE:
a) Obtain from the Dose Assess- a) IF offsite data is NOT ment Team Member the current available, GO TO Step M. Offsite Monitoring Data b) Obtain projected dose rate at the distance specified, from Step 13.b c) Compare dose rates from above Steps 14.a and 14.b l d) E data is significantly d) IF the actual and projected i different: data correlate, GO TO Step M-
)
--_.~- _ _ _ ,
ND.9788M30 NUMBER PROCEDURE TITLE REVISION 00
's / EPIP-4.03 DOSE ASSESSMENT CONTROLLING PROCEDURE PAGE 15 of 17
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 14. (CONTINUED)
- 1) Notify Radiological Assessment Director as to i the difference between actual and projected dose rates
- 2) Determine which set of data is to be used for dose
- projections
- 15. CONTINUE ASSESSMENT:
a) IF EOF is NOT manned a) IF EOF is manned GO TO Step 16, O. O,R OR E the radiological release OR potential release has NOT IF release OR potential terminated: release has teraineted GO TO Step 17.
- 1) Continue with Steps 6_ thru 15,
- 16. EOF MANNED:
a) Brief Radiological Assess-ment Coordinator at the EOF on: _
- 1) All current offsite dose projections to date AND
- 2) Status of offsite monitor-ing teams x
ND. 97087219 NUMBER PROCEDURE TITLE REVISION O V EPIP-4.03 DOSE ASSESSMENT CONTROLLING PROCEDURE 00 PAGE 16 of 17
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 16. (CONTINUED) -
b) Inform the Dose Assessment b) IF radio contact can NOT Team Member to: be established:
- 1) Instruct the Offsite 1) Continue contact with Monitoring Teams to monitoring teams establish radio contact with the EOF AND
- 2) Relay information from c) Instruct the Dose Assessment the teams to the EOF Team Member to maintain contact with the EOF relaying the following information received from the Radiological
[ h Assessment Director U
- 1) Meteorological data
- 2) Monitoring data
- 3) Sample rnalysis data d) Report readiness to the Radiological Assessment Director:
- 1) Continue with this instru-ction
- 17. ADMINISTRATION:
a) Gather all procedures, Attachments and sample analysis records AND Present to the Radiological Assessment Director ____ Os O
N3.97BS7210 NUMBER PROCEDURE TITLE REVISION 00 EPIP-4.03 DOSE ASSESSMENT CONTROLLING PROCEDURE PACE 17 of 17
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 18. TERMINATE EPIP-4.03:
a) Completed By: Dater Time: 1 END
Ns. ores 722o l NUMBER
% A TTACHMENT TITLE REVISION i EPIP-4.03 00 OFFSITE RELEASE A TTACHMENT WORKSHEET PA GE l 1 1 of 1 l 1
l l i I-131 Xe-133 CURIES RELEASED I/Xe DATE TIME Ci/sec Ci/sec I-131 Xe-133 RATIO i O O f
au. . _ . _ _ . . - m a c . m _- _ = a No. 91887220 1 NUMBER A TTACHMENT TITLE REVISION EPIP-4.03 00 A TTACHMENT OFFSITE RELEASE PAGE 2 WORKSHEET 1 of 1 SITE BOUNDARY - WHOLE BODY WIND STABILITY INTEGRATED PROJECTED DATE TIME X/Q SPEED CLASS DOSE RATE DOSE DOSE (W.B) (THY) l (W.B) (THY) (W.B) (THY) (W.B) (THY) l (W.B) (THY) (W.8) (THY) (W.B)
- (THY) l (W.B)
(THY)
\ .
4
.,,.--.,.---y. , - - , , ,,.-----,i - - - - - ~ - , - - -,-r. c.e- -m-.-e----,we ..n .e.-,-,--m---e,.,,w,yv- , , - - ., +-----m<. .e . - , ,
No.97887220 NUMBER A TTACHMENT TITLE REVISION EPIP-4.03 00
\d X/Q MULTIPLICATION FACTOR A TTACHMENT PAGE
, 3 1 of 1 l STABILITY CLASS Distance A B C D E F G Miles l 2 1.37E-2 1.12E-2 4.27E-2 6.37E-2 8.33E-2 1.28E-1 2.38E-1 h 5 6.02E-3 2.36E-3 8.84E-3 1.59E-2 2.42E-2 3.74E-2 7.79E 2 l l i l 10 3.11E-3 1.24E-3 2.80E-3 5.84E-3 1.00E-2 1.55E-2 3.24E-2 l l 0
Na.97887220 NUMBER A TTACHMENT TITLE REVISION N EPIP-4.03 00 CURRENT OFFSITE RELEASE A TTACHMENT HORKSHEET PAGE 4 1 of 1 DATE TIME SECTOR PROJECTED BY: MONITOR:
~
SAMPLE: WHOLE BODY SITE BOUNDARY 2 5 10 OTHER DOSE RATE INTEGRATED DOSE PROJECTED DOSE TIME OF ARRIVAL MILES SITE MILES GENERAL THYROID ' SITE BOUNDARY 2 5 10 OTHER DOSE RATE INTEGRATED DOSE PROJECTED DOSE TIME OF ARRIVAL .I MILES SITE MILES GENERAL O
No.97887230 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCEDURE TITLE REVISION 00 EPIP-4.04 EMERGENCY PERSONNEL RADIATION EXPOSURE PACE (With 3 Attachments) 1 of 6 PUHPOSE Provide to the Emergency Manager an evalution of the need for authorization of emergency exposure USER Radiological Assessment Director ENTRYCONDITIONS Any one of the following conditions exist:
- 1. Activation by another EPIP.
- 2. Survey results indicate 10CFR20 quarterly limits may be exceeded.
REVISION RECORD REV. 00 PAGE(S): Entire Procedure DATE:JUL 2 9 1982 l REV. PAGE(S): DATE: REV. PAGE(S): DATE: ( REV. PAGE(S): DATER l REV. PAGE (S) : DATE: REV. PAGE(S): DATE: ! REV. PAGE(S): DATE: APPROVAL RECOMMENDED APP OVED DA TE fA L 3W
>%E. N-IRMAN ST, TION NUCcEAR S,,ETY AND OPERA TING COMMITTEE n
No. 97887210 NUMBER PROCEDURE TITLE REVISION EPIP-4.04 EMERGENCY PERSONNEL RADIATION EXPOSURE PAGE 2 of 6
- STEP ACTION / EXPECTED RESPONSE RESPONSENOT OBTAINED l
- 1. INITIATE PROCEDURE:
a) Initiated By: f Date: Time:
- 2. ASSESS NEED FOR EMERGENCY EXPOSURE:
a) Assess need for exposure a) IF, exposure will NOT exceed GREATER THAN 10CFR20 quarterly 10CFR20 quarterly limits, limits: GO TO Step 12,.
- 1) Review Attachment 1 q ,/ b) Lifesaving
- 1) Search, rescue and re-moval of injured
- 2) Perform first aid
- 3) Entry to correct con-ditions that could, if unrepaired, result in onsite or offsite i injury c) Damage repair or corrective actions
- 1) Save valuable equipment
- 2) Limit offsite releases NOTE: Minimize exposure to monitoring personnel while obtaining sufficient data to estimate exposure.
C (
no. s7ssnte NUMBER PROCEDURE TITLE REVISION
/ 00 C EPIP-4.04 EMERGENCY PERSONNEL RADIATION EXPOSURE DAGE 3 ot 6
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 3. ASSESS ESTIMATED DOSE:
a) Request from Emergency Manager destination of emergency workers b) Determine length of expos-ure time c) Assess dose rate:
- 1) Area radiation monitor
- 2) Survey - Assign EPIP-4.14, Inplant Monitoring d) TOTAL DOSE = EXPOSURE TIME x DOSE RATE ,
( e) IF total dose - GREATER THAN e) IF total dose - LESS THAN 3 Rem, continue with this 3_ Rem, GO TO Step H. instruction
, 4. INSURE INITIATION:
a) Notify Emergency Manager to initiate EPIP-5.06, Emer-gency Radiation Exposure Limits
- 5. REVIEW EMERGENCY DOSE LIMITS:
I l a) Review attachment 1,for emergency exposure limits
- 6. ASSESS NEED FOR IMMEDIATE ACTION:
Consider the following prior l to authorization: a) Lifesaving actions:
No. 97887210 NUMBER PROCEDURE TITLE REVISION
/"N 00 EPIP-4.04 EMERGENCY PERSCNNEL RADIATION EXPOSURE PAGE 4 of 6
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 6. (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 9.E Ventilation of building Ch O 9LR Establishment of shielding
- 7. RECOMMEND EMERGENCY EXPOSURE:
a) Review with Emergency Man-ager alternatives available b) Insure with dose control b) IF individual previously that individual has NOT received emergency exposure, received once in a life- deny authorization. time exposure c) Submit recommendation to j the Emergency Manager NCfrE Emergency Manager may, at his discretion, wave requirements for Radiation Work Permit prior to entry and give verbal authorization. NOTE: Unless considered necessary, monitoring personnel should not remain in high exposure area.
_m.. - - . I N3.97887210 NUMBER PROCEDURE TITLE . REVISION 00 EPIP-4.04 EMERGENCY PERSONNEL RADIATION EXPOSURE PAGE 5 of 6
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINEO
- 8. PROTECTIVE ACTIONS a) Entry requires Radiation
[ Work Pezult b) Insure workers receive:
- 1) Proper protective clothing
- 2) Dosimetry capable of 4 measuring expected dose
- 3) Respiratory protection, if necessary
- 4) Instrumentation capa-ble of reading radia- ,
tion levels of up to 1000 R/hr c) If possible, direct workers to route of entry of lowest exposure d) Provide Health Physics coverage
- 9. REVIEW EXPOSURE EFFECTS:
a) IF time permits, Review Attachment 2, Radiation Effects Versus Whole Body Expos'tre, with volunteers
- 10. EMERGENCY EXPOSURE FORM:
a) Comp 1.ete the emergency
, worker Radiological l Exposure Record on
-l Attachment 3 l e >--.--y._- --- --
- - , ~ - , - . . - - ~ . . ..n.,.. , , , - . . _ .. --- - - w,- , , , - - - - - - - - - r - --
No.97887210 NUMBER PROCEDURE TITLE REVISION
\ 00 d EPIP-4.04 EMERGENCY PERSONNEL RADIATION EXPOSURE PAGE 6 of 6
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 10. (CONTINUED) b) IP large part of emergency b) GO TO Step 11.
exposure received:
- 1) Consider exposure once in lifetime exposure AND
- 2) Exclude from further expo-sure
- 11. FOLLOW UP ASSESSMENT:
a) IF in..tidual received a) Continue with this instruc-FREATE? THAN H Rem tion
- 1) Recommend evacuation to MCV
- 12. ADMINISTRATION:
a) Complete Attachment 3 b) Forward copy of Attachment 3 to Emergency Manager . c) Place the original Attach-ment 3 in individual's dose control file
- 13. RETURN TO CONTROLLING PROCEDURE UPON COMPLETION
- 14. TERMINATE EPIP-4.04:
a) COMPLETED BY: DATE: TIME: ElO
/
Ns.97887210 NUMBER A TTACHMENT TITLE REVISION h EPIP-4.04 , 00 A TTACHW'4T 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 75
- 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 bl/cking Os agents are available for rescue personnel. O NRC 10CFR20 QUARTERLY LIMITS
, Whole Body 1.25 Rem 3.00 Rem **
Hands / Feet 18.75 Rem Skin 7.5 Rem i E 5 (N-18) permits
Ns. 97887220 NUMBER A TTACHMENT TITLE , REVISION g EPIP-4.04 00 A TTACHMENT
- PAGE 2 RADIATION EFFECTS VERSUS WHOLE BODY EXPOSURE 1 of 1 EXPOSE EFFECTS 5-25 Rem Change in blood count; changes in chromo-somes of white blood cells; temporary reduction in sperm count.
25-75 Rem Loss of appetite in 19 to 50% of exposed individuals; nausea and fatigue in 1 to 30%; vomiting and diarrhea in 1 to 10% of those exposed; temporary sterility; chromo-somal changes in the skin. 75-100 Rem Increase in the above effects; loss of hair in 10% of exposed individuals; 1 to 5% of O those exposed will die within 60 days. 230-310 Rem 100% incidence of acute effects; 50% of those exposed may die within 60 days. 320-480 Rem 90% of exposed individuals will die within 60 days. 4
, _ _ . . ,...-.c ,y. _. - - , -
! Ns.97807220
- NUMBER ,
A TTACHMENT TITLE REVISION
'EPIP-4.04 00 v A TTACHMENT PAGE 3 EMERGENCY WORKER RADIOLOGICAL EXPOSURE RECORD 1 of 1 ,
1 NAME: AGE: YEARS Last First Mid. Init. J Soc. Sec. No.: _
- Current Quarterly Exposures rem Authorized Emergency Exposures rem Authorized by (Emergency Manager): Names at hours a
Date: 19 SELF-READING DOSIMETER RANGE STARTING READING STOP READING DOSE INTEGRATED BY ROENTGEN R TIME DATE R TIME DATE R DOSE R INIT. i i TLD BADGE NO. NO. CHECK ( ) DOSE INTEGRATED BY ISSUE READ TIME DATE REM DOSE / REM INIT. r--n- - - . - -r --,,-,-v,,n~ .v.- , , - - - . , , - - - ,
No. 978872 30 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCEDURE TITLE REVISION 00 EPIP-4.05 RESPIRATORY PROTECTION PAGE (With 3 Attachments) 1 of 4 PURPOSE Provide guidance for respirator protection. USER Radiological Assessment Director AND/OR Radiation Protection Supervisor. 1 ENTRYCONDITIONS Activation by:
- 1. EPIP-4.01, Radiological Assessment Coordinator Controlling Procedures O_R j 2. EPIP-4.02, Radiation Protection Supervisor Controlling Procedure.
l l REVISION RECORD i REV.PAGE (S) : DATE:JllL 201982 REV.PAGE(S): DATE: REV.PAGE (S) : DATE: REV.PAGE(S): DATE: REV.PAGE (S) : DATE: REV.PAGE (S) : DATE: ! REV.PAGE(S): DATE: l i APPROVAL RECOMMENDED APPROVED DA TE 5A -JUL 2 8 E lHAIRMAN STA TION NUCLEAR SAFETY ANO OPERA TING COMMITTEE i =
No. 97847230 NUMBER PROCEDURE TITLE REVISION 00
.W I EPIP-4.05 RESPIRATORY PROTECTION PAGE 2 of 4
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 1. INITIATE PROCEDURE:
a) Initiated By: Date: Time:
- 2. DETERMINE NEED FOR RESPIRATORY PROTECTION:
a) Consider use of respiratory a) W respiratory protection protection, if entering areas: deemed unnecessary, GO TO Step 7
- 1) htere high airborne concen-3 trations suspected 1
BUT Concentrations NOT verified gR
- 2) Monitoring indicates air GREATER THAN 25% of MPC using the relationship of:
E CONCi PSCi
- 3) Noxious gases or oxygen deficient air are present NOTE: Fuel melt situations may produce a large amount of beta and/or alpha-emitting contaminants not normally seen by analysis.
O l
No. 9 7887230 NUMBER PROCEDURE TITLE REVISION O 00 EPIP-4.05 RESPIRATORY PROTECTION PAGE 3 of 4
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 3. SELECT PROPER RESPIRATOR:
a) Assess respiratory hazards of area to be entered b) Review Attachment 1 to determine respirator type c) IF MPC man hours are to c) IF MPC man hours are NOT to be recorded for individ- be recorded, GO TO Step 4_. uals, refer to:
- 1) Attachment 2 d) Assign individual to main-tain Attachment 2
- 4. ISSUANCE:
a) Issuance will follow normal Health Physics practices .
- 5. STORED SUPPLIES:
a) Alternate supply of respira-tory equipment may be obtained from:
- 1) Surry warehouse
- 2) North Anna Power Station
- 6. BOTTLE CHARGING:
a) I_F normal bottle charging a) ,IF Health Physics area becomes uninhabitable: is habitable, GO TO Step 7
- 1) Set up cascade charging area l system in another location OR i p -
b
No.97887210 NUMBER PROCEOURE TITLE REVISION N 00 EPIP-4.05 RESPIRATORY PROTECTION PAGE 4 of 4
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
^
l
- 6. (CONTINUED)
- 2) Contact Station Fire Marshal AND Request use of South Annex bottle charger OR,
- 3) Charge bottles using portable compressor from operations department
- 7. RETURN TO CONTROLLING PROCEDURE O UPON COMPLETICN OF THIS PROCEDURE
- 8. TERMINATE EPIP-4.05:
a) COMPLETED BY: DATE: TIME: t END O V
ro.oreersto NUMBER A TTACHMENT TITLE REVISION b' ' EPIP-4.05 RESPIRATORY PROTECTION 00 A TTACHMENT PAGE 1 GUIDANCE FOR RESPIRATORY PROTECTION 1 of 2 HAZARPS RECOMM'END USE ACCEPTABLE USE
- 1. Oxygen Deficiency Self contained breathing 4
apparatus with full face, pressure demand respirator
- 2. Radioactive Particulate GREATER TIIAN OR EQUAL Full face respirator with No respirator BUT TO 0.25, BUT LESS THAN particulate cartridge record MPC-hours to insure LESS 10 CONCi THAN 10 hours /
MPCi week O Q GREATER TIIAN OR EQUAL Atmosphere supplying Full face respirator TO 10, BUT LESS TilAN (airline) with full with particulate face respirator cartridge and record MPC-hours 400 CONCi LESS TIIAN 10 hours MPCi week GREATER TilAN Self contained breath-ing apparatus with 400 CONCi full face, pressure MPCi demand respirator
- 3. Radiciodines GREATER THAN OR EQUAL Full face respirator with No respirator but
- TO O.25 BUT LESS TilAN iodine cartirdge and record MPC-hours 10 recordMPC-hoursLFg to insure LESS THAN 10 hours / week THAN g) hours /
week b G
9 No.97887220 l NUMBER A TTACHMENT TITLE REVISION N EPIP-4.05 00 RESPIRATCRY PROTECTION A TTACHMENT PAGE 1 GUIDANCE FOR RESPIRATORY PROTECTION 2 of 2
- 3. (CONTINUED)
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 400 CONCi MPC-hours to in-MPCi sure LESS g 10 ) hours / week GREATER THAN Self contained breathing apparatus with full 400 CONCi face pressure demand MPCi respirator
- 4. Unknown Atmosphere Self contained breathing apparatus with full j face pressure demand respirator (1)
A log should be kept to insure no individual will normally exceed 10 MPC-hours / week, airborne exposure. l i O
2? $.Ea a
= ! m:t h n:ttQ ,DPm i a mN I .ow oo NH>HH % 2 coPM=CMMHm I
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Rl i f FA t U t CT t fCAO f Y ) RES D TMR O 8 I H J I FT( R E P
) :C I SA G RR I HF K T (
M A C A I II J I A EW M I I V T - C E 0 F Y M F A1/ O T( . S C C ) O I D . M I E F. I D M T t M t P I C e( 8 E D 0 )04 ( C W
/. e f C o N X
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a E N F T I A
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No.97887220 NUMBER ATTACHMENT TITLE REVISION EPIP-4.05 00
% RESPIRATORY PROTECTION A TTACHMENT PAGE 3 PROTECTION FACTORS 1 of 1 PROTECTION FACTORS PARTICULATES PARTICULATES DESCRIPTION MODES ONLY CASES & VAPORS
- 1. Air Purifying Respirator Fullface with parti- Negative Pressure 50 culate cannister Fullface with iodine Negative Pressure 50 ci.nister
- 2. Atmosphere Supplying Respirators A. Airline Respirator Fullface Continuous flow 2,000 B. SCBA Fullface Pressure demand 10,000 i
rv .97487230 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCEDURE TITLE REVISION 00 EPIP-4.06 PERSONNEL MONITORING AND PAGE DECONTAMINATION (With 2 Attachnents) 1 of 7 PURPOSE Provide guidance for decontamination of personnel. USER Personnel Monitoring and Decontamination Team Member. ENTRY CONDITIONS n/
- y. 1. Activated by EPIP-4.02, Radiation Protection Supervisor Controlling Procedure REVISION RECORD REV. 00 PAGE(S): Entire Procedure DATEJUL2 91982 REV. PAGE(S): DATE:
REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: APPROVAL RECOMMEh 'E0 APPROVED DA TE
'- 5A
. 1-- 1 C 4 AIRMAN STA TION NUCLEAR SAFETY N S S 1982 AND OPERA TING COMMITTEE
N o. 97887210 NUMBER PROCEDURE TITLE REVISION EPIP-4.06 PERSONNEL MONITORING AND DECONTAMINATION PAGE 2 of 7
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 1. INITIATE PROCEDURE:
a) BY: DATE: TIME:
- 2. OBTAIN MONITORING EQUIPMENT:
a) Obtain an RM-14, with a) Alternate supply of equip-H.P. 210 probe, from ment available at SGRP H.P. office Clean Change Building AND GO TO Personnel Decon and Q Change Area b) IF PDCA area habitable, b) IP area is uninhabitable, decon individuals there request assistance from Radiation Protection Supervisor, for relocation l AND
- 1) Remove contaminated clothing AND l 2) Don clean protective l
clothing to minimize l spread of contamination c) IF large number of individuals are suspected l of contamination l l 1) Laundry should be used to handle overflow l l l l
to.97ss72:s NUMBER PROCEDURE TITLE REVISION N 00 EPIP-4.06 PERSONNEL MONITORING AND DECONTAMINATION PAGE 3 of 7
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINEO
- 3. CONTAMINATED PERSONNEL WITH INJURIES:
a) 1F contaminated individual a) IP contaminated individual injured and requires first NOT injured, GO TO Step 4,. aid:
- 1) Have first-aid team perform follow-up first-aid and decon-tamination in the H.P. laundry facility, if appropriate
- 2) Perform as much decontam-ination as medical status permits
- 4. PERFORM SURVEY:
v a) Perform initial survey, documenting results on Attachments 1 and 2
- 1) Pay particular attention to nose and mouth area to determine possible in-ternal contamination b) IF internal contamination is a) IF internal contamination is suspected, note on Attachment NOT suspected, GO TO NOTE 1: prior to Step 5,.
- 1) Have individual clean noce with wet cotton swabs
- 2) Have individual blow nose frequently
- 3) Record swab reading on Attachment 1 l
O s_ - I
No. 97847210 NUMBER PROCEDURE TITLE REVISION i 00 Ge EPIP-4.06 PERSONNEL MONITORING AND DECONTAMINATION PAGE 4 of 7
- STEP -
ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED NOTE: Cease decontamination IF skin becomes reddened OR bleeding.
- 5. DECONTAMINATE:
a) Remove contaminated clothing from individual b) jf, contamination problem widespread:
- 1) Shower using soap and water, keeping radio-active material away from body openings
) 2) Dry thoroughly, placing towel in plastic bag or contaminated material barrel
- 3) Repeat survey and log data on Attachment 1
- 4) IF contamination still 4) IF individual found non-exists, repeat showering contaminated, GO TO Step and surveying, recording 6.
survey data on Attach-ment 1,
- 5) IF contamination still 5) IF individual found non-exists, select most contaminated, GO TO Step highly contaminated 6.
areas and start decon-tamination for localized areas c) If contaminated area c) J:F,NOT localized, GO TO Step localized: 5.d.
- 1) Isolate the area e /
x_-
No. 9788723 0 NUMBER PROCEDURE TITLE REVISION EPIP-4.06 PERSONNEL MONITORING AND DECONTAMINATION PAGE 5 of 7
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTA" LED
- 5. (CONTINUED) d) Perform the following and ,
record data on Attachment 1 after each Step:
- 1) Clean using soap and water
- 2) Apply abrasive soap and water
- 3) Apply a mixture of 50%
cornmean and 50% deter-gent paste and scrub with brush O
- 4) Apply potassium permanganate soluti 4, rinse AND Apply sodium bisulfite solution e) E contamination found d) g g Step 5.f.
j in eyes ,OR open wound: l 1) Flush copiously with water
- 2) Record contamination data on Attachment l_
- 3) Notify Radiation Protec-tion Supervisor f) If contamination found e) g 3 Step 6_.
in hair:
- 1) Shampoo, isolating face and shoulders O
No. 97887210 NUMBER PROCEDURE TITLE REVISION O (j 00 EPIP-4.06 PERSONNEL MONITORING AND DECONTAMINATION PAGE 6 of 7
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 5. (CONTINUED)
- 2) Consider cutting or shav-ing the affected area if contamination cannot be removed
- 6. CONTAMINATION LIMITS:
a) IF individuals are deconned a) IF individual cannot be to LESS THAN 100 CPM, above deconned to LESS THAN 100 background, they may be CPM above background, released contact Radiation Protect-ion Supervisor AND n v Request assistance. b) E contamination is fixed individual may be released AND Follow-up decontamination and/or dose evaluation is ! made
- 7. INTERNAL CONTAMINATION:
i a) IF internal contamination a) IF_ Whole Body counter is { suspected: inoperable, use North Anna Power Station counter.
- 1) Evaluate as per H.P.
Procedure 3.1.1.4 OR, 3.1.1.6
- 8. ADMINISTRATION:
a) Return all completed survey results to the Radiation Protection Supervisor v
No.97867210 NUMBER PROCEDURE TITLE REVISION O EPIP-4.06 PERSONNEI MONITORING AND DECONTAMINATION 00 PAGE 7 of 7
- STEP ACTION /EXPECI'ED RESPONSE RESPONSE NOTOBTAINED
- 9. TERMINATE EPIP-4.06:
a) COMPLETED BY: DATE: TIME: O END O
Nb,91881223 NUMBER A TTACHMENT TITLE REVISION
) EPIP-4.06 00 V PERSONNEL DECONTAMINATION RECORD A TTACHMENT PAGE 1 1 of 1
- 1. Individual Contaminated:
- 2. TLD#: Date: TIME: RWP# _
- 3. Contamination Occurred in (Area):
- 4. While Involved in (Type Work):
- 5. Personal Clothing or Equipment Contaminated: YES NO
- 6. Items (List):
- 7. Disposition of above listed items:
O 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:
- 11. Decontamination:
SURVEY INSTRUMENT DECON TIME SKIN AREA & PROBE READING AGENT INITIALS Ilealth Physics Remarks: C' Health Physics Clearance and Signoff By Date
N3.97887220 NUMBER A TTACHMENT TITLE REVISION O EPIP-4.06 A TTACHMENT PERSONNEL SURVEY MORKSHEET 00 PAGE 2 1 of I n i ke *
- e. Y 0f s
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- i O =,y1
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No,97887230 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCEDURE TITLE REVISION 00 EPIP-4.07 PROTECTIVE MEASURES PAGE (With 5 Attachments) 1 of 6 PURPOSE Provide guidance to Radiological Assessment Director to promptly assess projected doses to population of risk and to recommend protective actions to the Emergency Manager. USER Radiological Assessment Director or Senior Health Physics Personnel onsite. ENTRY CONDITIONS
- 1. Activitation by EPIP-4.01, Radiological Assessment Director j
Controlling Procedure. REVISION RECORD REV. 00 PAGE(S): Entire Procedure DATE Wl. 2 9 198 REV. PAGE(S): DATE: REV. PAGE (S) : DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: APPROVAL RECOMMENDED O APPROVED DA TE e 5A
' ~
HAIRMAN STA TION NUCLEAR SAFETY AND GPERA TING COMMITTEE
to. e7 es72:3 NUMBER PROCEDURE TITLE REVISION O
\.,,,/ EPIP-4.07 PROTECTIVE MEASURES 00 PAGE 2 of 6
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 1. INITIATE PROCEDURE: -
a) Initiated By: Date: Time -
- 2. PROTECTIVE ACTION GUIDELINES FOR INITIAL ASSESSMENT OR FOR CON-TINUOUS RELEASE:
a) IF this is an initial assess- a) IF puff release ment E E release has NOT occurred f) ( E the radioactive release - GO TO Step 3_. continuous release, continue with this instruction b) Determine distance which projected dose exceeds:
- 1) 2.0 Rem Whole Body 3
12.0 Rem Thyroid AND/OR
- 2) 0.5 Rem Whole Body 3
- 3) 1.0 Rem Thyroid c) Review protective action guidelines in Attachment 1 d) Detemine the affected sector from the Emergency Connunicator
N3.97847216 NUMBER PROCEDURE TITLE REVISION 00 V' EPIP-4.07 PROTECTIVE MEASURES PAGE 3 of 6
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 2. (CONTINUED)
- 1) Review Sector Map in Attachment 5 e) Recommend to Emergency Manager protective actions for primary e sector AND Two adjacent sectors e) GO TO Step 5
- 3. PROTECTIVE ACTION GUIDELINES FOR A PUFF RELEASE:
a) E the release is a puff release pR_ 1 Radiological release is probable, but hss NOT yet occurred:
- 1) Continue with this instruction l b) IF offsite exposure b) GO TO Step 5.'
- 1) GREATER THAN OR EQUAL TO 2.0 Rem Whole Body AND/OR
- 2) GREATER THAN O_R R EQUAL TO 12.0 Rem Thyroid THEN Continue with +his instruction O-
No.97887210
=
NUMBER PROCEDURE TITLE REVISION p 00
\ EPIP-4.07 PROTECTIVE MEASURES PAGE 4 of 6
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINEO
- 4. CALCULATE NEED FOR EVACUATION OR SHELTERING:
4 a) Determine need for evacuation OR shelterine' based on Whole Body exposure
- 1) Obtain fron EPiP-4.01, the distance which the projected dore in Step 3 would be exceeded AtO
- 2) The projected dose rate at that point
- 3) Complete Attachment 3 v
- 4) Using information from Attachment 3 determine the protective actions from the following table E THEN
- 1. Projected dose LESS 1. No action THAN 0.5 Rem
- 2. Sheltering dose LESS 2. Shelter THAN 2.0 Rem l
- 3. Sheltering dose GREATER 3. Evacuate THAN 2.0 Rem, and Evacu-ation dose LESS THAN sheltering dose
- 4. Sheltering dose GREATER 4. Shelter THAN 2.0 Rem, and Evacu-ation dose GREATER THAN O_RR EQUAL TO sheltering dose O
t
No. 97887210 NUMBER PROCEDURE TITLE REVG10N f 0; Q) EPIP-4.07 PROTECTIVE MEASURES FAGE 5 of 6
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 4. (CONTINUED) b) Determine evacuation OR sheltering based on Thyroid exposure
- 1) Complete Attachment 3 using Thyroid exposure rate Atm 0.65 for structure shielding factor
- 2) Using information from p Attachment 3, determine (y protective actions to be recommended from following:
IF THEN ,
- 1. Protected thyroid dose 1. No action LESS THAN 1.0 Rem -.
- 2. Sheltering dose GREATER 2. Shelter THAN 1.0 Rem but LESS s THAN 12 Rem
- 3. Sheltering dose GREATER 3. Evacuate THAN M Rem and evacu-ation dose LESS THAN sheltering dose
- 4. Sheltering dose GREATER 4. Sheltel THAN 12 Rem and evacu-ation dose GREATER THAN OR EQUAL TO sheltering j dose l
V . 1 x
N3.97887219 , NUMBER PROCEDURE TITLE REVISION [' 00 EPIP-4.07 PROTECTIVE FIASURES PAGE 6 of 6
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT 08TAINE0 5.
DETERMINE NEED FOR PROTECTIVE ACTION ONSITE: a) Review survey and air sampling data with Radiation Protection Supervisor b) IF the Whole Body dose rate b) E onsite Protective Action exceeds 1_ Rem /hr in occupied Guidelines are NOT exceeded, areas of the plant
- 1) Recommend evacuation to OR low radiation area E projected Thyroid exposure OR exceeds 5 Rem (see Attachment
~
- 2) 2) For thyroid exposure recommend sheltering in closed buildings.
- 1) Recommend evacuation of onsite personnel NOT required for emergency response
- 6. RETURN TO CONTROLLING PROCEDURE:
' - a) Upon completion of this pro-cedure, return to EPIP-4.01,
, Radiological Assessment Direc-tor Controlling Procedure
- 7. TERMINATE PROCEDURE EPIP-4.07:
a) COMPLETED BY: r .- DATE: TIME: i - END s
)
_ - _ . e- - . . ~ , ,. , - , , , -- , ,.,c --
No. 97887220 NUMBER A TTACHMENT TITLE REVISION N EPIP-4.07 00 STATE OF VIRGINIA A TTACHMENT PAGE 1 PROTECTIVE ACTION GUIDELINES 1 of 1 4 OFFSITE: PROJECTED DOSE PROTECTIVE ACTIONS LESS THAN 0.5 Rem Whole Body OR No protective action necessary IF LESS THAN 1.0 Rem Thyroid radiological situation is unstable, consider recommendation of citizen alert. 0.5 - 2.0 Rem whole Body OR Recommend sheltering of public (N 1.0 - 12.0 Rem Thyroid GREATER THAN 2.0 Rem Whole Body OR , Recommend evacuation of affected 12 M Rem Thyroid sectors
\
ONSITE: PROJECTED DOSE PROTECTIVE ACTIONS LESS THAN 1.0 Rem Whole Body OR Recommend sheltering LESS THAN 5.0 Rem Thyroid GREATER THAN 1.0 Rem Whole Body OR Recommend site evacuation GREATER THAN 5.0_ Rem Thyroid b V
no.stsa m e NUMBER A TTACHMENT TITLE REVISION [~' EPIP-4.07 00
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N3.97887220 NUMBER A TTACHMENT TITLE REVISION f'N EPIP-4.07 00 EVAUCATION VERSUS SHELTER A TTACHMENT PAGE 3 WORKSHEET 1 of 2 NOTE: Use furthest distance in which protective action guidelines for sheltering have been exceeded.
- 1. Obtain approximate DISTANCE from Step 4 MILES
- 2. Obtain DOSE RATE at distance from Step 4 MR/HR
- 3. Estimation of RELEASE DURATION HOURS 4
ON PROJECTED DOSE = REM 1000
- 5. WIND SPEED MPH
- 6. PLUME TRAVEL TIME = DISTANCE (miles) HOURS
[V] WIND SPEED (mph)
- 7. Time SINCE _OR UNTIL, BEGINNING OF RELEASE a) E RELEASE HAS BEGUN:
TIME RELEASE HAS BEEN IN PROGRESS HOURS b) I_F RELEASE WILL BEGIN: RELEASE WILL START IN HOURS
- 8. TIME UNTIL EXPOSURE BEGINS:
a) I_F RELEASE HAS BEGUN: Item 6 - Item 7a HOURS b) IF RELEASE WILL BEGIN: Item 6 + Item 7b HOURS l 9. EVACUATION WEATHER CONDITIONS: , NORMAL ADVERSE
- 10. Use distance and weather conditions to obtain ESTIMATED EVACUATION TIME from Attachment 4, HOURS O
V
No,91887tt0 NUMBER A TTACHMENT TITLE REVISION EPIP-4.07 00 t O A TTACHMENT EVAUCATION VERSUS SHELTER PAGE 3 WORKSHEET 2 of 2 NOTE: IF time until exposure begins is longer than evacuation time, enter zero hours.
- 11. EXPOSURE TIME Evacuation Time - Time until exposure begins = HOURS
- 12. EVACUATION EXPOSURE PERIOD:
Smaller of either Exposure Time or Release Duration Time HOURS
- 13. PROJECTED DOSE from Step 4_ REM
- 14. EVAUCATION DOSE:
EVACUATION EXPOSURE PERIOD X DOSE RATE 1000 REM
- 15. SHELTERING DOSE:
PROJECTED DOSE x STRUCTURE SHIELDING FACTOR
- REM
- NOTE: FOR WHOLE BODY = 0.9 THYROID = 0.65 l
l t i END l O
.. - - - . . _ - _ - . - - - . . . - - . = . = _ - -- . . - . . .
- No. 9784M20 NUMBER A TTACHMENT TITLE REVISION EPIP-4.07 00 EVACUATION TIMES FOR SURRY POWER STATION-A TTACHMENT PAGE 4 1 of 1 1'
AREA TIME EVACUATION EVAUCATION TIME NORMAL TIME ADVERSE CONDITION CONDITION Total Area within 2-Miles 2:00 2:15 WITHIN 2-5 MILES Surry Co. 2:00 2:15
- Isle of Wight 2
- 00 2:15 l James City Co. 2:00 3:45 i
WITHIN 5-10 MILES Surry Co. 2:CO 2:15 James City Co. 2:00 5:15 Williamsburg 2:00 3:45 York Co. 2:00 3:15 Newport News 2:00 5:15
I MUMBER A TTACHMENT TITLE REVISION EPIP-4.07 00 A TTACHMENT SURRY SECTOR MhP PAGE 5 l of 1 TWp Q #Q* 7 Vj 6p .L F 4- .'" '; . % .
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P40.97887230 VIRGINIA ELECTRIG AND POWER COMPANY SURRY POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE O NUMBER PROCEDURE TITLE REVISION 00 EPIP-4.08 INITIAL OFFSITE PILEASE ASSESSMENT PAGE (With 8 Attachments) 1 of 10 PURPOSE
- 1) Initially assess cor. sequences of offsite releases or potential offsite releases.
USER Radiological Assessment Director O_R Members of Dose Assessment Team. ENTRY CONDITIONS O h 1. Entry from EPIP-4.01, Radiological Assessment Director Controlling Procedure;
- 2. Entry from EPIP-4.03, Dose Assessment Controlling Procedure; a
- 3. Direction of the Station Emergency Manager.
REVISION RECORO REV. 00 PAGE (S) : Entire Procedure DATE:JUL 2 9 1982 REV. PAGE(S): DATE: REV. . PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE (S) : DATE: REV. PAGE (S) : DATE: REV. PAGE(S): DATE: APPROVAL RECOMMENCE 0 APPROVED DA TE O. e e/ CHAIRMAN STA TION NUCLEAR SAFETY JUL 2 9 W AND OPERA TING COMMITTEE
No. 9788 7210 e NUMBER PROCEDURE TITLE REVISION
\, 00 V EPIP-4.08 INITIAL OFFSITE RELEASE ASSESSMENT PAGE 2 of 10 C
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 1. INITIATE PROCEDURE:
a) BY: DATE: TIME:
- 2. VERIFY EMERGENCY ,
CLASSIFICATION: a) E the emergency is an a) IF a SITE OR GENERAL emer-UNUSUAL EVENT OR ALERT: gency
- 1) Continue with this 1) GO TO Step ~4.
instruction NCTIE: Evaluation of percent technical specifications in this Step makea assumptions about flow rate, isotopic mixture and detector response. Further analysis upon completion of this procedure will be necessary to quantify release.
- 3. DETERMINE PERCENT TECHNICAL SPECIFICATION:
a) Obtain from operations number of the monitor in alarm
- 1) 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.
v
P40. 97887210 NUMBER PROCEDURE TITLE REVISION EPIP-4.08 INITIAL OFFSITE RELEASE ASSESSMENT PAGE 3 of 10
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 3. (CONTINUED) c) Obtain highest CPM, above c) IF monitor is offscale OR background, of monitor in not functional:
Step 3.a
- 1) GO TO Step 4.d.
- 1) Log on Attachment 1 d) Determine release rate:
- 1) Gaseous 1) E NOT a gaseous release, continue with this instru-CFM ction.
e) IF more than one monitor (~'} E in alarm: L.J
- 1) Total percent Tech Spec will be the sum of the percent from each monitor f) Determine the percent Tech- f) E monitor of interest NOT nical Specification from the listed in the attachments:
the appropriate figure in Attachment 2 1) GO TO Step 7, for follow-up assessment.
- 1) Log on Attachment 1 g) IF percent of Tech Spec g) IF percent of Tech Spec Limit LESS THAN 100%: Limit GREATER THAN 100%:
- 1) GO TO Step 7 1) GO TO Step 3.h.
h) E percent of Tech Spec h) IF percent of Tech Spec Limit LESS THAN 1000%: Limit GREATER THAN 1000%:
- 1) Confirm UNUSUAL EVENT 1) GO TO Step 3.i.
- 1) E percent of Tech Spec i) F percent of Tech Spec IF Limit GREATER THAN 1000%: Limit NOT GREATER THAN 1000%:
[ i v
No.97887210 NUMBER PROCEDURE TITLE REVISION 00 (V~'} EPIP-4.08 INITIAL OFFSITE RELEASE ASSESSMENT PAGE 4 of 10
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINEO
- 3. (CONTINUED)
- 1) Confirm ALERT emergency 1) GO TO Step 3.i.
j) IF event - ALERT: j) IF event UNUSUAL EVENT: OR 1) GO TO Step 7. IF Site Boundary dose rate requested:
- 1) GO TO Step 4_
- 4. DETERMINE SITE BOUNDRY WHOLE BODY DOSE RATE:
a) Request from the Emergency () Manager
- 1) Placement of an individual to observe the monitor in alarm and report increase or decrease in readings b) E Air Ejector is diverted b) Continue with Step 4.c.
to containment, M release from this pathway should be considered l f l c) F release path thru Process IF c) IF normal range monitors are ! Vent, Vent Vent, O_R R Air offscale: Ejector
- 1) GO TO Step 4.d.
AND Normal Range monitors are onscale, obtain from oper-ations: l
- 1) Obtain Number - monitor l of interest, and log on Attachment 3:
I . - _
. . . . - ~ - . . . - _ _ _ . - - . . - . - . . - .- - . - . . - . - . . _ . -- .
No. 97487230 i
=
huMBER PROCEDURE TITLE REVISION 00 EPIP-4.08 INITIAL OFFSITE RELEASE ASSESSMENT PAGE 5 of 10 i-
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT08TAINE0
- 4. (CONTINUED)
Vent Vent (VG-lO4) i Z Process Vent (GW-102) 4 Air Ejector (SV-111, 211)
- 2) Count rate (cpm), above background, for monitor of interest CPM
- 3) Flow rate (CFM)
- 4) Obtain, from the Emergency Communicator:
Stability class Wind speed - 5) Obtain conversion factor from Attachment 6, using l
- the monitor of interest
- and stability class 4 .
j Conversion factor
- 6) Determine Site Boundary dose rate:
CPM x CO!NERSION FACTOR x FLOW RATE = g i WIND SPEED HR 4 t i i
. , - - - . - . , , - - . , - . . . . - - , , , . -,----n. . -- . . - - - - - - - , , , . . - , - - , - - , - - ----,,-a, - - - - - . - . =-------n
No. 97487210 NUMBER PROCEDURE TITLE REVISION 00 EPIP-4.08 INITIAL OFFSITE RELEASE ASSESSMENT MOE 6 of 10
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 4. (CONTINUED)
- 7) Log mR/hr on Attachment 3
- 8) GO TO Step 5 d) F release path thru process IF d) E release thru main steam vent or vent vent system, GO TO Step 4.e.
AND OR Normal range monitors - IF high range monitors are offscale NOT on scale:
- 1) Obtain the number of 1) Recommend UNUSUAL EVENT monitor of interest emergency and log on Attachment 3:
(%..,/) 2) GO TO Step 7 Process Vent (RM-GW-122) gR Vent Vent (RM-VG-123)
- 2) Obtain from operations mR/hr of monitor of interest mR/hr
- 3) Convert mR/hr to uCi/cc using Attachment 5 uCi/cc ,
- 4) Obtain flow rate
- 5) Obtain from Emergency Communicator:
Stability class Wind speed J
Peo. 97887210 NUMBER PROCEDURE TITLE REVISION 00 $ EPIP-4.08 INITIAL OFFSITE RELEASE ASSESSMENT PAGE 7 of 10
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 4. (CONTINUED)
- 6) Using stability class and monitor of interest, obtain the conversion factor from Attachment 6 conversion factor
- 7) Determine Site Boundary dose rate:
uCi/cc x COINERSION FACTOR x FLOW RATE = MR WIND SPEED HR
- 8) Log mR/hr on Attachment 3
- 9) GO TO Step 5, e) IF actual or potential ralease e) GO TO Step 5.
path thru Steam Safety Relief Valves 3 Auxiliary Feedwater Pump Turbine Exhaust
- 1) Obtain from Operations mR/hr of monitor in alarm:
Main Steam Unit #1 RM-MS-124 RM-MS-125 RM-MS-126 Z O
No.97887230 NUMBER PROCEDURE TITLE REVISION O V EPIP-4.08 INITIAL OFFSITE RELEASE ASSESSPINT PAGE 8 of 10
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 4. (CONTINUED)
Main Steam Unit #2 RM-MS-224 RM-MS-225 RM-MS-226 Auxiliary Feedwater Pump Turbine Exhaust (AFWPT) Unit #1 RM-MS-129 O Unit #2 RM-MS-229
- 2) I_F AFWPT - isolated, no 2) Continue with this instru-release assumed from this ction pathway
- 3) IF release - thru both 3) Continue with this instru-relief valves and AFWPT, ction results are additive
- 4) Obtain from Emergency Communicator, stability class AND wind speed
- 5) Obtain from Attachment 6 conversion factor for Main Steam and/or AFWPT
- 6) Determine Site Boundary dose rate:
mR/hr (monitor) x CONVERSION FACTOR = g WIND SPEED HR O3
Peo. 97887210 NUMBER PROCEDURE TITLE REVISION
/]
b' EPIP-4.08 INITIAL OFFSITE RELEASE ASSESSMENT 00 PAGE 9 of 10
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 4. (CONTINUED)
- 7) Log mR/hr on Attachment 3
- 5. DETERMINE SITE BOUNDARY THYROID DOSE RATE:
a) Obtain Site Boundary Whole Body dose rate from Attach-ment 3 b) Determine conversion factor versus various types of accidents from Attacraent 8 c) Determine Site Boundary
)
Thyroid dose rate: O DOSE RATE x CONVERSION FACTOR = DOSE RATE (Whole Body) (Thyroid) d) Log Thyroid dose rate on Attachment 4
- 6. DETERMINE OFFSITE DOSE RATE AT 2, 5, AND 10 MILES:
a) Determine from Attachments 3 and 4 most current:
- 1) Stability class
- 2) Site Boundary Whole Body and Thyroid dose rate b) Dets mine multiplication facto from AttacFaent 7 for distance of 2_ miles ,
c) Determine dose rate: SITE BOUNDARY x MULTIPLICATION = DOSE RATE
; DOSE RATE FACTOR (2 miles) a
No. 97887210 NUMBER PROCEDURE TITLE REVISION i 00 EPIP-4.08 INITIAL OFFSITE PILEASE ASSESSMENT PA GE 10 of 10
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 6. (CONTINUED) e) Repeat Steps 6.b thru 6.d for distance of 5 and 10 miles f) Log on Attachment 3
- 7. RETURN TO CONTROLLING PROCEDURE:
a) Upon completion of this pro-cedure, return to EPIP-4.01, Radiological Assessment Director Controlling Procedure OR
~
f"% r C) b) EPIP-4.03, Dose Assessment Controlling Procedure
- 8. TERMINATE PROCEDURE EPIP-4.08:
a) COMPLETED BY: DATE: ! TIME: ? l I I END
_.__... _ .- -. .m . .-_ - . _ _. . _ _. .m_ _ . . _ . ._. .m_ _ 4 __ . _ _ No. 97887220 p. NUMBER A TTACHMENT TITLE REVISION EPIP-4.09 00 A TTAC# MENT % TECHNICAL SPECIFICATION DATA SHEET FAGE 1 1 of 1 MONITOR NET COUNT PER MINUTE % TECH EPECS l 1 O l l e l
--w .we.-.e- . ,y-e-.y-:. w .-e-mw,,, e., e ,
-9 7_--g 9 7 7 m._- . ._g ,, , .y v - 7 5 m, = , . _ ,_.,, _ , __,3
---+rT9y
No. 97887224 NUMBER A TTACHMENT TITLE REVISION
,- ,1 00 EPIP-4.08
[V A TTACHMENT
% TECH SPEC VENTILATION VENT PAGE 2
1 of 4 10
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Peo. 97887220 NUMBER A TTACHMENT TITLE REVISION A r i EPIP-4.08 00
\ f A TTACHMENT HIGH EANGE MONITORS p,gg 5 MAIN STEAM MONITORS 6 of 6 10
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No 97887220 NUMBER A TTACHMENT TITLE REVISION EPIP-4.08 00 A TTACHMENT CONVERSION FACTORS PAGE 6 1 of 1 l CONVERSION FACTORS NORMAL PANGE Stability Vent Vent Process Vent Air Ejector Class VG-104 GW-102 SV-111, 211 A 2.39E-11 2.39E-10 1.16E-8 B 7.98E-11 7.98E-10 3.86E-8 C 1.63E-10 1.63E-9 7.87E-8 D 3.74E-10 3.74E-9 1.81E-7 E 5,95E-10 5.95E-9 2.88E-7 F 9.27E-10 9.27E-9 4.49E-7 G 1.21E-9 1.21E-8 5.85E-7 HIGH RANGE Process Vent / Vent Vent Main Steam AFWPT A 4.09E-5 2.24E-1 5.85E+1 l - B 1.37E-4 7.47E-1 1.95E+2 C 2.79E-4 1.52E+0 3.98E+2 D 6.41E-4 3.50E+0 9.16E+2 E 1.02E-3 5.57E+0 1.46E+3 F 1.59E-3 8.67E+0 2.27E+3 G 2.07E-3 1.13E+1 2.96E+3 'I
No. 91887tt0 NUMBER A TTACHMENT TITLE REVISION EPIP-4.08 00 X/Q MULTIPLICATION FACTOR A TTACHMENT - PAGE 7 1 of 1 STABILITY " LASS Distance A B C D E F G Miles 2 1.37E-2 1.12E-2 4.27E-2 6.37E-2 8.33E-2 1.28E-1 2.38E-1 0 - 5 6.02E-3 2.36E-3 8.84E-3 1.59E-2 2.42E-2 3.,74E-2 7.79E-2 10 3.llE-3 1.24E-3 2.80E-3 5.84E-3 1.00E-2 1.55E-2 3.24E-2 9 n-
N3.97887226 NUMBER A TTACHMENT TITLE REVISION EPIP-4.08 00 A TTAC# MENT THYROID DOSE CONVERSION FACTORS PAGE 8 1 of 2 ACCIDENT TIME AFTER ACCIDENT CONVERSION (HOURS) FACTORS
- 1. LOCA 0.5 27 1.0 32 1.5 36 2.0 41 2.5 46 3.0 51 3.5 57 4.0 62 4.5 69 5.0 75 6.5 98 8.0 123 10.0 158 l 12.5 209 l
15.0 258 24.0 389 48.0 707 72.0 758 O
-- - _ . = . ._
No 97887220 NUMBER A TTACNMENT TITLE REVISION EPIP-4.08 00 A TTACNMENT THYROID DOSE CONVERSION FACTORS FAGE 8 2 of 2 THYROID CONVERSION FACTORS ACCIDENT FILTERED (CHARCOAL) UNFILTERED
- 2. Primary Gas Release 2.76E-2 2.76E-1
- 3. Steam Generator Tube Rupture 1.30E+2
- 4. Fuel Handling Accident 6.59E+1 5.58E+2 i
- 5. Waste Gas Decay Tank 7.67E-3 7.67E-2 i
- 6. Main Steam Line Break (with prior primary to secondary leakage) 3.79E+1 -
2.67E+2 l O 1
No.97887250 VIRGINIA ELECTRIC AND POWER COMPANY SORRY POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE O t NUMBER PROCEDURE TITLE REVISION 00 EPIP-4.09 SOURCE TERM ASSESSMENT PACE (With 4 Attachments) 1 of 9 PURPOSE Provide guidance and data to Dose Assessment Team to more accurately predict offsite releases. USER Dose Assessment Team Members. ENTRY CONDITIONS () Upon activation of EPIP-4.03, Dose Assessment Controlling Procedure. REVISION RECORO REV. 00 PAGE (S) : Entire Procedure DATE gUL 2 9 1982 REV. PAGE(S): DATE: REV. PAGE (S) : DATE: REV. PAGE(S): DATE: REV. PAGE (S) : DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: l APPROVAL RECOMMENCE 0 APPROVED DA TE l \s' . i ,
. o -
'O C IAIRMANSTA TION NUCLEAR SAFETY OUL S 0 1962 AND OPERA TING COMMITTEE i
i i No. 97887210 NUMBER PROCEDURE TITLE REVISION
/ h 00 EPIP-4.09 SOURCE TEAMS ASSESSMENT PAGE 2 of 9
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 1. INITIATE PROCEDURE:
a) BY: DATE: TIME:
- 2. SOURCE TERM ASSESSPINT:
a) Source term based on monitor readings should be used:
- 1) Initial assessment AND C' 2) Establish trends b) IF the source term is from monitor readings, sampling should be done to c. ore accurately determine the source term c) Source term will have units of i Ci/sec d) Source term may be obtained d) E source term from con-i from any of the following, tainment - GO TO Step 2.e.
in order of preference:
- 1) Sample of effluent - 1) ,I_F sample of effluent GO TO Step 4_ NOT available, GO TO Step 2.d.2.
2 2
- 2) Sample of Station Inventory 2) IF sample of station GO TO Step 6_ inventory NOT avail-able, GO TO Step 2.d.3.
2 OR O < l
No. s7ss 722 0 l NUMBER PROCEDURE TITLE REVISION i~ 00 l EPIP-4.09 SOURCE TEAMS ASSESSMENT PAGE 3 of 9
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 2. (CONTINUED)
- 3) Normal range station 3) E source term NOT thru monitors - GO TO Step 3_ the normal station monitors - GO TO Step 2.e.
e) IF event may produce releases e) IF, F event is NOT a release from containment, source term from containment - GO TO may be obtained from any of Step 9. the following, in order of preference
- 1) Sample of Containment Air - 1) IF F sample can NOT be GO TO Step 8, obtained from contain-ment - GO TO Step 2.e.2.
Q V
- 2) Containment high Range Monitor - GO "'O Step 7
- 3. SOURCE TERN - NCRM.E STATICN MONITORS:
a) Scurce term may be obtained u) IF normal rar.ge monitors from the folloving monitcrs: are offscale, GO TO Step 4.
- 1) Vent Vent VG-104 OR OR IF release pathway is thru the main steam system, GO TO Step 9_.
- 2) Process Vent GW-102
- e -
- 3) Condensor Air Ejector SV-111, SV-211 b) IF more than one effluent b) Continue with this instruc-5thwaysinvolved: tion
- 1) Add results of all monitors for total release
- O
No.97847210 NUMBER PROCEDURE TITLE REVISION {} V EPIP-4.09 SOURCE TEAMS ASSESSMENT 00 PAGE 4 of 9
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 3. (CONTINUED) c) Obtain the CPM, above background, for monitor of interest, from Radio-logical Assessment Director
- 1) Log date, time, monitor number and the net cpm on Attachment 1 d) ))[ Air Ejector NOT diverted d) )); Air Ejector ))! diverted to containment, continue to containment, no release with th4.s instruction from this pathway will occur:
- 1) GO TO Step 3.e.
O) ( , e) Obtain the flow rate (CFM) effluent pathway from Radio-logical Assessment Director
- 1) Log on Attachment 1 f) Obtain conversion factor for monitor of interest:
- 1) VG-104: 1.19 E-ll SE
- 2) GW-102: 1.19 E-10 SE
- 3) SV-lll,211:5.71 E-9 g) Perform following calcu-lations to obtain Ci/sec (XE-133 Equivalent):
CPM x CONVERSION FACTOR x CFM = Ci/sec O
No. 978872 30 NUMBER PROCEDURE TITLE REVISION EPIP-4.09 SOURCE TEAMS ASSESSMENT E 5 of 9
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED -
- 3. (CONTINUED)
- 1) Log results on Attachment 1 s h) GO TO Step 9,
- 4. SOURCE TERM - SAMPLE EFFLUENTS:
a) Request Radiation Protection a) IF sampling not required, Supervisor to initiate EPIP- GO TO Step 5,. 4.24, Gaseous Effluent Sampling During an Emergency, to obtain a sample:
- 1) Vent Vent -
O V E
- 2) Process Vent S
- 3) Condensor Air Ejector b) IF more than one effluent b) GO TO Step 4.c.
pathway involved:
- 1) Add results of all monitors for total release c) Have sample analyzed as per normal count room procedures l O_R R initiate EPIP-4.26, High Level Activity Sample Analysis
- 1) Log results of the analysis on Attachment 2 d) Perform calculations on Attachment 2 to obtain:
O
ho.97887230 NUMBER PROCEDURE TITLE REVISION 1
/^\ 00 Q EPIP-4.09 SOURCE TEAMS ASSESSMENT PAGE 6 of 9
- STEP ACTION / EXPECTED RESPONSE RESPONSE HOTOBTAINED
- 4. (CONTINUED)
- 1) Equivalent activity I-131 AND Xe-133 (uCi/ml) e) Obtain flow rate:
f) Calculate source term (Ci/sec) : EQUIVALENT ACTIVITY x CFM x 4.72E-4 = Ci/sec
- 5. CORRECT SOURCE TERM FOR MAXIMUM RELEASE:
a) I_F F sample from Step 4 was a) IF sample was NOT a grab a grab sample and is NOT sample OR IF sample g obtained at maximun release, obtained at maximum release correct for maximum release GO TC Step 9, rate:
- 1) Obtain the maximum monitor 1) IF monitor is offscale, reading GO TO Step 9_.
- 2) Obtain monitor reading at time of sample
- 3) Obtain source term from Step 4_
- 4) Perform following calcula-tion to obtain maximum release rate:
Monitor Maximum (cpm) x Source Monitor Sample (cpm) Term
= /sec b) GO TO Step 9, O
No. 97887213 NUMBER PROCEDURE 11TLE REVISION
/%
00 ( V) EPIP-4.09 SOURCE TEAMS ASSESSPINT PAGE 7 of 9
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 6. SOURCE TERM - STATION INVENTORY:'
a) IF, release originated from gas storage tank (ie. Waste Gas Decay Tank, Volume Control Tank, etc.):
- 1) Request sampling the activity remaining in tank
- 2) Have sample analyzed by normal count room procedures OR initiate EPIP-4.26, High Level Activity Sample Analysis
- 3) Log activity on Attachment 2 b
\/% b) Perform calculations on Attachment 2 to obtain:
- 1) Equivalent activity I-131 AND Xe-133 l c) Determine volume of release from the following equation:
112 VOLUME = TP 12 l 1) Obtain pressure prior to l release from operations (P )
- 2) Obtain pressure after release from operations (P )
2
- 3) Obtain the design volume of the tank minus the water volume in the tank from operations
- 4) Obtain temperature prior to release from operations
[)\
\.
(T = 'F + 459) 1
No. 97887210 NUMBER PROCEDURE 17TLE , REVISION O 00 (,/ EPIP-4.09 SOURCE TEAMS ASSESSMENT PAGE 8 of 9
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 6. (CONTINUED)
- 5) Obtain temperature after release from operations (T2 = 'F + 459) d) Perform the following to determine source term:
2.83E-2 x VOLUME (ft3) x EQUIVALENT ACTIVITY =
/ ec TIME OF RELEASE (seconds)
- 7. SOURCE TERM - CONTAINMENT HIGH RANGE MONITOR:
s ,) a) IF event - LOCA: a) IF source term NOT from LOCA, GO TO Step 9.
- 1) Cbtain the dose rate (mR/hr) of Containment High Range Monitor of affected unit, from Radiological Assessment Director b) Obtain length of time (HOURS) after shutdown c) Determine approximate extent of fuel damage using Attachment 3
- 1) Extrapolate, if necessary, to determine fuel damage d) Use data from Step 7.b, Step 7.c and Attachment 4:
- 1) Determine equivalent curies I-131 and Xe-133 e) Determine potential release rate:
[~'T EQUIVALENT CURIES x 3.39 E-8 = Ci/sec ()
No.97aa7210 NUMBER PROCEDURE TITLE REVISION EPIP-4.09 SOURCE TEAMS ASSESSMEllT PAGE 9 of 9
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINEO
- 7. (CO!1TI!1UED) f) GO TO Step 9
- 8. SOURCE TERM - CONTAI!IMENT SAMPLE:
a) IF event - LOCA: a) IP event NOT LOCA, GO TO Step 9_.
- 1) Request Radiation Pro-tection Supervisor initiate EPIP-4.22, Post Accident Sampling of Con-tainment Air b) Convert results of analysis p to equivalent activity (uCi/mL)
'Q of I-131 and XE-133, using Attachment 2 c) Determine potential release rate:
EQUIVALEllT ACTIVITY x 1.73 E-3 = Ci/sec
- 9. RETURN TO CO!! TROLLING I ROCEDURE:
a) Upon completion of this procedure, return to EPIP-4.03, Dose Assessment Controlling Procedure
- 10. TERMIllATE EPIP-4.09:
a) Completed By: Date: Time: END ( i
. - _ . . - _ . - . . . . -- - ~ - --. .. .- .. __ . . _ _ _ . - . . -- . _ _
1 No. 97887220 i j NUMBER A TTACHMENT TITLE REVISION EPIP-4.C9 .00 1 MONITOR DATA SHEET , A TTACHMENT PAGE ! 1 1 of 1 i 1 1 i CONVERSION DATE TIME MONITOR CPM FACTOR CFM Ci/sec (XE-133) i I i s i I l i I I f I i I i l ' 4 } i P i, b I , i i '.--.n,n-,-.-,,, --,.m.,.,,,.-~-,,,--.,_--,,.,--_ ,-._-,-n,-,- ._,,.nn-,,_,,- - , , , - , . - ~ - - - - . . _ . _ _ _ .
No.97887220 t NUMBER A TTACHMENT TITLE REVISION EPIP-4.09 00 O> EQUIVALENT ACTIVITY XE-133 A TTACHMENT IMMERSION DOSE PAGE 2 1 of 2 a ACTIVITY DOSE EQUIVALENT EQUIVALENT tlUCLIDE 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 4 XE-131M 4.30E-1 XE-133 1.00E+0 XE-133M 9.09E-1 O XE-135 XE 135M XE-137 5.57E+0 9.74E+0 4.12E+0 3 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 I-134 5.91E+1 I-135 3.55E+1 I of EQUIVALENT XE-133 = O
No. 91887220 NUMBER A TTACHMENT TITLE REVISION
) EPIP-4.09 00 V EQUIVALENT ACTIVITY I-131 A TTACHMENT INHALATION DOSE PAGE 2 2 of 2 ACTIVITY DOSE EQUIVALENT EQUIVALENT NUCLIDE FACTOR ACTIVITY A B AxB I-131 1.00E+0 1-132 1.19E-2 I-133 2.37E-1 1-134 3.12E-3 I-135 4.87E-2 E of EQUIVALENT I 131 = uCi/ml or C1 O
\
O
Nn.97887220 NUMBER A TTACHMENT TITLE REVISION EPI N .09 00 CONTAINMENT HIGH RANGE MONITOR A TTACHMENT PAGE DOSE RATE VS. TIME 3 1 of 1
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a No. 97887220
# REVIS/0N i EPIP-4.09 00 Q 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.
1 EQUIVALENT CURIES I-131
^ 3.52 E+2 (1% Clad Failure)
A 3.85 E+5 (100% Clad Failure) 5.93 E+5 (1% Fucl Melt) LOCA (10% Fuel Melt) A 5.93 E+7 (100% Fuel Melt) l i i I
\
No 91887230 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCEDURE TITLE REVISION 00 EPIP-4.10 DETERMINATION OF X/Q PAGE (With 5 Attachments) 1 of 6 PURPOSE Determine atmospheric diffusion factor, X/Q. USER Radiological Assessment Director AND/OR Dose Assessment Team. ENTRY CONDITIONS Activated by offsite dose assessment EPIP.
%d REVISION RECORD REV. 00 PAGE(S): Entire Procedure DATEJUL 2 9 1982 REV. PAGE (S) : DATE:
REV. PAGE (S) : DATE: REV. PAGE (S) : DATE: c REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: APPROVAL RECOMMENOEO APPROVED DA TE si QUMsn C 4 AIRMAN STA TION NUCLEAR SAFETY AND OPERA TING COMMITTEE
No. 97887210 NUMBER PROCEDURE TITLE REVISION 00 C) EPIP-4.10 DETERMINATION OF X/Q PAGE 2 of 6 l
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED 1
- 1. INITIATE PROCEDURE:
a) Initiated By: Date: Times
- 2. DETERMINE CENTERLINE X/Q:
a) IF_ X/Q is for centerline Site a) E X/Q is needed for other Boundary distance: OR 1) Off-centerline - to first determine centerline X/Q Distance of 0.25 mile incre- GO TO Step 2.b. ments from plant: s OR
- 1) Continue with this instruction 2) Distances other than 0.25 mile increments -
GO TO NOTE prior to Step 3, b) Obtain from Radiological b) IF Radiological Asessment Assessment Director, latest: Director NOT available:
- 1) Wind speed 1) Obtain information from Emergency Communicator AND
- 2) Stability class c) Determine distance (miles) for which X/Q to be calcu-lated d) With stability class, wind speed and distance j 1) Determine X/Q from Attach-ment 1
- 4 ,.._c . . . , . - - - - . _ , < , - , -
No. 974672 3 0 NUMBER PROCEDURE TITLE REVISION h V EPIP-4.10 DETERMINATION OF X/Q 00 PAGE 3 of 6
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 2. (CONTINUED) e) Correct X/Q from Step 2.d current wind speed:
ACTUAL X/Q = X/O WIND SPEED (mph) f) GO TO NOTE prior to Step 4, NOTE: Dispersion coefficients for stability class G_ are determined by: coefficents (stability class F_) x 0.6.
\s NOTE: For stability class A and distances GREATER THAN 1500 meters, o = 2000.
For stability class B and distances GREATER THAN 5000 meters, o = 2000. z
- 3. DETERMINE CENTERLINE X/Q AT ANY DISTANCE:
a) F X/Q is required for a) IF X/Q is required for off-distance other than 0.25 centerline increments
- 1) GO TO Step 3.b to deter-
- 1) Continue with this instru- mine centerline X/Q ction b) Determine distance required for X/Q (miles)
- 1) Convert miles to meters i
MILES x 1609 = METERS O
No.97887210 NUMBER PROCEDURE TITLE REV/SION 00 \_/ EPIP-4.10 DETERMINATION OF X/Q PAGE 4 of 6 -
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINEO
- 3. (CONTINUED) c) Obtain from Radiological c) IF Radiological Assessment Assessment Director: Director NOT available
- 1) Wind speed 1) Obtain information from Emergency Communicator AND
- 2) Stability class d) Convert wind speed to meters per second WIND SPEED (mph) x 0.447 = WIND SPEED (meters /sec) e) With distance downwind and
\ stability class, determiner
- 1) Horizontal coefficient (c )
Y from Attachment 2,. AND Vertical coefficient (c ) from Attachment 3
- 2) Determine X/Q by follow-ing formula:
X/Q = 1 (3.14 o zo +y 758) (WIND SPEED - meter /sec)
- 4. CETERMINE X/Q NOT ON CENTER-LINE:
a) IF X/Q is required for dis- a) IF off-centerline X/Q NOT tances off the conterline of required, GO To Step 5. the plume:
- 1) Continue with this instruction O
No.97887210 NUMBER PROCEDURE TITLE . RE VISION EPIP-4.10 DETERMINATION OF X/Q PAGE 5 of 6
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT 08TAINED
- 4. (CONTINUED) b) Determine centerline X/Q from Step 2 g Step 3 c) Determine Stability Class l used in Step 2_ g Step 3_
d) Determine downwind dis-tance (miles) for center-line X/Q from Step 2_ OR Step 3 e) Using distance and stability class, determine values
' fr m Attachment 4 2 2 Y
f) Detemine distance y, perpendicular to centerline g. which X/Q is to be calcu-lated (See Attachment 5)
- 1) Convert y to meters MILES x 1609 = METERS
- 2) Determine X/Q off center-line by the following formula:
X/O centerline X/Q = 1 , a e [ (2cy) } , O a
No. 97 a s 722 o NUMER PROCEDURE TITLE ggyyg,gy EPIP-4.10 DETERMINATION OF X/Q PAGE 6 of 6 i
-- STEP ACTION / EXPECTED RESPONS~c RESPONSE NOTOBTAINEO i
- 5. TERMI?! ATE PROCEDURE EPIP-4.10:
/ a) COMPLETiD BY:
DATE: TIME: l 4 h i l l l J l l END i i f l
No.97887220
- NUMBER A TTACHMENT TITLE REVISION 4
EPIP-4.10 00 j ATTACHMENT X/Q (SEC/M*) PAGE ' i 1 WIND SPEED = 1 MILE PER HOUR 1 of 2 DISTANCE (MILES) A B C D E F G Site Boundary 4.82 E-5 1.61 E-4 3.28 E-4 7.54 E-4 1.20 E 87 E-3 2.44 E-3 0.50 1.16 E-5 5.84 E-5 1.49 E-4 3.88 E-4 7.02 E-4 1.31 E-3 2.02 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._20E-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 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 2.25 5.90 E-7 1.30 E-6 1.10 E-5 4.00 E-5 8.80 E-5 2.00 E-4 5.06 E-4' 2.50 5.40 E-7 9.90 E-7 9.30 E-6 3.40 E-5 7.60 E-5 1.80 E-4 4.40 E-4 2.75 4.90 E-7 7.60 E-7 7.90 E-6 2.90 E-5 6.60 E-5 '1.50 E-4 3.90 E-4 2-3.00 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 ' 3.50 4.00 E-7 5.30 E-7 5.30 E-6 2.00 E-5 4.80 E-5 1.10 E-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-6 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-5 2.30 E-4 4 4.50 3.20 E-7 4.20 E-7 3.50 E-6 1.40 E-5 3.'40 E-5 8.00 E-5 2.10 E-4 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 5.00 2.90 E-7 3.80 E-7 2.90 E-6 1.20 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 1.10 E-5 2.80 E-5 6.50 E-5 1.70 E-4 ( 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-5 1.60 E-4 l 5.75 2.50 E-7 3.40 E-7 2.30 E-6 9.80 E-6 2.40 E-5 5.80 E-5 1.60 E-4
4 . at ro.stee m o c , w . _[.-- NUMBEh A TTACHMENT TITLE REVISION EPIP-4.10 00 A TTACHMENT X/2 (SEC/M*) PAGE (
- 1 WIND SPEED = 1 MILE PER HOUR 2 of 2 DISTAfiCE (MILES) A B C D E F G 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 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 4.70 E-5 1.30 E-4 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 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-5 1.10 E-4 e 8.00 1.90 E-7 2.50 E-7 1.30 E-6 6.00 E-6 1.60 E-5 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 1.50 E-5 3.70 E-5 1.00 E-4 1 8.50 1.80 E-7 2.40 E-7 1.20 E-6 5.50 E-6 1.50 E-5 3.50 E-5 9.60 E-5 8.75 1.70 E-7 2.30 E-7 1.10 E-6 5.30 E-6 1.40 E-5 3.40 E-5 9.30 E-5 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-5 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 8.40 E-5 9.75 1.60 E-7 2.10 E-7 9.60 E-7 4.50 E-6 1.20 E-5 3.00 E-5 8.10 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 O c
N) 97887223 NUMBER A TTACHMENT TITLE REVISION EPIP-4.10 00 A TTACHMENT
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1 Ms.orserano NUNDER ~ A TTACHMENT TITLE REVISION-EPIP-4.10 00 4 A TTAC# MENT VERTICAL DISPERSION COEFFICIENT - o-z PAGE 3 1 of 1 b ) 3 a 10 3 2
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' C-SLIGHTLY UNSTABLE 5 D-NEUTRAL ! [ / E-SLIGHTLY STABLE F-MODERATELY STABLE 2
i 0 10 102 2 5 10 3 2 5 10" 2 5 10 5 DISTANCE FROM SOURCE (meters) 4 O k
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No. 97887220 NUMBER A TTACHMENT TITLE REVISION EPIP-4.10 00 2 A TTACHMENT 7 PAGE 4 FOR STABILITY CLASS A 1 of 7 FOR STABILITY CLASS A 1.00E4
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no.enenso NUMBER A TTACHMENT TITLE REVISION EPIP-4.10 y73 00
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FOR STABILITY CLASS B 4 2 of 7 4 e a FOR STABILITY CLASS 8 1.00E 44 1.00E45 k ( an k h h N s N 1.00E 06
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1.00E-07 0 2 4 6 8 10 X - DISTANCE DOWN WIND (MILES) O
N3.97887220 NUMBER A TTACHMENT TITLE REVISION EPIP-4.10 00 1/ 2 (g) 2 A TTACHMENT FOR STABILITY CLASS C #d6f 4 3 of 7
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Ns.97887220 NUMBER A TTACHMENT TITLE REVISION EP1P-4.10 2 00 1/2 y
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FOR STABILITY CLASS D 4 4 of 7 FOR STABILITY CLASS D 1.00E44
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N3.o7es72 o NUMBER A TTACHMENT TITLE REVISION EPIP-4.10 g 2 00
# "######I ####
FOR STABILITY CLASS F
~4 6 of 7 FOR STABILITY CLASS F 1.00E43 1.00E 04 - -
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No. 97887220 NUMBER A TTACHMENT Tl!LE REVISION b Q EPIP-4.10 g 2 00
#II######I ####
FOR STAB 1LITY CLASS G 4 7 of 7 O d FOR STABILITY CLASS G 1.00E43
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- ree.enenso O NUMBER A TTACHMENT ' TITLE REVISION og EPIP-4.10 LO ON ppgg A TTACHMENT 5
1 of 1 PLAhT g < x 3e q y g 0FF CENTERbNE
- LOCATION
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No. 978872 30 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE C) V NUMBER PROCE00RE TITLE REVISION 00 EPIP-4.ll FOLLOW-UP OFFSITE RELEASE ASSESSMENT PAG (With 10 Attachments) 1 of 10 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 O_RRmembers of Dose Assessment Team. ENTRYCONDITIONS [ Any of the following:
- 1) Initiation by EPIP-4.01, Radiological Assessment Director Controlling Procedure.
- 2) Initiation by EPIP-4.03, Dose Assessment Controlling Procedure.
REVISION RECORO REV. 00 PAGE(S): Entire Procedure DATE.Al 2 8 1982 REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: REV. PAGE (S) : DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: APPROVAL RECOMMENCE 0 APPROVE 0 CA TE V n d4 JUL 2 S W C4 AIRMAN STA TION NUCLEAR SAFETY AND OPERA TING COMMITTEE
No. 9788722 0
\ NUM9ER PROCEDURE TITLE REVISION 00 EPIP-4.11 FOLLOW-UP OFFSITE RELEASE ASSESSMENT PAGE 2 of 10
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 1. INITIATE PROCEDURE:
a) Initiated By: Date: Time:
- 2. ASSESSMENT OF PERCENT TECHNICAL SPECIFICATION:
a) IF event - UNUSUAL EVENT OR a) IF the event is a SITE OR ALERT: GENERAL emergency:
- 1) Determine percent of Tech 1) GO TO Step 3_.
Spec Limit
- 2) Continue with this instru-ction b) IF liquid release: b) E gaseous release:
- 1) Obtain sample results 1) GO TO Step 2.c.
(uci/ml) and log on Attachment 1
- 2) Divide sample results (uCi/ml) by respective MPC AND log on Attachment 1
- 3) Sum results from Step 2.b.2 AND log on Attachment 1 i 4) IF F sample from Step 1 4) IF sample obtained from plant obtained from discharge system, GO TO Step 2.b.6.
canal, determine the per-cent Tech Specs by: Step 2.b.3 x 100 = % Tech Spec i 5) GO TO Step ~9 v
Peo.97887230 NUMBER PROCEDURE TITLE REVISION C) EPIP-4.11 FOLLOW-UP OFFSITE RELEASE ASSESSMENT 00 PAGE 3 of 10
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 2. (CONTINUED)
- 6) Obtain number of operating circulating water pumps from operations
- 7) Obtain the release rate (gpm)
- 8) Determine the % Tech Spect Step 2.b.3 x GPM x 5.0 E-4 = % T. S.
# of Circulating Water Pumps
- 9) GO TO Step ~9 O c) E gaseous release:
- 1) Continue with this instru-
- etion ,
d) Determine percent Tech Spec d) E Tech Specs are to be Limit for noble gases: determined for radiciodines and particulates:
- 1) Obtain sample results of noble gases 1) GO TO Step 2.e.
- 2) Log activity on Attachment 2
- 3) Obtain flow rate of release 3) IF NO MPC is listed, (CFM) from Radiological determine MPC from Assessment Director 10CFR20
- 4) Divide activity by PSC AND l 5) Sum Column i
l a
f40.9786722O NUMBER PROCEDURE TITLE REVISION 00 EPIP-4.11 FOLLOW-UP OFFSITE RELEASE ASSESSMENT PAGE 4 of 10
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAlf!ED
- 2. (CONTINUED)
- 6) Use equation 1 on Attachment 2 to determine percent Tech Spec Limit, for noble gases e) Detertaine percent Tech Spec Limit for radiciodines and particulates
- 1) Sum activity of all radio-iodines and particulates, with halflives GREATER THAN 8_ days
- 2) Use equation 2 on Attachment 2, 3 to determine percent of Tech
) Spec Limits
- 3. DETERMINE OFFSITE DOSE RATE:
a) Offsite dose rate may be determined by the following, in order of preference:
- 1) Sample results, GO TO Step 9,
- 2) Normal range monitors, GO TO Step 4_
- 3) High Range Monitors, GO TO Step 5, 4 DETERMINE OFFSITE DOSE WITH NORMAL RANGE MONITORS:
a) Determine Offsite Dose with a) IF sample analysis avail-Normal Range Monitor E sample able: analysis is NOT available
- 1) GO TO Step 9_.
O V
No. 97857210 NUMBER PROCEDURE TITLE REVISION 00 , EPIP-4.ll FOLLCTii-UP OFFSITE RELEASE ASSESSMENT - PAGE 5 of 10
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 4. (CONTINUED) b) IF release thru ventilation b) IF monitors are offscale:
system OR air ejector
- 1) GO TO_ Step 5_
AND QR, Any of the folicwing monitors are onscale: IP release thru main steam:
- 1) GO TO Step 6.
OR
- 1) Vent Vent (VG-104) IP release is thru AFWPT:
R O_R 1) GO TO Step 7
- 2) Process Vent (GW-102)
QR
- 3) Air Ejector (SV-111, 211) c) Obtain the following from c) E Director NOT available Radiological Assessment Director: 1) Request infonation from i Emergency Manager
'. 1) Number of monitor of l interest 1 i
- 2) Count rate
- 3) Flow rate (CFM)
- 4) Log information on Attachment 3 d) Obtain latest X/Q for Site Boundary from EPIP-4.03 1
O
No. 31s s1310 NUMBER PROCEDURE TITLE REVISION
/' 00 4
V) t EPIP-4.11 FOLLOW-UP OFFSITE PILEASE ASSESSPINT PAGE 7 of 10
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 5. (CONTINUED)
- 1) Continue with this instru-ction OR F release is thru the AFWPT, GO TO Step 7.
b) Log date, time and monitor of interest on Attachment 4 c) Obtain the mR/hr of monitor c) IF Radiological Assessment and the flow rate (CFM) from Director NOT available Radiological Assessment Director 1) Request mR/hr from Emer-gency Manager f] ( ,/
- 1) Convert mR/hr to uCi/cc using Attachment 5
- 2) Log flow rate (CFM) and uCi/cc on Attachment 4 d) Obtain X/Q for Site Boundary EPIP-4.03 e) Determine mR/hr at Site Boundary:
MR i uCi/cc x CFM x X/Q x 8.50E-1 =g f) GO TO Step 8
- 6. DETERMINE OFFSITE DOSES WITH MAIN STEAM:
a) Log date, time and monitor of interest on Attachment 6 b) Obtain the mR/hr from Radio- b) IF Radiological Assessment logical Asse 9 ment Director: Director NOT available: , s O 1 l
he. s7ssnie NUMBER PROCEDURE TITLE REVISION 00 EPIP-4.11 FOLLOW-UP OFFSITE RELEASE ASSESSMENT PAGE 8 of 10
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 6. (CONTINUED)
- 1) Convert mR/hr to uCi/cc 1) Request mR/hr from Emer-using Attachment 8 gency Manager
- 2) Log on Attachment 6 c) Obtain flow rate
- 1) IF Main Steam Safety Valve 1) IF NO valve has lifted, lifts _OR may potentially project release using lift request number of only one ialve.
valves from Radiological Assessment Director
- 2) Determine flow rate from
. Attachment 7, and log on d Attachment 6 d) Obtain X/Q for Site Boundary from EPIP-4.03:
- 1) Log on Attachment 6, e) Determine mR/hr:
uCi/cc x FLOW RATE (m3/sec) x 1.8E+3 x X/Q = g HR f) Gf TO Step 8,
- 7. DETERMINE OFFSITE DOSE WITH AFWPT MONITOR:
I a) IF main steam is unisolated a) IF main steam supply to the continue with this instru- AFWPT is isolated etion
- 1) Consider NO release from this pathway O
'u j -
e No. 97887210 NUMBER FROCEDURE TITLE REVISl0N O 00 EPIP-4.11 FOLLOW-UP OFFSITE RELEASE ASSESSMENT PAGE 9 of 10
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 7. (CONTINUED) b) Log date, time and monitor of interest on Attachment 6 c) Obtain mR/hr from Radio- c) E Radiological Assessment logical Assessment Director Director NOT available
- 1) Log on Attachment 6, 1) Request mR/hr from Emer-gency Manager d) Obtain X/Q from EPIP-4.03
- 1) Log on Attachment 9, e) Determine dose conversion factor from Attachment 7 f) Determine Site Boundary dose rate:
MR/HR (Monitor) x X/Q x 6.32 x DOSE COINERSION = MR/HR FACTOR
- 8. DETERMINE THYROID DOSE RATE:
a) Obtain Whole Body dose rate (mR/hr) from Steps 3 thru 7 b) Determine conversion factor listed on Attachment 10 c) Determine Thyroid dose rate: DOSE RATE (Whole Body) x CO!NERSION FACTOR = DOSE RATE (Thyroid) d) GO TO Step p O l 1
Peo. 97887210 NUMBER PROCEDURE TITLE REVISION b\ 00 V EPIP-4.ll FOLLOW-UP OFFSITE RELEASE ASSESSMENT PAGE
, 10 of 10 1 - STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 9. DETERMINE OFFSITE DOSE RATE FROM SAMPLE RESULTS:
a) Obtain equivalent activity (Ci/sec) for I-131 and Xe-133 from EPIP-4.03 b) Obtain current X/Q for Site Boundary from EPIP-4.03 c) Determine cose rate
- 1) Thyroid Oi/sec (I-131) x X/Q x 1.85 E + 9 = MR/HR O 2) htole Body Ci/sec (Xel33) x X/Q x 4.20 E + 4 =
MR/HR
- 10. RETURN TO CONTROLLING PROCEDURE:
a) Upon completion of this procedure:
- 1) Return to EPIP-4.03, Dose Assessment Controlling Procedure
- 11. TERMINATE EPIP-4.lls a) COMPLETED BY:
DATE: TIME: END
no. essenso NUMBER A TTACHMENT TITLE REVISION O EPIP-4.11 A TTACHMENT
% TECH SPEC LIQUID JO PAGE 1 WORKSHEET 1 of 1 (uCi/ml)i ISOTOPE UNRESTRICTED - MPC MPC1 H-3 3.00 E-3 KR-85 4.00 E-5 KR-85m 4.00 E-5 KR-P' 4.00 E-5 KR-80 4.00 E-5 Xe-131m 4.00 E-5 Xe-133 4.00 E-5 Xe-133m 4.00 E-5 Xe-135 4.00 E-5 MN-54 1.00 E-4 MN-56 1.00 E-4
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%.97ss7220 NUMBER A TTACHMENT TITLE REVISION D EPIP-4.11, 00 A TTACNMENT MAIN STEAM MONITOR PAGE FLOW RATES 7 1 of 1 I_F ONLY ONE RELIEF VALVE WAS LIFTED, DETERMINE THE NUMBER OF THE VALVE AND OBTAIN THE FLOWRATE (m /sec):
RELIEF VALVES FLOW RATE DECAY HEAT HCV-MS-104/204 0.611 m /see 1.33 m /see i PORV RV-MS-101/201 A,B,C SAFETY VALVE SV-MS-101/201 A,B,C 1.10 m /see SAFETY VALVE SV-MS-102/202 A,B,C 2.59 m /see f%d SAFETY VALVE SV-MS-103/203 A,B,C 2.59 m /sec SAFETY VALVE SV-MS-104/204 A,B,C 2.59 m /sec SAFETY VALVE SV-MS-105/205 A,B,C 2.59 m /see E MORE THAN ONE VALVE HAS LIFTED, THEN: TOTAL FLOW = F
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-% NUMBER
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No.97887224 NUMBER A TTACHMENT TITLE REVISION EPIP-4.11 00 A TTACNMENT THYROID DOSE CONVERSION FACTORS FACE 10 1 of 2 ACCIDENT TIME AFTER ACCIDENT CONVERSION (HOURS) FACTORS
- 1. LOCA 0.5 27 1.0 32 1.5 36 2.0 41 2.5 46 3.0 51 3.5 57 4.0 62 4.5 69 5.0 75 6.5 98 8.0 123 10.0 158 12.5 209 15.0 258 24.0 389 48.0 707 72 758
Peo. 97887229 NUMBER A TTACHMENT TITLE REVISION EPIP-4.11 00
)
A TTAC# MENT THYROID DOSE CONVERSION FACTORS PAGE 10 2 of 2 THYROID CONVERSION FACTORS ACCIDENT FILTERED (CHARCOAL) UNFILTERED
- 2. Primary Gas Release 2.76E-2 2.76E-1
- 3. Steam Generator Tube Rupture 1.30E+2
! 4. Fuel Handling Accident 6.59E+1 5.58E+2
- 5. Waste Gas Decay Tank 7.67E-3 7.67E-2 i
l I l
- 6. Main Steam Line Break (with prior primary to secondary leakage) 3.79E+1 2.67E+2 i
l l l
__ ._ _. . .m _
*do.97847230
. VIRGINIA ELECTRIC AND POWER COMPANY 4 SURRY POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE O NUMBER PROCEDURE TITLE REVISION 00 EPIP-4.12 CFFSITE ENVIRONMENTAL MONITORING MGE INSTRUCTIONS (With 2 Attachments) 1 of 7 PURPOSE Provide guidance to the Dose Assessment Team to direct Offsite Monitorir.g Teams to
- 1) Confirm radiological release
- 2) Track release
- 3) Determine radiological composition of release i
USER Dose Assessment Team Members. ENTRY CONDITIONS Any one of the following:
- 1. Release of radioactive materials with a SITE or GENERAL em'rgency condition and EOF is NOT activated.
- 2. Any other time which the Radiological Assessment Director deems it necessary.
- 3. Activation by another EPIP.
i i REVISION RECORD REV. 00 PAGE(S): Entire Procedure DATE:JULg 3 gg REV. PAGE (S) : DATE: REV. PAGE(S): DATE: REV. PAGE(S): DATE: ,i REV. PAGE(S): DATE: REV. PAGE (S) : DATE: REV. PAGE(S): DATE: Q APPROVAL RECOMMENDED APPROVEO DA TE [< A JUL2 % 138?. w CdAIRMAN STA TION NUCLEAR SAFETY i AND OPERA TING COMMITTEE
No.97887210 NUMBER PROCEDURE TITLE REVISION
) 00 J EPIP-4.12 OFFSITE ENVIRONMENTAL MONITORING INSTRUCTION PAGE 2 of 7
- STEP ACTIONNXPECTED RESPONSE RESPONSE NOTOBTAINED
- 1. INITIATE PROCEDURE:
a) BY: DATE: TIFI:
- 2. ACTIVATION UPON SITE OR GENERAL EMERGENCY:
1 a) The procedure applicable a) F EOF is activated and moni-IF upon radioactive release and toring' teams in the field: declaration of SITE or GENERAL emergency R O_R Whenever Radiological Assess- 1) Brief Radiological ment Director deems necessary Assessment Coordinator as to the current AND location of the monitor-ing teams and data The EOF is NOT manned received
- 2) Inform Monitoring Teams to receive instructions and report data to the Radiological Assessment Coordinator at the EOF.
- 3) GO TO Step _13_.
- 3. REVIEW PROJECTED DATA:
a) Review the projected release data b) Obtain from the Radiological i Assessment Director the current meteorological conditions:
No. 97887210 NUMBER PROCEDURE TITLE REVISION 00 ( EPIP-4.12 OFFSITE ENVIRONMENTAL MONITORING INSTRUCTION PA GE 3 of 7
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINEO
- 3. (CONTINUED)
- 1) Wind speed
- 2) Wind direction
- 3) Stability class
- 4. ASSESS MONITORING NEEDS:
a) Initially only one monitor-ing team may be available b) Use first monitoring team to initially:
,, / 1) Confirm release
- 2) Confinn direction of plume
- 3) Determine radiological composition c) Minimum of two monitoring teams desirable:
- 1) Locate one team near site and the other downwind at distance from plant
- 5. ESTABLISH RADIO CONTACT:
a) Initiate EPIP-4.19, Use of a) IF radio communic.ations Radios for Health Physics NOT able to be established: Monitoring:
- 1) Request assista!:e from
- 1) Establish radio communi- Radiological Assessment cation with team using Director radiophone
)
v
No. 97887210 NUMBER PROCEDURE TITLE REVISION
) 00 EPIP-4.12 OFFSITE ENVIRONMENTAL MONITORING INSTRUCTION PACE 4 of 7
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINEO s
- 5. (CONTINUED)
AND
- 2) Dispatch teams, instru-cting them to use public telephone to relay results to the TSC b) Instruct team to report data to TSC, until in-structed otherwise c) Give teams TSC telephone number
- 6. ESTABLISH MONITORING LOCATION:
a) Review Attachment 1 and 2 for for preselected monitoring locations around station b) IF preselected location b) IF, preselected locations
; is at plume centerline NOT at plume centerline, GO TO Step 6.e.
, 1) Place teams at pre-selected location c) Monitoring at locations OTilER THAN preselected locations can be identi- } fi<d using Attachment 1
- 1) Location are specified by use of Sector designa-tion and distance (miles)
' (i.e. distance of 2 miles North of plant: A-2) I i d) Locate team (s) in Jirection wind is blowing i i
No. 978872 3 0 NUMBER PROCEDURE TITLE REVISION CN oo i } v EPIP-4.12 OFFSITE ENVIRONMENTAL MONITORING INSTRUCTION PACE 5 of 7
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 6. (CONTINUED)
- 1) Wind direction from Step 3 indicates direction wind is coming from
- 7. CONFIRMATION:
a) Direct first monitoring team to the sector, near site, which is affected by plume b) Obtain the following data and/or samples, if appro- , priate
- 1) Maximum dose rate (mR/hr)
- 2) Air sample - particulate, iodine and gas
- 3) Soil sample c) Have initial confirmatory samples returned to Security Building l
- 1) Air sample should be immediately analyzed to determine Iodine / Noble Gas ratio NOTE: Unexpected readings may result from plume rise, looping or cloud meander
- 8. PLUME TRACKING:
a) Plume monitoring should continue, obtaining at a minimum, the dose rate at centerline of the plume
Peo. 97887210 NUMBER PROCEDURE TITLE REVISION C 00 V EPIP-4.12 OFFSITE ENVIRONPINTAL MONITORING INSTRUCTION PAGE 6 of 7 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 8. (CONTINUED) b) F unexpected reading occurs:
IF
- 1) Have team travel downwind a distance until plume is located c) Review the applicability of Attachment 3
- 9. FIXED ENVIRONPINTAL SAMPLERS AND TLD'S:
a) Fixed air samplers and TLD's V provide good information on the TOTAL release. Collection of these samples may provide best information after termination of release
- 10. ADDITIONAL SAMPLING:
a) Additional sampling for chronic exposure pathways is not normally within the scope of initial response b) Upon recovery phase of emergency, direct teams to obtain, as appropriate:
- 1) Milk
- 2) Water
- 3) Crop samples
)
i s s
No 97847230 NUMBER PROCEDURE TITLE REVISION O 00 EPIP-4.12 OFFSITE ENVIRONMENTAL MONITORING INSTRUCTION PAGE 7 of 7 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 11. CONTINUE MONITORING:
a) Continue Steps 7 tnru 12 until:
- 1) EOF MANNED, GO TO Step 2 OR
- 2) Release TERMINATED, GO TO Step 14 OR
- 3) E monitoring data becomes available, GO TO Step 13.
/ 12. ASSESS DATA:
a) _IF monitoring data becomes available:
- 1) Initiate EPIP-4.13, Offsite Release Assessment with Environmental Data
- 13. TERMINATE EPIP-4.12:
a) COMPLETED BY: DATE: + l TIME: END k
NUMBER A TTACHMENT TITLE REVISION l O EPIP-4.12 A TTACHMENT SECTOR MAP SURRY POWER STATIOli 00 PAGE i 1 1 of 6 1 q}c.,,
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- 00 GRID MAP SURRY P0k'ER STATION A TTACHMENT PAGE 1 2 of 6 l
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i No.97887220 NUMBER A TTACHMENT TITLE REVISION ' O EPIP-4.12 A TTACHMENT PRESELECTED MONITORING LOCATIONS 00 PAGE , 2 1 of 2 1 LOCATION DESCRIPTION
- 1. Surry Discharge TLD location at the end of the discharge structure
- 2. Hog Island Approximately 2 miles north on Route 650, from the power station
- 3. Surry Intake Low level circulating water pumps at be-ginning of intake canal
- 4. Scotland Wharf Surry side James River ferry on Route 31
\
North
- 5. Colonial Parkway From Jamestown, approximately 3, miles east on Colonial
- 6. Kingsmill From Jamestown approximately 6, miles east on Colonial Parkway. Location is prior to Halfway Creek.
, 7. Fort Sustis At Fort Eustis, take Lee Boulevard to Harrison Road. Location approximately 1 mile on Harrison Road.
- 8. Bacons Castle Intersection of Route 10 and Route 617
- 9. Alliance Intersection of Route 634 and Route 636 off Highway 10
- 10. Jamestown Jamestown (north), side James River k
No 7887220 NUMBER A TTACHMENT TITLE REVISION EPIP-4.12 00 sj PRESELECTED MONITORING LOCATIONS A TTACHMENT PAGE 2 2 of 2 LOCATION DESCRIPTION
- 11. Dow Chemical Substation at Dow Chemical Plant off i Route 60
- 12. Lee Hall On Route 60, approximately l_ mile North of intersection of Routes 238 and 60
- 13. Busch Gardens Anheiser Busch Brewery on Route 60
- 14. Route 10 - 676 Intersection of Route 10 and Route 676 (short cut to station off Route 10)
O V 15. Smithfield Substation Intersection of Route 10 and Route 258
- 16. Newport News Substation Jefferson Avenue downtown to 34th Street, turn right; cross bridge and turn right.
Substation located on right. l i (
. .. _ - _ . _ _ . . _ _ . . = , _ _ _ _ . _ - . . . _ _ . .__
No. 97887230 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCEDURE TITLE REVISION 00 j EPIP-4.13 OFFSITE RELEASE ASSESSMENT PAGE WITH ENVIRONMENTAL DATA (Hith 4 Attachments) PURPOSE ? Confirm onsite dose projections, using Environmental Monitoring data. } USER Radiological Assessment Director or Members of Dose Assessment. Team. ENTRY CONulTIONS O Any of the following:
- 1) Activation by EPIP-4.03, Dose Assessment Controlling Procedure; a
i i 2) Activation by EPIP-4.12, Offsite Environmental Monitoring Instructions. I ? l l REVISION RECORD REV. 00 PAGE (S) : Entire Procedure DATE:JUL 291982 j REV. PAGE (S) DATE: REV. PAGE(S) DATE: i REV. PAGE(S) DATE:
- REV. PAGE(S) DATE
REV. PAGE (S) DATE: l REV. PAGE(S) DATE: APPROVAL RECOMMENDEO APPROVED UA TE
\ .
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HAIRMANSTA TION NUCLEAR SAFETY N 2 0 1992 l AND OPERA TING COMMITTEE i i r s ~w - + - - - - - - - , - - , - - - - - - --- -- - - - - - - - - ,=
No. 9788721e NUMBER PROCEDURE TITLE REVISION ' 00 EPIP-4.13 OFFSITE RELEASE ASSESSMENT PACE WITH ENVIRONMENTAL DATA 2 of 8
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 1. INITIATE PROCEDURE:
a) Initiated By: Date: Time:
- 2. USE OF ENVIRONMENTAL DATA:
a) Offsite Environmental Data a) Continue with this instru-may be used to confirm dose etion. projection:
- 1) GO TO Step 3 OR V -
b) IF onsite release data b) IF onsite release data j from monitors and/or from monitors and/or vample analysis NOT sample analysis IS available: available:
- 1) Use Environmental data 1) Do NOT estimate Source to determine Source Term Term from environmental (Ci/sec) data AND
- 2) GO TO Step 8, 2) GO TO Step 12.
NOTE: Sample analysis data of environmental sc.mple should be used, when available, versus field analysis in determining offsite dose rate. .
- 3. CONFIRM DOSE PROJECTIONS:
a) Use offsite dose rate a) IF Source Term (Ci/sec) measurment to confirn _ __ calculations are needed projected dose rate using environmental data: OR 1) GO TO Step 8.
No. 97887210 NUMBER PROCEDURE TITLE REVISION O 5 ') 00
\-s EPIP-4.13 OFFSITE RELEASE ASSESSMENT WITH ENVIRONMENTAL DATA FA6f 3 of 8
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 3. (CONTINUED)
Establish real time dose rate offsite b) Insure measurements OR samples are taken at centerline of plume c) Dose rate may be obtained from:
- 1) Direct Measurements gR
- 2) Sample Analysis Data
( )
- 4. DETERMINE WHOLE BODY DCSE FROM DIRECT RADIATION READINGS:
a) Obtain from the monitoring a) IP dose rates not NOT from teams the centerline: centerline:
- 1) Log date, time, location 1) GO TO Step 6.
and dose rate on Attach-ment 1 2) Estimate centerline data b) Dose rate from Step 4.a may be considered the Whole Body 3) Return to Step 4.a.l. Dose Rate l c) Log dose rate on Attachment 1 l l S. DETERMINE THYROID OFFSITE DOSE RATE FROM SAMPLE ANALYSIS: a) Determine offsite dose rate a) IF data from air sample is to the Thyroid by using NOT yet available analysis from air sample taken at centerline of the 1) GO TO Step 6. the plume
\
L l
No. 97847210 F NUMBER PROCEDURE TITLE REVISION EPIP-4.13 OFFSITE PILEASE ASSESSMENT WITH ENVIRONMENTAL DATA PAGE 4 of 8
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 5. (CONTINUED) b) If sample analysis given in b) IF, sample data is given in counts per minute: uCi/ml
- 1) Obtain background count 1) GO TO Step 5.c.
rate (cpm) from monitor-ing team (s)
- 2) Determine the net counts per minute:
SAMPLE (cpm) - BACKGROUND (cpm) = NET (cpm)
- 3) Determine activity g
NET (cpm) x 3.18 E-ll = ACTIVITY I-131 (uCi/ml)
%/
c) Determine Thyroid dose rate: ACTIVITY (uci/ml) x 1.85 E+9 = MR/HR d) Log date, time, location and Thyroid dose rate on Attachment 1
- 6. OFF-CENTERLINE DOSE RATES:
a) IF dose rates from Step 4 and a) IF dose rates from Step 4 Step j[ were taken off-center- and Step j[ are taken from line centerline GO TO Step 7.
- 1) Initiate EPIP-4.10, Determination of X/Q
- 2) Determine X/Q at the perpen-dicular distance from sample location on the centerline of
- plume
- 3) Determine X/Q of the sample location
Peo.97887210 NUMBER PROCEDURE TITLE REVISION 00 D EPIP-4.13 OFFSITE RELEASE ASSESSMDrr WITH ENVIRONMENTAL DATA PAGE 5 of 8
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINEN
- 6. (CONTINUED)
- 4) Return to Step 6.b of this procedure b) Determine estimated centerline dose rate:
X/Q (SAMPLE LOCATION) x DOSE RATE (MR/HR) = DOSE RATE MR/HR X/Q (CENTERLINE) - c) Log date, time, location and dose rate on Attachment 1
- 1) Note in the remarks column
, that the sample was taken V off centerline
- 7. TRANSMIT DATA:
a) Upon completion of Attachment l_:
- 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 the Source Term (Ci/sec) of the NOT required, GO TO release Step M.
, b) Insure measurements or samples b) If data is NOT from the i taken are from the centerline centerline of the plume: of the plume
- 1) GO TO Step 6 to estimate centerline data AND
- 2) Return to Step 8.c.
! OT
- U-
No. 974 s 7210
. s NUMBER PROCEDURE TITLE 'i REVISION 00 EPIP-4.13 OFFSITE RELEASE ASSESSMENT-WITH E!NIRONMENTAL DATA FACE 6 of 8 l
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT CBTAINED o ,
- 8. (CONTINUED) c) Source Term may be estimated by:
- 1) Direct Measurements, GO TO Step 9, -
OR
~
- 2) Sample Analysis Data, GO TO.
Step M ,
- 9. DETERMINE SOURCE TERM FROM DIRECT MEASUREMENTS:
a) Obtain centerline dose rate a) IF, F dose rate measurements measurements: are NOT from centerline s of the plume: ,
- 1) Log location, time and dose rate on Attachment 1) GO TO Step 6 to estimate 2 centerline data
- 2) Obtain the current wind 2) Return to Step 9.a.l. s speed and stability class b) Determine the conversion factor:
- 1) From Attachment 3, IF measurement taken at' - ' '
preselected monitoring points, at centerline of plume s 0,R
- 2) Attachment 4, E NOT at preselected centerline
^
c) Determine source terms MR/HR x 3.05 E-5 x WIND SPEED x CO!NERSION FACTOR = Ci/sec -
No,siserano RJMBER PROCEDURE TITLE REVISION 00 EPIP-4.13 OFFSITE RELEASE ASSESSMENT WITH ENVIRONMENTAL DATA PACE 7 of 8
- S(EP ACTION / EXPECTED RESPONSE RESPONSE NOT 08TAINE0
- 9. (CONTINUED) d) Log results on Attachment 2 ,
- 10. DETERMINE SOURCE TERM FROM SAMPLE ANALYSIS:
a) Insure sample data is from a) If sample data is not from centerline of the plume centerline of plume l 1) GO TO Step 6 to estimate centerline data (use (uCi/ml) instead of data rate) AND
- 2) Return to Step 10.b.
b) Obtain uCi/ml measurements b) IF, sample data received in at sample locations counts per minutes
- 1) Log location, time, and 1) GO TO Step 5
~ activity on Attachment 2 i 2) Determine activity ! 2) Obtain the current wind (uci/ml)
- speed and stability class
! from Dos Assessment Team 3) Return to Step lO.b. l Leader l c) Obtain the conversion factor from Attachment 4, using the centerline distance from the plant d) Determine the source term: ACTIVITY x WIND SPEED x CONVERSION FACTOR = Ci/sec i .s (
uc.sses12to NUMBER PROCEDURE TITLE REVISION I 00 EPIP-4.13 OFFSITE PILEASE ASSESSMENT WITH EINIRCIWINTAL DATA PAGE 8 of 8
- STEP -
ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 11. TRANSMIT DATA:
a) Upon completion of Attachment 2
- 1) Inform Dose Assessment Team Leader of results
- 12. CONTINUED :.SSESSMENf:
a) E monitoring teams are a) IF, teams are to remain in to be relocated: the same location:
- 1) GO TO Step M to terminate 1) GO TO Step 12.b.
. this procedure f 2) Initiate EPIP-4.12, Offsite Monitoring Instruction b) IF EOF NOT activated b) IF emergency has terminated OR OR E release NOT terminated: E EOF activated:
- 1) Return to Step 3_ and 1) GO TO Step M.
repeat assessment when data received
- 13. ADMINISTRATION:
a) Return all procedures and Offsite data to the Radio-logical Assessment Director
- 14. TERMINATE EPIP-4.13:
a) COMPLETED BY: DATE: TIME: b y END
no. orsafaro NUMBER A TTACHMENT TITLE REVISION (- ,;
- EPIP-4.13 00
~/ OFFSITE E!NIRCr; met;TAL DATA SHEET A TTACHMENT PAGE 1 1 of 1 DATE TIME LOCATIOt3 WIiOLE BODY Tl!YROID DOSE RATE DOSE RATE (mR/hr) (mR/hr)
FIMARKS: f~%. U) r'S 4 l
%)
s
No. 97887220 A CHMENT TlHE ggyggggy EPIP-4.13 SOURCE TERM A TTACHMENT WORKSHEET PAGE 2 1 of 1 I a MR I-131 XE-133 WIND STABILITY Ci/SEC Ci/SEC TIME OF LOC. TIME HR (uCi/ml) (uCi/ml) SPEED CLASS (Xe-133) (I-131) RELEASE i i 1 1 O i I, m- - , . - - - + - - - , - - _*- _w,,y -- -, , - , _
Ns.97887223 NUMBER A TTACHMENT TITLE REVISION EPIP-4.13 00 FACTORS FOR PRESELECTED A TTAC# MENT #### MONITORING LOCATIONS 3 1 of 1 STABILITY CLASS A B C D E F G Surry Discharge 4.42E5 2.70E4 6.85E3 2.55E3 1.41E3 6.80E2 3.67E2 Hog Island 1.53E6 3.01ES 7.15E4 2.04E4 9.30E3 4.19E3 1.86E3 Surry Intake 1.01E6 1.33E5 3.23E4 1.01E4 4.91E3 .2.27E3 1.07E3 Scotland L'harf 3.78E6 1.75E6 3.95ES 9.30E4 3.68E4 1.58E4 6.05E3 Colonial Parkway 3.09E6 1.19E6 2.71E5 6.65E4 2.72E4 1.18E4 4.65E3
) Kingsmill 3.22E6 1.28E6 2.92E5 7.10E4 2.89E4 2.25E4 4.92E3 Fort Eustis 3.15E6 1.24E6 2.81E5 6.90E4 2.80E4 1.21E4 4.80E3 Bacons Castle 3.31E6 1.36E6 3.08E5 7.45E4 3.02E4 1.30E4 5.10E3 Alliance 3.59E6 1.59E6 3.59E5 8.55E4 3.41E4 1.47E4 5.70E3 Jamestown 3.78E6 1.75E6 3.95E5 9.30E4 3.68E4 1.58E4 6.05E3 Dow Chemical 3.28E6 1.33E6 3.03E5 7.35E4 2.98E4 1.29E4 5.05E3 Lee Hall 4.57E6 2.53E6 5.65E5 1.28E5 4.92E4 2.08E4 7.75E3 Busch Gardens 4.08E6 2.04E6 4.57ES 1.06E5 4.15E4 1.77E4 6.70E3 Route 10-676 4.33E6 2.28E6 5.10E5 1.17E5 4.53E5 1.92E4 7.25E4 Smithfield Substa. 7.85E6 7.30E6 1.58E6 3.19E5 1.13E5 4.62E4 1.59E4 N. N. Substa. 9.55E6 1.06E7 2.28E6 4.40E5 1.51ES 6.10E3 2.04E4 0
O
i reo. otes nro NUMBER A TTACHMENT TITLE REVISION EPIP-4.13 -00 FACTORS FOR OTHER THA!; A TTACNMENT PRESELECTED MONITORING LOCATIONS PAGE 4 1 of 1 Use the following Equation to obtain the conversion factor for other than preselected monitoring locations: i}}