ML20042B176
| ML20042B176 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 03/08/1982 |
| From: | Rogers W GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20042B173 | List: |
| References | |
| PROC-820308, NUDOCS 8203250055 | |
| Download: ML20042B176 (45) | |
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REGULATOPY INFORMATION DISTRIBUTION SYSTEM (RIDS) ACCESSION NdR:020;;;;E3o 00C.0 ATE: 82/03/01, NUTARIZED; NO. DOCKET # FACIL:50-321 Edwin I. naten Nuclear Plant, Unit 1, Georgia Powee C 05000321 50-3o6 Eowin I, naten nuclear Plant, Unit 2, Georcia Power C 050003e6 AUTH.NAME AUTHOR ArFILIATION ROGERS,n.H. Georgia Power Co. RECIP.NA9E RECIPIENI AFFILIATION SuoJECT: Central rites version of reviseo emergency o1,an implementing prececures,incluoing Procedure nNP-4852 re offsite cose est4eations,HnP-4064 re tecnnical support ctr & Hi4P-4665 re manning of operational support ctr. Transmittal sheet enc 1, DISTRIBUTION C00E: x002S CARIES RECEIVE 0:LTH _L Er.CL _l SIZE:___'hhb____ . TITLE: Emere Plan (CF Avail) NOTES: HECIPIENT COPIES RECIPIENT COPIES IU CODE /NA*E LTTR ENCL 10 CODE /6AFE LTTA ENCL ACTION: ORu #4 BC 1 0 FAIRTILt,M. 01 1 1 INTEshAL: 02 1 1 FEMA-REP DIV 09 1 1 IE 06 d. 1 IE/DEP OIn 1 0 IE/DEP/EP06 Oo 1 1 IE/DEP/EPLB 03 3 3 (<RH/OSI/AEb i 1 NHR/DSI/RAB 1 0 REs FILES 0/ 1 1 N
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GEORGIA POWER CCMPANY HATCH NUCLEAR P.LANT . l PROCEDURE . l Off Site Dose Estimations PROCEDURE TITLE HNP-4852 - PROCEDURE NUMBER Health Physics RESPONSIBLE SECTION NON-SAFETY RELATED ( ) SAFETY RELATED (X) _ _ _ _ _ _ _ . _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . ._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . r_______--_______.c --______ APPROVED APPROVED DEPT. PLANT DATE REV. DESCRIPTION HEAD
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6' See Titia Page 1 of 24 OFF SITE DOSE ESTIMATIONS NOTE This procedure supercedes HNP-4650 Revision 2.$ A. PURPOSE To describe methods which may be used,for estimating off site raciation dose during emergency conditions at Plant Hatch. B. REFERENCE ,
- 1. Manual of Protective Action Guides and Protective Actions for Nuclear Incidents, E.P.A. .
- 2. HNP-4850 .
- 3. FbP-4854
- 4. Reg. Guide 1.145
- 5. Reg. Guide 1.109, Rev. 1 C. DISCUSSION This procedure details methods which may be used in the event of an emergency situation to evaluate radiological conditions in the environment in order to asssst plant personnel and responsible agencies (State Dept. of Natural Resources, GEMA, etc.) in making appropriate decisions to evaluate and control the hazard to public health and safety. Meteorological data will be passed along to the State Representatives as received but their estimates of thyroid doses are expected to be approximately 300 times higher due to the differences in iodine / noble gas ratio.
Section D outlines a methodology for prompt estimates of offsite exposure. Sections E and F utilize meteorological and plant release data, to calculate offsite exposures. Sections G. H. and I use field measurements along with graphs from reference 8.1 to estimate dose.
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..; o See Titla Pace - 2 of 24 O. PROMPT FSTIMATION OF CFFSTTE DOSE .
NOTE This methodology is meant to be used by Control Room staff for quick estimates of cifsite exposure. A number of conservative assumptions have been made and more detailed calculations per Sections E., F., G., H., and I. should be performed as soon as possible. Only thyrcid exposures are calculated since they will be the Jimiting exposure for protective action decisions. Whole body exposures are calculated at 0.018 times the thyroid exposure. Specific assumptions are:
- a. Iodine : Noble Gas ratio 0.001
- b. Child Thyroid Exposure '
- c. Site Boundary is at 1 mile
- 1. Determine. release rate in Ci/sec per.HNP-48SO. Record on Worksheet No. 4, Section 1.
- 2. Record other meteorological data as indicated on Worksheet No. 4, Section 2. Record an estimated duration (hours, l
minutes) of the release.
- 3. Using Atemp. or Pasquill category find and record the appropriate J factor for the type of release point (stack or building vent).
- 4. Calculate dose rate (D/t) and total dose estimtes per Worksheet No. 4, Sections 4 and 5.
- 5. Use total dose estimates with HNP-4854 to implement, as necessary, appropriate protective actions.
- 6. File Workeheet No. A for future reference or subsequent calculation.
E. ESTIMATTrN OF ACCUMULATFD_COyFS OFFSITF AT HICHFRT X n/O - USpjC MET _ DATA AND Pl. ANT REl.FAEF DATA NOTE Maximum offsite whole body and maximum offsite thyroid (via inhalation) dose increments are determined for each discrete time interval when the atmosphoric stability classification remains constant and when the wind blows into the same azimuthal sector. Average wind speeds and release rates over each dsscrete time interval are used in determinsng the done i.n c r eme n t s .
- Accumulated doces in each sector are obtained by summing the dona increments in thu indtvidual sectors. Running totals for each y sector are matntained by repeat.tng this procedure as required.
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- 1. Turn on Hewlett Packard - 97 calculator and load offsite dose program.
- 2. Record date, time and projected 21 time on Worksheet 1 (stack release) or Worksheet 2 (vent release). Person performing calculations should enter initials in the name column.
- 3. Record wind direction and use litemperature to define the atmospheric stability category using Table 1A. Record stability category on Worksheet 1 (or 2) as app r or,riate.
- 4. Using wind direction and stability category, de'. ermine Ju/G from Table 2 (vent release), Table 3 (stack release), o '-
Table 4 (stack-fumigation conditions). Record Xu/O on - worksheet NOTE , Fumigation conditions for stack release calculations should be assumed for the first 1/2 hour of a stack. release.
- 5. Record wind speed on Worksheet 1 (or 2). For stack releases multiply the indicated wind speed times the ratio from Table 1C to determine actual windspeed at stack height.
- 6. Determine Source Term (s) in #Ci/sec using HNP-4850 and record on workeheet or, if available, attach isotopic analysis data. If isotopic data is used, go to step 8.
NOTE Step 7 is for estimating maximum offsite doses with a single source term estimate. Steps 8 through 10 should be followed if isotopic releace data is available.
- 7. Enter data into calculator as follows:
- a. Xu/G - press enter key
- b. Windspeed - press enter key
- c. Press Subroutine A key
- d. Source term - press enter key -
- e. Press Run/Stop (R/S) key
- Proceed to Step 11 4
- 8. Enter tne following data into the calculator:
- a. Xu/O - press anter key
- b. Windspeed - press enter key
- c. Release flowrate (cfm) - prens enter key
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4 of 24 See Title Page , Using isotopic analysis data and Table 5, input data for 9. each isotope as follows: .
- a. Isotopic concentration (pCi/cc) piess enter key
- b. Whole body isotopic dose factor (Table 5) - press enter key - press enter key
- c. Thyroid isotopic dose factor (Table 5).
- d. Press Run/Stop key .-
- repeat this sequence until all data is entered.
N__OTE If "ND" (No Data) is listed in Table 5, enter zero for the thyroid dose factor. Likewise for noble gas activities.
- 10. When all. data is entered - press subroutine key C.
Record tim,e and Atime on isotopic printout and attach to dose Worksheet.
- 11. Record dose rate information from printer output on dose Worksheet(s). The first number printed is(See whole body dose example printer rate, the second is thyroid dose rate.
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- 12. Write initials, date and t.tme on calculator printout.
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- 13. Multiply whole body and thyroid dona rated by A t imo (in e hnurnt and record the incremental doses columns on the dose w o r k s h e a t e,. . .r ** in the Atime-dose essa h '. *-.
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- 14. Update the cumulative dose estimate by adding the newly calculated incremental doses to the previous cumulative doses.
- 15. Use the total dose estimates (sum cumulative doses from all worksheets) and HNP-4854 to determine and' implement appropriate protective actions.
- 16. If Protective Action Guides are being approached, notify the -
Dose Assessment Manager, ECF Manager, or Emergency Director. F. ESTIMATION OF ACCUMULATED DOSES OFFSITE AT SELECTFD POINTS OF INTEREST - USING MET DATA AND PLANT RELFASE DATA
- 1. If dose rates and cumulative dosas are to be calculated at a specific point of interest, determine the distance to that (Multip3y miles times 1609) point from the plant in meters.
- 2. Mark a clean copy of Worksheet 1 or 2 (or both) to identify the location and distance.
- 3. Record date, time and estime on the worksheet and initial the "Name" column. Record approximate direction of point of interest in the Wind Direction Column.
- 4. Calculate Xu/G using the procedure in Reg Guide 1.145 (attached). Use section 1.3.1 for vent releases and 1.3.2 for stack releases. Record Xu/O on work::heet.
- 5. Follow steps E.S through E.16 to complete the calculations.
G. EST_I_MATION_CE_ACCUMy(61EQ_CggFS_OEE@ITE - U@ LNG LIMITFD NUM@gR_DE EIELD MEASURE [.FNTS NOTE Using this method, a crude and very conservative pattern of estimated exposure rates can be developed by assuming that the exposure rate calculated for the plume centerline also axists at points equidistant from the source (release pnint) in the downwind sector (22 1/2 degreen) and in the two adjacent sectors. This 67 1/2 degree sector allown for wind meander and some uncertainty in wind direction. The use of this method w131 likely result in an overestimato of the exposure rate in all areas downwind of the measurement pcint.
- 1. Determine the direction of the centerline for the plume by using wind direction data from the Control Room and the area map in the emergency kit.
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- 2. Dispatch an External Survey Team to some known distance greater than one mile from the release point and toward the direction of the plume centerline. Have the team determine the center line exposure rate by traversing the plume while taking continuous dose rate measurements. The highest reading should be at the centerline of the plume. Locate this maximum reading on the area map.
- 3. WORMSHEET 3 -
a s, Determine the azimuth direction, sector, and distance from the measurement above to the release point, using the map scale. Record all data on Worksheet No. 3, including the time of measurement.
- b. For distances from the release point other than the above, the exposure rate may be estimated from the c following equation: .
D2 = L. R1 R2 Where: D. = Exposure rate measured at distance R1. D2 = Exposure rate at distance R2.
- c. Determine exposure rates for areas of interest downw.ind using the equation in Step 3.b and record on Worksheet l No. 3.
- d. Estimate the whole body and thyroid dose to members of the population per Section H. Compare results with protective action levels in HNP-4654 and in general emergency procedures.
H. _USING 1.ARGE NUQQER_OE ESTIMATTON_OF_ ACCU [Ul_ATFD_DCSES OFFSITE FIELD MEASUREMFNTS
- 1. Determine the direction of the center line for the plume by using wind direction data from the control room and the area map in the emergency kit.
- 2. Dispatch External Survey Teams in to the downwind sector (PP 1/2 degrees) and in to the two adjacent sectors. Several downwind distances should be monitored and 12inmiles eachdownwind.
sector such as at the cite boundary and 2. S. Specific locations, such as population centars, dairy herda, etc. will be of special interest. Have the teams determsnu
- dose rates, run asr samples, and collect samples per HNP-4G25 and HNP-4725.
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- 3. WORKSHEET 3
- a. Mark the dose rates plus any additional data on the area map at each location and on Worksheet 5.
- b. Calculate the whole body and thyroftd' dose to members of the population per Section H. Compare results with protective action levels in HNP-4854 and in HNP-4520 4E.20, 4720 procedures.
I. WHCt,E PODY AND THYROID DOSE CALCULATION
- 1. WORKSHEET 3
- a. Determine gamma exposure rates from Sections F or G. .
- b. Determine the time interval, delta T, between the present dose rate and previous dose rate measurements.
Record on Worksheet 3.
- c. Apply the gamma dose rate and the delta.T time period to Figure 1 to estimate incremental W.B. dose for time l period delta T.
- d. Multiply the gamma radiation level by 0.01 and repeat Step 1. c. above using Figure 2 to estimate incrementa.1 thyroid dose.
- NOTE If the radioiodine/ Noble gas activity ratio is known to be other than 0.001 use the appropriate correction factor in Figure 3 instead of 0.01'before using Figure 2.
- e. Calculate the accrued dose by summing the latest delta t interval dose and tha previous accrued dose,
- f. From Figure 2 determine the radiciodine concentration l and record.
- g. Projected accrued doses may also be estimated using Figures 1 & 2. l
- h. Compare the whole body and thyroid doses with protective action levels in HNP-4854 and in HNP-4520, 4E.20, 4720.
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-0.32 to +0.95 0 0 D
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- " Witid Direction Downwind Direction (Denrecc) (Sector) (Decrees) (Se ctor) 348.75 168.75 N S 011.25 191.25 NNE -
SSN 033.75 213.75 NE ' . [ _ ' SU 056.25 236.25 ' ENE 'WSW 073.75 258.75 E - W - 101.25 281.25 - ESE' WNU 123.75 303.75 , SE NW "146.25 326.25 SSE NNW
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N 191.25 - 011.25 SSU NNE 213.75 033.75 SW NE 236.25 056.25 - USU ENE 258.75 078.75 W E 281.25 ' 101.25 WSW ESE 303.75 123.75 N'1 SE 326.25 146.25 - HMW SSE 343.75 168.75 l --
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TABLE IC RATIO CF WIND SPEED AT HEIGHT OF STACK TO WIND SPFFD AT 1M FEET Pasguill Catenary Ratio - A 1.00 B 1.00 C 1.13 D 1.24 E 1.47 F 1.47
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See Title Page aav+o= = o.r. Georgia Power A ... Mee Title Page , 18 of 24 F_IGURE 4 Rgg. Guide 1.149 1Aug. 19791 (Excerpts) 1,3.1 Releases Through Vents or Other Building Penetrations This class of release modes includes all rslease points or areas that are effectively lower than two and one-half times the height of adjacent solid structures (Ref. 9). Within this class, two sets of meteorological conditions are treated differently, as follows:
- a. During neutral (D) or stable (E, F, or G) atmospheric stability conditions when the windspeed a t.the lO-meter level is less than G meters per second, horizontal plume meander can be considered. x/O values may be determined through selective use of the following set of equations for ground-level relative .
concentrations at the plume centerline: UI)
- x/Q = Uso(no yz o+ A/2) c-xfg . _
1 (2) Uso(3noyg o) where
~
r/O is relative concentration, in sec/m8, n is 3.14159, LIg is windspeed at 10 meters above plant grado,
- in m/sec, cy is lateral plume spread, in m, a function of atmospheric -
stability and distance (see Fig. 5), cz is vertical plume spread, in m. a function of atmospheric stability and distance (see Fig. 6),
- Tha lO-meter level is representative of the depth through which the plume ss mixed with building wake effects.
A is the smallest ve.-tical plane cross-sectsonal area of tha reactor buslding, in m O , (Other structures and/or a directional cons i <te ra tion may be justified when appropriate). x/O values should be calculated using Equations 1 & 2. The values from Equations 1 and 2 should " be compared and the higher value d selected. {) %. V= .fg' ,, M v * "4-Ig ;. a 6 2 ^ L,\%; km kn I l --
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19 of 24 Ame Titto Page FIOLEg 4 ( CCNTINL,jED ) 1.3.2 Stack Releases . This class of release modes includes all release points at levels that are two and one-half times the height of adjacent solid structures or higher (Ref.9). Nonfumigation and fumigation . conditions are treated separately. -
- a. For nonfumigation conditions. the equation for ground-level relative concentration at the plume centerline for stack releases is:
I (4) [h**r x/Q = _ exp nUh"y# 2
- where U is windspeed representing conditions h at the release height, in m/sec, is effective stack height. in m:
h* h, = h, - h . - Ww Q : g
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See Title Pace 23 of 24 g KSHFFT NO. 3 OFFSITE _D_ OSE _TA8_Lt.ATION DISTA! ICE FROM RELEASE: , AZIt.*UTil DIRECTI0ti: _ DEGREES ,- .
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JATE 11ME AT GAI*.t'A
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E. l. Httch Nucicar Plant a oa== ~o HNP.4852 = See Title Page um.o= =o Georgia Power A . . ... See Title Pace , 24 of 24 WORMSHEET NO. 4 PROMPT CFFSITF DOSE ESTIMATION
- 1. Determine release rate per HNP-4850 & record. S= pCi/sec
- 2. Pecord the following data' Date/ Time _ ________
Windspeed ~~ liTemp. ~~# F Pasquill Category _ Wind Direction _____ Est. Duration of Release ____ Release Point ___
- 3. Use /iTemp. or Pasquill Category to select J value from Table 6A J= _
for appropriate type of release point (stack or building vent). ,
~____________________,,_____________________m____________,, _ _ _ _ _ _ _ _ _ _ _ _ .
6 Temp. Pasquill Category J Stack J Vent abt ve t 0.95 F 9.92 E-4 2.60 E-4
-0.32 to + 0.95 E 5.06 E-4 1.75 E-4
-0.95 to + 0.32 D 2.66 E'-4 1.28 E-4
-1.1 to - 0.95 C 8.22 E-5 8.34 E-5
-1.2 to - 1.1 0 2.89 E-5 5.64 E-5 below - 1.2 A 3.14 E-6 4.36 E-5
- 4. Calculate Est. Dose Rate (Thyroid)
D/t = Sx J = mrem /hr Windspeed
- 5. Estimate total dose (Thyroid)
D = D/t x Est. Duration = mrem Sum of previous dose estimate + mrem Total Accum. Dose Estimate (Thyroid) mcem
- 6. Implement Protective Actions in Accordance with HNP-4RSI on( yNQ-4854.
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HATCH NUCLEAR PLANT PROCEDURE TECHNICAL SLPPORT CFNTFR
=- =-- -
PROCEDURE TITLE HNP-4PE4 __ PROCEDURE NUMBER LAB RESPONSIBLE SECTION . SAFETY RELATED ( x) NON-SAFETY RELATED ( ) APPROVED APPROVED REV. DESCRIPTION DEPT. PLANT DATE HEAD MANA% R O New Procedure g-__-------
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-- GeorgiaPower d a See Title Pace . 1 of 2 TECHNICAL SUPPORT CENTER, NOTE This procedure supercedes HNP-31, Revision 3, dated 1/5/82.
A. PURPOSE The Technical Support Center (TSC) is.a facility for use by plant ' management, technical, and engineering support personnel in an emergency situation to provide technical direction and support to the control room for mitigation of and recovery from the incident. Implicit in this function is the need to provide staff to do detailed plant analysis. B. MANNING REGUIREMENTS During any situation requiring activation.of the Technical Support Center (TSC), it will be manned by supervisory personnel from Engineering, Maintenance, Operations and Health Physics. The ranking license certified person will assume the position of TSC Manager. This will normally be an Assistant Plant Ma' nager, Superintendent of Plant and Engineering Services or Superintendent of Operations. In addition, the TSC wil l be manned with knowledgeable individuals to handle communications functions of the center. Other knowledgeable and qualified personnel may be directed by plant or corporate management to man the technical support center. These might typically include Southern Services, Bechtel, or General Electric personnel. In addition, an NRC representation in the Technical Support Center can be anticipated. C. CRITERIA FOR ACTIVATION The technical support center shall be activated and manned during any General Emergency, Site Area Emergency or Alert. D. TECHNICAL SUPPORT CENTER FUNCTION
- 1. The personnel ,.anning the technical support center shall function to;
- a. Coordinate emergency core cooling measures
- b. Coordinate radioactive effluent and control
- c. Coordinate core damage assessment f-e Tp pt")"t,N.1 ?gi d s ==
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- E.1. Hatch Nucl::cr Plant oct=ac ~o
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- See Title Page 2 Georgia Power d .
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- d. Coordinate the on-site operational ' support center (OSC)
- e. Interface with the USNRC and the Emergency Operations Facility .
- 2. Personnel manning the center shall.be grouped as necessary according to their respective disciplines to implement the above coordinating functions.
- 3. The T.S.C. shall maintain continuous communications link with the control room and E.O.F.
E. TSC_ PERSONNEL RESPONSIBILITIES
- 1. Assistant Plant Manager or his designee assumes overall -
commsnd of TSC operations. He is responsible for communications with the Emergency Director, the NRC, and offsite support agencies. ,
- 2. Superintendent of Plant Engineering Services or his designee He is responsible for assessing the status of the plant.
may request assistance from onsite or offsite technical experts. He may make recommendations for Control Room operations during plant recovery operations. He may provide the Assistant Plant Manager with evaluations for commuinication to the Emergency Director.
- 3. Superintendent of Operations or his designee is the He primary shall coistact for communications with the Control Room.
assist the Superintendent of Plant Engineering Services in assessing the status of the plant. He shall direct operations support of plant recovery.
- 4. Superintendent of Maintenance or his designee shall direct service or repair of equipment needed for plant recovery.
He should consult with the Superintendent of Operations for priorities and with the Laboratory Supervisor for equipment access and Health Physics protection of maintenance workers. He may direct offsite maintenance supervisors or mechanics to report to the plant.
- 5. The Laboratory Supervisor or his designee shall be responsible for monitoring the TSC for habitability and as necessary defining protective measures such as breathing apparatus or TSC evacuation to the Control Room. He shall assess and interpret radiological conditions in the plant.
He may recommend exposura limits and protective equipment In the for plant workers involved in recovery operations. event of actual or anticipated releases, he may make recommendations to the Assistant Plant Manager for communication t o t hs rge s=gn=n c y D i r e c t o r . y m '* T" P fjel. (i.J i ** D '= f. = .t" n a,14 %, =
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.. PRCCEDURE.
MANNING Cf7 CPFRATTONAf SttPPCRT CFNTFR
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PROCEDURE TITLE HNP-4865 PROCEDURE NUMSER - LAB __ RESPONSIBLE SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( ) APPRDVED APPROVFD REV. DESCRIPTION DEPT. PLANT' DATE HEAD MAN ^ f;ER O New Procedure j _ _ _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .. _ _ _ _ _ _ _ _ _ . . stl ________ ___- _.
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See Title Pace , . yJING OF CPERATIONAL SUPPORT CENTER NOTE , This procedure supercedes HNP-32, Revision 3, dated 1/5/82. A. PURPOSE The purpose of this procedure is to designate the location of and the personnel who shall report to the" Operational Support Center (OSC). B. GENERAL
- 1. The OSC shall be located in the Operations Office and Conference Room area in the Service Building Annex. OSC -
shall be activated for Alert, Site Area Emergency and General Emergency. , C. PROCEDURE Personnel authorized to report to the Operational Support Center are as follows:
- 1. The members of the plant operating organization on site as required by HNP-4521, 4621, and 4721.
- 2. All oncoming shift personnel.
- 3. Off site personnel, other than GPC, requested by the Emergency Director.
- 4. GPC plant personnel other than oncoming shift crew who are requested by the Emergency Director to report to site for support.
- 5. Personnel arriving at the Operational Support Center shall remain in the Center unless authorized by the Shift Supervisor or Plant Management to report to specific locations. In the event the Operational Support Center becomes uninhabitable these personnel shall report to a pre-designated area as directed by notification on the PA system, telephone or verbally.
- 6. The oncoming Shift Supervisor or Shift Foreman shall be in charge of the OSC and direct personnel to other araan as deemed necessary by the Shift Supervisor on duty or Plant Management.
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~~. PROCEDURE' RE_ PAIR __AND CORRECTIVE ACTION FOLt..OWI_NG E RADIOt.OGICAL FMf RCFNC
\ ' PROCEDURE TITLE
--_ - HNP -4. R_ E.E. - -
PROCEDURE NUMBER
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RESPONSIBLE SECTION
==
SAFETY RELATED ( X ) NON-SAFETY RELATED ( )
..-_____-___---___p________
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APPROVED APPROVED DEPT. PLANT DATE REV. DESCRIPTION
- HEAD MANAGER O New Procedure /// [ } _ - _ _ _ - ..-__ (_, --___-___r___ m a --_.
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, HNP- 4866 E,. o o See Title Pags h9
- GeorgiaPower A . . .
9 op 7 Ane Title Page , REPAIR AND CORRECTIVE ACTION E06 LOWING A PADICLOGICAL_ EMERGENCY A. PURPOSE The purpose of this procedure is to provide.suidance to ensure that doses to workers performing repair and corrective action functions during an emergency situation are maintained as low as is reasonably achievable.
- 8. REFERFNCES
~1. NUREG-0654, " Criteria for Preparatson and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants." .
- 2. EPA-520/1 ,75 001, " Manual o'f Protective Action Guides and Protective Actions for Nuclear Incidsnts." ,
- 3. NCRP #39, " Basic Radiation Protection Criteria."
- 4. HNP-8002, " Radiation Exposure Limits."
- 5. HNP-4812 " Emergency Exposure Guidelines" C. ACCESS CONTROL
- 1. During an emergency, access to the protected area will be controlled. In addition, access to all areas beyond C-SP will require specific authorization and will be limited to personnel who are needed to provide specific functions in the Turbine and/or Reactor Buildings. An example of the personnel who will receive authorized clearance to these areas are: Control Room personnel, personnal on the fire brigade. PET members for the purpose of internal surveys and
. personnel required for repair and corrective action
* ;' , functions. A list of Control Roem personnel requiring
,' access shall be provided by the TSC manager or his
,b6' designee. All oth9r personnel shall require authorization
~, ' f! ' ' - s from the OSC manager or his designee after consultation with "v the TSC manager.
~.
., s Access for personnel to High Radiation Areas shall have more
' stringent requirements to be discussed in a later section of this procedure.
D. EXPOS! !RF L I MITS AND AUTHOR I Z AT TON 1.- All exposures to personnel are to be kept as low as is reasonably achievable. This pertains to all personnal who are required to remain on site during an emergency situation for the purposes of accident recovery. MANUAL SET
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E. I. Httch Nucicar Plant -ou =ac~o
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HNP- 4866
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- 2. Exposure to the whole body shall be limited to 300 mrem / week. Any expected whole body radiation exposure above 300 mrem in any one week shall necessitate the completion of HNP-8002 Form 2 " Authorization to Exceed Administrative Exposure Guides" by the indicated parties.-
- 3. Exposure to the whole body shall also be limited to 1,250 mrem / quarter. Any expected whole body exposure in excess of 1,250 mrem in any one quarter shall also necessitate the completion of HNP-8002, Form 2 " Authorization to Exceed Administrative Exposure Guides" by the indicated parties.
- 4. In some instances during emergency conditions it may be necessary to exceed 10CFR2O Exposure limits. In such instances, refer to HNP-4812, " Emergency Exposure Guidelines" for guidance. The Emergency Director, or his .
designee, are given the authority to permit these exposures.
- 5. Exposure of emergency workers to any level is justified only if it is determined that benefits to society are being achieved and efforts are being made to keep exposures ALARA.
E. CONDITIONS OF EXPOSURE
- 1. Persons performing the planned actions should be volunteers broadly familiar with exposure consequences.
- 2. Women capable of reproduction shall not take part in these actions.
- 3. Internal exposures shall be minimized by respiratory protection, and contamination controlled by use of protective clothing.
- 4. Workers that are to perform the required actions should be well trained in the jobs that they will be performing to cut down on the amount of time they need to spend in the area (c).
F. RAOIATTON WORK PERMITS
- 1. Whenever practical, an RWP should be initiated before any work is performed.
P. The most current survey snformation available for the area in which the work is to be performed is to be used unless conditions exist or there are indications that the radia t s on levels sn the area have sncreased osgnificantly.
- 3. Area Radiatson Monitors (ARM's) are to be used to the extent possible sn predicting general area radiatson levels.
u m. m MANUAL SET
E. l. Hntch Nucicar Plant oc= e ~o
^~ w' HNP. 4866
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atmoi mo See Title Page
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- 4. If there is not enough information regarding the radiation levels in the areas (s) to be entered or new up-to-date information is deemed necessary, the TSC Manager, after consultation with HP Supervision, may elect to send an Internal Survey Team, comprised of RET members, into the area to determine the radiation levels.,
- 5. All survey information should be placed on the appropriate Routine or Special Survey Map (See HNP-8012), whenever ,
practical. The use of these maps will aid in the routing of workers in the area, determining stay times and making man-rem estimates.
- 6. All areas that are surveyed are to be surveyed for Beta dose rates in addition to Gamma dose rates. All smears that are taken are to be counted for Beta activity as well as Gamma activity. .
- 7. It may be necessary, in some instanc'es, that the work needs to be done immediately. In such instances, the TSC managar, after consultation with H. P. Supervision, may elect to appoint an internal survey team, or member, to accompany the repair and corrective action team, to survey the area while In such instances, it may also the work is being performed.
be necessary to complete all documentation at a later time.
- 8. Low volume and/or High volume air samplers are to be used to the extent practical in determining airborne concentrations. In addition to these air samplers, CAM's and CIM CAM's will be used where appropriate in airborne concentration determinations. Isotopic compositions should also be performed to evaluate radiciodine concentrations.
G. EXPQBLIRE_CQNTROL
- 1. No personnel, other than Internal Survey Team members, may enter an area whare dose rates are not known, except as stated in F.7 above.
- 2. Personnel shall not enter areas where dose rates are beyond the ranDe of instruments being used.
- 3. Personnel shall be equipped with dosimeters capable of measuring anticipated doses. This shall include, but not ba limited to:
- a. Two direct reading pencil dostmeters for whole body exposure:
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- E. l. Hctch Nucinar Plant HNP- 48G6 aEv's'o " o See Title Page
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- b. A Thermoluminescent Oosimeter -(TLD) to permanently record whole body exposure.
Extremity dosimeters when the extremity exposure rate c. is likely to be four (4) times the whole body exposure rate and the extremity exposure rate is likely to be The extremity dosimeter (s) 400 mrem /hr or greater. is/are to be worn on that part of the body that is likely to receive the exposure. _
- d. A digital alarming dosimeter (0-10 The R) with areadout and digital predetermined alarm set point.
the alarm will enhance the worker's knowledge of his accrued dose.
- 4. Protective clothing shall always be worn by workers entering -
areas for the purposes of repair and corrective action. The minimum dress requirements shall be: ,
- a. One pair of cotton gloves
- b. One pair of rubber gloves
- c. One pair of cloth booties
- d. One pair of rubber booties In the event that more stringent requirements are specified on the RWP, or by H. P. Supervision, then those requi rements shall prevail.
- 5. Respirators shall be worn as appropriate. In all cases where airborne contamination is anticipated, personnel shall be fitted with pressure / demand Self Contained Breathing Apparatus (SCBA) as a minimum.
- 6. Potassium Iodine (MI) tablets should be administered to all personnel who are likely to inhale 2.3 uCi D.E. I-131 or greater. This decision is to be based on the results of previous Whole Body Counts and the projected exposure. HP Supervision shall make the final determination on whether or not KI should be issued.
- 7. All workers upon leaving a high airborne radioactivity area will be decontaminated as necessary and then given a wholo body r. o u n t . If indicated, other bicassay methods may be used An addition to the whole body count.
H. ALAR?A COtGIDFRATIONS
- 1. In order to maintain radiation exposures to personnel performing repair and corrective action functions during
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- P'T'* 3" emergency conditions as low as is reasonably achievable, the
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- a. Prebriefing-All workers that are to be sent into High Radiation Areas should be made aware of the dose rates in the area, stay times, and airborne concentrations.
All workers should be familiar with exposure consequences. An attempt should be made to estimate the total man-rem exposure of the prescribed action, based on radiation levels and man-hour estimates, and all attempts should be made to keep exposures below this estimate. Some of the methods that may be used to accomplish this are as folfows: (1) The workers should be informed of the magnitudes and locations of significant radiation sources at the task location or accesses, and should also be informed of low exposure waiting areas, if any, that are to be used when necessary. Using the most current survey information or anticipated
. levels, the workers should,be informed of the best way to reach their destination (i.e., the route that would result in the lowest exposures). Since the workers will most likely be wearing SCBA equipment, consideration should be given to reducing the amount of time needed to reach their destination since they will only have 30 minutes
. of supplied air.
The personnel in attendance at the pre-briefing should be: the work crew; a Lab Supervisor or Foreman; a Maintenance Supervisor or Foreman; the OSC Manager; and a Shift Supervisor or Foreman. (2) A tool list should be developed prior to entry, such that a worker is well equipped to perform the required actions. Since a lot of time will probably be used in reaching the destination, care should be taken to reduce the number of trips needed. (3) Consideration should be given to the use of special tools that may reduce the amount of time spent in the area, or that will enable the workar to handle " hot" pipes or valves remotely. These should only be used, however. by workers who are I familiar with their operation. (4) Consideration should be given to the prefabrication of systems outsids to the Hsgh Radiation Areas which would result in less time j being spent for the required action. ( ~~ [ (5) Considoration should be gsven to the removal of
" ' j,", i h % .. systems to be worked on from high exposure rate areas to low exposure rate areas, i f p rac t s cal, to further reduce exposures to workers.
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' aamio= % See Title Page Georgia Power ks Mao Title Ppoe . 6 of 7 (6) Consideration should be given to the use of communication systems (such as walkie-talkies, headsets, etc.) so that any problems or difficulties that are encountered may be related back to supervisory personnel for discussion or Comment. , (7) Workers that are to perform the required actions should be well trained in the job (s) that they will be performing in' order to cut down on the amount of time they need to spend in the area (s).
- b. Job Execution-Although prebriefing is an essential step in maintaining radiation exposures to station personnel ALARA, implementation o' exposure controls during the execution of a jr5 is the primary mechanism for -
maintaining radiosion exposures as low as is reasonably achievable. Scme examples of e,xposure controls methods that should be utilized are as follows: (1) In order to reduce internal doses, the proper respiratory protection equipment must be worn by all persons who have the potential of inhaling airborne radioactive materials. (2) Protective clothing needs to be worn to reduce the liklihood of skin contamination. (3) Time, distance, and shielding are the most effective ways of reducing exposures and must be utilized where- and whenever possible. (4) Proper communication between workers in high radiation areas and supervisory personnel who are monitoring the operations from other locations is essential in identifying problems incurrod during execution of the required actions. This will ba enhanced through the use of communication systems such as walkie-talkies or headsets.
- c. Post-briefing-Performance of this step will help in planning future jobs by using a type of " lessons learned" approach.
The personnel in attendance at the post-briefing should be: the work crew; a Lab Supervisor or Foreman; a Maintenance Supervisor or Foreman; the OGC Manager; and a Shift Supervisor or Foreman. The imoortance of this step stems from the p 7 { { Q [, M Nj ;.a'&=( 1 ) posstbstity that it may become necessary to g h "y 1, , g im 2 perform subsequent similar. actions during
,, 7 emergency conditions.
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7 of 7 Mao Ti+1a P2CL . . (2) Any problem or recommendations.that arise should be documented for the purposes of planning and execution of subsequent actions. These recommendations should be expressed by anyone involved in the operation. . (3) The degree of success or failure should be reviewed upon completion of each job and should also be documented for further use. I. EFFLUFNT RELEASES NOTE Due to the increased likelihood of fuel failure during an accident condition particular care must be taken in analyzing all releases. In addition to performing isotopics on a GeLi detector, all gaseous effluent filters must be measured for Beta emitters, particularly Sr-90. Refer to appropriate HNP-7000 series procedures for analysis. 6 9 l I E 4 a.7. N. . . ; a }Y b A, n ? 11 \/
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e GEORGIA PCWER COMPANY HATCH NUCLEAR PLANT PROCEDURE Review and Revision of Emergency Plan
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and Imnlementinj1 Procedures ~ ~ PIIUCEDURE TITLE HNP-4891 PROCEDURE NUMBER ,
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RESPONSIBLE SECTION - SAFETY RELATED ( X ) NON-SAFETY RELATED ( ) APPROVED APPROVED REV. DESCRIPTION . DEPT. PLANT DATE HEAD . MANAGER Pages 1, 2, 3&4 g 1 Deletion on Page 1
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, taws.o~ ~o See Title Page Georgia Power I ..e. ~o App T4+1p Page . 1 of 4 REVIEW AND REVISION OF_EMERGFNCY_ PLAN AND IMPLEMENTING PROCEDURES A. PURPOSE . To describe generally the methods for review,of emergency plans, agreements, and procedures. B. FREQUENgY (MINIMUM) .
- 1. Emergency Planning Coordinator Resgonsibili_tr Emergency Plan - Update as necessary; review and certify to be current annually.
Agreements - Update as needed; review and certify to be current annually. Procedures - Review annually and revise as needed. Emergency Call List - Update quarterly.
- 2. Indegendent Review Groug Resgonsibility Emergency plan, procedures, practices, training, readiness testing, equipment, and interfaces with State and local l governments -review nominally every twelve months, the interval from the previous review may be shortened, -but may
- not be extended beyond 15 months.
C. EMERGENgY PLANNING CCORDINATQR (EPC) The EPC will be responsible for reviewing and revising where necessary; the emergency plan, procedures, agreements, and call lists at the frequency in Section B. Documentation and scheduling of the procedure reviews will be through the use o' the normal plant procedure review process. Certification that the plan and agreements are current will be stated in Data Package 1 (Data Sheet 1). M v ~ .2.3=
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- c. It!DEPFNDEN LREVIFW CRCtjP, in The onsite GA organization shall conduct the review described Section B. Documentation for this review will be by report to the SRB and Plant Manager and to offsite agenci,es as appropriate.
E. EVell.lATION OF REVIEWS _AND RECOMMENQEQ_ CHANGE $ The PRB and SRB will review recommenced changes to the emergency plan, and agreements. The PRB will review recommended changes to emergency procedures and call lists. The PRB and SRB will evaluate the report on the independent - review and will assume implementation of the corrections which they deem appropriate. .
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3 of 4 See Title Pace . PROCEDL9E DATA PACNACE DOCt. MENT PC: Hre-4391-1 SERIAL PC: 001-PPL NO: N/A RTYPE: C15.03 XREF: N/A TOTAL STETS: 2 FREQUENCY: Annug1* COPPLETED BY: DATE COMPtiTED: 1 HA%E REVIE'40 THIS CATA PACHACE FCR CCNLETENESS NO ACA!rGT ACCEPTNJCE CRITERI A IN ACCCROANCE WITH HP#-830. ACCEPTNJCE UNACCEPTABLE REV!DCD DY: DATE REv!FWED: j REMARMS: 1 i Page 1 of J! HP48-4801 RO1
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* .1Di oEPCRf DATE The Emergency Plan and Agreemente have been revie ed and ars =
certified to be current. Emergency Plannsng Coordanator Page 2 of 2 HM'-48 31 ROI 4, s.- n *,1 % w f.R 3 ese
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