ML20081A810
| ML20081A810 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 09/29/1983 |
| From: | Cox F, Saunders R VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML18141A168 | List: |
| References | |
| PROC-830929-01, NUDOCS 8310260436 | |
| Download: ML20081A810 (127) | |
Text
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I
. y REVISIONS TO SURRY POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURES Enclosed are recently revised pages to the Surry Power Station Emergency Plan (
Implementing Procedures. Please take the following actions in order to keep your manual updated with the most recent revisions.
l EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING PROCEDURE Remove and Destroy Enter Pages 1 of 30 through Pages 1 of 31 through 30 of 30 31 of 31 Dated 07-29-82 Dated 09-23-83
^
EPIP-4.09 SOURCE TERM ASSESSMENT Remove and Destroy Enter Pages 1 of 9 through Pages 1 of 10 through 9 of 9 & Attachment 4 10 of 10 & Attachment 4 Dated 03-03-83 Dated 09-23-83 EPIP-4.12 0FFSITE ENVIRONMENTAL MONITORING INSTRUCTIONS Remove and Destroy Enter Pages 1 of 7 through Pages 1 of 8 through 7 of 7 & Attachment 2 8 of 8 & Attachment 2 Dated 02-24-83 Dated 09-23-83 EPIP-4.13 0FFSITE RELEASE ASSESSMENT WITH ENVIRONMENTAL DATA Remove and Destroy Enter Pages 1 of 8 through Pages 1 of 9 through 8 of 8 and Page 1 of 1 9 of 9, Page 1 of 1 of Attachment 3 of Attachment 3 and Dated 07-29-82 Attachment 5 Dated 09-23-83 EPIP-4.15 ONSITE MONITORING Remove and Destroy Enter Pages 1 of 9 and Pages 1 of 9 and Page 1 of 1 of Page 1 of 1 of Attachment 3 Attachment 3 4
Dated 02-24-83 Dated 09-23-83 g -
8310260436 831021 ._ W PDR ADDCK 05000280 F PDR
EPIP-4.16 0FFSITE MONITORING Remove and Destroy Enter
' Pages 1 of 11 through Pages 1 of 12 through 11 of 'il, Attachment 2 12 of 12. Attachment 2 and Attachment 4 and Attachment 4 Dated 02-24-83 Dated 09-23-83 EPIP-4.18 MONITORING OF EOF .
Remove and Destroy Enter Page 1 of 8 and Page 1 of 8 and Attachment 3 Attachment 3 Dated 02-24-83 Dated 09-23-83 EPIP-4.22 POST ACCIDENT SAMPLING OF CONTAINMENT AIR Remove and Destroy Entire Procedure Dated 02-24-83 EPIP-4.23 POST ACCIDENT SAMPLING OF REACTOR COOLANT Remove and Destroy Enter j Pages 1 of 14 through Pages 1 of 14 through
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14 of 14 14 of 14 Dated 02-24-83 Dated 09-23-83 EPIP-2.01 NOTIFICATION OF STATE AND LOCAL GOVERNMENTS i
j Remove and Destroy Enter i
Pages 1 of 17, 5 of 17 Pages 1 of 17, 5 of 17, l 8 of 17 and 12 of 17 8 of 17 and 12 of 17 i Dated 08-25-83 Dated 09-29-83 EPIP-3.01 CALLOUT OF EMERGENCY RESPONSE PERSONNEL Remove and Destroy Enter Page 1 of 3 Pages Page 1 of 3, Pages 3 of 6 and 4 of 6 of 3 of 6 and 4 of 6 of Attachment 1 Attachment 1 Dated 06-17-83 Dated 09-29-83 l
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EPIP-5.03 PERSONNEL ACCOUNTABILITY Remove and Destroy Enter Pages 1 of 7, 2 of 7 Pages 1 of 7, 2 of 7
- 3 of 7, Pages 2 of 3 3 of 7 Pages 2 of 3 and 3 of 3 of and 3 of 3 of Attachment 1 Attachment 1 Dated 08-15-83 Dated 08-15-83 EPIP-4.09 SOURCE TERM ASSESSMENT Remove and Destroy Enter Page 1 of 10 Page Page 1 of 10, Page 1 of 1 of Attachment 3 1 of 1 of Attachment 3 Page 1 of 3, 2 of 3 and Page 1 of 2 and 2 of 2 3 of 3 of Attachment 4 of Attachment 4 Dated 06-17-83 Dated 09-29-83 EPIP-4.22 POST ACCIDENT SAMPLING OF CONTAINMENT AIR Enter Entire New Procedure Dated 09-29-83 EPIP-3.01 EMERGENCY PERSONNEL NOTIFICATION LIST Remove and Destroy Enter Page 4 of 6. REV. 07, Page 4 of 6, REV. 07 of Attachment 1 of Attachment 1
- EPIP-S.01 TRANSPORTATION OF CONTAMINATED INJURED PERSONNEL l
Remove and Destroy Enter Page 2 of 4, REV. 02 Page 2 of 4, REV. 02 l
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LM1-031/jmj l
o sisa72so
- VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION --
EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCEDURE TITLE REVIS10N 01 EPIP-4.01 '~
RADIOLOGICAL ASSESSMENT DIRECTOR -
PA CE CONTROLLING PROCEDURE (With 2 Attachment) 1 of 31 PURPOSE ,
To initially assess emergency conditions, provide protective measures recommendations, establish an emergency organization and direct Health Physics Response to an Emergency.
USER Radiological Assessment Director or Senior Health Physics represen-tative onsite.
ENTRY CON 0lTIONS
- 1. Activation by EPIP - 1.01 l REVISION RECORD REV. 00 PAGE(S): Entire Procedure DATE: 07-29-82 REV. 01 PAGE(S): 1 of 31 through 31 of 31 DATE: SEP :: 3 c:3 REV. PAGE(S): DATE:
REV. PAGE(S): DATE:
REV. PAGE(S): DATE:
REV. PAGE(S): DATE:
REV. PAGE(S): DATE:
l APPROVAL RECOMMENCE 0 APPROV n CA TE
. . W SEP 2 31983 W CHAIRMANSTA TION NUCLEAR SAFETY OCR7E f AND OPERA TING COMMITTEE m - - - - . , .
e - --- - _ .-,w ,,- . .- - p g. _ ,,,,
PC. 97487210 NUMBER PROCEOURE T1TLE REvlSl0N 01 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING PROCEDURE 2 of 31
~ STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 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) II[ TSC is activated, report individual onsite should to the TSC.
report to the Control Rocs Il[ the ISC is NOT activated b) Request briefing with E=ergency 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 ASSESSMENT:
a) IF an offsite release has a) If no actual OR potential occurred: offsite release has nent occurred GO TO Step 15.
b) Request alternate on-shift technician to obtain, if possible, a sample of the effluent m m 4g.- - , , , , ew- 4 __- - . - , ,* ,
N3.97887210 NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR
- A6f CONTROLLING PROCEDURE 3 of 31
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 4. VERIFY EMERGENCY LEVEL:
a) IF the event - UNUSUAL a) IF the event is ALERT EVENT, continue with this or GREATER, GO TO Step 6.
instruction
- 5. EVENT - UNUSUAL EVENT:
a) E radiological release - a) E the event is NOT radio-continue logical release GO TO Step 11 -
b) Initiate EPIP-4.08 Initial Offsite Release Assessment to assess percent Tech Spec Limit AND Return to Step 5.c c) Assess percent Tech Spec:
- 1) E normal range monitors 1) _IJF, normal range monitors indicate LESS THAN 100% GREATER THAN OR EQUAL Tech Spec, inform Emergency TO 100% Tech spec, GO TO Manager initial results Step 5.e.2.
indicate LESS THAN UNUSUAL EVENT l
AND i
i GO TO Step 5.e l
l 2) E normal range monitors 2) E normal range monitors are onscale and indicate indicate GREATER THtdi GFIATER TEAN 100% Tech 1000% Tech Spec, Go TO Spec, but LESS THAN 1000% Step 6.
l Tech Spec S.R-l
P49.97887210 NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PAGE CONTROLLING PROCEDURE 4 of 31
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAIN:0
- 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 H.
f) Have sample (s) analyzed as per Health Physics procedure, H. P.
3.4.1.3 g) GO TO Step g for follow up assessment
- 6. EVENT - ALERT, SITE OR GENERAL:
a) E the emergency is classified a) E the event is NOT a j as an ALERT, SITE, M GENERAL radiological release, l EMERGENCY CO TO Step H.
AND l
Radiological release has occurred g may potentially occur, continue with this procedure
- 7. EVENT - CONDITION IV LIMITING FAULTS:
j a) IF, event - Limiting Fault a) IF accident is NOT a Accident: Limiting Fault, GO TO Step M.
ND.97887210 NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR ####.
CONTROLLING PROCEDURE 5 of 31
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 7. (CONTINUED)
- 1) LOCA - GO TO Step _1_1, 0,,1
- 2) Steam Generator Tube Rupture - GO TO Step ,9_
E
- 3) Main Steam Line Rupture -
GO TO Step 10 4-) Fuel Handling Accident -
GO TO Step 8
- 8. EVENT - FUEL HANDLING ACCIDENT:
a) _I,F, event - Fuel Handling accident:
- 1) Recommend evacuation of Fuel Building AND/OR
! Affected containment
! Building l
i i AND l
- 2) Restrict access until l 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 aup
\
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NA 97887210 NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR
- 68 CONTROLLING PROCEDURE 6 of 31 ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
-' STEP l
- 8. (CONTINUED) c) Initiate EPIP-4.08, Initial Offsite Release Assesscent, to assess offsite releases AND Return to Step 8.d d) Report results of above step to Emergency Manager e) GO TO Step M
- 9. EVENT - STEAM GENERATOR TUBE RUPHIRE:
a) IF event - Steam Generator a) IF event is NOT Steam Tube Rupture, req'lest the Generator Tube Rupture, following from Emergency GO TO Step M.
Manager:
- 1) Status of Air Ejector divert
- 2) Number of Steam Generator Relief Valves lifted, S.R.
Valves which may potentially lift
- 3) E relief valves lifted, length of time valves remained open
- 4) Status of main steam supply to the Auxilary Feedwater Pump Turbine
- 5) Current Steam Generator Blowdown pathway
N3.97887210 NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PAGE CONTROLLING PROCEDURE 7 of 31
(
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINEO
- 9. (CONTINUED) l b) ))[ Air Ejector diverted to b) If_ Air Ejector did NOT containment divert to containment AND g
{ Individuals are in affected IF NO individuals are in containment: affected containment:
l
- 1) Request immediate evacu- 1) Continue with this ation of containment instruction.
l l c) ))[ =ain steam supply to c) ))[ 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.
initiate isolation of main steam supply, of affected generator, to Auxiliary Feedwater Pump Turbine d) Request placement of oper-ations personnel in E=ergency Switchgear Room to report:
- 1) Initial readings l
l l 2) Increase or decrease in l Main Steam and AFWPT exhaust monitors e) Initiate EPIP 4.08. Initial Offsite Release Assessment:
- 1) Determine offsite dose l rate
Peo.97887210
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NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR ####
CONTROLLING PROCEDURE 8 of 31
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 9. (CONTINUED)
Ah3
- 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 Slowdown Cooler area
- 2) Steam Generator Blowdown Lines
- 3) Steam Generator relief valve area
- 4) Auxiliary Feedwater Pump Turbine exhaust area
- 5) Condensate Polishing Building h) IF, personnel are available h) Ij[ personnel are NOT avail-consider initiation of EPIP- able, consider sampling 4.23, Post Accident Sampling upon arrival of additional of[ Reactor Coolant, to manpower assess core damage l
AND l
l l Continue with this instru-l 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.
1
Nm. 97087210 NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING PROCEDURE 9 of 31
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 9. (CONTINUED) .
k) GO TO Step M
- 10. EVENT MAIN STEAM LINE RUPTUPI:
a) E Main Steam Line Rupture a) E event is NOT a Main occurs, review station ven- Steam Line Rupture, GO TO tilation monitors Step H.
- 1) E station monitors have 1) E station monitors-indicated a release, DO NOT indicate a re-initiate EPIP-4.08, lease, GO TO Step 10.b.
Initial Offsite Release Assessment
- 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 n
- 2) From Main Steam Relief Valve Lift I
t d) Request following information from the Emergency Manager:
- 1) Location of Steam Break
- 2) Actual or potential lifting of Main Steam Safety Valves
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ND.97887210
- r NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR
- 0#
CONTROLLING PROCEDURE ,
10 of 31
- STEP ACTICN/ EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 10. (CONTINUED)
- 3) J][ valves have lifted, length of time valve remained open
- 4) Status of Auxiliary Feed- 4) ))[ 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) J][ manpower is available: e) ))[ manpower is NOT available continue with this procedure
- 1) Consider initiation of EPIP-4.22, Post Accident AND t
Sampling of Containment Air Consider initiation once l
i manpower is available.
AND
- 2) Initiation of EPIP-4.23, l
Post Accident Sampling of Reactor Coolant i
l f) GO TO Step Jj[
l NOTE: LOCA accident may not initially result in large release, but may produce a large source with a potential for release from the containment building.
l
- 1) Evacuate Auxiliary l Building and Safeguards Building l
l l
l - - . - . - ,- .-. - . _ . . -. -
Ms.97887210 r
NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PAGE CONTROLLING PROCEDURE 11 of 31
(
- 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 offsite release has cccurred through monitored occurred through station ventilation, initiate unmonitored pathway EPIP 4.08, Initial Offsite Release Assessment OP Release has not occurred, but may potentially occure:
- 1) 1.ssess offsite release 1) Assign an individual to initiate EPIP 4.03, Dose Assessment 7
i Controlling Procedure l AND AhT
- 2) Return to Step ll.c 2) Assess actual or potential release from l
I containment.
c) Report results of above step to Emergency Manager d) IF, manpower is available, d) Ij[ manpower NOT available:
consider the following:
- 1) Continue with this
- 1) EPIP-4.22, Post Accident instruction.
Sampling of Containment Air AND l
1 I- - ,. _ _ _ - - __ _ . - _ . , , , _ _ _ _ _ _ _ _ _ , _
Ns.97887210
- t NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR "# '
CONTROLLING PROCEDURE 12 of 31 l
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 11. (continued) -
- 2) Initiation of EFIP-4.23, Post Accident Samnling of Reactor Coolant e) GO TO Step 13,
- 12. EVENT - RADIOLOGICAL RELEASE:
a) j][ event - Radiological a) ))[ event is NOT a Radio-Release, continue with this logical Release, GO To instruction Step 15.
b) Initiate EPIP-4.08, Initial Offsite Release Assessment:
- 1) Assess off site release AND
- 2) Return to Step 12.c c) Report results of above step to Emergency Manager d) Request the Emergency Manager place an in-l dividual at monitor of interest AND l
l Report increase or decrease in reading
- 13. VERIFY OFFSITE DOSE RATE:
a) ))[ results of offsite release a) )); results of offsite assessment at the Site release assessment at Site Boundary: Boundary:
i l
L
eso. 97887210 NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR #^ ##
CONTROLLING PROCEDURE 13 of 31
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINEO
- 13. (continued)
- 1) GREATER THAN g EQUAL 10 1) LESS THAN 50 mR/hr 50,uR/hr Whole Body Whole Body OR OR GREATER THAN g EQUAL TO LESS THAN 250 mR/hr 250 mR/hr Thyroid Thyroid
- 2) Continue with this 2) GO TO Step 5 l_5,.
instruction 14 PROTECTIVE MEASURES:
a) Obtain an estimate of a) I_F,no estimate can be duration of r lease (hours) given, assume 3, hours.
from Emergency Manager b) Use Site Boundary, 2, 5, and b) g 2, 5, and 10 mile dose 10 mile Whole Body and rate were NOT calculated.
Thyroid dose rates from: use dose rate at the distances calculated.
- 1) ". PIP-4.08, FIF, initial assessment 1) GO TO Step 14.b.2.
E
- 2) EPIP-4.03, IF, follow-up assessment c) Determine projected dose:
= PROJECTED DOSE DURATION OF RELEASE x DOSE RATE (hours) (mR/hr) (mR)
- 1) Repeat above calculation for all dose rates given in Step 14.b
eso. oresnio
?
NUMBER PROCEDURE TITI.E REVISION 01 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR
' CONTROLLING PROCEDURE 14 of 31
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTQBTAINED
- 14. (CONTINUED) d) IF projected dose - d) E projected dose -
GREATER THAN OR, EQUAL TO LESS THAN 500 mR Whole 500 mR Whole Body Sdy OR OR GREATER THAN g EQUAL TO LESS TL\N 1000 mR Thyroid 1000 Thyroid
- 1) Initiate EPIP-4.07, 1) Inform Emergency Man-Protective Measure ager NO, protective measure required
. AND AND
- 2) Determine protective 2) GO TO NOTE prior to measures for distances, Step M.
which projected dose equals or exceeds the above dose
- 3) Return to Step 14.e e) Recommend to the Emergency e) I_F,ji,0 0 protective measures Manager: required, 00 TO NOTE prior to Step g.
i
- 1) Protective measures re-quired offsite I
AND
- 2) Distance protective measures l required NOTE: First Aid considerations must be given priority over decontamination of individual.
i t
I l
No. 97887210 .
NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING PROCEDURE 15 of 31
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 15. EVENT - INJURED CONTAMINATED -
INDIVIDUAL:
a) E the event is an Injured a) E the event is NOT an In-Conta=inated Individual, jured Contaminated Indivi-dual, GO TO Step g.
AND Requires Offsite Medical Treatment:
- 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 c) Insure a Health Physics individual is available to accompany the victim d) Recommend to Emergency Manager transportation of victim to MCV e) E the event initiated e) E other EALs were only for contaminated in- exceeded GO TO Step 1_6,.
6 jured individual requiring offsite medical treatment, AND E other EALs exceeded:
- 1) GO TO Step E
No 97087210 NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING PROCEDURE 16 of 31 g
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 16. FOLLOW-UP ASSESSMENT:
a) IF TSC NOT activated a) IF TSC IS activated GO TO continue with this in- Step 18.
struction b) One member of Health Physics group should remain in the control room to assist the Emergency Manager c) IF, conditions require c) Continue with this instru-presence in another location: crion.
- 1) Inform Emergency Manager AND
- 2) Report to Control Room immediately upon completion of task d) IF,a radiological release has d) Ij; Njl release has occurred:
occurred:
- 1) GO TO Step 16.jt.
- 1) Continue with this instru-ction f
e) Obtain samples of the effluent e) IF NO samples can be ob-tained
- 1) Analyze samples as per normal Health Physics 1) Continue with this procedure instruction AND AND
- 2) IJ[ sample activity is high, 2) Use monitoring readings assign EPIP-4.26 High Level for follow-up assess-Activity Sample Analysis ment l
l l
i I . _ . _ _. _ , _ -. - - - _ _
r+a. orestno NUMBER " PROCEDURE TITLE REVISION 01 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR i CONTROLLING PROCEDURE
- 66 17 of 31
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 16. (CONTINUED) f) E time allows: f) E time is NOT available,
- 1) Initiate EPIP-4.03, Dese 1) GO TO Step h Assessment Controlling Procedure AND AND 2) Return to Step 16.f, when time becomes avail-
- 2) Return to Step h ,
able g) Insure dose control individual is available to supply dosimetry h) Provide H.P. coverage, as needed, for:
- 1) Damage Control Teams M
- 2) Access control E
- 3) Personnel monitoring 5
- 4) Sample analysis
- 1) E the emergency has 1) ,IF,the F emergency has NOT terminated GO TO Step 30 terminated GO TO Step 16.3 j) I_F,TSC E manned, GO TO j) E the TSC is NOT manned:
Step E
- 1) Obtain latest dose rate
- 2) Return to Step E m - ,-r y -~-w --~ y- g < -
1 ND.97887210
. 7 NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING PROCEDURE 18 of 31
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 16. (CONTINUED) .
AND
- 3) Repeat sampling and assessment, as necess-ary
- 17. VERIFY RL1IEF:
a) When a more Senior Health a) E relief is NOT needed, Physics individual arrives GO TO Step H.
onsite pR.,
g relief is needed:
- 1) Brief successor as to existing plant conditions M.
- 2) Offsite release assessment AND
- 3) H. P. actions currently underway b) Announce the change of l position to the Emergency
! Manager
- 18. ESTABLISH EMERGENCY ORGANIZATION:
l a) E the H. P. emergency a) IF emergency organization organization NOT activated, M activated, GO TO NOTE continue with this procedure prior to Step H.
l l
[
1 -
l
-F - _ , . _
No.97867214 NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PAGE CONTROLLING PROCEDURE 19 of 31
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 18. (CONTINUED) b) ))[ manpower is available: b) IF 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
- 2) Assign EPIP-4.03, Dose Assess-ment Controlling Procedure c) Establish position of c) J][ 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.
NOTE: During a SITE of GENERAL emergency, a minimum of two monitoring teams should be dispatched for offsite monitoring.
NOTE: The function of plume tracking /offsite monitoring will be the responsibility of the Radiological Assessment Coordinator, upon activation of EOF.
- 19. ASSESS NEED FOR OFFSITE MONITORING:
a) Evaluate need for offsite a) ))[ offsite monitoring NOT monitoring with Dose Assess- required, GO TO Step 21 ment Team Leader b) ))[ EOF NOT activated: b) ))[ EOF activated, GO TO Step 22,.
- 1) Request Radiation P.ro-tection Supervisor to initiate EPIP-4.16, Offsite Monitoring
ND.97887230 NUMBER PROCE00RE TITLE REVISION 01 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR pAGE CONTROLLING PROCEDURE 20 ef 31 g
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 19. (CONTINUED) c) Evaluate need of protective measures for offsite teams 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 Exnosure Limits AND
- 2) Return to Step 19.e e) E Thyroid exposure exceeds e) E Thyroid exposure will 0 NOT exceed 10 REM, GO TO
_1_0_ REM (refer to Attachment 2): Step 19.f.
- 1) Initiate EPIP-5.07, Admini-stration of Kadioprotective Drugs AND Return to Step 19.f I
l f) Inform Radiation Protection Supervisor:
- 1) Number of monitoring teams 1) IF adequate manpower NOT required available, GO TO Step E.
AND
- 2) Protective clothing required AND
- 3) Respiratory protection required I
g ,_ __ __ _, . , _ , _
' ^ - - y -
No. 97887219
- r NUMBER PROCEDURE TITLE REVISION 01 EPIF-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PACE CONTROLLING PROCEDURE 21 of 31
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 19. (CONTINUED) g) Assist Dose Assessment Team in placement of offsite monitoring teams.
- 20. OFFSITE ASSESSMENT: ,
a) E offsite releases occur: a) E N0 offsite releases have occurred
- 1) Request Emergency Manager place individual at monitor OR of interest IF there is NO potential for a release AND
- 2) Report increase or 1) GO TO Step 2l.
decreasein monitor readings b) The following information will be supplied periodically OR upon request:
- 1) Meteorological data
- 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
- 2) Give Attachment 1 to the Dose Assessment Team 5 , --.-,.-,--..--,%-r _w. i , - - , _ . - - -
No. oresn:o
- t NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PACE CONTROLLING PROCEDURE 22 of 31
- STEF ACTIONtEXPECTED RESPONSE RESPONSE NOTOBTAINED
- 20. (CONTINUED) d) Obtain latest offsite Release d) IF data not available, GO Assessment Data Sheet from H Step M.
Dose Assessment Team
- 21. VERIFY OFFSITE DOSE RATE:
a) E Site Boundary dose rate: a) E Site Boundary dose rate:
- 2) GREATER THAN O_R R EQUAL TO 2) LESS THAN 250 mR/hr 250 mR/hr Thyroid Thyroid b) Return to Step E b) GO TO Step M.
- 22. EOF ACTIVATION:
a) E EOF activated, continue a) I_F_ EOF NOT activated, with this instruction GO TO Step M.
I i b) Brief Radiological Assess-ment Coordinator:
L
- 1) Existing plant conditions AND
- 2) Current offsite dose pro-jections AND
- 3) H.P. actions underway l
l c) Inform Dose Assessment Team Leader to brief Radiological l
Assessment Coordinator:
t .
- . . - . , - . , . ~ , . _ . . , . - - - -. , _ . , _ .
no. ensme
- t NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PAGE CONTROLLING PROCEDURE 23 of 31
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
~
- 22. (CONTINUED)
- 1) Offsite dose assessment AND
- 2) Status and location of off-site monitoring teams d) Insure individual remains in radiological assessment area to transmit to EOF:
- 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) 11 NO, monitoring is monitoring and sampling needed GO TO Step 23.e.
areas c) Instruct Radiation Protection Supervisor to initiate EPIP-4.14. Inplant Monitoring AND EPIP-4.15, onsite Monitoring, as necessary -
m
- . - , - - , --. e -- - -- - - ---
No. 97 s87210 .
NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PAGE CONTROLLING PROCEDURE 24 of 31
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT 0 STAINED
- 23. (CONTINUED) 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.
e) Request from Radiation Protection Supervisor establishing initial and periodic monitoring of TSC and EOF
- 1) Based on survey data and plant conditions establish routine for surveys of the Emergency Centers f) IJF, a radiological release has f) CO TO Step 23.g.
occurred AND A change in plume direction OR increase in release has Eken place l
- 1) Notify Radiation Protection Supervisor AND
\
- 2) Request survey of emergency centers
~
l
No. 97887210 1
NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PACE CONTROLLING PROCEDURE 25 of 31 z
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOSTAINED
- 23. (CONTINUED) g) Based on survey data, direct the establishment of new control points:
- 1) Control spread of contasi-nation AND/OR
- 2) Limit exposure 24 ENTRANCE - ACCESS CONTROL APJ.A:
a) Entrance into access a) E entranca is not required controlled areas should GO TO Step 25.
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
- 1) If necessary, request 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 l
areas that:
1
No.97887210 NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PACE CONTROLLING PROCEDURE 26 of 31
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 25. (continued)
- 1) High airborne activity is 1) ))[ Airborne expected but not measured contamination NOT suspected, GO TO Step 27.
- 2) Airborne activity is 2) ))[ activity is LESS GREATER THAN 0.25 times THAN O_R_ EQUAL TO 0.25 maximum permissible maximum permissible concentration. concentration GO TO Step 27, c) Assess need for respiratory protection, as per EPIP-4.05 Respiratorv Protection and return to Step 26L
- 26. DETERMINE NEED FOR RADIOPROTACTIVE DRUCS:
a) Determine, from survey results, concentration of radiciodine (uCi/ml) b) Determine actual or projected length of exposure time (hours) c) ))[ repiratory protection c) ))[ respirator NOT worn, was worn, determine pro- use protection factor of tection factor: 1.
- 1) Refer to EPIP-4.05, Respirator Protection, Attachment 3, to determine protection factor d) Determine actual concen-tration:
Step 2.a Step 2.c
=
- uCi/ml
ma. stesnie NUMBER PROCEDURE TITLE REVISION 01 I EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PACE CONTROLLING PROCEDURE 27 of 31
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT 09TAINE0
~
- 26. (CONTINUED) .
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) E Thyroid exposure is exposure will be GREATER LESS THAN 10, Rem:
THAN g EQUAL TO 10 Rem Thyroid 1) GO TO Step E.
- 1) Request approval from Emergency Manager to administer radio-protective drugs g) E approval is granted:
- 1) Initiate EPIP-5.07, Administration of Radio-crotective 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 actual exposure, onsite, from release of radioactive material b) Determine direction of plume c) Determine from Emergency Manager duration of release d) E actual or projected d) E dose is LESS THAN evacu-exposure onsite: ation limits
. . , ,m _ _ _ _ _ y, , ,--..
NO.97887219 NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PACE CONTROLLING PROCEDUPI 28 of 31
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 27. (CONTINUED)
,IF, F plume is in the direction AND/OR of the evacuation route:
- 2) GREATER THAN g 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 e) Recommend evacuation of all non-essential personnel f) Report recocmendation to the Emergency Manager
- 26. ASSESS EXPOSURE TO EMERGENCY RADIATION WORKERS:
a) Prior to entry into a High Padiation areas, access
! possible exposure levels b) I_F,Whole Body expot,ure b) E entry into high radiation area will NOT
! exceeds 10CFR20 quarterly exceed exposure limits:
l j
- 1) Initiate EPIP-4.04, 1) GO TO Step g.
Emergency Exposure l
l AND
- 2) Return to Step g '
i
{
l 1
i
.v.,.,,
No.97887219
'~ . .
NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR pagg CONTROLLING PROCEDURE 29 of 31 g
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 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
- 30. VERIFY EMERGENCY:
a) _IF, emergency condition still a) E Emergency Manager exists, continue with this declares termination of instruction emergency GO TO Step H.
b) Return to Step E and direct repetition:
- 1) Survey (s)
AND/OR
- 2) Radiological sampling AND/OR
- 3) Offsite dose assessment c) Advise the Emergency Manager and the Radiation Protection Supervisor as to the increasing or decreasing trends of Emergency
Pea 97887210 NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PAGE CONTROLLING PROCEDURE 30 of 31
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBIAINED
- 31. EVENT TERMINATION:
a) Termination of emergency de-clared by Emergency Manager
- 1) Notify Radiation Protection Supervisor and , Radiation Assessment Coordinator of termination of emergency
- 2) Evaluate further use of monitoring team (s) for data collection b) Request review of recovery phase with the Emergency Manager and consider the following:
- 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:
l l
a) Initiate replacement of procedure and/or emergency
! equipment if necessary 1
b) Forward completed proce-dure (s), release calculations and survey results to the Emergency Manager w--n, --- , - ,,
No.97887219 3
PROCEDURE TITLE REVISION NUMBER U1 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PAGE CONTROLLING PROCEDLTE 31 of 31
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 33. TERMINATE EPIP-4.01:
a) COMPLETED BY:
DATE:
TIME:
EhT l
.w,--- ,
w r -w .m . ,- - - - --m-p -- ,w - - - _ - - ---~_m__ , _-----%4- ,,, ,_,,_,_,r .- -
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION , ,
EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCEDURE TITLE REVISION 02 EPIP-4.09 -
SOURCE TERM ASSESSMENT PA CE (With 4 Attachments) 1 of 10 PURPOSE Provide guidance and data to Dose Assessment Team to more accurately predict offsite releases.
USER Dose Assessment Team Members.
ENTRY CON 0lTIONS Upon activation of EPIP-4.03, Dose Assessment Controlling Procedure.
I l
l REVISION RECORD REV. 00 PAGE(S): Entire Procedure DATE:07-29-82 l
REV. 01 PAGE(S): 1, 3, 4, 5, 6, Att. 1 Page 1 DATE:03-03-83 REV. 02 PAGE(S): 1 of 10 through 10 of 10 & Attachment 4 DATE:SEP 2 3 1333
! REV. PAGE(S): DATE:
REV. PAGE(S): DATE:
REV. PAGE(S): DATE:
REV. PAGE(S): DATE:
APPROVED DA TE APPROVAL . ECOMMENCEO SEP 2 3 ISB3 0# # 'N CHAIRMANSTA TION NUCLEAR SA FETY AND QPERA TING COMMITTEE f
No. s7ee n t e .
NUMBER PROCEDURE TITLE REVISION 02 EPIP-4.09 SOURCE TEAMF ASSESSMENT PAGE 2 of 10
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 1. INITIATE PROCEDURE:
a) BY:
DATE:
TIME:
- 2. SOURCE TERM ASSESSMENT:
a) Source term based on monitor readings should be used:
- 1) Initial assessment AND
- 2) Establish trends b) IJF, the source term is from monitor readings, sampling should be done to more accurately detemine the source term c) Source term will have units of C1/sec d) Source term may be obtained d) E source term from con-from any of the following, tainment - GO TO Step 2.e.
in order of preference:
- 1) Sample of effluent - 1) E sample of effluent GO TO Step 4_ NOT available, GO TO Step 2.d.2.
~
_OR
- 2) Sample of Station Inv,entory 2) IF samnle of station GO TO Step 6 inventory NOT avail-able, CO TO Step 2.d.3.
~
_OR
+
_- f 9
no. ovesnio
?
NUMBER PROCEDURE TITLE REVISION 02 EPIP-4.09 SOURCE TEAMS ASSESSMENT p, ,.
3 of 10 g
- STEP ACTION / EXPECTED RESPONSE RESPONSENOT QBTAINED 2.
(CONTINUED)
- 3) Station monitors 3) ))[ source term NOT thru GO TO Step 3, the station monitors GO TO Step 2.e.
e) ))[ event may produce releases e) ))[ 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) )); sample can NOT be GO TO Step 8 obtained from contain-ment - GO TO Step 2.e.2.
- 2) Containment High Range Monitor - GO TO Step j[
- 3. SOURCE TERM - STATION MONITORS:
a) Source term may be obtained a) )); release pathway is thru from the following monitors: the main steam system, GO TO Step 9.
- 1) Vent Vent VG-109 l
O_R, l
- 2) Vent Vent (VG-131-2)
- 3) Process Vent GW-102 l 4) Process Vent (GW-130-2) l 0,,R_
l l 5) Condensor Air Ejector SV-lli, SV-211
' b) )); more than one effluen.t b) Continue with this instruc-pathways involved: tion
- 1) Add results of all monitors for total release i
l l
i
~
I i
l r
ND.978872:0 r
NUMBER PROCEDURE TITLE REVISION 02 EPIP-4.09 SOURCE TEAMS ASSESSMENT PAGE 4 of 10
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 3. (CONTINUED) c) )); source term is from vent c) If source term is from vent vent (VG-109), Process Vent vent (VG-131-2) or Process (GW 102) or Condensor Air Vent (Gk'-130-2) , obtain Ejector, obtain cps, above uC1/ce, for monitor of background, from the Radio- interest from Radiological logical Assessment Director Assessment Director.
- 1) Log date, time, monitor 1) Log date, time, monitor of number and the net cpm interest and uC1/cc on on Attachment 1 Attachment 1
- 2) CO TO Step 3.d.
d) ))[ Air Ejector NOT diverted d) ))[ Air Ejector ))[ diverted to containment, continue to containment, no release with this instruction frca this pathway will occur:
- 1) GO TO Step 3.e.
e) Obtain the flow rate (CFM) effluent pathway from Radio-logical Assessment Dizactor
- 1) Log on Attachment 1 f) Obtain conversion factor for monitor of interest:
- 1) VG-109: 1.19 E-11
- 2) VG-131-2 : 4.72E-4 91
- 3) GW-102: 1.19 E-10
- 4) GW-130-2 : 472E-4 91
- 5) SV-111.211:5.71 E-9 wM
Ns.97887210
- t NUMBER PROCEDURE TITLE REVISION 02 EPIP-4.09 SOURCE TYAMS ASSESSMENT PACE 5 of 10
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 3. (CONTINUED) .
g) Perform following calcu-lations to obtain C1/sec (XE-133 Equivalent):
cpm (or uC1/cc) x CONVERSION FACTOR x CFM = C1/sec
- 1) Log results on Attachment I
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 3.
4.24, Gaseous Effluent Sampling During an Emergency, to obtain a sample:
- 1) Vent Vent E
- 2) Process Vent E
- 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 l
c) Have sample analyzed as_per normal count room procedures OR initiate EPIP-4.26, M Level Activity Sample Analysis l
l l
L.
Ns.97847210 7
NUMBER PROCEDURE TITLE REVISION 02 EPIP-4.09 SOURCE TEAMS ASSESSMENT
- 'A GE 6 of 10
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 4. (CONTINUED)
- 1) Log results of the analysis on Attachment 2 d) Perform calculations on Attachment 2 to obtain:
- 1) Equivalent activity I-131 AND Xe-133 (uci/ml) e) Obtain flow rate:
f) Calculate source term (C1/sec):
EQUIVALENT ACTIVITY x CTM x 4.72E-4 = Ci/sec
- 5. CORRECT SOURCE TERM FOR MAXIMUM RELEASE:
a) E sample from Step 4 was a) IF sample was NOT a grab a grab sample and is NOT sample OR E sample obtained at maximum release, obtained at maximum release correct for maximum release GO TO 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-l -tion to obtain maximum release rate:
Monitor Maximum (cpm or uCi/ce) x Source = Max =um Ci/sec Monitor Sample (cpm or uC1/cc) Term b) GO TO Step 9 l
-- y r- - -+ - -
N.D. 97 047210 r
NUMBER PROCEDURE TITLE REVISION 02 EPIP-4.09 ,
SOURCE TEAMS ASSESSMENT PACE 7 of 10 g
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINEO
- 6. SOURCE TERM - STATION INVENTORY:
a) Ij[ 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 Ojt initiate EPIP-4.26, High Level Activity Sample Analysis
- 3) Log activity on Attachment 2 b) Perform calculations on Attachment 2 to obtain:
- 1) Equivalent activity I-131 AND Xe-133 c) Determine volume of release from the following equation:
P 112 VOLUME =
l2
- 1) Obtain pressure prior to release from operations (Pg)
- 2) Obtain pressure after release from operations (P3)
- 3) Obtain the design volume of the tank minus the water volume in the tank fr.om operations
- 4) Obtain temperature prior to release from operations (Ty = *F + 459) y - - 6-. w ,
ws_ _
No. 97867210 NUMBER PROCEDURE Tlil,E REVISION 02 EPIP-4.09 SOURCF. TEAMS ASSESSMENT PAGE 8 of 10
- STEP ACTION / EXPECTED RESPONSE - RESPONSE NOT OBTAINED
- 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 (ft )8x EQUIVALENT ACTIVITY = C1/sec TIME OF RELEASE (seconds)
- 7. SOURCE TERM - CONTAINMEh"I HIGH RANGE MONITOR:
a) IF event - LOCA: a) IF source tern NOT from LOCA, GO TO Step 9_.
- 1) Obtain the dose rate (cR/hr) of Containment High Range Monitor of affected unit, from Radiological Assessment Director b) Obtain length of time (HOURS) i after shutdown c) Determine approximate extent of fuel damage using Attachment 3 l
- 1) Extrapolate, if necessary, '
to determine fuel damage l
l l d) Use data from Step 7.b Step 7.c l and Attachment 4:
l j
- 1) Determine equivalent curies l I-131 and Xe-133 I
i 1
1- -
No.97887210 NUMBER PROCEDURE TITLE REVISION 02 EPIP-4.09 SOURCE TEAMS ASSESSMENT PAGE 9 of 10
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 7. (CONTINUED) e) E containment effluent e) E containment effluant flow rate unkown, determine flow rate known, detarmine potential release rate: potential release rate:
Equivalent Curies x Equivalent Curies x 3.39 E-8 = C1/sec 9.29 E-9 = C1/sec f) GO TO Step 9
- 8. SOURCE TERM - CONTAINMENT SAMPLE:
a) E event - LOCA: a) IF event NOT LOCA, CO TO Step 9.
- 1) Request Radiation Pro-tecticn Supervisor initiate EPIP-4.22, Post Accident Sampling of Con-cainment Air b) Convert results of analysis to equivalent activity (uC1/mL) of I-131 and XE-133, using Attachment 2 c) Determine potential release rate:
EQUIVALENT ACTIVITY x 1.73 E-3 = C1/sec
- 9. RETURN TO CONTROLLING PROCEDURE:
a) Upon completion of this procedure, return to EPIP-4.03, Dose Assessment Controlling Procedure
~7
.m- 4 -et w -.i -
Ns.97887210 NUMBER PROCEDURE TITLE REVISION 02 EPIP-4.09 SOURCE TEAMS ASSESSMENT PAGE .
10 of 10
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 10. TERMINATE EPIP-4.09:
a) Completed By:
Date:
Time:
END e
e e w - , ,,y, - --- a g' - - m.w+ w?--4
No s7ss7220 .
NUMBER A TTACHMENT TITLE REVISION EPIP-4.09 02 A T'ACHMENT CONTAIW.ENT HIGH RANGE MONITOR PAGE (PERSONNEL HATCH) 4 1 of 3
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NA 97BO7220 NUMBER A TTACHMENT TITLE ggytStog EPIP-4.09 02
< TTACNMENT EQUIVALENT CURIES I-131 FOR LOCA ACCIDENT PAGE 3 of 3 NOTE: Within the first 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> following LOCA incident, IODINE decay is insignificant.
EQUIVALENT CURlES WENT I-131 LOCA 3.85 E+3 (1% Clad Failure)
LOCA 3.85 E+4 (10% Clad Failure)
LOCA 3.85 E+5 (100% Clad Failure)
LOCA 5.93 E+5 (1 Fuel Melt)
LOCA 5.93 E+6 (10% Fuel Melt)
LOCA 5.93 E+7 (100% Fuel Melt)
, 9-- ..
p - , - -
3o go,7 set:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION -. y EMERGENCY PLAN IMPLEMENTING FROCEDURE NUMBER PROCE00RE TITLE REVISION 02 EPIP-4.12 -
0FF5ITE ENVIRONMENTAL MONITORING PACE
~~~
INSTRUCTIONS (With 2 Attachments) 1 of 8 PURPOSE ,
Provide guidance to the Dose Assessment Team to direct Offsite Monitoring Teams to:
- 1) Confirm radiological release
- 2) Track release
- 3) Determine radiological composition of releata USER Dose Assessment Team Members.
ENTRY CONDITIONS Any one of the following:
- 1. Release of radioactive materials with a SITE or GENERAL emergency condition and EOF is NOT activated.
- 2. Any other time which the Radiological Assessment Director deems it 3
necessary.
- 3. Activation by another EPIP.
I l
l REVISION RECORD REV. 00 PAGE(S): Entire Procedure DATE:07-29-82 REV. 01 PAGE(S): Page 1, 6, and 7 DATE:02-24-83 REV. 02 PAGE(S): 1 of 8 through 8 of 8 and Attachment 2 DATE: SEP 3 3 1383 REV. PAGE(S): DATE:
REV. PAGE(S): DATE:
REV. PAGE(S): DATE:
REV. PAGE(S): DATE:
APPROVAL RECOMMENDED APPROVED CA TE 8?^ -O SEP 2 31993 0# < '# CHAIRMAN STA TION NUCLEAR SAFETY AND GPERA TING COMMITTEE
- l. ,,
I
Peo, 97847230 7
NUMBER PROCEDURE TITLE REVISION 02 EPIP-4.12 0FFSITE ENVIRONMETIAL MONITORING INSTRUCTION 2 of 8
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OSTAINEC
- 1. INITIATE PROCEDURE:
a) BY:
DAIE:
TLME:
- 2. ACTIVATION UPON SITE OR GENERAL EMERGENCY:
a) The procedure applicable a) IF, EOF is activated and moni-upon radioactive release and toring teams in the field:
declaration of SITE or GENERAL emergency SR.
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 M.
- 3. REVIEW PROJECTED DATA:
a) Review the projected release data b) Obtain from the Radiological Assessment Director the current meteorological conditions:
N3.97867210 NUMBER PROCEDURE TITI.E REVISION 02 EPIP-4.12 0FFSITE ENVIRONMENTAL ####
MONITORING INSTRUCTION 3 of 8
(
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 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) Confirm direction of plume
- 3) Determine radiological composition c) Minimum of two monitoring teams desirable:
- 1) Locate one team near site l and the other team in preselected monitoring location in downwind sector i
l 5. ESTABLISH RADIO CONTACT:
l l a) Initiate EPIP-4.19, Use of a) IF radio communications
! Radios for Health Physics NOT able to be established:
Monitoring:
- 1) Request assistance from 7
- 1) Establish ~ radio communi- Radiological Assessment l cation with team using Director radiophone l
I L
N D. 97887 210
- t NUMBER PROCEDURE TITLE REVISION 02 EPIP-4.12 0FFSITE ENVIRONMENTAL MONITORING INSTRUCTION 4 of 8
~
- STEPe ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 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) Place teams at preselected location in downwind sector
- 1) Wind direction from Step 3 indicates direction wind is coming from c) Instruct teams to find plume centerline AND Report exact location once centering located
ND. 97887210 NUMBER PROCEDURE TITLE REVISION 02 EPIP-4.12 OFFSITE ENVIR0hMENTAL PAGE MONITORING INSTRUCTION 5 of 8
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 6. (CONTINUED) d) Monitoring can be identified 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)
- 7. CON'i1RMATION:
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) Exact location
- 2) Maximum dose rate (mR/hr)
- 3) Air sample - particulate, iodine and gas l
- 4) Soil sample c) Have initial confirmatory samples returned to Security Building
- 1) Air sample should be immediately analyzed to determine Iodine / Noble Gas ratio
, - , , . . n 9 .,,-g,, ,, - - , , -
.y, ,, . n,,- -.- . .- , , -., , -
ND.97847210 NUMBER PROCEDURE TITLE REVISION 02 EPIP-4.12 0FFSITE ENVIRONMT.NTAL MONITORING INSTRUCTION 6 of 8
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 7. (CONTINUED) d) GO O E Step M upon receipt d) If monitoring data NOT of monitoring data available, continue.
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 dase rate at centerline of the plume AND Report exact location b) g unexpected reading occurs:
- 1) Have team travel downwind a distance until plume is located
- 9. FIXED ENVIRONMENTAL SAMPLERS AND TLD'S:
a) Fixed air samplers and TLD's provide good information on the TOTAL release.
Collection of these samples may provide best information after termination of release
Ns. 978872:0 NUMBER PROCEDURE TITLE REVISION 02 EPIP-4.12 0FFSITE EhTIRONMENTAL MONITORING INSTRUCTION 7 of 8
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOiOBTAINED
- 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
- 11. CONTINUE MONITORING:
a) Continue Steps 7 thru 12 until:
- 2) Release TERMINATED, GO TO Step g OR l
- 3) E monitoring data becomes available, GO TO Step H.
- 12. ASSESS DATA:
a) E monitoring data becomes available:
1 1) Initiate EPIP-4.13, offsite Release Assessment with Environmental Data
Ns.97887210 7
NUMBER PROCEDURE TITLE REVISION 02 EPIP-4.12 0FFSITE ENVIRONMENTAL PAGE MONITORING INSTRUCTION 8 of 8 z
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT O9TAINED
- 13. TERMINATE EPIP-4.12:
a) COMPLETED BY:
DATE:
TIME:
END
--ma y y -y-,,-g - ,,,s, yq -,,m,
- , .,,,,-y-p,,, y -- --~v- .m -- n-7 - - , - - - , < , , - -~- ---.s7
NO. 97847220
- t NUMBER A TTACHMENT TITLE REVISION EPIP-4.12 02 PRESELECTED MONITORING LOCATIO;iS A TTAC# MENT A4GE 2 1 of 3 LOCATION SECTOR DISTANCE (mi) DESCRIPTION
- 1. B-2 2 miles North on Route 650 at Hog Island Air Sampling Station.
. 2. F-1.6 Low level circulating water pumps at beginning of intake canal.
- 3. E-1.9 1.9 miles South on Route 650, left at road to public boat landing.
Monitoring point 1 mile, under Vepco power lines.
- 4. J-2.0 2.0 miles South on Route 650; monitoring point at natural gas pipeline signs.
- 5. K-2.1 Route 650 South, right on Route 617, right on Route 10, right on Route 634.
Follow signs to Chippokes State Park, enter park and follow signs to historic section. Monitoring point at Chippokes Mansion.
- 6. L-2.3 Route 650 South, right on Route 617, right on Route 10, right on Route 634 Follow signs to Chippokes State Park; enter park and follow signs to Historic section. Monitoring point located at intersection of road and College Run Creek.
- 7. H-5.5 Rushmere Shores. South on Route 650, lef t on Route 626, lef t on Route 676.
At bend in the road, bear right on Route 686, left on Route 2001 into Rushmere Shores.
- 8. J-5 Route 650 South, left on Route 628.
Monitoring point 1.2 miles from intersection of Routes 650 and 628.
(Remote Assembly Area).
No.97887220 NUMBER A TTACHMENT TITLE REVISION EPIP-4.12 02 A TTACHMENT PRESELECTED MONITORING LOCATIONS PAGE 2 2 of 3 LOCATION SECTOR DISTANCE (mi) DESCRIPTION
- 9. R-5 Route 650 South, right on Route 10.
Monitoring point k mile from intersection of Routes 10 and 650 at bend in road.
- 10. L-5 Route 650 South, right on Route 617, right on Route 10, right on Route 633.
Monitoring point b North on Route 633.
- 11. M-5 Route 650 South, right on Route 617, right on Route 10 for approximately 5 miles, right on Route 634 Monitoring point 1.3 miles from intersection of Routes 634 and 10. Alliance Air Sampling Station, intersection of Routes 634 and 662.
- 12. N-4 Trom location 11, monitoring point 2 miles North on Route 662.
- 13. P-5 Scotland Wharf. Surry side on James River Ferry on Route 31 North.
- 14. Q-5 James River Ferry to Jamestown Route 31, right on Route 359. Follow signs to Colonial Parkway, left on Colonial Parkway. Monitoring location ik mile on Colonial Parkway.
- 15. R-5 James River Ferry to Jamestown side, Route 31 East, right on Route 682 " Neck of Land Road", left on Lake Powell Road, 1.3 miles to intersection of Routes 617 and 618.
- 16. A-5 James River Ferry, Route 31 East, right on Route 359, follow signs to Colonial Parkway, left on Parkway. Monitoring point 6.5 miles, k mile past Halfway Creek.
_ . - - , , , , , , , ,.n .,
No.97887220
?
NUMBER A TTACHMENT TITLE REVISION EPIP-4.12 02 A TTACHMENT PAGE 2 3 of 3 LOCATION SECTOR DISTANCE (mi) DESCRIPTION
- 17. B-5 Take Colonial Parkway from Jamestown, 7 miles to Route 199 East, Route 60 East, 3 lights, right on Kingsmill Road.
Monitoring location 1 mile from Route 60 and Kingsmill Road intersection.
- 18. C-5 Take Colonial Parkway from Jamestown, 7 miles to 199 East, Route 60 East, 3k,
-4 1es to Ron Springs Road (road prior to Carter's Grove), right on Log Cabin Beach Road to sewage treatment plant.
- 19. D-5 Take Colonial Parkway from Jamestown, 7 miles to 199 East, Route 60 East, past Cartet's Grove to Badische Corporation, right 1 mile to Vepco Substation.
- 20. E-5 Take Colonial Parkway from Jamestown, 7 miles to 199 East. Take Route 60 East to Fort Eustis. Right at Fort Eustis, right at Lee Blvd., right on Kerr Road.
Monitoring point located at load dock.
- 21. F-4.8 Take Colonial Parkway from Jamestown, 7 miles to 199 East. Take Route 60 East to Fort Eustis, right at Fort Eustis, right at Taylor Road, left on Harrison Road. Monitoring location 0.6 miles South from intersection of Harrison Road and Back River Road.
~
e
o sjsemo VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION r EMERGENCY PLAN IMPLEMENTING PROCEDURE PROCEDURE TITLE I REVISION NUMBER 01
~
EPIP-4.13 __.
OFFSITE RELEASE ASSESSMENT PA CE WITH ENVIRONMENTAL DATA (With 5 Attachments) 1 of 9 PURPOSE ,
Confirm onsite dose projections, using Environmental Monitoring data.
USER Radiological Assessment Director or Members of Dose Assessment Team.
ENTRY CON 0lTIONS Any of the following:
- 1) Activation by EPIP-4.03, Dose Assessment Controlling Procedure; SE
- 2) Activation by EPIP-4.12, Offsite Environmental Monitoring Instructions.
REVISION RECORD REV. 00 PAGE(S): Entire Procedure DATE:07-29-82 REV. 01 PAGE(S): 1 of 9 thru 9 of 9; Att. 3 pg. 1; Att. 5 DATE:SEP : 3 H33 REY. PAGE(S): DATE:
REV. PAGE(S): DATE:
REV. PAGE(S): DATE:
REV. PAGE(S): DATE:
REV. PAGE(S): DATE:
APPROVAL RECOMMENDEC APPROVED DA TE 0# A'V'" CHAIRMANSTA TION NUCLEAR SAFETY AND CPERATING C059MITTEE
- , _ _ . _ -- , _ . _ . _ _ . , . . _ _ . . _ , _ . - . - _ . _ . - - . _ . _ . . . . _ _ . . . . ~ . _ . _ _ . , _ _ _ . . _ . _ - - - - . _
Pse. 97887210 NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.i3 0FFSITE RELEASE ASSESSMENT WITH ENVIRONMENTAL DATA 2 of 9
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 1. INITIATE PROCEDURE:
a) Initiated By:
Date:
Time:
- 2. USE OF ENVIRONMENTAL DATA:
a) IF environmental data used a) IF environmental data to to confim dose projections: be used to detemine Ci/sec release rate:
- 1) GO TO Step 3_ 1) GO To Step 2.b b) IF onsite release data b) IF onsite release data Eom monitors and/or Eom monitors and/or sample 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 AND
- 2) GO TO Step 8, 2) GO TO Step M.
- 3. CONFIRM DOSE PROJECTIONS:
a) Use offsite dose rate measurement to confirm projected dose rate pR,
N:3. 97 8 87210 t
NUAfBER PROCEDURE TITLE REVISION 01 EPIP-4.13 0FFSITE RELEASE ASSESSMENT PAGE WITH ENVIRONMENTAL DATA 3 of 9
- c. .
- 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 SE
- 2) Sample Analysis Data
- 4. DETERMINE WHOLE BODY DOSE FROM DIRECT RADIATION READINGS: l a) Obtain from monitoring a) IF, F dose rates NOT from team centerline dose rate centerline:
- 1) GO TO Step 6_
b) Log date, time, location and dose rate on Attachment 1
- 5. DETERMINE THYROID OFFSITE DOSE RATE FROM SAMPLE ANALYSIS:
a) Determine centerline a) IF F data from air sample is thyroid dose rate from NOT yet available. GO TO air sample analysis Step 1_2, pR,
_IF sample NOT from centerline, continue with this instruction
- r
NO.97887210 7
NUMBER PROCEDURE TITLE REVIS10N 01 EPIP-4.13 0FFSITE RELEbSE ASSESSMENT ^# .
WITH ENVIRONMENTAL DATA 4 of 9
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 5. (CONTINUED) b) If sample analysis given in b) E sample data is given in counts per minute: uCi/ml:
- 1) Obtain background count 1) GO TO Step 5.c.
rate (cpm) and volume (ft')
from monitoring team (s)
- 2) Determine the net counts per minute:
SAMPLE (cpm) - BACKGROUND (cpm) = NET (cpm)
- 3) Determine from Attachment 5, the conversion factor vs.
volume
- 4) Determine activity:
NET (cpm) x Conversion Factor = Activity (pCi/ml) c) Deter;2ine Thyroid dose rate:
ACTIVITY (uci/ml) x 1.85 E+9 = MR/HR d) E sample taken at d) E sample taken off-centerline: centerline, GO TO Step 6
- 1) Log date, time, location and dose rate on Attachment 1
- 6. OFF-CENTERLINE DOSE RATES:
a) E dose rates from Step 4 and a) IF dose rates from Step 4_
Step 5 were taken off-center- and Step 5 are taken from line centerline, GO TO Step 7.
- 1) Initiate EPIP-4.10, Determination of X/Q Spud ar-g--- - - - - -
m-, - - -- , , - , - , , , - - , . - _ - . _
ND. 978 87210 t
NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.13 0FFSITE RELEASE ASSESSMENT PACE WITE ENVIRONMENTAL DATA 5 of 9
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 6. (CONTINUED)
- 2) Determine centerline X/Q
. perpendicular to sample location
- 3) Determine X/Q of the sample location AND .
- 4) Return to Step 6.b of this procedure b) Determine centerline dose rate:
X/Q (CENTERLINE) x DOSE RATE (MR/HR) = DOSE RATE (MR/HR)
X/Q (SAMPLE LOCATION) CENTERLINE c) Log date, time, location and dose rate on Attachment 1
- 1) Note in the remarks column that the sample was taken off centerline t 7. TRANSMIT DATA:
a) Upon ccmpletion of Attachment J_:
l 1) Relay the Attachment to the Dose Assessment Team Leader.
Ah"d
- 2) GO TO Step J2_
l
Ns.97847210 7
NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.13 0FFSITE RELEASE ASSESSMENT FACE k'ITH ENVIRONMENTAL DATA 6 of 9
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTSINED
- 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 12.
b) Insure measurements or samples b) If data is NOT from the taken are from the centerline centerline of clie plume:
of the plume
- 1) GO TO Step 6 to estimate centerline data AND
- 2) Return to Step 8.c.
c) Source Term may be estimated by: "
- 1) Direct Measurements, GO TO Step 9 QR_
- 2) Sa'mple Analysis Data, GO TO Step g I
- 9. DETERMINE SOURCE TERM FROM DIRECT MEASUREMENTS:
a) Obtain centerline dose rate measurements from Step 8,
- 1) Log location, time and dose rate on Attachment 2
AND
- 2) Obtain the current wind speed and stability class l
i
~
l
~
Pe t. 97847210 -
NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.13 0FFSITE RELEASE ASSESSMENT
- EE WITH ENVIRONMENTAL DATA 7 of 9
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED
- 9. (CONTINUED) b) Determine the conversion
. factor:
- 1) IF measurements taken 1) IF measurements are NOT at preselected monitoring at preselected points, determine factor monitoring points, from Attachment 3 determine from A*.tachment 4 ,
c) Determine source term:
MR/HR x 2.38 E-3 x WIND SPEED x CONVERSION FACTOR = C1/sec 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 fro =
centerline of the plume centerline of plume:
- 1) GO TO Step 6 to esti= ate centerline data (use (uC1/ml) instead of data rate)
AND
- 2) Return to Step 10.b.
b) Obtain uC1/ml measurements b) IF, sample data received in at sample location: counts per minute:
- 1) Log location, time, and 1) GO TO Step 5_
activity on Attachment 2 l 2) Determine activity l
- 2) Obtain the current wind (uCi/ml) l speed and stability class from Dose Assessment Team 3) Return to Step 10.b.
Leader i
i l -
l
_ - - - , , - - - . ,. - . - . . - ,- - .n ,
No. 97847210 NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.13 0FFSITE RELEASE ASSESSMENT WITH ENVIRONMENTAL DATA 8 of 9
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 10. (CONTINUED) c) E sample from preselected c) E sample not from points. Obtain the conversion preselected point, obtain factor from Attachment 3, conversion factor from Attachment 4 d) Determine the source term:
ACTIVITY x WIND SPEED x CONVERSION FACTOR = C1/sec a) Upon completion of Attachment 2
- 1) Infor= Dose Assessment Team Leader of results
- 11. TRANSMIT DATA:
a) Upon completion of Attachment 2
- 1) Inform Dose Assessment Team Leader of results
- 12. CONTINUED' ASSESSMENT:
a) E monitoring teams are a) E teams are to remain in to be relocated: the same location:
- 1) GO TO Step J4,to 4 terminate 1) GO TO Step 12.b.
this procedure AND
- 2) Initiate EPIP-4.12, Offsite Monitoring Iristruction b) IF, EOF NOT activated b) E emergency has terminated OR OR l -
Ns.97887210 NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.13 0FFSITE RELEASE ASSES $ MENT
- ^ O#
L'ITH ENVIR021 ENTAL DATA 9 of 9
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 12. (CONTINUED)
E release NOT terminated: E EOF activated:
- 1) Return to Step 3_ and 1) GO TO Step E.
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:
END
,..me-
No.97887220 t
NUMBER A TTACHMENT TITLE REVISION EPIP-4.13 00 ATTAC# MENT FACTORS FOR PRESELECTED ####
MONITORING LOCATIONS 1 of 1 STABILITY CLASS LOCA SECT DIST A B C D E F G 1 B- 2 1.51E6 5.55E5 7.14E4 2.08E4 1.00E4 4.17E3 1.72E3 2 F- 1.6 1.26E6 3.08E5 5.13E4 1.50E4 6.90E3 3.17E3 1.35E3 3 E- 1.9 1.50E6 5.50E5 7.10E4 2.00E4 1.00E4 4.10E3 1.60E3 4 J- 2.0 1.51E6 5.55ES 7.14E4 2.08E4 1.00E4 4.17E3 1.72E3 5 K- 2.1 1.60E6 6.62E5 8.00E4 2.27E4 1.06E4 4.54E3 1.85E3 6 L- 2.3 1.70E6 1.32E6 1.27E5 3.45E4 1.51E4 6.66E3 2.56E3 7 H- 5.5 3.85E6 2.86E6 4.00E5 1.00E5 3.85E4 1.64E4 6.24E3 8 J- 5 3.45E6 2.63E6 3.45E5 8.33E4 3.45E4 1.43E4 5.26E3 9 K- 5 3.45E6 2.63E6 3.45E5 8.33E4 3.45E4 1.43E4 5.26E3 10 L- 5 3.45E6 2.63E6 3.45E5 8.33E4 3.45E4 1.43E4 5.26E3 11 M- 5 3.45E6 2.63E6 3.45E5 8.33E4 3.45E4 1.43E4 5.26E3 12 N- 4 2.86E6 2.13E6 2.38E5 5.88E4 2.50E4 1.07E4 4.00E3 13 P- 5 3.45E6 2.63E6 3.45 E5 8.33E4 3.45E4 1.43E4 5.26E3 14 Q- 5 3.45E6 2.63E6 3.45ES 8.33E4 3.45E4 1.43E4 5.26E3 15 R- 5 3.45E6 2.63E6 3.45E5 8.33E4 3.45E4 1.43E4 5.26E3 16 A- 5 3.45E6 2.63E6 3.45E5 8.33E4 3.45E4 1.43E4 5. 26E3 17 B- 5 3.45E6 2.63E6 3.45E5 8.33E4 3.45E4 1.43E4 5.26E3 18 C- 5 3.45E6 2.63E6 3.45E5 8.33E4 3.45E4 1.43E4 5. 26E3 19 D- 5 3.45E6 2.63E6 3.45ES 8.33E4 3.45E4 1.43E4 5.26E3 20 E- 5 3.45E6 2.63E6 3.45ES 8.33E4 3.45E4 1.43E4 5.26E3 21 F- 4.8 3.33E6 2.50E6 3.13E5 7.70E4 3.13E4 1.35E4 5.00E3
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Na,97887220 NUMBER A TTACHMENT TITLE REVISION EPIP-4.13 01 A TTACNMEyr RM-14 CONVERSION FACTOR PAGE 5 1 of 1
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VIRGINIA ELECTRIC AND POWER COMPANY
- SURRY POWER STATION --
EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCEDURE TITLE REVISION 02 EPIP-4.15 , , , ,
ONSITE MONITORING ,
PA GE (With 3 Attachments) L of 9 PURPOSE ,
Confirm initial offsite releases and provide surveys for personnel pro-tection program onsite.
USER Onsite Monitoring Team Member ENTRY COACITIONS Any one of the following conditions:
- 1. ALERT, SITE or GENERAL emergency.
- 2. Activction by another EPIP.
REVISION RECORD REV. 00 PAGE(S): Entire Procedure DATE:07-29-82 REV. 01 PAGE(S): 1, 3, 4, 5, 7, 8 Act. 2 p.1, Act. 3 p.1 DATE:02-24-83 REV. 02 PAGE(S): Page 1 of 9 and Attachment 3 page 1 of 1 DATE:SEP 2 l333 REV. PAGE(S): DATE:
REV. PAGE(S): DATE:
REV. PAGE(S): DATE:
REV. PAGE(S): DATE:
APPROVAL RECOMMENDED APPROVED DA TE
~
SEP231383 QCREV W CHAIRMANSTA TION NUCLEAR SAFETY
,f,b ,, AND OPERA T]NG C5MMITTEE
94o,97887220
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g.,=>m VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PRCCEDURE TITLE REVISION 01
^
EPIP-4.16 _ , ,
OFFSITE MONITORING PACE (With 4 Attachments) 1 of 12 PURPOSE ,
a Provide guidance for offsite monitoring teams in obtaining equipment, tracking plume, taking samples and transmitting data.
~
USER Offsite Monitoring Team members.
ENTRY CONDITIONS Initiation by EPIP-4.02, Radiation Protection Supervisor Controlling Procedure.
l I
( REY!S10N RECORO REV. 00 PAGE(S): Entire Procedure DATE:07-29-82 REV. 01 PAGE(S): 1, 2, 3, 4, 7, 8, 9. Att. 4 p.1 DATE:02-24-83
- REV. 02 PAGE(S): 1 of 12 thru 12 of 12; Att. 2; & Att. 4 DATE:SEP 2 3 ;353 l
REV. PAGE(S): DATE:
REV. PAGE(S): DATE:
REV. PAGE(S): DATE:
REV. PAGE(S): DATE:
APPROVAL RE QMMENCEO APPROVED DA TE
- '- SEP 2 31983 00 RE H, CHAIRMANSTA TION NUCLEAR SAFETY
/
_bg [Q AND OPERATING COMMI&EE
No.978472:0 NUMBER PROCEDURE TITLE REVISION 02 EPIP-4.16 0FFSITE MONITORING 1 PA GE 2 of 12
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT 087AINED
- 1. INITIATE PROCEDUKE:
a) BY:
DATE:
TIME:
- 2. TEAM ASSIGNMEN.T:
a) Offsite monitoring team shall consist of two individuals:
- 1) Only one need be a H.P. l technician l
- 3. PJQUEST BRIEFING:
a) Request briefing with the Radiation Protection Super-visor as to the following:
- 1) Required monitoring 1) IF no location OR survey locations requirenents given, proceed to security building and
- 2) Samples and surveys await instructions.
required
- 3) Anticipated radiation levels
- 4) Protective clothing and dosimetry and/or respir-atory gear required b) Obtain information on who to report survey data to:
- 1) ISC SR
( 2) EOF l
l l
No.97847210 NUMBER PROCEQURE TITLE REVISION 02 EPIP-4.16 0FFSITE MONITORING PAGE 3 of 12
- STEP -
ACTION / EXPECTED RESP 0KSE RESPONSE NOTCSTAINED
- 4. OBTAIN VEHICLE:
a) Health Physics truck will a) Request assistance from
, be used as primary trans- Radiation Protection Super-portation for Offsite Teams visor or Radiological Assess-ment Director in obtaining vehicles, b) Insure vehicle has at least 1/4 tank of gas
- 5. OBTAIN MONITORING KIT:
a) Obtain a monitoring kit specified by Radiation Protection Supervisor b) Obtain additional equipment b) Additional equipment avail-from 'd.P. Office: able at EP instrument repair shop.
l 1) Battery powered air sampler
- 2) KH-14 with H.P. 210 prebe
- 3) Package of silver zeolite cartridges and particulate filters
- 6. PERFORM INSTRUMENT CHECK:
a) Perform operability check:
- 1) Battery check
- 2) Current calibration sticker
- 7. PROCEED TO MONITORING LOCATION:
a) Obtain and den protective a) I.[no J gear is specified, clothing, dosimetry, and continue with this instruc-respiratory gear as speci- tion.
fled in Step 3
,m 9 3 y.,,,-_.7 g ---r- - - - -
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i N3 97867280 t
NUMBER PROCEDURE TITLE REVISION
. 02 EPIP-4.16 0FFSITE MONITOP.ING g,gg 4 of 12
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OSTAINED 7.
(CONTINUED) b) Use Attachment 1 and 2 to determine:
- 1) Initial location SR,
- 2) Location specified by personnel in TSC (EOF) c) Proceed to monitoring c) j][ no monitoring locatior location specified in specifiec:
Step 3,
- 1) Report to Security Building AND
- 2) Await further instruct-ions.
- 8. ESTABLISH RhDIO CONTACT:
a) Initial radio communication will be with cmergency res-ponse personnel in the TSC b) ))[ EOF is activated, radio communication will be with i EOF c) Establish radio communica-tion with the TSC or EOF by initiation of EPIP-4.19 Use of Radios for Health Physics Monitoring
( 1) To transmit:
l
" Mobile (Number of Vehi-cle) to TSC (EP-2) or EOF "
(HP-3).
Our location is
(
O l
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.~ . _ - . - _ _ _ .. . _ _ _ _ . . _ _ _ _ _ _ . . . . _ , _ _ . . _ .
NO.97847280 NUMBER PROCEDURE TITLE REVISION 02 EPIP-4.16 0FFSITE MONITORING PAGE 5 of 12
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 8. (CONTINUED)
- 2) Request telephone number of emergency center and use in case of radio f ail-ure NOTE: Survey reading should i'acrease as you approach center of the plume, then decrease once past centerline.
- 9. P1,UME TRACKING:
a) IJ[ directed to locate a) GO TO Step 10,.
plume:
- 1) Proceed to location specified by TSC or EOF b) Obtain portable survey instrument from emergency kit:
- 1) Open beta window c) Traverse the plume in a c) Il[ NJ1 readings are observed, crosswind direction: notify TSC (or EOF).
- 1) Hold survey meter out 1) Request advice on relo-of window cation AND AND
- 2) Observe readings 2) Return to Step 9.c.
d) Traverse plume several times until maximum point (centerline of plume) is located
r .neento t
NUMBER PROCEDURE TITLE REVISION 02 EPIP-4.16 0FFSITE MOSITORING FACE 6 of 12
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 9. (CONTINUED) e) Close beta window:
- 1) Observe readings f) Log on Attachment 3:
- 1) mR/hr
- 2) Location
- 3) Date
- 4) Time
- 5) Instrument used and serial number g) Inform TSC (or EOF) of monitor readings and location h) Relocate'to an area h) IF,further monitoring outside the plume: required, stay within the plume until com-
- 1) Await further instructions plete.
- 10. NOBLE GAS SAMPLING:
a) J][ noble gas sample a) Il[ noble gas sample is NOT requested, go to the requested, GO TO Step 11,.
centerline of plume 0,,R, Location specified by TSC (or EOF) b) Obtain a 100 ce gas b) ))[ gas chamber NOT avail-bomb from emergency kit able, request gas chambers be prepared and brought to
- 1) Remove top and wave the survey team.
chamber in air
+ r- - < - - - - w + y -- y , * - - - - , - - - - T *-
. Pes.97887220 NUMBER PROCEDURE TITLE REVISION 02 EPIP-4.'16 0FFSITE MONITORING
.M CE 7 of 12
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT08TAINED
- 10. (CONTINUED)
- 2) Ensure petcocks are
- closed and replace top
- 3) Place chamber in plastic bag and label with date, time and location c) Log information in Step 10.b.3 ,
on Attachment 3
- 11. PARTICULATE AND IODINE SAMPLE: ,
a) ))[ particulate and/or iodine a) ))[ sample NOT required, sample required: GO TO Step 12.
- 1) Obtain battery powered air sampler
- 2) Load samples with parti-culate filter and silver zeolite cartridge b) ))[ sample required during b) Continue with Step 11.c.
high humidity:
- 1) Shelter sample from moisture
- 2) Report weather conditions so TSC or EOF NOTE: Sample volume should be lessened when sampling high activity airborne concentrations 8
c) Obtain an approximate 3 ft air sample 1
1
No. stas 72 o NUMEER PROCEDURE 77TLE REY:SION 02 EPIP-4.16 0FFSITE MONITORING pA05 8 of 12
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 11. (CONTINUED)
- 1) Connect cables to vehicle battery terminal
- 2) Turn on air sampler
- 3) Disconnect cables after sample volume collected
- 4) Log sample volume on Attachment 3 d) Place iodine cartridge and particulate filter in a plastic bag and label:
- 1) Date
- 2) Time
- 3) Volume
- 4) Location e) Log information in Step 11.d on Attachment 3 NOTE: Air sample must have been taken using silver reolite cartridge to use this method for analysis.
- 12. ACTIVITY DETERMINATION:
a) E air sample analysis required:
- 1) Proceed to a low back-ground area w-,y-- - -- ,- ,. -.. - , r..w. , . . .-, -- , .=p. e,. v ---
No. 97487210
?
NUMBER PROCEDURE TITLE REVISION 02 EPIP-4.16 OFFSITE MONITORING PAGE 9 of 12
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 12. (CONTINUED) b) Turn on RM-14 (f risker)
- 1) Obtain a background count rate (cpm) c) Hold silver zeolite cart-ridge one-quarter inch from detector, with influent side ,
of cartridge facing the detector d) jg[ gross count rate on d) II gross count rate off scale, continue scale:
- 1) Return to Step 11, AND
- 2) Obtain a smaller sample volume e) Determ16e net count rate:
GROSS (cpm) - BACKGROUND (cpm) = NET (cpm) f) Determine from Attachment 4 the conversion factor for specific sample volume.
l 1
g) Determine activity:
NET (cpm) x Conversion Factor =
ACTIVITY (uC1/ml) l h) Log on Attachment 3:
- 1) Date
- 2) Time l
( -_
1 l
~
l NE. 97847210
^
- t NUMBER PROCEDURE TITLE REVISION 02 EPIP-4.16 0FFSITE MONITORING PAGE 10 of 12
-- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 12. (CONTINUED)
- 3) Location
- 4) Activity
- 1) Place sample in poly bag and label:
- 1) Date
- 2) Time
- 3) Volume
- 4) Location
- 13. SOIL DEPOSITION:
a) IJ; soil sample IS, requested: a) II[ soil sample NOT requested, GO TO Step
- 1) Obtain a sample by marking 14 off an approximate one square foot area
- 2) Remove top 1/4 to 1/2 inch layer of soil
- 3) PI:ve soil in a clean poty bag b) Label sample with:
- 1) Date
- 2) Time
- 3) Location c) Save sample for lab analysis m - --.-,,,, _
l I
N2.s7ss721o NUMBER PROCEDURE TITLE REVISION 02 EPIP-4.16 0FFSITE MONITORING PAGE 11 of 12
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT 037AINED
- 14. TRANSMIT DATA:
a) Transmit results of all
, surveys C]t sample analysis to TSC (or EOF), as soon as possible
- 15. LABORATORY ANALYSIS OF SAMPLES:
a) All samples will be saved ,
for future analysis at laboratory facilities b) Bag all samples in a clean poly bag c) Insure samples are properly -
labeled d) Return all samples to the Security Building, as requested
. SE!
As time and location permit
- 16. CONTINUED SAMPLING:
a) ))[ TSC or EOF does NOT a) ))[ TSC or EOF requests request return to station: return to station:
- 1) Return to Step j[ 1) GO TO Step 12,.
- 2) Repeat sampling and surveys as requested
~
- 17. ADMINISTRATIVE:
a) All procedures and forms used for offsite monitoring should be returned to the Radiological Assessment Director at TSC or the Radiological Assessment Coordinator at EOF
' - - --ry --.-. - . ,
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I No.97047210 .
NUMBER PROCEDURE TITLE REVISION 02 EPIP-4.16 0FFSITE MONITORING PAGE 12 of 12
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 18. TERMINATE EPIP-4.16:
a) COMPLETED BY:
DATE:
TIME:
e p
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No. 97487220
?
NUMBER A TTACHMENT TITLE REVISION EPIP-4.16 02 PRESELECTED MONITORING LOCATIONS FAGE A TTAC# MENT 2 1 of 3 LOCATION SECTOR DISTANCE (mi) DESCRIPTION
- 1. B-2 2 miles North on Route 650 at Hog Island Air Sampling Station.
- 2. F-1.6 Low level circulating water pumps at beginning of intake canal.
- 3. H-1.9 1.9 miles South on Route 650, left at road to public boat landing.
Monitoring point 1 mile, under Vepco power lines.
- 4. J-2.0 2.0 miles South on Reute 650; monitoring point at natural gas pipeline signs.
- 5. K-2,1 Route 650 South, right on Route 617, right on Route 10, right on Route 634.
Follow signs to Chippokes State Park, enter park and follow signs to historic section. Monitoring point at Chippokes Mansion.
- 6. L-2.3 Route 650 South, right on Route 617, right on Route 10, right on Route 634 Follow signs to Chippokes State Park; enter park and follow signs to Historic section. Monitoring point located at intersection of road and College Run Creek.
- 7. B-5.5 Rushmere Shores. South on Route 650, left on Route 628, left on Route 676.
At bend in the road, bear right on Route 686, lef t on Route 2001 into Rushmere Shores.
- 8. J-5 Route 650 South, left on Route 628.
Monitoring point 1.2 miles from intersection of Routes 650 and 628.
(Remote Assembly Area).
L _
no.97as722o Y
NUMBER A TTACHMENT TITLE REVISION EPIP-4.16 02 A TTACNMENT PRESELECTED MONITORING LOCATIONS PAGE 2 2 of 3 LOCATION SECTOR DISTANCE (mi) DESCRIPT-ION
- 9. K-5 Route 650 South, right on Route 10.
Monitoring point k mile from intersection of Routes 10 and 650 at bend in road.
- 10. L-5 Route 650 South, right on Route 617, right on Route 10, right on Route 633.
Monitoring point h North on Route 633.
- 11. M-5 Route 650 South, right on Route 617, right on Route 10 for approximately 5 miles, right on Route 634. Monitoring point 1.3 miles from intersection of Routes 634 and 10. Alliance Air Sampling Station, intersection of Routes 634 and 662.
- 12. N-4 From location ll, monitoring point 2 miles North on Route 662.
- 13. P-5 Scotland Wharf. Surry side on James River Ferry on Route 31 North.
- 14. 'Q-5 James River Ferry to Jamestown Route 31, right on Route 359. Follow signs to Colonial Parkway, left on Colonial Parkway. Monitoring location ik mile on Colonial Parkway.
- 15. R-5 James River Ferry to Jamestown side, Route 31 East, right on Route 682 " Neck of Land Road", left on Lake Powell Road, 1.3 miles to intersection of Routes 617 and 618.
- 16. A-5 James River Ferry, Route 31 East, right on Route 359, follow signs to Colonial Parkway, left on Parkway. Monitoring point 6.5 miles, k mile past Halfway Creek.
E
, ,,.-m . - . - --
r Nr.97847220 ,
- Y NUMBER A TTACHMENT TITLE ~^ REVISION EPIP-4.16 02 PRESELECTED MONITORING LOCATIONS PAGE A TTACHMENT 2 3 of 3 LOCATION SECTOR DISTANCE (mi) DESCRIPTION
- 17. B-5 Take Colonial Parkway from Jamestown, 7 miles to Route 199 East, Route 60 East, 3 lights, right on Kingsmill Road.
Monitoring location 1 mile from Route 60 and Kingsmill Road intersection.
- 18. C-5 Take Colonial Parkway from Jamestown, 7 miles to 199 East, Route 60 East, 3k miles to Ron Springs Road (road prior to Carter's Grove), right on Log Cabin Beach Road to sewage treatment plant.
- 19. D-5 Take Colonial Parkway from Jamestown, 7 miles to 199 East, Route 60 East, past Carter's Grove to Badische Corporation, right 1 mile to Vepco Substation.
- 20. E-5 Take Colonial Parkway from Jamestown, 7
. miles to 199 East. Take Route 60 East to Fort Eustis, Right at Fort Eustis, right at Lee 31vd., right on Kerr Road.
Monitoring point located at load dock.
, 21. F-4.8 Take Colonial Parkway from Jamestown, 7 miles to 199 East. Take Route 60 East
- to Fort Eustis, right at Fort Eustis, l right at Taylor Road, left on Harrison i
Road. Monitoring location 0.6 miles South from intersection of Harrison Road and Back River Road.
l l
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. No. 97387229 NUMBER A TTACHMENT TITLE REVISION EPIP-4.16 02
^ "' RM-14 CONVERSION FACTOR 4 1 of 1 i
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SURRY POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCEDURE TITLE REVISION 02 EPIP-4.18 g.. MONITORING OF EOF _ pAGE (With 4 Attachments) 1 of 8 PURPOSE -
Provide Health Physics coverage for personnel manning the EOF.
i USER Member of Inplant Monitoring Team.
ENTRY CONDITIONS Initiation of EPIP-4.02, Radiation Protection Supervisor Controlling Procedure; REVISION RECORD REV. 00 PAGE(S): Entire Procedure DATE:07-29-82 REV. 01 PAGE(S): 1,4,5,6,7,8, Att. 3 page 1, Att. 4 Page 1 DATE:02-24-83 REV. 02 PAGE(S): Page 1 of 8 and Attachment 3 DATE:SEP 2 31583 REV. PAGE(S): DATE:
REV. PAGE(S): DATE:
REV. PAGE(S): DATE:
REV. PAGE(S): DATE:
APPROVED DA TE APPROVAL RECOMMENDED SEP 2 31983 QC REV CHAIRMAN STA TION NUCLEA R_ SAFETY
, ) _ .
AND GPERA TING COMMITTEE
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No.97887220 7
NUMBER A TTACHMENT TITLE REVISION EPIP-4.18 02 RM-14 CONVERS7.ON FACTOR NE A TTAC# MENT 3 1 of 1
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i VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION -
EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PRCCEDURE TITLE REVISICN 02 EPIP-4. L ' POST AC,C,lDENT SAMPLING OF PIACTOR COOLANT FA CE (With 1 Attachment) 1 of 14 PURPOSE ,
- 1. To collect a post accident sample of reactor coolant from the hot leg of Unit 1 g Unit 2 Reactor Coolant Systems.
USER Chemistry Team Leader AND Chemistry Team Member.
ENTRY CONDITIONS
- 1. Entry directed by Emergency Technical Director S
- 2. Entry directed by Station Emergency Manager 1
REVISION RECORD REV. 00 PAGE(S): Entire Procedure DATE:07-29-82 REV. 01 PAGE(S): 1, 13, 14 DATE:02-24-83 PIV. 02 PAGE(S): Pages 1 of 14 through 14 of 14 DATE:SEP 2 31333 REV. PAGE(S): DATE:
l DATE:
REV. PAGE(S):
REV. PAGE(S): DATE:
REV. PAGE(S): DATE:
APPROVED DA TE APPROVAL RECOMMENDED N^ SEP 2 31983 OC REVI W CHAIRMAN STATION NUCLEAR SAFETY AND OPERATING CabfMITTEE 1
I
N3.97857210 NUMBER PROCE00RE TITLE REVISION 02 EPIP-4.23 POST ACCIDENT SAMPLING OF REACTOR COOLANT FACE (With 1 Attachment) 2 of 14
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 1. INITIATE PROCEDURE:
a) By:
Date:
Time:
NOTE: Only one reactor coolant sample may be obtained from this system.
- 2. VERIFY STATION SYSTEMS:
a) Systems Operable a) IF NOT ope able, request operations assistance to l
- 1) Station Service Electrical insure system operability i System per OP-21
- 2) Component Coolant System i per OP-H l 1
- 3) Compressed Air Service System l per OP-M i
- 4) Ventilation System per OP- H
- 5) Radiation Monitoring System per OP-56, 6
- 3. DESIGNATE SAMPLING PARTY:
a) Chemistry team leadcrs AND b) Chemistry team members
. . - .r - . _ y -_ . - , .
NL 97887210 NUMBER PROCEDURE TITLE REVISION 02 EPIP-4.23 POST ACCIDENT SAMPLING OF BIACTOR COOLANT PAGE (With 1 Attachment) 3 of 14
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED 4 VERIFY RWP:
a) RWP issued a) IF NOT issued, request initiation of RWP.
- 5. OBTAIN REQUIRED '
EQUIPMENT:
a) 2 adjustable wrenches b) Extension wrench c) Come-A-Long or equivalent d) ,5_ gallon poly bottle e) 10 ft. of 3/4" tygon tubing
- 6. DRESS OUT:
a) Have sample party dress out IAW RWP
- 7. OBTAIN SAMPLE ROOM RAD LEVEL:
a) RM-RMS-156, " Sample Area Monitor"
- 8. BRIEF SAMPLING PARTY:
a) Review sampling procedure b) Review entry and exit routes c) Review RWP requirements
- 1) Stay times
- 2) Protective clothing
- 3) Dosimetry
- 4) Respiratory equipment
- 5) H.P. monitoring
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NUMBER PROCEDURE TITLE REVISION 02 EPIP-4.23 POST ACCIDENT SAMPLING OF REACTOR COOLANT PAGE (With 1 Attachment) 4 of 14
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT QBTAINEO
- 8. (CONTINUED) d) Review cautions
- 1) High radiation levels
- 2) High sample activity level
- 3) High pressure sample
- 4) High temperature sample
- 5) Open valves slowly
- 9. NOTIFICATIONS:
a) Notify Station Emergency Manager sampling party is being dispatched AND Notify Shift Supervisor sampling party is being dispatched
- 10. DISPATCH SAMPLE TEAM:
a) Insure sample party has a copy of this procedure NOTE: Refer to attachment 1 for system arrangement
- 11. PROCEED TO PRIMARY SAMPLE ROOM:
a) Monitor radiation levels b) Follow preplanned routes c) Leave rope at Aux. Bldg.
entry Door.
)
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Ns.97887210 NUMBER PROCEDURE TITLE REVISION 02 EPIP-4.23 POST ACCIDENT SAMPLING OF REACTOR COOLANT PACE (With 1 Attachment) 5 of 14
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 12. VERIFY SAMPLE COLLECTION CYLINDER CONNECTED:
a) Cylinder - IN SHIELDE.D a) IF NOT, place in " PIG"
" PIG" b) Quick Disconnect - CONNECTED b) IF NOT, connect quick disconnect c) Vent valve 1-SS-237 - CLOSED c) IF NOT, close valve 1-SS-237 d) Vent plug on tank 2 - REMOVED d) IF NOI remove plug
- 13. ENTER PRIMARY SAMPLE ROOM:
a) Observe radiation readings on RM-RMS-156 " Sample Room Monitor"
- 14. VERIFY DILUTION WATER - TK_3:
a) Insure dilution water a) IF NOT updated, drain checklist on wall is sampling tank updated AND Add 835 ml of DI water through funnel AND GO TO STEP M
- 15. VERIFY NITROGEN BOTTLE PRESSURE:
a) Open isolation valve 1-SS-241 on Nitrogen Bottle
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NUMBER PROCEDURE TITLE REVISION 02 EPIP-4.23 POST ACCIDENT SidiPLING OF REACTOR COOLANT PAGE (With 1 Attachment) 6 of 14
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 15. (CONTINUED) b) Verify Nitrogen Bottle b) IF NOT, leave area pressure GREATER THAN 200 PSIC AND initiate Nitrogen Bottle replacement AND GO T0 step 16
- 16. VERIFY VALVE LINE UP:
a) Insure follosing valves - CLOSED 1-SS-229 1-SS-230 1-SS-233 1-SS-236
~
1-SS-238 1-SS-239 1-SS-240 i 1-SS-241 1-SS-242 valve "K" valve "L" b) Insure following valve - OPEN 1-S5-231
- 17. VENT AND DRAIN HOLDING TANK - TKJ_
a) Remove vent plug on TK1, b) Insure following valves - CLOSED 1-SS-234 1-SS-235 a-,-- m m - -,-m-,-
Ns.97847210 NUMBER PROCEDURE TITLE REVISION 02 EPIP-4.23 POST ACCIDENT SAMPLING OF REACTOR COOLANT PAGE (With 1 Attachment) 7 of 14
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 17. (CONTINUED) c) Attach tygon tubing to 1-SS-234 AND Attach opposite end to
,5_ gallon poly bottle d) Insure following valves - OPEN 1-SS-234 1-SS-235 e) Drain until flow to 5 e) IF N0 flow detected gallon poly bottle stops Go TO Step 18_
- 18. ISOLATE HOLDING TANK:
a) Insure following valves - CLOSED 1-SS-235 1-SS-234
- 19. DETERMINE UNIT TO BE SAMPLED:
a) IF UNIT 1 to be sampled a) IF UNIT 2 to be sampled GO TO NOTE prior to Step 20_ GO TO NOTE prior to Step H NOTE: Step g is for sampling Unit 1_.
- 20. SAMPLE UNIT 1,:
a) Insure control room valves - CLOSED TV-SS-106A TV-SS-106B
N D, 97887210 NUMBER PROCEDURE TITLE REVISION 02 EPIP-4.23 POST ACCIDENT SAMPLING OF REACTOR COOLANT PAGE (With 1 Attachment) 8 of 14
(
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 20. (CONTINUED) b) Insure following valve CLOSED 1-SS-228 c) Insure UNIT J_ sample line trip valve (solenoid valve back of sample room) -
OPEN HCV-SS-101D d) Insure following valve - OPEN 1-SS-233 e) Insure control room trip valves - OPEN TV-SS-106A TV-SS-105B CAUTION: Flow of high activity reactor coolant will connence when next steps are performed.
f) Observe sample line pressure gage PI-SS-200 g) Carefully open following valve 1-SS-229 AND AT 20 PSIG on PI-SS-200 l insure following valve - CLOSED 1-SS-229
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43.9F867230 NUMBER PROCEDURE TITLE REVISION 02 EPIP-4.23 POST ACCIDENT SAMPLING OF REACTOR COOLANT PAGE (With 1 Attachment) 9 of 14
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT 0 STAINED
- 20. (CONTINUED) h) Insure following valve - CLOSED l-SS-233 i) Insure following valves - OPEN 1-SS-236 valve "I" l-5S-236 valve "J" j) Observe sample pressure gage PI-SS-200 k) Cycle following valve 1-SS-229 AND AT 100 PSIG on PI-SS-200 Esure following valve - CLOSED l-SS-229 AND E TO G Step E NOTE: The following step is for sampling UNIT 2
! 21. SAMPLE UNIT 2,:
i a) Insure control room valves - CLOSED TV-SS-206A TV-SS-206B t
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us. orsanto NUMBER PROCEDURE TITLE REVISION 02 EPIP-4.23 POST ACCIDENT SAMPLING OF REACTOR COOLANT PAGE (With 1 Attachment) 10 of 14
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 21. (CONTINUED) b) Insure following valve - CLOSED 2-SS-240 c) Insure UNIT 2 sample line trip valve (solenoid valve - back of sample room) -
OPEN HCV-SS-201D d) Insure following valve - OPEN 1-SS-233 e) Insure control room trip valves - OPEN IV-SS-206A TV-SS-206B l
l CAUTION: Flow of high activity reactcr coolant will commence when next steps are performed.
f) Observe sample line pressure gage PI-SS-200 l
i b
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N3.97887210 NUMBER PROCEDURE TITLE REVISION 02 EPIP-4.23 POST ACCIDENT SAMPLING OF REACTOR COOLANT PAGE (With 1 Attachment) 11 of 14
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 21. (CONTINUED) g) Carefully open following valve 1-SS-230 AND AT 20 PSIG on PI-SS-200 insure following valve - CLOSED 1-SS-230 h) Insure following valve - CLOSED 1-SS-233 i) Insure following valves - OPEN
- 1-SS-236 valve "I" 1-SS-236 valve "J" j) Observe sample pressure gage PI-SS-200 k) Cycle following valve 1-3S-230 AND AT 100 PSIG on PI-SS-200 E sure following valve - CLOSED 1-SS-230
- 22. ISOLATE AND TRANSFER CALIBRATED SA.WLE:
a) Insure following valves - CLOSED 1-SS-236 valve "I" 1-SS-236 valve "J"
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NL 97867210
- t NUMBER PROCEDURE TITLE REVISION 02 EPIP-4.23 POST ACCIDENI SAMPLING OF REACTOR COOLANT PAGE (With 1 Attachment) 12 of 14
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 22. (CONTINUED) b) Insure following valves - OPEN valve "K" valve "L" l-05-236 c) Verify valve 1-SS-238 - OPEN until pressure on sample bottle is appx. 50 PSIG AND Wait appx. one minute to complete transfer.
d) Insure following valves - CLOSED f I
I l-SS-238 valve "K" 1-SS-236 valve "L" 1-SS-236 f
- 23. DISCONNECT. SAMPLE CYLINDER:
a) Use adjustable wrench b) Disconnect quick disconnect c) Lower lid onto sample " pig"
- 24. SURVEY SAMPLE PIG:
a) Survey sample " pig" to.
determine rad levels and hot spot locations g -=w4y - - ..ym, .-.
N3.97887210 NUMBER PROCEDURE TITLE REvlSION j
~
02 I EPIP-4.23 POST ACCIDENT SAMPLING OF REACTOR COOLANT PACE (With 1 Attachment) 13 of 14
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 25. TRANSPORT PIT:
a) Unlock wheel brakes b) Use preplanned exit route c) Avoid hot spots on pig ,
d) Roll sample pig to Aux. Bldg.
exit door CAUTION: The sample pig is extremely heavy and may present a hazard if allowed to roll down the ramp un-restrained. Use caution in lowering.
- 26. LOWER PIG DOWN RAMP:
a)" Use come-a-long to lower sample pig down ramp
- 27. TRANSPORT PIG TO HOT LAB:
a) Roll. pig to Chemistry Hot Lab l
I b) Place shielded sample pig in corner by the A.A.
- 28. RECORD SAMPLE DATE/ TIME a) Date b) Time l
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20.97887210 i
NUMBER PROCEDURE TITLE REVISION 02 EPIP-4J23 POST ACCIDENT SAMPLING OF REACTOR COOLANT PAGE (With 1 Attachment) 14 of 14
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINEC
- 29. HAVE SAMPLE TRIP VALVES SHUT:
a) Notify Shift Supervisor that sampling completed b) IF sampling Unit 1, have a) IF sampling Unit 2_, have Control Room shut TV-SS-106A Control Room shut AND TV-SS-106B TV-SS-206A AND TV-206B i
- 30. NOTIFICATIONS:
a) Notify following that sampling completed
- 1) Shift Supervisor
- 2) Station Emergency Manager
- 31. SAMPLE ANALYSIS:
a) Request initiation of RWP to dilute sample b) Consider initiation of EPIP-4.26, High activity Sample Analysis, upon termination of procedure
- 32. TERMINATE EPIP-4.23:
a) COMPLETED BY:
THIE:
DATE:
b) , Forward procedure to SNSOC for review EhT
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VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION --
t EMERGENCY PLAN IMPLEMENTING PROCEDURE I
. NUMBER PROCEDURE TITLE REVISION ;
l 04 EPIP-2.01 NOTIFICATION OF STATE AND I.0 CAL GOVERNMENTS _ . PA GE (With 2 Attachments) 1 of 17 PURPOSE
- 1. To initially notify state and local governme:its cf the declaration of an emergency; AND
- 2. To provide periodic status updates to state and local governments during an emergency; AND
- 3. To notify state and local governments of any change in emergency status.
USER Emergency Communicator or Station Emergency Manager.
ENTRY CONDITIONS Any one of the following:
- 1. Emergency is declared; E
- 2. Approximately 30 minutes have passed since last notification; E
- 3. The status of any notification item has changed; E
- 4. Entry directed by Station Emergency Manager.
! REVISION RECORD REV. 00 PAGE(S): Entire Procedure DATE:07-29-82 REV. 01 PAGE(S): 8 of 17 DATE:09-02-82 REV. 02 PAGE(S): 1 of 17, 4 of 17, and 9 of 17 DATE:02-03-83 REV. 03 PAGE(S): 1, 7 thru 15, Att. 1, pg. 1; Act. 2, pg. 2 DATE:08-25-83 REV. 04 PAGE(S): 1, 5, 8, 12 DATE g g 333 l REV. PAGE(S): DATE REV. PAGE(S): DATE:
APPROVA v MENDE APPROVED CA TE M p 3
' / '/ C IAIRMANSTA TION NUCLEAR SAFETY UI 2 31383
\
MC REVIEW , . '&, fl' /
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AND GPERATING COMMITTEE l
No.stsspsto NUMBER PROCEDURE TITI.E REVISION 04 EPIP-2.01 NOTIFICATION OF STATE AND LOCAL GOVERNMENTS PACE 5 of 17 e e r
- STEP ACTION! EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 6. (CONTINUED) l TABLE 3 SIGMA THETA STABILITY SIGMA THETA STABILITY (DEGREES) CLASS (DECREES) 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 I
c) Record stability class in Step M {
l
- 7. CHECK RADIOACTIVE RELEASE STATUS:
a) Release - HAS OCCURRED a) IF NOT, record "None" in item 8_ of Attachment 1, pR, AND Release - IS OCCURRING GO TO Step H.
0R Release - IS PROJECTED
- 8. DETERMINE AFFECTED SECTORS:
a) Use wind direction from 7 Item 7 of Attachment 1 AhT
- ~ - + ,
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1 No.stestato NUMBER PROCEDURE TITLE REVISiCN 04 EPIP-2.01 NOTIFICATION OF STATE AND LOCAL GOVEPJ E TS PACE 8 of 17
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 13. RECORD YOUR NAME AND TITLE:
a) Record in Item H of AttachmentJ_
- 14. OBTAIN APPROVAL TO TRANSMIT l
MESSAGE:
a) Show completed Attachment I to Station Emergency Manager b) Receive approval to transmit
_ 15. TRANSMIT MESSAGE TO STATE AND LOCAL GOVERhMTS:
a) Use Insta-Phone a) IF NOT operable, use normal station telephone. Call following in order listed:
- 1) Surry County 9-1-294-3156
- 2) James City County 9-1-253-2300
- 3) State of Virginia 9-1-323-2300 Ask for Duty Officer
- 4) Isle of Wight 9-357-2151 or 9-357-3191
- 5) Williamsburg 9-1-229-1544
- 6) Newport News 9-1-247-2578 9-1-247-2579
- - 9-1-247-2580
-. , ,-- .,- n. .... , . - . . - . .
No.s7ss7220 NUMBER PROCEDURE TIT.E REVISION 04 EPIP-2.01 NOTIFICATION OF STATE AND LOCAL GOVERNMENTS PAGE 12 of 17
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED 24 RECORD METEOROLOGICAL DATA:
a) Obtain wind direction, w'ind speed, and stability class from most recent Attachment 1 completed b) Stability Class c) Record in item 5 of Attach-ment 2
- 25. DETERMINE TEMPERATURE:
a) _IF_ in Control Room, obtain a) IF NOT, contact Control Room temperature from "CH.A - and request data.
Temperature" recorder -
b) Record temperature in Item 6 of Attachment 1
- 26. DETERMINE PRECIPITATION: I a) Determine AND record pre-cipitation from in Item 6 of Attachment 2
- 27. INFORM RADIOLOGICAL ASSESSMENT DIRECTOR:
a) Inform Radiological Assess-ment Director of tempera-ture AND precipitation data
- 28. UPDATE STATUS BOARD:
a) IF status board being main- a) IF NOT, GO TO next step.
tained, insure temperature and precipitation data updated N
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VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION !
EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCEDURE TITLE REulSION 07 EPIP-3.01 CALLOUT OF EMERGENCY RESPONSE PERSONNEL _ .PA CE (With 1 Attachment) 1 of 3 PURPOSE ,
- 1. To callout station AND corporate emergency response personnel if they are not already at their normal work locations.
USER Security Team Leader g Station Emergency Manager ENTRY CONulTIONS e
- 1. Initiation directed by the Station Emergency Manager.
a l
REVISION RECORD REV. 01 PAGE(S): Page 1 of 3 & Att. 1, Page 3 of 6, 4 of 6 DATE: 10-07-82 REV. 02 PAGE(S): Page 1 of 3 and Attachment 1, Page 2 of 6 DATE: 02-03-83 REV. 03 PAGE(S): 1 of 3 & Att.1 Pg. 1 of 6, 2 of 6, 3 of 6 DATE: 03-10-83 REV. 04 PAGE(S): 1 of 3, Act. 1 Pg. 1 of 6 and 2 of 6 DATE: 03-11-83 REV. 05 PAGE(S): 1 of 3, Att. 1 Pg. 3 of 6 and 4 of 6 DATE: 04-15-83 REV. 06 PAGE(S): 1 of 3, Att. 1 Pg. 2 of 6 DATE: 06-17-83 REV. 07 PAGE(S g 1, att. 1 pg. 3, 4 DATE:SEP g g 1983 APPROVA NCEO ! APPROVED DA TE
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No.97887220 N. UMBER A TTACHMENT TITLE REVISION EPIP-3.01 07 EMERGENCY PERSONNEL NOTIFICATION LIST 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 EIT. TELEPHONE hTMBER H. W. Kibler 214 9-357-5413 Beeper 83 or 9-1-(629-8116) n Mike Haduck 213 9-238-3165 John Patrick 228 9-357-3310 Dick Mudd 447 9-1-850-0458
- 7. SECURITY DEPARTMENT MESSAGE: "This is Security at Surry Power Station . This message is to inform you that an emergency has 'aeen declared at the station."
l NAME EXT. TELEPHONE hTMBER Otto Wegman 310 9-357-5815 H. J. Van Dyke 314 9-1-838-1365 W. D. Sweaney 514 9-1-294-5105 mus-mae- eep W p+.e oee e. -@ m D-e
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w Na, 97887210 NUMBER PROCEDURE TITLE REVISION EPIP-3.01 07 EMERGENCY PERSONNEL NOTIFICATION LIST PAGE 1 4 of 6
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 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 accordancc with your departmental emergency notification list."
NAME EXT. TELEPHONE NUMBER l
W. R. Runner 358 9-1-541-0779 j E. P. DeWandel 217 9-1-420-6064 F. M. Cox 393 9-357-5070 Luther Farinholt 359 9-1-294-3063 B. B. McDuffie 377 9-1-595-2569 l
- 9. OUALITY CONTROL 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 EIT. TELEPHONE NUMBER Richard Driscoll 259 9-1-340-2167 Frank Rentz 257 9-357-5509 Dean Grady 256 9-1-874-5089 Rich Euebner 253 9-1-495-3469 I
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go,7as7230 VIRGINIA ELECMIC AND POWER COMPANY SURRY POWER STATION -"
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EMERGENCY PLAN IMPLEMENTING PROCEDURE NUVBER PROCEDURE TITLE REVISION 03 EPIP-5.03 PERSONNEL ACCOUNTABILI"T , . P4 05 (With 1 Attachment) 1 of 7 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.
- 2. To previde a periodically updated list of all personnel inside the protected area.
USER Security Team Leader.
~ ENTRY CON 01,10NS m
Any one of the following:
- 1. Activation by another EPIP; E
- 2. Declaration cf a Site Emergency, or General Emergency; E
- 3. Any time deemed necessary by the Station Emergency Manager.
1 REVISION RECORD REV. 00 PAGE(S): Entire Procedure DATE:07-29-82 PIV. 01 PAGE(S): 1 of 7, 2 of 7, 6 of 7 DATE:02-24-83 REV. 02 PAGE(S): 1 of 7, 2 of 7; Act, 1, pg. 1, 2 & 3 DATE:08-15-83 REY. 03 PAGE(S): 1, 2, 3, Att. 1, pg. 2, 3 DATE:ggp 3 9 W REV. PAGE(S): DATE:
REV. PAGE(S): DATE:
REV. PAGE(S): DATE:
APPRC MMEN APPROVED DA TE a #M .3 A ggpgy g
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NUMBiR PROCEDURE TIT!.E REVISION 03 EPIP-5;03 PERSONNEL ACCOUNTABILITY PAGE 2 of 7
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 1. INITIATE EPIP-5.03:
a) INITIATED BY:
TIME:
DATE:
- 2. VERIFY EVACUATION STATUS:
a) Evacuation - NOT ORDERED a) IF evacuation ordered, GO TO Step 10.
NOTE: Each Emergency Assembly Area will have an Emergency Assembly Area Leader. This person will be a supervisor or other
_ cognizant person normally working in the Emergency Assembly Area.
Each Emergency Assembly Area Leader will it: mediately 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.
Each Emergency Assembly Area Leader will record the above information and forward it to Security.
l l
l 3. INITIATE ACCOUNTABILITY WITHOUT I
EVACUATION:
a) Make announcement on station Gai-Tronics system as follows:
- 1) " Emergency Assembly Area Leaders - TAKE ACCOUNT-ABILITY"
- 2) " Emergency Assembly. Area Leaders deliver results of accountability to security"
/ 3) " Warehouse, Environmental lab &
-- South Annex call exts. 345 or 350 and report results of accountability to security"
4 Pso. 99889230 7
huMBER PROCEDURE TITLE REvlSION 03
~
EPIP-5.03 PERSONNEL ACCOUNTABILITY PAGE 3 of 7
(
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 3. (CONTINUED) b) Repeat Step 3.a THEN con- ,
tinue with this instruction
- 4. CALL PIP:
a) Use station PBX - #84-456 b) Instruct them to perform accountability c) Instruct them to report results to extension (give number)
- 5. CALL TRAINING CENTER:
a) Use station PBX - #270, 271, or 272 l b) Instruct them to perform i
accountability j c) Instruct them to report results to extension l
l (give number) i
- 6. RECORD RESULTS:
a) As accountability results l arrive, record on Attach-ment 1, Personnel Account-ability Form
- 7. BALANCE RESULTS:
l a) Balance Column 1 against l
Column 2
( 1) Strike names appearing j /' in both columns
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PC. 97887220
- 3 NUMBER A TTACHMENT TITLE REVISION EPIP-5.03 03 PERSONNEL ACCOUNTABILITY A TTACHMENT PAGE 1 2 of 3 Column 1 - those missing Colu:nn 2 - those present ASSEMBLY AREA from their assembly area that should not be here (Name) (Name and Badge No.)
SOUTH ANNEX:
Engineers Q. C. Department Reproductions Station Records -
Medical Department W. B. Count Room INSTRUMENT CAL LAB:
~
Instrument Cal Lab Personnel CONTROL ROOM:
Operations Dept.
INSTRUMENT SHOP:
I Instrument Dept.
HEALTH PHYSICS OFFICE:
H.P. Department Dose Control l Clean Change Room CHEMISTRY LAB:
Chemistry Dept.
-' MAINTENANCE SERVICES:
Maintenance Services
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N9.97887220 NUMBER A TTACHMENT TITLE REVISION EPIP-5.03 03 PERSONNEL ACCOUNTABILITY A TTACHMENT PAGE 1 3 of 3 Column 1 - those missing - Column 2 - those present ASSEMBLY AREA from their assembly aren that should not be here (Name) (Name and Badge No.)
CONDENSATE POLISHING:
Operations Dept.
Tool Room 1St Floor NEW MACHINE SHOP:
Mechanical Maintenance Electrical Maintenance Weld Shop
_ Planning
- 1 TURBINE BLDG. BASEMENT:
Non VEPCO Construction STORER0OM:
i Storeroom Personnel Fire Marshal and Staff 1
PD l
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, VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION --
- t EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCEDURE TITLE REVISICN 03 EPIP-4.09 -
SOURCE TERM ASSESS} m . . PA CE (With 4 Attachments) 1 of 10 PURPOSE Provide guidance and data to Dose Assessment Team to more accurately predict offsite releases.
USER Dose Assessment Team Members.
ENTR f CONDITIONS Upon activation of EPIP-4.03, Dose Assessment Controlling Procedure..
REVISION RECORD REV. 00 PAGE(S): Entire Procedure DATE:07-29-82 REV. 01 PAGE(S): 1, 3, 4, 5, 6, Act. 1 Page 1 DATE:03-03-83 REV. 02 PAGE(S): 1 of 10 through 10 of 10 & Attachment 4 DATE:09-23-83 REV. 03 PAGE(S): 1, Att. 3 page 1, Att. 4 pages 1 & 2 DATE:SEP 2 3 boJ REV. PAGE(S): DATE:
REV. PAGE(S): DATE:
REV. yGE(S): DATE:
APPROVA ' ENDED APPROVED DA TE
/
M REVI Al9 t r< k ,,,,,~
/ '/ H RMANSTA TION NUCLEAR SAFETY
\,, , ,f qf Qc3 AND GPERA TING COMMITTEE g i .
Nr.97887220 NUMBER A TTACHMENT TITLE REVISION E?IP-4.09 03 CONTAINMENT HIGH RANGE MONITOR A TTACHMENT (PERSONNEL HATCB) PAGE 1 1 of 1
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No,s7ssrzro NUMBER A TTAC# MENT TITLE ggyjgyn'y EPIP-4.09 QI T C E ES I-131 FOR LOCA ACCIDENT ATTAC# MENT PAGE g 2 of 2 NOTE: Within the first 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> following LOCA in'cident. IODINE decay is insignificant.
QUIVALENT CURIES EVENT I-131 LOCA 3.85 E+3 (12 Clad Failure)
LOCA 3.85 E+4 (10% Clad Failure)
LOCA 3.85 E+5
- (100% Clad Failure)
LOCA 5.93 E+5 (1% Fuel Melt)
LOCA 5.93 E+6 (10* Fuel Melt)
LOCA 5.93 E+7 (100% Fuel Melt) p e
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g.; nw VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION --
EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCEDURE TITLE REVISION 00 EPIP-4.22 -
POST ACCIDENT SAMPLING OF CONTAINMENT AIR ,
PACE 1 of 6 PURPOSE
- 1. To collect a post accident sample of containment air from Unit 1 OR Unit 2 Contairment.
USER Sample Team.
ENTRYCONDITIONS
- 1. Entry directed by Emergency Technical Director, SE
- 2. Entry directed by Station Emergency Manager.
I i REVISION RECORD REV. 00 PAGE(S): Entire Procedure DATE: ggp 2 3 1983 REV. PAGE(S): DATE:
REV. PAGE(S): DATE:
REV. PAGE(S): DATE:
REV. PAGE(S): DATE:
REV. PAGE(S): DATE:
REV. PAGE(S): DATE:
RWIN f$
3% z. p ,
/ f 'j / IRMANSTA TION NUCLEAR SAFETY
( , &L ,/c ,/p a AND CPERATING CbMMITTEE
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. No.97887210
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NUMBER PROCEDURE TITLE REVISION 00 EPIP-4<22 POST ACCIDENT SAMPLING OF CCNTAU; MENT AIR PACE 2 of 6
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 1. INITIATE EPIP-4.22:
a) BY:
DATE:
TIME:
1 NOTE: The RWP for drawing this sample should specify the following, if appropriate:
- 1. High and low range dosimetry,
- 2. Wrist, head, and ankle TLDs,
- 3. Full waterproof protective clothing,
- 4. Continuous H.P. monitoring using a 0-1000R meter, and
- 5. Self contained breathing apparatus.
- 2. VERIFY RWP:
a) RWP - ISSUED a) IF NOT issued, initiate RWP.
- 3. DESIGNATE SAMPLING TEAM:
a) 1 Operator AND b) 1 Monitoring Team Member
~
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No. 99887810 i
NUMBER PRGCECURE 17TLE REVISION 00 EPIP-4.22 POST ACCIDENT SAMPLING OF CONTAINMENT AIR FACE 3 of 6
( _ .
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 4. PREPLAN ROUTES: -
a) Coordinate with Radiation Protection Supervisor b) Check area survey caps to locate lowest dose fields for moving to and from sampling point
- 5. BRIEF SAMPLING TEAM:
a) Review this procedure b) Review entry and exit routes c) Review RWP requirements:
- 1) Stay times
- 2) Protective requirements
- 3) Dosimetry
- 4) Respiratory equipment
- 5) Monitoring d) Review cautions: c
- 1) High radiation levels
- 2) High activity samples
- 3) Buddy system
- 6. DRESS OUT:
a) Have sample party dress
i een, 97887210 '
- t l NUMBER PROCEDURE TITLE REvlSION 00 EPIP-4.22 POST ACCIDENT SAMPLING OF ,
CONTAINMr3T AIR FAGE 4 of 6
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 7. NOTIFICATION:
a) Notify following that sample team being dispatched:
- 1) Station Emergency Manager *
- 2) Radiological Assessment Director
- 3) Shift Supervisor
_ 8. DISPATCH SAMPLE TEAM:
a) Give sample party a copy of this procedure and OP-12.1 NOTE: The following steps are performed by the sampling team to draw a sample. The sample will actually be taken by performing the applicable steps of OP-12.1 High Radiation Samoling System.
- 9. PERFORM THE FOLLOWING SECTIONS OF OP-12.1:
a) Section 5.1, HRSS Startup 5.1.1 5.1.5 5.1.2 5.1.6 5.1.3 (Step 9 continued next page)
--. .- - y -
9
No. 97887280 NUMBER PROCE00RE TITLE REVISION 00 EPIP-4.22 POST ACCIDENT SAMPLING OF CONTAINMENT AIR PAGE 5 of 6
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 9. PERFORM THE FOLLOWING SECTIONS OF OP-12.1: (continued) b) Section 5.10, Containment l Air Sampling Procedure 5.10.1 5.10.5 l 5.10.2 5.10.7 l
5.10.3 5.10.8 5.10.4 5.10.9
_ 10. TRANSPORT SAMPLE:
a) Place gas chamber in poly bag b) Hold bag away from body j
i
! c) Transport to Chemistry Hot Lab using preplanned route.
- 11. LABEL SAMPLE:
l a) Label gas chamber with following information:
- 1) " Unit _ containment gas",
- 2) "I ce gas sample",
- 3) "1:100 dilution",
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No.97887210
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NUMBER PROCEDURE TliLE REVISION 00 EPIP-4.22 POST ACCIDENT SAMPLING OF CONTAINMENT AIR I #A6E 6 of 6
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT CBTAINED
- 12. PERFORM THE FOLLOWING SECTIONS OF OP-12.1:
a) Section 5.13, HRSS Shutdown 5.13.1 5.13.9 5.13.2 5.13.12 5.13.4 5.13.13 5.13.7 5.13.14 5'.13.8 5.13.15 n
- 13. NOTIFICATIONS: .
a) Notify the following that sampling completed:
- 1) Radiation Protection Supervisor
- 2) Shift Supervisor
- 3) Station Emergency Manager
- 14. TERMINATE EPIP-4.22:
a) COMPLETED BY:
TIME:
DATE:
- 15. FORWARD PROCEDURE:
/' a) Forward procedure to SNSOC
~' for review END m.w- +esee. un *
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No.97827220 NUMBER A TTACHMENT TITLE REVISION l EPIP-3.01 07 EMERGENCY PERSONNEL NOTIFICATION LIST EM 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 358 9-1-541-0779 E. P. DeWandel 217 9-1-420-6064 F. M. Cox 393 9-357-5070 Luther Farinholt 359 9-1-294-3063 --
B. B. McDuffie 377 9-1-595-2569
- 9. QUALITY CONTROL 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 NCiBER Richard Driscoll 259 9-1-340-2167 Frank Rent: 257 9-357-5509 Dean Grady 256 9-1-874-5089 Rich Huebner 253 9-1-495-3469
N s. 97887210 9
NUMBER PROCEDURE TITLE REVISION 02 EPIP-5.01 TRANSPORTATION OF CONTAMININATED
- A68 INJURED PERSONNEL 2 of 4
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 1. INITIATE EPIP-5.01:
a) BY:
DATE:
TIME:
- 2. VERIFY PERSONNEL CONTAMINATED INJURED:
a) Assure HP-3.6.1, Personnel a) Direct Health Physics to injury-ACTIVATED initiate HP-3.6.1 Personnel Injury, then GO TO Step 3_.
- 3. VERIFY AM3ULANCE:
a) Insure First-Aid Team a) Verify offsite rescue ,
Mecber obtains ambulance personnel notified if key from Security onsite ambulance NOT available l b) Insure ambulance is brought i to required location
! 4 REQUEST NIGHTINGALE
! ' AIR AMBULANCE:
a) If requested bf first aid a) IF NOT reauested then ;
team call Nightingale Air GO To Step 5.
Ambulance at 1-800-572-4354 i for cransport to Medical College of Virginia y ,w- ,
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