ML20039B408

Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures 2904.2 Re Magnitude of Release for Unit 2 & 1903.24 Re Oil Spill Prevention Control & Countermeasure Plan

ML20039B408
Person / Time
Site:	Arkansas Nuclear
Issue date:	03/26/1981
From:	Ohanlon J ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML20039B398	List: ML20039B404 ML20039B408
References
PROC-810326, NUDOCS 8112220677
Download: ML20039B408 (54)

Text

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.,._ _ . ar a Arkansas Nuclear One MAGNITUDE OF RELEASE PROCEDURE FOR'.' 1000 CC A q.,g .. MAGNITUDE OF RELEASE - UNIT 2 g yyC 2904.02 REV. 2

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W}my' tv RECORD OF CHANGES AND REVISIONS PAGE REVISION CHANGE PAGE PEVISION CHANGE PAGE REVIS4CN CHANGE 1 1 20 0 2 1 21 0 3 1 22 0 4 0 23 0 5 1 24 0 6 1 25 0 7 0 8 0 9 1 r 10 0 11 1 12 2 13 2 14 2 15 1 16 1 17 1

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APPROV L DATE 8112220677 811215  !

PDR ADOCK 05000313 /

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PLANT M ANUAL SECTION: PROCEDUREN/ORK PLAN TITLE: NO:

' , MAGNITUDE OF RELEASE ppocrmmr MAcNTTimE OF RFT F ASE - UNIT 2 2904.02 L

(~) M PAGE 1 of 25 ARKANSAS NUCLEAR ONE _aevisioN 1 oATe a/13/81 CHANGE DATE 1.0 PURPOSE The purpose of this procedure is to provide an initial estimate of the radio-logical conditions at .the ANO Exclusion Area Boundary, provide information to determine the Emergency Action Level, define the of fsite area (s) poten-tially affected by an airborne radiological release, provide an estimate of the whole body and child thyroid dose rates and refine projections based on available field monitoring data.

2.0 SCOPE 2.1 This procedure is applicable to airborne radioactive releases from ANO, Unit Two as indicated by normal ventilation system stack monitors; if the monitors are off scale, refer to 1904.03, " Auxiliary Building Ventilation Exhaust Emergency Radiation Monitor".

2.2 This procedure does not take into account effects caused by terrain and precipitation.

3.0 REFERENCES

3.1 References Used in Procedure Preparation:

() 3.1.1 Arkansas Nuclear One Emergency Plan 3.1.2 " Manual for Protective Actions, Appendix D", Environmental Protection Agency .

3.1.3 " Workbook of Atmospheric Dispersion Estimates", U.S. Depart-ment of Health, Education and Welfare 3.1.4 Memorandum Number CL-1460 (By A. L. Smith) 3.2 References Used in Conjunction with this Procedure:

3.2.1 1602.38, " Field Test for Iodine 131"

- 3.2.2 1903.10, "Emeigency Action Level Response" 3.2.3 1903.43, " Duties.of the Emergency Radiation Team" 3.2.4 1904.03, " Auxiliary Buildin'g Ventilation Exhaust Emergency Radiation Monitor"

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3.3 Related ANO

References:

3.3.1 1904.02, " Magni _tude ,of' Release - Unit 1" 0u./

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PLANT M ANUAL SECTION: PROCEDUREN/ORK PLAN TITLE: NO:

MAGNITUDE OF RELEASE noncemme MAGNYTFDF OF RFTTASE - INIT 2 2904.02 O M __PA G E 2 of 25 G ARKANSAS NUCLEAR ONE fevisioN i oATE 3/ta/8t CHANGE DATE 4.0 DEFINITIONS 4.1 09 (sigma theta) - The standard deviation of the net change of the horizontal wind direction 4.2 at (delta t) - The vertical temperature differential between the upper and lower temperature sensors on the meterological tower (in degrees centigrade).

4.3 X/Q - The ratio of the concentration of radioactive material (at a specific location) and the release rate (at the origin) in units of pCi/cc/Ci/sec.

5.0 RESPONSIBILITIES 5.1 The Shift Operations Supervisor is the Duty Emergency Coordinator until relieved.

5.2 The Shift Operations Supervisor is responsible for determining if an unplanned gaseous release to the environment is indicated by symptoms such as high stack monitor readings, area radiation monitor alarms or other indications.

s j 5.3 The Duty Emergency Coordinator, or his designee, is responsible for performing the magnitude of release calculations.

5.4 The Duty Emergency Coordinator is responsible for notifying appro- .

priate groups per 1903.10, " Emergency Action Level Response".

5.5 The Offsite Radiological Monitoring Section of the Emergency Radia-tion Team is responsible for determining offsite radiological hazards per 1903.43, " Duties of the Emergency Radiation Team".

6.0 LIMITS AND PRECAUTIONS l

! 6.1 This procedure provides an initial projection of the radiological conditions; field monitoring is necessary to determine the actual

_ conditions.

! 6.2 Conversion factors which are provided to establish the child thyroid

iodine dose rate are based on design basis accidents and should be l considered less reliable than the calculated whole body dose rate.

l 6.3 Actual terrain and weather conditions will generally limit the ac-

! curacy of the projected doses at a specific location.

6.4 The diffusion overlays used in this procedure represent long-te rm

_, average conditions.

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PLANT MANUAL SECTION: PROCEDURE /tfdORK PLAN TITLE:

"" NO:

tiAGNITUDE OF RELEASE J

b PRnt'FDIrRF MAGNITUDE OF RELEASE - UNIT 2 2904.02 3 ~

naad- ARKANSAS NUCLEAR ONE PAGE aEvisioN -

3 ot 25 t oAre 3/13/81 CHANGE DATE

. 7.0 DETERMINATION OF EXISTING METER 0 LOGICAL CONDITIONS AND THE GASEOUS RELEASE RATE 7.1 Etcord the current date and time in Lines 1 and 2 respectively of Form 2904.02A. If onsite meterological data is unavailable, enter

'.'OOS" (Out of Service) in the appropriate space.

.< 7.2 Record,the a0 from recorder AAR 9300 on Form 2904.02A, Line 3. If 00 y ,

is not available, record the At from recorder AAR 9300 and note appro-

, priately.

s .

7 .3 Reedrd the-wind speed from recorder WSR 9300 on Form 2904.02A,.Line 4.

\ x s 7.4 . Record thh pt'evailing wind direction from recorder WDR 9300 on Form 2904.02A, Line 5.

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7.5 Record the' net' counts per minute and the corresponding system flow rates for each of the following process monitors that are in service 5' on Form 2904.02A. For each system which is not in operation, enter

. .\ "00S" (Out cf Service) in Column 1.

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7.5.1 . Auxiliary Building Extension ( j ) Lines

.m ,  !

6 and 7, respectively.

7.5.2 Containment Purge ( /,' Lines 8 and 9

[, respectively, \

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7.5.3 Fuel liandling Area \

respecIively. [, Lines 10and11 ,

r- 7.5.4 Rad Waste Area  ; Lines 12 and 13 re-spective!.y. \

\ 7.5.5 Hydrogen, Purge \7 Lines 14 and 15 respectively. .

7.5.6 Hydrog[dPurge  !, Lines 16 and 17 respedtively. M 7.5.7 Penetration Room Lines 18 and 19, respectively.

7.5.8 Penetration Room Lines 20 and 21, respectively.

7.6 Make the following determinations:

7.6.1 If this is the initial calculation, proceed to Section 8.0 (Data Conversion).

t

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7.6.2 Compare the present readings to the values on which the

, , . latest projections have been made.

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. A. If 'the values have not deviated f rom the most recently

,g,i -

cbc_ked column on Form 2904.02A by more than the fol-

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4 Icwing list, return to Section 7.0. New data should be x taken.as specified by the Duty Emergency Coordinator.

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PLANT M ANUAL SECTION: I PROCEDURE / WORK PLAN TITLE: NO:

MAGNITUDE OF RELEASE PROCEDURE MAGNITUDE OF RELEASE - UNIT 2 2904.02 PAGE 5 of 25 O'- ARKANSAS NUCLEAR ONE aevision CHANGE i oarE 3/i,/ai DATE 10.0 PLLME DEFINITION NOTE: The attachments contained in this procedure are provided for ILLUSTRATION ONLY. The scaled overlays and maps necessary to do the actual calculations with are located in the follcwing emergency kits:

a. Control Room Kit

b. Onsite Technical Support Center Kit

c. Emergency Control Center Kit 10.1 Select the overlay (Attachmente 1-7) which corresponds to the exist-ing atmospheric stability category (Form 2904.02B, Line 1.2).

10.2 Place the selected overlay on the ANO area map (Attachment 8) with the origin directly over the ANO site center and align plume center-line with the downwind direction.

10.3 Complete Form 2904.02F to calculate the Plume Boundary, Whole Body Dose Rate and Child Thyroid Dose Rate at selected downwind distances.

10.3.1 Locate the plume boundary (from Form 2904.02F Line 2) on the overlay corresponding to the Atmospheric Stability Ca tego ry.

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10.3.2 Any sectors which are contained (or partially contained) within the plume boundary line should be designated as an affected area.

10.3.3 The maximum downwind extent of the affected area may also be determined by the extent of the plume boundary.

10.3.4 If it is necessary to calculate plume arrival time (in hours) for a specific location, divide the distance (in miles) from the plant to the location by the windspeed (in mph).

10.4 Summarize the projected Whole Body Dose Rate, Child Thyroid Dose Rate, and Affected Sectors at selected downwind distances on Form 2904.02E.

11.0 NOTIFICATIONS 11.1 Provide radiological release intormation to appropriate groups per 1903.10, " Emergency Action Level Response" and establish a follow-up

( schedule for updating release information.

1 l 11.2 The Emergency Radiation Team may be dispatched to obtain field radio-I logical data at the discretion of the Duty Emergency Coordinator /

Recovery Manager. They shall be dispatched upon declaration of a Site Emergency. If the Emergency Radiation Team is dispatched, re-fer to Section 12.0.

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PLANT M ANU At SECTION: PROCEDURE / WORK PLAN TITLE' N O-MAGNITUDE OF RELEAS E PROCEDURE MAGNITUDE OF RELEASE - UNIT 2 2904.02

_PAGE 6 of 25 O

'd ARKANSAS NUCLEAR ONE aEvisioN i oATE 3/12/81 CHANGE DATE 11.3 Return to Section 7.0. New data should be taken as specified by the Duty Emergency Coordinator / Recovery Manager.

NOTE: This section may be used during periods that monitoring teams have been dispatched, to improve dose projections based upon the comparison of projected and measured whole body dose rates at field locations on the plume centerline. This section is designed to complement rather than replace the ongoing dose projections of Sections 7.0 through 10.0.

12.0 VERIFICATION OF PROJECTED DOSE RATES BY FIELD MEASUREMENT 12.1 Based on vind direction, the Duty Emergency Coordinator / Recovery Mina-ger should dispatch offsite radiological monitoring teams to sample the plume at specified locations. Preselected survey points in each sector and zone are shown on the area map (Attachment 8).

12.2 The radiation survey at each location should include a direct exposure rate measurement (mR/hr) and an air sample to determine iodine concen-tration (pCi/cc). As the survey teams approach the assigned survey location, continuous radiation measurements should be taken to identi-fy the location of the highest radiation level. As survey results are obtained, the radiological monitoring team should report the results to

() the Duty Emergency Coordinator / Recovery Manager and proceed as directed.

12.3 Determination of Iodine Dose Factor by Field Measurement.

12.3.1 Iodine concentration (pCi/cc) Whole Body Dose Rate (mR/hr) shall be measured in the field and the results reported per 1602.38 " Field Test for Iodine 131".

12.3.2 Record on Form 2904.02G, the Field Location in Column 1, ,

the Iodine Concentration in Column 2 and Whole Body Dose Rate in Column 3.

12.3.3 Calculate the Iodine Dose Factor for each field location in Column 4. (The most recent calculated Iodine Dose Fac-tor may be used for future Child Thyroid Dose Projections.)

12.4 Determination of Whole Body Overlay Scale Factor 12.4.1 Scale factors may be determined to refine future whole body dose estimates based upon field measurements. Because the dose rate may change rapidly with distance from the plume centerline, scale factors should be based only upon a comparison of a projected plume centerline dose rate with the highest measured field dose rate determined by traversing the plume at the projected downwind distance. This ensures

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that the projected plume centerline dose rate is compared with the actual plume centerline dose rate.

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PLANT M ANU AL SECTION: PROCEDURElWORK PLAN TITLE- NO:

MAGNITUDE OF RELEASE I PROFFDImr MAGNITUDE OF RELEASE - UNIT 2 2904.02 m

h PAGE 9 ot 25 (3

ARKANSAS NUCLEAR ONE EaEvision i oATE 3/13/81 CHANGE DATE yjlT ARKANSAS POWER & LIGHT COMPANY FmI '

mamsC Arkansas Nuclear One N evre-ec- en.m74ense ei y soy l FOS" '*0- sons on REv. # 1 PC

• PAGE 2 of 2 READING

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LINE ITEM 1 2 3 4 5 20 PEXETRATION ROOM (2RE-8846-2) CPM 21

' fENETRATICN ROOM FLOV PATE (CFM) 22 i "A" STEAM HEADER, mR/hr 23 l NO. SAFETIES OPEN (!!EADER "A") l

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24 "B" STEAM HEADER, mR/hr l

O 25 26 NO. SAFITIES CPEN (EEACER "B")

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PLANT M ANUAL SECTION: PROCEDUFtEAVORK PLAN TITLE:

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MAGNITUDE OF RELEASE b

J l ppyrrtyr L h MAcNTTimF OF RFTFAM - UNIT 2 2904.02 PAGE 11 of 25 3 em"4a2--

ARKANSAS NUCLEAR ONE laEvismN I oats 3mm CHANGE DATE s

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ARKANSAS POWER & LIGHT COMPANY manum Arkansas Nuclear One ME ,w ,m ,,t,,cr , m vn,v,y,,7 l rom e ?q _n?c REV. t1 FC #

PART 1 TOTAL GASE0l:S RELEASE RATE

. Column 1 Column 2 Column 3 Column 4 Monttor Ventilation Monttor Q System Name Reading System Flow

& Monitor Calibration (CUS)

(cpm) Rate (CFM) Conversion Ites Number Factor 1 .[ Aux. Bldg.~_

Ext. 1.9E-9 2 (ContairmentPurge m

i XXX 3

a f-lFueTHaiE11ing Area 5.0E-10

,: N A, 4

l *Rad wme Area 3.9E-10

, _ *% s,-ww x 5 fliydrogen ' Purge i 3.6E-10

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6 tifydrogen Purge 8.1E-10

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7 7 Penetration Room 750 5.7E-10 a iPenetration Roos 750 3.9E-10 9 Aux. atog.' Vent. XXX XXX XXX Exhaust Emer.

Rad. Monitor

• 10 "A" Steam Safeties ** XXX XXX XXX 11 "B" Steam Sa feties ** XXX XXX XXX 12 XXX ~

l Total XXX XXX j PART 2 1.

Determination of Caseous Release Rate (Q ) =

Column 1 x Column 2 x Column 3 8

2. Total Gaseous Release Rato, Q

., ,e .o gas = sum of values in Column 4 3.* 6 m%%. -e.

Aux. Bldg. Vent. Exhaust Emergency Radiation Monitor Release Rate Data f rom Form 1904.038, Column 9.

4.** net mR/br x No. Steam Safeties Open x 0.0341 Ci/sec =

C1/sec (Qgas) OR mR/hr net mR/hr x lb/hr Steam Exhausted x 2.26E-8 =

C1/sec (Qgas).

Performed by: /

INITIAL IIPI Reviewed by:

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• e PLANT M ANU AL SECTION: PROCEDUREiWORK PLAN TITLE: $ NO-MAGNITL'DE OF RELEASE ,

PROCEDURE MAGNITITE OF RELEASE - INIT 2" g PAGE 12 of b , 2004.02 U ARKANSAS NUCLEAR ONE aevision 2 D*TE ,/2sest CHANGE DATE

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pT ARKANSAS POWER & LIGHT COMPANY FeI amm i Arkansas Nuclear One W rvre-evev .<, ray v rt r e nevrew n37 py l rcaw No. yo, ,, g REV. # 2 Pt tage L ut 1 Column A Column B CALCULATICN CF DCSE RATE A.% CAL AVERAGE EXISTING

& MPC AT THE EXCLUSION CONDITIONS CCNDITIONS AREA BCCNDARY (0.65 MILES)

Line Ca t e eo ry: N/A Units Category-1.0 Enter the Total Gaseous Release Rate (Q ) (Froa 2904.02C) in Columns #1'& B.

Ci/Sec 2.0 Select and Enter' the khole Body

• dose factor from the following list shtch corresponds to the existing Atmospheric Stability Category (f rc:a 290!. 028) in Column B. 1.26 mR/hr Atmospberic

• fg Stability V Cateeory k'B Dose Factor A 1.83 B 9.3 C 19.9 D 42.5 E 64.1 F 92.3 G 153 3.0 Calculate the l'ncorrected khole Body Dose Rate at the Exclusion Area Boundary (Line 1.0 X Line 2.0) and enter the products in Column A and B, respectively, mR/hr 4.0 Enter the existing windspeed i

(from 2904.02B) in Column B. XXXXXXXXX7.X (mph) 5.0 Correct the bhole Body Dose Rate for windspeed (Line 3B + Line 48) and enter results in Column B. XXXXXXXXXXX mR/hr

• l 6.0 Enter the current scale factor. XXXXXXXXXXX (NCNE) 6.1 If field data is avatlable, enter the most recent entry f rcm for:n 2904.02G (Colu.,ui 7) in Column 8.

6.2 If field data is not avail-able, enter "1" in Column B.

1 1

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PLANT MANUAL SECTION: PROCEDURE / WORK PLAN TITLE: NO:

MAGNITUDE OF RELEASE PROCEDFRE MAGNITI'DE OF RELEASE - UNIT 2 2004.02 PAGE 13 of 25

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v ARKANSAS NUCLEAR ONE aevision CHANGE 2 oarE 4/2s/si DATE i

ARKANSAS POWER & LIGHT COMPANY

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rage i ot J Column A Column B ANNUAL AVERAGE EXISTING Conditions l'a i t s Conditions 7.0 Correct the Wole Body Dose Rate for the current scale factor (Line 5 X Line 6) and enter re-sults in Column B. Transfer mR/br(whole value from Line 3A to Line 7A. body) 8.0 Select the iodine dose factor. mR/hr(thyroid)

., mR/hr twbole body) 8.1 If field data is available, enter the most recent entry from Form 2904.02G, (Column 4),

in Columns A and B.

(A)

U 8.2 If field data is not avail-able, select and enter the ap-prcpriate dose factor f rom the following list based on the current plant conditions in Columns A and B.

Plant Condition Iodine Dose Factor Vaste Gas Tank Rupture 2.tE-4 Steam Generator Tube Rupture 0.13 (to Condenser)

Fuel Handling Accident 8.2 Large-Break LOCA 22.8 Small LOCA (outside 69.0 Containment)

None of the Above 3.4 9.0 Calculate the projected Child Thyroid Dose Rate at the Exclusion Area Boundary (Line 7 X Line 8) and enter the results in Columns A and B, respectively. mR/hr(child 10.0 Select and enter the appropriate Y' Xe-133 MPC Factor corresponding to the existing Atmospherte Stability Category (from 2904.02B, Step 1.2) in Colueen B. 10.6 "PC/mR/

Atmospheric Stability Xe-133 MPC Caterory Factor A 14 8 15 C 18 O D 23

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25 30

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PLANT M ANUAL SECTION: PROCEDURE / WORK PLAN TITLE- N O-MAGNITUDE OF RELEASE i PROCEDURE FfAGNITUDE OF RELEASE - UNIT 2 2904.02 I

PAGE 14 of 25 O ARKANSAS NUCLEAR ONE aavision CHANGE 2 oare DATE 3/2s/8i p, ARKANSAS POWER & LIGHT COMPANY Fat suun Arkansas Nuclear One TittE: , , , , , , , l Fopu No , , ,

REV e2 FC #

iage 3 ot 1 Column A Column B ANNUAL AVERACE EXISTING Condittens Units. Conditions 11.0 Calculate the Xe-133 MFC Ratio at the Excluston Area Boundary (Line 7 X Line 10) and enter results in ralt ans A and B. ."JC 12.0 Summarize the results of the ralcula-tions in Column 'A of the following table. If agnitude of release de-terminations have been initiated on Unit 1, enter the results of the de-terminations for Unit 1 (from form 1904.020) in Column A and sua the results to obtain the combined ef-fects. If Unit 1 is not involved in maning a release, enter "NA" in Col-

's u.T.n 1.

Column 1 CoIumn 2

! Unit One Unit Two Step Item (Form 1904.02D) (Form 2904.02D Total i

Q2.1 Line 7 (Column A) l i 12.2 Line 7 (Colurr.n B) i i 12.3 Line 9 (Column A) !

12.4 -Line 9 (Column 8) t 12.5 iLine 11 (Column A) i i 12.6iLine 11 (Column B) i  !

13.0 Using the results from 12.0 above, determine the appropriate Emergency Action Level (EAL) based upon the following criterta: EMERGENCY ACTION LEVEL INDICATED EAL CHITERIA  !

3 USUAL EVENT (UE) .12.5 (Total'; 1.0 MPC h.LERT(A) 12.5 (Total) > 0.0 MPC bITEEMERGENCY(SE)l12.1(Total) > 5.0 mR/br b71 or I !12.3 (Total) > 25.0 r.R/hr CT CENERAL EMERGENCY !12.2 (Total) > S.0 mR/hr 4B or (CE) I l 2 . l. (Total) > 25.0 mR/hr CT Performed by: /

INITIALS / TIMI.

Reviewed by:

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PLANT M ANUAL SECTION. PROCEDUREAVORK PLAN TITLE: NO:

MAGNITUDE OF RELEA':E ppnt rmmr h

MAGNITUDF OF RETFASE - IINIT 2 2904.02 M PAGE O# ARKANSAS NUCLEAR ONE aEvisioN CHANGE 15 of 25 i oATE DATE 3/13/81 T

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ARKANSAS POWER & LIGHT COMPANY Arkansas Nuclear One I%rrern- esaynincicar pcovrTiry stwapy l '0" NO ?90'. c2r REv. 1 PC #

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• M10LE EODY DOSE CHILD TifYh01D DOW WIND RATE DOSE RATE RATIO AFTECTED a CATE/TI.T DISTANCE (nR/ER) (mR/HR) MPC XE-133 SECTORS INIT 4

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PLANT M ANUAL SECTION. PROCEDUREAVORK PLAN TITLE: NO:

MAGNITUDE OF RELEASE l penrrmmr h

M.\cNITimF OF RETFASE - UNIT 2 2904.02 M PAGE 16 of 25 P

\ ARKANSAS NUCLEAR ONE #EvisioN i DATE anam CHANGE DATE I

Q. ARKANSAS POWER & LIGHT COMPANY gy N Arkansas Nuclear One m .- ,, r ~ e r m, .r-, m:q l FORM NO. g g.

REV. # 1 PC &

CALCCI.ATION OF OFFSITE DOSES AT SELECTED DISTA.NCES Date

1. Record the following information:

1.1 X/Q at Exclusion Area Boundary (0.65 miles) f rom selected overlay 1.2 W ole Body Dose Rate at Exclusion Area Boundary (from Form 2904.02D, 12.2 TOTAL) 1.3 Child Thyroid Dose Rate at Exclusion Area Boundary (from Form 2904.02D, 12.4 TOTAL)

2. Calculate the X/Q line corresponding to the plume outer boundary (0.05 mr/br Wole Body):

[XfQ EAB (Line 1.1) + Wole Body Dose Rate (Line 1.2) lx 0.05 (X/Q Ior 0.05 mR/hr) ~++w c *, s.o g 3. Calculate the Projected Wole Body and Child Thyroid Cose Rate at selected

)

Ns downwind distances of 1, 2, 5 and 10 miles.

(1) (2) (3) (4)

Downwind Plume Projected Projected Distacce Centerline Wole Body Child Thyroid (mi) X/Q Dose Rate Dose Rate Initials

• 1 2

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5 10 l

I CALCUIATIONS :

- Column 2: Determine X/Q f rom overlay corresponding with atmospheric e,4.* a stability category. -

Column 3: Proje:ted n ote Body Dose Rate (mR/hr) =

Column 4: Projected Child Thyroid Dose Rate (mR/hr) =

Performed By /

Inttrals/ Time Reviewed By Ov .

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PLANT M ANUAL SECTION: PROCEDUREiWORK PLAN TITLE. I

" NO; MAGNITUDE OF RELEASE I J pencemme M4 c

h MAcNIT10E OF 3ETFASE - UNIT 2 2904.02 O

v M- ARKANSAS NUCLEAR ONE PAGE

]svisioN 17 of 25 t DATE 3/t3/81 CHANGE DATE r

p ARKANSAS POWER & LIGHT COMPANY rai Arkansas Nuclear One mamm N eme rimoec+rewrwynypypyytnwrgycrwy_d'O""O i p , m.

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(1) (2) (3) (4) (5) (6)

Field footne Cone. (7) khole Body Iodine Projected WR Ratto of Current Location (pct /cc) Dose Rate Dose Dose Rate Wale Body Scale (mR/hr) Factor (From Form Dose Rate Factor 29%.02E) l l

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• r2 CALCLU TION: *

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Column 4: Determination of Iodine Dose Factor: .f 8 (mR/hr/pCi/ce)

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Column 6: Determinatson of Ratio of W ole Body Dose Rates: - }"

Column 7: Cetermination of Current Scale Factor: Form 2904.02D, Lane 6 X Column 6 Performed By /

Initials /fime Reviewed By v -

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i j;y ARKANSAS POWER & LIGHT COMPANY a

Pf AC t c4 Arkansas Nuclear One TRANSMITTAL l FOAM tJO. 1013.02H Arkansas Nuclear One Russellville, Arkansas Date March 27, 1981 MEMORMDUM

.TO: HOLDERS OF SERIES 1904 - MAGNITUDE OF RELEASE PROCEDURES - UNIT 1 PROCEDURES 1904.01 -- 1904.XX

~

FROM: ANO DOCU'IENT CONTROL

SUBJECT:

ANO dASTER PLANT MANUAL The procedures, revisions, permanent changes, and/or temporary changes listed below have been / /should be / /placed in your set of the plant manual.

PROCEDURE # REV. # PERM. CHG. # TEMP. CHG. # PROCEDURE TITLE 1904.02 1 MAGNITUDE OF RELEASE - UNIT 1 COPIES TO:

w/o att: Word Processing SI-Emer. Kit 3 - ECC w/att: 1-Control Room - Unit 1 59-Admin. Copy - 2nd Floor 3-Control Room - Unit 2 65-Emergency Kit - Local Office 6-Ops. Maint. Mgrs. 66-ECC 14-Plant Admin. Mgr. 78-ANO Library 19-Tng./Coun. Supv. 84-Emergency Planning Coord.

20-Tng./Coord. Ops. 92-Training - NSC 108-NRC Washington 27-Engr./ Tech. Supp. Mgr. 93-Ops. Tech. 109-NRC Washington 28-Tech. Anal. Supt. 100-NRC Region 110-NRC Washington 29-IIealth Physics Supv. 101-NRC Region lll-NRC Washington 32-Asst. Health Physics Supv. 102-NRC Region TI2-NRC Washington 48-Planning & Scheduling 103-NRC Washington (Info Only) 49-Emer. Kit 1 - Control Room 104-NRC Washington 19-Trng./Coun. Sup i.

Updated 50-Emer. Kit 2 - 1st Floor

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Clerk 105-NRC Washington 106-NRC Washington 107-NRC Washington (Vandergrift)

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Lgg'E ARKANSAS POWER & LIGHT COMPANY Arkansas Nuclear One tuw MAGNITUDE OF RELEASE PROCEDURE l rORY 1CCO C6A g MAGNITI'DE OF RELEASE - UNIT 1

,g 1904.02 REV 1 T  %* ?ch h 1~ 0 .)L k

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RECORD OF CHANGES AND REVISIONS PAGE REVISION CHANGE PAGE PEVISION CHANGF. PAGE PEvls:CN CWANGE 1 1 20 0 2 1 21 0 3 1 22 0 4 1 23 0 5 1 24 0 6 1 7 0 8 1 9 0 10 1 11 1 12 1 13 1 14 1 15 1 16 1 17 0 18 0 19 0 APPROVED BY APPROVAL DATE w e.;....,

3/2. &/97

/

PLANT M ANUAL SECTION: PROCEDURE / WORK PLAN TITLE- NO-MAGNITUDE OF RELEA sE PRorFDURF M AGNITimF OF MPTF A9F - UNIT 1 1904.02 PAGE 1 of 24 ARKANSAS NUCLEAR ONE atvisiON CHANGE i o^rE DATE 3/16/81 1.0 PURPOSE The purpose of this procedure is to provide an initial estimate of the radio-logical conditions at the ANO Exclusion Area Boundary, provide information to determine the Emergency Action Level, define the offsite area (s) poten-tially affected by an airborne radiological release, provide an estimate of the whole body and child thyroid dose rates and refine projections based on available field monitoring data.

2.0 SCOPE 2.1 This procedure is applicable to airborne radioactive releases from ANO, Unit One as indicated by normal ventilation system stack monitors; if the mor.itors are of f scale, refer to 1904.03, " Auxiliary Building Ventilation Exhaust Emergency Radiation Monitor" 2.2 This procedure does not take into account ef fects caused by terrain and precipitation.

3.0 REFERENCES

3.1 References Used in Procedure Preparation:

llh 3.1.1 Arkansas Nuclear One Emergency Plan 3.1.2 " Manual for Protective Actions, Appendix D", Environmental Protection Agency 3.1.3 " Workbook of Atmospheric Dispersion Estimates", U.S. Depart-ment of Health, Education and Welfare 3.1.4 Memorandum Number CL-1460 (By A. L. Smith) 3.2 References Used in Conjunction with this Procedure:

3.2.1 1602.38, " Field Test for Iodine 131" 3.2.2 1903.10, " Emergency Action Level Response" 3.2.3 1903.43, " Duties of the Emergency Radiation Team" 3.2.4 1904.03, " Auxiliary Building Ventilation Exhaust Emergency Radiation Monitor" 3.3 Related ANO

References:

3.3.1 2904.02, " Magnitude of Release - Unit 2" k

73

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PLANT M ANUAL SECTION: PROCEDUREjWORK PLAN TITLE; NO:

MAJNITUDE OF RELEASE PROCEDURE MAGNITUDE OF RFEFASF - UNIT 1 1904.02 PAGE 2 of 24 ARKANSAS NUCLEAR ONE aevision CHANGE i oATE 3/16/s1 DATE 4.0 DEFINITIONS 4.1 c0 (sigma theta) - The standard deviation of the net change of the horizontal wind direction 4.2 at (delta t) - The vertical temperature differential between the upper and lower temperature sensors on the meterological tower (in degrees centigrade).

4.3 X/Q - The ratio of the concentration of radioactive material (at a specific location) and the release rate (at the origin) in units of pCi/cc/Ci/sec.

5.0 RESPONSIBILITIES 5.1 The Shift Operations Supervisor is the Duty Emergency Coordinator until relieved.

5.2 The Shift Operations Supervisor is responsible for determining if an unplanned gaseous release to the environment is indicated by symptcms such as high stack monitor readings, area radiation monitor alarms or other indications.

llll 5.3 The Duty Emergency Coordinator, or his designee, is responsible for performing the magnitude of release calculations.

5.4 The Duty Emergency Coordinator is responsible for notifying appro-priate groups per 1903.10, " Emergency Action Level Response" 5.5 The Offsite Radiological Monitoring Section of the Emergency Radia-tion Team is responsible for determining offsite radiological hazards per 1903.43, " Duties of the Emergency Radiation Team".

6.0 LIMITS AND PRECAUTIONS 6.1 This procedure provides an initial projection of the radiological conditions; field monitoring is necessary to determine the actual conditions.

6.2 Conversion factors which are provided to establish the child thyroid iodine dose rate are based on design basis accidents and should be considered less reliable than the calculated whole body dose rate.

6.3 Actual terrain and weather conditions will generally limit the ac-curacy of the projected !oses at a specific location.

e' 6.4 The diffusion overlays used in this procedure represent long-term average conditions.

\_..

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PLANT M ANUAL SECTION: PROCEDUR UWORK PLAN TITte NQ '

MAGNITUDE OF RELEAS E PROCEDURE MAGNITUDE OF RELEASE - UNIT 1 1904.02 PAGE 3 of 24 1 ARKANSAS NUCLEAR ONE aevision CHANGE 1 care DATE 3/is/81 l

i I

7.0 DETERMINATION OF EXISTING METER 0 LOGICAL CONDITIONS AND THE G/ 3EOUS RELEASE RATE 7.1 Reccrd the current date and time in Lines 1 and 2 respectively of Form 1904.02A. If onsite meterological data is unavailable, enter "OOS" (Out of Service) in the appropriate space.

7.2 Record the os from recorder AAR 9300 on Form 1904.02A, Line 3. If 00 is not available, record the at from recorder AAR 9300 and note appro-priately.

7.3 Record the wind speed from recorder WSR 9300 on Form 1904.02A, Line 4, 7.4 Record the prevailing wind direction from recorder WDR 9300 on Form 1904.02A, Line 5.

7.5 Record the net counts per minute and the corresponding system flow rates for each of the following process monitors that are in service on Fo rm 1904.02A. For each system which is not in operation, enter "00S" (Out of Service) in Column 1.

7.5.1 Stack i -

Lines 6 and 7, respectively.

, 7.5.2 Penetration Room, ~), Lines 8and9,respectively.

i 7.5.3 Penetration Room' J, Lines 10 and 11, respectively.

7.5.4 Hydrogen Purge ' Lines 12 and 13, respectively.

7.5.5 Hydrogen Purge, Lines 14 and 15, respectively.

7.6 Make the following determinations:

7.6.1 If this is the initial calculation, proceed to Section 8.0 (Data Conversion).

l 7.6.2 Compare the present readings to the values on which the latest projections have been made.

l A. If the values have not deviated from the most recently checked column on Form 1904.02A by more than the fol-lowing list, return to Section 7.0. New data should be taken as specified by the Duty Emergency Coordinator.

, Indication Allowable Deviation Wind Direction 120 degrees Wind Speed -+20%

) 09 1 New Atmospheric Stability Category at 1 New Atmospheric Stability Category CPM 120%

Flow Rate +20%

PLANT M ANUAL SECTION: PROCEDUREAVORK PLAN TITLE: N O-MAGNITUDE OF RELEA sE PROCEDURE MAGNITUDE OF RELEASE - UNIT 1 1904.02 PAGE 5 ot 24 ARKANSAS NUCLEAR ONE aEvisioN i oATE 3/16/81 CHANGE DATE 10.0 PLUME DEFINITION NOTE: The attachments contained in this procedure are provided for ILLUSTRATION ONLY. The scaled overlays and maps necessary to do the actual calculations with are located in the following emergency kits:

a. Control Room Kit

b. Onsite Technical Support Center Kit

c. Emergency Control Center Kit 10.1 Select the overlay (Attachments 1-7) which corresponds to the exist-ing atmospheric stability category (Form 1904.02B, Line 1.2).

10.2 Place the selected overlay on the ANO area map (Attachment 8) with the origin directly over the ANO site center and align plume center-line with the downwind direction.

10.3 Complete Form 1904.02F to calculate the Plume Boundary, Whole Body Dose Rate and Child Thyroid Dose Rate at selected downwind distances.

10.3.1 Locate the plume boundary (f rom Form 1904.02F Line 2) on the overlay corresponding to the Atmospheric Stability Category.

O 10.3.2 Any sectors which are contained (or partially contained) within the plume boundary line should be designated as an affected area.

10.3.3 The maximum downwind extent of the affected area may also be determined by the extent of the plume boundary.

10.3.4 If it is necessary to calculate plume arrival time (in hours) for a specific location, divide the distance (in miles) from the plant to the location by the windspeed (in mph).

10.4 Summarize the projected Whole Body Dose Rate, Child Thyroid Dose Rate, and Affected Sectors at selected downwind distances on Form 1904.02E.

11.0 NOTIFICATIONS 11.1 Provide radiological release information to appropriate groups per 1903.10, " Emergency Action Level Response" and establish a follow-up schedule for updating release information.

11.2 The Emergency Radiation Team may be dispatched to obtain field radio-logical data at the discretion of the Duty Emergency Coordinator /

Recovery Manager. They shall be dispatched upon declaration of a

/; Site Emergency. If the Emergancy Padiation Team is dispatched, re-(.

fer to Section 12.0.

1 PLANT M ANU AL SECTION: PROCEDURE / WORK PLAN TITLE: N O-MAGNITUDE OF RELEASE PROFFnFPE MAGNITUDE OF REIEASE - UNIT 1 1904.02 PAGE 6 of 24 ARKANSAS NUCLEAR ONE aevision i oarE 3/i6/81 CHANGE DATE 11.3 Return to Section 7.0. New data should be taken as specified by the Duty Emergency Coordinator / Recovery Manager.

NOTE: This section may be used during periods that monitoring teams have been dispatched, to improve dose projections based upon the comparison of projected and measured whole body dose rates at field locations on the plume centerline. This section is designed to complement rathe_ than replace the ongoing dose projections of Sections 7.0 through 10.0.

12.0 VERIFICATION OF PROJECTED DOSE RATES 2Y FIELD MEASUREMENT 12.1 Based on wind direction, the Duty Emergency Coordinator / Recovery Mana-ger should dispatch offsite radiological monitoring teams to sample the pluce at specified locations. Preselected survey points in each sector and zone are shown on the area map (Attachment 8).

12.2 The radiation survey at each location should include a direct exposure rate measurement (mR/hr) and an air sample to determine iodine concen-tration (pCi/cc). As the survey teams approach the assigned survey location, continuous radiation measurements should be taken to identi-fy the location of the highest radiation level. As survey results are obtained, the radiological monitoring team should report the results to the lllh Duty Emergency Coordinator / Recovery Manager and proceed as directed.

12.3 Determination of Iodine Dose Factor by Field Measurement.

12.3.1 Iodine concentration (pCi/cc) Whole Body Dose Rate (mR/hr) shall be measured in the field and the results reported per 1602.38 " Field Test for Iodine 131".

12.3.2 Record on Form 1904.02G, the Field Location in Column 1, the Iodine Concentration in Column 2 and Whole Body Dose Rate in Column 3.

12.3.3 Calculate the Iodine Dose Factor for each field location in Column 4. (The most recent calculated Iodine Dose Fac-tor may be used for future Child Thyroid Dose Projections.)

12.4 Determination of Whole Body Overlay Scale Factor 12.4.1 Scale factors may be determined to refine future whole body dose estimates based upon field measurements. Because l the dose rate may change rapidly with distance from the plume centerline, scale factors should be based only upon a comparison of a projected plume centerline dose rate with the highest measured field dose rate determined by traversing

/

'T/ the plmne at the projected downwind distance. This ensures that the projected plume centerline dose rate is compared

^#

with the actual plume centerline dose rate.

1

PLANT M ANUAL SECTION: PROCEDUREAVORK PLAN TITLE: N O.

MAGNITUDE OF RELEAS E PROCEDURE MAGNITUDE OF RELEASF - UNIT 1 1904.02 PAGE 8 of 24 3 ARKANSAS NUCLEAR ONE aevisioN CHANGE 1 oATE DATE 3/i6/81

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l i 3 ARKANSAS POWER & LIGHT COMPANY 4m ""

Arkansas Nuclear One e m - s ,, , ~ ,1. , ~, , , ~,. m I =~ ,,,.. ,, , s REV. i 1 FC #

READING

() () () () ()

LINE ITEM i 2 3 4 5 1 l DATE I 2 l TIME (l0LT1) i 1 l ( ) o 9 (degrees) [or ( ) at (*C))l 4 l WIND SPEED (MPH) l 5 l VIND DIRECTION (FROM, IN DEGREES) I 6 l STACK 1 CPM i 7 I STACK kFIhwRATE(CFM) f [

8 PENETRATION ROOM CPM  !

9 PENE.TRATION ROOM ( FLOW l RATE (CFM) ( I

, 10 PENETRATION ROOM kCPM l l 11 PENETRATION ROOM e / FLOW RATE (CFM) / l 12 l HYDROGEN PLRCE r fCPM i 13 HTEROGEN PLPGE FLOW [

_ RATE (CFM) I 14 I HYDROGEN PLPGE (CPM 15 HYDROGEN PL'RGE FLOW

~

RATE (CDf) 16 "A" STEAM HEADER i MR/HR

! 17 NO. SAFETIESOPEN(HkADER"A")

18 "B" STEAM HEADER' MR/HR 19 NO. SAFETIES OPEN (HEADER "B")

20 INITIALS REVIEkID BY:

. ~

, PLANT M ANU AL SECTION- PROCEDURE / WORK PLAN TITLE: NO-MAGNITUDE OF RELEAS PROCEDURE MAGNITUDE OF RELEASE - UNIT I 1904.02 PAGE 10 of 24 A ARKANSAS NUCLEAR ONE aEviSion CHANGE t o^re DATE i/16/8i

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ARKANSAS POWER & [.lGHT COMPANY mams Arkansas Nuclear One

• evemm creraer e tw t;noveure? l FC" *0- lonr, mc REY. # 1 FC f PART 1 TOTAL CASEOUS RELEASE RATE Column 1 i Column 2  ? Column 3 iColumn 4 l Moottor Ventilatton Mc11 tor Q System Nace Reading Systen Flow

& Monitor (cpm)

Caltbration (Cff5) item Rate (CFM) Conversion Number Factor 1 l Stack ~~~ l l 2.05E-Il 2

m) 7.33E-13 IPenetrationReml* l-3 i

,lPenetrit, ton 3

Room li 7.33E-13 l

4 l Hydrogen Purge 9.28E-12 i I 5 jHydrogen Purge 9.28E-12 g f  %

) 6

( -- Aux. Bldg. lent.

Exhaust Emer.

XXX XXX XXE Rad Monitor

• 7 "A" Steam S fe- l ties e 1** f XXX XXX XXX 8 "B" Steam 5;fe- j ties' ~ 1 ** [I XXX  ! XXX XXX 9 l Total l XXX l XXX lXXX l ]

PART 2 1.

Determination Column 1 x Column of2Gaseous x Column 3Release Rate (Q888) =

2.

Total Gaseous Release Rate, Q , = sum of values in Column 4

3.

• Aux. Bldg. Vent. Exhaust Emergency Radiation Monitor Release Rate Data from Form 1904.038, Column 9.

4 ** net mR/hr X No. Safeties Open X 0.0152 ""

= Qgas, net mR/hr X No. Ib/hr Steam exhausted X 1.9E-8 = Qgas Performed by: /

INITIAL TIME Reviewed by:

r

. PLANT M ANUAL SECTION: PROCEDURElWORK PLAN TITLE: NO:

MAGNITUDE OF RELEASE PR O('F T11'R F M.iGNITir:1F OF RETF.\SF - UNIT 1 1904.02 PAGE 11 of 24 ARKANSAS NUCLEAR ONE atvisiON CHANGE i DarE 3/isesi DATE f

? ARKANSAS POWER & LIGHT COMPANY y

j Arkansas Nuclear One M

rw-ecryrv . ~ e n s v e* T r verreutsgiey I '0" O m; gp REY. + 1 FC #

iage 1 ut 3 Column A Column B CALC 11ATION OF DOSE RATE ANNUAL AVERACE EXISTING

& MPC AT THE EXCLUSION CONDITIONS CONDITIONS AREA EOUNDARY (0.65 MILES)

Line Ca t ego ry : N/A Units Category:

1.0 Enter the Total Gaseous Release Rate (Q ) (From 1904.02C) in Columns8 A'& B. Ci/Sec 2.0 Select and Enter' the khole Body dose factor from the following list which corresponds to the existing Atmospheric Stability Category (from 1904.02B) in Column B. 0.69 mR/hr Atmospheric '#

Stability G Ca te go ry A

B k'8 Dose Factor 1.0L 5.14 C 11.0 D 23.5 E 35.4 F 51.0 G 84.4 3.0 Calculate the Uncorrected khole Body Dose Rate at the Excluston Area Boundary (Line 1.0 X Line 2.0) and enter the produc ts in Columr. A and B. respectively, mR/hr 4.0 Enter the existing windspeed (from 1904.02B) in Column B. XXXXXXXXXXX (mph) 5.0 Correct the khole Body Dose Rate for windspeed (Line 3B + Line 48) and enter result in Column B. XXXXXXXXXXX mR/hr 6.0 Enter the current scale factor. XXXXXXXXXXX (NONE) 6.1 If field data is available, enter the most recent entry from Form 1904.02G (Column 7) in Column B.

o.2 If field data is not avail-able, enter "1" in Column B.

A

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PLANT M ANU AL SECTION: PROCEDURE / WORK PLAN TITLE: NO:

MAGNITUDE OF RELEA sE I PROCEDURE MAGNIT"DE OF RFIFASE - UNIT 1 1904.02 PAGE 12 of 24 ARKANSAS NUCLEAR ONE aaviSioN

. CHANGE i oATE DATE

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g, ARKANSAS POWER & LIGHT COMPANY gg W-Arkansas Nuclear One rwre r.:w .

• w =: v e. e.

. crert p s , vi: l FCAu NO , ,,

Fr.' s1 TC

• rage . vt J Column A Column B AMTAL AVERAGE EXISTING Conditions L: nits Conditions 7.0 Correct the Whole Body Dose Rate for the current scale factor (Line 5 X Line e) and enter re-sults in Column B. Transfer the _

mR/hr(shole value from Line 3A to Line 7A. body) 8.0 Select the iodine, dose factor. mR/hr(thyroid) mh/hr(shole body) 8.1 If field data is available, enter the most recent entry from form 1904.02G, (Column 4),

in Columns A and B.

8.2 If field data is not avail-S able, select and enter the ap-propriate dose f actor from the following list based on the current plant conditions in Columns A and B.

Plant Condition Iodine Dose Factor Waste Gas Iank hupture 0.049 Steam Generator Tube Pupture (to Condenser) 0.054 Fuel Handling Accident 1.7 Large-Break LOCA 63 Rod Ejection Accident 814 None of the Above 9.3 9.0 Calculate the projected Child Thyroid Dose Rate at the Exclusion Area Boundary (Line 7 X Line 8) and enter the results in Columns A and B, respectively. mR/hr(child

~- Y' 10.0 Select and enter the appropriate Xe-133 MPC Factor corresponding to the extsting Atmosphertc Stability Category (from 1904.02B, Step 1.2)

MPC/

in Column B. 19.2 mR/g Atmo=ph-ric Stabil.ty Xe-133 MPC Category Factor A 15 B 27 C 32 D 41 E 46 F 55 (O)

V G 84 '

PLANT M ANU AL SECTION: PROCEDURE / WORK PLAN TITLE: NO:

MAGNITUDE OF RELEAS E PROCEDl'RE MAGNITlT)E OF RELEASE - INTT 1 1004.02 PAGE 13 of 24 ARKANSAb NUCLEAR ONE aEvismN CHANGE 1 DATE m6m DATE O. ARKANSAS POWER & LIGHT COMPANY gg N Arkansas Nuclear One rwee-ey v vmy v nyt errecyyy m ns l N"W % gn; n73 REV a 1 FC a FJge J v1 )

Column A Column B ANhCAL AVERACE EXISTING Conditions Units Conditions 11.0 Calculate the Xe-133 MFC Ratto at the Exclusion Area Bounda ry (Eine 7 X Line 10) and enter results in Columns A and B. ."#C 12.0 tions Summarize the results in Column X of theoffollowing the calcula- '

table. If magnitude of release de-terstnations have been initiated on Unit 2, enter the results of the de-terminations for Unit 2 (from Form 2904.02D) in Column B and sum the results to obtain the combined ef-S fects. If Unit 2 is not involved in making a release, enter "NA" in Col-umn 2.

i , Unit One Unit Two j Step' Item  ?(Form 1904.02D) I(Form 2904.02D Total 12.1 'Line 7 (Column A)

!12.2 Line 7 (Column B) i i

i12.3 Line 9 (Column A) i 12.4 -Line 9 (Column B) i i

12. 5 ' Line 11 (Column A) 12.6 lLine 11 (Column B) i 13.0 Using the results from 12.0 above, determine the appropriate Emergency Action level (EAL) based upon the following criteria: E'IERGENCY ACTION LEVEL INDICATED

__ EAL i CRITERIA i D.TSUAL EVENT ( UE) l12.5 (Total) > 1.0 MPC I LERT (A) !2.5 (Total) > 10.0 MPC 1 -

SITE EFERGENCY (SE)112.1 (Total) > 5. 0 mR/h r b3 o r

!!2.3 (Total) > 25.0 mR/hr CT G  !!2.2 (Total) > 5. 0 mR / h r k'3 o r !

lENERALEMERGENCY (CE)  !!2.4 (Total) > 25.0 rR/h r CT l Perf orme d by: /

INITIALS / TIME.

p Reviewed l>y:

o, -

PLANT M ANUAL SECTION: PROCEDURE! WOR;t PLAN TITLE: N O-MAGNITUDE OF RELEAS E PROCEDl'RE MAGNITUDE OF RELEASF - INIT 1 1904.02 PAGE 14 of 24 ARKANSAS NUCLEAR ONE aavision CHANGE i caTE DATE 3/16/81 I

. ARKANSAS POWER & LIGHT COMPANY 4 Arkansas Nuclear One r % . , m .-. m.c,. mm-., _,cy l o~ % y Fri .1 F FC F-(1) (2) (1)

(4) (5)

J

. l PROJECTED PROJECTED 1

, i

,( l MIOLE EODY DOSE CHIII ThTROID PE0JECTED 1  !

j ' DobN WIND ' RATE l DOSE RATE RATIO AFFECTED i jDATE/TI.S ' DISTANCE j (mR/KR) (mR/HR) *1PC XE-133 SECTORS INIT.f

' ('!ILES) } '

!' l (SECTION I 10.3.2) l

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, i I J l j f i k  !

f

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i  !  ! l l i j I i l I l i l l  ! I I l I.

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!  !  ! l l l PERFCE.ED BY /

Iontaals/Izme FEVIEb1D BY

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r PLANT M ANUAL SECTION: PROCEDURE / WORK PLAN TITLE: NO:

MAGNITUDE OF RELEAS PROCEDURE MAGNITUDE OF RELEASE - INIT 1 1904.02 PAGE 15 of 24 ARKANSAS NUCLEAR ONE aEvisiON CHANGE 1 oarE DATE 3/16/81 I

O. ARKANSAS POWER & LIGHT COMPANY g N Arkansas Nuclear One nrre rr ver nonrr m rye l N NO g ._. , , g y RI.V . # 1 PC #

CALCULATION OF OFFSITE DOSES AT SEIICTED DISTANCES Date

1. Record the following information:

1.1 X/Q at Exclusion Area Ecundary (0.65 miles) from selected overlay 1.2 khole Body Dose Rate at Exclusion Area Boundary (from Form 1904.02D, 12.2 (Total) 1.3 Child Thyroid Dose Rate at Exclusion Area Boundary (from Form ,1904.02D, 12.4 (Total) ,

2. Calculate the X/Q line corresponding to the plume outer boundary (0.05 mr/br khole Body):

[X/Q EAB (Line 1.1) + khole Body Dose Rate (Line 1.2)  ! X 0.05 =

(X/Q for 0.05 mR/hr)

AFFECTED SECTOR (S) =

3. Calculate the Projected khole Body and Child Thyroid Dose aate it selected downwind distances of 1, 2, 5 and 10 miles.

(1) (2) (3) (4)

Downwtad Plume Projected Projected Distance Centerline ktole Body Child Thyroid (mt) X/Q Dose Rate Dose ca te . Initials 1  !  ! l l

! I  !

2 l I s l l i I

! 10 l f I l  ! i i I

i l I l t

l l I l 1 CALCL'LATIONS :

( Column 2: Determine X/Q from overlay corresponding with atmospheric stability category.

umn U ne 1.2 Column 3: Projected khole Body Dose Rate (mR/hr) .

Line 1.1 n2XUp 1.3 Column 4: Projected Child Thyrotd Dose Rate (nB/hr) =

Line 1.1 Performed By /

Instrals/ Time

/O Reviewed By l \u l

l

r PLANT M ANUAL SECTION: PROCEDURE / WORK PLAN TITLE: NO-MAGNITUDE OF RELEAS  ?.

PROCEDURE MAGNTTUDE OF RELEASE - UNTT i 1904.02

_PAGE 16 of 24 ARKANSAS NUCLEAR ONE aEvisiOn i D*TE 3/is/8i CHANGE DATE I

. ARKANSAS POWER & LIGHT COMPANY g =

Arkansas Nuclear One m . - . - , - , . .: , , ~: .. .. . . , .. s e g av ~a - cy REV. # 1 FC #

(1) (2) (3) j (4) (5) j (b) (7) i Field g Iodine Conc. lI khole Body! Iodine t Projected WB i Ratio of Current l LocatioaI (pCi/cc) jDoseRate j Dose Dose Rate lWholeBody Scale }

} ( (r.R/hr) ! iFactor (From Form Dose Rate l Factor f 1904.02E) i  !

l  !

l l l  ! l

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! t i  !  ; I e i I  !  !

l l  !  !

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f  ; I l l

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, I  !  ! i l I l l  ! l  ! I i i I l l i

J 1 i  ! l  !

l  ! I I i CALCUIATION:

Column 4: Determtntion of Iodine Dose Factor: - - -

1. h'IP I" Column 6: Determination of Ratio of Whole Body Dose Rates:

3 Column 7: Determination of Current Scale factor: form 1904.02D, Line 6 X Column 6 i Performed By /

l Initials / Time l

Reviewed By A

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j 3y ARKANSAS POWER & LIGHT COMPANY mm,in rc Arkansas Nuclear One v c TITLE:

TRANSMITTAL '[ FORM No" v 1013.02HI Arkansas Nuclear One ..,, .e-Russellville, Arkansas '

Date March 27, 1981 j

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MEMORANDUM ,

l

.TO-HOLDERS OF SERIES 1903 - EMERGENCY PLAN PROCEDURES 1903.01 -- 1903.XX FROM: ANO DOCUMENT CONTROL -

SUBJECT:

ANO MASTER PLANT MANUAL The procedures, revisions, permanent changes, and/or temporary changes listed below have been / /should be / /placed in your set of the plant manual.

PROCEDURE # REV. # PERM. CHG. # TEMP. CHG. # PROCEDURE TITLE 1903.24 0 OIL SPILL PREVENTION CONTROL AND COUNTERMEASURE PLAN 1

COPIES TO:

w/o att: Word Processing 59-Admin. Copy 2nd Floor w/att: 1-Control Room - Unit 1 65-Emer. Kit - Local Office 3-Control Room - Unit 2' 66-ECC.~

6-Ops./Maint. Mgrs. .78-AN0 Library 14-Plant Admin. Mgr. ~

,81-Burny Surversor 17-Human Resources Supv.

, lid2^1; nard'ayuse . ,

18-Emp./Coun. Supv. <

'M-F)aergency Planning Coord.

19-Trng./Coun. Supv. '#

~ 88-gaxilin 20-Trng.Coord.,0p).

' Tr6g.-- gvNSC ,0pe ra tors 25-Security Coordinator 93-Ops'.' Tech.

27-Eng./ Tech. SeN . Mgr. 100-NRC Region 108-NRC Washington 28-Technical And. Supt.

~

101-NRC Region 109-NRC Washington 29-Health Physict Supv. 102-NRC Region '* 110-NRC Washington 32-Asst. Health Physics Supv. 103-NRC Washington / Ill-NRC Washington 48-Planning & Scheduling 104-NRC Washington .r112-NRC Washington 49-Emer.-Kit 1 - Control Room 105-NRC Washington -l' '(Info Only 50-Emer Kit 2 - 1st Floor 106-NRC Washington

,' 19-Trng. Coun.Supv.

51-Emer. Kit 3 - ECC -107;NRC Washington ,

(Vandergrift)

Updated f

,, i r- _. _

r p T* ARKANSAS POWER & LIGHT COMPANY

/d L 7 Arkansas Nuclear One ces s.

EMERGENCY PLAN PROCEDURE FORM 1000.06A

.. OIL SPILL PREVENTION CONTROL

.s AND COUNTERMEASURE PLAN

1903.24 REV. O g-

• ,k llgk! - a !! t : 0E[ d fi 3! P4I 0e

[ RECORD OF CHANGES AND REVISIONS ,

FAGE REVISION CHANGE PAGE REVISION CHANGE PAGE REVISION CHANaE 1 0 2 0 3 0 4 0 A 5 0 l

6 0 7 0 8 0 9 0 r

- 10 0

.. 11 0 i

12 0 13 0 14 0 15 0 16 0 17 0 Q)

APPROVED BY; APPROVAL DATE

. .- + ,.. - . - y2o/o i

s s '

. N PLANT M ANUAL SECTION: PROCEDURE! WORK PLAN TITLE: NO:

, EMERGENCY PLAN OIL SPILL PREVENTION CONTROL i i PRO ('PnHRR & COUNTERMEASURE PLAN 1903.24 C) ARKANSAS NUCLEAR ONE Sv'siON O$ ATE wm

, CHANGE DATE TABLE OF CONTENTS

~. SECTION NO . _ DESCRIPTION PAGE NO.

1.0 PURPOSE. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 2.0 SCOPE. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3

3.0 REFERENCES

. . . . . . . . . . . . . . . . . . . . . . . . . . . 3 4.0 OIL SPILL ACTION . . . . . . . . . . . . . . . . . . . . . . . . 3-4 5.0 RESPONSIBILITIES . . . . . . . . . . . . . . . . . . . . . . . . 5 6.0 POTENTIAL SOURCES OF OIL SPILLS. . . . . . . . . . . . . . . . . 4

6. l' Fuel Oil Storage Tank . . . . . . . . . . . . . . . . . . . 4-5 s.2 Fuel Oil fruck Unioading Station. . . . . . . . . . . . . . 5 6.3 Emerr,ency Diesel Fuel Tanks . . . . . . . . . . . . . . . . 6 d 6.4 Diesel Generator Day Tanks.

s

. . . . . . . . . . . . . . . . 6-7 6.5 Diesel Fire Pump Fuel Oil Day Tank. . . . . . . . . . . . . 7 6.6 SbartupBoilerFuelOilDayTank. . . . . . . . . . . . . . 7

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6.7 Turbine Generator Lube Oil Reservoir. . . . . . . . . . . . 7-8 5.3 Clean anU Dirty Iube Oil Storage Tank . . . . . . . . . . . 8 6.9 Turbine Generator Lube Oil System . . . . . . . . . . . . . 9 s

'6.10 Transfoimec Oil . '. . . . . . . . . . . . . . . . . . . . . 9

. 6.11 Unit 2 Plant Heating Boiler Day Tank 2T22 . . . . . . . . . 9 9

- 6.12 W ste Oil Storage Tank T114 . . . . . . . . . . . . . . . . 9 6.13 Security, Diesel Generator Day Tank . . . . . . . . . . . . 10

'7.0 ' FACILITY DRAINAGE AND TREATMENT FACILITIES.

. . . . . . . . . . . 10 s - _

3.0 GULK STORAGE TANKS . . . . . . . . . . . . . . . . . . . . . . . 10

,3

, 9.0 INSPECTIONS AND RECORDS. .' . . . . . . . . . . . . . . . . . . . 10 Q) '

10.0 SECURITY . 11

'11.%'PERSONELTR/_INING-. . . . . . . . . . . . . . . . . . . . . . . 11

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,, . PLANT MANUAL SECTION: PROCEDUREMORK PLAN TITLE: No:

EMERGENCY PLAN OIL SPILL PREVENTION CONTROL

, l poncrmyr A COUNTERBfEASURE PLAN 1903.24 I h O " ARKANSAS NUCLEAR ONE PAGE

_REvistoN 2 of 11 O DATE 3/4/81 CHANGE DATE TABLE OF CONTENTS SECTION NO. DESCRIPTION PAGE NO.

12.0 ATTACHMENTS AND FORMS Attachment 1 Procedure for Use of Special Equipment for Removal of Oil 12 from Surface of Water Attachment 2 Oil Spill Response Team Organization and Responsibilities 14 Attachment 3 Criteria for notifying anc' reporting oil spills to Company 15 Officials and Government Agencies Form 1903.24A Report of Spill 16 Form 1903.24B Notification Record 17 O

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. . PLANT M ANU AL SECTION: PROCEDUR UWORK PLAN TITLE: NO:

Et1ERGENCY PLAN OIL SPILL PREVENTION CONTROL

[ ppnernimr

& COUNTER.'fEASURE PL\N 1903.24 O-O ARKANSAS NUCLEAR ONE PAGE laEvisioN 3 oi 17 o oATE a/4/rsi

' CHANGE DATE 1.0 PJRPOSE This plan exists to fulfill the requirement of 40CFR112.3 (a) that

" Owners or operators of. . . facilities. . .that. . .could reasonably be expected to discharge oil in harmful quantities. ..into or upon the navigable waters of the United States or adjoining shorelines, shall prepare a Spill Prevention Control and Countermeasure Plan (herein-after "SPCC Plan"), in writing and in accordance with 40CFR110.3 as

" discharges...which (a) violate applicable water quality standards, or (b) cause a film or sheen upon or discoloration of the surface of the water or adjoining shorelines or cause damage or emulsion to be deposited beneath the surface of the water or upon adjoining shorelines."

2.0 SCOPE This SPCC Plan delineates potential sources of oil spills and estab-lishes procedures for limiting consequences of an oil spill to the environment. Criteria for notifying company officials and/or federal and state agencies of an oil spill is also described.

3.0 REFERENCES

() 3.1 References Used in Procedure Preparation:

3.1.1 CFR, Title 40, Part 110-Discharge of 011 3.1.2 CFR, Title 40, Part 112 - Oil Pollution Prevention 3.2 References Used in Conjunction With This Procedure None l .

l 3.3 Related ANO References l

None

- 4.0 OIL SPILL ACTION 1

1 4.1 In the event of an oil spill, available resources shall be used to l prevent any oil from entering Lake Dardanelle. Ditches and/or dikes i

shall be formed, as necessary, with available machinery to contain oil in the area where the spill occurred.

4.2 If oil reaches the lake, equipment on the oil spill trailer should be I used expeditiously to minimize the consequences. The oil spill trailer is equiped with an oil containment boom and is located near the ANO fg discharge for quick access. Refer to Attachment I for instrucitons in

() the use of the oil spill trailer equipment and oil sorbent. Keys to the trailer compartments, boat house and both boats are located in the guardhouse on a common key ring labeled " Oil Spill". See Attach-ment 2 for Oil Spill Response Team organization and call list.

PLANT M ANUAL SECTION: PROCEDURUWORK PLAN TITLE: NO:

, EMERGENCY PLAN OIL SPILL PREVENTION CONTROL M s nencrmmp _ x cotNTFRkfEAMitRF PTAN 1903.24 Mh ~ ' " ~ ~ ' ' '

PAGE 4 oi 17 M

O ARKANSAS NUCLEAR ONE 1REvis10N CHANGE O DATE DATE 3/4/81 4.3 Initial Notification 4.3.1 The Duty Emergency Coordinator shall be notified of any oil spi.11 that has the potential of reaching Lake Dardanelle.

4.3.2 If oil in any quantity reaches the lake, the Duty Emergency Coordinator shall be notified as soon as possible. The Duty Emergency Coordinator shall then notify the General Manager, the Technical Analysis Superintendent and the Chemistry / Environmental Supervisor.

4.4 Subsequent Notification 4.4.1 The General Manager or his designee (listed in Paragraph 4.3.2) shall determine if and when additional notification shall be made.

4.4.2 Criteria for notification and providing written reports to company officials and other authorities is given in Attach-ment 3.

4.4.3 When it has been determined that an oil spill has occurred, the Duty Emergency Coordinator shall activate the Oil Spill C'i Response Team by calling the Oil Spill Response Team Leader or one of his alternates. See Attachment 2 for Oil Spill Response Team call list.

5.0 RESPONSIBILITIES 5.1 It shall be the responsibility of the Duty Emergency Coordinator to activate the Oil Spill Response Team as stated in Section 4.4.3 5.2 It shall be the responsibility of the Oil Spill Team Leader to co- .

ordinate oil containraent and clean up as pointed out in Attachment

, 2 of this procedure.

5.3 It shall be the responsibility of the General Manager or his designee to make all notifications and written reports necessary see Attach-ment 3.

6.0 POTENTIAL SOURCES OF OIL SPILLS l

6.1 Fuel Oil Storage Tank, T-25 6.1.1 The Fuel Oil Storage Tank is of welded steel construction, located on a solid foundation and has a capacity of 185,000 U.S. gallons. The tank has been painted to resist exterior fS corrosion. Cathodic protection is used as required. The I

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PLANT MANUAL SECTION: PROCEDUR UWORK PLAN TITLE: NO:

EMERGENCY PLAN OIL SPILL PREVENTION CONTROL I procrnrng K cotNTERMF A91!RF PLAN 1903.24 h

PAGE M ~5 of 17 O ARKANSAS NUCLEAR ONE aEvisioN CHANGE 0 DATE DATE 3/4/81 tank is inspected periodically per OP 1304.71, " Fuel Oil, Lube Oil Tank Integrity Test". It is enclosed by an earth fill containment dike which has the capacity of containing the entire tank volume plus approximately 10% rainwater. A gate valve, which is normally closed, is installed at the lowest elevation to allow water drainage. The tank overflows to a sump which has a connection for a portable pump. In the event of an overflow the contents of the sump are trans-ferred to 55 gallon drums for disposal as required. T-25 is within the Plant Security System (fence and TV surveillance).

The tank is visually inspected once per shif t by Operations and may be kept under continuous surveillance via the plant TV system.

6.1.2 The Fuel Oil Storage Tank feeds the emergency diesel storage tanks and the startup boiler day tank by gravity or pump and the diesel fire pump day tank by pump. The Unit 2 plant heating boiler day tank is normally filled by pump. All piping is underground and cathodic protection is supplied as required.

6.1.3 Major oil spills shall be disposed of using applicable

/( methods.

G 6.2 ruel Oil Truck Unloading Station 6.2.1 The truck unloading station normally handles one truck at .

a time. Each truck has a capacity of approximately 7250 gallons of diesel fuel oil. It is the responsibility of the truck driver to make all connections required to trans-fer the fuel oil f rom the truck into the fuel oil storage tank. The drivers have been trained to check all valves and fittings before and af ter the truck unloading. An .

ANO operator is present during all fuel oil transfer opera-tions.

6.2.3 In the event of a major leak, fuel unloading will be stopped immediately and applicable valves will be closed. If the leak cannot be stopped immediately, ditches or dikes will be formed out of dirt or gravel to direct the oil drainage away from ditches or drains which empty into the lake and contain the spill in the smallest area possible.

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_. PLANT M ANUAL SECTION: PROCEDURE / WORK PLAN TITLE NO:

EMERGENCY PLAN OIL SPILL PREVENTION CONTROL pnnernfmr & COUNTERMEASURE PLAN 1903.24 O " ARKANSAS NUCLEAR ONE PAGE JEvisioN 6 of 17 0 DATE ata/81 CHANGE DATE 6.3 Emergency Diesel Fuel Tanks, T-57 A & B and 2T57 A & B.

6.3.1 The Emergency Diesel Fuel storage tanks have a capacity of 22,500 gallons each and are located in separate under-ground vaults. These tanks maintain 100% volume at all times and are gravity fed from T-25. The tanks are equipped with vent piping. The volume of the below door elevation is sufficient to contain the oil in the event of a ruptured fuel tank.

6.3.2 Tanks T-57 A & B, feed the Unit 1 emergency diesel generator day tanks exclusively through a combination of pumps-P16 A & B. Valves for Unit 1 are lined up per OP 1104.36.

Tanks 2T-57 A & B, feed the Unit 2 emergency diesel generator day tanks exclusively through a combination of pumps 2P16 A & B. Valves for Unit 2 are lined up per OP 2104.36.

6.3.3 Each emergency tank vault has a sump which is connected to a main sump equipped with a manually operated sump pump. In the event of a main sump overflow, the oil will be contained in the vault building basement area. Excess oil accumulation is alarmed by annunciators in the respect-ive control room.

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6.3.4 In the unlikely event of a tank rupture, a fuel tank alarm will sound from the vault. Operations shall immediately close valve FO-4. This action will stop the ,

gravity feed from the Fuel Oil Storage Tank, T-25.

6.4 Diesel Generator Day Tanks, T-30 A & B and 2T30 A & B 6.4.1 The Diesel Generator Day Tanks are located on the diesel generator f rame. Each diesel generator room is equipped ,

with metal containment dikes at the doors and are con-nected to the oil water drain system (OWS). Unit I diesel generator day tanks have a capacity of approximately 375 gallons. Unit 2 diesel generator day tanks have a cap-acity of approximately 550 gallons.

6.4.2 For Unit 1, transfer pumps P-16 A & B in the underground Storage Tank Vault connect T-57 A & B to the Diesel Gen-erator Day Tanks through buried piping. For Unit 2, trans-fer pumps 2P-16 A & B in the underground Storage Tank Vault connect 2T-57 A & B to the Diesel Generator Day Tanks through buried piping. This piping was designed to ANSI B31.10 and ANO QA program requirements. Valve line up for all Diesel Generator Day Tank fills are performed per OP 1104.23.

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PLANT MANUAL SECTION: PROCEDUREN/ORK PLAN TITLE: NO:

, EMERGENCY PLAh OIL SPILL PREVENTION CONTROL s ppnernFrr h

A COUNTERMFASURE PTAN 1903.24 M PAGE 7 ot 17

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ARKANSAS NUCLEAR ONE aEvisia 0 DATE 3/4/81 CHANGE DATE 6.4.3 In the event of a day tank rupture or fuel line break, the fuel oil will drain to the turbine building sump. A tank rupture may cause P16 to begin pumping, resulting in more fuel spillage than the quantity contained in the Diesel Generator Day Tanks. In this case a turbine building oil sump high level alarm will signify fuel problems in its respective control room.

6.5 Diesel Fire Pump Fuel Oil Day Tank, T-29 6.5.1 The fire pump day tank is located in the upper level of the intake structure and is protected by a concrete containment dike which is capable of holding the day tanks full capacity of 280 gallons.

6.5.2 T-29 is filled directly from the Fuel Oil Storage Tank per OP 1104.23 by pumps P-74 A & B.

6.5.3 A tank rupture would be signified by annunciation K12, D-6,

" Diesel Tank T-29 Level Low".

6.6 Startup Boiler Fuel Oil Day Tank, T-28 6.6.1 The Startup Boiler Day Tank has a capacity of 19,000

['~~N) gallons and is located in the northwestern section of the turbine auxiliary building. The fuel oil tank feeds the startup boiler nozzle by fuel oil service pumps P-13 A & B.

6.6.2 T-28 is filled directly from the Fuel Oil Storage Tank per OP 1104.23 by gravity or pump.

6.6.3 Overflows or tank leaks are contained in the sump and pumped by P-93 to the Unit 1 turbine building sump. ,

6.7 Turbine Generator Lube Oil Reservoirs 6.7.1 Unit 1 Lube Oil Reservoir T-27 (a) The Turbine Generator Lube Oil F servoir has a capacity of 14,000 gallons and is locater in a containment room on the ground floor in the souttern section of the tur-bine building. Lube oil transfer is handled per OP 1106.01, " Turbine Lube Oil Transfer".

(b) Any Oil Spillage would be accumulated by OWS drains and piped to the turbine building sump. The drain piping is equipped with a stop valve, which is located in the tur-bine building basement on the south wall outside T-26 tank room. This valve may be closed if it becomes necessary to contain the lube oil in the containment

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room. The drain valve is normally open in order to prevent accumulation due to normal leakage (considered as a fire hazard).

PLANT MANUAL SECTION: PRCCEDUREMNORK PLAN TITLE NO:

. EMERGENCY PLAN OIL SPILL PREVENTION CONTROL nnnernene c

L r entNTrnvr Act'pr DT AV 1903.24 PAGE M 8 of 17 O ARKANSAS NUCLEAR ONE aEvisioN CHANGE 0 DATE DATE 3/4/81 (c) If there is a major oil leak or tank rupture, the oil flow to the turbine building may be stopped by using the drain valve.

6.7.2 Unit 2 Lube Oil Reservoir 2T-27.

(a) The Unit 2 Turbine Lube Oil Reservoir has a capacity of of 6400 gallons and is located in a containment room below ground level in the north enu of the Unit 2 tur-bine building. Lube oil transfer for Unit 2 is handled per OP 2106.01.

(b) Any oil spillage would be accumulated by (OWS) drains and piped to the turbine building sump.

6.8 Clean and Dirty Lube Oil Storage Tanks 6.8.1 Unit 1 Clean and Dirty Lube Oil Storage Tank T-26.

(a) The Clean and Dirty Lube Oil Tanks are located side by side with the clean tank overflowing into the dirty lube oil tank. T-26 is located in the southeast corner of the turbine building basement and has a total capacity O. of 31,218 gallons. The tank is contained in a room equipped with a fireproof, watertight door and an OWS drain with a stop valve just downstream of the drain (located on the floor outside the containment room). .

This valve is normally open to prevent any accumulation of any tank leakage.

(b) The T-26 drain is connected to the turbine building sump. As with the T-27 drain valve, this stop valve may be closed if required. -

6.8.2 Unit 2 Clean and Dirty Lube Oil Storage Tank 2T-26.

(a) The Unit 2 Clean and Dirty Lube Oil Tanks are located side by side with the clean tank overflowing into the dirty lube oil tank. 2T-26 is located in the north-west corner o' the Unit 2 turbine building basement and has a total capacity of 32,000 gallons.

(b) Tank 2T-26 is contained in a room equipped with a fire-proof water tight door and aa OWS drain that connects to the Unit 2 turbine building sump.

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PLANT MANUAL SECTION: PROCEDURUWORK PLAN TITLE: NO:

EMERGENCY PLAN OIL SPILL PREVENTION CONTROL l PRneFntmF & COUNTERMEASURE PLAN 1903.24 h

O " ARKANSAS NUCLEAR ONE {_PAGE Revision 9 of li 0 DATE uw CHANGE DATE 6.9 Turbine Generator Lube Oil System Unit 1 and Unit 2 6.9.1 If any leaks or ruptures in the turbine generator lube oil systems occur, it will be contained in one side of the Unit 1 or Unit 2 turbine building basement by a containment wall which runs the full length of each basement. The oil shall then be disposed of using applicable means.

6.10 Transformer Oil 6.10.1 The ANO Unit 1 transformer yard has four main transformers with a capacity of 8490 gallons each, two startup trans-formers with a capacity of 7994 gallons each, and an auxi-liary transformer holding 7994 gallons. The accumulative capacity for Unit 1 is 57942 gallons of transformer oil.

The ANG Unit 2 transformer yard has three main transformers with a capacity of 14000 gallons each, one startup trans-former with a capacity of 5600 gallons and an auxiliary transformer with a capacity of 5600 gallons of transformer oil. The accumulative capacity of transformer oil for Unit 2 is 53,500 gallons. Both Transformer yards are unattended but are within the plant security system (fence and TV se rveillance) ,

6.10.2 Any major loss of insulating oil in the equipment would cause a transformer failure. A failure will immediately cause an f}

% alarm in its respective control room. Each transformer is surrounded by a concrete containment which has the capability of holding all the oil in the transformer. All oil spillage would be routed to the main oil and water separator via drains -

within the containment. The OWS main sump is inspected after any major oil spill and, if required, the level will be lowered using applicable methods.

6.11 Unit 2 Plant Heating Boiler Day Tank 2T-22 6.11.1 The Plant Heating Boiler Day Tank is located at ground level Elv. 354 in a room equipped with a dike and a floor drain connected to the oil water system drains. The capacity of 2T-22 is 1936 gallons.

_ 6.11.2 In case of a tank rupture the oil will be contained in the turbine building sump and processed by appropriate means.

6.12 Waste Oil Storage Tank T-114 6.12.1 The Waste Oil Tank receives dirty oil from the oil water sep-aration unit at ANO. The tank capacity is approximately 3000 gallons.

6.12.2 Tank T-ll4 is located outside near the oil water separator and is contained within a containment dike equipped with drains In case of a tank rupture the oil would be returned to the oil water separator sump.

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[ PLANT M ANUAL SECTION: PROCEDURDWORK PLAN TITLE: NO:

, EMERGENCY PLAN OIL SPILL PREVENTION CONTROL poncrmmr & COUNTER 5fEASURE PL AN 1903.24 O

%/

O ARKANSAS NUCLEAR ONE PAGE 3EvisiON 10 of 17 O DATE 3/4/81 CHANGE DATE 6.13 Security Diesel Generator Day Tank 6.13.1 The Security Diesel Generator Day Tank is a Simplex Packaged Day Tank System. It is automatically filled by a 1/3HP mo-tor from T-28 and has a capacity of 25 gallons.

6.13.2 The Security Diesel is located approximately ten feet north of the Administration Puilding at ground elevation. The Day Tank is located at the west end of the Diesel Generator.

6.13.3 The operation of the Security Diesel Day Tank pump is veri-fied weekly per Surveillance procedure 1305.10. -

6.13.4 The Day Tank level is checked, via use of the gage mounted on the Simplex Diesel Day Tank panel, weekly per Surveil-lance procedure 1305.10.

7.0 FACILITY DRAINAGE AND TREATMENT FACILITIES 7.1 Drainage from the earth dike around T-25 is controlled by a manually operated gate. This valve is kept closed at all times except when rainwater is drained from the containment.

D)

(_ 7.2 Drainage from Unit 1 and Unit 2 turbine building sumps and drainage from the maintenance facility floor drains are processed through the oil water separator unit. The oil water separator is equipped with an oil skimmer unit and a dissolved air flotation unit. Oil from the ,

oil water separation facility is collected and stored in a waste oil tank and disposed of by applicable means.

7.3 All plant drains located on the plant grounds discharge into the plant discharge and intake canals. All potential oil spill locations are l situated such that any oil spill could be diverted from these drains by .

! dikes, ditches or ground landscaping.

8.0 BULK STORAGE TANKS

- 8.1 All bulk supplies of fuel oil or lube oil are stored in tanks con-structed of material compatible to the ambient and oil temperatures encountered. Storage tanks are inspected periodically for signs of deterioration, leaks, etc., per OP 1304.71, " Fuel Oil, Lube Oil Tank Integrity Check". Any deficiencies acted are corrected as soon as i

practical.

1 9.0 INSPECTIONS AND RECORDS 9.1 The fuel oil and lube oil tanks are inspected for leaks and levels recorded once per shif t and are periodically inspected per OP 1304.71,

() (Fuel Oil, Lube Oil Tank Integrity Check". All findings of this procedure are reviewed by the Operations Superintendent.

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PLANT M ANUAL SECTION: PROCEDURE! WORK PLAN TITLE: NO:

, EMERGENCY PLAN OIL SPILL PREVENTION CONTROL ponernepr & COUNTERMEASURE PLAN 1903.24 n%/

d ARKANSAS NUCLEAR ONE

'PAGE laevision 11 01 12 o DATE 3/4/81 CHANGE DATE 10.0 SECURITY 10.1 Access into the plant area is controlled through gates by guards 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a day. . All plant oil storage facilities are within the ANO security system. All outside areas are fenced, well lighted and under TV surveillance. Admittance to tank areas outside the r.ain plant buildings is limited and is under supervisory control.

11.0 PERSGNNEL TRAINING 11.1 All plant operating personnel are provided on-the-job training and must be completely familiar with the equipment and procedures used before they are authorized to perform work pertaining to oil handling.

11.2 Training sessions shall be held semi-annually for the Oil Spill Response Team. Training shall consist of classroom training, on-the-job training, and drills which involve use of the oil spill clean up equipment.

11.3 Training and retraining on this emergency procedure will be accomplished by inclusion in the operations and maintenance training departments training schedule on a yearly cycle beginning in January 1981.

12.0 ATTACHMENTS AND FORMS O 12.1 Attachment 1, " Procedure for Use Of Special Equipment For Removal Of Oil From Surface Of Water" 12.2 Attachment 2, " Oil Spill Response Team Organization And Responsibili-ties" 12.3 Attachment 3, " Criteria For Notifying Company Officials And Govern-ment Agencies" 12.4 Form 1903.24A, " Report Of Spill" 12.5 Form 1903.24B, " Notification Record" C)

PLANT M ANUAL SECTION: PROCEDUREWORK PLAN TITLE NO:

, Et!ERGENCY PLAN OIL SPILL PREVENTION CONTROL PROCEDUpr t enrNTrnMrrermr pr AN 1903.24 h

PAGE p) M ARKANSAS NUCLEAR ONE _aEvisiON 12 of 17 0 oAre

% 3/4/ai CHANGE DATE Page 1 of 2 ATTACIRIEhT 1 Procedure for Use of Special Equipment for Removal of Oil from Surface of Water 1.0 IFDfEDIATE ACTION 1.1 The first objective should be to deploy the floating oil boom to form a barrier and confine the oil to as small an area as possible.

1.2 Locate the trailer near the water so that the oil boom can be pulled from the back of the trailer and directly into the water without dragging boom across the ground, if possible.

1.3 Lower the tailgate of the trailer and fasten one of the nylon tow bridles to the end of the boom.

1.4 Pull the boom from the trailer with a boat. Locate the boom in the water so that both ends can be tied to suitable restraints leaving the boom where it will confine oil to an area and facilitate removing 7s oil from the water.

( 2.0 SUBSEQUENT ACTION 2.1 After oil is confined with the boom, the next step is to remove oil .

from the surface of the water.

2.2 If oil is >l/2 inch deep, the skimmer pump can be used to pump oil into barrels or other suitable containers as follows:

l 2.2.1 Locate the skimmer pump close to the water containing oil -

l and rig up suction and discharge hoses. There are seven l 10-foot long sections of 3-inch diameter suction hoses containing yellow floats and two 25-foot long sections j of 3-inch diameter discharge hoses without floats.

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2.2.2 Couple the five foot diameter semi-circular skimmer head r to the free end of the suction hose and shove the suction l hose into the water locating the skimmer head in the largest concentration of oil possible. A floating bridge assembly is provided on the trailer and should be used to lift and suspend the suction hose over the boom if it is necessary that the suction hose cross the boom.

1 2.2.3 Rig the free end of the discharge hose so that oil will be

discharged into barrels or other suitable container.

l 2.2.4 Start the skimmer pump and begin pumping.

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. PLANT M ANUAL SECTION: PROCEDUREWORK PLAN TITLE: NO:

EMERGENCY PLAN OIL SPILL PREVENTION CONTROL l ppnermmP

& COUNTERMEASURE PLAN 1903.24 O e ARKANSAS NUCLEAR ONE

_PAGE REVISION 13 of 17 O DATE 3/4/81 CHANGE DATE Page 2 of 2 2.2.5 The original boom can be repositioned with the boat causing the oil to be moved to the skimmer head or a second section of boom can be deployed inside the original boom and used for this purpose.

2.2.6 Continue pumping until oil is less than inch deep. Then use oil absorbing material for further cleanup.

2.3 If oil is <1/2 inch deep, oil absorbing material should be used to absorb and " mop up" oil. Oil absorbing materials are available either on the trailer or in the storeroom; these materials and their use are described as follows:

2.3.1 Sacks of granulated sorbent are located on the trailer.

This material will absorbe 9 to 15 gallons of oil per bag and floats indefinitely even when saturated with oil.

This material can be removed from the water with the skimmer pump.

2.3.2 3M type 100 sorbent located in the storeroom. This f 3, material is in rolls 3 feet x 150 feet long. It will (j absorb 13 to 25 times its weight in oil and will not sink. It is recommended for use in open areas on smaller spills. It is used by spreading it on the surface of the water or on the shoreline. It is .

retrieved with hay forks, shovels, or other long-handled tools.

2.3.3 3M type 126 sweeps located in the storeroom. This item i is made from the same material described in 2.3.2 above.

l It is 22 inches x 100 feet long and contains a durable .

rope to provide strength. It is used by extending be-tween two boats and sweeping the surface of the water.

Recommended for removing rainbow sheens and other thin slicks.

2.3.4 3M type 156 sheets located in the storeroom. This item is made from the same material described in 2.3.2 aboze.

It is made in 18" x 18" squares and is recommended for small spills in congested areas, shallow water and rocky .

shorelines. These sheets can be " wrung out" and reused.

2.4 The washdown pump can be used to " herd" oil around on the surface of the water, wash the shoreline : nd clean up equipment. The pump should be placed in the water before starting or shaft damage will result.

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, PLANT MANUAL SECTION: PROCEDURE / WORK PLAN TITLE:

" NO:

,q EMERGENCY PIAN OIL SPILL PREVENTION CONTROL J y ppggggg33 t ent NTFDMFAmmF prAN 25 h 1903.24 PAGE m M- ARKANSAS NUCLEAR ONE laEvismN 14 of 17 0 DATE 3/4/81 CHANGE DATE Page 1 of 1 ATTACHMENT 2 Oil Spill Response Team Organization and Responsibilities The purpose of the ANO Oil Spill Response Team is to minimize the consequences of an oil spill upon the environment of Lake Dardanelle. The Oil Spill Response Team shall be activated per Section 4.4.3 of this procedure. Upon activation the team shall initiate action as described in Section 4.2 and Attachment 1 of this procedure. The oil spill team leader shall be responsible for coor-dinating oil containment and clean up activities and report to the Technical Analysis Superintendent.

The ANO Oil Spill Response Team shall consist of a Team Leader and two alternates, with eight (8) members as shown on the following call list:

Call List For Oil Spill Response Team NAME PHONE Team Leader (1) C. Adams [

Alternate Team Leader (1) D. Calloway '

Alternate Team Leader (2) T. Baker i Members Chemist (1) Gary Lipham I

Mechanical (2) Sherman Yancy ,

l Maint. l .

(3) Joe Mason l (4) Barry Waldron

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(5) Larry Greathouse (6) Steve DeYoung

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Mech. 901's (7) Sid Hawkins  ;

(8) Mike Esll  !

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PLANT M ANU AL SECTION: PROCEDURUWORK PLAN TITLE: Ho, EMERGENCY PLAN OIL SPILL PREVENTION CONTROL 2 I nenrrmmr K COUNTERMFASURE PLAN _ 1903.24 M9 h M PAGE IS of 17 (N/) ARKANSAS NUCLEAR ONE LEY $10N O DATE #4/81 CHANGE DATE Page 1 of 1 ATTACllMENT 3 Criteria for Notifying Company Officials and Government Agencies a.

40CFR110.9 reads in part: "Any person in charge of any.Sufacility shall, as soon as he has knowledge of any discharge of oil from;such. .. facility. .,

immediately notify the U.S. Coast Guard of such discharges. .". The U.S.

Coast Guard National Response Center (USCGNRC) was contacted on 8/3/77 to inquire about specific criteria for notifying USCGNRC of an oil spill. It was determined that USCGNRC desires to be notified if > one teaspoon of oil enters Lake Dardanelle.

The General Manager or his designee shall make all notifications:

The USCGNRC shall be notified first, the Arkansas Department of Pollution Control and Ecology shall be notified second, then notify Generation and Construction Technical Analysis.Section I of the attached oil spill report form shall be completed prior to making notifications. Section ! Ahallibe filled out by ANO >

personnel cognizant of the conditions of the oil spill. ire f

(3) Notification of USCGNRC fulfills all federal law for notification of an oil spill. In the event the National Response Center can notcbe reached, individual federal agencies must be notified. f:

The attached oil spill report form and all notification record forms shall be filled out completely and retained for the purpose of evaluating the oil spill event.

A written report in memorandum form shall be made to the : Manager of Generation and Construction Technical Analysis for proper distribution to various agencies ,

as required. The report shall include a general description of the event, how the spill occurred, counter measures taken to prevent a re-occurrance of the spill and copies of the oil spill report forms and notifipation records filled out at the time of the spill.

U

PLANT V ANU AL SECTION: P AOCEDUREN.'CR4 PLAN TITLE: ho' 3 EMERGENCY PLAN OIL SPILL PREVENTION CONTROL h N "m ~t' r & col'NTERMEASL'RE PLAN 1903.24 O N ARKANSAS NUCLEAR ONE S ision O c '/d meu CHANGE DATE Q. ARKANSAS POWER & LIGHT COMPANY gg =

Arkansas Nuclear One

. . ,. , .. , . . . ec~ ~o ,_,,,1 ,

Rr; r o TC

• REPGRT CF O!I. SPIII OATE/ TIE CF WTIFICATICN / -

I. Description of Spall A. Spill Cate: Tire:

B. General Weather Conditicas:

Temperaturs . *T kind Spe*d tiles /hr & / / gusty er / / steady 1.ind Directica (direction vind is M )

Lake Surf ace Ccadition (rtppling, cheppy, whiteca ptog)

("" C. Locatien of Spill (intake canal, discharge canal, etc.)

N )}

D. Movesent of spilled eatertal:

E. Material Spilled (#2 Diesel oil, turbine lube oil, etc.)

F. Q2au.ity Spilled (gallcas, barrels, etc.)

G.

Scurce of Spt11 (targe, truck, oil cooler lesk, etc. ,)

H. Operatico in Progress (unlcading oil, transferring oil, etc.)

I. Corrective Actics taken:

J. Name of Personnel that discovered spill:

K. Name of Personnel to contact at scene of spill:

b G

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'. O PLANT M ANU AL SECTION: PROCEDUREAVORK PLAN TITLE-OIL SPILL PREVENTION C0hTROL 3,9b EMERGENCY PLAN ppncentmy  ;, COINTFRMFASimF Pr AN 1903.24 I 17 of 17 PAGE

1. i M- Revision , O DATE 3/4/81 ARKANSAS NUCLEAR ONE. CHANGE DATE ARKANSAS POWER & LIGHT COMPANY Arkansas Nuclear One l FCm M 1903.248

• NOTIFTCATION FFCORD REY. p u PC e DATE/ TIME PHONE CONTACTED ~

AGENCY PERSON CONTACTED USCG National Response Center State Dept. Pollution Control _

& Ecology AP&L G&C Technical Analysis Dale L. Swindle Office

' Home AP&L G&C Technical Analysis Edward L. Green Office Home

^~

AP&L G&C Technical Analysis Sharon R. Tilley Office I Home Forinformationpurposes,thefollowingnumbersareproEided: \

U.S. Coast Guard (Memphis) 24-Hour Emergency EPA, Dallas -

i 24-Hour Emergency i

' \

Corps of Engineers }

I Other Agencies Notified:

DA_TE/ TIME

! PHONE CONTACTED AGENCY PERSON CONTACTED l

1 i

f 1

t l -

l Person Making Notification: -

I i

+j 7j ARKANSAS POWER & LIGHT COMPANY

^

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crat Arkansas Nuclear One

• TRANSMITTAL - DELETION OF PROCEDURES l FORM NO. 1013.02N Arkansas Nuclear One Russellville, Arkansas Date March 16, 1981

.. MEMORANDLN TO: HOLDERS OF SERIES 1903 -

EMERGENCY PLAN PROCEDURES 1903.01 - 1903.xx FROM: ANO DOCUMENT CONTROL

SUBJECT:

ANO MASTER PLANT MANUAL - DELETION OF PROCEDURES .,

/

The procedures listed below have been / / should be Q / DELETED from your set of the ANO Master Plant Manual.

PROCEDURE # REV. # AND/0R AhT CHANGES PROCEDURE TITLE 1903.01 2 Response & Accountability 1903.03 0 Evacuations 1903.15 2 Unit 1 & 2 Auxiliary Building Ventilation Exhaust Emergency Radiation Monitors COPIES T0: w/o att: Word Processing 65-Esar. Kit - Local Office w/att: 1-Control Room - Unit 1 66-ECC 3-Control Room - Unit 2 78-ANO Library 6-Operations Manager 81-Burns Supervisor 14-Plant Admin. Mgr. 82-Cuardhouse 17-Human Resources Supv. 84-Emergency Planning Coord.

18-Emp./Coun. Supv." -

88-Auxiliary Operators 19-Tng./Coun. Supv. 92-Trng. - NSC 20-Tng./Coord. Ops. 93-Ops. Tech.

25-Security Coordinator 100-NRC' Region 27-Eng./ Tech. Supp. Mgr. 101-NRC Region 28-Technical Anal. Supt. 102-NRC Region 29-Health Physics Supv. 103-NRC Washington 32-Asst. HP Supervisor 104-NRC Washington 48-Planning & Scheduling 105-NRC Washington 49-Emer. Kit 1 - Control Room 106-NRC Washington 50-Emer. Kit 2 - 1st Floor 107-NRC Washington 51-Emer. Kit 3 - ECC 108-NRC Washington m 59-Admin. Copy - 2nd Floor 109-NRC Washington (d UP dated Clerk 110-NRC Washington

~ i111-NRC Washington s

g2-NRCWashington (INFO O'NLY) 19-Tng./Coun. Supv.- (Vandergrift)

jy ARKANSAS POWER & LIGHT COMPANY O 44 Ark ns s Nuclear One nrrden nr prirTinNS To STATION PROCFDtIRES l FORM f10. 1013.02B1 Procedure Number [f8 h, [ Revision Number L Procedure Title _$[M __

COOMTM/d /

Comments: /E '

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ffh Yo f0 x 2h $ r f,'f gj F2 commended for deletion:

"Depa rtment ?!anager

,L A Date } d/8 [

/

b.h '

PSC, Chairman Gf applicable)

Date

/

l0fY! /

Approval fo deleti n:

/

Gene,ral Manager Date ] lj G) 9 /

O O -

,,~..,,._y.,. .m, _ . _ . _ . , . - . _ _ , _ , , , , , _ _ , . . , , - . _ , . , . _ , . , ,

7j ARKANSAS POWER & LIGHT COMPANY

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• nr+n or nrrrrrna vn synn.: pyncentmes I roav so. io13.02M Procedure Number O), Revision Number h Procedure Title Md comments: red k cegl bz. /903. 3D , , 5/,_a , f2 e $l3_ itI /

Recommended for deletion:

h a

/ Date $& ff Department Manager ~/ / /

h/f PSC, Chal[rman (if applicable)

Date_)l/0,/Vl Approval for deletion:

fi n-Gene ral' Manager Date h) L ) T)

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v e

,n -

ARKANSAS P WER & LIGHT C MPANY O 7c xiRT ca Aricansas Nuclear One perrkn nr nrTFTTONS TA 97.iTinN PROCED! IRES l FORM NO.1013.02M Procedure Number / O he /f Revision Number Procedure Title _ // / !d A// T b I- b. /dI. 8 AY

{lM NO. klCA) 'WM Comments: _fej?/_LC_ggf /90 </, o3

[e_Ef 34gfj) mmended for deletion:

] ts De'partment Manager Date 2, 8[

// /

h $f . Date S /E,l

___ PSC, Cifairman (if applicable) / /

Approval ' r dele ion:

General Manager Date 3)ft )[]

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_ _ _ . .