ML20083H770

Public Version of Rev 3 to Emergency Plan Implementing Procedure EPIP-4.23, Post-Accident Sampling of Reactor Coolant

ML20083H770
Person / Time
Site:	Surry
Issue date:	12/08/1983
From:	Rentz F, Runner W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML18141A292	List: ML18141A291 ML20083H770
References
711, EPIP-4.23-01, EPIP-4.23-1, NUDOCS 8401050025
Download: ML20083H770 (18)

Text

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VIRGINIA ELECTRIC AND POWER COMPANY REVISIONS TO SURRY POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURES Enclosed are recently revised pages to the Surry Power Station Emergency Plan Implementing Procedures.

Please take the following actions in order to keep ycur manual updated with the most recent revisions.,

EPIP-4.23 POST ACCIDENT SAMPLING OF REACTOR COOLANT Remove and Destroy Enter Pages 1 of 14 through Page 1 of 16 through 14 of 14 of the 16 of 16 of the procedure disregarding procedure disregarding Dated 12-08-83 8401050025 831228 a

gDRADOCK 05000280 PDR LM1-031/jaj X@(

c noenemo VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCEDURE TITLE REVISION 03 EPIP-4.23 POST ACCIDENT S/MPLING OF REACTOR COOLANT PAGE (With 1 Attachment) 1 of 16 PURPOSE l.

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

USER Chemistry Team Leader AND Chemistry Team Member.

ENTRY CONDITIONS k

1.

Entry directed by Emergency Technical Director 3

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: 09-23-83 REV. 03 PAGE(S): Pages 1 of 16 through 16 of 16 DATE: DEC 8 1083 REV.

PAGE(S):

DATE:

REV.

PAGE(S):

DATE:

REV.

PAGE(S):

DATE:

APPROVAL R 0 CEO APPROVED CA TE l

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DEO I I!IO3 c

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QC REVIEW CHAIRMANSTA T10N NUCLEARSAFETY h

AND OPERA TING COMMITTEE l

ns.orestz:o NUMBER PROCEDURE TITLE REVISION 03

)

EPIP-4.23 FOST ACCIDENT SAMPLING OF REACTOR COOLANT PAGE (With 1 Attachment) 2 of 16 STEP ACTION /EXPECTEO RESPONSE RESPONSEN0TOBTAINED 1.

INITIATE PROCEDURE:

a)

By:

Late:

Time:

NOTE: Only one reactor coolant sample may be obtatued f rom this system.

2.

VERIFY STATION SYSTEMS:

a) Systems Operable a) IF NOT operable, request

('..l, operations assistance to

1) Station Service Electrical insure sys' tem operability System per OP-26_

2) Component Coolant System per OP,5_1,

3) Compressed Air Service Systes per OP-6

4) Ventilation System per OP-H

5) Rad.ation Monitoring System per OP-566 l

3.

DESIGNATE SAMPLING PARTY:

a) Chemistry team 1saders uD b) Chemistry team members l

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No. stssvsto NUMBER PROCEDURE TITLE ret'ISION

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03 EPIP-4.23 POST ACCIDENT SAMPLING OF REACTOR COOLANT p,

(With 1 Attaci. ment) 3 of 16 STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED 4

VERIFY RWP:

a) RWP isaued a) IF NOT issued, request initiation of RWP.

5.

OBTAIN REQUIRED EQUIPhENT:

a) 2, adjustable wrenches b) Extension wrench c) Come-A-Long or equivalent d) 5 gallon poly bottle I

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 I

1 j

i m.stes72 o NUMBER PROCEDURE TITLE REVISION 03 EPIP-4.23 POST ACCIDENT SAMPLING OF REACTOR COOLANT PAGE (With 1 Attachment) 4 of 16

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STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED 8.

(CONTINUED) d) Review cau: ions

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 btation Emergency Maaager sampling party is being dispatched y

Notify Shift Sopervisor sampling party is being dispatched 10.

DISPATCH SAMPLE TEAM:

a) Insure sample party has a copy of this procedure NOTE:

Refer to attachment 1 for system arrangement 11.

PROCEED TO PRIMARY SAMPLE ROOM:

a) Monitor radiation levels b) Follow preplanned routes c) Leave rope at Aux. Bldg.

entry Door.

Nn.97847210 NUMBER PROCEDURE TITLE REVISION 03 EPIP-4.23 POST ACCIDENT SAMPLING OF REACTOR COOLANT PAGE (With 1 Attachment) 5 of 16 STEP ACTION / EXPECTED REhuMSE RESPONSE NOT08TAINEO

~

12.

VERIFY SAMPLE COLLECTION CYLINDER CONNECTED:

a) Cylinder - IN SHIELDED a) IF NOT, ple.ce in " PIG" upygn b) Quick Disconnect - CONNECTLD b) JJ 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:

+

,b 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 4

checklist on wall is sampling taak updated AFD Add 835 al of DI

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water through funnel AND GO TO STEP 15 15.

VERIFY NITROGEN BOTTLE PRESSURE:

a) Open isolation valve 1-SS-241 on Nitrogen Bottle

+

.Pos 97867210 NUMBER PROCE00RE TITLE REVISION 03 EPIP-4.23 POST ACCIDENT SAMPLING OF REACTOR COJLANT PAGE (With 1 Attachment) 6 of 16 STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED 15.

(CONTINUED) b) Verify Nitrogen Bottle b) IF NOT, leave area pressure GREATER THAN 200 PSIG AND initiate Nitrogen Bottle replacement

.A_ND_

GO TO step 16 16.

VERIFY VALVE LINE UP:

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(j a) Insure following valves - CLOSED 1-SS-229 1-SS-230 1-SS-233 L

1-SS-236 1-SS-238 1-SS-239 1-SS-240 1-SS-241 1-SS-242

~-

1-SS-236 valve "K"

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1-SS-236 valve "L" b) Insura following valve - C?EN 1-SS-231 17.

VENT AND DRAIN HOLDING TANK - TK1, a) Remove vent plug on TKJ, b) Insure following valves - CLOSED 1-SS-234 1-SS-235 i

4

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l ND.97487210 NUMBER PROCEDURE TITLE REVISION 03 EPIP-4.23 POST ACCIDENT SAMPLING OF REACTOR COOLANT PAGE (With 1 Attachment) 7 of 16 STEP ACTION / EXPECTED RESPONSE RESPONSE NOTORTAINED 17.

(CONTINUED) c) Attach tygon tubing to 1-SS-234 MtD Attach opposite end to 5 gallon poly bottle d) Insure following valves - OPEN 1-SS-234 1-SS-235 e) Drain rutil fl a to 5 e) IF No flow detected h

gallcn poly bottle stops GO TO Step 3 18.

ISOLATE HOLDING TANK:

a) Insure following valvas - CLOSED 1-S5-235 1-55-234 19.

DETERMINE UNIT TO BE SAMPLED:

a) IF UNIT 1 to be sampled a) IF UNIT 2 to be sampled GO TO NOTE prior to Step p GO TO NOTE prior to Step 2l i

NOTE:

Step g is for sampling Unit 1.

20.

SAMPLE UNIT 1:

a) Insure control room valves - CLOSED TV-SS-106A TV-SS-106B l

l l

l l

No. 9F887210 NUMBER PROCEDURE TITLE REVISION 03 EPIP-4.23 POST ACCIDENT SAMPLING OF REACTOR COOLANT PAGE (With 1 Attachment) 8 of 16 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT08TAlhE0 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 coolaat will commence when next steps are performed.

f) Observe sample line pressure gage PI-SS-200 g) Carefully open folicwing valve 1-SS-229 AND AT 20 PSIG on PI-SS-200 insW e following valve - CLOSED

/

1-SS-229 s-e l

. - _ -.. _ _ ~

No. 97887210 NUMBER PROCEDURE TITLE REVISION 03 EPIP-4.23 POST ACCIDENT SAMPLING OF REACTOR COOLANT PAGE (With 1 Attachment) 9 of 16 STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED 20.

(CONTINUED) h) Insure following valve - CLOSED 1-SS-233 i) Insure following valves - OPEN 1-SS-236 valve "1" 1-SS-236 valve "J" j) Observe sample pressure Sage 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

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NOTE:

The following step is for sampling UNIT 2 21.

SAMPLE UNIT 2:

a) Insure control room valves - CLOSED TV-SS-206A TV-SS-206B C

Poe. 97 887210 NUMBER PROCEDURE TITLE REVISION 03 EPIP-4.23 POST ACCIDENT SAMPLING OF REACTOR COOLANT PAGE (With 1 Attachment) 10 of 16 STEP ACTION / EXPECTED RESPONSE RESPONSENOT OBTAINED 21.

(CONTINUED) b) Insure following valve - CLOSED 2-SS-240 c) Insure UNIT 2 sample line trip valve (solenoid valve - back of sample room) -

OPEN HCV-SS-201D d) Insure following valve - OPEN 1-SS-233

(

e) Insure control room trip valves - OPEN TV-SS-206A

,TV-SS-206B CAUTION: Flow of high activity reactor coolant will commence when next steps are perfomed.

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

l lv 1

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f...oresiano NUMBER PROCEDURE TITLE REVISION 03 EPIP-4.23 POST ACCIDENT SAMPLING OF REACTOR COOLANT PAGE (With 1 Attachment) 11 of 16 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 21.

(CONTINUED) g) Carefully open following valve 1-SS-230 AND AT 20 PSIG on PI-SS-200 insure following valve - CLOSED 1-SS-230 h) Insure following valve - CLOSED 1-$5-233

['.

1) Insure following valves - OPEN 1-SS-236 valve "1" 1-SS-236 valve "J" j) Obc.erve sample pressure gage PI-SS-200 k) Cycle following valve 1-SS-230

$E AT 100 PSIG on PI-SS-200 insure following valve - CLOSED 1-SS-230 22.

ISOLATE AND TRANSFER CALIBRATED SAMPLE:

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

']

1-SS-236 valve "J"

.N3.9744721s NUMBER PROCEDURE TITLE REVISION 03 EPIP-4.23 POST ACCIDENT SAMPLING OF REACTOR CCOLANT PAGE (With 1 Actschment) 12 of 16 ACTION! EXPECTED RESPONSE RESPONSENOTOBTAINEO STEP 22.

(CONTINUED) b) Insure following valves - OPEN 1-SS-236 valve "K" 1-SS-236 valve "L" c) Verify valve 1-SS-238 - OPEN until pressure on sample bottle is appx. 50,PSIG AND Wait appx. one minute to complete transfer.

b d) Open 1-SS-241 until ptassure on regulator is approx. 50,psig 0

e) Insure following valves - CLOSED 1-SS-238 1-SS-236 valve "K" 1-SS-236 valve "L" 23.

DISCONNECT SP2LE CYLINDER:

~

a) Use adjustable wrench or extension wrench if HP determines it is necessary b) Disconnect quick disconnect c) Lower lid onto sample " pig" 24.

SURVEY SAMPLE PIG:

a) Survey sample " pig" to determine rad levels and a.

hot spot locations u

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. No. 97887210 NUMBER PROCEDUME TITLE REVISION 03 EPIP-4.23 POST ACCIDENT SAMPLING OF REACTOR COOLANT FACE (With 1 Attachment) 13 of 16 STEP ACTIO!UEXPECTED RESPONSE RESPONSENOTOBTAINED t

23.

TRANSPORT PIT:

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a) Unlock wheel brakes b) Use preplanned exit route c) Avoid hot spots on pig d) Roll sample pig to Aux. Bldg.

exit door CAUTION: The sample pig is extremely heavy and may present a hazard if allowed to roll down the ramp un-(']

restrained. Use caution in lowering.

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26.

LOWER PIG DOWN RAMP:

a) Use'come-a-long or equivalent to lower sample pig down ramp (

27.

TRANSPORT PIG TO HOT LAB:

t a) holl. pig to Cheaistry Hot Lab b)

<? lace shielded sapple pig in corner by the A.A.

28.

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

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No.97887210 NUMBER PROCED')RE TITLE REVISION 03 EPIP-4.23 POST ACCIDENT SAMPLING OF REACTOR COOLANT RAGE (With 1 Attachment) 14 of 16 STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED 29.

HAVE SAMPLE TRIP VALVES SHUT:

a) Notify Shift Supervisor that sampling completed b) E sampling Unit 1. 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.

VERIFY RWP:

',,7 a) kequest initiation of RVP to dilute sample b) Dress out IAW RWP i

'e)

Observe precautions and A

limitations noted in RWP 32.

VENT SAMPLE BOMB:

a) Raise lid covering sample bomb to highest' position

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o b) Ensure suction through AA vent N

c) Attach vent hose to AA, vent l

s d) Attach vent hose to sample v ' '-

bomb

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seo.s7es7:10 NUMBER PROCEDURE TITLE REVISION 03 EPIP-4.23 POST ACCIDENT SAMPLING OF REACTOR COOLANT PAGE (With 1 Attachment) 15 of 16 STEP ACTIONMXPECTED RESPONSE RESPONSE NOTOBTAINED 32.

(CONTINUED) e) Open sample bomb valve to vent pressure to hood f) Remove vent hose from sample.

bomb 33.

REMOVE SAMPLE FROM SAMPLE B0MB:

a) Attach appx. 6" micro-bore tubing to syringe needle b) Carefully insert tubing

(

into sample bomb and withdraw 1 ml of sample c) Expel 1 mi sample into marinelli beaker and mix well with 999 als DI water 34.

SAMPLE ANALYSIS:

a) Label sample beaker as to:

PASS sample, date, time of

~

sample, final dilution, actual mis sample used l

b) Transport diluted sample to HP count room c) Have HP count sample c)

IF, sample will not count, consider initiation of EPIP-4.26, High Activity g le Analysis, upon tera-ination of procedure.

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. No. 97 887210

=

NUMBER PROCEDURE TITLE REVISION 03 EPIP-4.23 POST ACCIDENI SAMPLING OF REACTOR COOLANT PAGE (With 1 Attachment) 16 of 16 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT08TAINEC 35.

TERMINATE EPIP-4.23:

a) COMPLETED BY:

TIME:

l BY:

b) Forward completed EPIP-4.23 and other applicable records to secretary SNSOC

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.____.__m

VIRGINIA EI.ncrnIc ann Powna COMPANY Rrenxonn,VrnorarA 20061 W.L.StuwAmT y,g' [*,," * ' " * ",

December 14, 1983 V

Mr. James P. O'Reilly Serial No. 711 Regional Administrator N0/ REB /jmj :LM1-031 U.S. Nuclear Regulatory Commission Docket Nos. 50-280 Region II 50-281 101 Marietta Street. Suite 2900 License Nos. DPR-32 Atlanta, Georgia 30303 DPR-37

Dear Mr. O'Reilly:

a REVISIONS TO SURRY POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURES Pursvant to 10CFR 50 Appendix E, paragraph 50.54(q), revisions to the Surry Power Ststion Emergency Plan Implementing Procedures, numbers, and subjects as listed on enclosures are submitted.

neerely, k4 W. L. Stewart Enclosures cc:

2) w/o Enclosures cc:

Mr. Steven A. Varga. Chief Operating Reactors Eranch No. 1 Mr. D. J. Burke - (NRC - Surry)

K Od Il t

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