ML20211J976
| ML20211J976 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 06/18/1985 |
| From: | DAIRYLAND POWER COOPERATIVE |
| To: | |
| Shared Package | |
| ML20211J948 | List: |
| References | |
| PROC-850618, NUDOCS 8606270119 | |
| Download: ML20211J976 (43) | |
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LACBWR EMERGENCY PLAN PROCEDURE NP m ORGANIZATION AND OPERATIONS DURING EMERGENCIES
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- g -f~? U,f! *ll{l kes&,= ei RECORD AND CONTROL OF INITIAL ISSUE, REVISIONS & PERIODIC REVIEWS PREPARED BY OR EPC OPS. SUPV. QA SUPV. Il& S *
- APPV'D & ISSUED
- ISSUE PERIODIC REVIEW BY REVIEW REVIEW REVIEW REVIEW EFFECTIVE DATE SIGNATURE DATE SIGN. DATE SIGN. DATJ SIGN. DATE SIGN. DATE OF ISSUE
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((vg EMERGENCY PLAN PROCEDURE ORGANIZATION AND OPERATIONS DURING EMERGENCIES Issue Notice No. 20 Dated 6/18/85 INSTRUCTIONS Remove Insert Description of Old Page Nos. New Page Nos. and Reason for Change Remove and des- Insert Pages Changes to incorporate new troy all pages all pages Sping 4 noble gas detector :
Pages 0.1, 0.2, Pages 0.1, 0.2, conversion factors on ;
and 10, 20, 31, and 10, 20, 31, IRAD/ RAD formj to provide more !
63, and 64 of 63 and 64 of complete followup information EPP-2, Issue 19. EPP-2, Issue 20. and change reference on TSC computer instructions.
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PAGE SCHEDULE No. Issue No. Issue No. Issue No. Issue No. Issue 0.1 20 17 18 35 18 53 18 71 18 0.2 20 18 18 36 18 54 18 72 18 i 1 18 19 18 37 18 55 18 2 18 20 20 38 18 56 19 3 18 21 18 39 18 57 19 4 18 22 18 40 18 58 18 5 18 23 18 41 18 59 18 i 6 18 24 18 42 18 60 18 7 18 25 18 43 18 61 18 8 19 26 18 44 18 62 18 9 18 27 18 45 18 63 20 10 20 28 18 46 18 64 20 11 18 29 19 47 18 65 18 12 19 30 18 48 18 66 18 13 18 31 20 49 18 67 18 14 18 32 18 50 18 68 18 15 18 33 18 51 18 69 18 g(} 16 18 34 18 52 18 70 18 This issue shall not become e'f fective unless accompanied by a-new -
cover' sheet properly signed off in the appropriate' review / approval Columns.
T P:go 10 EPP-2 Issue 20 f( ) 4.3.4 (P) - Notify Vernon County Sheriff and Wisconsin Warning Center 1 (Wisconsin Division of Emergency Government) that an alert is being declared and the offsite agencies should be placed on a standby basis. The message should state: "THIS IS (CALLER'S IDENTIFICATION) CALLING FROM THE LA CROSSE BOILING WATER REACTOR. AN ALERC HAS OCCURRED AT LACBWR. THIS CALL IS BEING MADE TO COMPLY WITH NRC NOTIFICATION REQUIREMENTS ONLY AND NO ASSISTANCE OR OTHER ACTION BY YOUR AGENCY IS HEQUIRED AT THIS TIME." (15-min. notice, following EAL declaration)
Call via NAWAS to notify Vernon County and Wisconsin WCl or call 637-2123 Vernon Co. INITIALS TIME and 1-266-3232 Wisc. DEG INITIALS TIME VERIFICATION: Vernon County TIME Wisc. WCl TIME (INITIALS) 4.3.5 (P) - Notify Houston County Sheriff with message in Step 4.3.4. (15-min. notice, following EAL declaration) call: 1-507-724-3379 or 1-507-724-5122 INITIALS TIME
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VERIFICATION: Houston County INITIALS TIME 4.3.6 (P) - Notify Minnesota Division of Emergency Services with message in Step 4.3.4. (15-min. notico, following EAL declaration)
Call: 1-612-778-0800 (Request Duty Officer) or .
1-612-296-2100 ( Leavo mossage, request Duty Officer to I return call)
INITIALS TIMM VERIFICATION: Minnesota DES INITIALS TIME 4.3.7 (P) - Notify the USNRC via the ENS network (red phone).
INITIALS TIME 4.3.8 (P) - Once the Technical Support Contor is activated, establish liaison with the Control Room. If the TSC/ EOF Data Acquisition System has not already beon shifted to its omorgency mode of operation (Modo 2), manually shift it as por LACHWR Operating Manual, Volume IV, l
Section 11.
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ERD Initials .
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P go 20 EPP-2 Issue 20
() 4.4.17 (P) -
Activate the Emergency Operations Facility by calling the personnel listed on the EOF roster (Appendix
, C).
Persons Contacted (ECD) (IRAD) (ODCTS) l (SRAD) (TC)
(EOPD) (TC) 4.4.18 (P) - Notify the USNRC via the ENS network (red phone).
INITIALS TIME 4.4.19 (P) - Inform the Emergency News Director that a Site Area Emergency exists. Activate JPIC and media I services.
INITIALS '
( ) 4.4.20 (P) - Notify the Nuclear Emergency Preparedness Director, R. Marose.
Call: Ext. 210 or 1-786-1090 or 8-380 INITIALS TIME 4.4.21 (P) - Once the Technical Support Center has been I activated, establish liaison between the Control Room and TSC. If the TSC/ EOF Data Acquisition System has not already shifted to its emergency mode of operation (Mode 2), manually shift it as per LACHWR Operating Manual, Volume IV, Section 11.
INITIALS
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PROJECTED DOSE (REM) TO THE THE POPULATION RECOMMENDED ACTIONS COMMENTS Whole Body < 1 No planned protective Previously recom- ,
actions. State may issue mended protective l and advisory to seek shelter actions may be !
and await further instruc- reconsidered or l tions. Monitor environ- terminated. 1 mental radiation levels. j Whole Body 1 to Seek shelter as a minimum. If contraints exist,
<5 Consider evacuation. special considera- i (Emergency field teams and tion should be given workers should consider KI for evacuation of administration.) infants, children, Thyroid 5 to Monitor environmental and pregnant women. i
< 25 radiation levels. Control access.
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and Above tion. Monitor environ- would be an alterna- l mental radiation levels and tive if evacuation Thyroid 25 adjust area for mandatory were not immediately and Above evacuation based on these possible.
levels. Control access.
(O (Emergency field teams and workers should be administered KI.)
____________________________________________________________________ l 4.5.23 (P) - If offsite evacuation has been recommended, the vernon County Sheriff may contact the ECD and request that LACBWR security personnel in a loudspeaker equipped truck, notify people in a sector around the ,
facility (depending on wind direction). The Security l Guard will maintain radio contact with the facility and l will, using the loudspeaker, notify residents to l evacuate in accordance with the instructions provided in the annual public education mailing (EPP-16). The Security Guard will be provided with a portable radiation monitoring instrument and will provide readings on indicated radiation fields to the plant. ;
4.5.24 (P) - Once the Technical Support Center has been l activated, establish liaison between the Control Room and the TSC. If the TSC/ EOF Data Acquisition System has not already shifted to its emergency mode of operation (Mode 2), manually shift it as per LACHWR Operating Manual, Volume IV, Section 11.
k INITIALS WP33 l
, Page 63 TABLE 1 EPP-2 :
ERAD/ ECD DAIRYLAND POWER COOPERATIVE Iseus 20 l
, ERAD/ ECD STATUS UPDATE FORM i
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. l DATE/ TIME /
O FOLLOW UP MESSAGES TO OFFSITE AGENCIES SHOULD CONTAIN THE FOLLOWING INFORMATION IF KNOWN AND APPROPRIATE.
STATUS: TIME CURRENT EAL INITIATED ACTUAL l] EXERCISE l]
CLASSIFICATION: ESCALATING l] DE-ESUALATING l] UNUSUALEVENTl]
ALERT l] SITE AREA EMERGENCY l] GENERAL EMERGENCY l] OTHER RELEASE UNDER WAY: YES l] NO l] TYPE PROJECTED DURATION s
RELEASE RATE: NOBLE GAS CI/SEC IODINE CI/SEC METEORLOGICAL DATA: WIND SPEED / WIND DIRECTION /
10M/100M 10M/100M AFFECTED SECTORS: STABILITY CLASS PRECIPITATION TYPE PROJECTED DOSE: LOCATION WHOLE BODY DOSE REM THYROID DOSE: REM PROTECTIVE ACTION RECOMMENDATION / PROGNOSIS:
'O ERAD SIGNATURE:
ANY ADDITIONAL MESSAGE:
ONSITE ASSISTANCE NEEDED:
ECD APPROVAL:
MESSAGE TO: SEND SENT SEND SENT SEND SENT
- - - ~ -
USNRC (REGION III) STATE OF WI R.A.7 JPIC -l l ~
USNRC R.A.P. -
USNRC (BETHESDA) [ ] HOUSTON CO. (CALEDONIA) [ [ IOWA
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f VERNON CO. (VIROQUA) _ _ STATE OF MN~(ROCHESTER) INPO _I i 4
d STATE OF WI (TOMAH) WW3 _ _ . STATE OF MN (ST. PAUL) _ _
OTHER s
- STATE OF WI'(MADISON) WW1 _ _ STATE OF MN'R.A.P.. _ _ l l
CALLER:
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j IRAD/ RAD TABLE 2 P4te 64 l DAIRTLAND POWER COOPERATIVE EPP-2 RADIOLOGICAL DATA PORM Issue 20
, DATE/ TIME /
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RELEASE: IN PROGRESS ~
MET DATA 3
POTENTIAL
$ NONE 10M 100M
]
RELEASE TTPE: WIND SPEED WIND DIRECTION i
, (1) AIRBORNE ] (2) LIQUID ,
of SURFACE ~
SPILL ~
AFFECTED SECTOR ELEVATED ~ CROUND STABILITT CLASS RIVER [ PRECIPITATION TTPE ONSITE SURVEYS DATA CALCULATED OFFSITE DOSE i
i (1) CB CRADE LEVEL (ARM 7) ares /hr (1) HIGHEST OFFSITE NOBLE CAS DOSE (2) HRCBARM EAST R/hr Rea in Mrs WEST R/hr SECTOR DISTANCE (3) HIGHEST RAD LEVELS (a) OUTSIDE C. B. (2) HICHEST OFFSITE RADI0 IODINE AT Ren in Mrs (b) SITE FENCE SECTOR DISTANCE I
AT i (4) AIRBORNE ACTIVITY EPP-5 CALCULATION (TSC) l 4
TOTAL I-131 WC1/cc 6 pC1/cc R THYROD CALCULATION (TSC) l
, COMPUTER CALCULATION (EOF) ] l STACK RELEASE DATA
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(1) STACK BLOWERS OPERATING:
+ -
l] O BLOWERS cc/sec Est. l] 1 BLOWER l] 2 BLOWERS 1.65 E7 cc/see 3.3 E7 cc/see (2) RELEASE CONCENTRATION FROM: SPING 3 l] SPINC&l]
NOBLE CAS (a) CH $ CONC WC1/cc x cc/sec
- 106=l C1/sec ALARM CONDITION l Release Rate (b) CH 7 CONC TBeqMev/cc x 7.0 E-4* x cc/sece106=l C1/sec
- I ALARM CONDITION l Release Rate RADI0 IODINE
- 106= C1/sec !
ALARM CONDITION Release Rate (d) NC CONC pC1/cc x .02 x cc/sec
- 106- C1/sec l Release Rate FIELD INFORMATION TEAM LOCATION SECTOR MILES FROM PLANT (1) IMMERSION DOSE RATES ADDITIONAL SAMPLES TAKEN Y ar/hr 8 arad/hr VECETATION NCPM S DIRECT (2) DIRECT GROUND READINGS SOIL NCPM 8 DIRECT cpeS E pC1/ cud PRECIPITATION (3) AIR SAMPLE READING MILK (a) PARTICULATE FILTER RIVER WATER cpu ! DC1/cc OTHERS (b) IODINE CARTRIDGE
, cpm ! DC1/cc i
ADDITIONAL INFO'JtATION
, (%.)
! *FOR 30 MINUTES TO 6 HOURS AFTER REACTOR SHUTDOWN. (USE 1.1 E-3 if Channel 9 YBeqMev/cc BEING USED.) l
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RECORD AND CONTROL OF INITIAL ISSUE, REVISIONS & PERIODIC REVIEWS l PREPARED BY OR EPC OPS. SUPV. QA. SUPV. H&S** DIR.ENV.AF. APPV'D*
l ISSUE PER. REVIEW BY REVIEW REVIEW REVIEW REVIEW REVIEW DATE I SIGN. DATE SIGN. DATE SIGN. DATE SIGN. DATE SIGN. DATE SIGN. DATE OF ISSUE 9
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EMERGENCY PLAN PROCEDURE l
ESTIMATE OF OFFSITE DOSE Issue Notice No. 9 Dateo, 6/20/85 INSTRUCTIONS Remove Insert Description of
, Old Page Nos. New Page Nos. and Reason for Change Remove and des- Insert Pages Delete Page 24 (Attachment B-troy Pages 0.1, 0.1, 0.2, 3, 5 DP/L-7) - no longer required, 0.2, 3, 5 thru thru 12, 15, and other minor changes.
12, 15, 23, and 23 of EPP-5, Revises conversion factors and 24 Issue 9. for YBeqMeV/cc to pCi/cc.
(Attachment B -
DP/L-7) of EPP-5, Issue 8.
(
PAGE SCHEDULE No. Issue No. Issue 0.1 9 13 7 0.2 9 14 7 1 7 15 9 2 7 16 7 3 9 17 6 4 7 18 6 5 9 19 6 6 9 20 6 7 9 21 6 8 9 22 7 9 9 23 9 10 9 11 9 12 9
()This issue shall not become effective unless accompanied by a new cover sheet properly signed off in the appropriate review / approval columns.
WP33 l
' Pcgs 3 EPP-5 Issue 9 4.6 D. Bruce Turner, Workbook of Atmospheric Dispersion Estimates, U.S. Department of Health, Education, and Welfare, revised 1970.
4.7 NUREG-0771, " Regulatory Impact of Nuclear Reactor Accident Source Term Assumptions," June 1981.
4.8 Shafer, P.W., DPC LAC-TR-107, " Potential Offsite Noble Gas Immersion Dose Rates and Radiciodine Child Thyroid Dose Equivalents for the 165 MW t LACBWR Following a Designed Basis " Maximum Credible Accident" and Theoretical Class-9 Type Accidents," January 1982.
4.9 NCRP Report No. 55, " Protection of the Thryoid Gland in [
the Event of Releases of Radioiodine," Oct. 1, 1979.
4.10 LACBWR Safeguards Report, ACNP-65544, August, 1967. l 4.11 10CFR50, " Domestic Licensing of Production and l Utilization Facilities," Section 50.47.
4.12 DP/L-7, " Interrogation of the ML9350 Data Logger," LACBWR I Meteorological Procedures Manual.
4.13 " Technical Evaluation of LACBWR Meteorological I (s) Monitoring Program 1983."
l 4.14 NUREG/CR-2644 (ENICO-ll10, "An Assessment of Offsite, l l
Real-Time Dose Measurement Systems for Emergency f Situations," April, 1982.
4.15 NUREG/CR-30ll (PNL-4491), " Dose Projection Consideration I for Emergency Conditions as Nuclear Power Plants," May, 1983.
4.16 NUREG/CR-30ll (PNL-4510), Volume 2, " Interactive Rapid !
Dose Assessment Model (IRDAM," June, 1983.
4.17 Till, John E. et.al. (Ed.), Radiological Assessment, NTIS, i September, 1983.
4.18 Pasquill, F.
Sons, 1983.
et.al., Atmospheric Diffusion, John Wiley and }
4.19 LACBWR Operating Manual, Volume X, Section 5.4.2.6.2, Table 5-1.1, and Figure 5.2.
4.20 Shafer, P.W., " Basis for NUREG-0737 Technical Specification Implementation," May 17, 1985.
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Pcgo 5 EPP-5 Issue 9 p
r 7.0 ESTIMATION OF OFFSITE DOSE 7.1 Selection of Offsite Dose Calculational Method There exist various methods (following this procedure) for calculating offsite noble gas immersion dose rate and radiciodine thyroid dose equivalent estimates which are available to DPC Emergency Response Personnel. Methods (2) and (3) are preferred. Calculate for downwind sector and one sector on each side. Report the highest dose calculated.
(1) Hand calculations using this procedure can be performed using a TI-59, HP-llc, or HP-33e. Calculators with this program are available at the plant.
(2) A computer-based program for offsite dose computations, "R Thyrod" is available in the TSC.
(3) A computer program available at the EOF may be used to j rapidly compute offsite adult and child radiciodine thyroid dose equivalent and noble gas gamma immersion dose '
rates. l
[] 7.2 Frequency of Offsite Calculation A_/
The offsite dose initially should be computed using the most recent historical hourly average meteorological data.
Following the availability of 15-minute average data, the offsite dose calculation should be made every 15 minutes and forwarded to the Radiological Assessment Director (RAD).
In the event of an extended release, forecast winds and stability information should be obtained from the National Weather Service (Section 8.0). Dose projections should l then be performed utilizing the forecast meteorological and radiological data. These dose projections should be forwarded to the ERAD, labelled as forecast data with expected time of occurrence.
7.3 Source of Meteorological Data The primary source of meteorological data is the onsite equipment in the Annex. These readings are available to the Control Room on strip chart recorders. The TSC and EOF have this information available to them on the l Data Acquisition System. The EOF can also contact the onsite meteorological computer directly. See Reference fs 4.12 for procedure.
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- Issue 9
(( ) 7.4 Choice of Dispersion Equations 7.4.1 Stack Release Dispersion Calculation:
Complete Data Sheet No. 1 for determination of the atmospheric dispersion characteristics at the various downwind distances. (Ref.: Section 7.7.1)
Calculate for the downwind sector and one sector on each side. Report the highest dose calculated.
7.4.2 Surface Release Dispersion Calculation:
Complete Data Sheet No. 2 for determination of the atmospheric dispersion characteristics at the various downwind distances. (Ref.: Section 7.7.2)
Calculate for the downwind sector and one sector on each side. Report the highest dose calculated.
7.5 Noble Gas Activity Release Determination:
Complete Data Sheet No. 3 for the determination of noble gas releases to the environment by using known concentrations (pCi/cc or Y Beq-MeV/cc) from Channel 05 or 07 (whichever is on scale) from the CT-2 microprocessor of the SPING-3/4, and multiplying this number times
T conversion factors to obtain a noble gas release rate in x) Ci/sec. If SPING-3/4 stack monitors are out of service, or to more accurately determine noble gas isotopic mixture and total pCi/cc to YBeg-MeV/cc conversion factor, Cy, take a flow-through 2.7-liter Marinelli at the SPING-4 in line at outlet of last gas chamber and analyze in lab to determine gas concentration in pCi/cc by Ge(Li) or HPGe Analysis in accordance with HSP-02.16.
7.5.1 The Sping 4, Channel 7, is considered to be the initial post accident noble gas monitor. Its alarm setpoints are set to alarm at YBeqMeV/cc values, which would correspond to approximately 2 and 500 mrem at the worst case receptor site under adverse meteorological conditions. (Channel 9 is set to alarm at approximately 1.0 and 5.0 Rem /hr under similar conditions.)
7.5.2 For long-term post-accident noble gas monitoring, samples of stack gas will be taken at the Sping 4 with a Marinelli, analyzed by germanium-MCA and the total pCi/cc compared to the Sping 4 Channel 7 or 9 YBeqMeV/cc readings to obtain adequate pCi/YBeqMeV conversion factors, Cy, for offsite dose calculations at different times after reactor shutdown.
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\- One can refer to Figure 5.2 of LACBWR Operating 7.5.3 Manual, Volume X, for an approximate direct conversion of Channel 7's indicated YBeqMeV/cc to pCi/cc at times after reactor shutdown ranging from 30 minutes to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
7.6 Iodine Activity (I-131) Release Determination:
Complete Data Sheet No. 3 for the determination of Iodine-131 releases to the environment by:
(1) using the known activity in 10 minutes (pCi/10 minutes) from Channel 03 from the CT-2 microprocessor of the SPING-3/4 and multiplying this number times appropriate conversion factors to obtain the I-131 release rate in Ci/sec.
(2) multiplying the noble gas release rate, in Ci/sec, times 0.02 to get radiciodine release rate, or (3) obtain a Ag-Zeolite or TEDA charcoal cartridge sample f rom the SPING-4 grab sampling capability or f rom the
~
stack atmospheric post-accident sampling system located in the No. 3 Feedwater Heater Area, and b(s)g Ge(Li) -MCA analyse this cartridge sample for I-131, I-132, I-133, I-134, and I-135 activity and convert to radiciodine release rate.
7.7 Formulas for Calculating Offsite Atmospheric Dispersion:
Air concentration values (X) are computed from the Gaussian plume diffusion formula:
X= 0 exp -1/2(y 2 + he2) (1)
Iloyzo U oy2 Q gs 6:
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. EPP-5 Issue 9 O' 7.7.1 Formula for stack release, centerline surface concentration (y=o):
XU100 = 1 exp -(he2) (2)
O Hoyzo 20 z2 WHERE:
X/O is relative concentration, in sec/m 3, H is 3.14159, U100 is windspeed at 100 meters above plant grade, in m/sec, oy is lateral plume spread, in m, a function of atmospheric stability and downwind distance (See Figure 1).
og is vertical plume spread, in m, a function of atmospheric stability and downwind distance (See Figure 2).
he is effective stack height, in m:
he = 115m - ht '
ht is the maximum terrain height above plant grade between the release point and the point for which the calculation is made, in m, ht cannot exceed 115m. If ht 2.115m, assume ht= ll5m, (he = 0).
Refer to Data Sheet No. I for calculations.
[ Equation 2 is automated on EOF computer.]
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O WP33
. Prgs 9 EPP-5 Issue 9 O 7.7.2 Formulas for surface release, centerline, surface concentration, and no plume rise, and building wake correction, from Regulatory Guide 1.145:
XU10 = 1 (3)
O Hoyo z + 330 XU10 = 1 (4) 0 3Ho yzo whichever equation gives the highest number.
Table 4 contains pre-tabulated results of these equations at selected downwind distances.
WHERE:
X/O is relative concentration in sec/m 3, H is 3.14159, U19 is mean windspeed at 10 meters above plant grade, in m/sec, oy is lateral plume spread, in m, a function of atmospheric stability and downwind distance (See Figure 1),
cz is vertical plume spread, in m, a function of atmospheric stability and downwind distance (See Figure 2),
Refer to Data Sheet 2 for calculations.
[ Equations 3 and 4 are automated on the computers.] l 7.8 For stack releases, terrain heights may be read off of a topographic map of the Genoa area, or refer to Table 1 for pre-tabulated terrain heights. (NOTE: The computers have g pretabulated terrain heights at preset downwind distances.)
7.9 For determination of stability class, the following methods should be employed.
7.9.1 If the AT is operable, refer to Table 2 for stability class.
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. Pcgo 10 EPP-5 Issue 9 (D
(_/ 7.9.2 If the AT is not operable, utilize surface wind speed, and outdoor observations as indicated in Table 3.
7.10 Once the atmospheric stability class is determined, the values for o y and a z for a given downwind distance (x) can be obtained from Table 5.
7.11 Using equations 2, 3 or 4 for stack or surface release respectively, the values of XU/0 can be evaluated by inserting the values for a y, a z, he , obtained in Steps 7.8 and 7.10 above. Record on Data Sheet No. 4.
7.12 In the event that either the 10M or 100M wind measurements (or both) are inoperable, the following methods should apply:
7.12.1 If 10M wind direction inoperable, substitute the 100M wind direction. Calculate for the downwind sector of interest and also two sectors on each side. Select the highest dose calculation to report.
7.12.2 If 10M wind speed in inoperable, substitute the following:
STABILITY CLASS FACTORa A 0.8 B 0.7 C 0.6 D 0.6 E 0.5 F 0.5 G 0.5 Substitute 10M Wind Speed = Factor x 100M Wind Speed (NOTE: This wind speed correction is automatically incorporated in the EOF l computer.)
7.12.3 If 100M wind direction is inoperable, substitute the Mound Ridge site wind direction. Calculate for the downwind sector of interest and also two sectors on each side. Select the highest dose calculation to report. DPC's Mound Ridge site ;
located on the ridge top 2 miles ESE of the LACBWR '
stack. Interrogate with automatic 300/1200 Baud O,' ASCII equivalent terminal. (Phone- 1-689-2142)
Follow procedure in Reference 4.12.
.- ' abased upon power law relat'ionship, EPA CRSTER~ Air'Ouality M'odel.
I WP33
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EPP-5 l Issue 9 l P
N_s) 7.12.4 If 100M wind speed is inoperable, substitute the Mound Ridge wind speed.
Substitute 100M Wind Speed = Mound Ridge Wind Speed DPC's Mound Ridge N.E. site located on the ridge top 2 miles ESE of the LACBWR stack. Interrogate with ASCII equivalent terminal with automatic 300/1200 Baud modem. (Phone: 1-689-2142) Follow procedure in Reference 4.12, 7.13 By multiplying the noble gas release rate in Ci/sec by the X/O on Data Sheet No. 4 and then multiplying the values of offsite noble gas concentrations in Ci/m 3 by the 3.1x105 (mrem /hr), the offsite noble gas immersion gamma Ci/m 3 dose equivalent rates can be determined.
The offsite noble gas immersion beta dose equivalent rates can be determined by multiplying the gamma dose equivalent rates on Data Sheet No. 4 by 1.68. The offsite skin dose equivalent rates can then be determined by adding the immersion gamma and beta dose equivalent rates and fs recording them on Data Sheet No. 4.
N_) 7.14 By multiplying the radiciodine release rate in Ci/sec by the X/O on Data Sheet No. 4, the values of offsite radioiodine concentrations in Ci/m3 can be determined. By knowing the projected offsite exposure times to radioiodine, the offsite infant and adult thyroid dose equivalents to radiciodine can be determined by utilizing Figure 1.
8.0 NATIONAL WEATHER SERVICE FORECAST INFORMATION 8.1 Required information for dose projection includes:
(1) Forecast wind speed and wind direction at release point height (10M or 100M)
(2) Forecast Pasquil/Gifford stability class. If N.W.S.
forecaster is unable to estimate this, a-determina-tion may have to be made following Table 3.
The above information may be obtained from Step 8.2.
8.2 Lacrosse, Wis. N.W.S. office telephone: NAWAS or 782-4533 (weekdays only)
/\ Milwaukee, Wis. N.W.S. office telephone: NAWAS or
\'J 414-744-8000
. (24-hour)
' Rochester, Minn. N.W.S. office telephone: 507-288-9609 WP33
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. Pago 12 EPP-5 Issue 9 s_/ 9.0 (1) If the SPING-3/4 Stack Monitors are inoperable and if no Ag-Zeolite or TEDA charcoal cartridge sample at SPING-4 or from stack PASS can be obtained and analyzed, or (2) If containment is isolated and an accident listed in the following categories has occurred with designed leakage at surface dispersion to the environment, and if no containment PASS atmospheric sample can be obtained and analyzed; the following corresponding estimated noble gas source strengths can be used as the noble gases release rate, and the estimated radiciodine source strengths can be used as the radioiodine release rate. (The radioiodine source strengths correspond to an estimated 0.24 -0.30 of the total noble gas source strength.)
Estimated Estimated Noble Gas Radiciodine Type of Accident Source Strength Source Strength
- 1. Release of 25% of Pressurized 2x10-2 Ci/sec 6.0x10-3 Ci/sec Holdup Tank
- 2. Release of 100% of Pressurized 8x10-2 Ci/sec 2.4x10-2 Ci/sec Holdup Tank
- 3. Heavy Object Dropped On Fuel 2.4x10-1 Ci/sec 7.2x10-2 Ci/sec In Core
() 4. Fuel Cask Drop 4.7 Ci/sec
@ Maximum
- 1.4 Ci/sec
@ Maximum
- 5. 1% Fuel Degradation + Loss to Containment (MCA)'+ Designed 5.0x10-3 Ci/sec 1.2x10-3 Ci/see Basis Containment Leakage @ Maximum @ Maximum
- 6. 10% Fuel Degradation and Loss to Containment (Class 9) and 0.1% Containment Volume Leakage / 5.0x10-2 Ci/sec 1.2x10-2 Ci/sec 24 Hours @ Maximum @ Maximum I
- Duration is expected not to exceed 100 seconds at which time the source strength should decrease to near normal levels.
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. _ _ . -- _. = -_ . - - - - . - . - . _ - - - . _ - _ _. . .
Pags 15 2
EPP-5
. Issua 9 DATA SHEET NO. 3
- DATE/ TIME /
(Previous) (Present) pCi 1-131 - UCi 1-131 = A pCi I-131 + 5.40 E4 cc/ Min.
I Min. = UCi/?? T 431
- 18. MULTIPLY THE NOBLE GAS CONCENTRATION (pCi/cc) BY 0.02 TO OBTAIN AN ESTIMATED l
l RADI0 IODINE CONCENTRATION.
1 pCi/cc NG x 0.02 2 pCi/cc Radioiodine l IC. OBTAIN A AG-ZEOLITE OR TEDA CHARC0AL CARTRIDGE SAMPLE FROM THE EFFLUENT STREAM AT THE SPING-4 GRAB SAMPLE PORTS OR FROM THE STACK ATMOSPHERIC PASS SYSTEM AS PER l
EPP-6. (IF USING A TEDA CARTRIDGE, IT MUST BE PURGED WITH AIR AT < 2.0 CFM FOR I
5 MINUTES TO REMOVE ALL ABSORBED NOBLE GASES PRIOR TO ANALYSIS.) >
RECORD SPECIFIC ACTIVITY #Ci/cc (I-131) + pCi/cc (I-132) +
uCi/cc (I-133) + #Ci/cc (I-134) + '
UCi/cc (I-135) =
pCi/cc Radioiodine
- 2. CALCULATE THE ESTIMATED RELEASE RATE (QI) FOR RADI0 IODINE BY MULTIPLYING THE HIGHEST SPECIFIC ACTIVITY IN 1A, IB OR IC BY THE STACK EXHAUST FLOW RATE.
I i a. 1 BLOWER = pCi/cc x 1.65 E7 cc/sec x IE-6 Ci/Sec = Ci/Sec
( b. 2 BLOWER = pCi/cc x 3.30 E7 cc/sec x IE-6 Ci/See = Ci/Sec 1
i NOBLE GASES ACTIVITY RELEASE DETERMINATION f *lA. RECORD SPING-3/4 SPECIFIC ACTIVITY FROM CHANNEL 5 = pCi/cc
]
- lB. RECORD SPING-4 SPECIFIC ACTIVITY FROM CHANNEL 7 (Y Beq-MeV/cc).
[USE THIS IF SPING-3/4 CHANNEL 5 IS > 0.05 pCi/cc.]**
Y Beq-MeV/cc TIME AFTER RX CV =
SHUTDOWN ( pCi/cc )
- MULTIPLY Y Beq-MeV/cc x Cv (Y Beq-MeV/cc) 30 MINUTES-1 HOUR 5.29 E-4 l Y Beq-MeV/cc x 1 HOUR-6 HOURS 6.90 E-4 l 6 HOURS-24 HOURS 1.00 E-3
= pCi/cc UNKNOWN Use 7.0 E-4 j - - _ __ _
i IC. IF SPING FAILS, OR TO VERIFY NOBLE GAS ISOTOPIC MIXTURE AND DETERMINE MORE l ACCURATE, Cv, OBTAI'3 A FLOW THROUGH MARINELLI SAMPLE AT THE SPING-4 AND GAMMA SCAN FOR TOTAL NOBLE GAS CONC. UCi/cc COMPARE WITH INDICATED SPING YBeqMeV/cc for Cv. i
! 2. CALCULATE THE ESTIMATED RELEASE RATE (Q) FOR NOBLE GASES BY MULTIPLYING THE HIGHEST VALUE FROM 1A , IB, or IC TIMES THE STACK EXHAUST FLOW RATE.
- a. I BLOWER = pCi/cc x'1.65 E7 cc/sec x IE-6 Ci/See = Ci/Sec
. b.. 2 BLOWER =. pCi/cc'x 3.30 E7 cc/sec x.1E-6 Ci/Sec = Ci/See
! -* Control Room Data f **For Sping-4 Channel 9 Cy = 1.1 E-3 l
i
. - - . , . - _ . . - _ . - - , - _ , , ,. . _ . . .___.-_,._-..._.,_....-,_..-....,_..,._.-.__,-.,_-__,.,-.,,,e.-- - e _.--s-s .~ ,
Pegn 23
, EPP-5
. Issua 9 ATTACHMENT A (i"\
U HORIZONTAL AND VERTICAL DISPERSION PARAMETERS FOR COMPUTER PROGRAMS g
ee y meters cy= aRb R = downwind range, meters Stability Class a b A 0.3658 0.9031 B 0.2751 0.9031 C 0.2089 0.9031 D 0.1471 0.9031 E 0.1046 0.9031 F 0.0722 0.9031 G 0.0481 0.9031 oe z meters
( ) oz = aRb+C Stability 100 <R <1000 R >1000 i Class a b c a b c I A 0.00066 1.941 9.27 0.00024 2.094 - 9.6 B 0.0382 1.149 3.3 0.055 1.098 2.0 C 0.113 0.911 0.0 0.113 0.911 0.0 D 0.222 0.725 -1.7 1.26 0.516 -13.0 E 0.211 0.678 -1.3 6.73 0.305 -34.0 F 0.086 0.74 -0.35 18.05 0.18 -48.6 G 0.052 0.74 -0.21 10.83 0.18 -29.2
REFERENCE:
NUREG-0324, X0QD0Q Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations, (Draf t,
[( August 1977), J. F. Sagendorf & J. T. Goll.
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- La Crosse ' Boiling Water Reactor eage o.1 EPP-6 o ! LACBWR
(/ op e EMERGENCY PLAN PROCEDURE SAMPLE COLLECTICN AND .TN? LYSIS DUPIl?G EMER';ENCIES
'WF m DA/RYLAND o' u lS$0(S!?
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x e RECORD AND CONTROL OF INITIAL ISSUE, REVISIONS & PERIODIC REVIEWS PREPARED BY OR EPC OPS. SUPV. QA SUPV. H&S** APPV'D & ISSUED
- ISSUE PERIODIC REVIEW BY REVIEW REVIEW REVIEW REVIEW EFFECTIVE DATE SIGNATURE DATE SIGN. DATE SIGN. DATE SIGN. DATE SIGN. DATE OF ISSUE
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O EPP **H&S Supv. or Rad. Prot. Engineer *LACBWR Plant Superintendent
n Paga 0.2 EPP-6 LACBWR EMERGENCY PLAN PROCEDURE SAMPLE COLLECTION AND ANALYSIS DURING EMERGENCIES Issue Notice No. 5 Dated 6/20/85 INSTRUCTIONS Remove Insert DescriTLion of Old Page Nos. New Page Nos. and Reason for Change Remove and des- Insert Pages Incorporate NRC troy Pages 0.1, 0.1, 0.2, 2, 3, recommendations.
0.2, 3, 4, 6, 7, 4, 6, 7, 10, 11,l 10, 11, 14, 16, 14, 16, 17, 18, 17, 18, 21, 22 21, 22, 29, and and 29 of EPP-6, 36 of EPP-6, Issue 4. Issue 5.
O PAGE SCHEDULE No. Issue No. Issue No. Issue No. Issue 0.1 4 11 5 23 2 35 2 0.2 4 12 2 24 2 36 2 1 2 13 2 25 2 2 5 14 5 26 2 3 5 15 4 27 2 4 5 16 5 28 2 5 2 17 5 29 5 6 5 18 5 30 2 7 5 19 2 31 2 8 2 20 2 32 2 9 2 21 5 33 2 10 5 22 S 34 2 (G This issue shall not become effective unless accompanied by a new
%) cover sheet properly signed off in the appropriate review / approval columns.
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- Paga 2 EPP-6 Issue 5
() 3.9 NRC Regulatory Guide 1.3, " Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of l
Coolant Accident for BWRs."
3.10 LACBWR Safeguards Report, ACNP-65544, August, 1967. l l
3.11 HSP-05.3, "Celorimetric Cl Determination." l 3.12 HSP-05.21," Chloride Determination In Selective Electrode." l 3.13 HSP-05.10, " Dissolved Oxygen Determination." l 3.14 HSP-05.19, "Colorimetric Boron Determination in Water." l 3.15 LACBWR Operating Manual, Volume II: l Section 6.5, " Containment Atmosphere Sampling Operations" Section 6.6, " Stack Gas Sampling Operations" Section 6.7, " Reactor Coolant Sampling Operations" 3.16 LAC-TR-115, " Calculations of LACBWR Post Accident Sampling l System Personnel Whole Body and Extremity Gamma Dose Equivalents," P. W. Shafer, May 1983.
3.17 LAC-TR-ll6, " Calculations of LACBWR Post Accident Stack l Iodine Sampling System, Personnel Whole Body and Extremity (s Dose Equivalents, P. W. Shafer, June 1983.
4.0 PREREQUISITES 4.1 Prior to any entry to the Radiological Restricted areas or their proximity during emergencies, calculations shall be made to determine the maximum allowable staytime in such areas. (Personnel cumulative dose estimates for various post accident samplings are found in Attachment E).
4.2 Comparisons must be made between the results of Step 4.1 and the known transit and sampling times for various activities around the plant:
(1) From Control Room to No. 3 FWH Area (PASS location) via Change Room and Radioanalytical Chemistry Lab and return to lab = 10 minutes total /5 minutes each .
way.
(2) Sampling for primary coolant via the Reactor Coolant PASS: 10 minutes including purging of lines and demineralized water dilution to at least a 4/1 ratio demin H 2 O to coolant.
O
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Pago 3
. EPP-6 Issue 5
/~'s tj
' (3) Sampling for Containment Building atmospheric sample l
via PASS including sample purge time = 10 minutes at 200 cc/ min.
(4) Sampling stack effluents for particulates, iodines and noble gases via the stack atmospheric PASS
= 5 minutes at 7.3 scfm.
(5) From Control Room to Sping-4 (T.B. Mezzanine) via Change Room. Sping-4 stack effluent particulate and charcoal cartridge changes - data collection, filter and cartridge change tne return with cartridge and filter to analytical chemistry laboratory
= 10 minutes.
4.3 In addition to the transit and sample collection times considered in the previous step, sample handling, preparation, and analysis times shall be considered prior to entry into the effected area. .For obtaining and '
preparing a Primary coolant sample for analysis via the PASS:
(a) 10-second contact cylinder disconnect time (1 cm from partielly shielded sample cylinder).
O (b) 5-minute cylinder transport time using a 1.75" thick Pb mobile pig with a 3-foot handle (91.4 cm from sample cylinder shielded by 1.75" Pb).
'l (c) 20-second contact cylinder reconnect time (1 cm l from partially shielded sample cylinder).
(d) 20-minute sample preparation time behind Pb [
bricks in laboratory hood (15.2 cm from sample cylinder shielded by 6" of Pb).
l l
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- Pcga 4 l EPP-6 !
Issue 5 l
'( _)g (2) For obtaining and preparing a Containment Building atmospheric sample for analysis via the PASS: l (a) 1-minute contact cylinder disconnect time (1 cm f rom unshielded sample cylinder).
(b) 15-minute cylinder handling time with 4" tongs (10 cm from unshielded sample cylinder).
(c) 5-minute cylinder transport time using a 1.75" thick Pb mobile pig with a 3-foot handle (91.4 cm from sample cylinder shielded by 1.75" Pb).
(d) 20-minute sample preparation time behind 6" of Pb bricks in laboratory hood (15.2 cm from sample cylinder shielded by 6" of Pb).
(3) For replacing and preparing SPING-4 filter and
~
cartridge for analysis:
(a) 1-minute removal of SPING filter / cartridge plugs.
(b) 10-second removal of cartridge retaining ring.
(c) 15-second placement of filter and cartridge in 1.75" Pb mobile pig.
(d) 5-minute cylinder transport time using a 1.75" thick Pb mobile pig with a 3-foot handle (91.4 cm from sample cylinder shielded by 1.75" Pb).
(e) 15-second removal from Pb pig with 48" tongs placed behind Pb in lab hood.
(f) 10-minute removal of AgZ from cartridge and cutting of filter paper through 6" Pb in hood at 10 cm.
4.4 The sum of the times and resulting exposures of Steps 4.2 and 4.3 shall be made prior to entry with the realization that some additional exposure will result during analysis of the samples. Total exposures shall not exceed the limits of General Design Criteria 19, Appendix A, 10CFR50 i (i.e. 5 Rem whole body, 75 Rem extremity).
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Pego 6 EPP-6 Issue 5 (m) 5.5.1 Set the potentiometers to the following scale values:
High Voltage--------3.60 Threshold-----------6.26 Window--------------0.20 Ensure the window switch is on (upward "in" position), the power switch is on (located on the back), and the test switch is off (to the right).
5.5.2 Using a Ba-133 check source, check the instrument response using a 1-minute count.
5.5.3 If a TEDA charcoal cartridge is used to collect radiciodines, noble gases will have to be purged to reduce Compton and annihilation radiation ef fects on SCA iodine analysis. If Ag-Zeolite is used, purging will not be necessary. If the dose rates at 1 cm f rom the cartridge are < 100 R/hr, proceed to next step. If the dose rates are > 100R/hr, disassemble cartridge per Step 6.2. 2. 5(a ) .
5.5.4 Insert the charcoal cartridge in the pig containing the SPA detector with the collection side (inlet O' side) facing the detector.
shelf (3rd of 5).
Place on the middle 5.5.5 Count the sample for one minute using the appropriate " timed" switch positions. Record the counts.
5.5.6 Adjust the " threshold" pot to 6.60 and recount the sample.
5.5.7 Subtract the value obtained in the second count (Step 5.5.6) from the counts obtained the first time (Step 5.5.5).
5.5.8 If the result of the preceding step is positive, multiply the net counts / minute by 4.15 E-5 pCi/ cpm j to obtain the pCi in the sample.
5.5.9 Divide the pCi by the sample volume of Step 5.3 to obtain the air concentration. The maximum permigg{ble for I concentration (MPC) for a 40-hour week without respiratory protection in a restricted area is 9.0 E-9 pCi/cc.
l O
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< 1 Page 7 EPP-6 Issue 5 l l
l 5.5.10 5.5.7 are negative, noble
(~-
x_ IftheresultsjnStyg8, gases.(e.g. Kr 8 , Xe etc.) may still be entrained on the cartridge. Use a SCBA spare air bottle at low flow rate to purge the cartridge of noble gases for at least 15 seconds by blowing air into the inlet side of the cartridge.
5.5.11 Attempt to repeat Step 5.5.5 through 5.5.8 to obtain a positive net count per minute value.
5.5.12 If negative results are still obtained, assume 10% I of the gross count rate in Step 5.5.5 are net I l31 counts per minute and complete Steps 5.5.8 and 5.5.9.
5.5.13 The sample may be held for decay of the short-lived noble gases (e.g. Xe138, Kr87, etc.) in 2 or 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> or analyzed on a multichannel analyzer when available.
I t
6.0 RADIOACTIVE EFFLUENT SAMPLE COLLECTION AND ANALYSIS DURING l ACCIDENTS 6.1 Offgas System Releases 6.1.1
() Provisions should be made to route the gases through the radioactive offgas system gas storage tanks if possible. This will provide indication of releases via the following monitors:
(1) SPING-3 (particulate, I-131, low- and mid-range noble gas) Stack Monitor.
(2) SPING-4 (particulate, I-131, extended range noble gases) Post Accident Stack Monitor.
(3) Victoreen Fuel Integrity Monitor.
(4) Tracerlab 10-Minute Holdup Tank Monitor.
6.2 Stack Releases (Offgas, Ventilation Exhaust, and Dilution Exhaust]
f WP33
e Page 10 EPP-6 Issue 5
/~T
(_/ 6.2.2.4 Bring the filter and/or cartridge to the '
lab for sample preparation. l 6.2.2.5 Place filter and/or cartridge behind Pb bricks inside lab hood. Measure y dose rates at 1 cm from filter and/or cartridge. If the dose rates are < 4 mR/hr at 1 cm, the cartridge / filter will be sealed in a plastic bag, and counted directly on the Ge(Li) detector at 10 cm extended geometry. If the dose rates are
> 4 mR/hr at 1 cm, the cartridge / filter l will have to be disassembled.
6.2.2.5 If the cartridge needs to be disassembled, (a) perform the following:
, (1) With a hole punch or cutter, cut open l the upstream face of the cartridge and remove the retaining filter paper exposing the charcoal /Ag Zeolite granules.
(2) Remove a small aliquot of charcoal /
fg Ag Zeolite granules and place them
( j into a preweighed planchet.
i (3) Determine the dose rate of the planchet containing the granules.
If < 4 mR/hr at 1 cm, continue with next step. If > 4 mrem, remove some of the charcoal granules until a dose rate of < 4 mrem /hr is obtained.
(4) Weigh the planchet and granules to determine the weight of the charcoal.
Weight of Charcoal (AgZ) and Planchet------------- g Weight of Planchet--------- g Weight of Charcoal (AgZ)--- g (5) Place planchet and granules inside a sealed platic bag. Label bag as radioactive materials.
(6) Determine I-131, I-133, and other radiciodines specific activities in pCi/g by counting the sample on a O
Ge(Li) detection system.
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Pags 11 EPP-6
[ Issue 5
[~h (7) Multiply the pCi/g for each isotope
\- by the total quantity of charcoal /Ag2 granules inside the cartridge as below:
FOR CHARCOAL pCi/g I-131 x 26.4 g(a) = pCi I-131 pCi/g I-133 x 26.4 g(a) = pCi I-133 pCi/g I- x 26.4 g(a) = pCi I-FOR AG-ZEOLITE
= pCi I-131 pCi/g I-131 x 70.0 g((b) b) = pCi I-133 pCi/g I-pCi/g I-133 xx 70.0 70.0 g g(b) =, pCi I-
- (a) Based on average weight of charcoal inside standard TEDA charcoal cartriges.
1 (b) Based on information supplied by Radeco on GY-130 AgZeolite cartridge.
(8) DividethetotalpCibyghetotal flow (lpm x minutes x 10 = cc)*
to obtain pCi/cc of the radiciodine q {(/] isotopes.
- Multiply by 28.32 to convert cfm to lpm.
6.2.2.5 If the filter paper needs to be (b) disassembled, perform the following:
(1) Cut out a 1-cm diameter piece of filter paper. l (2) Put the 1-cm filter piece on planchet. Place planchet in sealed plastic bag.
(3) Determine dose rates of planchet containing 1-cm diameter filter piece. If < 4 mR/hr at I cm, continue to next step. If > 4 mrem /hr, cut the filter into a smaller section until a dose rate of
< 4 mrem /hr is obtained.
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Prgo 14 EPP-6 Issue 5
() 7.0 SAMPLING OF REACTOR PRIMARY COOLANT DURING ACCIDENT CONDITIONS 7.1 During accident conditions, the Reactor Coolant PASS (located in the No. 3 FWH Area) will be the normal sampling location.
7.2 When it has been determined that a sample is to be taken, the HP Technician and one person to assist him shall:
(1) Review the LACBWR Operating Manual Procedure (Volume XI, Section 6.7) for operating the Reactor Coolant PASS System and perform the required walkthrough.
(2) When confident with the operating procedure, they shall proceed to the Radio-Chemical Lab and obtain the following equipment:
(a) One high-range survey meter - preferrably a meter with extended probe capability.
(b) Items listed in Section 7.4 found in the laboratory. l (3) Establish a shielded area, using lead bricks, inside the laboratory hood. This shall be of sufficient i size to reduce the possible high radiation levels of Cx the sample. Set up the mirror in back of hood.
Obtain necessary tongs, ring stand, hoses, etc.
(4) Ensure the transfer route is cleared of any obstacles.
(5) Ensure the ND6600, spectrophotometer, chloride probe, and mV meter, are operating properly. l 7.3 After the Health Physics Technician is confident all preparations for drawing a sample are complete, he shall report to the Onsite Radiological Assessment Director (RAD).
I
()
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Pago 16 EPP-6 Issue 5 I^')
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7.10 Increase the dilution ratio until a piping dose rate of less than 30 R/hr at 10 cm is obtained. A minimum dilution flow of 4/1 for severe fuel degradation is necessary to maintain doses below GDC-19 levels.
NOTE: The maximum dilution rate has been determined to be about 10/1, at which point dilution water pressure would cut off flow of reactor coolant with the I
reactor water pressure at less than approximately 60 psig. A dose rate of 30 R/hr at 10 cm would correspond to approximately 1000 R/hr at 1 cm from the cylinder. Refer to Attachment B.
7.11 Secure the sample system and obtain a final dose rate on the Al/Pb mobile shield (" Speed Wagon") and associated piping and tubing. If less than 30 R/hr at 10 cm, proceed i to Step 7.12. If not perform, Step 7.9 through Step 7.11 again.
7.12 The HP Technician will quickly di'sconnect the 10 cc sample cylinder from the flexible stainless steel tubing and then back off a safe distance.***
- Worst case dose equivalents are found in a technical study, Reference 3.16, Attachment B and E. j 7.13 Using the 3-foot T-handle and pull the " Speed Wagon" out of the No. 3 FWH area. If practical, assistant will measure dose rates to person pulling cask. Move cask to I the lab, locating the cask near hood. Measure dose rates.
7.14 Remove pin which secures Al/Pb shield assembly with 10 cc l cylinder to mobile cart.
7.15 Using Al/Pb shield top T-handle, lift Al/Pb shield assembly with 10 cc cylinder off the mobile cart platform, and transfer behind lead shield in the laboratory hood. l Using tongs, if practical, gently connect the sample valve [ i onto one end of the 10 cc cylinder housed inside the Al/Pb shield with hemispherical wing shield in the closed position, t
7.16 Measure the dose rate levels in the laboratory. Make sure extremity dosimeter is worn on the finger expected to be closest to the sample.
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. Pcgo 17 EPP-6 Issue 5 I'T 7.17 Utilizing the mirror placed onto the back of the lab hood, and lab tongs, place the sample depressurization line and l valve with the valve closed onto the other end quick disconnect of the sample cylinder housed inside the Al/Pb shield. Place far end of depressurization line inside large beaker of water and secure in place. Gently, crack l
open depressurization valve to bleed off cylinder pressure. Close valve. Move depressurization line out of beaker of water and attach to hook at about 2 to 3 feet above lab hood shelf. Gently crack open the depressurization valve. Next open the sample valve on other end of cylinder and allow coolant sample to flow into a vial shielded by a cylindrical pig behind lab hood Pb shield. Close valves on cylinder and place the A1/Pb shield assembly and cylinder onto the mobile cart and remove " Speed Wagon" from the lab.
7.18 The following analysis will have to be performed on the sample:
(1) pH (2) Chlorides (3) Gamma scan (4) Boron - If it has been injected into the primary system.
s s NOTE: During laboratory analysis the lab technician shall wear surgical gloves. Due to the possibly high levels of contamination, gloves should be changed routinely.
7.19 To obtain a gamma scan of the sample:
NOTE: If sample container has lower dose, it may be counted on the GeLi using the extended geometry and Job Stream.PASSPP.
(1) Insert a 100 um1 auto pipete into shield vial l containing coolant sample, and withdraw ~ 0.1 ml of coolant.
(2) Dilute this with 1000 ml of water in poly bottle behind shield. Place cap on bottle. Shake the bottle to mix the sample with dilution water in hood.
(3) Measure bottle dose rate, if < 4 mrem /hr at 4 inches, proceed to Step (4). If > 4 mrem /hr at 4 inches, dilute sample with an additional 1000 ml of water.
(4) Remove dilution bottle with coolant sample to center
() of lab bench on tray with absorbent paper. Transfer 10 ml of the diluted sample into a 10-cc vial.
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, Page 18 EPP-6 Issue 5 (5) Place the vial on No. 1 GeLi on the extension. l (6) Count the sample using Job Stream.VEXT.
(7) Report results to RAD.
7.20 The RAD can compare coolant isotopic concentrations with Attachment C to obtain approximate fuel degradation conditions, j 7.21 To obtain a Cl result:
(1) Insert the auto pipete into shielded sam)14 vial l containing coolant sample and withdraw 0.1 ml of coolant.
(2) Dilute to 100 ml of water. Measure dose rate of I sample.
(3) Follow procedure HSP-05.21 to complete analysis. l NOTE: There is now a dilution factor of 1000 which must be considered in the final result.
7.22 Obtain a pH on the coolant sample:
'f~h V (1) Insert the 100 uml auto pipete into shielded I sample vial containing coolant sample and withdraw =
0.1 ml of coolant.
(2) Place one drop of coolant onto a piece of pH indicating paper, which would have a indicated range between 4.0 and 7.0.
(3) Compare color results for pH.
7.23 To obtain a boron concentration if required: (Only performed if boron has been injected into reactor. Check this with OPD.)
(1) Insert 100 um1 auto pipete into shielded sample I vial containing coolant sample and withdraw ~ 0.1 ml of coolant.
(2) Dilute to 100 ml of water.
(3) Proceed with HSP-05.19 to complete the analysis.
NOTE: A dilution factor is 1000 for this analysis, j
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. Pags 21 EPP-6 Iccun 5 8.8 The Health Physics Technician shall contact the RAD to
(-)g
(_ inform them that they are about to establish flow in the Containment Building atmosphere PASS system.
8.9 Following the operating procedure for the Containment Building atmosphere PASS system, establish flow into the system.
NOTE: Constantly measure the piping dose rate.
8.10 Secure the sample system and obtain a final dose rate on the sample container.
8.11 The Assistant shall grasp the sample container with the extended tongs.
8.12 The HP Technician wi)1 quickly disconnect the sample container from the system and then back off a safe distance.
8.13 With the extension tongs, gently lower the sample container into the shielded transfer cask, if utilized.
Lift the 3-foot T-handle and pull the transfer cask out of the No. 3 FWH area. If practical, assistant will measure dose rates to persons pulling cask. Move cask to the lab, locating the cask near hood. Open transfer cask. Measure
() dose rates. If not using transfer cask, transfer cylinder lab using extension tongs.
8.14 Using the extension tongs, place the sample container behind the lead shield in the laboratory hood.
8.15 Measure the dose rate levels in the laboratory.
8.16 If the sample container has a dose rate of < 4 mrem /hr, it can be counted directly on the GeLi using Job Stream.PASGAS.
8.17 If the sample cylinder has a dose rate > 4.0 mrem /hr at 10 cm, dilution of the containment atmospheric sample will have to be done.
8.17.1 Conncei an ,vacuated 3.7-liter marinelli with
[
appt9P:hn valves, fittings, and pressure gauge to the quick disconnect at one end of the 300 cc sample cylinder behind the Pb bricks inside the lab hood. Crack open the valve on connected end of 300 cc cylinder. Slowly open corresponding valve on the 3.7-liter marinelli and equalize l pressure between cylinder and marinelli. [The
4 cc cylinder has been calculated to contain
! /~ = 1,360 cc of gas at 14.7 psia if containment has k-}- reached design basis pressure of 52 psig.]
Observe marinelli pressure which should be at 0 psig.
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c Pcgo 22
- EPP-6 Issue 5 8.18 Place 10-cc offgas syringe (designed to transfer l
() gases) into septum at available marinelli port. Open port valve. Draw out 10 cc sample of gas as you would with a normal offgas or sipping sample. Transfer to 10-cc evacuated vial.
8.19 Determine vial dose rate at 10 cm and if < 4 mR/hr, count on GeLi contact geometry; if > 4 mR/hr, count on extended geometry. (Refer to HSP-13.6 for proper ND6600 job stream.)
8.20 Report results to RAD.
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O O O ATTACHMENT D APPROXIMATE CONTAINMENT BUILDING ATMOSPHERIC ACTIVITY CONCENTRATIONS HRCBARM READINGS AND 300-CC PASS CYLINDER GAMMA DOSE RATES AT l-CM & 10-GM AS RELATED TO APPROXIMATE FUEL DEGRADATION CONDITIONSiaJ APPROX. CONTAINMENT PASS 300-CC SAMPLE APPROXIMATE INITIAL COMTAINMENT ACTIVITY CYLINDER y DOSE RATES APPROXIMATE HRCBARM CONCENTRATIONS (pCi/cc)(D) (R/HR)(c) FUEL DEGRADATION READINGS (R/HR) NOBLE GASES RADIOIODINES PARTICULATES @ l CM @ 10 CM CONDITION 6.0 EOS 4,830.0 1,184.0 119.0 160 39.4 100% Fuel Degra-dation, LOCA 6.0 E04 483.0 118.4 11.9 16.0 3.9 10% Fuel Degra- O dation, LOCA 6.0 E03 48.3 11.84 1.19 1.6 0.39 1% Fuel Degra-dation, LOCA 6.0 E02 4.83 1.18 0.12 0.16 0.039 0.1% Fuel Degra-dation, LOCA 4.0 E02 3.62 0.59 0.01 0.10 0.025 Major Fuel Gap Activity Lost, LOCA 70-100 0.67 0.16 0.01 0.02 0.005 1 Fuel Rod Degraded, LOCA 7-10 0.07 3.5 E-03 1.13 E-03 < 0.01 < 0.001 No Fuel Degra-dation, Loss of , i Activity to Containment 5
U2 T *
(a) Assumes 100% of the noble gases, 25% of the radiciodines and 1% of the particulates move froms &
the fuel to containment f ree air space and mix uniformly.
(b) Assumes containment isolated.
(c) Calculated by vu = SL '(0 1+0 2) for an approximate line source @ 10 cm since 4nr 2
SL = Sy wr or SL = Sy (l.563) at 10 cm, and sample cylinder height in = 36 cm.
WP33
Pago 36
?!!d s FIGURE 6 6 PEE DWAGON
- T" H AMDLE Pb LINING WALLS Al
'T'/4AMDLE Pb SHIELD REACTOR COOLANT STAIMLESS STEE L FLEX 16LE SAMPLE Lih)ES
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I/2" Al '
N t) lO cc SAMPLE CYL IM DER.
6El6MIC RETAIMiklC7
$ Plus o h RETAIMIMG PIM RETAINIM6 PIN-O "6 PEED WAGON" A'/Pb Md81LE POST ACCIDENT ,
REACTOR. COOLAMT SAMPLE SM IELD !
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La Crosse 'Boilind o Water Reactor Page 0.1 r- LACBWR k or EMERGENCY PLAN PROCEDURE DISTRIBUTION OF POTASSIUM IODIDE i [ 1. ~
g 'DAMYL AND
.._/ 5. !.?]??]T.. '
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RECORD AND CONTROL OF INITIAL ISSUE, REVISIONS & PERILDIC REVIEWS PREPARED BY OR EPC OPS. SUPV. QA.SUPV. H&S** APPV'D & ISSUED
- ISSUE PERIODIC REVIEW BY REVIEW REVIEW REVIEW REVIEW EFFECTIVE DATE SIGNATURE DATE SIGN. DATE SIGN. DATE SIGN. DATE SIGN. DATE OF ISSUE aWWA % S Hfl V 0A l o 2sn%"
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- Paga 0.2 i
EPP-9 g-) LACBWR U EMERGENCY PLAN PROCEDURE DISTRIBUTION OF POTASSIUM IODIDE Issue Notice No. 1 Dated 6/20/85 INSTRUCTIONS Remove Insert Description of Old Page Nos. New Page Nos. and Reason for Change Remove and des- Insert Pages Change Attachment B to a troy Pages 0.1, 0.1, 0.2, and 6 workable form.
0.2, and 6 of of EPP-9, EPP-9, Issue 0. Issue 1. .
l CE)
PAGE SCHEDULE No. Issue 0.1 1 0.2 1
- 1 0 l 2 0 t
3 0 4 0 5 0 6 1
/~ This issue shall not become effective unless accompanied by a new
(_}- cover sheet properly signed off in the appropriate review / approval columns.
EPP33 l - .-.- -- . - _ _ __ ._ _ _ _ _ . _ _ _ _ _ _ _ _ _ , _ . _ _ _
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.Pago 6 EPP-9 Issue 1
() ATTACHMENT B POTASSIUM IODIDE INVENTORY l i
(1) TSC SUPPLY INVENTORY DATE INVENTORIED BY POTASSIUM IODIDE EXPIRATION DATE i NUMBER OF BOTTLES OF KI AVAILABLE i
(2) GENOA 1 ASSEMBLY POINT SUPPLY INVENTORY DATE INVENTORIED BY ._____
i POTASSIUM IODIDE EXPIRATION DATE NUMBER OF BOTTLES OF KI AVAILABLE O
REVIEWED BY (H&S Supervisor)
(Emergency Preparedness Director) ,
i I
. (:)
EPP33 l
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La Crosse ' Boiling Water Reactor Page 0.1 o ! LACBWR Q qP EMERGENCY PLAN PROCEDURE s y EXERCISES AND DRILLS f DAMYLAND L k . . ~ ~ -
- ISSUE PERIODIC REVIEW BY REVIEW REVIEW REVIEW REVIEW EFFECTIVE DATE SIGNATURE DATE SIGN. DATE SIGN. DATE SIGN. DATE SIGN. DATE OF ISSUE
~~ . SIM, ? 22 N e OP 1, __ /*blti 3 .MA2 ctg 'c NEH O ? S l/ N &? t U. k llf ALhhk y/ ' r
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l EPP **ll&S Supv. or Rad. Prot. Engineer *LACBWR Plant Superintendent
9 Pago 0.2 EPP-17 1
LACBWR EMERGENCY PLAN PROCEDURE EXERCISES AND DRILLS Issue Notice No. 4 Dated 7/1/85 i INSTRUCTIONS Remove Insert Description of Old Page Nos. New Page Nos. and Reason for Change Remove and des- Insert Pages To incorporate Temporary troy Pages 0.1, 0.1, 0.2, and 2 Change.
0.2, and 2 of of EPP-17, EPP-17, Issue 3. Issue 4.
e O
PAGE SCHEDULE No. Issue 0.1 4 0.2 4 1 2 2 4 3 3
]
i 3 This issue shall not become ef fective unless accompanied by a new
) cover sheet properly signed off in the appropriate review / approval columns.
1 WP33 i
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EPP-17 Issue 4
' f3 Qualified personnel will observe and critique exercises
(_) 4.3 and drills. Overall results will be documented and reported to the Nuclear Emergency Preparedness Coordinator.
4.4 The Operations Review Committee shall review documentation of exercises. The Plant Superintendent will assign necessary corrective action activities.
5.0 REQUIREMENTS 5.1 Exercises (1) An exercise will be conducted approximately annually as determined with the Nuclear Regulatory Commission, State, and local agencies.
(2) This exercise requires coordination between LACBWR, State, and local authorities and other support agencies. The exercise will be prepared, with the cooperation of the Vernon County Sheriff, the County Civil Defense Director, and the Wisconsin or West Central Area Office of Emergency Government and will check out the actions required by these
,_ organizations.
\- (3) The exercise shall include notification of state and local personnel and resources adequate to verify the
. capability to respond to an accident scenario requiring response. The scenario should be varied from year to year such that all major elements of the plans and preparedness organizations are tested within a 5-year period. Normally this exercise will be performed between 8:00 AM and 4:00 PM. Each organization should make provisions to start and exercise between 6:00 PM and midnight and another between midnight and 6:00 AM and once every six years. Exercises should be conducted under various weather conditions as possible.
(4) During an exercise, the CAS Operator, Badge Issue Officer, SAS Operator, and Security Guard at the l front gate shall not evacuate their posts.
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