ML20079N812

Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures 1004.15 Re post-accident in-plant Sampling & 1004.31 Re Airborne Radioactivity Sampling & Analysis

ML20079N812
Person / Time
Site:	Crane
Issue date:	01/19/1984
From:	Giangi G METROPOLITAN EDISON CO.
To:
Shared Package
ML20079N806	List: ML20079N812
References
PROC-840119, NUDOCS 8401300353
Download: ML20079N812 (74)

Text

~_

A 1004.15 Revision 4 01/19/84 IMPORTANT TO SAFETY NON-ENVIRONMENTAL IMPACT RELATED THREE MILE ISLAND NUCLEAR STATION UNIT NO. 1 EMERGENCY PLAN IMPLEMENTING PROCEDURE 1004.15 POST ACCIDENT IN-PLANT SAMPLING Table of Effective Pages Page Revision Page Revision Page Revision Page Revision 1.0 4

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l /1hY tw l

V Signatufe Date

)

)

Signature Date Document ID: 0007W DO O

F PDR

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9

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g 1004.15 Revision 4 THREE MILE ISLAND NUCLEAR STATION UNIT NO. 1 EMERGENCY PLAN IMPLEMENTING PROCEDURE 1004.15 POST ACCIDENT IN-PLANT SAMPLING 1.0 PURPOSE This procedure specifies the method of obtaining and analyzing primary coolant samples under accident conditions.

2.0 DISCUSSION A requirement exists for timely analysis of primary coo n er emer-gency conditions without overexposure of personnel.

radiation levels associated with sampling and analysis may high, special precautions are requ The Chemistry C tor is responsible for implementing this p u e when request the Emergency Director /

9 Radiological nt Coordinator me ng the criteria set forth in Appendix r

elr discretto diological Controls Coordina-tor is res ible to ensure t.

ample is obtained without incur-ring a radiation exposure to ividual in exc f 3 REM to the whole body and 18 3/4 he extremities.

3.0 REFERENCES

V 3.1 Drawings

'O

3. C 302 671 3.2 Emergen Implementing Pr (EPIP) 1004.33

__4.0_ ATTACHMENTS 4.1 - Analysis Area Schematic 4.2 - Post Accident Sample Equipment Inventory 4.3 - Post Accident hmpling System Valve. Schematic 4.4 - Prerequisite Post Accident Sampling Valve Positions 5.0 E0UIPMENT 5.1 Radiation Protection Clothing and Equipment l

1.0

3 1004.15 Revision 4 5.2 Lead-glass shleid 5.3 Remote handling tools 5.4 Locking syringe with 8 1/2" needle 5.5 (2) Sample shields (lead pigs) 5.6 Wheeled cart 5.7 Ensure that the chemistry lab exhaust hoods, hand n is and other equipment are set up as per EPIP 1004.

5.8 Containment Barrier 6.0 PROCEDURE kt 5

NOTE:

N1 teps upon com 6.1 Pre 1.

ps 5.1 to 5.6 i P

4.33 must be completed prior to sampling.

2.

The Nuclear r

Closed Cooling tem is in operation per Operati r

re 1104-11.

V 3.

Veri w

control room th th ntrol building ventilla-t

' m is in emergen re. culation mode with the

_.and_AH-E.-3.L fans _ ope _ ting _(per OP 1004-19) and will not be interrupted.

4.

The Recialmed Water Portion of the Nuclear Chemical Addition l

l System is operational per Operating Procedure 1104 47.

i 5.

Verify with the control room that the Aux. 81dg. Sump has adequate capacity (at least 100 gallons) to receive water from the sample sink.

1 i

2.0

o 1004.15 Revision 4 6.

The original sample container shall be pre-labelled to specify date and time of sample, sample location, sample type and the individual obtaining the sample. Subsequent dilution sample containers shall be pre-labelled to include dilution factor and original sample data.

7.

Chemistry Technicians shall be briefed and e i as pre-r.

The Radio-scribed by the Radiological Controls C logical Centrols Coordinator shall e hP is prepared and adhe Minimum require ar.

2 alls D

t on gloves N

2 pr. rubber es v

surgeon's g cloth 3p shoe covers u e shoe covers reon's cap oods pressure demand SCBA TLD low range self-reading dosimeter Xetec high range dosimeter dose rate instrument finger rings and wrist TLDs lapel breathing zone air sampler Rad Con escort 3.0

h 1004.15 Revision 4 8.

Ensure that the following valves on the nuclear sampling control panel are closed (verify with control room or physic.

ally check):

CA.V13 l

CA.V1 CA.V2 CA.V3 9.

Verify valve positions par Attachment he isite Post

, v Accident Samoling Valve Positions.

NOTE 1:

Supervisor m no ified prior to The RM-R6A chart should be ed accordingly.

l l

l 10.

fy that the Post Ac i CS Sample Argon bottle pressure is reater than 2 i

and the associa regulator is set at 6 psig.

11. Verify that P'

Accident RCS bottle pressure is grea an 500 psig, and o ated regulator is set at NOTE.

. reakers _No. _1_th rough

o. 8_at_Di stribution.

MG-1 should be checked closed.

During a loss of offsite power, the analysis equipment located in the Primary Chem Laboratory will be supplied power via an extension cord. The extension cord has four double recep-tacles spaced at intervals to accommodate the equipment location in the laboratory and will be connected to duplex receptacle No. 7 located on the West Wall in the Canberra 4.0 i

s 1004.15 Revision 4 Counting Room (See Attachment 5).

Receptacle No. 7 receives power from Distribution Panel MG-1, Breaker No. 6.

The extension cord is stored in the post accident equipment cabinet.

The CPU air conditioner located in the Canberra Counting Room is connected to a duplex wall receptacle tha r.

ves power from Distribution Panel CT-6, Breaker No.

ing a loss of offsite power, connect the CPU air c er to duplex wall receptacle No. 4 located on t Hall near the East Wall. R t le No. 4 receives o from Distribution Pane reaker No. 6 (Se Q ment 5).

12. Co et close the samp e oo 13 ta the containme b r in the hallway between the lear sampling r d rimary chemist lab.

6.2 Precautions 6.2.1 Ensure 1 required sam 1 pment is available be in ating samolin,, c off Appendix C, Post Sample Eculom h v tory.

6.2.

ppropriate numb etermined by Chemistry

- ~ - - - - -

rdinatorrof technicians witivequipped iraccor-dance with the RHP or instructions provided by the Radiological Controls Coordinator.

5.0

1004.15 Revision 4 6.3 Sampling Procedure NOTE:

Personnel performing sampling will leave Sample Room :

and notify their Supervisor immediately if it appears :

that their extended exposure limit (as established by Radiological Assessment Coordinator) might be exceeded.

NOTE:

Personnel performing sampling will ve f,

cedure steps that require time limits wt unicator :

outside of the sampilng area.

NOE[

te valve extens

~

W

=

y NOTE:

iation levels w 1b pendent on the status of mal RCS samplin lv Contact control room o find our pos CAV 1, 2, 3, 13.

If open, radiation level c be high; if not, levels are expected to e

vely low until sampling begins.

. Chemistry ans will enter after discus-sing radi ards'with Rad Technician per-formin r

6.3 Radiological t

(Rad Con) Techni 1 enter Sampling Room carrying e

r with probe ex nd perform rapid survey of radiati s.

The Rad Con chn tan shall leave the room and

_ _then_.

s _radiationjevels an _ ther_ hazards __ wtth_ chemistry personnel assigned to enter the sample room. Stay times shall be established by the Radiological Controls Coordinator. These actions shall be performed in a timely manner to accommodate the three hour time limitation.

6.3.1 Chemistry Technician No. I shall proceed as follows:

6.3.1.1 Place leaded glass shield in front of CA_V-16, (in sample sink).

6.0

1004.15 Revision 4 6.2.1.2 Place wheeled cart with two sample shields (one for liquid sample and one for gas sample) in front of the nuclear sampling sink.

6.3.1.3 Open hood and place polyethylene sample bottle (F) with cap removed into hood.

6.3.1.4 Verify open valve *CA-V330 (on PAS Pan )

tart vacuum pump.

6.3.1.5 Open the following valvas:

317 (on Argon Bott 22 (on PAS Pa 6.3.1.6

-V321 to per ar line to drain for 15 seconds close *CA-V3 6.3..

Open the foil g

es:

CA-V30 rogen Bottle)

(o Nitrogen line

// -

(on PAS Panel

-V315 (on PAS Pane

• CA-V323 (on PA 6.3.1 rge nitrogen to dral opening *CA-V322 for 15 seconds then close the following valves:

CA-V309 (on Nitrogen line)

• CA-V314 (on PAS Panel) l

• CA-V315 (on PAS Panel)

• CA-V323 (on PAS Panel)

• CA-V322 (on PAS Panel) l 7.0 l

1004.15 Revision 4 6.3.1.9 Verify that the pressure at PI 1104 has reached approxi-mately 28.8 inches Hg vacuum and record on Data Sheet (Appendix 8).

(If not, verify [on PAS Panell that CA-V-330 is open, CA-V-329 and CA-V-326 are closed and that the vacuum pumo is running. Recheck at PI 1104 reads approximately 28.8 inches Hg vacu

.)

6.3.1.10 Close *CA-V330 (on PAS Panel), and e vacuum pump.

6.3.1.11 Close or verify closed the folio es:

V26A (behind nucle amp g control panel along fl

-V26B (behin nu r sampling control panel alc 1

)

CA-V26C h

nuclear sampling control panel floor)

CA ehind samplin ink a ng floor) 6.3.1.12 Ope r

y open the foll g

ves:

-V25A (behind nuc mpling control panel along CA-V25B (behind ar sampling control panel along floor) 6.3.1.13 Open the following valves:

• CA-V325 (on PAS Panel) l

• CA-V324 (on PAS Panel) i I

1 I

l 8.0

1004.15 Revision 4 6.3.1.14 Notify the control room to cpen the following valves and ensure that they remain open (these valves may shut automatically due to high radiation interlocks). Check panel after acknowledgement has been received:

CA-V13 CA-V2

^ - _.

CAUTION: Adjust *CA-V-110 carefully sin s

e of 125 PSIG :

Do not stand :

downstream will cause CA-RV-5 r

f valve CA-RV-5 near the drain funnel in wh ~

f s mple hood).

di ges (west side in Den *CA-V-Il0 (f li?

riction device; behind 6.3.1.15 ing sink along 1

) o obtain pressure of 40-60 PSIG on CA6 PI.

6.3.1.

Check temper d cator TI 1023 r increase in temperat 6.3.1.17 Check '

ss indicator PI O

nerease in pressure.

NOTE:

L of increase in re or pressure indicates :

H -- pcssibi

' n in sample lines. If i

s occurs, go di io step d.4 and proceed with :

+

urging lines.

---

=

6.3.1.18 Chemistry Technician No. I should return to step-off pad, check dosimeter and inform Rad Con Technician of exposure received.

Allow the sample to recirculate through the 40 ml cylin-der at least five minutes before proceeding.

l 9.0

i 1004.15 Revision 4 6.3.1.19 Rad Con Technician will enter sample room with Teletektor extended, quickly check radioactivity levels, leave sample room, and record and report results to Rad Con Coordinator and Chemistry Coordinator. The Rad Con Technician shall discuss radiation levels d other hazards with chemistry personnel assign ter the sample room. Stay times shall be oy the Rad Con Coordinator. These actions shal ormed in a time

.anner to accommodat thr e hour time 11 D

6.3.2 stry Technician o.

til proceed as follows:

6.3 1

ify that tempe 150* or less is indicated on CA4 TI (in sa s

area corner). If temperature exceeds 150 this procedur notify the Chemis~-

try C r.

6.3.f.2 Rai h

r and open CA-I hisimin water; in sample i

o flush sink.

6.3.2.

CA-V16 and clos oor. Allow CA-V16 to purge pen) for 15 seconds.

6.4.2.4 Close CA-V16, leaving CA-V107 open to flush sink.

6.3.2.5 Cbtain grab sample by placing sample bottle (F) under drain line (hold sample bottle with remote handling tool), open valve CA-V-16 (in sample sink) and fill sample bottle to premarked fill line level (approximately 20 - 30 mil.

10.0

)

1004.15 Revision 4 6.3.2.6 Close CA-V-16, leaving CA-V107 (demineralized water) open to flush sink.

I 6.3.2.7 Move sample bottle to lead pig (C )on cart, and push cart to containment (tent) barrier.

6.3.2.8 Completely close hood.

6.3.2.9 Return to step-off pad and infonn Rad C h cian of exposure received.

6.3.2.10 Rad Con Technician will enter sa with Teletektor exten quickly check radio ivi level s, leave sa and record an repo esults to Rad Con or and Chemistry nator. The Rad Con ician shall disc s a f ation levels and other hazards with chemi ersonnel assigned to enter the sample room.

mes shall be es lished by the Rad Con Coo r.

These actions shall perfonned in a time to accomodata e

hour time li on.

A.3.3 Technician il proceed as follows:

6.3.3 k that steady stat perature has been reached in 40 ml cylinder, via TI 1023. (If not, return to step-off pad, allow system to recin:ulate and remotely monitor temperature).

6.3.3.2 Close or verify closed the following valves:

• CA-V324 (on PAS Panel)

• CA-V325 (on PAS Panel)

• CA-V110 (behind sampling sink along floor) 11.0

i 1004.15 Revision 4 CA-V33 (behind sampling sink along floor)

CA-V34 (behind sampling sink along floor) 6.3.3.3 Close the following valves (on nuclear sampling control panel) and notify the control room that they are closed:

CA-V-13 CA-V-2 6.3.3.4 Record pressure on PI 1103 and tem a

'F) on TI 1023 on data sheet (Appendix B).

a.

temperature on TI 1 sg ater than 150*F.

valve CA-V313 AS anel) to allow deminer-D 0a12edwaterin c 1 ng bath.

(If not, go to step 6.3.3.5).

b.

Leave p nitor from remote location.

v c.

When t is e on TI 1023 below 150*F, r

panel and close Ive

-V313.

6.3.3.5 Ope y open the foi g

Ives:

CA-V315 (op PAS Pane

• CA-V326 (on PA

_6.3.

_ cord pressure at PI on data sheet (Appendix B).

6.3.3.7 Open *CA-V-321 (on PAS Panel).

6.3.3.8 Open valve *CA-V-323 (on PAS Panel) as required to bubble argon through 40 mi sample cylinder.

6.3.3.9 Close valve *CA-V326 (on PAS Panel) when pressure at PI 1104 reaches 2 psig.

6.3.3.10 Record exact pressure at PI 1104 on data sheet (Appendix B).

12.0

i i

1004.15 Revision 4 6.3.3.11 Withdraw gas sample from 300 m1 expansion cylinder via the septum guide tube using the locking syringe with 8 1/2 inch needle.

6.3.3.12 Remove syringe from septum, and place syringe in lead pig 2

(C ) on cart.

6.3.3.13 Open hood door and close valve CA-V107 n

ing sink).

6.3.3.14 Take samples on cart to laboratory 1 sis.

6.3.3.15 Upon returning from laboratory, imeter and info

'ad Con Technician of sur received.

6.3.4 C1 Gas Sampling TM of gas sampli t

hould be performed within ours after gas sa as been taken or prior to taking the nex whichever occurs first.

Rat! Con Tech 11 first enter ple room with Teletek c)ded,quicklych radi ion levels, leav d recced and t

ults to Rad Con o

ator and Chemist C

tor. The Rad Con h cian shall disc r

ation levels and other anis with chemistry _

_onnel assigned to enter the sample room. Stay times shall be established by the Rad Con Coordinator. These actions shall be perfomed in a timely manner to accomodate the three hour time limitation.

Chemistry Technician shall proceed as follows:

6.3.4.1 Close or verify closed the following valves:

i

• CA-V321 (on PAS Panel)

• CA-V315 (on PAS Panel) 13.0

1004.15 Revision 4 6.3.4.2 Start vacuum pump.

6.3.4.3 Open the following valves:

• CA-V330 (on PAS Panel)

• CA-V326 (on PAS Panel) 6.3.4.4 When pressure indicator PI 1104 reads app imately 28.3 inches Hg Vac, close valve CA-V330 o Panel) and stop vacuum cump.

6.3.4.5 Open or verify open the followin (on PAS Panel) for-ximately 30 second rat water out of the ga s ng system:

D C*CA-V329

• CA-V315

• CA-V322

(

")

6.3.4.6 Close *CA-V '

AS Panel).

6.3.4.7 Open t wing valves (on Panel and flush lower sys minutes (return s

off pad while

-V312

• CA-V314 6.3.4.8 Open *CA-V326 (on PAS Panel).

6.3.4.9 Close *CA-V315, and flush upper system for 2 minutes (return to step off pad while waiting).

6.3.4.10 Close valve CA-V312.

6.3.4.11 Open valve *CA-V315, and let system drain for 1 minute (return to step off pad while waiting).

6.3.4.12 Open CA-V309 (on Nitrogen line).

14.0

i 1004.15 Revision 4 6.3.4.13 Purge for 30 seconds with nitrogen to remove remaining moisture.

6.3.4.14 Close or verify closed the following valves:

CA-V304 (on Nitrogen bottle)

CA-V309 (on Nitrogen line)

• CA-V314 (on PAS Panel)

• CA-V326 (on PAS Panel)

• CA-V329 (on PAS Panel)

V315 (on PAS Panel) 3 (on PAS Pan 6.3.4.15 CA-V321 (on PAS Danel or 3 seconds to purge argon 6.3.

Close or verify s

he following valves to decommis-sion the sys CA-n rgon bottle) on PAS Panel)

V

-V321 (on PAS Pan 1)

-V322 (on PAS ne 6.3.4.

h 1stry Technician sho return to step off pad, check dosimeter, and inform Rad Con Technician of exposure received.

NOTE:

The following steps are to be taken only in the event :

of a line blockage in the sample lines.

6.4 In the event of blockage in sample lines, proceed as follows:

6.4.1 Open or verify open the following valves:

[

CA-V309 (on Nitrogen line)

• CA-V314 (on PAS Panel) l

'5.0 l

l

i 1004.15 Revision 4 6.4.2 Record as found position on data sheet (Appendix 8) and open or verify open valve *CA-V325 (on PAS Panel).

6.4.3 Record as found position on data sheet (Appendix 8) and close or verify closed valve *CA-V324 (on PAS Panel).

6.4.4 Open or verify open valve *CA-V315 (on PA nel).

6.4.5 Record as found position on data sheet x B) and close or verify closed CA-V306 (on tr n line).

6.4.6 Open valve CA-V308 (on Nitrogen d purge sample line 30 seconds.

6.4.7 Clo e following valv s. 9 C*CA-V315(onPA ane

• CA-V314 (on 1)

CA-V308 i

en line) 6.4.8 Return the o{

valves to th ound positions record ta sheet (Append

).

(on PAS Panel) v

-V324 (on PAS P 1

CA-V306 (on Nit en ne)

__ _ _ _ _._ _ _. 6.4.9 ReturrLto. step.6.3.L l. d pro:eed.

16.0 I

1004.15 Revision 4 APPENDIX A Post Accident Sample Procedure Initiation Setpoints*

RMS Parameter Setpoint RM-Li High Channel 8.5E3 Low Channel 4.5E5 RM-G8 1

RMA-2 Gaseous Chan cpm RMA-9 Gaseous Chan 7.lE cpm Q.

3 cpm RMA-5 Gaseous C e

b w

• These nts are provided t th for guidance in determining the necessi procurement of le in accordance with this procedure d analyzed in c with EPIP 10

33. Any RCS samples taken below these s during an e cy requires that the RAC consider whet ditional radiolo recautions are necessary.

O s

l l

l 17.0 l

l

1004.15 Revision 4 APPENDIX 8 Data Sheet for Post Accident Sampling System 1

Record pressure on PI 1104 from Step 6.3.1.10 2

Record pressure on PI 1103 from Step 6.3.3.4 3

Record temperature on TI 1023 from Step 6.3.3.4 T 4

Record pressure at PI 1104 from Step 6.3.3.6 5

Record pressure at PI 1104 frcm Step 6.

O O

v If 4

emoving Line e is performed, Record the f 1 ow Step _6.4.2__

A found position for

-V32S Step 6.4.3 As found position for *CA-V324 Step 6.4.5 As found position for CA-V306 (on Nitrogen line) 18.0

ATTACHMINT 1 Analysis Area Scher.atic 1004.15 l

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0 19.0

1004.15 Revision 4 ATTACHMENT 2 Page 1 of 2 INVENTORY CHECKED BY DATE j

POST ACCIDENT SAMPLE EQUIPMENT INVENTORY DESIGNATION EQUIPMENT AMT. REQ.

AMT. IN LOCKER A

4" Thick x 24" long x 12" high I

laminated glass shield B

S0111 catch can 24" x 24" x 2" deep C'

Lead pig for licuid sample bottle C*

Lead pig for gas (syringe) sample C3 Lead pig for chloride sample 1

C' Lead p1 d No. I 1

D' Magn base Q

l 2

0 Ma tir base 1

E' iter coly bottle cc a ig 1

1 0 ml DI water a ti r

E2 1 liter poly bot e ining 1

1000 ml DI wa n

ir bar F

125 mi samp e containing 1

sample (

p e cart)

V r

G' 10 ml o ng vial containin 1

of D e

2 G

unting vial contal i ml 1

ter H

10 mi scintillation vial for chloride 1

analysis I

250 mi beaker containing 99 ml DI 1

water and stir bar i

20.0 1

4 1004.15 Revision 4

)

ATTACHMENT 2 (Cont'd)

Page 2 of 2 POST ACCIDENT SAMPLE EQUIPMENT INVENTORY DESIGNATION EQUIPMENT AMT. REQ.

AMT. IN LOCKER I'

250 m1 breaker containing 99 m1 DI 1

water and stir bar I*

250 mi breaker containing 29 ml OI 1

water and stir bar NOTE:

I' and I* will be used for the c analysis and can be prepared within the 7 hour8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> time period.

J 0.1 mi pipet w/tip on n

1 isle c p

K 1.

endorf pipet w/ 10 o enter 1

is cc er top L

d pig for used pip nd 1

ringe N

1 mi locking syr 1/2" needle 1

0 Piston bure r ase (for boron titration)

P Lamina ass shield 12" x 1 4'

I thic Q

M ni 1

0" w/ scoop 1

R C1 for pH adjustmen 1

T 3' long handled tongs 1

U Short handled tongs i

V Poly bags 1

W Roll of tape 1

X Lead brick 1

Inventory check by Date l

21.0

i i

1004.15 AlfAarHlf3:

I ACCIIUff PESTRJ S#flim SYSTUI SODNIC Revision 4 To Plant Exliaust PIi104 J L PI1103 Smok Elim$nator TIl023 I

Vacuum Pump Sample Ilood

/

l Sliteld Wall l

Relief

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$332 I

Set at 2500 psig k305 l

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• l 329 Relief S i

/

I g' '

At 25 psig

^

l k 328 I

M g,,

'25B 11 Sample j

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b 30

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335 333 n

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l336 334 26C f

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311 f2M Pressure 6000 pulg 33 Volume 494 Cu. Ft.

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Delay Coll 2

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317 To e

Pu f ic-tion

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At 15 psig C,

3D4 3

318 P e) l 321 Arnon 99.9995%

M 12 0 32p 1'

V SampleSink[24

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i Pressure 1585 pain 119 volume 100 liters I

i CE104 l

• Penotes Valve llandwlicel Extensions 22.0 pq Valve l

l

i 2004.15 Revision 4 ATTACH!ENT 4 Page 1 of 2 PREREQUISITE POST ACCIDENT SAMPLING VALVE POSITIONS VALVE NO.

VALVE DESCRIPTION POSITION CA-V-16 P.C letdown sample valve Closed CA-V-2 9 Isolation to upstream of MU-F-1A/B Open CA-V-3 5 CA-V-110 RC Sample Pressure Control C..-V-33 3 To RC Gas Sample Cylinder

>2 n CA-V-334 To RC Gas Sample Cylinder Open CA-V-335 From RC e Cylinder.

Open CA-V-336 From s

mple Cylinder D

Open CA-V-324 F

Sample Cylinde Closed CA-V-325 C Gas Sample Cylin W

Closed CA-V-323 40 ml Cylinder Dr Closed CA-V-315 40 ml Cylinder 30 1 Cylinder losed CA-V-326 300 ml Cy1 n e I t

Closed CA-V-327 PI 1104 Valve Open CA-V-332 PI s ure Test C1csed CA-V-329 m

linder to Vacuum ain Cl osed CA-V-330 YacuM Pump Inlet Open CA-V-314 N + Demin. Water Inlet Closed 2

CA-V-312 Demin. Water Flush Inlet Cl osed CA-V-309 N Purge Needle Valve Closed 2

CA-V-308 N Pressure Regulator Bypass Closed 2

CA-V-306 N Pressure Regulator Inlet Open 2

CA-V-304 N Bottle Outlet Closed 2

23.0

1004.15 Revision 4 ATTACHMENT 4 (Cont'd)

Page 2 of 2 PREREQUISITE POST ACCIDENT SAMPLING VALVE POSITIONS VALVE NO.

VALVE DESCRIPTION POSITION CA-V-313 Den;1n. Water to 40 ml Cylinder Closed Cooling Bath CA-V-321 Argon Purge Inlet C

ed CA-V-319 Argon Purge Needle Valve p

CA-V-317 Argon Bottle Outlet osed CA-V-322 40 ml Cylinder Orain losed CA-V-30 RC Bomb I lon Closed CA-V-31 RC Bomb n

Closed CA-V-25C RC le Sel. Valve Closed CA-V-337 I -

Inlet Open CA-V-33 tilary Tube Is n

ve, Open Sampie.

CA-V-34 Capillary Tub n Valve, Open RC Sample CA-V-2 RC Samp lation V

Closed CA-V-13 RC L mple Isolation Closed 0

g 24.0

f 1004.15 1

Revision 4 i

arTKHMEA 7^ 5

/

,EMERGEAICf A0 toe /2 CONAlCCT/oAl DU/2/AfG L0S3 0F OFFStTE POidEA?

Electrical 'Redept cles (Receptacle l's as ind ted adjacent to each receptacle)

I

[I.

MA Canber a N=

3 S c

c 5

v 1 y

1 3

Exten 109 ed Dof 6

~ ~S A

s i.

NOTE: 1 C

tr Conditioner curr ly nected to unnumbered outlet

[_ _ _, _ _ _, _

wee

1. 4 & #6. during oss r, connect to 74 Primary Chem Lab.

2 Ex e n c.ord to be connected t p,acle #7 1

U2 I

I Duplex 4

s.

Receptacles 25.0 1

6 1004.33 Revision 5 01/19/84 IMPORTANT TO SAFETY NON-ENVIRONMENTAL IMPACT RELATED THREE MILE ISLAND NUCLEAR STATION UNIT NO. 1 EMERGENCY PLANNING IMPLEMENTING PROCEDURE 1004.33 HAN0 LING HIGH ACTIVITY REACTOR COOLANT SAMPLES - BORON, CHLORIDE, GAS, AND GAMMA SPECTRUM ANALYSIS - ACCIDENT CONDITIONS Table of Effective Pages Page Revision Page Revision Page Revision Page.

evision Y

1o 3.0 5

4.0 5

5.0 5

6.0 5

7.0 5

8.0 5

9.0 5

9 10.0 5

11.0 5

12.0 5

13.0 5

14.0 5

15.0 5

16.0 5

17.0 5

21.0 5

22.0 5

23.0 5

24.0 5

25.0 5

25 o 5

/f)Yb'Y mn TJig~ natured Date Signature Date Document ID: 0003H

1004.33 Revision 4 THREE MILE ISLAND NUCLEAR STATION UNIT NO.1 EMERGENCY PLANNING IWLEMENTING PROCEDURE 1004.33 HANDLING HIGH ACTIVITY REACTOR COOLANT SAWLES - BORON, CHLORIDE, GAS, AND GAM 4A SPECTRUM ANALYSIS - ACCIDENT CONDITIONS 1.0 PURPOSE The purpose of this procedure is to provide ~ guidance to tech icians involved in the handling and preparation of post acciden coolant samples for baron analysis, chloride analysis, gamma analysis and gas analysis, as described in NUREG 0737. It d to provide prompt analytical results for the above mentio pa ters while minimizing technici es per the re u.ireme of NUREG 0737.

Specifically, th q

ements include:

D 1.

Boron a

mpleted within h rs or less from the time a

'deci s made to obtain a 2.

Gamma is topic analysis re uation of degre f core damage t.

completed within 3 o

ss from the time a sion is made to obtain a samp e 3.

Chloride anal ompleted within 1 if sume 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />), if done in-h sent off-sit s

will be completed within a

~ ~ ~ ~

4.

Total Gas alysis completed within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> or less from the time a decision is made to obtain a sample.

l S.

The above sampling and analysis completed without incurring a i

l radiation exposure to any individual in excess of 3 Rem to the

- whole body or 18 3/4 Rem to the extremities.

i 1.0

1004.33 Revision 5 j

All of the above requirements assume a highly radioactive initial sample with a source term as specified in Regulatory Guide 1.4.

The Chemistry Coordinator is responsible for implementing this procedure in coordina-tion with implementation of EPIP 1004.15, Post Accident Samoling.

2.0 REFERENCES

2.1 Chemistry Procedure CP N1956 2.2 Chemistry Procedure CP N1957 2.3 Chemistry Procedure CP N1904 2.4 Chemistry Procedure CP N1990 2.5 Chemistry Pro N1880 2.6 Chemistry e

CP N1918 Q

2.7 Post Ac quipment Invent At chment 1) 3.0 ATTACHME l

3.1 Attach nt 1 - Post Ac e

mple Equipment ventory 3.2 - Anal s

Schematic 3.3 - H Concentration 1

n 3.4 Instrument Line-U 3.5 Attachment o Ion 100 Con ograming Form

~

3.6 Attac n

- Estimation of Co ge By Gamma Spectrum Analysis

~ ~ ~ ~~ ~ ~~ 3. /

Attachme 7 7 Post ~ Accident Reactor ~ Coolant Sample ~ Summary-4.0 EMERGENCY ACTION LEVELS 4.1 An emergency condition has been declared and a request has been j

made for a gamma spectrum analysis, boron analysis and chloride analysis of high activity reactor coolant liquid sample. In addition a gas analysis of a high activity reactor coolant gas sample is also required (both samples are obtained per EPIP 1004.15).

2.0

1004.33 Revision 5 5.0 PROCEDUR'E NOTE:

Initial steps upon completion.

NOTE:

Steps 5.1 to 5.6 shall be completed prior to taking a :

sample in accordance with 1004.15.

5.1 Verify Radiological Control personnel are availab sist Chemistry technicians by providing complete r lo ical coverage, (i.e., prescribe proper protective clothin etry require-ments, Scott A c or supplied brea air requirements, perform init n continual dose survey while the chemistry 9

technici w

s with the sampi an nitor chemistry technicians' exp e

ghout the pro NOTM The Radiol ntrols Coordina r shail ensure that chem sonnel confor he exposure Limits c

in EPIP 1004.9, ooical Contr no Emergencies.

$. T1/hY MY.._

~~

kcessary, transpof t mple to the dilution NOTE:

M n.

Reduce ra i vels to minimize inter- :

nce on the ope a ion the counting facility.

5.2 Ensure tM the shift supervisor has been riotified that work on the sample is to commence and verification has been provided that the control building ventillation system is in the emergency recircula-tion mode of operation with the AH-E-90 and AH-E-91 fans operating and will not be interrupted.

5.3 Ensure that the appropriate number of Chemistry Technicians (as determined by the Chemistry Coordinator) are dressed and prepared to obtain, prepare, and analyze the sample.

3.0 l

l

1004.33 Revision 5 5.4 Ensure that all personnel involved with handling and analyzing the sample are thoroughly familiar with this and other referenced procedums.

5.5 Prior to handling the liquid sample, establish equipment in chemistry laboratory exhaust hoods per Attachment 2.

All dilution water must be added to the containers and the con i re_

labelled prior to handling sample. Label sam 1

(F) and cormsponding lead pig with labels stating 4Mi OTTLE F and time, date and of Chemistry Techni i el Vial H and cormspondi g with labels ing AL H and time, date 1

2 and name i try Technician. S stirrers D and D,

run ro n.

5.6 Prio handling gas sa are gas chromatograph (GOW-MAC 69 570) and Strip Cha r (GOW-MAC 70 70 and calibrate with Standanis, i da e with Proced N19, N1957. Check that chromatogr abl e.

NOTE:

ainder of this e

will be perfomed f r a liquid and as mple have been taken and mples have been b o the laboratory in lead

~ ~-

l gs, and the above s (5.0 5.6) have been comp 1eted.

I I

5.7 Gas Analysis 5.7.1 Remove syringe containing gas sainple from lead pig on cart.

5.7.2 Inject sample into gas chromatograph and discard syringe into lead receptacle (L).

5.7.3 Measure the height of the hydrogen peak from base ifne.

l 4.0

1004.33 Revision 5 5.7.4 When sample has been completed, shut down the recorder by I

turning the recorder to "Off" and lift the pen.

5.7.5 Calculate hydrogen concentration using Attachment 3.

The sample liquid volume and expansion bulb volume are given in the calculation sheet.

5.8 Baron, Chloride and Ganana Scan Sample Preparation 2

(E ) on NOTE:

All dilutions shall be done with

)

stir plates to ensure proper mi 5.8.1 Util ong handled tongs Chemistry Technician sha ove sample (F) f nsport pig and place in ig ( ) (refer to At hme

2).

5.8.

ckly and caref 0.1 ml of sample, using Eppendorf pipe m sample bott (F) to the 1 litar poly bo

).

5.8.3 Di scard m pipet (J) into d

ceptacle (L).

5.8.4 Tra from SAMPLE B to beaker (I) using e

).

Discard tip m

t (K) into lead acle (L).

5.8.5-lace-new tip.on-pipet-(

-and -.transf er. 3 mL from.sampie______

bottle (F) to vial (H). Close lid on vial (H). Put vial 3

(H) in lead transfer pig (C ) and place pig on cart.

Discard tip from pipet (K) into lead receptacle and place new tip on pipet (K).

5.8.6 Place new tip on pipet (K) and transfer 2 ml from sample 2

bottle to vial H in hole of lead block in the hood.

2 H will be used to detennine pH. Discard tip from pipet (K).

5.0

1004.33 Revision 5 NOTE:

Vial (H) will be used to do chloride analysis.

5.8.7 Using short handled tongs, replace cap on SAMPLE BOTTLE l

(F). Place SAMPLE BOTTLE (F) back into transfer pig

[previously used for transporting bottle (F)], place on cart and move cart to far side of the la 1

poly bottle l

5.8.8 Using pipet (K), transfer 1.0 m1 fro I

2 n

o vial (E ) to 1 liter poly bottle (E )

I I

I (G ).

Cap vial (G ) and cap (

)a lace (E )

in left hand corner of d 1 behind the lead k.

Q 5.8.9 ie tip from pipe

)

to lead receptacle (L), and l

place new tip on 5.8.10 Using short ongs, transfer ker (I) from hood 1 to d

nd (place on bo tor magnetic stir ba 5.8.11 Wi tip on pipet (K), r sf 1 m1 from bottle j

2 2

t vial (G ), Cap p (E ) and ard tip from pipe to lead mceptacle (L).

2

'o~s'e cover on~nsieptad1T(L). Place (E )~1n back lef t~

hand corner of hood 1 behind the lead brick.

I 2

5.8.12 Place vials (G ) and (G ) into individual poly bags I

2 and tape bags shut. Survey (G ) aad (G ) with a dose rate instrument.

NOTE:

It may be necessary to mmove the sample from the primary laboratory to conduct an accurate dose rate due to a high background radiation-level in the l aboratory.

6.0 t

1004.33

)

Revision 5 NOTE:

For guidance, samples reading > 1 mr/hr will be too active for counting on the Geli detector /MCA system.

i.e., greater than 15 percent dead time.

If both samples read > 1 mr/hr, further dilution of the con- :

tents of bottle (E*) is required. Note all sub-sequent dilutions of (E*) so that correct volume calculations can be performed.

n erference :

NOTE:

If background noble gas levels result with Gell analysis (high deadtime on,

re shield cover on Geli cave is close tiate compressed air purge of cave.

f.

NOTE:

If ground levels do no low e use of the 1/MCA system, an. y ay be performed by ing samples t I-2 o to the mobile lab Environmental A 9 t Group.

^ - - - -

If counting via (

se the volume of 1 x 10-* ml.

ting vial (G*), volume is

(

1 x 10 " ml A

M

.1--.

A-_ ____

5.9 Gamma Scan e reading <1 mr/hr) l 5.9.1 Tra o

opriate sample

( r ting room and count i detector /MCA system l

r 90.1.

A

.. __. _. NOTEN -For a-PostAccident Sample,- after placing-themmph:

on the detector, check the dead time by starting a count using the MCA keyboard control. The dead time :

should be <l5 percent.

NOTE:

L onto the VT-100 terminal by typing HELLO POST ACCIDENT / SAMPLE. Start the sample count by answering :

the computer prompts. At the end of the count, SPECTRAN-F will print a report. Record results in 7.0

1004.33 Revision 5 5.10 Boron Analysis 5.10.1 Perform boron analysis on the contents of the beaker (I) per Chemistry Procedure CP N1904 observing the following l

cautions and exceptions:

a.

In the calculations given in section 6.0 of Chemistry Procedure CP N1904, sampi me, "S", is l

b.

Us f 1 KAP standard for Na0 rdization may be used vice 3 as specif N1904.

c.

ked sample will 5.10.2 1

g titration, peu ntents of beaker (I) down sink and flush i fc approximately 2 minutes with demin water.

5.11 Chlor Analysis Perform chloride a s

the contents o ial (H) as follows:

5.11.1 Pr is es 5.11.1.1 r

erforming thi e, the technician shall e a thorough know CP N1880 and CP N1918.

5.11.1.

io control exposure from RCS Waste water from the IC Unit, construct a lead cave using available lead bricks surrounding the 500 ml poly bottle. Haste water shall not be allowed to accumulate more than 20 mis. Promptly dispose of water after each analysis sequence using appropriate tools.

8.0 l

4 1004.33 Revision 5 5.11.1.3 The It Unit can be relocated to the east-side countertop to minimize portable shield usage if needed. This should not be necessary if IC Sample pathway is purged with demin water and columns are changed out regularly.

Radiological controls will evaluate via surveys after each use.

5.11.2 Apparatus 5.11.2.1 In addition to the equipment used 18, use the followi ng:

a.

n 100 Controller y ex on Autosampler b 6P x-Model SC 011 ton Roy Pump el NSI-33R d.

Polystyrene C t tubes by Corning (16 x 125 mm) 5.11.3 Drocedure 5.11.3.1 Set up of atograph a.

Se CP N1918 exce ve and tubing nections as shown ment 4.

5.11.3.2 p of Ion Chromat Startup per CP N1 5.11.3'.3 tupofIn'tegrator

~

~~-

~

~

a.

Set up per CP N1918 5.11.4 Sample Preparation 5.11.4.1 Post accident samples may contain up to 10 ppm Cl,

therefore it maybe necessary to dilute the samples to bring them into the range of CP N1918 (less than 200 ppb Cl-). Dilute 1 ml of sample from vial H in a beaker 9.0

1004.33 Revision 5 I

containing 99 mis of demineralized water, labeled I.

Dilute another 1 ml of sample from vial H in another beaker containing 29 mis of demineralized water and label it I'.

5.11.5 Sample Analysis 5.11.5.1 Press the control on the Auto Ion 100 C 1

for System 1 5.11.5.2 Move from LOCAL to REMOTE on the n

ity Detector for S m 1.

V 5.11.5.3 Co System 1 dete r cab to the integrator D

5.11.

4 METH 2 ENTER on e ntegrator keyboard.

5.1 Press START and T apid sequence on the integrator keyboard.

5.11.5.6 Review t grM in the Contro ler an ompare with the writt in Attachnen 5.11.5.7 Mo Schedule Mode and e number of samples to a lyzed.

5.11.

to Run Mode.

5.11.5.9 urn the Autosampler On.

5.11.5.10 Turn on the water sourte for the Autosampler and adjust the flow so the reservoir will remain full. Use demineralized water.

5.11.5.11 Turn on the Milton Roy Mini Pump and prime the pump with a syringe to eliminate bubbles and dead space in the sample line. Set the pump to 50 perterit pumping efficiency.

10. 0 l

1004.33 Revision 5 5.11.5.12 Put approximately 10 ml of sample into polystyrene tubes and place the tubes in the carousel of the Autosampler.

Make sure the first sample is directly in line with the 1

pipet arin of the Autosampler. Label the tubes 1 and 2

1 respectively.

5.11.5.13 To start the sampling process, press the n TART control in the Operation Select Sect o

Controller. Al so press the brown ot n the Advanced Chroma aphy Module for Sys 1

LOCAL to REMOTE.

The eps start aut atic ation. The Auto Ion ller is now cont g the entire analysis.

5.11.

rdization 5.1 Standardization of System is required once per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> shift f es.

5.11.6.2 Prior to ng the instrum nt, a ze a ater blank usi t

ove analys.is deming The chloride the blank should be p

s n 5 ppb. If eat the analysis or contact istry Supervision.

~-~

5.11.6.3 hloride Calibration a.

A standard which contains 50 ppb of chloride is used to calibrate the Integrator.

b.

Analyze the standard using the analysis procedure above.

11.0

1004.33 Revision 5 c.

Examine the Integrator printout. Chloride should be listed as CAL No.1.

If not, check the retention time printed on the chromatogram versus those contained in the calibration table. Modify the retention times in the calibration table if necessary and repeat the analysis o andard.

5.11.6.4 The reported amounts for chloride sh thin + 10 percent of the standard concentra

not, recalibrate the system by pres g

B.

5.11.6.5 Rep h

nalysis of the stand until the above r

are met.

5.11.7

1. ation 5.1 Calculate the fina ntration of chloride in ppb in each sample lying the report concentration by the appli tion factor, then act the water blank f valu e.

ppb Chloride (concentration pp x ion factor) - blank 5.12 pH Measu t

2 5.12.

onn pH measurement ntents of vial H.

hood sink and flush sink for approximately 2 minutes with demin water.

12.0

1004.33 l

Revision 5 6.0 FINAL CONDITIONS The remainder of this procedure can be done at a later time, to allow the radioactivity level to decay:

6.1 Lead pig (s) containing sample bot:le (F) must be placed in a locked High Radiation Cubicle (for example, precoat filter room) as directed by the Radiological Controls Coordinator.

exact location must be specified in the space below.

High Radiation Cubicle location:

/>

Et

%~

6.2 Poly bott E2 must be emp $

o the sink and the sink flushed inutes with dem n all d water.

6.3 C, Esti t no Core Damage By Gamma Soectrum Analys 6.4 Complete Attachmen Accident Reacto t Sample Summary.

6.5 Notify the Shift er sor that sampli g 7 ysis of the Post Accident Sa ve een completed e y the results.

0

- _ x 13.0

l 1004.33 Revision 5 ATTACHMENT 1 POST ACCIDENT SAMPLE EQUIPMENT INVENTORY DESIGNATION EQUIPMENT AMT. REO.

AMT. IN LOCKER A

4" Thick x 24" long x 12" high 1

laminated glass shield 8

Solli caten pan 24" x 24" x 2" deep 1

C' Lead pig for liquid sample bottle 1

C' Lead pig for gas (syringe) sample C'

Lead pig for chloride sample 1

C' Lead pig for hood No. 1 pl D'

Magnet ase 1

D*

Ma. c r base ty 1

E' 1

e oly bottle con ng i

1 DI water and i

E*

lite,r poly bott o a ning 1000 1

DI water and F

125 mi sampi ot containing sample (on a le cart)

G' 10 ml al containing V1 9 ml wa er 2

G 10 o

ing vial conta 1

m f I water H

mi scintillation vial 1

rfde anaTisls

- -~-

I 250 ml beaker containing 99 ml DI 1

water and stir bar I'

250 mi beaker containing 99 ml DI 1

water and stir bar i

14.0

1004.33 Revision 5 ATTACHMENT 1 (Cont'd) j POST ACCIDENT SAMPLE EQUIPMENT INVENTORY DESIGNATION EQUIPMENT AMT. REQ.

AMT. IN LOCKER I*

250 ml beaker containing 29 ml DI 1

water and stir bar l

NOTE:

I' and I* will be used for the chloride.

lysis and can be prepared within the 72 to u time period.

y J

0.1 mi eppendorf pipet w/tip on 1

center isle counter top K

1.0 ml dorf pipet w/tip o I

center nter top L

Le used pipet tips D 1

nge N

1 cking syringe 1

needle 1

0 iston buret w/s as-for boron 1

itration)

P Laminated g s

d 12" x 12" x 4' thick Q

Mannit coop V 1 R

Dil e for pH adjustme 1

T andled tongs 1

___.-___.____...__U

. _ handled tongs.__

1 V

Poly bags 1

W Roll of tape 1

X Lead brick 1

Inventory Check By Date 15.0 l

l l

1004.33 Analysis Area Schematic p,visinn g ATTACHMENT 2:

ii

(.MNIS)

Q'

,0,.

N.I E55

\\\\

t.

2 ons a>3 Ar b

b g

r N O Q

S ll 6D

=

vk'

^

.g m

9 Q

nWL7

.i

.i c

td <.

E V

A U

s 2

N 5

q'N

!j h.,,

.v a

.s e

q g,r,q;edc h :

p (D

.g.

. = '

\\ >

N

't

@fT dio 5J H) 5 q

g,

_w\\x ;

_3. _

!:x

'S h \\ )

Ni 1

a E

.>.E

'E. $

s g

o

=

e i

1 16.0

1004.33 Revision S ATTACHMENT 3 HYOROGEN CONCENTRATION CALCULATIONS A.

Hydrogen Analysis Peak Height (mm)

Attenuator Setting Volume Injected Sample:

Standard:

1.

Percent Hydrogen = (% Standard Conc.)(Sample Peak Height 11 NAF)

Standard Peak Height Where:

AF = Attenuator Setting for Samole Attenuator Setting for Standard VF = Volume of Standard Injected Volu f Sample Injected 2.

Calculation of cc' Sample Temper F)

\\(

Stripping e

e Pressure (P

) w CC Hydrogen =

drogen)(BV) x n49 x

PSIG + 14.7 V

100

• T + 460 14.7 BV = Volume of Exp o

b = (300 CC) 3.

Calculation of cc's of er olume e,1,,u,cen).

cc,,,te, H,e,oSen (cc,,d,o

. e ml) 17.0

\\

1004.33 Revision 5 ATTACHMENT 4 IC INSTRUMENT LINE-UP Sy5Dem

[

Lo2]lhject %Ive

%Ive A Giv ut I ',

/.

't 4$g F

AP w df 3,

h hk E

q itrttav supreese' u-,

n..

• 4 h

F i

ser h g t ce,)

s 7

(

s

1. 3 c.

=

c - ---. - -

/ 5 4l<.2Tes v2(va is on LOAD << OFF

,'Ied:cate, vaive :s on DI.7ECT ar OU 18.0 l

l

l Revis'iori 5 1004.

I I

ATTACHMEilT 5 Autolon" 100 Controller Programming Form SAMP E h95$

ff[Jem1

..hl. ____. _

SYSTEM NO.

. ____ f dalen(veragira e.e, A4;,, SeparaCe',detea Fi6e 5.fren.-

COLUMt4S{afish (estf@3%[efjELUENT 0.0011M Nall% 0.go SK4*tMa C9J DATE._b!Y */ /.

PRGGII AM NO., _ _l____.

s HEMARKS HEV O

ANALY11 CAL PUMP CilFIOMAIO HAPalV MODULE CONDUC E1[C10ft flEL AYS AC OU TL ETS flow Temp No 1

1 2

3 4

1 2

SIEP WE I

"I Itate Eluent Temp A

8 C

Offset ange 1

(mL min-8)

No.

Select

'M OFF/ON (% )

OFF/ON g

g k MFF 0FF 0FF O.O

2. 1 l

X 0hD YFkh I. ]

0FF

"[

4 og l

((p L

2 o,,

l. I bil 0FF w

y

l. 2-J f / )

d Al T. 2

/%

k W>

'l 0FF p

% f

.V 0FF s

c.c

% J )

on

>h L.o lE)I h

(

v c.

([ n y o// 2

(LL.

u Uke

7. *T OA

\\/

7 Q.

v A

l u

(0.0

\\

h l

{:

C A)

W OY h l

\\/

OFF V

\\./

10.I

\\l

\\/

LOA D i

83 i

14 i

IS I

19.0 1

1004.33 Revision 5 ATTACHMENT 6 ESTIMATION OF CORE DAMAGE By GAMMA SPECTRUM ANALYSIS 1.0 PURPOSE The purpose of this calculaticn is to provide an initial gross estimate to the extent of core damage by gamma spectrum analysis following accident conditions.

2.0 REFERENCES

2.1 TDR-431, Rev. O. Method for Estimating Extent of r

ge Under Severe Accident Conditions.

3.0 PROCEDURE 3.1 Basis For Estimating Core Damage 3.1.1 Th g NRC matrix sha 1 sed in reporting the es egree of core e u 111 zing specific lide data and ot t parameters, b

u ee of Min Intermediate Major adation

( <,M7 (l0% - 50%)

(> 50%)

> 1 No uel Damage t

G Cladding Failu 4

F Fuel Overhea h

6 7

M Fuel Melt

)1 8 10 VJ V

The matrix c ts of four general of damage and three degrees of within each of the s except for the "N0 FUEL DAMA 3.2 Calcu t 3.z.i amma' Scan Res0Tts mC1/mi I-131

=

mC1/mi I-133 mci /ml Ba-140 mC1/mi Cs-134 mC1/mi Cs-137 mCl/mi Ru-103 Te-12SM -

mC1/mi 20.0

1004.33 Revision 5 ATTACHMENT 6 (Cont'd) 3.2.2 Plant Parameters RCS Tave.

• F at estimated time of failure.

K-Density Correction Factor from TABLE I assume sample at 90*F.

V. V Sump gal.

• Vi - V RCS gal. *

(V.e. at 580*F is approximately 91,

)

l Power level at Failure A

• Co to operating T.

__erlevelchangedh than 10% in last 22 NOTE:

f s, record the fo lowf id Power Level _

w v

Time to make n

Tc) hr + 2 hr median time to make the change Time ompletion of c n hen core damage 1

x to have occur f

A r

Tc

+f

+2 2

t - median time t e power change plus the time :

" ~ ~ ~ ~ ~ ~ ~

~ " ~

after the~ power ~ change ~untti damage'~1s~expec- :

ted to have occurred, in days.

3.2.3 Activity Correction Aei.,33 - (A.

,33V, + A,_,nV,

+... + A,_,33V.) K=

pC1/ml V.cs Ae,.iii -

(A,.,3,V,

+ A,_,3,V2

+... + A..,3,V.) K =

pC1/ml V.cs

+ A.....oV,) K-pC1/ml Ae

._i.a

= (As.-,.oV, + A...i.oV2

+

V cs t

21.0 l

1

1004.33 Revision 5 ATTACHMENT 6 (Cont'd)

A. - Equivalent Nuclide Activity Ai - Activity of Each Sample corrected for density Vi = Volume (Gal) of each Component Sampled corrected at operating temperature K = Volume Correction Factor 3.2.4 Inventory Correction a.

If Steady State Power Level is 100 percent X.is

- Xi_

_i.o X = 100

% Power b.

ransient condition

• ex sted in the past 22 lculate X for ea h lide.

100 X0

=

-0.796t\\

-0.796t

+

)

Pie P:

-e l

=

isi 4tsCP

/

-0.0864tl Pe P(1-e i

X...

.a =

0

=

/

0.0542Y\\

.0542t +

P(e

)

Correcting Facto 3.2.5 u

e Damage to C Gap Activity

~ ~~

v G = Nrcent 6f Rods with~REptured'Cliddliiif ReliaRng

~ ~ ~ ~ ~

~

Gap Activity G = [(1.863 x 10-2)( Aei _i si)(X.i si)] - [(8.31 x 10-8)( Ae i i s a)(Xi.i n s)]

G=

22.0

1004.33 Revision 5 ATTAC}iMENT 6 (Cent'd) b.

Fuel Failure F = Percent of Rods Overheated with Fuel Releasing Activity F = {(1.684 x 10-')( Ae i.i 3 3 )(X.. i 3 3 )] - [( 3.64 x 10- 8 )( Ae i s i )(Xi.i s i)]

F=

c.

Fuel Melting M = (0.002)(Ae..i..)(X...i42)

M = Percent of Rods with Mo t NOTE:

nce of Rutheni TM1uriumactivity. -----

RCS and/or norm D ating Cesium activity elsindicatethgno el melting has occurred.

v 0

23.0

1004.33 Revision 5 ATTACHMENT 6 (Cont'd) 1 TABLE 1 DENSITY CORRECTION FACTORS FOR RCS EQUIVALENT VOLUME CALCULATION DENSITY CORRECTION FACTOR, K Reactor Coolant System RCS SAMPLE TEMPERATidRE. 'F Temperature at Time of AN Accident *F 80 90 N JO 100

.996

.998 1

150

.983

.98

.987 200

.966

.96

.970 250

.945 7

.949 300

.921

.924

.897 350 D.894

.862

.86

.865 400 450

.827

\\Q 8

.830 500

.787

.788

.790 550

.739

.740

.741 560

.728

.729

.731 57

.717

.718

.719 580

.7

.708

.709 590

.694

.695

.683 600

.681 Ah DENGITY CORRFK ION FA OR, K m M temperature i Wmately90*F.

Use uCTE.

Normai aCS S this tempera f no other in i available.

e 24.0

1004.33 Revision 5 ATTACHMENT 7 Page 1 of 2 POST ACCIDENT REACTOR COOLANT SAMPLE

SUMMARY

Date Time Chemistry Coordinator A.

CHEMISTRY ANALYSIS RESULTS 1.

Baron (KAP) 2.

Gas Analysis (hydrogen peak) hAD 3.

Gamma Scan AdD MM

\\

4.

Chlorid n

~\\ X o

n\\

5.

Hyd Concentration 6.

pH B.

CORE DAMAGE ESTIMATE 1.

Percent of fu r

th ruptured cla g

easing gap activity (G) 2.

cent ds overheated u

releasing activity 3.

Perce, ds with molten fuel C.

RADIOLOGICAL DATA 1.

Dosage a.

Chem Tech Others:

Name

/ Date b.

Chem Tech Name

/ Dat-I c.

Chem Tech Name

/ Date j

d.

Rad Con Name

/ Date 25.0

f 1004.33 Revision 5 ATTACHMENT 7 (Cont'd)

Page 2 of 2 POST ACCIDENT REACTOR COOLANT SAMPLE

SUMMARY

2.

Exposure Levels a.

Sampling Room (after sampling) mR/hr at b.

Analysis Room (after sampling) mR/hr at c.

Sample Bottle (F)(unshielded) mR at d.

Sample Bottle (F)(pig)

_m e.

Vial H (unshielded) m hr at f.

Vial H (pig)

R/hr at

.aw i

3.

Sarr;:le Storage a.

Locked h h adiation cubicle 1 n

Ab

\\s a

b.

Die location D

M

/

@T 4v

.d By Name

/

Title g

Date 26.0

" TEMPORARY CHANGE" Three Mile istEnd Nuciscr Stati:n Tsmparcry Chinga Notics (TCN) 12.TCN No b'{2if.j-bbli 2J (Fr m TCN Loginden!

f NOTE instructions and guidelinesin AP1001 A

'P ] I g

must be followed when completing this form

_,oim&

13.tmolementation Date SS/SF Signature i

fP SP I 804"'I

• *I C^ t M I'* n' " _ M T4Per tearson.

1.

Procedure No Present Rev No Tatie 2.

Change Onclude page numoers. paragraph numbers. and exact wording of enange (Attaen additional sneets if necessary and provu:le the genene nature of the change on this sheet.)

~

N" M N e.tcet e a s pp.y-3.

Reason for Change:

6Qw s %tW d-N- M K A

4.

Duration of TCN - No longer than ninety days from implementation dat f

or'as in (al or (b) below wnienever occurs first.

a Procedure Change P (a)TCN will be cancelled by a proc re r te on sued as s

F A

^

ubm:t PCR as soon as Recuest to be submitted by inoaus suonwn.

N possible)

C (b)TCN is not valid af Wdi m cwcumstanc reht m TCN bemg cancened) 5.

Is procedure "importa.

tyM YE yes E!To O if "Yes" a safety evalu t na quered iside 2).

6.

is procedure "

e pact Related")

_\\

yesO no P If "Yes" an env ntalimpact evaluation is req de 2).

[

7.

Does the change of t the intent of the o e ure?

A yes O noW NOTE: sf answers to #5.' 6 and 7 are "no nange may be approve h Shif t Supervisor.

NOTE: If answer to #7 is "yes" e ust be reviewed an porove accordance with Table 2 pnor to implementation.

NOTE: If answer to # 7 is "n an a ers to #5 or 6 are ~

h may be either (a) two member reviewed or (b) rev nc a proved in accordane ta 2.

8.

Cha g R c mend" ?

Date / /r/ /iT N bM f k

)I Date 17e=/M" 9.

• Procedure Owner Co u

. Responsitue off ce Depabn@'eus Designee may concur if Proceeure Owner es unavedabie

.ResoonseeTee a w

__. %,e.,1_

'!'f b Date

10. Tech. Functions Rep. Notified Of read.) N "A

11. Approval (s):

!g r I te AM OO1 Ah

{#,rR h M tlff f s Ig (a) Two Members of the GPUN Mng R

Staff Route p( mn.weW c/ Js

.,/,./ p

/

det.

I 1

Sqnature page g

2.

l

'S..name oa,e (c) SS Approval Only: (This approval only Wetnen fourteen (14) days: (Approval i

used if anwers to Questions #5. 6 and per AP 1001 A must occur) l 7 are all "No*.)

1 S.e,aiore o.ie l

SS 5.gnature Date Signature Caie l

14. TCN is Cancelled SNf t Supervisor & Stufi Foreman Daie e.di Aoool132 A

" EVAL.U ATIO N" Side 2 Three Mile Island Nuclear Station res so @ N 8' E Safety / Environmental impact Evaluation 1.

Procedure E 9t P r ero4. >

c /f 3,Was, yg,_

peu pee rsevye.>r, n

%o Tate j

2.

Safety Evaluation Does the attacned procedure change

• fa) increase the probability of occurrence or the consecuences of an accident or yes C no 2 malfunction of equipment important to safety)

• !b) create the possibdity for an ace: dent or malfunction of a different type tna yesC nor i

evaluated previously in the safety analysis report'.

I

• (c) reduce tne margin of safety as defined in the basis for a t n i

ves O no R i

i specification ?

l 8

l Details of Evaluation (Explain why answers to above questions ar o

acn additional pages if f

recuired.)

ht Pse e.a tu e. s,

c. o., c, t.

A, e e,m;,

mdO F#c.

i fa %g,gstue og n

g, p 89 8-O 7"L N Ag 0

WIS m3 **f*

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1%A- 0% o Oct Ibem ua x mg r

D b isu fb / w t7M "Me#

30f AS,

/ //= /84 Evaluation ByT Date

• 1f any of these questions nswered "YES" the e

t be reviewed and proved by the NRC pnor to l

implementation.

3.

Environmentalimpact Evaluation Does the attached procedure cha g fa) possibly involve a sign e

nmen tal impact).,

yesC noC Gf 3(a) is yes", a w stions (b) and (c) and fill i tails of Evaluation" below. lf no, state y

g in the "Detads of E n

lo w )

• (b) have a significan effect on the environ 7

yesO noO

• tc). involve a signi t environmentatmatter or question not-previously-reviewed--yesC-noC --

and evaluated by. e N R C.

Details of Evaluation (Attaen additionalpagesif recuired) e Evaluation By Date

• 1f any of these Questions are answered "YES" tne enange must ce reviewed and approved by the NRC onor to implementation.

4.

Normal Approval (s)

4. (2) If "Two (2) members of the Within fourteen (1 41 Days

( r GPUN management staff route:

Approval per AP 1001 A g[%snature E

pare Segnature Cate Segnature Date q su.h d ud als las.

3.gaa:ure Oase Segnature case Sw arure oa e 8-a2 Aooot t323

l i

t sI:'.:0N SHEEI Replace present atta:hmen: '!I! W'

r. tne "TCS Air Iant e t;ctr.ograph.

l

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e atior. : : e Tel::r:r.ix 4351: -i.i::. ;;;er., Ensure all

::.er.:s are c.se;i:ed ar.t ::ntectc-d ts shown below:

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Ir.:er cassette,

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. m A).

(see s:ner.ati:

V Se:ress the " Auto !. cad" button (S.

......atic - Item 2' the keyboard.

11.

12.

Begin ;rograr execution.

\\

'3.

The EAC shall utili:e .P. 'i s.. the Acrisc re'

'o rroject dose ates.

Tre U.: shall

.... Ee-i infinite moe 1

~

l

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f/_ __

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ClO8r GPUN D: cum:n si;w Sh::t Date

Subject:

Proposed Document 100_4.] _._ _ M & t_

OnstM hse __Mogdow Numties I ttle From:

_Mocedur(_ Coorsj_d.3CAVO This form may be photocopied and used Int inteenal destribution purposes. hut comments being returned qng. nato. s eunce.ones s' tie to the originator must be forwarded as a hatch from each Division /tintf.

To-O,_b_. ___K O U d new.eweef funce.onas s.ii.s

_h hh___f.sJ 6.Rh Atkinessees are regisested to review and provide comme

/

jinator nolater than o r,ti m

f DatfcAnts versuned fleviewer 6 < //. M/8WA/

Date of Cothhd//// / P'7 Origin %r /)

_ Date of flesolution ltem fleference CommentsV/

Accept Originator flesponses No.

Page/ Para.

(Show actual proposed rewordirig/i og[

Comment 3

/

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GPUN D: cum:n

.ri:w shast Date -

/&O4.7I_OEOld[Qnnle__)o.s...e._PhtjEdai subjeci:

Proposed noci ment

. _ ~.

feom:

_hocedure brd,_d_. SCdk__

This form mry be photocopied and used Ior internal distnbution porposes.but comments Iwing returocd qimmat<w's funcimat s'"a to the originator must be forwarded as. a balch f rom eacti Divisinn/ Unit h M,1.._b To:

,... _, _,.o.,

j 6nYmbhokT._

t Addrrsseen are requested to review and provide comme y oppinator nolater than Datfcpeqh nts serrm.d l

A

/j fleviewer d[_.n8aMg Date of CorhhV,/,

Originhr _)_)

__ Date of flesolution item Fleference Comments Accept Originator flesponses osg)

Comment q

No.

Page/ Para.

(Show actual proposed rewordir i

U 7 4 e c s y/ w yis uvillc% e

@ -f Jady

[

foij G abt

)

f4

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4 6

=

Aivm ie a ni i

s.n.n inwwe Ar>u s2ss 01 31a n2p t

f

" TEMPORARY CHANGE" Three Mile Island Nuclear Station Temporary Change Notice (TCN) s

12. TCN No. b~b"E (From 7CN t.og inceal NOTE. Instruccons anc guicet.nesin AP1001 A must ne feitawed wnen comoteting tnis form gg

13. implementation Date SS/SF Signature "7 ]

i. pr m e EP* mov.si f

A i L,% It-il i e A d.i s -

I.J

/ d = k es No Presen Aev No.

Tsine Change (htude page numbers, paragraon numt:ers. and e xact wording of enange. (Attach ac$nonal sneets 2.

if necessafY and provice the genenc nature of the cnanogon this sheet.)

5.e.. W.L.4 g 1.s e& m.t 7.e,s.o,t.e,so.efs.l.e,#4.,#7.o,/t'.e, d f.ed..

3.

Reason for Change:

A $*=T

=3. s y d**== **=M'3 Mao ll To e4dr 14 sI e a s k da-ses A

4 Duration of TCN. No longer tnan ninety days from implementation of$N or as en (a) or (b) below l

wnienever occurs first.

(a)TCN will be cancelled by a procedure ritvision iss a

esult of a Procedure Change 5 Request to be atted by 1t-W W

• L (Suomit PCR as soon as inervioues 5:Q ' TCN possa4He)

(b)TCN is not v a

C n in encurne u rewiin tcN nong conceimo y

yes I no ['.

antpafety*7

^

5.

is procedure *1mp If "Yes" a sa ev is recurid (side 21.

S.

Is proc oneitentalImpact Related yesC no 3

~

If "Yes" att e mentalwnpact evalue r

(sade 2).

b yes C no B 7.

'Does the change effect the intent of ^t.

a rocedure?

NOTE:if answers to #5.6 and "n '

che'ngimay ~be ao e Shlf t Supervisor.

NOTE: If answer to #7 is "y th e ange must be review so rowed in.: ?idance with Table 2 pnor to irnplemen NOTE:if answer to #7 answers to #5 or 6 e snge may be either (a) two member reviewed or (b) and approved in acco acte 2.

,//%V Review Signatures:

b NT Cate 8.

Change Recom g.

• Procedure trence' N f_ M b M N U 0 *-

• Date

/N I ed

. %,, e, r.,_,,,,,

. Meesonsom onieep _1 d. or ne oemenee enev 6 d Procesure owner = uneveme

• Assoonense f j

Tech. Funcoons Rep.Nonfied (If read.) N Oate 10.

w_

V **

11. Approvel(s):

onna cute Per AP1001 A);

(a) Two Members of the GPUN hg.

Staff Route nr G.I.G l

,9 F C$ b i /i,/e4 l

s ensiure om j

• ~

l

2. A f &

iln49-l g I-le-t<f i

senem

, osie l

(c) SS Approval Only: (This approval oniv Within fourteen (141 days: (Approval I

used if anwers to ouestions #5. 6 and per AP 1001 A must occur) l 7 are all "No".)

5.gnature osse l

SS 5.gneiure om sgneiure Oeie l

i l

14 TCN la Cancelled sa.it sueerv..or & sadi sorernen om

~~

8 d2 Acoot i n A

"EVA LU ATIO N" Sida 2-Three Mile Island Nuclear Station

.c3 % Q1-g-igeir e! ',

Safety / Environmental Impact Evaluation i

1.

Procedure Y II M'h" I* ' "

No.

r:ne t

i 2.

Safety Evaluation f

Don tne attacned procedure enange:

• tal increase the procaodity of occurrence or tne consecuences of an accicent or yksC no3 I

malfunction of equioment important.to saf sty ?

• tbl create tne possiodity for an accidenttor malfunction of a differern r;pe an any yes O no E I

evaluated previously in the safety analysis report E l

'fel reduce the margin of safety as cefinec in the casas for n t n scal yes C no 3 I

spec:flCation 7

./

i Details of Evaluation (Exotain wny answers to aeove cuestion a Attach additional pages if j

recuired.)

71,;, Tcn n iiftss S g d.es k -a o% L, 9a k

~

l

c. 4crP.

. W L y.. - ~.--L r,

• 4. L~. A e

/ 44 -

~

l J,.

1.4(

w ~ i,.r f6 4

Evaluanon By Date

/

• 1f any of these cu s are answered "YES" st be reviewed and approved by the NRC pnor to i

implementation.

g

~

w 3.

Environmentallmpact Evaluation

, Does tne attacned procedure fal possibly involve a si i onmentalimpact?

yes O no C (if 3tal is *yes".

r ou stions (b) and tc) a u.n rads of Evaluatir n-be6ow.If no stat y filitig in tne "Detads of Ev below.)

• tb) nave a sign a erse effect on the env m t yes C nc C

• (c) involve

• g t environmental matter Mtion not previously reviewed yes C no C

. _.. _ _and oval by tne N R.C. _.

Details of Evaluation (Attaen additional pages if recuired) i Evaluation By Data f-

• !f any of these cuestions are answered"YES" tne enange must be reviewed and aporoved by the NRC pnor to imolementation.

l l4. (1) Normal Approvella)

4. (2) If "Two (2) memoets of the Within fourteen (14) Days (Per AP 10Q1 A g

GPUN management staff route:

Approval per AP 1001 A 9 f G.' 4) vin /("

i?P C4 h 6/g s.v.i.

c.i.

s-i.

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s.v.i.

.i.

odb_

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s e-.,,,

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8 84 Aeoo113:3

i e

FOR USE IN UNIT I ONLY 1004.31 Revision 8 NOTE:

Personnel performiny this portion of the procedure are required to initial eac'. step upon completion and prior to perfoming the next step.

4.b.1 Containment Atraospheric Post Accioent Sarapling System' l

(CATPASS).

4.b.l.1 Contact the Control Room anc request cur R ctor Builcing pressure.

If Reactor Build re exceeds 30 PSIG, samples.shall not be tak

[

~-

4.6.1.2 Before ceeding to the samp s

on, request that sec.ars.

s the oom i::1 =

py; utMay valves CH.V.1, t

anc-V4 if not 1rea shut due to ESFAS actua-Also request h instrument air is available in the Intermedi ing for sampling operations.

NOTE:

If ins t

is not availab e Inter.

i mediata ng, bottled air t be onnected at I

the san tion ayer to y at reducing val

~~

~

'~

ruinebabitab' 4.6.

f ne sampling area prior to s s. ~ rlae sampling by:

1.

g up a continuous air mentew

~

~

in the vicinity of the sample station ano 2. Takiny dose rate readings in the sampling area.

NOTE:

If a sampling system line ruptures, close valves Ch.V-12 and Ch.V-13 and switch valve W-V-10 to the recirc. mode at the rumote sample panel. Notify the :

RAC to have the Control Room close valves CN-V.1, V2, V3, and V4. A rupture may be indicated by an abnomal or unexpected change in flow or pressure.

......... _................ _ ;.. _. g. g...........,..,....,.., _ _

f@

T4 e whec Less 04 Caelmat Ae.a.,*/ d (f.oc.A) he.s f

n. 4, H % r.L. ur W" M" kab M' i

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, b f,.,.

4 l

i w___-

u.

FOR USE IN UNIT I ONLY 1oc 31 Revision 8 I

4.6.1.4 The Radiological Controls Coordinator shall conduct 4 briefing with those personnel directly involved in the sampling evolution. Attachments IV ano V should be used l

to familiarize sampling personnel with the sampling system and sample panel. Heat insulating gloves will be s

a needed for handling the sample flask aft p ing.

7 E * = b

Switch heat tracing "0N" at the 4.6.1.5 ioIIof b w 6 bi1 M s$ cI f.

. N.t. N b k.n:

4.b.1.6 Install the sample flask at the f 1

etween valves l

CH-V.12 CM-V-13 at the s sta on if not already in pl asure that the sola 'on valves attached to le flask (CH-V. 5 a h.Y.37) are open one (1) t nly and tnat valve ll,H-V-36) is shut.

l Il0TE:

Velves Ch.V 4 anc LH.V.36 quarter turn :

ball velves, alves are op n the handle i,

'f on the v igned with the tubing and shut wh handle is at a ang e o the system :

tubin.

following valves:

l 4.6.1.7 If t

ady closed, c1 a

and CM-V.14 (a e

ple station), CM.V.16, V-17.-and CM-V.18-(at-tne instrument / bottled-air-- _.__

station), and CM-V.12 and CM.V.13 (at the remote sample panel).

4.:.1.8 Place valves CM-V-7, V8, anc V10 in the sample mode at l

the remote sample panel.

4.e.1.9 Switen valve CH-V-9 to "t,0CL ShPL" position at the remote

{

sample panel.

i a... I% c-.ut..+,. L,J i.,..,.Q.t Q i.P C C LI

~'

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L i

6R U$iE lNoONI~

l ORLV

~

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i

l l

FOR USE IN UNIT I ONLY

~

1004.31 kevision 6 l

4.6.1.10 If bottleo air is usec, open the valve on the supply l

bottle ano acjust tne reducer (Ch-V.Ses to acnieve 901u0 psig on the regulator outlet guage, then open CN.V.16.

4.6.1.11 " Crack" open valve Ch.V-17 to obtain a reading of 25 to

[

30 psig on PI.997 at the sample station, then imediately shut Ch.V-17.

Then crack open valve CM-obtain a reacing of %5 tu 30 psig on Pl.995 at s

le station, then imediately shut CM.V.18.

4.6.1.12 Record 1 pressure gauge indi ionLAt the sample stat'

995,

, P _996

, Pl.997 4.6.1.13 m utes and again I

pressure gauge indica --- -- -- J

, Pl.997, Pl.955, L, w e4Mo s.dmi.e es ftA%

4.6.1.

If there is as d n pressure o= fI-Mf A, the pressure inte acceptable, f

essure integrity is unacce otify the RAC.

efo[./__/.,_....

_ _....}E :

.. 4._f... _.

N7F e y 3/fioy/s hedt ac g tepfpe

,e tn sy euj

_ _7...._l

. y.. l..p..

_ _ 4.6.1.1 L..ufl,a 4

w.,n. q f.Q

• ,y y

4c L a f Y ancik3, ensure that valves Ch-V.7, V8, and V10 are in the sample mode.

NOTE:

Ch.V.9 may be placed in either " COOL SMPL" or "ISOK SWL" position dependent on whether the RAC desires a sample from the RN-A2 Isokinetic Probe or the Cooler Discharge. Note the position used on sample cata sheet.

FOR USE (N UNIT I ONLY

FOR USE IN UNIT I ONLY 1004.31 -

Revision 8 4.6.1.16 Request, through the RAC, to have the Control Room l

override the EsFAS function of valves CM.V-1, V2, V3 and V4 (if ESFAS is actuated) and open valves Ch-V.1, V2 V3, and V4.

4.6.i.17 Fully open <alve Ch.V.17.

If bottled air is useo, also l

cpen CM-V.16.

4.o.1.18 upen valves CH.V-ll ano Ch.V-14 at the tati on.

4.6.1.19 Switen valves CM-V-12 anc Ch-V.13 to E'

at the remote sample panel.

NOTE:

Val

-.12 and CM.V.

ree positions:

e "Open", anc "Op s".

The "Open

" mode bypasses e

tective pressure ies that normall t

.V.1% eno CM.V.13 n over pressur on. Do not use this position unless ci to do so by this procecure.

4.6.1.20 Ve rt fy........; '

l

.,.. ;; A W.U.n t;; :: 'n:t _y_ v" -d that F1-838 at A.

a flow exists in the the r le panel indi s

em. Flow is when the needle on F

s to the left o i

enter mark.

...$.M Tl9.4 _ _........ ===_v.;_..__............_.........__..;= =_

1. 4EE:

he sample flask and other exposeo metal portions of :

the sample system will be HOT. Heat insulating gloves should be used to handle any exposed metal portion of this system.

4.6.1.21 After 5 minutes, samples may be'crawn from the system by opening the septum valve (LM-V-30) and inserting the tip i

of a syringe through the sept *Jm and withorawing a small volume of Containment atmosphere into the syrin9e.

~

FOR USE (N UNIT I ONLY

FOR USE IN UNIT I ONLY 1004.31.

Revision 8 4.6.1.27 Slowly open valve CM.V-18 to flush all lines with instru-ment /Dottleo air.

NOTE:

Keep valves CM.V.7 and Ch.V.8 in the sample mode until tneir respective sample lines are depressurizac :

to Reactor Building pressure as indicated on Pl.995 and PI.hh7.

4.o.A.2B At tne ccmpletion of a i minute purge ti lo val ve j

Ch-Y-A8 then switch valve CH-V-12 to '

t the remote sarapie panel.

4.6.1.29 Request t the Lontrol Roou ev ves Lh-V.3 ano i

Ch-V. '

these valves

- shu, switch valve Ch.V.6 position at he te sample panel.

4.6.1.

As completion of n tional 2 m.inute purge, close alve CM.i.17.

o o air was used, also close valve CM.V.16 &nd th 5 en the bottle soun:e. Switen s

valve CH b

close" at the te sampie panel.

4.6.1.31 Requ

1. e Control koo k lves CM.V.1 ano CM i

nen these valve re t, swit::n valve CH-V-7 2" position at r e ote sample panel.

-off-heat-tracing at -the y, s M 6x i b d d i

crt; rr,!; cx.. -- - --

4--

--- - - - 4. 6.1. 3 2 --

f L 5.,4 a, skW.

l 4.6.1.33 Shut valves CM-V-il and CM-V-14 at the sample station.

4.0.1.34 The samplets) shoula now be analyzed per the applicable 1990 Chemistry Procedure.

4.6.1.35 Relay the results of the gama analysis to the Racio-logical Assessment Coorcinator to be used in EPIP 1004.7.

FOR USE IN24) NIT I ONLY

~

FOR USE IN UNIT I ONLY

~

1004.31 Revision 8 4.7.3 Open the sample panel and survey the two cartridge l

holders and the lead shield. Enter the contact dose rate for each cartridge holder / lead shield on the data sheet (Att. VIII). S*I**Y b

• Y

P k 4. J c..+ J 1.5,+... t. ne u d a s. I, v t,.. e 44 st.ll.1 biJ r LIJ~ M ~< M ANh&.

= 4..i-4.5 ~+.

NOTE:

Dose rate from channels 1 and/or 2 ay erfere or mask the dose rate from channel is is l

suspected, sampling steps 4.7.

u 4.7.9 should :

be pe ed for all channel nd n a more accurate:

cont se rate determine oving the in artridge hol rs to low background a.

9 4.7.4 flow rate (s) on ed channel (s) on the sample l

data sheet (Att.

I (Flow rate during sampling 4 A m.i h.'-

4A should bejapp y 3000 cc/ min) se the panel.

4.7.5 Depress utton ca the ired

,annel(s). The l

"0FF"

.. Q id go on, the 0 ' ght should go off.

g........................

NOTE:

e 2 and 3 will e

purge cycle before t

9 off.

/

4 4.7.6 ess " PURGE" button on desired channel to remove any noble gases which may have been present,'- t rif r.t

+6e The " sample" light should go off and the " purge" light should go on. The elapsed purge time indicator for channel No.1 should start to increment i# '"* I 1 #5

\\esin env4.

4.7.7 Depress "0FF" button on desired channel after at least of j 7 one (1) minute f

r FOR USE IN oUNIT I ONLY

FOR USE IN UNIT I ONLY

~

100,,31

~

Revision 6 4.7.8 Record elapsed time (in minutes), flow rate (in ec/ min),

for the appropriate channel number on sample data sheet

( Att. VIII).

4.7.9 Open the panel and, remove cartricge holder (s) by l

releasing quick disconnect fittings on sampie line.

NOTE:

Cartridge holder in channel 1 is ene de an 80 lb. lead shield. Shield and ca lder should be remond as one unit, if e, i f the cartridge holder would present ant exposure :

hazard if unshielded.

4.7.10 If a sampling is essa

, insert new silver rtridge (with the I pointed towant the blue O the cartridge) and particulate filter into the cartridge ho r.

4.7.11 Insert cartri r into place wA ensurig sample

~

~

flow i s th par 1:iculate iter Nst (blue end of the fi e er shoulc be o t

).

4.7.12 En r ick disconnect fitt are securely att,tchec n

e panel.

4.7.13 _

te._ cartridge holdart s)_ re_ installed,_ verify _ sample

__l flow rate by depressing sample and purge pump, "0N" button, then depress the channel " SAMPLE" button. Veri fy l

3000 cc/ min flow rate on the applicable flow meter for approximately 5 seconds.

If flow rate is not 3000 cc/ min., adjust flow rate by rotating the knob at the bottom of the flow meter.

Men depress Sample anc Purge Pump "0FF" button.

044_emL. r, L it Ac. &.l v J c g!,-. ! --.i. 9

, N ew -

A,oTD6dd 1,p uiw.%,+g 4.7./4.fA ~~ ws. ! !'r =mkE mu,/,

sf

4. 7. I 6,

8

"*6

-/aO Fr LTS E ins.TJ NTT l O bT.J ~

~

~~

~

I

FOR USE IN UNIT I ONLY

~

1004.31 Revision 6 4.7.14 Wait until all three channels have stopped cycling then depress Sample and Purge Pump " AUT0" button.

4.7.15 Depress "AUT0" button for all three channels, and then depress " RESET" button for all thrse channels. The "AUT0" button light should be on and the LED readouts should read zero. This now places the MAP-pling station back in automatic standby to p pense to RM-A5, b, or 9 low channel alam.

4.7.16 Ensure that the sample and purg ave not been distu al settings are.

nnel 2, sample -

4 e - 36 sec. ; Ch

, sampl e - 4 sec.,

396 sec.).

las=M sb A 84.7.1 Ilw.y y.34. k* e=.

4.8 Po st ent Sampling of Con Vacuum Exhaust, Reactor Build-ing Purge or Auxiliary a ndlir.g Buildi Exhaust using the NRC MAP-5 sampling g(. ns manual mode. N 4.8.1 When d 3 the Radiologi J

sment Coordinator l

ob*

pies by manual ope A s follows:

(Refer to j

'i.;aumnynb VII).

p 4.8.2 4 pie panel is curre operating replace the present filter mecia with new filter media per 4.7.2 through 4.7.12 above, for all dhannels then proceed to l

L*g,, s ~e,n r n i x u a t, u.-

l 4.6.3 jf depress "PISET" on all three channels to clear display.

l 4.8.4 Depress "0N" button f or ptmp.

Pump "0FF" light shoul d go off. Pump " AUT0" lignt should be off. Pump "0N" light sho:1 d go on.

FOR USE IN JN!T I ONLY

6 o

~

4. 7. I *I SgI

-(y u, w;I( b-p A d L

,.W~ K-I

.g :mW.

n M,o cL.-:, +.y p.

L...

4. 7. i y rt..I.,fL vs.lf, G A p.

.- /y,4 A'L ft J :.I.f -( As,,,

+ c J.

6~- f. L w J i N ov.7 O

o@

9P o+

v4 y

f

O

=

FOR USE IN UNlT I ONLY 1004.n Revision 6 4.8.5 Depress channel " sal @LE" button on the desired channel control.

" SAMPLE" light should go on.

Elapsed time indicator should begin count for that channel. Record the flow rate for the appropriate channel (s) on the sample data sheet ( Att. VIII)*k AS -rI* Ib N I a=v/4.-

, A. A + h,.

4.8.6 When desired sample time is reache dept b e " PURGE" l

button, the purge light should go on.

1 g Channel r

nting in 1, elapsed time display should beg n seconds. Purge all channel s fo t

st one (1) minute.

4.8.7 To s operation, depress FF" button for the d

nnel.

" PURGE" 1 Sh ould go out.

"0FF"

. oul d go on.

+

4.8.8 dhen sampling is c.

, depress pump "0FF" button.

l Pump "0N" li g r'

go off. Pump r" 11ght should go on.

/

4.8.9 Record 1 ample time (i on the sample l

data

( Att VIII). Open el and survey the two

\\

.i e holders and s hield. Re:orti the n

t dose rate for ea rtridge holder / lead shield on the sample data sheet ( Att. VIII). Inform the Radio-logical Assessment Coordinrtor of the survey results before proceeding.

4.8.10 Remove cartridge holder (s) by releasing quick disconnect fittings on sample line.

I 1

FOR USE IN UNIT I ONLY

~

co' FOR USE IN UNIT I ONLY 1004.31 Revision 8 4.8.11 If additional sampling is necessary, insert new silver zeolite cartridge (with the arrow pointed towaro the blue i

half of the cartridge holder) and particulate filter into the cartridge holder.

4.8.12 Insert cartridge holder into place while ensuring sample flow is through the particulate filter fi

( ue end of the cartridge holder should be on top 4.8.13 Ensure quick disconnect fittings a ly attached l

and clos panel.

4.8.14 Dep

" button on d sirad annels to clear l

fe.s a.

a d time. Allfdisp hould read zero.

4.8.15 that the sample urge times have not been e. ngs are:

Channel 2, sample - 4 disturbed.

(No J

se.c-, purg e -

t CliannetW s

- 4 sec., purge

- 396 sec 4.8.16 For ad t anual samplin back te Step 4.8. A, i

4 4.8.17 Fo' o -f ps 4.7.12 thrw '

to pla:e sampling l

't back in kytoma y af ter manual sampli%.

._. 4.8.18 _

p euanalyses will be onted in.accordance with the applicable 199U Chemistry procedures.

4.8.19 Relay the results of the gama analysis to the Radio-l logical Assessment Coordinator to be used in EPIP 1004.7.

5. 0 FINAL CONDITIONS l

5.1 All samples taken after release has been tenninated.

5.2 All monitoring teams ordered to return to base.

5.3 All samples given to Radiological Controls for analysis.

l

~

FOR USE liVUNIT I ONLY 1

e*

'O ATTACHMENT V TCHEMATIC 0F CATPASS REMOTE SAMPLE PANEL CM-V18 n

n l

J V

b CM-V7 V1

/

TO lISOK.

DC I

fimuty.g PROBE CM-V9

'A 4's.

lRM-lWNml TI 992 goK COOL I

j h,-

4 W b f

b M RISMPLJ V_

n

(

f/ff.

v u'- d %g(rHEAT MFk0d RACING L

u v

v 3

\\

j E OPEN/BYP OPEN CL E OPEN/EYP p

_____-....,4, p _ ___

f SAP 7LE

-- f

@ s m u

>mi be

>-V12 CM CM-V13 N,,,/

24.0

... -