Text

Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures EPIP-4.22 Re post-accident Sampling of Containment Air & EPIP-4.01 Re Radiological Assessment Director
	ML20078F930
Person / Time
Site:	Surry
Issue date:	09/23/1983
From:	Cox F, Saunders R; VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	;
Shared Package
ML18141A153	List: ML18141A152; ML20078F928; ML20078F930;
References
	PROC-830923-01, NUDOCS 8310110240
	Download: ML20078F930 (100)
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vc 97887230 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIFICTOR PACE CONTROLLING PROCEDURE (With 2 Attachment) 1 of 31 PURPOSE To initially assess emergency conditions, provide prctective 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 t

t I

REVISION RECORD REV. 00 PAGE(S): Entire Procedure DATE: 07-29-82 REV. 01 PAGE(S):

1 of 31 thrct:gh 31 of 31 DATE: SEP :: 3 c:3 REV.

PAGE(3):

DATE:

A-REV.

PAGE(S):

DATE:

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REV.

FAGE(S):

DATE:

REV.

PAGE(S):

DATE:

REV.

PAGE(S):

DATE:

APPROVAL RECOMMENDED APPROVerv g;75 N

SEP 2 31953 O' #' ' E CHAIRMAN STA TION NUCLEA R SA FETY l

AND OPERA TING COMMITTEE 8310110240 831005 PDR ADOCK 05000200 F

PDR

Nn.07887210 NUMBER PROCE00RE TITLE REVISION 01 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING PROCEDURE 2 of 31 STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED 1.

INITIATE PROCEDURE:

a)

BY:

DATE:

TIME:

NOTE: During the initial stages of the emergency the Shift Supervisor may assume the position of Emergency Manager.

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2.

CHECK CONDITIONS:

a) The Senior Health Physics a) 1];TSC is activated, report individual onsite should to the TSC.

report to the Control Room

))[ the TSC is NOT activated b) Request briefing with Emergency Manager to determine:

1) Existing Plant Conditions

2) Emergency Action Levels (EALs) exceeded l

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 cent

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occurred GO To Step 15.

b) Request alternate on-shift technician to obtain, if possible, a sample of the effluent I

4 Ns.97ss7210 NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR

d6f CONTROLLING PROCEDURE 3 of 31 j

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) IF radiological release -

a) E the event is NOT radio-continue logical release GO TO Step L5.-

b) initiate EPIP-4.08 Initial Offsite Release Assessment to assess percent Tech Spec Limit Mm Return to Step 5.c l

c) Assess percent Tech Spec:

1) E normal range monitors

1) E normal range monitors indicate LESS THAN 100%

GREATER THAN E EQUAL I

Tech Spec, inform Emergency TO 100*. Tech Spec, GO To l

Manager initial results Step 5.e.2.

indicate LESS THAN UNUSUAL EVD;T AND GO TO Step 5.e

2) Il normal range monitors

2) E normal range monitors are onscale and indicate indicate GREATER TFJdi GREATER THAN 100% Tech 1000% Tech Spec, GO TO Spec, but LESS THAN,1000%

Step 6_.

Tech Spec M

l e

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td3. 97867210 NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PAGE CONTROLLING PROCEDURE 4 of 31 STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED 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)

IF, sample CANNOT be effluent release path obtained GO TO Step g.

f) Have sample (s) analyzed as per Health Physics procedure, H. P.

3.4.1.3 g) CO TO Step g for' follow up assessment 6.

EVENT - ALERT, SITE OR GENERAL:

a) E the emergency is classified a)

IF,the event is NOT a F

as an ALERT, SITE, g GENERAL radiological release, i

EMERGENCY GO TO Step E.

AND l

Radiological release ha:

occurred O_R may potentially occur, continue with this procedure i

i 7.

EVENT - CONDITION IV LIMITING

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FAULTS:

a) E event - Limiting Fault a) E accident is NOT a Accident:

Limiting Fault, GO TO Step g.

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1 N3.97887210

)

1 NUMBER PROCEDURE 17TLE REVISION 01 l

EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PACE CONTROLLING PROCEDURE 5 of 31

(

STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED l

i 7.

(CONTINUED)

1) LOCA - GO TO Step g i

)

S$E I

2) Steam Generator Tube Rupture - GO TO Step 9 2R,

3) Main Steam Line Rupture -

GO TO Step IC[

pR,

4) Fuel Handling Accident -

GO TO Step 8 8.

EVENT - FUEL HANDLING ACCIDENT:

a) Ij[ event - Fuel Handling accident:

1) Recommend evacuation of l

Fuel Building l

AND/OR Affected containment l-Building AND

2) Restrict access until radiological assessment can be made b) Assign EPIP-4.06, Persannel b)' I_F, individual found non-Monitoring and Decontamination contaminated, continue to monitor and decontaminate, with this instruction, as necessary, individuals evac-uated from accident area I

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No.97887210 NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING PROCEDURE 6 of 31 f STEP ACTION / EXPECTED RESPONSE RESPONSEN0TOSTAINED 8.

(CONTINUED) c) Initiate EPIP-4.08 Initial Offsite Release Assessment, to assess offsite releases AND Return to Step 8.d d) Report results of above step to Emergency Manager e) GO TO Step 13 9.

EVENT - STEAM GD;ERATOR TUBE RUPTURE:

a) IF event - Steam Generator a) IF event is NOT Steam Tube Rupture, request the Generator Tube Rupture, following from Emergency GO TO Step 10.

Manager:

1) Status of Air Ejector divert

2) Number of Steam Generator Relief Valves lifted, pR, Valves which may potentially lift

3) IJ[ relief valves lifted, length of time valves remained opeu

4) Status of main steam supply to the Auxilary Feedwater

? ump Turbine

5) Current Steam Generator Slowdown pathway

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N o. 97:en:o NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR i

^

CONTROLLING PROCEDURE 7 of 31 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 9.

(CONTINUED).

b) ))[ Air Ejector diverted to b) ))[ Air Ejector did NOT containment divert to containment l

AND OR l

t

[

Individuals are in affected IF NO individuals are in containment:

affected containment:

1) Request immediate evacu-

1) Continue with this ation of containment instruction.

c) ))[ main 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, f

1) Request Emergency Manager

1) GO TO Step 9.d.

initiate isolation of main steam supply, of affected l

generator, to Auxiliary Feedwater Pump Turbine I

d) Request placement of oper-ations personnel in E=ergency Switchgear Room to report:

l 1

1) Initial readings i

AhT I

2) Increase or decrease in i

Main Steam and AFWPT l

exhaust monitors 1

e) Initiate EPIP 4.08, Initial l

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Offsite Release Assessment:

1) Determine offsite dose rate i

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N3.97887210 NUMEER PROCEDURE TITLE REVISION 01 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PAGE CONTROLLING PROCEDURE 8 of 31 STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED 9.

(CONTINUED)

AND

2) GO TO Step 9.f of this instruction f) Report results of the above step to Emergency Manager g) Restrict access, until survey (s) confirm no radiological hazards:

1) Steam Generator Blowdown Cooler area

2) Steam denerator Blowdown Lines

3) Steam Generator relief valve area

4) Auxiliary Feedwater Pump Turbine exhaust area

5) Condensate Polishing Building h) ))[ personnel are available h) ))[ personnel are NOT avail-consider initiation of EPIP-able, consider sampling 4.23, Post Accident Sampling upon arrival of additional oj[ Reactor Coolant, to

=anpower assess core damage AND Continue with this instru-crion.

1) Consider sampling of $ team 44-Generator Blowdown and Main Steams of affected unit j) Potential liquid release pathway may occur through the Main Steam Safety Valve.

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N3.97887210 NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR

1. 6f CONTROLLING PROCEDURE 9 of 31 STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED 9.

(CONTINUED) k) GO TO Step M 10.

EVENT MAIN STEAM LINE RUPTURE:

a) g Main Steam Line Rupture a) E event is NOT a Main occurs, review station ven-Steam Line Rupture, GO TO tilation monitors Step M.

1) IF, 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.

Ir.itial Offsite Release Assessment

2) Assess offsite dose rate

3) Return to Step 10.b b) Report results to the Emergency Manager E _N,0, initial release has 0

c) occurred, source term may develop:

1) Inside containment 0,,R

2) From Main Steam Relief Valve Lift d) Request following information from the Emergency Manager:

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1) Location of Steam Break

2) Actual or potential lif ting of Main Steam Safety Valves y

N 3, 9788 7210 NUMBER PROCEDURE TITLE REVISION j

01 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR P,4 GE CONTROLLING PROCEDURE 10 of 31 STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED 10.

(CONTINUED)

3) ))[ 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) )); manpower is available:

e) ))[ manpower is NOT available continue with this procedure

1) Consider initiation of EPIP-4.22, Post Accident AND Sampling of Containment Air Consider initiation once manpower is available.

AND

2) Initiation of EPIP-4.23, Post Accident Sampling of Reactor Coolant f) GO TO Step 13, l

NOTE: LOCA accident may not initicily result in large release, but

=ay produce a large source with a potential for release from the containment building.

A --

11.

EVENT - LOCA

[

a) IF event - LOCA:

a) IF NOT LOCA, GO TO Step

_12.

1) Evacuate Auxiliary Building and Safeguards Building h

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r Np.97887210 NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PAGE CONTROLLING PROCIDURE 11 of 31 STEP ACTION / EXPECTED RESPONSE RESPONSE N0' J9TAINED 11.

(CONTINUED) wD l

2) Restrict entry until survey (s) confirm no radiological haz:ards b) "IF offsite release has b) IF cffsite release has occurred through monitored occurred through station ventilation, initiate unmanitored pathway EPIP 4.08, Initial Offsite Release Assessment 0]L Release has not occurred, bat may potentially cecure:

1) Assess offsite release

1) Assign an individual to initiate EPIP 4.03, Dose Assessment Controlling Procedure i

AND AND

2) Return to Step 11.c

2) Assess actual or i

potential release from I

containment.

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c) Report results of above step to Emergency Manager

(

l d) IF manpower is available, d) _I_F;=anpcwer NOT available:

consider the following:

1) Continue with this I

1)

EPIP-4.22, Post Accident instruction.

Sampling of Containment cb Air m- -

AND

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N3. 97847 210, '

?iUMBER PROCEDURE TITLE REVISl0N

~

01 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR

1. 0#

CONTR')LLING PROCEDURE 12 of 31 1

STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 3

11.

(continued)

2) Initiation of EFIP-4.23, Post Accident Sampling of Reactor Coolant e) GO TO Step M 12.

EVENT - RADIOLOGICAL RELEASES a) E event - Radiological a) E event is NOT a Radio-Release, continue with this logical Release, GO TO instruction Step M.

b) Initiate EPlP-4.08, Initial Offsite Release Assessment:

l)' Assass offsite 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-dividual at monitor of interest AND Report increase or decrease in reading 13.

VERIFY OFFSITE DOSE RATE:

a) Nresultsofoffsiterelease a) E results of offsite assessment at the Site release assessment at Site Soundary:

Boundary:

N,D. 97 847210 NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR

^ ##

CONTROLLING PROCEDURE 13 of 31 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 13.

(continued)

1) GREATER THAN g EQUAL TO

1) LESS THAN 50 mR/hr

,5,,0_ mR/hr Whole Body Whole Body 0

OR OR GREATER THAN OR EQUAL TO LESS THAN 250 mR/hr 250 mR/hr Thyroid Thyroid

2) Continue with this

2) GO TO Step M.

instruction 14.

PROTECTIVE MEASURES:

a) Obtain an estimate of a)

I_F,no estimate can be duration of release (hours) given,' assume 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months .

from Emergency Manager b) Use Site Boundary,.2, 5, and b) E 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) EPIP-4.08, E initial assessment

1) GO TO Step 14.b.2.

2) EPIP-4.03, E follow-up assessment c) Determine projected dose:

PRO.TECTED DOSE DURATION OF RELEASE x DOSE RATE

=

(hours)

(mR/hr)

(mR) n. a

1) Repeat above calcufation for all dose rates given in Step 14.b

'Ns.97887210 NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECIOR CONTROLLING PROCEDURE 14 of 31 STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED

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14.

(CONTINUED) d) IF projected dose -

d)

I_F, projected dose -

GREATER THAN O_R EQUAL TO LESS THAN 500 mR Whole 500 mR Whole Body Body OR OR GREATER THAN g EQUAL TO LESS THAN 1000 mR Thyroid 1000 Thyroid

1) Initiate EPIP-4.07,

1) Inform Emergency Man-Protective Measure ager NO protective measure required AND AND

/

2) Determine protective

2) CO 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) IF NO protective measures Manager:

required, GO TO NOTE prior to Step M.

1) Protective measures re-quired offsite AND

2) Distance protective measures required M.

NOTE: First Aid considerations must be given priority over decontamination of individual.

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'ND.97887210 NUMBER PROCEDURE T1TLE 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) ))[ the event is an Injured a) ))[ the event is NOT an In-Contaminated 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) ))[ individual decenned, 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) ))[ the event initiated e) ))[ other EALs were only for contaminated in-exceeded GO TO Step 16.

jured individual requiring offsite medical treatment,

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AND

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NO,other EALs exceeded:

O

1) GO TO Step jf[

'Ns.97887210 NUMBER PROCEDURE TITLE REVISION 01 EPlP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR

1. 0E CONTROLLING PROCEDURE 16 of 31 STEP ACTION / EXPECTED RESPONSE RESPONSENOT OBTAINED 16.

FOLLOW-UP ASSESSMENT:

a) E TSC NOT activated a) IF TSC IS activated GO TO continue with this in-Step M.

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:

ction.

1) Inform Emergency Manager AND

2) Report to Control Room immediately upon completion of task I

d) E a radiological release has d) IF NO release has occurred:

occurred:

1) GO TO Step g,

1) Continue with this instru-ction e) Obtain samples of the effluent e) IF NO samples can be ob-tained l

1) Analyze samples as per normal Health Physics

1) Continue with this procedure instructica AND AND l

2) E sample activity is high,

2) Use monitoring readings assign EPIP-4.26. High Level for follow-up assess-c._

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Activity Sample Analysis cent e

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ne.oreersia NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR

1. 66 CONTROLLING PROCEDURE 17 of 31 STEP ACTION / EXPECTED RESPONSE RESPONSE NOTQBTAINED l

16.

(CONTINUED) l l

IF, time allows:

f) E time is NOT available, f)

F I

l

1) Initiate EPIP-4.03, Dose

1) GO TO Step h Assessment Controlling Procedute AND AND

2) Return to Step 16.f.

l when time becomes avail-

2) Return to Step h able g) Insure dose control individual I

is available to 5upply dosimetry h) Provide H.P. coverage, as needed, for:

1) Damage Control Teams 9.E

2) Access control S

l

3) Personnel monitoring 0.3

4) Sample analysis

1) E the emergency has

1) E the emergency has NOT terminated GO TO Step E terminated GO TO Step 16 3 j) IF TSC IS manned, GO TO j) E the TSC is NOT manned:

Step ~17

1) Obtain latest dose rate b-(

2) Return to Step E l

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ND.97847210 NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PAGE CONTROLLING PROCEDURE 18 of 31 STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED 16.

(CONTINUED)

AND

3) Repeat sampling and

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assessment, as necess-ary 17.

VERIFY RELIEF:

a) When a more Senior Health a) E relief is NOT needed, Physics individual arrives GO TO Step H.

onsite 0,,R, E relief is needed:

1) Brief successor as to existing plant conditions AND

2) Offsite release assessment AND l

3) H. P. actions currently underway b) Announce the change of position to the Emergency Manager l

18.

ESTABLISH EMERGENCT ORGANEZATION:

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a) IF,the H. P. emergency a) E emergency organi:ation organization NOT activated, M activated, CO TO NOTE continue with this procedure prior to Step 2 I

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, me.svesnie NUMBER PROCEDURE UTLE REVISION 01 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR P40E CONTROLLING PROCEDURE 19 of 31 STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED 18.

(CONTINUED) b) IF manpower is available:

b) IJ[ 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)

IF, 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.

I 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) Ivaluate need for offsite a) E offsite comitoring NOT monitoring with Dose Assess-required, GO TO Step 22,.

ment Team Leader l

b) IF EOF NOT activated:

b) IF EOF activated, GO TO l

Step H.

1) Request Radiation P,ro-tection Supervisor to initiate EPIP-4.16, Offsite Monitoring 4 -

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ND.97847219 NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PAGE CONTROLLING PROCEDURE 20 of 31 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 10CTR20 limits, limits:

G_0 TO Step 19.e.

1) Initiate EPIP-4.04, Emergency Exposure Limits AND

2) Return to Step 19.e e)

_IF, Thyroid exposure exceeds e) E Thyroid exposure will 1_0, REM (refer to Attachment NOT exceed M REM, GO TO 0

2):

Step 19.f.

1) Initiate EPIP-5.07, Admini-stration of Radionrotective Drugs AND Return to Step 19.f f) Inform Radiation Protection Supervisor:

1) Number of monitoring teams

1) E adequate manpower NOT_

required available, GO TO Step 20_.

AND

2) Protective clothing required

3) Respiratory protection required i

l I

'No.97867213 NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PAGE CONTROLLING PROCEDURE 21 of 31 STEP ACTION / EXPECTED RESPONSE RESPONSE NOTQBTAINED 19.

(CONTINUED) g) Assist Dose Assessment Team in placement of offsite monitoring teams.

20.

OFFSITE ASSESSMENT:

a) IF offsite releases occur:

a) IF NO offsite releases have occurred

1) Request Emergency Manager place individual at monitor O_R R

of interest IF there is NO potential for a release AND

2) Report increase or

1) GO TO Step H.

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) E no data received GO TO Step 20.d.

1) Complete Attachment 1

2) Give Attachment 1 to the

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Dose Assessment Team g :

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Peo. 97887218 NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PACE CONTROLLING PROCEDURE 22 of 31 STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED 20.

(CONTINUED) d) Obtain latest offsite Release d) IF data not available, GO TO, Step 22.

Assessment Data Sheet from O

Dose Assessment Team 21.

VERIFY OFFSITE DOSE P. ATE:

I_F, Site Boundary dose rate:

a) E Site Boundary dose rate:

a)

F

1) GREATER THAN OR EQUAL TO

1) LESS THAN 50 mR/hr 50 mR/hr Whole Body Whole Body OR OR

2) GREATER THAN _OR EQUAL TO

2) LESS THAN 250 mR/hr 250 mR/hr Thyroid Thyroid b) Return to Step J4 b) GO TO Step E.

22.

EOF ACTIVATION:

a) IF EOF activated, continue a) IF EOF NOT activated, with this instruction GO TO Step M.

b) Brief Radiological Assess-ment Coordinator:

1) Existing plant conditions AND

2) Current offsite dose pro-jections AND A

3) H.P. actions undervey c) Inform Dose Assessment Team Leader to brief Radiological Assessment Coordinator:

=

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e No. 97887210 l

l 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 E0F:

1) Meteorological data AND

2) Monitor data AND

3) Sample analysis data 23.

ESTABLISH IN-PLANT MONITORING:

a) Brief Radiation Protection Supervisor as to existing plant conditions b) Assist in selecting proper b) IF NO monitoring is monitoring and sampling needed GO TO Step 23.e.

areas c) Instruct Radiation Protection Supervisor to initiate EPIP-4.14, Inplant Monitoring

m..

,u;D EPIP-4.15, Onsite Monitoring, as necessary

I

'No.97847218 NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PAGE CONTROLLING PROCEDURE 24 of 31 STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED 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) E a radiological release has f) GO TO Step h.

occurred AND A change in plume direction OR increase in release has Eken place

1) Notify Radiation Protection Supervisor

. s

^

AND

2) Request survey of emergency centers 4,

P90.97887210 NUMBER PROCEDURE TITLE REVISl0N 01 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PACE CONTROLLING PROCEDURE 25 of 31 STEP ACTION /EXPECTE0 RESPONSE RESPONSEN0TOBTAINED 23.

(CONTINUED) g) Based on survey data, direct the establishment of new control points:

1) Control spread of contami-nation AND/OR

2) Limit exposure 24.

ENTRANCE - ACCESS CONTROL AREA:

a) Entrance into access a) IF entrance is not required controlled areas should GO TO Step M.

require an evaluation of radiological hazards prior to entrance b) Assist Emergency Manager in obtaining Health Physics coverage, if necessary c) Consult with the Radiation Protection Supervisor as to the entrance requirements

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 h.

non-essential personnel in

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areas that:

'N).97987219 NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.01

. RADIOLOGICAL ASSESSMENT DIRECTOR PAGE CONTROLLING PROCEDURE 26 of 31 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 25.

(continued)

1) High airuorne activity is

1) E Airborne expected but not measured contamination NOT suspected, GO TO Step E.

2) Airborne activity is

2) E activity is LESS THAN 0,R, EQUAL TO 0.25 GREATER THAN 0.25 times R

maximum permissible maxi =um permissible concentration.

concentration GO TO Step E.

c) Assess need for respiratory protection, as pe'r EPIP-4.05 Respiratorv Protection and return to Step 26_

26.

DETERMINE NEED FOR RADIOPROTACTIVE DRUGS:

a) Determine, from survey results, concentration of radiciodine (uC1/ml) b) Determine actual or 1

l projected length of I

exposure time (hours) l i

c) E repiratory protection c) E respirator NOT worn, was worn, determine pro-use protection factor of tection factor:

1.

3

1) Refer to EPIP-4.05, Respirator Protection,, to determine protection factor h

d) Determine actual concen-

~

tration:

Step 2.a uCi/ml

=

Step 2.c l

l

=

- - - +

,,f

---rw

No. 97867210 NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PAGE CONTROLLING PROCEDUFI 27 of 31 STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED 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-nrotective 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-ESSENTLU, PERSONNEL:

a) Determine with Dose Assessment Team Leader, the projected or actual exposure, onsite, from release of radioactive material b) Determine direction of plume

<b c) Determine from Emergen.cy Manager duration of release IF, actual or projected d)

I_F dose is LESS SIAN evacu-d)

F exposure onsite:

ation limits

}

Peo. 97887210 NUMBER PROCEDURE TITLE REVISION 01 EPlP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PACE CONTROLLING PROCEDURE 28 of 31 STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED 27.

(CONTINUED)

~

1) GREATER THAN OR EQUAL TO g

1 Rem Whole Body E plume is in the direction AND/OR of the evacuation route:

2) GREATER THAN OR EQUAL TO

1) Consider sheltering of 5_ Rem Thyroid non-essential workers AND AND

3) Plume is NOT in the direction

2) GO TO Step 28.

of the evacuation route, con-tinue with this instruction e) Recommend evacuation of all non-essential personnel f) Report recommendation to the Emergency Manager 28.

ASSESS EXPOSURE TO EMERGENCY RADIATION WORKERS:

a) Prior to entry into a High Radiation areas, access possible exposure levels b) E Whole Body exposure b) g entry into high exceeds 10CFR20 quarterly radiation area will NOT exceed exposure limits:

1) Initiate EPIP-4.04,

1) GO TO Step H.

Emergenev Exposure AND M

2) Return to Step H

\\

w

NO.97887210 NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PACE CONTROLLING PROCEDURE 29 of 31 STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED 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,.

rescus 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) E 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 1,ncreasing

-- a or decreasing trends of Emergency

_..r_____,

.,.,m,y, n

g.

'No.97847214 NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PAGE CONTROLLING PROCEDURE 30 of 31 STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED 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 fer deconta-mination effort, Health Physics support person-nel and radwaste pack-aging and disposal 32.

ADMINISTRATION:

a) Initiate replacement of procedure and/or emergency equipment if necessary

L b) Forward completed proc"e-dure (s), release calculations and survey results to the Emergency Manager e

~ ten.97867210

,r NUMBER PROCEDURE TITLE REVISION

/

U1 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR PAGE CONTROLLING PROCEDURE 31 of 31 STE ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 33.

TERMINATE EPIP-4.01:

a) COMPLETED BY:

DATE:

TIME:

EhT M

e

.=-,-,--,9

,-m--

y.

.,mr..--,w-

-y-.--,

y.; nw VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCEDUR' TITLE REVISION 02 EPIP-4.09 SOURCE TERM ASSESSMENT PAGE

(

(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 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:SEP 2 3 E!.3 FIV.

PAGE(S):

DATE*

REV.

PAGE(S):

DATE:

PIV.

PAGE(S):

DATE:

REV.

PAGE(S):

DATE:

APPROVAL, CCOMMENDED APPROVED CA TE SEP 2 3 383 0#

CHAIRMAN STA TION NUCLEAR SA FETY l} }

AND GPERA TING COMMITTEE e

,~

~ - - -

,,--,,,,,w,,,-,,---.-w, e

me. neeme NUMBER PROCEDURE TITLE REVISION 02 EPIP-*.09 SOURCE TEAMS ASSESSMENT PACE 2 of 10 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 1.

INITIATE PROCEDURE:

a)

BY:

DATE:

TIME:

2.

SOURCE TERM ASSESSMENT:

a) Source term based on mor.itor readings should be used:

1) Initial assessment AND

2) Establish trends b) E the source term is from monitor readings, sampling I

should be done to more accurately determine the source term l

c) Source tem will have units of C1/sec d) Source tem 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, CO TO Step 2.d.2.

S OR l

t l

2) Sample of Station Inv,entory

2) E sample of station A

GO TO Step 6 inventory NOT avail-able, GO TO Step 2.d.3.

pm-ew------,--_.-g-

-,n--

Ns. 9700M 10 NUMBER PROCEDURE TITLE REVISION 02 TPIP-4.09 SOURCE TEAMS ASSESSMENT PA GE 3 of 10 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 2.

(CONTINUED)

3) Station monitors

3) IF source term NOT thru GO TO Step 3, the station monitors GO TO Step 2.e.

e) IJ[ event may produce releases e) IJ[ 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) J][ 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[

l 3.

SOURCE TERM - STATION MONITORS:

l l

a) Source term may be obtained a) ))[ release pathway is thru from the following monitors:

the main steam system,

1) Vent Vent VG-109 SE

2) Vent Vent (VG-131-2) i l

3) Process Vent GW-102

(

4) Process Vent (GW-130-2)

.QR f

5) Condensor Air Ejector l

SV-111, SV-211 l

b) )); more than one effluen.t b) Continue with this instruc-1--

~~

I pathways involved:

tion

1) Add results of all monitors for total release t

1

N:3. 97887210 NUMBER PROCEDURE TITLE REVISION U2 EPIP-4.09 SCURCE TEAMe ASSESSMENT P40E 4 of 10 STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED 3.

(CONTINUED) c)'

IF 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 (GW-130-2), obtain Ejector, obtain epm, above uCi/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 epm interest and uCi/cc on on Attachment 1

2) GO TO Step 3.d.

d) I]; Air Ejector NOT diverted d) ))[ Air Ejector Il diverted to containment, continue to containment, no release with this instruction from this pathway will occur:

1) GO TO Step 3.e.

e) Obtain the flow rate (CFM) effluent pathway from Radio-logical Assessment Director l

1) Log on Attachment I l

f) Obtain conversion factor for monitor of interest:

l

1) VG-109: 1.19 E-11 I

2) VG-131-2 : 4.72E-4 SE

3) GW-102: 1.19 E-10 u

~

4) GW-130-2 : 472E-4 91

5) SV-111,211:5.71 E-9

~

no. oresnio NUMBER PROSEDURE TITLE REVISION 02 EPIP-4.09 SOURCE TEAMS ASSESSMENT g j, 5 of 10 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 3.

(CONTINUED) g) Perform following calcu-lations to obtain Ci/sec (IE-133 Equivalent):

C1/sec cpm (or uC1/ce) x CONVERSION FACTOR x CFM

=

1) Log results on Attcchment I

h) CO TO Step 9, 4

SOURCE TERM - SAMPLE EFFLUENTS:

a) Request Radiation Protection a) IJ[ sampling not required, Supervisor to initiate EPIP-GO TO Step 5.

4.24, Gaseous Effluent Sampling During an Emergency, to obtain a sample:

I L) Vent Vent

(

-OR l

2) Process Vent E

3) Condensor Air Ejector b) ]g[ more than one effluent b) CO TO Step 4.c.

pathway involved:

l l

1) Add results of all monitors l

for total release 2- -

c) Have sample analyzed as per normal count room procedures OR initiate EPIP-4.26, M Level Activity Sample Analysis l

4 -

1

~

\\

l

ND.97847210 NUMBER PROCEDURE TITLE REVISION 02 EPIP-4.09 SOURCE TEAMS ASSESSMENT PAGE 6 of 10 STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED 4.

(CONTINUED)

1) Log results of the analysis on Attachment 2 d) Perform calculations on to obtain:

1) Equivalent activity 1-131 AND Xe-133 (uCi/ml) e) Obtain flow rate:

j f) Calculate source term (Ci/sec):

Ci/sec EQUIVALENT ACTIVITY x CFM x 4.72E-4

=

5.

CORRECT SOURCE TERM FOR MAXIMUM RELEASE:

(

a) ))[ sample from Step 4, was a) ))[ sample was NOT a grab l

a grab sample and is NOT sample Ojt I][ sample obtained at maximum release, obtained at maximum release correct for maximum release GO TO Step i rate:

1) Obtain the maximum monitor

1) ))[ monitor is off scale, reading GO TO Step 9_.

l

') Obtain monitor reading at l

time of sample

3) Obtain source term from Step 4,

4) Perform following calcula-a tion to obtain maximum

~-

release rate:

Monitor Max 1=um (cpm or uCi/cc) x Source Mx Ci/sec

=

Monitor Sample (cpm or uCi/cc)

Term b) GO TO Step 9 4 ;'

l

N3. 97887210 NUMBER PROCEDURE TITLE REVISION 02 EPIP-4.09 SOURCE TEAMS ASSESSMENT P40E 7 of 10

& STEP ACTION / EXPECTED RESPONSE RESPONSE NOT QBTAINED 6.

SOURCE TERM - STATION INVENTORY:

l a) IF release originated from gas storage tank (ie. Waste Gas Decay Tank, Volume Control Tank, etc.):

1) Request sampling the activity

' remaining in tank

2) Have sample analyzed by normal count room procedures Cyl initiate EPIP-4.26, High Level Activity Sample Analysis

3) Log activity en Attachment 2 b) Perform calculations on to obtain:

l

1) Equivalent activity I-131 AND Xe-133 c) Determine volume of release from the following equation:

PVT, 11~

VOLUME =

12

1) Obtain pressure prior to release from operations (P )

1

2) Obtain pressure after release from operations (P )

3

3) Obtain the design volume of the tank minus the water 4+ -

volume in the tank from

~ * - -

operations

4) Obtain temperature prior to release from operations (T = 'F + 459) 1 s;'

,-w g.

.-e

---;,m-7

,.-a.

N3.97ss721o NUMBER PROCE00RE TITLE REVISION 02 EPIP-4.09 SOURCE TEAMS ASSESSFJ.NT PAGE 8 of 10 STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED 6.

(CONTINUED)

5) Obtain temperature after release from operations (T = 'F + 459) 2 d) Perform the fcllowing to cetermine source ters:

2.83E-2 x VOLUME (ft3) x EQUIVALENT ACTIVITY

= C1/sec TIME OF RELEASE (seconds) 7.

SOURCE TERM - CONTAINMENT HIGH RANGE MONITOR:

a) IF event - LOCA:

a) IF source' tern NOT from LOCA, GO TO Step 9_.

1) Obtain the dose rate (mR/hr) of Containment High Range henitor of affected unit, l

from Radiological Assessment Director b) Obtain length of time (HOURS) l after shutdown c) Determine approximate extent of fuel damage using Attachment 3 l

l

1) Extrapolate, if necessary, to determine fuel damage d) Use data from Step 7.b, Step 7.c and Attachment 4:

a

1) Determine equivalent, curies I-131 and Xe-133 l

N3.97187210 NUMBER PROCEDURE TITLE REVISION 02 EPIP-4.09 SOURCE TEAMS ASSESSMENT PAGE 9 of 10 STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED 7.

(CONTINUED) e) IF containment effluent e) IF containment effluent flow rate unkown, determine

' flow rate known, determine potential release rate:

potential release rate:

Equivalent Curies x Equivalent Curies x 3.39 E-8 = Ci/sec 9.29 E-9 = C1/sec

/

f) GO TO Step 9 8.

SOURCE TERM - CONTAINMENT SAMPLE:

a) H event - LOCA:

a) IF event NOT LOCA, GO TO Step 9_.

1) Request Radiation Pro-tection Supervisor

, initiate EPIP-4.22, Post Accident Sampling of Con-tainment Air b) Convert results of analysis to equivalent activity (uCi/mL) of I-13: and XE-133, using 7

I c) Determine potential release Iate:

i C1/sec EQUIVALENT ACTIVI'"Y x 1.73 E-3

=

9.

RETURN 10 CONTROLLING G;CE RE:

a) Upon completio. g t,h.

procedure, return to L J-4.03, Dose Assessment Controlling

~

Procedure r

g e

l

N3.97887210 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 Na<

", L I

No,97887220 NUMBER A TTACHMENT TITLE REVISION EPIP-4.09 02 A TTACHMENT

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NO.97802220 NUMBER A TTACHMENT TITLE REVISION EPIP-4.09 02 EQUIVALENT CURIES I-131 FOR LOCA ACCIDENT PAGE A TTAC# MENT 4

3 of 3 NOTE: Wittiin the first 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months following LOCA incident, IODINE decay is insignificant.

EQUIVALENT CURIES EVENT 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)

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gigsemo VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION EMERGENCY PLAN lMPLEMENTING PROCEDURE PROCECURE TITLE REVISION NUMBER 02 EPIP-4.12 0FFSITE ENVIRONMENTAL MONITORING PAGE INSTRUCTIONS (With 2 AttacFaents) 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) Detemine radiological composition of release 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.

9 2.

Any other time which the Radiological Assessment Director deems it necessary.

l 3.

Activation by another EPIP.

i l

l i

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 2 31S83

.-b..

REV.

PAGE(S):

DATE-REV.

PAGE(S):

DATE:

REV.

PAGE(S):

DATE:

REV.

PAGE(S):

DATE:

APPROVAL RECOMMENCE 0 APPROVED DA TE M--

SEP 2 3 ISS3 OC R IEW CHAIRMAN STA TION NUCLEAR SA FETY

}

AND OPERATING COMMITTEE o *

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N).97847210 NUMBER PROCEDURE TITLE REVISION 02 EPIP-4.12 0FFSITE ENVIRONMENTAL

1. 66 MONITORING INSTRUCTION 2 of 8 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 1.

INITIATE PROCEDL"RE:

a)

BY:

DATE:

TIME:

2.

ACTIVATION UPON SITE OR GENERAL EMERGENCY:

a) The procedure applicable a) E EOF is activated and moni-upon' radioactive release and toring teams in the field:

declaration of SITE or GENERAL emergency OR 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

- A b) Obtain from the Radiological Assessment Director the current meteorological conditions:

N3. H s 4M10 NUMBER PROCEDURE T1TLE 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 and the other team in preselected monitoring location in downwind sector 5.

ESTABLISH RADIO CONTACT:

a) Initiate EPIP-4.19, Use of a) I]; radio communications Radios for Health Physics NOT able to be established:

Monitoring:

+-

1.) Request assistance from

1) Establish radio communi-Radiological Assessment cation with team using Director radiophone s.'

e

Ns. 97887210 NUMBER PROCEDURE TITLE REVISION 02 EPIP-4.12 0FFSITE ENVIRONMENTAL PAGE MONITORING INSTRUCTION 4 of 8

(

STEP 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 I

c) Instruct teams to find plume centerline AND Report exact location once centering located e--., -, -

~

3

N'9. 97887210 NUMBER PROCEDURE TITLE REVISION 02 0FFSITE ENVIRONMENTAL EPIP-4.12

^

MONITORING INSTRUCTION PAGE 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.

CONFIRMATION:

a) Direct first monitoring team to the sector, near site, which is affected by plume b) Obtain the following data and/or samples, if appro-priate

1) Exact location

2) Maximum dose rate (mR/hr) i

3) Air sample - particulate.

l iodine and gas t

4) Soil sample c) Have initial confirmatory samples returned to Security Building

1) Air sample should be immediately analyzed to l

determine Iodine / Noble a

Gas ratio l

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ND.97887210 NUMBER PROCEDURE TITI.E REVISION 02 EPIP-4.12 0FFSITE ENVIRONMENTAL

^ 0#

MONITORING INSTRUCTION 6 of 8 STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED 7.

(CONTINUED) d) g g 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 dose rate at centerline of the plume AND Report exact location b) E unexpected reading occurs:

1) Have team travel downwind a distance until plume is located j

i f

9.

FIXED ENVIRONMENTAL SAMPLERS l

AND TLD'S:

t a) Fixed air samplers and TLD's provide good information on the TOTAL release.

Collection of these samples may provide best information l

after termination of release a

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N3.97487210 NUMBER PROCEDURE TITLE REVISION 02 EPIP-4.12 0FFSITE ENV!RONMENTAL

1. 6#

MONITORING INSTRUCTION 7 of 8 STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED 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:

j

1) EOF MANNED, CO TO Step 2 OR l

2) Release TERMINATED, GO TO Step M OR

3) IF, monitoring data becomes F

available, GO TO Step g.

12.

ASSESS DATA:

a)

_IF, monitoring data becomes available-f

1) Initiate EPIP-4.13, Offsite l

Release Assessment with Environmental Data l

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Ms.$7887210 NUMBER PROCEDURE TITLE REVISION 02 EPIP-4.12 0FFSITE ENVIRONMENTAL

1. 0f MONITORING INSTRUCTION 8 of 8 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 13.

TERMINATE EPIP-4.12:

a) COMPLETED BY:

DATE:

TIME:

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No. 97887220 NUMBER A TTACHMENT TITLE REVISION EPIP-4.12 02 PRESELECTED MONITORING LOCATIONS A TTAC# MENT PAGE 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 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.

l 6.

L-2.3 Route 650 South, right on Route 617, l

right on Route 10, right on Route 634 Follow signs to Chippokes State Park; l

enter park and follow signs to Historic section. Monitoring point located at intersection of road and College Run l

Creek.

7.

E-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, left on Route 2001 into Rushmere S,hores.

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.97887220 NUMBER A TTACHMENT TITLE REVISION EPIP-4.12 02 PRESELECTED MONITORING LOCATIONS PAGE A TTACNMEgr 2

2 of 3 LOCATION SECTOR DISTANCE (mi)

DESCRIPTION 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.

I 11.

M-5 Route 650 South, right on Route 617, right on Route 10 for approximately 5 rdles, 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 I

to Colonial Parkway, left on Colonial Parkway.

Monitoring location ik mile on Colonial Parkway.

l 15.

R-5 James River Ferry to Jamestown s:.de,

l Route 31 East, right on Route 682 " Neck i

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 i

point 6.5 miles, k mile past Halfway Creek.

i

~

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 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 Blvd., right on Ker: 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.

Penitoring location 0.6 miles South from intersection of Harrison Road and Back River Road.

N-

P l

sc 97887230

* ~

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PRCCEDURE TITLE REVISION 01 EPIP-4.13 0FFSITE RELEASE ASSESSMENT PA GE WITH ENVIRONMENTAL DATA (With 5 Attachments) 1 of 9 PURPOSE Ccnfirm 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; 9.R_

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 2 31933 REV.

PAGE(S):

DATE:

~ -

.7--

REV.

PAGE(S):

DATE:

REV.

PAGE(S):

DATE:

REV.

PAGE(S):

DATE:

PIV.

PAGE(S):

DATE:

APPROVAL RECOMMENCEJ APPROVE 0 g;75 GC REVIEW 0 ~00 t

CHAIRMAfiSTA TION NUCLEAR SA FETY AND GPERATING COMMITTEE

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Ns.97887210 NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.13 0FFSITE RELFASE ASSESSMENT

1. 68 WITH ENVIRONMENTAL DATA 2 of 9

(

STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED 1.

INITIATE PROCEDURE:

a) Initiated By:

i Date:

Time:

2.

USE OF ENVIRONMENTAL DATA:

a) E environmental data used a) E environmental data to to confirm dose projections:

be used to determine Ci/sec release rate:

l j

1) GO TO Step 3

1) GO TO Step 2.b l

b) IF onsite release data b) IF onsite release data l

from monitors and/or" from monitors and/or sample analysis NOT sample analysis IS available:

available:

1) Use Environmental data

1) De NOT estimate Source to determine Source Term Ter= from environmental (C1/sec) data AND AND

2) GO TO Step 8

2) GO TO Step M.

I 3.

CONFIRM DOSE PROJECTIONS:

a) Use offsite dose rate measurement to confirm projected dose rate OR

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Na,97847210 NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.13 OFFSI*E RELEASE ASSESSMENT gj g~,

WITH ENVIRONMENTAL DATA 3 of 9 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 3.

(CONTINUED)

Establish real time dose rate offsite b) Insure measurements g samples are taken at centerline of plume c) Dose rate may be obtained from:

1) Direct Mea _surements 0,,R

2) Sample Analysis Data 4

DETERMINE WHOLE BODY DOSE FROM DIRECT RADIATION READINGS:

a) Obtain from monitoring a) E dose rates NOT from team genterline dose rate centerline:

l

1) GO TO Step 6, b) Log date, time, location and dose rate on 5.

DETERMINE THYROID OFFSITE DOSE RATE FROM SAMPLE ANALYSIS:

a) Determine centerline a) E data from air sample is thyroid dose rate from NOT yet available. GO TO air sample analysis Step M OR E sample NOT from centerline, continue with this instruction l

l

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NB.37887210 NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.13 0FFSITE RELEASE ASSESSMENT AAGE WITH ENVIRONMENTAL DATA 4 of 9 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 5.

(CONTINUED) 1 b) If sample analysis given in b) ))[ sample data is given in counts per minute:

uCi/ml:

1) Obtain background count

1) GO TO Step 5.c.

rate (cpm) and volume (f t3) from monitoring team (s) i

2) Determine the net counts 5

per minute:

NET (cpm)

SAMPLE (cpm) - BACKGROUND (cpm)

=

3) Determine from Attachment 5, the conversion factor vs.

volume

4) Determine activity:

NET (cpm) x Conversion Factor = Activity (pC1/ml) c) Determine Thyroid dose rate:

MR/HR ACTIVITY (uci/ml) x 1.85 E+9

=

d) II[ sample taken at d) )); sample taken off-centerline:

centerline, CO TO Step 6,

1) Log date, time, location and dose rate on Attachment 1 6.

OFF-CENTERLINE DOSE RATES:

a) ))[ dose rates from Step 4 and a) IF dose rates from Step 4 line c.enterline, GO TO Step 7.

Step 5,were taken off-center-and Step j[ are taken from

1) Initiate EPIP-4.10, Determination of X/Q

-~

Ns.97887210 NUMBER PROCEDURE TITLE REVISl0N 01 EPIP-4.13 0FFSITE RELEASE ASSESSMENT WITH EhTIRONMENTAL DATA 5 of 9 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 6.

(CONTINUED) l

2) Determine centerline X/Q l

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:

DOSE RATE (MR/HR)

X/Q (CENTERLINE) x 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 7.

TRANSMIT DATA:

a) Upon completion of Attachment 1,:

l

1) Relay the Attachment to the l

Dose Assessment Team Leader.

1

}

AND

\\

2) CO TO Step 12_

l I

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ND.97847210 NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.13 0FFSITE RELEASE ASSESSMENT

AEI WITH ENVIRONMENTAL DATA 6 of 9 STEP ACTIONMXPECTED RESPONSE RESPONSE NOT OBTAINED 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 the plume:

of the plume

1) GO TO Step 6 to estimate centerline data AND

2) Return to Step 8.c.

c) Source Ter= may be estimated by:

1) Direct Measurements, GO TO Step 9, pR,

2) Sample Analysis Data, GO TO Step 10, 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 5

7-.-

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Ns.97387210 NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.13 0FFSITE RELEASE ASSESSMENT PACE WITE ENVIRONMENTAL DATA 7 of 9 STEP ACTION / EXPECTED RESPONSE RESPONSE NOTQBTAINE9 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 c) Determine source term:

MR/HR x 2.38 E-5 x WIND SPEED x CONVERSION FACTOR = Ci/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 from centerline of the plume centerline of plume:

1 l

1) GO TO Step 6 to esti= ate centerline data (use (uCi/ml) instead of data rate) 1 1

AND l

2) Return to Step 10.b.

b) Obtain uCi/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

2) Determine activity

2) Obtain the current wind (uci/ml) speed and stability class from Dose Assessment Team

3) Return to Step 10.b.

Leader

N3.97887210 NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.13 0FFSITE RELEASE ASSESSMENT PAGE WITH ENVIRONMENTAL DATA 8 of 9 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT CBTAINED 10.

(CONTIN'JED)

IF, sample from preselected c) E sample not from c)

F points, Obtain the conversion preselected point, obtain factor from Attachment 3, conversion factor from.

d) Determine the source term:

C1/sec ACTIVITY x WIND SPEED x CONVERSION FACTOR

=

a) Upon completion of Attachment 2

1) Inform 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 tea =s are to remain in to be relocated:

the same location:

1) GO TO Step E to terminate

1) GO TO Step 12.b.

this procedure AND I

2) Initiate EPIP-4.12, Of f site Monitoring Instruction b) IF EOF NOT activated b) IF emergency has terminated w

OR

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OR

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Ns.97887210 NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.13 0FFSITE RELEASE ASSESSMENT

" ^ '

WITH ENVIRONMENTAL DATA 9 of 9 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 12.

(CONTINUED)

IF, release NOT terminated:

E EOF activated:

1) Return to Step 3,and

1) GO TO Step 13.

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 l

l I

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No.97887220 NUMBER A TTACHMENT TITLE REVISION EPIP-4.13 00 FACTORS FOR PRESELECTED A TTACNMENT PA GE MONITORING LOCATIONS 3

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 1.35 E3 3

H-1.9 1.50E6 5.50E5 7.10E4 2.00E4 1.00E4 4.10E3 1.60E3 4

J-2.0 1.51E6 5.55E5 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 2.56 E3 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 3.45 E5 8.33E4 3.45E4 1.43E4 5.26E3 11 M-5 3.45E6 2.63E6 3.45E5 8.33E4 3.45E4 1.43E4 5.26 E3 12 N-4 2.86E6 2.13E6 2.38E5 5.88E4 2.50E4 1.07E4 4.00E3 l

13 P-5 3.45E6 2.63E6 3.45E5 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 l

l 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 l

l 18 C-5 3.45E6 2.63E6 3.45ES 8.33E4 3.45E4 1.43E4 5.26E3 i

[

19 D-5 3.45E6 2.63E6 3.45E5 8.33E4 3.45E4 1.43E4 5.26E3 l

20 E-5 3.45E6 2.63E6 3.45ES 8.33E4 3.45E4 1.43E4 5.26E3 21 F-4.S 3.33E6 2.50E6 3.13E5 7.70E4 3.13E4 1.35E4 5.00E3 l

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gmenn VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCEDURE TITLE REVISION 02 EPIP-4.15 ONSITE MONITORING PA DE (With 3 Attachments) 1 of 9 PURPOSE Confirm initial offsite releases and provide surveys for personnel pro-tection program onsite.

USER Onsite Monitoring Team Member ENTRY CONDITIONS Any one of the following conditions:

1.

ALERT, SITE or GENERAL emergency.

2.

Activation by another EPIP.

i REVISION RECORD REV. 00 PAGE(S): Zntire Procedure DATE:07-29-12 REV. 01 PAGE(S):

1, 3, 4, 5, 7, 8 Att. 2 p.1, Att. 3 p.1 D ATE:02-24-83 REV. 02 PAGE(S): Page 1 of 9 and Attachment 3 page 1 of 1 DATE:STP : 3 :2?3 REV.

PAGE(S):

DATE:

b PIV.

PAGE(S):

s DATE:

REV.

PAGE(S):

DATE:

REY.

PAGE(S):

DATE:

APPROVAL RECOSIMENDED APPROVED DA TE M

SEP 2 31333 00REV %

7 CHAIR & FAN STA TION NUCLEAR SAFET

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AND OPERA TING COMMITTEE n -:

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gsgeomo VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCEDURE TITLE REVISION 01 EPIP-4.16 0FFSITE r10NITORING PACE (With 4 Attachments) 1 of 12 PURPOSE 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.

REVISION RECORD 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 ~333 REV.

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APPROVAL RECOMMENCEO APPROVE 0 DA TE stp 2 31983

#5?

CHAIRMANSTA TION NUCLEAR SAFETY

_bg AND GPERATING COMMITTEE

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4 N2.97tS7210 NUMBER PROCEDURE TITLE REVISION 02 EPIP-4.16 0FFSITE MONITORING PAGE 2 of 12 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 1.

INITIATE PROCEDURE:

a)

BY:

DATE:

TIME:

2.

TEAM ASSIGNMENT:

a) Offsite monitoring team shall consist of two individuals:

- 1) Only one need be a H.P.

technician 3.

REQUEST BRIEFING:

a) Request briefing with the Radiation Protection Super-visor as to the following:

1) Requ, ired monitoring

1) IF no location OR survey l

locations requirements 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-acory gear required

(

b) Obtain infor=ation on who to report survey data to:

l

1) TSC i

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2) EOF l-l

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e No. 97887210 NUMBER PROCEDURE 77TLE REVIS10N 02 EPIP-4.16 0FFSITE MONITORING PAGE 3 of 12 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 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 H.P. Office:

able at EP instrument repair shop.

1) Battery powered air sampler

2) RM-14 with H.P. 210 probe

3) Package of silver eolite cartridges and particulate filters l

6.

PERFORM INSTRUMENT CHECK:

a) Perform operability check:

1) Battery check l

2) Current calibration l

sticker

~.

7.

PROCEED TO MONITORING LOCATION:

i

]:; no gear is specified, a) Obtain and don protective a) j l

clothing, dosimetry, and centinue with this instruc-respiratory gear as speci-tion.

t I

fled in Step j[

,c

Na.97887210 NUMBER PROCE00RE 17TLE REVISION 02 EPIP-4.16 0FFSITE MONITORING PA Gc, 4 of 12 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 7.

(CONTINUED) b) Use Attachment 1 and 2 to determine:

1) Initial location pR

2) Location specified by personnel in TSC (EOF) c) Proceed to monitoring c) ))[ no monitoring location l

locat1on specified in specified:

Step 3,

1) Report to Security Building AND

2) Await further instruct-ions.

8.

ESTABLISH RlDIO CONTACT:

a) Initial radio com=unication will be with emergency res-pense personnel in the TSC l

l b) Il[ EOF is activated, radio com=unication will be with EOF c) Establish radio com=unica-tion with the TSC or EOF by initiatien of EPIP-4.19.

Use of Radios for Health Physics Monitoring

1) To transmit:

" Mobile (Number of Vehi-cle) to TSC (HP-2) or EOF (HP-3).

Our location is

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ms.ofas72:o NUMBER PROCEDURE TlTLE REVISION 02 EPIP-4.16 0FFSITE MONITORING PAGE 5 of 12 STEP ACTIONiEXPECTED RESPONSE RESPONSE NOT QBTAINED 8.

(CONTINUED)

2) Request telephone number of emergency center and use in case of radio fail-ure NOTE: Survey reading should increase as you approach center of the plume, then decrease once past centerline.

9.

PLUME TRACKING:

a)

IF, 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) IF NO readings are cbserved, 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.

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w. -

d) Traverse plume several times until maximum point (centerline of plume) is located I

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No. s7 ss72to NUMar9 PROCEDURE TITLE REVISION 02 EPIP-4.16 0FFSITE MONITORING PAGE 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 a

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) ))[ further monitoring outside the plume:

required, stay within the plume until com-

1) Await further instructions plete.

10.

NOBLE GAS dAMPLING:

a) ))[ noble gas sample a) j][ 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 anle, request gas chambers be prepared and brought to

1) Remove top and wave the survey team.

chamber in air

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N5.97847210 NUMBER PROCEDURE TITLE REVISION 02 EPIP-4.16 0FFSITE MONITORING PAGE 7 of 12

(

STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED 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) E particulate and/or iodine a) E sample NOT required, sample required:

GO TO Step E.

1) Obtain battery powe' red air sampler

2) Load samples with parti-culate filter and silver zeolite cartridge b) IF sample required duting b) Continue with Step 11.c.

high humidity:

1) Shelter sample from moisture

2) Report weather conditions to TSC or EOF NOTE: Sample volume should be lessened when sampling high activity airborne concentrations a

c) Obtainanapproximatehfc 8

~

air sample

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No.s7estric NUMBER PRO:EDURE TITLE REVISION 02 EPIP-4.16 0FFSITE MONITORING PACE 8 of 12 STEP ACTION / EXPECTED RESPONSE RESPCNSE NOT OBTAINEC 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 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 :eolite cartridge to use this method for analysis.

12.

ACTIVITY DETERMINATION:

a) Il[ air sample analysis required:

1) Preceed to a low back-ground area

~7

Nr. 97s S7210 NUMBER PROCEDURE TITLE REVIS10N 02 EPIP-4.16 0FFSITE MONITORING PAGE 9 of 12 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 12.

(CONTINUED) b) Turn on RM-14 (frisker)

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) E gross count rate on d) IF gross count rate off scale, continue scale:

1) Return to Step H AND

2) Obtair. a smaller sample volume e) Determine net count rate:

NET (cpm)

BACKGROUND (cpm)

GROSS (cpm)

=

f) Determine from Attachment 4 the conversion factor for specific sample volume.

g) Determine activity:

ACTIVITY (uCi/ml)

NET (cpm) x Conversion Factor

=

h) Log on Attachment 3:

1) Date

2) Time 2 2 i n

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N 9. 97847210 NUMBER PRCCEDURE TITLE REVISION 02 EPIP-4.16 0FFSITE MONITORING PAGE 10 of 12 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 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) IF soil sample IS requested:

a) IF soil sample NOT requested, GO TO Step

1) Obtain a sample by marking J4.

off an approximate one square foot area

2) Remove top 1/4 to 1/2 inch layer of soil

3) Place soil in a clean poly bag b) Label sample with:

1) Date

2) Time

3) Location

-..a

~

l c) Save sample for lab j

analysis l

l I

2 I

s2.stes7sto NUMBER PROCEDURE TITLE REVISION 02 EPIP-4.16 0FFSITE MONITORING PAGE 11 of 12 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 14.

TRANSMIT DATA:

a) Transmit results of all surveys g 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 S

As time and location permit 16.

CONTINUED SAMPLING:

a) IF TSC or EOF does NOT a) IF TSC or EOF requests request return to station:

return to station:

1) Return to Step 9

1) Go To Step E.

2) Repeat sampling and surveys as requested 17.

ADMINISTRATIVE:

u 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 2

l j

I N3.97887210 NUMBER PROCEDURE TITLE REVISION 02 EPIP-4.16 0FFSITE MONITORING PAGE 12 of 12 STEP l ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 18.

TERMINATE EPIP-4.16:

a) COMPLETED BY:

DATE:

TIME:

END N**

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NE.91681220 NUMBER A TTACHMENT TITLE REVISION EPIP-4.16 02 PRESELECTED MONITORING LOCATIONS A TTAC# MENT PAGE 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 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, l

l left on Route 628, left on Route 676.

At bend in the road, bear right on Route 686, left on Route 2001 into Rushmere Shor.,es.

~

- + -

8.

J-5 Route 650 South, left on Route 628.

Monitoring point 1.2 miles from l

intersection of Routes 650 and 628.

(Remote Asse=bly Area).

l

[

5 3 l

NB.97887220 NUMBER A TTACNMENT TITLE REVISION EPIP-4.16 02 A TTACNMENT PRESELECTED MONITORING LOCATIONS FAGE 2

2 of 3 LOCATION SECTOR DISTANCE (mi)

DESCRIPTION 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 11, monitoring point 2 miles North on Route 662.

l I

13.

P-5 Scotland Wharf.

Surry side on James l

River Ferry on Route 31 North.

l 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.

l 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 =ile past Halfway Creek.

No.97047223 NUMBER A TTACHMENT TITLE REVISION EPIP-4.16 02 PRESELECTED MONITORING LOCATIONS A TTAC# MENT gjgg 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 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.

M*

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gs7se7230 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCEDURE TITLE REVIS10!:

02 EPIP-4.18 MONITORING OF EOF PACE (With 4 Attachments) 1 of 8 PURPOSE Provide Health Physics coverage for personnel manning the EOF.

USER Member of Inplant Monitoring Team.

ENTRY CONulTIONS Initiation of EPIP-4.02, Radiation 'frotection Suoervisor Controlling Procedure; REVISION RECORD REV. 00 PAGE(S): Entire Procedure DATE:07-29-82 PIV. 01 PAGE(S):

1,4,5,6,7,8, Act. 3 page 1, Act. 4 Page 1 DATE:02-24-83 REV. 02 PAGE(S): Page 1 of 8 and Attachment 3 DATE:SEP 2 3 1333 REV.

PAGE(S):

DATE:

C-REV.

PAGE(S):

DATE:

REV.

PAGE(S):

DATE:

REV.

PAGE(S):

DATE:

APPROVAL RECOMMENCE 0 APPROVED DA TE M

SEP 2 31983 0E AE" CHAIRMAN STA TION NUCLEA R SA FETY

)l, AND GPERATING COMMITTEE

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No.97887220 I

NUMBER A TTACHMENT TITLE REVISION EPIP-4.18 02 D-14 CONVERSION ? ACTOR A TTACHMENT p,gg 3

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gi,mnz VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCEDURE TITLE REVISION f

02 EPIP-4.23 POST ACCIDENT SAMPLING OF REACTOR COOLANT PA CE (With 1 Attachment) 1 of 14 PURPOSE l.

To collect a post accident sample of reactor coolant from the hot leg of Unit 1 OR Unit 2 Reactor Coolant Systems.

USERChemistry Team Leader AND Chemistry Team Member.

I ENTRY CONDITIONS 1.

Entry directed by Emergency Technical Director pR 2.

Entry directed by Station Emergency Manager REVISION RECORD REV. 00 PAGE(S): Entire Procedure DATE:07-29-82 REV. 01 PAGE(S):

1, 13, 14 DATE:02-24-83 REV. 02 PAGE(S): Pages 1 of 14 through 14 of 14 DATE:SEP 2 31333 REV.

PAGE(S):

DAT-.

REV.

PAGE(S):

DATE:

REV.

PAGE(S):

DATE:

REV.

PAGE(S)e DATE:

AP?ROVAL RECOMMENCEO APPROVED DA TE O# #N' CHAIRMAN STA TION NUCLEAR SAFETY N%%f AND GPERA TING COMMITTEE w-2 ae,s-r---

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ees. nsenso NUMBER PROCEDURE TITLE REVISION 02 EPIP-4.23 POST ACCIDENT SAMPLING OF REACTOR COOLANT PAGE (With ! Attachment) 2 of 14 STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED 1.

INITIATE PROCEDURE:

a)

By:

Date:

Time:

NOTE: Only one reactor coolant sample may be obtained from this system.

2.

VERIFY STATION SYETEMS:

a) Systems Operable a) IF NOT operable, request operations assistance to

1) Station Service Electrical insure system operability System per OP-g j

2) Component Coolant System f

per OP-H i

l

3) Compressed Air Service System i

per OP-M

4) Ventilation System per OP-21

5) Radiation Monitoring System per OP-H 3.

DESIGNATE SAMPLING PARTY:

a) Chemistry team leaders AND b) Chemistry team members n2

=

y m,

Ns.97847210 NUMBER PROCEDURE TITLE REVISION 02 EPIP-4.23 POST ACCIDENT SAMPLING OF REACTOR COOLANT PAGE (With 1 Attachment) 3 of 14 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT 08TAINE0 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

'?

J

Ns. ste snio l

l NUMBER PROCEDURE TITLE REVISION 02 EPIP-4. 23 POST ACCIDENT SAHPLING OF REACTOR COOLANT pagg (k'ith 1 Attachment) 4 of 14 STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINEC 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 i 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.

'r 2 2

NL 97887210 NUMBER PROCEDURE TITLE REVISl0N 02 EPIP-4.23 POST ACCIDENT SAMPLING OF REACTOR COOLANT PA GE (With 1 Attachment) 5 of 14 O

STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED 12.

VERIFY SAMPLE COLLECTION CYLINDER CONNECTED:

a) Cylinder - IN SHIELDED 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 NOT, 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 j

Add 835 ml of DI l

water through funnel AhT C0 TO STEP M 15.

VERIFY NITROGEN BOTTLE

[

PRESSURE:

-~

~

l a) Open isolation valve l-55-241 on Nitrogen Bottle n -2

~

t

No. 97487230 NUMBER PROCEDURE TITLE REVISION 02 EPIP-4.23 POST ACCIDENT SAMPLING OF REACTOR COOLANT PAGE (With 1 Attachment) 6 of 14 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 15.

(CONTINUED) b) Verify Nitrogen Bottle b) IF NOT, leave area pressure GREATER THAN 200 PSIG AND initiate Nitrogen Bottle replacement AhT CO TO step 16 16.

VERIFY VALVE LINE UP:

a) Insure following valves - CLOSED l-SS-229 l-SS-230 1-SS-233 1-SS-236 1-SS-238 1-SS-239 l-SS-240 1-SS-241 1-SS-242 valve "K" valve "L" b) Insure following valve - OPEN 1-SS-231 17.

VENT AND DRAIN HOLDING TANK - TK1 a) Remove vent plug on TK1 m-

-+.

b) Insure following valves - CLOSED 1-SS-234 1-SS-235 n

.s =

res.e7estato NUMBER PROCEDURE TITI.E REVISION 02 EPIP-4.23 POST ACCIDENT SAMPLING OF REACTOR COOLANT PAGE (With 1 Attachment) 7 of 14

(

STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED 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:

l I

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 g NOTE:

Step 20 is for sampling Unit 1.

20.

SAMPLE UNIT 1:

l a) Insure control room m.

4-

~

' ~

valves - CLOSED l

TV-SS-106A TV-SS-106B l

n 's '

I l

l I.

no. s7senso NUMBER PROCEDURE T1TLE REVISION 02 EPIP-4.23 POST, ACCIDENT SAMPLING OF REACTOR COOLANT p,

(With 1 Attachment) 8 of 14 STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED 20.

(CONTINUED) b) Insure following valve CLOSED 1-SS-228 c) Insure UNIT 1, 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-106B CAUTION: Flow of high activity reactor coolant j

will commence when next steps are j

performed.

- - - - x

- - - - w f) Observe sample line pressure gage PI-SS-200 l

g) Carefully open following valve 1-SS-229 i

I AT 20 PSIG on PI-SS-200 l

insure following valve - CLOSED 1-SS-229 r -2 a

1

No. 9F847210

, NJMBER PROCEDURE TITI.E REVISION 02 EPIP-4.23 POST ACCIDE::T SAMPLING OF REACTOR COOLANT PACE (k'ith 1 Attachment) 9 of 14 STEP ACTION / EXPECTED RESPONSE l

RESPONSE NOTOBTAINED 20.

(CONTINUED) h) Insure following valve - CLOSED 1-SS-233 i) Insure following valves - OPEN 1-SS-236 valve "I" 1-SS-236 ialve "J" j) Observe sample pressure gage PI-SS-200 k) Cycle following valve 1-SS-229 AND AT 100 PSIG on PI-SS-200 insure following valve - CLOSED 1-SS-229 AND CO TO Step 22, NOTE:

The folicwing step is for sampling UNIT 2 l

21.

SAMPLE UNIT 2:

I a) Insure control room l

valves - CLOSED

":e.

TV-SS-206A I

TV-SS-206B y,

t i

y

Ns. 97887210 NUMBER PROCEDURE TITLE REVISION 02 r

EPIP-4.23 POST ACCIDENT SM? LING OF REACTOR COOLANT PAGE

(ith l Attachment) 10 of 14 STEP ACTION / EXPECTED RESPONSE RESPONSENOT OBTAINED 21.

(CONTINUED) b)'

Insure f:llowing 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 TV-SS-206A TV-SS-206B

- - - - x CAUTION: Flow of high activity reactor coolant will commence when next steps are performed.

* * * ****w

- - - - =********

f) Observe sample line pressure gage PI-SS-200 w

e I

/

e l

1 l

NL 97887210 NUMBER PROCEDURE TITLE REVISl0N 02 EPIP-4.23 POST ACCIDENT SAMPLING OF REAC OR C001 ANT 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 EsEe following valve - CLOSED 1-SS-230 h) Insure following valve - CLOSED 1-SS-233

1) Insure following valves - OPEN 1-SS-236 valve "I" i

1-SS-236 valve "J" l

j) Observe sample pressure gage PI-SS-200 k) Cycle following valve 1-SS-230 l

AND AT 100 PSIG on PI-SS-200 E sure foll: wing valve - CLOSED 1-55-230 l

22.

ISOLATE AND TRANSFER 2~

4 l

CALIBRATED SAMPLE:

~

a) Insure following valves - CLOSED 1-SS-236 valve "I" 1-SS-236 valve "J" l

l l

% 2 l

I

Ns.97887210 NUMBER PROCEDURE TITLE REVISION 02 EPIP-4.23 POST ACCIDENT SAMPLING OF REACTOR C00IANT 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 F1-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-SS-230 AND AT 100 PSIG on PI-SS-200

-insure following valve - CLOSED 1-SS-230 22.

ISOLATE AND TRANSFER

- - 4~

CALIBRATED SAMPLE:

a) Insure f ollowing valves - CLOSED 1-SS-236 valve "I" 1-SS-236 valve "J" y.: 1

r 9

N3.97887210 NUMBER PROCEDURE TITLE REVISION 02 EPIP-4.23 POST ACCIDENT 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" 1-SS-236 c) Verify valve 1-SS-238 - OPEN until pressure on sample bottle is appx. 50 PSIG AhT Wait appx. one minute to complete transfer.

d) Insure following valves - CLOSED 1

1-SS-238 valve "K" 1-SS-236

(

valve "L" 1-SS-236 f

23.

DISCONNECT. SAMPLE CYLIhTER:

a) Use adjustable wrench j

b) Disconnect quick disconnect i

l c) Lower lid onto sample " pig" l

24 SURVEY SAMPLE PIG:

-i-a) Survey sample " pig" to, determine rad levels and hot spot locations 3 2 l

L

No. 97457210 1/ UMBER PROCEDURE TITLE REVISION 02 EPIP.-4. 23 POST ACCIDENT SAMPLING OF REACTOR COOLANT PAGE (With 1 Attachment) 13 of 14 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 25.

TRANSPORT PIT:

a) Unlock wheel brakes b) Use preplanned exit route c) Avoid hot spots on pig d) Rol1 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.

- - - - x I

26.

LOWER PIG DOWN RAMP:

a) Use come-a-long to lower j

sample pig down ramp 27.

TRANSPORT PIG TO HOT LAB:

l a) Roll. pig to Chemistry Hot l

Lab i

l b) Place shielded sample pig l

l l

in corner by the A.A.

28.

RECORD SAMPLE DATE/ TIME a) Date b) Time l

1 l

l 1

n

-1 l

No. 97887210 NUMBER PROCEDURE TITLE MVISION 02 EPIP-4.23 POST ACCIDENT SAMPLING OF REACTOR COOLANT AGE (With 1 Attachment) 14 o' 14 STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED 29.

HAVE SAMPLE TRIP VALVES SHUT:

a) Notify Shift Supervisor that sampling completed b) E sampling Unic J_, have a) E sampling Unit 2, have Control Room shut TV-SS-106A Control Room shut AND TV-SS-106B TV-SS-206A AND TV-206B 30.

NOTIFICATIONS:

a) Notify following that sampling completed

1) Shift Supervisor

2) Station Emergency Manager 31.

SAMPLE ANALYSIS:

a) Request initiation of Rb'P to dilute sample b) Consider initiation of EPIP-4.26, High activity Samole Analysis, upon termination of procedure 32.

TERMINATE EPIP-4.23:

a) COMPLETED BY:

TDIE:

DATE:

b) Forward procedure to SNSOC for review i

END n2

_

ML20078F930

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ML20078F930

Text

,-

+-== =.===

5__;

1: a =.-;.? - - - a =.== =' ? = :==-- = --:

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