ML20081L946
| ML20081L946 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 10/12/1983 |
| From: | Thomas Greene, Nix H, Rogers W GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20081L933 | List: |
| References | |
| PROC-831012-01, NUDOCS 8311160488 | |
| Download: ML20081L946 (183) | |
Text
{{#Wiki_filter:. GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PROCEDURE OffsitiRadiological Eny.irome.ntal Monitar.fsj ouring Emer_pncias PROCEDURE TITLE
. HNP-4827
? PROCEDURE NUMBER
. Lab
. RESPONSIBLE SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( )
- _________________________. . _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ . L________________ F_______.
APPROVED APPROVED REV, DESCRIPTION' DEPT. PLANT DATE HEAD MAN ER r__ ____ _____ _ F______. 0 New Procedure ( _ _ .F
, q Fg_ _g 4_. _
- 1 1 Pages 1 thru 15 . g r____________________. - _ _ _ . __________ ___ _ _ _ _ _ _ _
F___ ______ _____ F__.
.r___________.r___________ _ r________ ___
r__. F____.________.F_____. F________________ F_____. ______ s____________________. r________________ F____________-___ F_______. F_ ___ __ _ _____ F___________ - __ F______. i 1 ( .__.p_---______m..h -_-__--_- _ h ____ _.p___.== r____ _ _________.____ _ F________________ F________________.r_______. r___ __ F_________..__ F_______________. _ _ _ _ _ _ _ . r____________________ F________________ p________________. _______. F____________________ F________________ F________________. _ _ _ _ _ _ _ . F____________________ F________________ F________________+ _ _ _ _ _ _ _ . l ._____ ____________________ F _______________ F________________ - _ _ _ _ _ _ .
._____. ____________________F________________p________________ _ _ _ _ _ _ _ .
i l HNP-9 8311160488 831110 PDR ADOCK 05000321 , F pog l i j maae at set Dr'
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** ;- PROCEDUDE REVIGIObl REGUEGT PROCECURE NO. I-NP-NT SHEET 1 OF.j,_,
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Revision No. O -
-_..x__.._______.-
OEPARTMENT WEAD APPROVAL REQUESTED UY = Signeture: Da te: Name: . Date: 9 iz B 9 fy
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REVISION CHANGES ( NOOE) Yes OF CFERATION (K) No GR INTENT AS DESCR Cl-lANGE IN'JOLVES:
/. ) An unrevieweri Safety Guestion ( ) Tech. Specs. ([) Neither (See back for GaFety Evaluation if required).
Safety Related ( K) Non-Safety Related ( ) f PRESENT STATUS:
) Yes to - - , ,
The above Safety /Non-Dafety Status has changed ( , Attach marI<ed up copy of procedure to this form. REASON FOR REGUEST: 70 k_Mesred - u o fewest 3_p(_-b This lab cur off5 . . . . . . . . . . . . . .
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J - DESCRIP'TTON OF CH/.NGES: _ _ _ Md__fi .D - PRD RECGMMF OS APPROVAL (Y)Ves ( )No PRB Secretary
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SAFETY
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EVALUATION .. -. ___...___. _ . . . _ . . . , . , lg . t t constitute aa unreviewed safety question as explained , f.. _Tpis revis.j_on_does no _
~ _
be.l--ow. - - . _ - - l'. 'The probab.i.lity_o_f _o.cc.urrence and the c_o.nsequences o_f an accident or i-IP.a.l_functi.g.n._o.f,_egu_i.pment impor_ tan,t to sa,,fety are not increase _
- t. hose analyz_e_d.._in the FSAR du_e to this revision becau_s_e_th_e P. __
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-.qe.3 not__c, hance'the pur_ pose oi perf_ormance of the aystem.
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T ~ T.] .K . __ l, _- i * ) l} . _ . _ __ - _ lp g different type than _ _?u T. h_g,,pgssibili.ty_ of an accident or malfunction of a _ ana.yzedl _ _in the FSAR does not result from this revision because the i u.e...m. .re.sp.o._nd_s _and is operated as before the revision. s ,
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yy p(w- _-. l 1 _ _ ---_J.4x ifications is
..____ [ The margin of safett as defined in the Technical Spec not redu ed due to this revision because the revision does not change _
h would allow a safety limit
.anylimited_s5fetysystemsettingswhic ll _ _ . .
i to be
'..t_o be exceeded or allow a limiting condition for operat ons
~ r excebded as_ stated in Technical Specifications.
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Ese Title Paae 1 of 15 4 OFFSITE R@lQLOGICAL ENVIROMENTAL MONITORING RyRING_EMERGENCIgg i i-t!QIE This prociedure supercedes FN'-4625 Rev. 5 and Fe@-4725 Rev 5. A. PURPOSE
~
To provide a method for the determination of radiological
' conditions in the plant environs, due to_the release of radioactive materials from the plant under accident conditions. .
'Also, this procedure will provide instructions for integrated-offsite survey teams consisting of some combination of state, local, and GPC. personnel.
B. ggFINITIONS APO Tgt!@
- 1. EOF - Emergency Operations Facility , t
- 2. REC - State Radiological Emergency Coordinator
- 3. RET.- Radiological Emergency Team
- 4. Dose Assessment Management - Integrated state, local, and GPC personnel collectively consisting of the Dose Assessment Manager,-the REC, and lead personnel from local civil defense organizations.
C. SCOPE
- 1. The activities of the offsite monitoring teams will generally be performed in the Emergency Planning. Zones t
- (EPZ), from the plant to distance of approximately (but not l limited to) 10 miles.
l
- 2. Offsite monitoring teams will be under the direction of the
. Dose Assessment Management in the EOF.
(
- NOTE It is understood that the ultimate responsibility
' - fo'r offsite radiological environmental monitoring rests with the State.
D. REFERENCES
- 1. FN2-4620 " Site Area Emergency"
- 2. HPF-8142 " Stabilized Assay Meter SAM-2 Operation and Ca1ibration"
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- 1. , leam Composition a.l* The' teams are expected to generally consist of 3 of 4
- persons, depending upon the avilability of personnel and the nature of the mission to be performed.
Functions to be performed may include: (1) Driver (2) Navigator (3) Data Recorder (4) In-transit Instrument Reader (5) Field Sampler (6) Communicator (7) Sample Taker (8) Sample Analyzer
- b. The Dose Assessment Management shall designate a team captain for each monitoring team. The team captain.
shall assign responsibility for each of the above functions (as applicable) to individual team members. Team members may be assigned responsibility for multiple functions. The team captain is responsible for assuring that all necessary actions are performed.
- 2. Team Responsibilities
- a. Collect environmenta2 media.
- b. Conduct radiological field measurements (plume monitoring) with readings by location.
, c. Conduct air monitoring by location.
- d. Communicate sample analysis data, dose rate informetion, and personnel dosimetry to the EOF.
F. ACTI6NS
- 1. Radiological Emergency Team personnel should meet in the EOF to get instructions, find out the events that have taken P lace, 'and to be assigned to a monitoring team.
- 2. The Dose Assessment Management is to divide personnel into teams using combinations of state, local, and GPC personnel. Teams should consist of a max of 4 people (avg.
3). 4-East at let - 70008')
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HNP- 4827 Sao Titlo Pcg3 acoso. w 2 i GeorgiaPower d .. See Title Pace 3 of 15
- 3. Offsite teams may use vehicles equipped with two-way communication devices belonging to GPC, the state, or the
, ' locals as appropriate. In addition, portable radios and antennas.obtained from the EDF will be used as alternative com'm ' uni cations. If personal vehicles are used, the portable radios and antennas will be the primary communication system and the Bell system as an alternative.
- 4. The Dose Assessment Management shall designate a team captain for each team.
- 5. Once the teams and team captains have been designated, each team captain will be responsible for assigning each member of his team certain tasks, ie, driver of the vehicle, navigator, data recorder, in-transit instrument reader, field sampler, communicator, sample taker, and sample analyzer. ,
- 6. Upon the classification of an ALERT level emergency, the ,
offsite teams may be activated at the discretion of the Dose Assessment Management. If the classification is a SITE AREA or GENERAL Emergency, teams shall be activated. The Dose Assessment Management directs the staffing and deployment.
- 7. Dbtain a survey team kit at the EOF.
- 8. Complete the checklist in Data Package 1, Data Sheet 1.
- 9. After the equipment is checked for operability, the monitoring team will establish communications with the EDF.
- 10. Turn on survey instruments, allow them to warm up, and j verify response with the check source provided.
- 11. Install glass fiber filter and silver zeolite cartridge in sample holder of air sampler. Turn on sampler and confirm j proper operation. Turn off.
~
- 12. Proceed to area specified by Dose Assessment Management.
1 -
- 13. While in transit, survey meter for measuring dose is turned on. The instrument is positioned for continuous viewing and ready a'ccess for recording readings. If readings above l
l background are detected, record appropriate information on l Data Package 2, Data Sheet 1.
- a. Indicate observed readings on survey map. (Report any
[ indication of a plume to the EDF). Record on Data Package 2, Data Sheet 1.
- b. Record time entering the plume as indicated by the survey meter reading on Data Package 2, Data Sheet 2.
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See Title Paae 4 of 15 c.c . If dose rate is in. excess of 5 mr/hr, report reading to the EOF.
.* - NQIE
-Minimize traversing of.the plume as much as pr.actical to maintain exposures ALARA. Contact the EOF prior to exceeding any administrative exposure guidelines. Provide periodic personnel.
exposure updates to the EOF when exposures'are considered significant. Record personnel exposure. data in Data Package 2, Data Sheet 1.
- 14. Upon arrival at the sampling location, perform a dose rate a survey in the following manner:
- a. At waist level, hold GM probe HP-210 or GM survey meter (or equivalent) with the window facing up, read meter, and record results on Data. Package 2, Data Sheet 2. ,
- b. 'At 2" above the ground, hold GM probe with detector window facing the ground, read meter, and record results on Data Package 2, Data Sheet 2.
- c. At waist level, hold high range survey meter horizontal, read and record dose rate on Data Package 2, Data Sheet 2. ,
l d. Repeat step c above, but at 2" from the. ground.
- 15. Take air sample at designated area when requested by Dose l! ~ Assessment Management as follows:
- a. Place a silver zeolite (AgX) cartridge in the sample f.
head, and. mark the cartridge to specify the inlet side of the cartridge. Place a particulate filter upstream of the AgX cartridge, and place the sample head in the air sampler.
.b. With the engine running, connect the air sampler power leads to the vehicle battery, taking care to connect the positive and negative cables to the positive and
' - ~
negative battery terminals respectively.
- c. Start air sampler and record time of Data Package 2, Data Sheet 2.
- d. Check air flow indication and record flow rate.
- e. Run air sampler 10 minutes, record flow rate from I calibration sticker on Data Package 2, Data Sheet 2.
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. sample times.
f.'-Make radiation survey as in step 14 above while running the air sampler. NOTE If levels are greater than 10 mr/hr report reading to the EDF and await instruction from the Dose Assessment Management.
- g. Remove the AgX cartridge and particulate filter from the sampler head, and place in separate plastic bags.
- h. Air samples should be labeled and a log entry made in the log book of the following information: ,
Date and start time of sample Duration of sample Flow rate of sample Location of saraple point (map location, landmarks, etc.) Survey team name Air sampler number SAM-2 Analyzer serial number (if used) NOTE During air samoling, monitoring teams should observe the dose rate instrument for significant changes in dose rates. Report any significant
, changes to the EDF. Record personnel doses on Data Package 2, Data Sheet 2 while sampling.
l
- i. Insert GM survey meter probe (HP-210) into sample holder _(SH-4A) and record background reading.
.j. Place glass fiber filter in SH-4A holder and obtain reading (CPM). Calculate airborne concentration per l
Data Package 2, Data Sheet 3. j I k. Place silver zeolite cartridge (which has been placed I in plastic bags) directly against orobe (HP-210). l Obtain reading (cpm) and calculate airborne l concentration per Data Package 2s Data Sheet 3. (pci/cc) l l
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~
-If SAM-2 Counters are available, ,artridges may,be counted using Hlf-8142 and HNP-4826.
..' Record data on Data Package 2, Data Sheet 2 as CPM (net).
- 1. Place sample. filters in envelopes.and record on envelopes time, location, flow, sample time, cpm, background, and air activity. Hold for further analysis at place EOF.
- 16. Collect soil, vegetation and water samples when requested by the Dose Assessment Management, as follows:
- a. .Take bag (mark-it soil) and small scoop, fill with surface soil from a bare-spot, tape closed, and tag with the date, time, and location. -
- b. Take bag (mark it. vegetation) and scissors. Cut .
vegetation approximately two (2) inches above ground, fill bag, tape closed, and tag with the'date, time and location. (If-possible, choose vegetation that might be ingested by animals).
- c. Fill poly bottle with surface water, close and tag with date, time and location.
- 17. Record time out of the plume on Data Package 2, Data Sheet 2, and determine total stay time.
- 18. Report all results to EOF and await further instructions.
Document all results in Data Package 2.
- 19. When. directed by the Dose Assessment Management, proceed to environmental TLD and air sample cabinet locations. Change out TLD and filters at the stations noting time and date of
, change-out. Return samples to the EOF.
. 20. Return all data sheets fo the EDF for review, analysis and temporary storage. These data sheets shall be permanently stored in Document Control upon termination of the emergency . -con d i t i'on. i f Base al Set l
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;- PROCEDURE DATA PACKAGE DOCUMENT NO: HNP-4827-1_
- ?. SERIAL NO: R_Q1-MPL NO:
RTYPE:__q15 01 XREF: TOTAL SFEETS: 2 FREQUENCY: COMPLETED BY: DATC COMPLETED: 4 I HAVC RCVIEWCD THIS DATA PACHACC FOR COPOLETENESS AND AGAINST ACCEPTANCE CRITERIA IN ACCORDANCE WITH HtP-830. ACCEPTADLE UNACCEPTADLE
. REVIO'CD BY:
DATE REVIEWED: REMARKS: Page 1 of 2 HNP-4827 RO1 FIGURE 3 Page 1 of 2 mass at set I"
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!$2!1IQBING TEAM CHEQSIGI .
Data Sheet 1 A. ' Inventory Hit and Vgrify Necg11ggn1.tgma
- 1. -SAM-2'Analyaer (optional)
- a. Battery and source check
- 2. Surey Instruments
- a. Battery and source check
- 3. AgX Cartridges 4 Particulate Filters
- 5. Calculator
- 6. Stop Watch
- 7. Log Book
- 8. Cample Dags .
- 9. ' Pocket dosimeters
- 10. T'.D s
- 11. EOF Telephone Numbers (in log book)
- 12. Airborne Activity Calculation Form
.13. Gloves 14 Tweezers
- 15. Labeling Materials (labels, pens, etc)
- 16. Maps and Procedures
- 17. Spare Datteries
~
- 13. 01ank Gmears
- 19. " Portable Air Sampler
- 20. Sample, Bottles 21'.' +P 310 Probe / Holder D. Prior to departing the [Q[nverify the f ollgwingj,
, 1,. Survey instrument in cab and on lowest scale
- 2. Team members equipped with dosametry
- 3. Maps in cab
- 4. Vehicle radio check completed Page 2 of 2 HNP-4827 R01 FIGURE 3 Page 2 of 2 massai set I-m a.. -
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PROCEDURE DATA PACKAGE DOct. PENT NO: HNP-4827-g
- C. SERIAL NO: RO1-PFL NO:
RTYPE:__q1L92 XREF: TOTAL SFEETS:_5 . FREQUENCY: COMPLETED BY: DATE COMPLETED: I HAVC REVIEWED THIS DATA PACKAGE FOR COPPLETENESS AND AGAINLI ACCEPTANCE CRITERIA IN ACCORDANCE WITH HM'-830. ACCEPTADLE UNACCEPTADLE REVIEWED BY: DATC REVIEWED:
~
. REMARMC:
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. DATA PACHAG Lg Data Sheet 1 Utenetseing Teen Page of Date EXPtzsIE NATE M EIPtMAIE DEASAIEpWi? QATA FGIFI
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** LOCAT!tps TIsE BJtWV CROs@ LEWI. PERW7 EEL DIIIECT ?!86 IpeTutJEpiT ter NAT tat RLeotn c DDatserTwi2- ME-penne PGITED S R P QTSER 2 metee 1 metee Contact samme seeme tadt/hr 3 todt/hel tadt the p t edt ) (sp > tadt p
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CG GITIG9 MI1El la. Peteessian sed &de (Nt3 recammended. **Locatiefta te, sector. la. Esp'esure rate 25 mA/hr ed radtetedine easless directed othere.ase Dr Dese este marker, derection, 183 Il a6e 6s not knesen. destance, read sagne. Accessment Management. lanenseks. Pesy e* s. etc. 2a. Total espesure 100 udt. Ea. Centact Dese Assessment Management and advise. D. Total espesure 3 A. D. Evacuatsen recomumended. unless directed otherease er Oese Assessment Menagement.
- c. Total espesure 25 R. c. Evacuatsen mandatory, contact Dese Assessment management.
g: Anrtame espesure rate geester se egual to 25 aft /he t regardless of air actavstr3. Dese Assessment Remagement must to contacted. S
- Setter n e Male
- P e Sample Pesnt fl.27 Page 2 of 5 HNP-4327 RO1 FIGURE 4 Page 2 of 5 mass ai set I 700e80
I, == E. l. H:tch Nucl;;r Pl:nt **ce== = 1 HNP- 4827 - av'8** = Sea.Titio Pega- g 2 c Georgia Power al . See Title Paae 13 of 15 t E.
- 96TA PACHAQQ_g Data Sheet 2
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l- OFFSITE EMERGENCY MONITORLNG TEAM Team Date Time entering plume Time Exiting Plume Plume Stay Time Sample: Loca Gon Sample Time On Sample Time Off Flow Rate: LPM Sampler Type Serial Number qR,ggS_AlRQORNC ACTIVITY -(Class Fiber Filter) (Sample t background CPM) CPM (Background CPM) CPM (Sample + background CPM)-(background CPM)= Corrected CPM CPM (net)* From Figure 1 particulate airborne concentration = uci/cc** Serial Number
- Instrument Type 1991LC_0lR00RNQ_AQTIVl_TY (AgX Filter)
(Sample i background CPM) CPM (Background CPM) (Sample t background CPM)-(Dackground CPM)= Corrected CPM CPM (net)* From Figure 2 Todine Airborne concentration = uci/cc** From Data Sheet 3 Thyroid Dose Rate mc/hr Instrument Type Serial Number COUNT /DOQQ RATG_gtJJ,g Count / dose rate while in transat CPM Mr/hr l . Count rate @ waist level (window facing down) CPM Count rate @ 2' from. ground (window facing ground) CPM { Dose rate @ waist level Mr/hr i .
- Dose cate G 2* from ground Mr/hr 1 - -
l -Instrument type Serial Number l' Instrument type Serial Nuttber I Page 3 of 5 HNP-4827 RO1 i FIGURE 4 Page 3 of 5 .. , [ q" . g\-
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S o Titlo Pago ! o.,, . Georgia Power v.- - , Mme Title Page 14 of 15 , I 4 _ QATA PACKAG L2_IGONT) Data Sheet 2 OFFSITE EMCRGENCY MON 11 @ltn_Iget! PERSCNEL DDSIPETRY*** Time Team member Dose mr Team member Dose mr Team member ~* Dose mr Team member Dose mr QAt![LEQ_QQLLEQILQ Direct radiation TLD's Milk V8getation Well Water Soil _ Drinking Water from surface source Other (specify) Other (specify)
~ *
- Note: If GAM-2 used record CPM (net) as instrument reading.
** Note: If activity (CPM), flow rate (LPM). or sample times (min) are different from informatson on Figures 1 & 2 use Data Gheet 3 for calculations and record results on Data Sheet 2 (pci/cc).
*** Note: Read and record personnel doseimtry at least one time while at each sample location. (More frequently if does rates are high).
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I i l l - . Page 4 of 5 HNP-4827 RO1 FIGURE 4 Page 4 of 5 See al 809 t+; z -
^ ~=va'. E.1. H::tch Nuclzr PI:nt aociova. o HNP- 4827 a aevisio e Sao Titic Peg 2 2
om a Georgia Power d ... See Title Paa*' 15 of 15 e _
. QATA PAQACgJ Data Sheet 3 ENVIROPfENTAL AIRBORNE ACTIVITY CALCtLATION FORM
- 1. Net Particulate (CPM) (from Data Sheet 2)
- 2. Nethodine(CPM) (from Data Sheet 2)
- 3. Sample , time min. (from Data Sheet 2) 4.- Flow rate LPM (from Data Sheet 2)
Pgr11g,y1313
- 5. Gross Airborne Concentration = ,
Particulate ( CPM (net) (4.5E-9) _________ _______--______ = pci/cc * ( LPM) ( min.) 1941n1 G. Airborne Concentration = Iodine l ( CPM (net) (4.5E-8)
-------- ---------------- = pci/cc
( LPM) ( min.)
- 7. Thyroid Dose Rate =
(line 5 pci/cc) x (1.85Ef3 mr/hr/pci/cc) = mr/hr
*If a SAM-2 is used the graphs are not usable. The formuld following must be used:
i l .(Net CPM) (1.5 E-9) ' -------------------- for charcoal cartridge (volume in liters)
~ ~(net CPM) (1.58 E-9)
-------------------- for silver zeolite (volume in liters)
I ' i l
- Page 5 of 5
' HNP-4827 RO1 FIGURE 4 i Page 5 of 5 L w mese at let i
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U' ] GEORGIA POWER COMPANY t HATCH NUCLEAR PLANT PROCEDURE - \(~~)%
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Radiation and Contamination Control PROCEDURE TITLE HNP-ROOS
.- PROCEDLtRE NUMBER Lab RESPONSIRLE SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( )
- - - - - -.. - - _ - - - - - - - - - - - _ - - - - --s----------------a- --------------..--------
APPROVED APPROVED REV. DESCRIPTION DEPT. PLANT DATE HEAD MAN ER . 12 General Revision N m j
------ .------ ---_---------- JJ. -- - --
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-13 Pages 2, 4,14 & 16 _- %g ye _f_ _t'..
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- - 14 .
General Revision
- 4. *t4
_- -.-- - - f6 1 #d'u' 15 Pages 8 & 9
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-Q3D b PROCCOURE REUTF. TON REGO.GT .
- OC'l -- J PROCEDURE NO. HNP- T OO N__ SHEET 1 OF__G_
Revision No. / __,
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IkGUESTEDOY DEPICTt_f.ENT l.CZ5 t,PPROVAL Date: c' a
----~
ej Name: - , h=]& Q bW A't MG. bar cu3 0 3 3 $ ~A //Lj ,g j REVISION CHANGES NODE OF EF ERATION OR It T AS DESCRICED IN FSAR:
'( ) Yes ( ,) No CIVNGE INVOLVES:
(- ) An unreviewed Safety Guestion ( ) Tech. Specs. ()(, ) Neither (See tiack .for Saf ety Evaluation if required). Safety Related (K) Non-Gafety Related (- ) PPESENT STATUS: The above. Safety /Non-Safei y Status has changed ( ) Yes to . , , _ Attach marked up copy _of procedure to this form. REASON FOR REGUEST: \D Qf;cf QC f u 0 Q<&M4 b Q0aC tyy u.QL _ t.0k 99__gj,wdtic 10 90 s o i G L' bbcdok Vtak K__ ,
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'P R B S e c r e t a'i' y 8.3-176 q,4. g PRO Numbee Date
- HNP-9
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]. 36EETY We%UATIQi ___ . . _..._ _ _ _ _ __This revision does not constitute _an unrevidwed safety question'as explained ___ l
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- 1. The bvobability of 0.c.currence and the_ consequences of an accident or i l
malfuncti.g.n of equipment important to safety are not increased above _
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those ana.]ned,in the FSAR (ue to this revision because'the revision
'does not change'the purpose _oF performance of the system.
- 2. The possibility of an_ acciden,t or malfunction of a different type th.an analyzgd in the FSAR does not result from this revision because the nstem responds and is operated as before the revision. '
.l~J . .j_ . _ .c - . t. . __
i. I- _ --- ._ - 3.._Ijie margin of safety as defined in the Technical Specifications- is not reduced due to this revision because the revision does not change
.a.ny limited safety system settings which would allow a safety limit -_ .'~,
to be exceeded or allow a limiting condition for operations to be l _
' [ex_ceededasstatedinTechnicalSpecifications. !~ _
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. l r P_R__OCE_D..U_9E _ . . R.E. V._I _S_I ON R.E.G. __ _.lE..GT SHEET _Q OF_..a___ __
e PROCEDURE NO. I-NP _1(O 5- _ l
. REVISION NO. __M N .
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REAGON FOR,.REGU5ST:- 6b& ha o O \ _ .
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HNP- 8005 Sei Titlo Pcg2- =vem mo om . Georgia Power d - ,.o See Title-Page 1 of-27 lj 0, ' - r
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RADIATION Ato CONTAMINATION CONTROL A. EWRPOSE'- To outline.the procedures.which'will be used by-Health Physics
-personnel and by all plant personnel to ensure that potential radiation hazards are adequately defined, that adequate controls are instituted so that radiation exposure to personnel working in Radiation Control Areas:or working with radioactive materials is minimized, and that~_each person carries out his work in a radiologically safe and economical manner.
-B. REFERENCES
- 1. 10~CFR 20 _
2.. HNP-8000 and 8100 Series Procedures -
.C. SAFETY
- 1. Observe radiation protection procedures.
-Q' D. GENERAL MONITORING V
- 1. External Radiation Measurement i
- a. All individuals entering a Radiation Control Area ar2 required to wear _a TLD badge and pocket _ dosimeter at all-times. A record of accumulated external radiation exposure received is obtained principally from the interpretation of the TLD badge. Direct reading pocket dosimeters provide an "on-the-spot" reading for the individual.
- _b. ~
Radiation Control Areas within the Primary Protective l Area are classified and identified as to levels of radiation and for contamination. Strict procedures will :tur enforced for access to these areas.
- 4. There are numerous area radiation monitors located throughout the plant which alert personnel to abnormal radiation levels.
- d. In addition to the measurements made by the area radiation monitors, the measurement of external dose rates is accomplished by portable survey instruments.
The operation of survey instruments will be in accordance with the operating instructions outlined in O each particular instrument procedure. Instruments covering high, intermediate, randy,lew ranges are - available in the plant andrin ncy g g
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- m a=== E. l. Hatch Nuclear Plcnt ===
HNP. 9005 Sea Title.Pcgo commoc Georgia Power A % i See Title Page n 2 of 27 OE .
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- 2. Loose Surface' Contamination Measurement
- a. . 'In Radiation Control Areas loose surface' contamination
,is normally, determined by_ wiping a disc smear over a 100 square' centimeter area of the surface being
. monitored. Detailed procedures for contamination surveys are found in I-f@-8012, SLRFACE RADIOACTIVE
'C.,QN_ TAMINATION St.RVEYS. The smear is then counted using a beta-gamma (G-M) count rate meter. Alpha activity of a smear is determined by means of a gas proportional detector.
- b. In areas not normally expected to be contaminated, the loose surface contamination will be determined by '
wipin~g a disc smear over a 100 square centimeter area and counting the smear with a proportional or G-M counter for gross beta gamma. -
- 3. Airborne Contamination Measurement .
In addition to the area radiation monitors particulate airborne activity will be determined as'needed by. utilizing portable air samplers with filter paper and mobile continuous air monitors (C.A.M.'s). Filter samples from , ( f. portable air samplers are counted for gross beta activity using a gas-flow proportional or G-M counter. Alpha activity of a sample is determined by means of a gas-flow proportional counter. The continuous air monitors are self contained and therefore record air activity continuously on a strip chart recorder. Operation of these air samplers will be in accordance with HNP-8013, 8109, and 8128. E. ROUTIhE AREA MONITORING
- 1. Health Physics personnel will perform surveys that are necessary for the designation of Radiation Control Areas.
. Surveys will include routine checking of areas for external radiation hazards and contamination, as well as for airborne radioactivity.
- 2. . ~Routine radiation, airborne, surveys'will be conducted in the plant to establish and contamination levels throughout the
' facility. Whenever practical, Health Physics personnel will make the first entry into areas of unknown radiation levels. Otherwise, licensed operating personnel entering areas of unknown radiation levels will carry survey meters to determine radiation levels.
I O
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u aaaao = E I. H tch Nucle:r Pirnt. aaxeouae~o HNP- 8005 Saa Titlo Pcga newsu= ~o
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om GeorgiaPower A ..oe ,.o
- See Title-Page 3 of 27 F. SPECIAL, AREA MONITORING
- 1. Spe^cial radiation, airborne and contamination surveys.in additio,n to routine surveys, will be made when necessary.
Examples of situations requiring special surveys are.
- a. During any test or work items involving:
(1) Installation or removal of in-core fission chambers. (2) Installation or. removal of core startup sources. (3) . Installation or removal of reactor components.. (4) Loading and unloading fuel elements. (5) The opening of a primary coolant. system , (conducting a special survey of the surrounding area for contamination after the opening or removal operation has been completed and before other work is resumed).
- (6) The removal of any material which has been in contact with the primary coolant (i.e., valves, pumps,_ sections of piping, demineralizer resin, etc.).
(7) During reactor operation after the-initial installation of, and a?ter repairs or modifications to,. radiation shielding.
- b. Following any situation which may result in radioactive contamination.
- c. Before~and after any decontamination operation.
- d. Checking shop areas in which contaminated equipment is being worked on.
1 - - . l e. When rupture of a radioactive - material container occurs, or when spills are reported.
- f. When handling spent fuel.
l l g. Unconditional release of items to unrestricted areas. l O . mang a4 ,
. g L. m _ . _ , , . _ , _., _ ,. ___,., _ ,,_ , , , _ _ _ _ , , _ , _ _ _ _ , , _ , , , . _ _ , , _ _ , , , _ _ _ _ _ _ , , ,
.- - E. l.- Hctch Nuclear Plent aa===am HNP. 8005 Ses Titio Paga amso= =o Georgia Power d om .
,som See Title Page. 4 of 27 l i : Q' G. ..CONTA>lINATION LIMITS o .
_ -) 1...: Personnel, material ~and equipment released-from Radiation .l
' Control Areas shall be free of significant radioactive l
_ con'tamination. Release surveys will be made'and will ; include alpha,_ beta and gamma radiation detection unless it ,
'is known that a;given type is not present. Release. surveys must be performed where the background does not exceed 200
. cpm - on beta-gansna - detection meters or 50 dpm on alpha
. detection meters. .The procedure for surveys is found in i+P-8012 SLRFACE RADIOACTIVE CONTAMINATION SURVEYS.
- 2. Surface Contamination Limits
- a. Clean Areas For areas outside_the boundary of a Contaminated Area, surface conta nination will be kept at a minimum and maintained below the limits set for Contaminated Areas . ,
in i+P-8003 RADIATI@ CONTROL AREA CLASSIFICATIONS. .
- b. Contaminated Areas - Frequent Access For areas which become contaminated and which require frequent access, efforts will be made to clean up the O_ contamination as soon as possible, provided the clean-up. operation will not result in unnecessary exposure to clean-up personnel.
4 . i For frequent access areas in which it-is impractical to decontaminate immediately, contamination levels will be ! maintained below the following: l-L (1) Smearable surface radioactive contamination l-Beta-Gamma 50,000 dpm/100 cm' Alpha 50 dpm/100 cm b (2) Fixed surface radioactive contamination Beta-Gamma 10 mR/hr at 1" using a RO-2A
~ ~
cr RO-3A
^
Alpha 50 dpm per detector area L c. Contaminated Areas - Occasional Access For contaminated areas which may require occasional access, the values in E.2.b may be increased by a factor of 10-100. !
" 'S O.
When the above values in G.2.b. and G.2.c. are . exceeded, the areas involved should 99eal sat , ) decontaminated as soon as possible. l i teesse I
.-,---_...~.... ,- -, _ _ _. _ _ _.__-_ _ ___ ..,-_,___,.....___,_ ___ ___ _____.._ _ ____..-__.-.__ _ _. -
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.j + - E. l. H tch Nucicer Plcnt = =o m HNP- 9005 S:o.Titlo Pega moom l o... Georgia Power A ...
3- :See Title Page 5 of 27 .O.
- d. Regulated Equipment
~ Equipment of a portable nature, such as hand tools, l
. small pumps and motors, of such design which makes
~. decontamination impractical, will be considered re,gulated equipment and stored in a designated area, which will be labeled-as a Radioactive Material Area.
The department using this equipment wi)V be responsible for proper storage of this equipment. Regulated equipment may n.sve smearable contamination on
. exposed surfaces up to 50,000 dpm/GM probe area beta-gamma and 50 dpm/ detector probe area alpha,.and may have radiation levels up to 10 mR/hr at.one inch.
This equipment must remain in a designated storage area within a Radiation Control Area, and can be used only in Radiation Control Areas by workers wearing protective. clothing. Workers requesting to remove regulated equipment from a designated storage area must - first notify Health Physics. Health Physics will determine the radiation and contamination levels on'the regulated equipment and determine if it is acceptable for this equipment to be used in the requested work area. Equipment having radiation levels higher than 10 mR/hr may be used after consideration of all factors O. involved, i.e., the nature of the equipment, the frequency of use, and the length of time it may be in use. Movement of regulated equipment will be controlled such that highly contaminated equipment will not be used in relatively clean areas.
- e. Personnel Contamination Limits (1) Personnel contamination levels shall be kept as low as possible at all times, therefore the following limits may be used as a guide to release personnel to clean areas:
Seta-Gamma SK.IN OR CLOTHING INTERNAL Fixed Removeable 35.1000 DPM/ No Detectable 5% MPBB Probe Area Activity AlphR SHIN OR CLOTHING INTERNAL Fired
'(]) JE 50 DPM/
RemoveakJ e No Detectable , N/A Probe Area Activity " mang gg . 4 W . . - - . . , . - . - - . . . - - - - - - - ~ . - - -
- E.1. Httch Nuciscr PI:nt a x - ~o HNP. 8005 Sea Title Paga uwsion no 25 om . Georgia Power d me.
Sao Title Page 6 of 27-Y c
.I NOTES
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'All, Beta,~ Gamma measurements are made using a pancake
'* probe G.M. detector with count rate instrument or
' equivalent.
All Alpha measurements are made using a PAC-4G and a MS-2 Counter set-up for alpha detection. An Alpha Survey is performed.if there is reason to suspect alpha contamination such as when handling fuel assemblies. (2) Personnel with contamination levels greater than the above values shall notify Health Physics and decontamination shall be .=+ tempted. If. contamination levels cannot-be reduced below-the above values a Health Physics Supervisor or his , designated alternatt will determine the release. (3) Movement of Material and Equipment from a Radiation Control Area Any. component, item of equipment, or tools having been used in a Radiation Control Area, will. L(]) require,--as much as practical, a beta gamma dose
- rate and contamination survey prior to or after l coming out of a Radiation Control Area. All released items will be classified by Health Physics personnel as either an unconditional release or conditional release.
- (a) Unconditional Release Item:
Material and equipment will be given an unconditional release by Health Physics
. personnel for use outside the boundary of a Radiation Control Area if no smearable beta gamma or alpha contamination is found using a smaar technique and radiation levels i at one inch are-less than 100 CPM above l l
background using a GM count rate meter with l HP-210 Probe or equivalent. NOTE Material and equipment which contain ! inaccessible and/or porous surfaces will not be released until the material or
- equipment is known not to be
.. s . contaminated.
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-700838
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=^v -E. l. H tch Nuclear Plent- aa=== =
HNP- 8005 Sea Titio.-Pega avision w
" 25
- om Georgia Power d .. _ i
- See Title Pace 7 of 27 !
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~
. (b) Special Releases:
An assistant Plant Manager may authorize the
. unconditional. release of certain radioactive material when it has been determined that the total activity of the material is less than that specified in 10 CFR Part 20 Appendix "C*.
(c) Conditional Release Item: Removal of material and equipment from Radiation Control Area with radiation and contamination levels in excess of those limits specified for unconditional release must be approved for conditional. release by Health Physics personnel. Contaminated material and equipment'will be placed in containers, when practical, prior to removal . from a Radiation Control Area and tagged with Figure 1 tag or labeled with a radioactive , material label. These labels will contain the levels of radioactivity, description of i : material, initials of individual performing j the survey and date. When it is not practical to place contaminated material and equipment in
- containers, movement out of an RCA will be
! controlled to prevent contamination spread. No conditional release item will be allowed to leave the Primary Protected Area without the express approval of the Health Physics staff. (d) Contaminated Equipment Control: Certain items of material and equipment used during maintenance activities may, from time to time, become contaminated, and prior to
- ~
return to the Maintenance Shop Tool Room, must be stored until decontamination can be performed. In this' event, Figure 3 may be completed by Health Physics, if requested by Maintenance, and may be' forwarded to the Maintenance Department and the equipment will be stored under lock and key until such time decontamination can be performed. O , _ k- of '<
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_ u a ~ at E. I. Hctch Nuciccr Plcnt =====~o HNP. 8005 Sea Title Paga = mum mo Is oam Georgia Power d ... l rs See Title Page 8 of 27 kw] c
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(4) Laundered Protective Clothing: , i l- (a) Returned laundered protective clothing shall l be surveyed by' Health Physics personnel for )
. acceptable limits of contamination as ;
described in HP-8007, LAUPOERING OF ! PROTECTIVE CLOTHING.
~
(b) Procedures for handling and surveying protective clothing is detailed in HNP-8007, LAL.20ERING OF PROTECTIVE CLOTHING. ! H. RADIATION WORK PERMIT
- 1. The Radiation Work Permit (RWP) (HNP-8008) is a procedure used to provide _ radiation safety and an awareness of _
significant exposure radiation levels in areas where personnel will be working.
- 2. Procedures for issuing and using an RWP are found in FN'-8008, RADIATION WORK PERMIT.
I. PROTECTIVE APPAREL AhD EQUIPPENT
- 1. Location Protective apparel and equipment are kept in the warehouse and in other areas as judged necessary by the Health Physics Supervisor. A minimum supply of clothing and equipment is kept in the Radwaste Building 132' elevation, Reactor Building 228' elevation, Turbine Building 112', Reactor Building 130' elevation and Reactor Building 158' elevation.
- 2. Protective Apparel l
Hard hats, coveralls, shoe covers, hoods and gloves are
~a vailable for use. This apparel is distinctively colored (yellow for clothing,-magenta for hard Mats) and should be used only as anti-contamination clothing.
- 3. Use.of Protective Clothing The following procedure will be used by personnel required to wear full protective clothing in Radiation Control areas.
- a. Entry Procedures (1) Obtain hard hat, coveralls, gloves, head covers, l shoe covers, rubbers, and other equipment as O required by the Radiation Work Permit.
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. a- : E. i. Hatch Nuclear Plcnt = = = = =
HNP- 8005 Sco;Titlo Pago ave = = Georgia Power d .. , See Title Page 9 of 27 c
. --[2 ) Follow FN5-8011, PROTECTIVE CLO NING DRESSING AhD
..., . !&QR_ESSING.
? ,
NOTE When working in contaminated areas,-personnel should periodically check-levels of contamination on. protective clothing with a. G.M. survey meter or count rate meter. If gross contamination is detected, i.e., radiation levels in excess of 5 mR/hr at one
. inch, the protective clothing should be removed and clean protective clothing put on.
- b. Radiation Control Area Exit Procedure (1) Fallow FN'-8011, PROTECTIVE CLOTHING DRESSING AhD UNDRESSING, to remove clothing to prevent .
contamination of the skin or articles of clothing ~ underneath. (2) Place protective clothing in the proper containers as they are removed. () (3) Monitor self and personal clothing with count rate meter before leaving the access of the Radiation l Control Area. (4) If no contamination exists, exit the Radiation Control Area. (5) -If_ contamination is present, n.otify Health Physics t personnel immediately.
- 4. Additional Protective Clothing Requirements
.As the conditions warrant, additional protective clothing may be required for operations involving high levels of contamination or in situations where a splash hazard from contaminated liquid may exist.
- 5. ~ Respiratory Protection
.a. Respiratory protection devices may be required in any situation arising from plant operations where the potential for airborne radioactivity exists.
NOTE L{} Hard hats will be worn with all respiratory protection devices with the exception'of supplied air hoods. m Z ,=_jp .- na mai set ,
.e 9 .
g were . _ _ _ . . _ _ . . . , , . . . _ _ . . . . . . - . . _ , , . , , . , _ . _ _ . . . . _ . - - - _ . _ , _ . . . . - , , _ _ . . . _ , . , . . - . _ . . , _ _ _ .;
aa = = E.1. Hctch Nucl;cr Plant a=== ~o HNP- 8005 Seo Titlo Pcg3 uwoom w.
" 25 Georgia Power d See Title Page 10 of 27
-O c
,b . .fn such cases, the air will be sampled by Health Physics personnel and the necessary protective devices
'specified according 1:o the. concentration and type of
.. airborne contaminants present. It is the
' responsibility of the individual and his supervisor to notify Health Physics personnel when working with radioactive materials-that are likely to.become airborne. Every precaution should be taken to keep the air contamination to a minimum through use of proper ventilation and prior decontamination of equipment or work areas.
- c. Issuance and use of all respiratory protection equipment is described in HNP-80lO.
J. TEIPORARY SHIELDING
- 1. General Criteria for Installing Temporary Shielding Prior to installing shielding on a seismically analyzed -
system, an evaluation of the loading effects of the
- shielding material on the system must be completed.
All temporary shielding installations involving a seismically analyzed system must be performed under a ({} Maintenance' Request. For temporary shielding involving ( equipment or areas other than seismically analyzed systems, an H.P./ Lab foreman or supervisor will determine the necessity for a loading evaluation and Maintenance Request, and will request assistance as necessary from the ' appropriate department (s). A Design Change Request (DCR),- in addition to an MR, is required if shielding is to be made '
. permanent.
Temporary shielding is defined as shielding installed to reduce personnel exposure during job performance, to reduce
. background cadiation levels in frisking areas, or to bring radiation. levels in an area into compliance with NRC regulations. This type shielding should only be installed for a specific time period, i.e. for the duration of a job, to the next scheduled outage when corrective measures may be
' taken, or as directed by plant management.
- 2. Installation on a Seismically Analyzed System
- a. The person requesting the shielding on the safety-related system will first contact the Engineering Department.
O
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'V - e 11~of 27 ,
i
~
.b. The Engineering Department will make or have made an
.. ' evaluation as to'how the. shielding will affect the
?" seismic or design loading of the' piping or the ;
equipment to.which it is applied. Engineering will coordinate the evaluation with the Health ~ Physics-staff for specifications of the shield, i.e. size, shape, material, thickness, etc. All evaluations will be documented. f l c. Upon the : completion and acceptance of the evaluation, an PR will be initiated for placement of the shielding.- A copy of the evaluation will be attached to the MR..
- d. The Temporary Shielding Log will be completed per
-Section J.4. below. _
- 3. Installation on a Non-Seismically Analyzed System
- a. The person requesting the shielding will contact a Health Physics foreman or supervisor.
- b. The H.P. foreman or supervisor will determine, using assistance from other departments as necessary, if the shielding installation is of such magnitude to warrant
- a. loading evaluation and if an MR should be issued. If so, step J.2.b.-and/or J.2.c. will be completed.
- c. The Temporary Shielding Log will be completed per Section J.4..below.
- 4. , Temporary Shielding Log '
Information concerning the installation will be logged in a Temporary Shielding Log maintained at the Health Physics office. The log will include a description of the type . ~s hielding, the location where the shielding is to be installed, Maintenance Request number, RWP number (if RWP is required), when shielding is to be removed and any remarks deemed necessary.
- 5. Removal of Shieloing
- a. The person who requested the shielding is responsible for its removal at the time designated in the Temporary Shielding Log. Reasons for time extensions should be documented in the log.
- b. Health Physics will review the log on a monthly basis
.O to assure temporary shielding installations are removed in a reasonable time frame aftet;$he removal date .
specified. ?? 4 ffj w mag g ,
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- .1 a- E. l. H:.tch Nuclecr Picnt- = = = =
HNP. 9005 Sea Titio Paga nams= = Georgia Power d om .. See Title Page 12 of 27 O. ~ 6.- Discrepancies 1 IF-unauthorized temporary shielding is observed, a -Deviation HRepBrt will be completed and corrective action taken as l
-deemed necessary by plant management. l
- 7. Types.of Shielding
.a. Alpha and Beta Radiation.
Alpha and beta radiation can be stopped or shielded
'with a sheet of paper and a small piece of steel, respectively. Gawww and Neutron radiation require considerably more material for shielding.
- b. Gamma Radiation I
(1) For gamma radiation, various thicknesses of dense . material such as-steel, lead, or concrete can be used to reduce the radiation to desired levels; (2) A convenient concept to use for rough gamma
~
shielding estimates is the tenth value thickness. 1 This value is that thickness of material which
) will reduce the radiation level by a factor of ten (10). As shown in the following table, the tenth value thickness differs with different shield 4
. materials and with gamma energy. The tenth value thickness for 6 Mev should be used for lines and E equipment containing steam or reactor water. The 1 Mev Values should be used for irradiated fue),
for isolated equipment and for,all equipment during plant shutdown. TABLE 2 TENTH VALUE THICKESSES APPROXIMATE TENTH VALUE THICKNESS MATERIAL 1 EV GAlttA 6 EV GAMMA I Lead 1.5 inches 2 inches Steel 4 inches 5 inches Concrete 12 inches 20 inches Water 24 inches 40 inches NOTE The half value thickness for the listed materials is one-third of the tenth val,ue thickness. NNk g v. 70e010
- E. l. Httch Nucicer Plant- aoc==a m HNP- }O05 i Sao Titlo Pcg1 newsmse 1 25 i om _
Georgia Power d ... o See Title Page 13 of 27 ()- ,
,c . J4eutron Radiation
..; Neutron radiation can be shielded best by using a
?' hydrogenous material such ac water, plastic, or
' paraffin to-thermalize the neutrons and by surrounding-oor- impregnating this hydrogenous material with baron,
-cadmium or lithium to absorb the thermal neutrons. An approximate half value thickness-for 1 Mev neutrons is-1.3 inches of paraffin and approximately 2.7 inches for 5 Mev neutrons.
K. RADIATION ~OCCt.RRENCE REPORTS (ROR)
- 1. The purpose of an ROR is to assure that conditions of a serious nature which are-adverse to radiological safety are properly identified, corrected and reported to management.
NDTE , The requirement for the use of this report will be - determined by a Health Physics Supervisor or designated alternate.
- 2. Radiation occurrences should be reported to plant management
-])
( for corrective action and should be documented by_use of Figure 2, REPORT OF RADIATION OCCURRENCE. Types of radiation occurrences are described as follows:
- a. External exposure:
Includes: p ~ l . (1) Uncontrolled personnel exposure from external sources. (2) Uncontrolled personnel exposure from contamination on protective clothing. (3) Uncontrolled dose rates existing outside of Radiation Control Areas.
.~- - (4) Dose rates inside a Radiation Control Area greatly exceeding normal levels.
(5) Exposure of personnel to dose rates such that a weekly permissible dose of radiation could be received in less than 6 minutes. O h 7eeslo
--e, , , , , , . . - . - . . - - , , , . , . - , . - - , . - _ . - - . . , . . _ . - - - . _ . - - - - - - - - - , - , - - _ - - + - . - - - - - . _ _ . - - - . - - - - - , - - - - , - - - - .
U a== E. l. Hitch Nucl:cr Pitnt- ==== = HNP. 9005 S;a Title Pcgo t ewsomo-25 om Georgia Power d ... See Title Page 14 of 27
.( ) b. , Personnel contamination control:
Includes:
'.(1) Any contaminated injury.
(2') Any significant personncl exposure to contaminated air without adequate protection.
~
- c. Surface contamination control:
. Includes:
(1) Any contamination transported outside of GPC controlled boundaries. (2) Spread of significant contamination outside of Radiation Control Areas. (3) Spread of significant contamination in the . immediate work area beyond that which was planned or might normally be expected. (4) Any fire or explosion in a Radiation Control Area. ( (5) Release of contamination to the air, ground, or water which greatly exceeded normal conditions.
- d. Administration control:
Includes: (1) Employee working in a Radiation Control Area without required or adequate monitoring. (2) Employee failing to take corrective action requested by H.P. personnel on a radiological problem. (3) Employee working in a Radiation Control Area without personnel dosimetry.
~ - .
l (4) Employee working in a controlled area beyond the time estimated to result in permissible weekly exposure.
- 3. Procedures for completion of the report is as follows:
- a. The individual initiating the Radiation Occurrence will complete Figure 2. Figure 4 will be used as a monthly
() tabulation for the Occurrences. He will complete the report through the section, " Action taken At Time of ~ Occurrence". He will then* forward the r q g a Laboratory Foreman or Supervisor. - r~~rn
- E. l. Hatch Nuclear Picnt = = = =
HNP- 8005 Sea.Titio Pcga , 25
= .
, Georgia Power , _ ,
^
See Title Page 15 of 27 Q
- b. " he Laboratory Foreman or Supervisor will review the
-report,_and, if further action is required, will
~. forward the report to the-appropriate-supervisor,
" keeping the pink copy for a temporary' suspense file.
Iff no further action is required, he will complete the form,-sign at the bottom, and distribute the copies to the Plant Manager, appropriate supervisor ana Health Physics file. The pink copy will be placed in the individual's exposure record file.
- c. .If further action is required, the appropriate supervisor will review the report and specify what specific action is being, or was taken to prevent a similar occurrence, when the action will be completed and by whom. He will then return the report.to the Health Physics Supervisor or his designated alternate.
- d. The Health Physics Supervisor will review the report, and sign at the bottom. He will then distribute the copies to the Plant Manager, appropriate supervisor and Health Physics file. The pink copy will be placed in the individual's exposure record file.
L.- RADIOLOGICAL DEFICIENCY REPORTS (RDR) 1.- The purpose of a Radiological Deficiency Report (RDR) is to provide a simple means that any employee can use to identify an unsatisfactory radiological condition to the appropriata person so that the deficiency will be corrected in a timely manner. 2. The Radiological Deficiency Report is to be used for radiological deficiencies and radiological procedure non-compliances which are less severe than those requiring a Radiation Occurrence Report provided the deficiency reported , can be properly corrected at the foreman or supervisory
-level and dd not, individually, need to be brought to the attention of senior plant management.
- 3. A Radiological Deficiency Report (RDR) is appropriate .
. w
_henever the radiological deficiency observed cannot be corrected as part of the normal duties of the person finding the problem or whenever the deficiency cannot be corrected during the shift lwnen the problem was found.
- 4. In addition, an RDR should be used to identify to the appropriate supervision deficiencies of a recurring nature.
- 5. The types of deficiencies that should be identified on an RDR include:
a. steam or water leaks ashich'could cgigte an
- A
. a~mm
a== E.'I. Hctch Nucich Plcnt aa===am HNP. 8005 Sea Tit 10. Pag 2 - ams.ou a om Georgia Power d e JSee Title Page 16 of 27 , .h ,.
.b. .fontaminated material not properly bagged or marked.
~
c..., [ Improper wearing of-Anti'Cs. 7
- d. ~ Failure to follow the radiological requirements in a work procedure or RWP.
ar . Unsatisfactory work practices that could result in a spread.of contamination.
.f. . Equipment deficiencies such as a defective high
' radiation area door lock or problems in the operation of a CAM.
- g. Unsatisfactory radiological housekeeping conditions such as resin or water on the floor.
- h. Re-occurring type radiological deficiencies. ,
- 6. The person finding a radiological deficiency should fill-out a radiological deficiency report form-(Figure 6) including the date, time, location, nature of the deficiency and, if possible,'the persons involved. The RDR should state what immediate action was taken and, if necessary, what j }' additional' action should be taken and by whom. The radiation technician or other person initiating the RDR should deliver the RDR promptly to his supervisor who should review the problem. The RDR should be logged at the HP office and copy a filed in the RDR suspense file. Copy 1 of the RDR should be forwarded to the appropriate supervisor for action. The-supervisor should take corrective' action, complete Copy 1 of the RDR and return it to the HP office.
. The HP office will match Copy 2 and Copy' 1 of the RDR, note completion in the RDR log and file Copy 1 in the completed RDR file. Copy 2 may then be destroyed.
. NOTE Nothing in this procedure relieves the person finding a problem from the responsibility of immediately notifying the appropriate supervision if immediate
- - - action is necessary.
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- See Title Page 17 of 27 J _
FIGURE 1 RADIOACTIVE __ MATERIAL TAG e e 1 L t
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. PROCEDURE DATA.PACHAGE DOCUCNT NO: HPP-8005-1 SERIAL ND; R15-PPL NO:
RTYPE: _Q15.14 XREF: TOTM. ECETS: 2 , FREQlINCY: As_BRAM1Eid COPPLETED BY: U(N DATE CatfLETED: Q. I I HAVE REVIEWED THIC DATA PACHACE FCR COMPLETE?ESS AND ACAINGT ACCEPTANCE CRITERIA IN ACCORDANCE WITH HP-830. ACCEPTABLE bCCEPTADLE REVIEWED BY: . DATE REVIEWED: __ REMARHS: a Page 1 of a M -8005 R15
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HNP. 8005 Sea Titio Pcg] muo. w 25 o... Georgia Power A .. . r^ See Title Pace 19 of 27 ( . s % a QATA PMNAGg_1 REPORT OF RADI ATIW OcctbRENCE
........ .....................................................................................' P4JPGFR I
tbE!I.Es.ls H.A.ICU ...............*...............* l gggORT OF RADIATION OCCURRFNFE OATE CF ISMANCF TYPE OF OCCURRENCE LOCATION REFERENCES RWP'S. SLRVFYS F.TC. DATE & TIPE' OF OCCURRENCE REPORT REVIFWED BY3 POTENTIAL C PCALTH PHYSICS SUPFRVISOR ,
......................~........................,................................................
PERSONPC1. INWLVED LENGTH OF SERVICE EXTFRNAL INTERNAL EXPOGURF ON PRESENT JOB EXPOSWE ..........'.........<............... NAME OEPARTPENT . F1 REM
- YES NO POSSfBLE
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.............................~..............................,..........o.........................
OESCR1rTION OF OCCWRENCE (INCLLCE ALL PRINCIPLE CAUSES Arc SIGNIFICANT PFASLREMENTS) 151II M 2.81 00'T: (hCT10N TMEN AT TIPE (F OCCtRRENCE
..!!Y.t+m QEPT SUPFRVISORS C REFERRED TO IPO!VIOUAL'S CUPERVISJ4 FOR ACTION DATE:
_= W4AT SPECIFIC ACTION IS BEING. OR WA3 TMEN TO PREVENT A BIMILAR OCCURRFNC6 ?
..MJEtLidtb"II4.D.ACIlQU.IE.CQ5etEIE09 BY WF CORRECTIVE ACTION REVIEWED AND APPROVE.D FCAL.TH PHYSICS SUPFRVISOR 1
C "iE K.4H PHYSICS FILE (ORIC & P!Peu C PLANT MCR (9LUE) C EPPLOYEE'S suPFRV!W (CREEN Page 2 of 2 p W -BOO 5 R15 s w/ FIGl.RE 2 ; Page 2 of 2 {~ W- j gg
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a == E. l. H tch Nucle:r Plant = = = = HNP. 8005 Sea Titio Pcg2 mmo. o
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See Title Page 20 of 27 1 r t) - l i PROCCDURE DATA PACHACE - DOCUPCNT NO: FtP-ggg5-2 SERIAL NO: R15-PFL NO: RTYPE:._Q15.14 KREF: TOTAL SFEETS: 2 _ , , FREQUENCY: As Rgsgir,td COPPLETED BY:
/
DATE COMPLETED:
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I HAVE RCVIEWED THIS DATA PACHACE FOR' COPPLETENEC3 APO AGAINGT ACCEPTANCE CRITERI A IN ACCORDANCE WITH ter-830. ACCEPTM3LE M CEPTADLE REVIEWED DY: DATE REVIEWED: REMARHG: Page 1 of 2 HNP-BOOS R15 O FIGURE 3 Page 1 of 2 Elassal set ,
= a6 E. l. Hatch Nucl::ar PI:nt oa=== o l HNP- 8005 l Sea Titio Paga aem o. o o... GeorgiaPower d ...
See Title Page 21 of 27
- O ,
V s' . QA_IA_PACMAGC_g CONTAMINATED EQQ1Et2lI_GQt!IBA TO MAINTENANCE SFOP STORE ROOM: TFE FOLLOWING NAPED IFDIVIDUAL HAS LEFT THIS EQUIPPCNT AT FCM TH PHYSICS DUE TO RADIOACTIVE CONTAMINATION: NAPE DATE ITEM g, . .-
- 2.
- 3.
- 4.
- 5.
- 6. .
7. 8.
- 9. "-
- 10. ..
O .V TFC EQUIPMENT LISTED ADOVC WILL DE GTORED LNDER LOCH AND HEY IN A DESIGNATED AREA LNTIL THE EQUIPMENT 6%3 BED 4 DECONTAMINATED NO RELEASED FOR NORMAL USE. p* - y. TH PHYSICS DATE~
~
Page a of a FNP-8005 R15 O FIGURE 3 : Page 2 of 2 Bassai sat , m 790000
. a = ova' E. l. Hatch Nucl:Cr Plant aaociou= ~o HNP. 8005 Sea Titlo Pcg] uvisio= w o... . GeorgiaPower d ..m . See Title Page 22 of 27 c., U .: PROCEDURE DATA.PACHAGE CoCUMENT NO: ,_t.E-Q005-3 t SERIAL NO:__B12- 1 1 l IPL NO: l l RTYPE: _G15114 l XREF:,_ * - TOTAL SEETS:__2 , FREQUENCY ,_A_1 _Elmir15L.__ CarfLETED BY: DATE COMPLEYED: I HAVE REVIEWED THIS DATA PACHACE FOR C0ffLETENESS MO ACA! PCT ACCEPTANCE CRITERIA IN ACCORDANCE WITH HNP-830. ACCEPTABLE UNACCEPTADLE REVIEWED BY: , DATE REVIEWED: __ _ REMARKS: Page 1 of 2 W -BOOS R15 O V ' FIGURE 4 ' Page 1 of 2 maisaf sat , v.
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" - E. l. H;tch Nucle:r Plant a= = =oua= = !
HNP- 8005 ! Sea Titio Pcg2 aeviso. o
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l f- s, See Title Page 23 of 27 i 4
'%/ ,
DATA PACMAg W
- REPORT CF* RADIATION.QqQ@Mg3 MONTH YEAR 2CC QE.QCCmRENCE PERSOP4El. CONTAMINATION CONTAMINATION IN LNCONTROLLED AREAS _
UFCXPECTED HIGH RADIATION MINOR INJWY , CONTAMINATED ITEMS IN LNCONTRn e m AREAS , HIGH AIRDORPE ACTIVITY -- OTHER TOTAL O U t!QQl.EROBAhg_GA_lJQg .. IPPROPER DRESS IPPROPER CLOTHING REMNAL NOT FOLLOWING PROCEDWE INSLTFICIENT PLA>NING INADCQUATE OR NO MONITORING EQUIPMENT FAILURE INADCGUATC CLEAN-LP OF CONTAMINATION Uba(NOW OTI ER TOTAL NUMBER OF OCURREfCES ISSUED -
. COMPLETED BY DATE:
Page 2 of 2 FNP-8005 R15 O FIGURE _,4 Page 2 of 2 gg -
- = = at E. l. H:tch Nucl:Cr Pl:nt aa===am HNP. 8005 Sea Titic Pcg3 ansio o
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See Title Page 24 of 27-
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PROCEDURE DATA.PACMACE DOCtDENT NO: N -8003-4 SERIAL NO: R15- l i PPL NO: RTYPE: _G15 14 XREF: - TOTAL SHEETS: 2 . FREGUCNCY: As Reggiry,d COMPLETED BY: DATE COPPLETED: I HAVC REVIEWED THIS DATA PAEMAGE FOR COMPLETEPCSS APO AGAINGT ACCEPTANCE CRITERI A IN ACCORDANCE WITH 1+P-830.
- ACCEPTABLE t.NACCEPTABLE REVIEWCD BY:__ ,
DATE REVIEWCD:,, REMARMG: Page 1 of a ge-8005 R15 o o b FIGURE 5 . Page 1 of 2 manual sat \
, =a' E. l. Ha!.cli Nucl:Cr PI:nt aa==ovam HNP- 8005 Sea Title Pcg2 aus.o o 15 o... GeorgiaPower d ...
'See Title Page 25 of 27 o
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~
DATA PACKAGE _& EMIAT ION DCQ1ptR ANCC . ISOUANCg_ LOG - OCCURRENCE. ISSUED OCCURRENCE DATE MJMOER BY ON l l x, a. 1_____..___. . . - _ _ _ - - . . . . . _ _ _ _ .. , _ - _ _ _ _ _ _ . _ _ _ _ - - _ . r J. Page 2 of 2 HP-8005 R15 (s
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FIGURE 5 Page 2 of 2 ~ Elassai agg e teesso .
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,-s See Title Page 26 of 27 U, s' .,
PROCCCURE DATA.PACHACE DOCUPENT ND: FfJP-BOOG-5
!ERIAL NO:J 15-PFL ND:
RTYPE: C15.14 XREC:
- TOTAL SFEETS: 2 FREQUENCY: As Reogiggd COPPLETED BY:
(]' DATE COPPLETED: I HAVE REVIEWED THIS DATA PACHACE FOR COMPLETENESS
#C AGAINGT ACCEPTANCE CRITERIA IN ACCORDANCE WITH HNP-830.
ACCEPTABLE UNACCEPTABLE REVIEWED BY:, , DATE REVIEWED:
~
REMAnHG: I L Page 1 of 2 HPP-8005 R15 O V FIGURE 6 j 7 g -3 _lp, Page 1 of 2 , _; v. f^. c
o aa aovat E. l. H~tch Nucl::r Plcnt aa = === = HNP. 8005 ; Sea Tit 10 P::ga arv's* * ' Georgia Power d
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See Title Page 27 of 27
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. DATA PACTJ(A g J RADIOLOCIC& g giq1ggg Lgg gpI
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.. . ......_ _ . .... ................ .. ................. -- ==
RAD 10LOCICAL DEFICIENCY REPORI NO: DATE: TIPE: LOCATION: TYPE (F OEFICIENCYi pct 90@EL C EQUIP / FACILITY PROCEDURE C OTFCR C (EXPLAIN) OESCRIPTION CF OEFICIENCY: IPPCDI ATE ACTICN TAKEN:
- s. -
m FURTER ACTION PECESSNtY: YES C NO DESCRIPTION: FORWARD TO FOR ACTION SIGNATURE OF ORIGINATOR SIGNATURE OF REVIEkER _-- ..................... ........-.........- g.-........- ...-.--- FINAL ACTION TAKEN: l ? t l SICNATURE OF ACTIONLE mm: l l Page 2 of 2 l W -8005 R15 l t f~%.
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FIGURE 6 ' Page 2 of a v
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GEORGIA POWER COffANY l HATCH NUCLEAR PLANT I (-) 1 1 V .c , PROCEDURE Dec_ontamination of Protag_ti_Yg_C. loth 1Da_ add _ Ward Ha N PROCEDURE TITLE
~ -
- H N .P . 8_ 0_ 0 7
. PROCEDURE NUMBER Lab l RESPONSIBLE SECTION SAFETY RELATED ( X) NON-SAFETY RELATED ( )
__--__.._ _______--_______--..--_--__-____----. ._____________-a ________ APPROVED APPROVED REV. DESCRIPTION DEPT. PLANT _DATE HEAD MANAGER
.___ _ _-_--- __8 _______. .
7 Page 2 4bY
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-- . - + f -
8 Pages 1 and 2
/o
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_ _ _ _ _ - . .______---_---_______. <_ ___ -__--__ --4 ________
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, _____-. . _ _ _ - - _ _ _ _ - - _ _ _ _ _ _ - _ _ . . _ - _ _ _ _ _ _ - - _ _ _ _ _ _ . .__-_-_____-_____4 ________
.(v)
--____. . _ _ _ - _ _ _ _ _ - _ _ _ _ _ - - - _ _ . . _ _ _ _ - - _ - _ _ _ _ _ _ _ _ . ._-_____---_-____4 -__-_---
_____. . _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ - - - _ . . _ - - - _ - _ _ _ - - - _ - - _ . .____---________-4 ________ _ - - - _ _ . . _ - - - _ _ _ _ _ - _ _ _ _ _ _ _ - _ _ . . _ _ _ - - - - _ _ _ _ _ _ _ - - . .__----_---__-_--y -__-__-.
- - - _ _ _ . . _ _ - - - - - _ - _ _ _ _ - - - _ _ - _ . ..--_-________-_-. .______-__--___--4 --______
. _ - _ - - . . _ _ - - _ _ - - - - _ _ - _ _ _ _ - - - . . _ _ . - - _ _ _ _ _ _ - _ - - _ . .-_---_______--_-4 _--___--
l - - _ - _ - . .---____--_-_________. .--___--_-__-____. .__-_-_-_______-_4 _-_____-
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. _ _ _ - . .----_____-______----. ._-_-__---_______. .-___-_____----__4 -_____--
1 _ _ _ _ - _ . . _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ . ._-_-__-_---_____. ._____-____-_____4 -_--._-_ r q - _ _ _ - _ . . _ _ _ _ - - _ - _ _ _ _ - - - _ _ _ _ _ . e_-_______----___.1________----____, . - - - _ - - - - , alaisal sat s 1 i i 1 , , _ . . , , _ _ _ , _ _ _ , . . _ .
urko/a PROCEDURE DEVTGION REGUEST O .. . eROCEcuRENO.NNe_-soc 3__ SNEeT 1 Ora _
~
Revision No. Ii _
~
REGUESTED OY OEfhTMENT HEAD APPROVAL Name: - Date:
- Da te:
O dG SOdY %-Q-4 % & r - qlc: f 3 REVISION CilANGES MODE OF CPERATION OR IrITENT AS DESCR1GED IN FSAR: ( ) Yes ( d No CHANGE INVOLVES: ( ) An unres*ieweri Gafety Guestion ( ) Tech. Specs. ( d Neither (See tiack for Safety Evaluation if required). PRESENT STATUS: Safety Related ( V) Non-Safety Related (, ) l The above Safety /Non-Safety Status has changed ( ) Yes to f, Attach marked up-copy of procedure to this form. REASON FOR REGUEST: Tes chv'i nagkeus 1 kN d M QL6 O AmAadaoNAb 8th w\adt 0
~ ~ --
iw91L , DESCRIPTICN OF CHANGES: katfLC. s _9 . k3
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- 1. T.he probability of occurrence and the consequences of an accident or ,,
rpglfgn.q.tj.gn_of-nt equipment important to safety,are not increased above t.bose a_na.]ngd, in the FSAR due to this revision' because the revision
~
p.qgs not__chanae the purpose oi performance of the system. 2 _ The possibility of an a,ccident or malfunction of a different type than analyzed in the FSAR does not result from this revision because the J.yji. tem respond _s an'd is operated as before the revision. L._I_hq mar _qin,of safety,as defined in the Technical Specifications is
.n.g_t reduced due to this revision because the revision does not change ny limited __ safety _sys_ tem settings which would allow a safety limit _
to be exceeded or allow a limiting condition for operations to be eiceeded as stated in Technical Specifications. N . J., Q CtLCOr SC C w:, C C 'A - h 4 O I 0\nt.'tku ki W4 - _th te O k:ttdhmicab _gktcuv i ,t ____
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O enocgoyag_n.svIsIon ngGUEST SHEET S2_,OF k,, PROCEDU9E NO, 1-p - h^i
. REVISIONNO.,,,,_[__ -
REASON FOR REGUEST: , 6Gh(Aed, \_ _ ___ _' ' _.e_____-_ ___ __ _ _ _ _ _ - - i DESCRIPTION OF CHANGES: $ 1Ah4 AMW " 8 k y&,0 I
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(. 2 **===. E. l.' Hatch Nucl:ar Plcnt = ce= a= = HNP-9007 Sec Titlo Pcga a=ws.o= o ' om Georgia Power A ... See Title Page 1 of 3
'O c QEGQlEAMINATION OF PROTECTIVE CLQTHING AfC HARO,_ HATE
.A. ElEPQEg .
~To establish' a standard procedure for handling radioactively contaminated protective clothing.
B. M Observe radiation protection procedures. C.- ggL(R_AL, Radioactive _ contaminated. protective clothing requires special handling to insure that such clothing is not inadvertently sent to an unlicensed commercial laundry or that contamination on the dirty clothing;is not spread to an uncontrolled area. Clean .
' laundry returned for re-use by a licensed facility requires
'special monitoring to insure that it presents no significant '
hazard to personnel. It is the responsibility of the Health Physics staff to insure that all protective clothing used in Radiation Control Areas is properly monitored, packaged, and
- shipped to a. licensed laundry for decontamination. When clean laundry is' returned to the station, the staff insures that it is properly monitored and made available for use by personnel entering Radiation Control Areas requiring protective clothing.
D.. HAIOLING PROTECTIVE CLOTHING
- 1. Preparation of contaminated protective clothing for shipment to laundry.
- a. As contaminated laundry containers are filled, the assigned personnel will close and seal the inner plastic bag and close and seal the shipping container.
- b. Health Physics will survey the outside of the container in accordance with Procedure hbp-8016, SHIPMENT OF RADIOACTIVE MATERIAL.
- c.
- Each drum lid should have the words " Radioactive LSA" or a Radioactive Materials tag (Figure 1) affixed.
- d. Store filled containers awaiting shipment-in designated storage area (s). Areas should be posted or roped off.
- e. Re f e r to 1+P-8016, SHIPPENT OF RADIOACTIVE MATERIALS for shipping information.
=== .
- o. . . , . . .
U i a = *' E.1. H'tch Nuciccr Plcnt ==am HNP-8007 S o Titlo Pega aavisoom o... GeorgiaPower d ..om See Title Page 2 of 3
.f . "When loading of the laundry containers is completed for
. return shipment, the door to the truck will be sealed
. with a lead seal by the HP technician.
~
- 2. Handling Hard Hats Used in Contaminated Areas
\
- a. As contaminated hard hat racks are filled, the assigned !
personnel will collect the used hard hats and seal them I inside a purple plastic bag.
- b. . Health Physics will survey the bag and affix a Radioactive Material tag to the bag.
- c. The contaminated hard hats will then.be delivered to the respirator decon room for decontamination and re-use at control points / dress out areas.
- d. All hard hats will be surveyed after decontamination to ensure they are within the limits of 5.a below. ,
NOTE The foam sweat band in these hard hats is r- unnecessary and may be removed if decontamina-tion is not possible.
- 3. Receigt of Decontaminated Protective Clothino Survey the outer surface of the containers containing the decontaminated laundry as it is unloaded from the truck with a rate instrument (E-400 oc teletector). Any drum reading greater than 2.0 mr/hr at the surface will be set aside and checked. The drum will be opened and the protective clothing will be surveyed to insure it meets the limits for decontaminated protective clothing.
- 4. -Survering Decontaminated Protective Clothing All protective clothing will be surveyed after decontamination. The commercial laundry is responsible for
. _ surveying each piece of protective clothing after decontamination. This responsibility is written into the purchase order by GPC, and the commercial laundry has also insured Georgia Power Company they will meet the radiation levels for protective clothing for reuse in a G.A. program.
This written G.A. program is kept on file at Plant Hatch.
- 5. Radiation Limits _on Protective Clothing i
I ' () a. Hard hats, coveralls, hoods, cloth booties, rubber shoes less than 1.0 mr/hr beta, gamma, and no smearable .. contaminati,n. I mahlaf sat , l
n i
.~= E. l. Hc.tch Nucl:ar Pirnt =====
HNP.8007
, Sao Titio Pogo umo o- i
.... GeorgiaPower d ..
l
.7y See Title Page 3 of 3 i G .:
~
- t. Rubber gloves less than 2000 cpm.above background per probe area withfan HP-210 probe, fixed radioactive
;- material and no smearable contamination. All rubber
- gloves will be air tested for leaks by the laundry.
Rubber gloves greater than 2000 cpm or failing the leak test will be disposed of in radwaste.
- c. Protective clothing greater than 1.0 mr/hr but less than 5.0 mr/hr will not be reused but placed in storage at the plant until a convenient time exists to send it back to the laundry for rewashing to reduce levels to less than 1.0 mr/hr. All protective clothing greater than 5.0 mr/hr will be disposed of as radwaste.
G D O O e g O : Rand ut .
e
,. GECRGIA PObER COPPANY i,
HATCH NUCLEAR PLANT
/ ,*
V % PROCEDURE Oceratign of thi Mo d e l B_-100_C__om_Ra c t o r _ -.
,- PROCEDURE TITLE HP-8431- __ _
PROCEDURE NUPEER Lab RESPONSIBLE SECTION SAFETY RELATED ( ) NDN-SAFETY RELATED ( X)
.. _---o_----------_-----___,, - - _ - - - - - - _ _ - - - - - , , _ - - - - - _ - - - - _ _ - - - , ,-------.
APPROVED APPROVED ~ REV. DESCRIPTION DEPT. PLANT DATE y . New ,V[ O / A,
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U SECTION . Revision No. _.__ _Q_ _
~~~
REGUESTED DY DEPARTMENT I$EU~EPPROU5L Date- Signature; Date: Name: A M L-9ll~5l%3 W ,
,/ 9/alr3 CPERATION OR INTEN AS DESCRIGED IN FSAR:
REVISION CHANGES k.OCE O' ) No ( ) Yes ( CHANGE INVOLVES: ( ) An unreviewer: Safety Guestion ( ) Tech. Specs. ( d Neither l (See t>ack for Safety Evaluation if required). 9/f(/O PRESENT STATUS: Cafety Related ( [ Non-Safety Related (M. l The above Safety /Non-Safeiy Status has chenged ( M es to M..N._rh M y/m/D e - Attach marled up copy of procedure 'to this form. b o REASON FOR REGUEST: .f. 9Mhh _ _ _ V t b % q @ ._.___ l OESCRIPTIGN OF CHANGES:h4E .,4, %" K4 dag i k." _b.m.T.7._.e... o t h 4 e $L W q n 8a
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' _Jp,b..rgvision does not constitute _an unrevidwed safety question as explained
,(d e ~
_) glow. -
- 1. ihe probabj.]ity of occurrence and thg consequences o_f an accident or ,
malfunctli.g.n._of equipment important to safety are not increased above , _ t. hose analne_d_ in the FSAR due to this revision because the revisio _ __si.qgS_not chanae. the purpose o r perfonnance of the system. __
- 2. The possibility of an_ accident or malfunction of a different type than _
. Analyzed in the FSAR does not result from this revision because the ,__,,
skstem_respon.,d.s and is o_p_erated as before the revision.
. . . .. .. ?
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- 3. ' .Lhe margin ,of safety as defined in the Technical' Specifications is _
not reduced due to this revision because the revision does not change __. ____...any limited safety system settings which would allow a safety limit to be exceeded or allow a limiting condition for operations to be _ excee{ed as stated in Technical Specifications. _, O
-- - = ~ . . - - _-_.-_ ________
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- E. l. Hctch Nucl::ar Pl nt *===ai ~o HNP- 8431 Sea Titlo Pcga armnw wo 2
.... GeorgiaPower A ,.o. .
See Title Page 1 of 3 ;c
- g OPERATION 0F THE MODEL B-100 COMPACTOR
~
A. PURPDGE' The purpose.of this procedure is to provide instructions in the operation of the'Medel B-100 Compactor. B. SAFETY
- 1. Observe safety rules outlined in Georgia Power Company, SAFETY, Section "O".
- 2. Observe radiation protection procedures.
WARN 1NG
- 3. Special hazards exist while operating the compactor. .
- a. Both doors on the compactor must be closed prior to.
compaction. Do not avoid this precautionary measure. If a plastic bag contains dust it may become airborne if the door is left open. () b. Be sure all power to compactor is turned off prior to cleaning or working inside the compactor, especially when cleaning the push bar which will automatically retract when the power is turned on.
- c. Special care should be taken when handling bags of trash to avoid sharpe objects.
C. REFERENCEG l
.Model B-100 operations and maintenance manual and parts list.
I D. INITIAL CONDITIONS
- 1. CPC B-25 reinforced containers are available.
- 2. Compactor dust evacuator filter is in a clean condition.
- 3. Hydraulic fluid level is acceptable.
NOTE All trash must be sorted and segregated prior to compacting.
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= *t E. l.-H:tch Nucis r Plcnt == == ~o HNP- 8431 Saa Titlo.Pcg2 =vem =o.
om Georgia Power d .... See Title Page 2 of 3 E. TO COPPAC TRASH _ FOLLOW THE SEQUENCE BELOW
- 1. Wit,h ram'in full up position.and both doors open, insert container completely into compaction chamber. (NOTE: use only CP.C'B-25 reinforced containers specifically designed for this. application.
- 2. Close and secure lower door and depress start switch.
- 3. -Load material into chamber to full capacity of compaction chamber.
- 4. Manually close the loading door. l S. Simultaneously depress 2 DOWN switches until full compaction light is illuminated, indicating ram has reached maximym downward travel. .
- 6. Simultaneously depress 2 UP/ EJECT switches until ram is .
returned to full up position.
- 7. Manually open the loading door. l
- 8. Repeat steps 3 through 7 until material level is
(]) approximately 12 inches below top of container.
- 9. Insert anti-spring back retainer and repeat steps 4 through 7 locking retainer at lowest travel of ram.
! 10. Repeat step 7 and add additional material. i f 11. Repeat steps 3 through 10 until such time as additional l anti-spring back retainer (s) are not forced less than 12 inches into container under FULL COMPACTION. l
- 12. ~
Place additional material on top of last anti-spring back retainer to fill container.
- 13. Repeat step 7 and manually open lower door.
14.- . Remove the container from the compaction chamber. l L CAUTION 1 ! To prevent overheating of fluid, do not allow hydraulic power unit to operate more than 10 l minutes with lower door open.
- 15. . Inspect container for any damage during compacting, place l I) lid on container and secure with metal clips.
l r
6 F . a w a6 E. I. Hatch Nucl:ar Picnt *===a== HNP. 8431 Sao Titio Pcga ae.,s.o o
- o. . Georgia Power d ,ao.
See Title Page 3 of 3 O- .:
- 16. AssuEe appropriate labeling is on the container and that it
- has_been logged on the appropriate log sheet.
- 17. Sto're the container in a designated area for future shipment l offsite,.
F. OPERATION OF THE PURGE SYST_r_4 _ _E The purge system'can be initialized _by depressing simultaneously ' 2 PURGE buttons on the control panel. CAUTION The purge buttons on the control panel are used as an override system for the operation sequence and should not be used unless an individual qualified in the use of this, system is present. 6 O l i l I l I 9 O e e l O v l nam ul est , l l
,, _ _ _. _, I
e CEIRCIA POER COPPANV HATCH M.lCLEAR PLANT
- PROCEDURE OH Site Dost_ggj;imati2D5 -
PROCEDLRE TITLE HP-4853 PROCEDLRE NUPEER H g 1 t h P h y.m i n RF'3PONSIBLE SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( ) _----_. ..--_-__----_---__--_.._-----_--___--_-a._--_--_______--4 -------. APPROVED APPROVED REV. DESCRIPTION DEPT. PLANT DATE EAD ER _ _ _ - - - ..------__--__--------. . . - - - _ _ - - - - - _ - - - - . .-_ --_-- -_--_-4-- '_._-. 1 General Revision m _ f_ y3,-_--_L , j gg ,gt _ _ - _ - - _ ....----_--_--___----- - - _ _ - - u--__. .. -9 - _-- 2 General Revision [N - -_- _. M _-. 3 Pages 1-8, 11, 13, 4
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PROCECURE NO. HNP- 5 21 sheer 1 Oe z- - g - Revision No. i j DEPhnTMs5T WEAD APPROVM_ REGUESTED_0Y _ _ _ , _ e-Name: Date: {3 [)v-q_-
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' /d REVISION CHANGEG( MOOO OF CPERATION GR IrlTENT AS DESCRIGE
) Yes (K) No CHANGE ItNOLVES: ( ) Tech. Specs. ( M Neither I. ) An unreviewed Safety Guestion (See t.ack for Safety Evaluation if required).
Non-Saf e ty Related .( ) PRESENT STATUS: Safety Related ( N) ( ) Yes to _____u_..___ The above Safety /Non-Safety Status has changed " Attach markod up copy of procedure 'to this form. REASON FOR REGUEST: O C - m a b O& dins o-n _'TKDGMA<- , NwfCt!)o M C0(M _(yf35 ~ ' i 1 0SE" Otesrcr
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'88-187 /d-f,-r.3 Date PRO Numbec HNP-9
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.. PROCgCip E REVISION RgGUESI SHEET _2_ 0F_7 _ _
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REVISION NO.__ y REASON FOR REGUEST: 0 C Me v d! Ih. - Dr00drC i Nt, '~ l t
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bel _q.wu._ _ i' T.he probability of occurrence and the consequences of an accident or l important to sa ety are no t incre_ased above en f _ ___qajf.pnction of eg,i.pge,t th.o.se anal.yzed.._i_n_the FSAR due to this revision becaus.e__the revis
~
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' sus. tam resp _on_ds and 9C ope _ rated as before the revision.
?Y bM- T. _
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l . _ _ _ _ _ .
.; L The margin of safety, as defined in the Technical Specifications is t change _-
..__not reduced due to this revision because the revision d any limited safety system settings which would allow a safety lim l _
to be exceeded or allow a limiting condition for operations to be exceeded" as stated in Technical Specifications. T ,.h.N_ -_ s ~
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aa m va' E. l. H;tch Nucl':Cr Pihnt =awa= = HNP. 4 52 Sea Titlo Pcg2 a.viso. = 5 4
- m. Georgia Power mk. -..
See Title Page 1 of 40 hh
~
OFF SITE DOSE ESTIMATIONS NOTE
. This procedure supercedes HNP-4650 Revision 2.
' A. -EUREQSE To describe methods which may be used for estimating off site radiation dose during emergency conditions at Plant Hatch.
B. EgEg8ENCE
- 1. Manual of Protective Action Guides and Protective Actions for Nuclear Incidents, E.P.A.
- 2. HNP-4854
- 3. Reg. Guide 1.145 -
- 4. Reg. Guide 1.109, Rev. 1
- 5. Workbook of Atmospheric Dispersion Estimates, E.P.A.
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 assist 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 l along to the State Representatives as received but their estimates of thyroid doses are expected to be appr;ximately 3 to 300 times higher due to the differences in iodino, noble gas ratio. The metho,dology is based on Reg. Guide 1.145 dispersion models and Reg. Guide 1.109, Rev. 1 dose factors. These models have been programmed on a mini-computer located at the EOF. The same program can be run on a mini-computer located near the General Office (Atlanta) Emergency Center. i o > A". ygg 6 *N U # [" + Y
. om E.1. H:tch Nucl:cr Picnt awa=as ao HNP. 4152 Seo Titlo Pcg] namnw uo om GeorgiaPower d ....
See Title Page 2 of 40 D. Estimation of Offsite Exposures NOTE The miniccmputer system is designed to take various plant l and meterological data as input and calculate offsite dose l rates, cumulative doses, and tabulate these for each sector at 1, 2, 5 and 10 nile distances. Protective Action Recommendat' ions are also tabulated using the criteria of HNP-4854. The system is designed for updating every 15 minutes and has the added capability to forecast exposure data for hypothetical sets of release parameters. Tabulation of field monitoring data is also provided.
- 1. Set up the minicomputer per Chucklist No. 1.
- 2. Enter initial data as requested by the computer.
- 3. When the " verification run" is complete, assure the valbes match those on Checklist No. 1. If they do not match, * ,
repeat system setup using an alternate disk. ,
- 4. Enter radiation monitor or sample data as requestri. This information is obtained from a communicator / recorder.
Meteorological data is also provided by the communicator / recorder.
- 5. Three copies of printout are available for use by:
- 1. Status Board Recorder - and subsequent Posting
- 2. Dose Assessment Manager
- 3. Field Team Coordinator
- 6. All data printouts should be reviewed and initialed by the Dose Assessment Manager.
- 7. . Periodically perform verification calculations using data from Tables in Appendix A of this procedure. For the appropriate stability class, wind speed and distance, multiply the curies per second release rate by the Table factor to estimate dose rate. Compare with printout data.
Inconsistencies must be reported to the Dose Assessment Manager.
- 8. Provide all data and Protective Action Recommendations to State (DNR/EPD) personnel.
O g sd g. n _ _ _ - _ - _ _ _ _ _ _ _ - _ - _ _ _ _ _ - _ _ _ _ _ - _ . _ _ _ . . . . d'
HNP. 4852 Sea. Tit 10 Pcg3 amsnm w 5 om . Georgia Power d .... . i See Title Page 3 of 40
~
E Protective Action Recommendations are based on cumulative doses plus a two hour projection. Longer projections may be made by simply multiplying the calculated dose rates by the projections time desired.
- 9. Exposure estimates for field monitoring teams can be made by periodically checking pocket dosimeters (whole body) and multiplying stay times by measured radiolodine concentrations using the following conversion factor:
mrem /hr (thyroid) = 1.85 Et9 i$1/cc (I-131) W e
- 4 Gb 0
O m e e mEEEN 8't
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. .vam E. I. Hatch Nucl;;r Picnt a"<=a' ao HNP. 4852 Sea Titlo Pcg3 ..mios uo om Georgia Power A ....
See Title Page 4 of 40 CFECHLIST NO. 1 SETt.P OF DOSE CALCtLATION MINICOPPUTER
- 1. Move Computer Console and Printer to Dose Assessment Area. Plug both units to 120 A.C.
power. Connect printer to computer.
- 2. Turn Printer on (switch is in back) and press reset button.
- 3. Turn Computer on (switch is on right hand side).
- 4. Insert Diskette and close door. Red light should go on.
- 5. When red light goes off, press reset button.
_ _ 6. Type in Data and Time (24 hour clock) as
- requested and press Enter key. ,
- 7. Type in the following sequence:
(1) Basic (Enter key) (ii) Press "2" Enter l (iii) (Enter key) (iv) LOAD " DOSE" (enter key) l B. Type in information as requested.
- 9. Compare verification run with the following values:
VERIFICATION RUN VALUES (meem) DISTANCE. WHOLE BODY THYROID 1 mile 1225 3484 2 miles 503 1431 5 miles 108 306 10 miles . 41 117 tLol If the verification run values do not match those above, return to Step 4 and use an alternate diskette.
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APPEICIX A VERIFICATIt'N TARLES VER1FICAf!0N TAR.E
* $7AOL t.EVEL REEASE
$7A3!LITY CLASS A TWGAf!0N R1LL! HEP /HR PE8 CURIE /SEC OF IODINE RE1. EASED UPPE8 W!W N@ DM N NE W SPEED tem 1 M! 2 nt 2 n! 4 M1 S R1 6 M1 7 RI S n! 9 MI te nt 1 4.35E43 2.44E43 1.69E43 1.31E43 1.31t*t3 1.31E43 1.31E43 1.31E43 1.31E43 1.31E43 2 2. E+83 1.n+83 8.44E42 6.5M42 6.55E42 6.52 42 6.5%+t2 6.5M42 6.53E*82 6.+M+t2 3 1.52 43 8.12+t2 5. 1 42 4.37: 42 4.37E42 4.37E42 4.37E42 4.37E42 4.3A+t2 4.3M+t2 4 1.14E+43 6.8aE42 4.22 42 3.:E42 3.2M42 3. E42 3.2E42 3.2SE42 3.2BE42 3.X+32 3 9.!!!42 4.87E42 3.2E42 2.M+42 2.M+t2 2.Q42 2.M 42 2.E+82 2.E+82 2.m+t2 6 7.59E42 4.8d*82 2.81E+02 2.!K+82 L1E+42 2.!E+82 2.!E42 2.18E42 2.1K42 2.tE+42 7 ' 6.51E42 3.48E42 2.41E42 1.8K+82 1.84+t2 t.83+82 1.84 42 1.87E42 1.87E42 1.8M+t2 5 5.69E+02 3.84E*82 2.t!E 32 1.64E42 1.64E42 1.64E+22 1.64E42 1.64E42 1.64E42 1.64E42 9 5.8g+82 L71E42 1.88E42 1.46E42 1.46E42 1.46E+t2 1.46E42 1.46E+22 1.46E42 1.4E+42 18 4.5M42 2.44E42 8.69E42 1.31E42 1.31E42 1.31E42 1.31E+t2 1.3'!42 1.31E+42 1.31E42 11 4.14E+42 2.21142 1.54E+82 1.19E42 1.19E42 1.19E+t2 1.19E+82 1.19E42 1.19E42 1.19ET 12 3.88E42 2.83E42 1.41E+42 1.89E42 1.!9E42 1.21E42 1.89E+02 1.89E+t2 1.89E+82 1.89E+t2 13 3.!E+82 1.87E42 1.38E+82 1.81E42 1.81E+82 1.81E42 1.81E+82 1.81E42 1.81E42 1.81E+42 14 3.3E42 1.M42 1.21E+02 036E+0! L36t+81 9.36E+41 9.36E41 9.36E41 9.36E41 9.36E41 13 3.84E42 1.62 42 1.13E42 8.74E41 8.74E+t1 8.74E41 8.74E+81 8.74 41 8.74E+41 8.M41 le 2.85E42 1.52+02 1.86E+02 8.19E+81 8.19E41 8.1?E41 8.19E41 8.19E41 8.19E41 8.19E41 17 2.6E+42 1.4X+82 9.93E41 7.71E41 7.7tE41 7.71E+41 7.71E41 7.71E41 7.71E41 7.71E41 9.3E41 7. K41 7.:E+81 7, SE41 7.28E+01 7.28E41 7.:BE41 7.2E41 18 2.5x+82 1.35E+42 19 2.4E+82 1.28E+82 8.89E41 6.98E41 6.98E+81 6.98E+41 6.9tE41 6.9tE+81 L98E+01 6.9E+61 28 2.:g,82 1.22+02 8.44E41 6.55E41 6.53E41 6.55E+81 6.53E41 6.53E+61 6.5M41 6.55E41 21 2.!E+42 1.16E+82 8.84E+41 6.24E+01 6.24+81 6.24E41 6.24E41 6.24E+41 6.24 41 6.24E41 22 2.84+42 1.11E42 7.6E41 5.9E+41 5.96E41 5.96E+0! 5.96E41 5.96E41 5.9d41 5.9E41 23 1.9E+82 t.td+02 7.34E41 5.7E41 5.7tE+81 5.72E41 5.72E+41 5.7E41 5.7E+01 5.7E41 24 1.9tE+82 1.81E42 7.84E41 5.46E4 5.46E41 5.46E+41 5.46E*81 5.46E+01 5.46E41 5.4d41 25 1.82+t2 9.74E41 6.75E+81 5.24 41 5.24E41 5.N41 5.04E41 5.24E+41 5.24E41 5.24E41 26 1.EE+42 9.3M41 6.49E41 5.84E41 5.34E*01 5.84E41 5.84 41 5.84E+81 5.84E+41 5.84E+61 27 1.69E42 9.82+81 4.:H+41 4.86E41 4.86E41 4.86E41 4.66E41 4.86E41 4.8M41 4.86E41 S !.G42 8.72 81 6.81 41 4.68E41 4.68E+81 4.6K11 4.68E41 4.6BE+t1 4.68E*t1 4.6tE41 5.82 41 4.12 41 4.5 E41 4.5 E41 4.52+81 4.M+81 4.5 2 ,91 4.52+0!
29 1.5342 f.6tE41 38 15242 ' 8.12+81 5.G+41 4.37E41 4.37E41 4.37E+81 4.3M+41 4.37E+81 4.37E41 4.3M+81 33 1.44+t2 7.8g41 5.4M41 4.23E41 4.21 41 4.23E41 4.;3E41 4.22 41 4.:3 41 4.:1 41 12 1.42 42 7.61E+81 1.28E41 4.1E41 4.1E41 4.1E41 4.!K+81 4.18E41 4. tee 41 4.1E41 33 !.38E+t2 7.38E41 5.12 41 3.9'E41 3.97E41 194+t! 3.97E41 3.97E41 3.97E41 3.94 41 34 1.34E42 7.16E+81 4.97E41 3.86E41 186E41 3.66E+81 3.86E41 3.86E41 3.96E41 3.8E+0! 25 1.3E+42 6.86E*41 4.82+81 3.75E41 3.75E41 3.75E+41 3.75E41 3.7H41 3.75E41 3.7M4 36 1.2X+42 6.76E41 4.69E41 3.64E41 3.66E41 3.64E41 3.64E41 3.64 41 3.64E41 36441 37 1.23E42 6.5K+81 4.5d41 3.54E41 3.54E41 3.54E+81 3.54E41 3.54E41 3.54E+81 3.54 41
- M 1.28E+82 6.41E41 4.44E41 3.45E+81 3.45E41 145E41 3.45E+81 3.45 41 3.45E41 3.45E41
, 39 1.14 42 6.24E+81 4.3X+81 136E41 3.36E41 3.3d+41 3.3d41 3.36E41 3.36E41 3.36E41 ! 48 1.14E42 6.89E*81 4.22+01 3.2E41 3.2E+81 3.28E41 3.:SE41 3.:SE41 3.29E41 LX41 ! 41 1.11E+82 5.94 41 4.12+81 128E41 3.28E41 3. E41 12tE+81 3.22E+81 1E41 3.2E41 42 1.8E+t2 5.8tE+81 = 4.82 41 3.12E+81 3.12+81 3.12 41 3.12 41 3.12 41 112+81 3.12 41 43 1.tg+t: 5.66E+81 3.9X41 3.t!E41 3.t!E41 3.EE41 3.et 18v4: 3.eE.81 3.EE4: 44 1.84 42 5.53E41 3.84+81 2.93E41 2.98E41 2.98E41 L9EE+81 2.9E 41 2.95E+0! 2.9E+81 45 1.t1E42 5.41E41 3.75141 2.91E41 2.91E41 2.91E41 2.9tE41 19!E41 2.91E41 L91E41 46 9.9E+01 5.29E+0! 3.67E41 2.8%+41 2.85E41 2.EE41 LEE 41 2.EE41 2.E!41 2.85E41 47 9.69E41 5.18E41 3.59E41 2.79E41 L79E41 2.79E41 2.79E41 2.79E41 2.79E*01 2.79E+t1 48 9.49E*01 5.84 41 3.52+41 2.72 41 2.73E41 2.71 41 2.73E41 L73E41 2.73E41 2.73E+81 49 9.;9E+81 4,97t+41 3.45E41 2.6E41 2.68E41 2.63E41 2.68E41 2.68E41 2.68E41 2.6E41 58 9.11E41 4.84+41 3.3BE41 2.62+81 2.M41 2.62 41 2.G+81 2. Q 41 2.62+81 2.E+0!
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, APPEDOIX A VERIFICATION TABLES WERIF12ATIC1 TA8LE g.
STA0( LEVEL ELEASE 8 ASILITY CLASS I FUM! GAT!m MILL!EP/MA PEA CURIE /SEC Otr IODINE RE1. EASED UPPE8
-Wlag IkAssi!ND DISTANCE HOM Tif PUWT MES (MPm 1 M1 2 Mt 3 MI 4 Rt 5 Mt 6 M: 7 Mt 8 M1 9 MI 13 Mt 1 2.63E+44 - 7.91 43 3.E43 2.86E43 1.43 43 1.31143 1.31E43 1.31E43 1.31E43 I.31E43 2 1.M44 19d43 1.81E43 1.81+03 ' 7.88E42 6.5H42 6.55E42 6.55542 6.55E42 6.5M+02 3 8.92+s3 2.64+e3 1.21E43 6.87E+02 4.72 42 4.37E42 4.M+02 4.37E+82 4.37E+32 4.34,82 4 6.ME43 1+9E43 9.84 42 115E42 3.N+02 3.28E42 3. E42 3,28E42 3.28E42 3.2E42 5 5.35E43 1.59E43 7. . E42 4.12 42 2.83E42 2.G+02 2.G 42 2.E42 2.G 42 2.62 42 6 4.4d43 1.32 43 6. k 12 14I 42 2.3d42 2.tE42 2.1K42 2.18E42 2.18E42 2.!E42 7 3.82E43 1.1X+83 5.1E42 2.94E42 2.22 42 I.E342 1.87t+82 1.87E+Ts2 1.87E42 1.8M42 8 3. M 43 9.9tE42 4.53E+t2 2.57E42 1.77E+42 1.64+82 1.64 42 1.64E42 1.64E42 1.64E42 9 2.97E43 8.81E42 4.IJE42 2.29E42 1.57E42 1.4d42 1.4d42 1.46E42 1.46E42 1.4d42 18 L68E43 7.M42 162+02 L8d42 1.43 42 1.31142 1.31E+82 1.31E42 1.31E42 1.31E42 11 2.43E43 7.21E42 3.3E42 1.8N42 1.29E+42 1.19E42 1.19E42 1.19E+t2 1.19E+02 1.19E42 12 2.21 43 6.61E42 3.82+02 1.73+82 1.1E+82 1.89E42 1.29E42 1.39E42 1.89E42 1.95 42 13 2.8d43 6.18E42 2.79E42 1.58E42 1.09E42 1-81E42 1.81E+t2 1.t!E42 1.51E42 1.81142
- 14 1.91E43 5.6d42 2.59E*02 1.47E42 1.81E42 9.3d+01 9.36E41 9.3d41 9.36E41 9.3d*
15 1.7EE43 5.29E42 2.42 42 1.37E42 9.44E41 8.74E48 8.74E41 8.74E41 8.74E41 . 8.M+01 16 1.67E43 4.95E42 2.2A42 1.29E*02 8.85E41 8.19E+01 8.19E41 8.19E+01 8.19E41 - 8.19E+01 17 1.?7E43 4.%E42 2.13i 4 2 1.21E42 8.33E+81 7.71E41 7.71E41 7.71E41 7.71E41 7.71E+61 18 1.49E43 4.4E42 2.81E42 1.14E42 7.8d41 7.28E41 7.28E41 7.2SE*ft 7.28E41 7.2E41 19 1.41143 4.!M42 1.91142 1.88E42 7.65141 6.95 41 6.9E41 6.9tE41 6.9eE41 6.9E41 29 1.M43 3.96E42 1.81E42 1.83E+t2 7.8E41 4.55E41. 6.53E41 6.55E41 6.55E41 6.51 41 21 1.27E+t3 3.78E+82 1.73E42 9.81E41 6.74E41 6.24E41 6.24E41 6.N41 6.N41 6.24E41 22 1.23 43 3.6tE42 1.E42 9.3d+81 6.42 41 5.96E41 5.96E+81 5.96E+81 5.96E41 5.9d+0! 23 1.16E43 3.45E42 1.58E42 8.95E41 6.15E41 5.72E41 3.7tE+tt 5.7E+t! 5.7E41 5.7E41 24 1.!!E43 3.32E42 1.51E42 8.5E41 5.90E41 5.46E41 5.4d41 5.46E41 5.46E41 5.4d41 25 !.t'E43 3.17E42 1.4M42 %.24E 81 5.66E41 5.24E41 5.24E4" 5.N41 5.24E41 5.M41 26 1.82 43 3.85E42 1.31E42 7.93+01 5.44E41 5.84E+tt 5.24E41 5.84 41 5.24E+tt L N 41 27 9.91142 2.94E42 1.M42 7.E41 5.24141 4.86E41 4.86E41 4.86E+81 4.86E41 4.8d41 29 9.56142 2.82 42 1.3tE42 7.3d41 18sE41 4.68E41 4.6E41 4.6SE41 4.68E+01 4.6E+01 29 9.21 42 2.72 42 1.25! 4 2 7.13 41 4.82E41 4.53+21 4.53 41 4.53 41 4.53 41 4.53+0! 38 8.93 42 2.64E42 1.21E42 6.87E41 4.73+t! 4.3'E41 4.37E41 4.37E41 4.3'I41 4.37E41 31 , 8.E42 2.5d+42 1.17E42 6.64E41 4.57E 21 4.23E41 4.23E41 4.23E41 4.23E41 4.21 41 32 8.36E42 2.4eE42 1.13E42 6.44 41 4.43 41 4.15 41 4.12E41 4.1tE41 4.13 41 4.!E41 33 8.!!E42 L4E42 1.12E42 6.24E41 4.29E41 3.97! 4 1 3.97E41 3.93+81 3.9'Z41 3.77E41 ! 34 7.84 42 L3I42 1.87E42 6.86E41 4.12 41 3.8d41 3.86E41 3.86E+t1 3.86E+81 3.86E41 l 35 7.65! 4 2 2.2T+02 1.84E42 5.88E41 4.84E41 3.75E41 3.75E*tt 3.75E11 175E41 3.75E41
'4 7.4I 42 _2.2E42 1.81E42 5.72 41 3.93E41 3.64E41 3.64E41 3.64E41 3.64E41 164+0!
37 7.2I 42 2.14E42 9.8IE41 5.57E41 3.83E41 3.M 41 3.54E41 3.54E41 3.54E41 3.54 41 3 7.84E42 2.29E42 9.54E41 5.42 41 3.71 41 3.45E41 3.45E41 3.45E41 3.45E+81 3.45E+81 39 6.86E42 2.83E42 9.38E41 5.28E41 3,E+01 3.36E41 3.36541 3.36E41 3.36E+81 3.3d41 ! 49 6.69E+t2 1.9E42 9.84 41 5.1M41 3.54E41 12SE+M1 3.28E41 3.28E+0! 3.28E41 3.2E+tt 41 6.5I 42 1.91 42 8.85E41 5.85 41 145E+41 3.28E41 3.2fE+01 3.2E41 3.22E+61 3.2E41 42 6.34 42 1.89E42 8.E 41 4.9eE41 3.34 41 3.12 01 3.12 41 3.12 41 3.12E41 3.13 41 43 6.22 42 1.84 Eat 2 8.43E+81 4.79E41 3.29E+0! LEE 41 3.tSE41 3.t5E41 3.85E41 3.EE41 44 6.8E42 1.8E42 8.N 41 4.6E41 3.22 41 2.98E41 192E41 2.9K41 2.9EE41 2.9E41 45 5.95E42 1.76E42 8.86E41 4.5E41 3.15E41 2.91E41 2.91E41 2.91E+0! 191E41 2.9tE41 46 18342 1.73 42 7.8E41 4.4K41 3.08E41 2.85E41 L85E41 2.85E41 2.85E41 2.85E41 47 169E42 1.69E42 7.73 41 4.3E41 2.81E41 2.79E41 2.79E41 2.79E41 2.79E*01 2.79E41 48 5.5442 .1.65E42 7.56E41 4.29E41 2.9M41 2.72 41 2.72 41 2.73E41 2.73E41 2.71 41 49 5.46E42 1.G42 7.6EE41 4.2E41 2.89E41 2.68E41 2.68E41 2.68E41 2.6BE+01 2.6E41 58 5.25E42 1.59E42 7.2*E41 4.12 41 2.82 41 2.62 41 2.62+01 2.G41 2.62 41 2.63 41 msgud s_et y. rooe:o 'TI - c>
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8 M1 9 MI te MI 1 4.8I 44 1.75ES 9.12 43 5.59E+03 3.79E43 2.74E43 2.89E43 1.77E+U :.59E43 1.4M43 2 2.82 4 8.M43 4.5E43 2.79E43 1.89E43 1.37E43 1.84E43 8.82 42 7.95E42 7.24E*02 3 !.34 44 5.82 43 3.84E+d3 1.8E43 1.26E43 9.15E42 6.95E42 5.83 42 5.3OE42 4.81 42 4 1.01E44 4.3E43 2.2K+03 1.E43 - 9.47E42 6.BE+02 5.22+42 4.42E42 L9K42 3.E 42 5 8.97E43 3.49E+03 1.82 43 1.12 43 7.57E42 5.49E+02 4.17E*02 3 5JE42 118E42 2.9E42 6 6.72 43 2.91E43 1.52+03 - 9.31E42 6.31E42 4.57E42 3.48E+02 2.94E42 2.E42 2.41E+02 7~ 5.76E+43 2.49E+03 I.3E+03 7.98E+32 5.41E42 3.92+02 2.98E42 2.52 42 2.2E42 2.37E42 B 5.84E43 2.!K43 !.tE+03 6.98E42 4.M42 3.4X+02 2.61E+02 2.21E+42 1.99E42 1.81E*02 9 4.4E43 1.94+83 1.81E+83 6.21E+32 4.21E 82 3.35E42 2.32 42 1.9E42 1.77E42 1.61E42 II 4.82 43 1.75E+03 9.12+02 5.59E42 3.79E+02 2.74E42 2.09E+42 1.77E42 1.59E+42 1.45E+t2 11 3.67E43 1.59E43 0.29E+82 5.8K42 3.44E42 2.49E42 1.9EE+82 1.61E42 1.45E42 1.32Ee 12 3.3E+83 - 1.W43 7.6K42 4.6E+02 3.!E42 - 2.29E42 1.74E+02 1.47E42 1.31 42 1.21E42 . 13 3.:E43 1.34E+83 7.81E42 4.3EE+02 2.91E+02 2.11E42 1.6E42 1.36E42 1.22 42 1.11E4f 14 2.88E*a3 1.25E43 6.51E+t2 3.99E42 2.78E+02 I.9E+42 1.49E42 1.26E42 1.14E+42 1.RDR2 15 2.69E43 1.1E+03 4.IK+82 3.M 42 2.52 42 1.8I 42 1.39E42 1.18E42 1.8bE42 9.45E41 16 2.52 43 1.99E43 5.78E42 3.49E42 2.37E42 1.72 42 1.3E42 1.tE42 9.94E+01 9.85E41 17 2.3K43 1.H43 5.3E42 3.29E42 2.21 42 1.61E42 1.2X42 1.84E42 9.3E41 8.52E41 18 2.24E43 9.69E42 5.8E+02 3. !E+42 2.!E+42 1.52 42 :.16E42 9.81E+0! 8.94E41 B.04E41 19 2.12 43 9.1E+02 4.8K42 2.94E42 1.99E42 1.44E42 1.!E+02 9.3rE41 8.37E41 7.E 41 20 2.82 43 8.7I 42 4.5E42 2.79E42 1.99E42 1.37E42 1.34E42 8.83E+t! 7.95E41 7.M+41 21 1.92 43 8.31142 4.34E42 2.66E42 1.8E+82 1.31E42 9.93E41 7.5E41 8.41E41 6.9K41 22 1.E43 7.E42 4.14E42 2.54E42 1.72 42 1.:*E+32 9.4E41 8.E*e! 7.2X >41 6.5E41 23 1.75E+a3 7.59E42 3.96E42 2.E 42 1.E42 1.19E42 9.84 41 7.63E41 6.93+01 6.M41 24 1.6EE43 7.27E42 3.M42 2.3X+82 1.!E42 1.14E42 8.69E41 7.36I+81 4.E41 6.81+01 25 1.61I 4 3 6.99E+42 3.65E42 2.24E+82 1.51E+22 1.!K42 8.34E41 7.87E41 6.36241 5.79E+01 26 1.55E43 6.71E42 3.51E42 2.15E42 1.46E42 8.82 41 1.86E+22 6.79E*31 6.12 41 5.57E41 27 1.49E43 6.46E42 3.3aE+02 2.27E42 1.4aE+02 1.22 42 7.72 41 6.54E41 5.89E41 5.3E41 28 1.44E43 6.2X+02 3.26E+82 2.0K42 1.ZE42 9.8EE41 7.45I+t! 6.31E41 5.68E+81 5.17E41 29 1.39E43 6.82 42 3.14E42 - 1.92 42 1.21E42 9.46E41 7.19E-81 4.29E41 5.49E41 4.99E41 38 I.34E43
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- 21 I.16E44 6.!8E43 4.29E43 3.3:E43 2.72E+83 2.29E43 1.94 43 1.77E+83 1.*9E+83 1.44E43 22 1.12 44 5.9tE43 4.t9E43 3.1H43 2.58E43 2.19E43 1.92E+B 1.&aE+t3 1.52 43 1.38E43 23 1.36E44 5.64E43 3.91E43 3.82 43 2.4E43 2.t9E43 1.82 43 1.6.s43 1.d43 1.32 41-24 1.t;E44 5.41E43 3.72 43- 2.89E43 2.36E43 2.8:E43 1.74E43 1.5M43 1.39E43 1.26E43 3 9.71E43 5.19E+B 3.6E43 2.7E+0 2.2'E+03 1.93E43 I.67E43 1.4EE43 1.33E+83 1.2tE43 26 9.M43 4.99E+03 146E43 2.64 43 2.12E+83 1.85E43 - 1.6:E 83 !.E+83 1.28E43 1.1H43 27 8.9'E43 4.8 E43 3.33E43 2.5H43 2.12 43 1.78E43 1.*5E43 1.34 43 1.24E43 1.12 43 28 8.67E+43 4.64+83 3.21E43 2.48E43 2.83543 1.72 43 1.52E43 1.33! 4 3 1.19E43 1. gee 43 29 8.37E43 4.48E43 3.tE4 2.39E43 1.92 43 1.66E43 1.44E43 1.2SE43 1.15E43 !.t3E43 34 8.19E43 4.32 43 3.IE43 2.31E43 1.89E43 ' !.6tE43 1.42E43 1.N43 1.11E43 1.t:E43 31 7.83E43 4.19E43 2.9E43 2.24! 4 3 !.8X+33 1.55E+83 !.35E43 1.22 43 1.88E+0 9.79E42
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43 1.;II C 5.*II-31 1.&24 1.4!E 21 1.32 4 3.92 41 1 3;E t 2.46E41 2.09E4 1.E:E41 41 1.EEC 3.tsE-I! 1.G41 1.29I 4 2.% M ! 2.4:E41 2.2'.I-11 1.7?E t 1.5*E-21 42 . TIC 5.! 141 3.3 2-31 1.72 { !.54E-!! 1.II4; 1. LM 1.2'EC 5.3EIC 3.73E-21 LE'E4' *MC 1.99E t 43 2.!:I-21 2.3E-M 1.1!E-21 I.67E4 f.!E41 1.ZM: 1,;24 44 9.E241 5.2!4' 3.1* 31 1.itES !.G{ !.32 41 1.2H
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- 1. 9I-31 1.'sE11 1.171-C 1.1!E<
9.2EC 4.7241 3.4;E41 2.63E41 1:!Et 47 2.1:E{ 1.:I!41 I.24E11 !.11-: 48
- 7.21M1 4.1 2 -21 3.3+31 *!E41
. l.7E-31 f.!!!t 1.2 M1 1.12-;
4.*2 41 3.2'E@ 2.!2 41 2.*.d-El 1.75E-21 1.t'f41 !.ZEt 47497 8.t:EC ,t.49E41 13241 1.19E41 1.23Es
. '4.32 41 3.::M1 2.m41 2.3241 1.71 H 1
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. STA3 tra ELEAE h $W:LITY CUSS F Gm:3A!!M /
. MILLIfe!ER FE3 C E E/5E: W E3LE GASES EZLEME3
'MEP C's DOM D:57#G FEH Nd7 INE 18 M!
5 51 6 MI 7 MI E MI 9 31 (Pio 1 Mt 2 R! 3 91 4 M1 l L2:14: 3.2iE-et 2.3'E*3: 1.79E41 1.4tH1 1.*4E41 !.22141 9.!!Mt 3.61Mt 7.E2E- 3 8.?iM3 L21E42 5.m43 4.79N3 4.3;M3 191M3 2 3.12 41 1.6Mt 1. 6E41 7.33+23 3 2.tef4: !.134: 7.?-M2 1.1 E42 4.EN+t2 4.144r 3.62 M 3 3.19H3 2.E71-t3 2.t:E4: 4 1.5341 B.37E42 5.3;M3 4. E 42 3.11I 4 3 3.:EC 2.72E42 2. M C Ll!MI I.9:IC 5 1.2141 07:I43 4.6d48 L!SE42 tm42 2.dE45 2.14F+3R 1.13 4 1.7"EC 1.!?E C
& l.2tN! 5.!!E43 3.1'M2 19Ede 2.44E43 2.3*M3 .t.HE43 1.12 M 3 1.44*f3 1.33 4 7 5.9'IC 4.'EE43 3.22C 2.5tE42 2.F M I 1.7'MI 1.54 42 1.2'M2 1.:2t c 1.:3 43 4.:'I43 2.83 42 1.8E43 1.55E-33 1.35N3 1.;2M3 1.23IC 9.PI41 -
3 7.3E43 2.24E+23 3.?'Est L!!M2 1.17542 1.G40 1.3EE4A 1.;2E4: 1.2t M 3 9. ?E-2: 3.*3 41 . 9 6.9tM3 13 6.2tMI 3.3'E48 2.33 43 1.7M48 1.4d40 1.24M3 1.33E4: 1. tie 41 8.6:E{ 7.tE41 * . 1: 5.6tM2 3.bEC 2.1tM3 1.13 42 1.32i 4 2 1.G48 9.t3-2: 8.7:E-11 7.E7E4: ?.:341 12 5.22HC 2.77H3 1.4M3 1.49He 1.23 43 1.32 43 . 9.2:N1 7.* 71-21 7.;iH: 4.!!!41' 13 4.E342 2.!EE42 1.71M2 1.3EM3 1.13E4! 9. 5 41 E.3:H' 7.37148 A&241 6.CI41 14 4.WN 2.37M3 1.66M2 1.22143 !#E43 8.5 I41 7.73 41 6.3'E-41 6.15HI 5.FI41 15 4.1EEC 2.:2EC 1.5! N 3 1.19E42 9.76f-It 8.2EE-31 7.*fE41 6.33E-31 5.7.ES 5.0141 16 3.9:E43 2.UH3 1.45M2 1.1 3 -33 9.:5E-31 7.76H1 6.7!Et 5.99E-11 5.3?H1 4.1 4 -21 17 14M2 1.9E42 1.3"E-02 1.25! 4 3 E.6:E-21 7.2EE41 6.2cM: 5.G41 5.221C 4.63-t! 13 3.*fEC 1.!!M2 1.24 43 9.95E-6: B.!I-91 6.*2 41 6.3tI-11 5.2341 %.75M1 4.EH1 9.G41 7.7341 L!4E 81 5.&it-!! 5.2441 4.121 4 4.13 41 19 3.2:IC !.?cE C t.:3C 4.3;H: 191H1 g L:343 1.t'I 23 1.!9M2 1.ltHe 1.!!! 22 B.91H1 B.1X{ 7.33 41 6.9'I-21 L21E41 5.9:141 5.W-31 5.14E-31 4.77141 4.!42-21 4.1 3 -21 173-tl T. 2.9fM2 22 2.35M3 1.5 3 -38 1.81M3 1.14E-31 6.15H1 5.i;E41 4.91H1 4.; HL 3.9 3 -31 3.562-31
- 3 2.73 42 1.4&EC 1.nM2 7.79E-41 L37E41 LE-31 4.73- 4.16Et 3.M4' 3.*IEC t.4!c 9.65!-31 7.46E41 L1E-31 5.17E41 4.1Z-31 3.99E-4: 3.51E41 3.71141 26 2.61E+N 25 2.5:E42 1.3.N3 9.:9E-31 7.11E-31 1.561-21 4.97H1 4.3 3 -81 3.a-21 144HI 11241 26 2.l:M3 1.:iM3 B.9141 Lt'E-91 5.62I-01 4.7E-Il 4.16H1 3.63E41 3.31H1 3.21H1
- 7 2.2 Hf 1.:iM2 9.E-U LG41 5.G-31 4.63E-31 4.t:E-31 L!!H' 2.19E-31 :.TM1
- S 2.2tH2 1.2E4 3.2fMI 6.E41 5.2 1 -31 4.E41 3.36E-il 3.4 3 -31 3.HH1 2.EI4 29 2. tim 2 1.11M2 f.!'H1 6.:tE-O! L2!E-31 4. 3E-3: 3.77-t1 L:3-31 2.9'E41 17Z141 32 2.29Mt 1.13 43 7.74I-11 5.97H!- 4.3EE-31 L14I41 3.1541 3.l'H1 2.!?! Il 2.6:H1 3: 2.CIC 1. tie 42 7.497-31 5.7EH1 4.7 3 -31
- 4.11E{ 3.6E-ti 3.2c141 2.*?i-t! 2.52E-t!
32 1.h!43 1.233:3 7.26H1 5.!E41 4.!E-31 3.3E41 3.3E4! 2.944! 2.61H1 2.G4! 23 1.t3C 1.2tE C 7.3 4 -21 ' 5.42E-t 4.4*E-t! 3.76E4' 3.27E{ 2.92H1 2.t:H: 2.3"It 34 1.15!c 9.E5H! LE2H1 5.2 3 -21 4.3tH1 3.65H1 3.1E-31 L3341 2.!E-2: 2.3JE41 Z l.79MS 9.57E-21 6.63E-Il 3.13 41 4.!aE-21 3.!!M 3.UH: 2.74E41 2.4tH: 2. 4 41 36 1.N43 9.2I41 6.4!H1 4.97E41 4.I'E41 LG31 3.22H1 2.16HI 2.3?I{ 2.17H1 37 1.6cE C 9.CE-tt L"5E47 4.t;E41 3.ftt-21 3.2tH1 2.93 41 2.59E41 2.3]E41 2.13 4. 33 1.6!I-23 8.E:E41 .6.11E-31 4.7:E41 3.5 HI 3.27E-31 2.N4: 2.5 H1 2.27MI 2.tiH' 29 1. t'.Mt E.!ti-fi L9524 4.59E41 3.7:E-31 3.11H1 2.77141 2.4d41 2.T.E-2: 2.21-t 8.3*Et 5.3:E4I ~ 4.4EMI 3.hiH1 3.!t!{ 2.73 4! 2.3'H1 2.11H1 1.hMi 43 g l.5"MJ 2.34 41 2.12H! 1.9:H: 4: ,1.52E 2 8.1'E41 Litt-3: 4.3'E-t! 3.!'E-3: 3.t22-31 2.64E-81 42 1.49M3 7.9'H1 5.1X4! 4.21HI 3.49H1 2.9241 2.57!-91 2. !HI 2.2'H1 1.!6E{ 43 ' I.4tE42 7.E41 L4341 4.11I 4 1 3.E41 :.9cE-It 2.5tE41 2.02it 2.Ki-2: 1.13-2* 14 1.43 43 7.i!E-21 5.13E41 4.8.'i-31 3.3E-21 2.8:1-11 2.4&H1 2.18H1 1.91!C 1.75 4 1.9;Mt... J.14H g)e 1.29E-(2 7.4*t4: 5.:1541
- 7. !!-:: .5.MI41 3.9EH1 3.FH1 3.3E41 8.1E41 2.7d-4:
2.7E4 2.4tE 2* 2.ZH1
" *Kr.E' 2.23H: 1.5'I-Z' l.7:H' 1.h!43 2.2tE4: 2.24-4: _ .l.E21-31 __1 4714, 47
- 1.3E43 7. 341 -4.94E41 3.8:E41 3.11E-91 2.14E E1
_4.t;E 31 3.73E-Il 3.25!-81 2.5?H1 2.E!41 12341 ; 1.7M-21 !.E-I 48 1.2E43 6.9K-31 3 49 - l.3M3 083-21 3.t E-t! 2. % 41 2.52 41 '. 2. 's-t! 1.f5E-Il cl.7&f-t! 1.e34
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. APPOOIX A VERIFICATION TABLES
+
. m: cat:en rat STA0(IIT RE11ASE 57AI1LITY CLASS A NO PJMIGATION M:111 HEM /HR PER CURIE /SEC OF IODINE RELEASED UPPER ute DCWil2 DISTANCE FROM M PLANT WER IMful 1 M! 2 M1 3 MI 4 M! 5 MI 6 M1 7 MI 8 M1 9 M1 13 M1 4.55E43 2.44E*t3 1.69E+83 1.31E+53 1.3:E43 1.3:E+83 1.31E43 1.31E+I3 1.31E43 1.3;E41 1
2 2.X43 1.22+83 8.44E+02 6.55E42 . 6.55E+82 6.55E+02 6.55E42 6.55E+02 6.55E+82 6.55E42 3 1.52 43 8.12+42 5.62+t2 - 4.37E+02 4.37E+02 4.34 42 4.37E42 4.37E+02 4.3%+02 4.37E+t2 4 1.14E43 6.89E42 4.2:E+82 3.3E42 L:8E42 3.:K42 3.28E42 3.3E42 3.2E42 3.NE+82 5 9.11E42 4.8N+82 3.3E+02 2.62E42 2.E42 2.62+02 2.62E+02 2.62E+t2 2.62+42 2.E+02 6 7.59E+82 4.86E E2 2.E1E42 2.1E42 2.!E42 2.18E42 2.18E+82 2.1E42 2.1SE42 2.13E+82 7 6.5 E42 3.E 42 2.41E42 1.87E42 1.87E42 1.84+02 1.87E+82 1.84 42 1.97E+t2 1.87E*02 8 5.69E42 3.94E42 2.!!E42 1.64E42 1.64E42 1.64E+02 1.64E42 1.64E+82 1.64E+42 1.64E42 9 5.86E42 2.71E42 1.8BE+02 1.46E42 1.46E+82 1.46E42 1.46E42 1.46E42 1.46E42 1.46E42 10 4.55E42 2.44E+02 1.69E+t2 1.31E42 1.3:E42 1.31E42 1.31E42 1.31E+02 1.31E42 1.31E 81 11 4.14E+42 2.21E+9: 1.54+42 1.19E+32 1.19E42 1.19E+t2 1.19E42 1.19E+t2 1.19E42 1.19E42
- 12 3.80E42 2.81+82 1.41E42 1.89E42 1.89E+02 1.89E42 1.89E42 1.39E42 1.89E+t2 1.99E+42 13 3.5E42 1.87E+42 1.3tE+42 1.t1E42 1.0:E42 1.0 E42 1.81E42 1.81E42 1.81E+t2 1.t:E42
- 14 3.3E42 1.74E+t2 1.21E+42 9.36E41 9.36E+61 9.36E+01 9.36E+01 9.36E41 9.36E41 9.36E41 3.0+E+82 1.E42 1.13E42 8.74E41 8.7+E+01 8.74E41 8.74E41 8.74E41 8.74E+81 8. M *01 15 2.EE42 1.52+82 1.96E42 8.19E+01 8.19E41 8.19E41 8.19E+61 8.:9E41 8.19E+81 8.19E41 16 17 2.68E42 1.G42 9.92 41 7.71141 7.71E+01 7.71E41 7.71E41 7.71E41 7.71E41 7.71E+41 18 2.53E42 1.35E+t2 9.38E41 7.28E41 7.28E41 7.28E41 7.3E41 7.28E41 7.28E41 7.3E41 6.92+41 6.9E41 6.9E+81 6.9tE+t1 6.92E41 19 2.4K+42 1.:E42 8.89E+01 6.91+01 6.90E41 6.55E41 6.15E41 6.55E+81 6.55E+01 6.SiE41 6.55E+01 6.55E41 3 L3E42 1.2:E42 8.44E+61 6.;4E+61 6.24E+81 6.24 41 2.17E+82 1.16E+82 8.84E41 6.24E41 6.24E41 6.24E41 6.24E41 21 5.96E41 5.96E41 5.96E+01 5.96E+4 5.96E+31 5.96E+31 5.96E41 22 2.84 42 1.11E42 7.68E+81 5.7K41 23 1.9BE42 1.86E42 7.34E+01 5.78E+0! 5.7E41 5.72 41 5.7E41 5.7tE+01 5.7:Dt1 1.81E42 7.84E41 5.46E41 5.46E41 5.46E41 5.46E41 5.46E41 5.46E41 5.46E41 24 1.9E+02 5.24E41 5.24E41 5.24E41 5. 4E41 5.24E41 5.24E+81 5.N+41 3 1.E+02 9.74E41 6.75E+81 6.49E41 5.84E+61 5.84E41 5.84E+01 5.84E+01 5.24E+t1 5.84E+t1 5.84E41 26 1.75E42 9.37E+01 4.86E+31 4.86E41 4.86E+81 4.86E41 4.86E41 4.86E41 27 1.69E+82 9.82 41 6.2E+81 4.86E41 4.68E41 4.E+61 4.6EE41 4.68E+81 4.68E+01 4.68E41 28 1.62 42 8.7E41 6.23E+81 4.68E41 29
- 1.57E+t2 8.48E41 5.82+41 4.52 41 4.52 41 4.52 41 4.52 41 4.52+01 4.52 41 4.52+01 1.52+82 8.12 41 5.E+81 4.37E41 4.37E41 4.37E+81 4.37E41 4.37E+01 4.37E+81 4.32 41 33 5.45E41 4.23E41 4. 3E41 4.23E41 4.2X+01 4.22 41 4.2X+01 4.23E41 31 1.47E42 7.86E41 32 1.43 42 7.61E41 5.3E41 4.12E41 4.12E+31 4.12E41 4.!K+t1 4.1tE+41 4.1K41 4.12+41 1.30E42 1.38E+41 5.12+81 3.97E41 3.97E41 3.93 41 3.97E41 3.97E+01 3.97E41 3.93 41 33 4.97E41 3.86E41 3.66E41 3.86E41 3.86E41 186E41 3.86E41 3.86E41 34 1.34 42 7.16E+01 4.E 41 175E+01 3.75E+01 3.75E41 3.75E41 3.75E41 3.75E41 35 1.3E42 6.96Dt1 3.75E+01 6.76E41 4.69E+81 3.64E+01 3.64E41 3.bE+61 3.64E4' 3.pE41 3.64E41 164+01 36 1.2T+02 3.54E41 3.54E+01 3.54E41 3.54E41 3.54E+31 3.54E41 37 1.21 42 6.5E41 4.56E+61 3.54E41 6.41E41 4.44E41 3.45E+81 3.45E+41 3.45E41 3.45E+0! 3.45E41 3.45E41 3.45E+41 3 1.22E+02 624E41 4.3I 41 3.36E41 3.36E+41 3.36E41 3.36E41 3.36E 81 3.36E41 136E41 39 1.1A+42 4.22+41 3.28E41 3.NE+0! 3.3E41 3.3E+t1 3.3E41 3.:SE41 3.3E*01 48 1.14E42 6.89E41 41 1.1 E42 5.9eE41 4.12 41 3.22E41 12K41 3.:2E41 3.22E41 3.:2+01 3.2tE41 3.3E41 42 1.3BE+82 5.83E+31 = 4.8241 3.12 41 3.t:E+41 3.12+01 3.12+01 3.12+81 3.12 41 3.12 41 43 1.86E+t2 5.66E+d! 3.93E+01 3.5E+01 3.25E41 3.EE41 3.25E41 3.35E41 3.cE41 3.EE.81 44 1.24 42 5.5I+01 1 6E+01 2.98E+01 2.98E41 2.9E+81 2.98E41 2.98E41 2.99E41 2.98E+0!
L41E41 W+01 2.91E41 2.9 E41 2.91E+01 2.91E41 191E+81 2.91E41 2.9:E41 45 1.81E42 46 9.9tE41 L29E41 3.6TE+41 2.EE+01 2.EE+21 2.85E+0! 185E41 2.85E+61 2.EE41 2.85E41 3.59E41 2.79E+01 2.79E+01 2.79E41 2.79E41 L79E41 2.79E41 2.79E41 47 9.69E41 5.18E41 187E41 3.52+61 173E41 2.73E41 2.73E41 2.73E41 2.73E41 2.73E41 2.71 41 48 9.49E41 16E+t1 2.6E41 2.68E+41 2.E+81 2.6E+31 2.6E+81 2.6E+61 49 9.29E+41 4.97E41 3.45E41 58 9.11E41 4.87E+01 3.3E41 2.62+t1 2.62 41 2.62 41 2.62+01 2.E+0! 2.62 41 2.62+31 l, m ... 3
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HNP. 4852 Sea Tit 10 Pcga asio ,,o
- Georgia Power A -
See Title-Page 18 of 40
, . APPEl@IX A VERIFICATION TABLES ~
GFICATION TABLE 4 STA0( LEVEL lELEAE S*AIILITY CLASS 3 No FUM GAft0N MILLIEM/HR PER CLAIE/EC OF IODINE ILEt. EASED UPPER W!g 00n1ND DISTANCE FROM M PLMT SPID upm ' 1 MI 2 Mt 3 MI 4 MI 5 MI 6 MI 7 MI 8 Mt 9 MI 18 M!
!' 2.60E44 7.92 43 3.E+43 2.06E43 142+03 1.3:543 1.31E43 1.3:E43 1.31E43 1.31E43 2 1.34E44 3.9d43 1.81E43 1.02 43 7.OK42 L55E42 LSM42 L55E42 6.55E42 6.5 % 02 3 8.92 43 2. W 43 1.21E+83 6.87E42 4.72E42 4.34 42 4.37E42 4.3A+02 4.3X42 4.37E42 4 L69E43 1.9E43 9.07E42 5.15E42 3.54E42 3.:K42 3.:E+32 3.2E42 3.28L42 3.X42 5 5.35E43 1.59E43 7.25E42 4.12 42 2.8X+02 2.E42 2.62 42 2. E +t2 2.62E42 ' 2.62 42 4- 4.4d43. 1.32+43 6.84 42 3.E+02 2.3d42 2.1E42 2.!E42 2.!E42 2.18E*t2 2.1K42 7 3.82 43 1.1X+83 5.1E42 2.94E42 2.32+42 1.84 42 1.8A42 1.87E+02 1.87E42 1.87E42 8 3.34E+a3 9.91E42 4.52 42 2.57E+02 1.7K+02 1.64E42 1.64E42 1.64E42 1.64E+02 1.64E 82 9 197E43 8.81E42 4.E+02 2.29E42 - 1.57E42 1.46E42 1.4d42 1.46E42 I.46E42 1.46E42 18 2.68E43 7.92+02 3.E+82 2.ad42 1.42 42 1.31E42 1.3:E42 1.31E+C !.31E42 1.31E42 11 2.E 43 7.21E42 3.30E42 1.8X42 1.29E42 .1.19E42 1.19E42 1.19E42 1.19E42 1.15E41 12 2.23E43 061E42 3.32 42 1.72 42 1.tE+42 1.89E42 1.09E42 1.89E42 1.89E42 1.89E42
- 13 2.86E43 6.taE42 - 2.79E42 - 1.58E42 1.99E42 1.01E+02 1.t:E+82 1.5:E42 1.21542 1.B:E42 . -
14 1.91E43 5.6d42 2.59E+02 1.47E42 1.0:E42 9.3d41 9.3d41 9.36E41 9.EE41 9.3d41 15 1.7EG 3.29E42 2.42 42 1.3E+52 9.44E+01 8.74E41 8.74E41 8.74E+0! 8.7M41 8.74E41 16 1.63 43 4 95E42 2.27E+42 1.29E42 8.85E41 8.19E41 8.19E+01 8.19E41 8.19E*01 0.19E41 17 1.55 43 aE42 2.!I+02 ~ 1.21E42 8.31 41 7.71E41 7.71E41 7.71E41 7.71E+61 7.71E41 18 1.44 43 4.48E42 ' 2.21E+02 1.1E42 7.82 41 7.28E41 7.:8E41 7.2E41 7.:8E+41 7.28E41 19 1.41E+33 4.17E+02 1.91E42 1.08E42 7.45E41 6.90E41 6.9tE41 090E41 6.9EE41 6.90E41 28 1.34E43 3.96E12 1.81E+32 1.81+32 7.08E41 4.55E41 6.55E41 6.53E41 6.55E41 6.55E41 21 - 1.27E43 3.78E+82 1.73E42 9.81E41 - 074E41 6.24E41 6.2E+01 4.2E41 6.24E41 6.24E41 22 1.22 43 3.E42 1.65E42 9.36E41 LE41 5.96E41 5.96E41 5.96E41 5.96E+41 5.9d41 < 23 1.13 43 3.45E42 1.58E42 8.95E+01 6.1M41 5.7tE41 5.7E41 5.7BE41 5.78E41 5.7E41 24 1.!!E43 3.3EE42 1.51E42 8.58E41 5.90E41 5.46E41 5.46E41 5.46E41 5.4d41 5.4d41 25 1.87E43 3.1A+82 1.45E42 8.24E41 5.6d41 5.24+01 5.24E41 5.24E41 5.24E41 5.24E41 26 1.83E43 3.35E42 1.39E+82 7.92 41 5.44 41 5.84E41 5.84E41 5.f441 5.24E*01 5.84E41 27 9.91E42 2.94E+42 1.34E42 7.E 41 5.24E41 4.8d41 4.ESE41 - 4.86E41 4.86E41 4.86E41 28 9.56E+02 2.83E42 1.3EE42 7.ME41 5.8d41 4.68E41 4.6K41 4.68E41 4.68E41 4.68E41 29 9.23E42 172+82 1.25E+82 7.18E41 4.8E41 4.52+41 4.52+01 4.52 41 4.53 41 4.53 41 30 8.92 42 2.kE42 1.21E+t2 6.87E+01 4.7 E41 4.37E41 4.37E+d! 4.34 41 4.3E+01 L37E+01 31 8.E+32 ' 2.56E+02 1.1E+t2 6.64E+61 4.57E+41 4.22 41 4.23E41 4.22 41 4.2X+0! 4.23E41 32 8.36E42 148E*42 - 1.1X+02 6.44E+01 4.42 41 4.13E41 4.taE+41 4.12E*01 4.1E41 4.1E41 33 8.!!I42 2.4E42 1.1tE42 6.24E41 4.29E41 3.97E41 3.SM41 3.97E41 3.97E41 3.97E41 34 7.87E42 -2.33E42 1.34 42 6.8d+01 4.16E41 3.86E41 3.36E41 3.86E41 3.86E41 3.86E41 35 7.65E42 2.27,E+42 1.24E+02 5.88E+01 4.84E4! 3.75E+41 3.7M+81 3.75E41 3.75E41 3.75E41 36 7.E 42 2.:gE+02 1.21E42 5.72+01 3.93E41 3.64E41 3.ME41 3.64E41 3.64E41 3.64E41 37 7.2I 42 2.14E42 9.8tE41 5.57E41 3.E41 3.54E+01 3.54E41 3.54E41 3.54E41 3.54 41 3 7.04 42 2.89E42 9.54E41 5.42+0! 3.E+tl 3.45E41 3.45E41 3.45E+01 3.45E41 3.45E41 39 6.86E42 2.8I+R2 9.3tE+t1 5.28E41 3.E41 3.3d41 3.36E11 3.36E41 3.36E41 3.36E41 48 L69E42 1.98E42 9.tE+31 5.15E41 3.54E41 3.2E41 3.:8E41 3.28E+01 3.28E+01 3. E41 41 6.52 42 1.E*t2 8.EE4 5.2 E41 3.4!E41 3.::E41 3. 2E+et 3.:2 41 3.:tE41 3.20E41 42 6.37E42 1.89E+02 8.6:E+81 4.9EE41 3.37E41 3.12! 4 1 3.12+41 3.12 41 3.1 E41 3.12 41 43 6.22 42 1.84E42 8.E+t! 4.79E+91 3.29E41 3.EE41 3.25E41 3.2H41 3.EE+41 3.e5E41 44 6.aE42 1.8tE+02 8.24E41 4.68E+81 3.22 41 2.E+0! 198E41 2.98E+81 2.98E41 2.98E41 45 5.9M42 1.7d42 0.02 41 4.58E41 3.1M41 2.91E41 2.91E41 2.91E11 2.9;E+01 2.91E41 46 - 5.82 42 1.72+32 7.8E41 4.48E+41 3.8E+dt 2.85E41 2.85E41 2.EE41 2.85E+01 2.8M41 , 47 5.69E+t2 1.69E+02 7.72+41 4.38E+41 3.21E*01 2.79E41 2.79E41 2.'9E41 2.79E41 2.79E41 l 48 5.57E42 1.65E42 7.!d41 4.29E41 2.95E+0! 2.73E+41 2.E41 2.73E41 2.73E41 2.71 41 l 49 5.46E42 1.62 42 7.40E41 4.22E41 2.89E41 2.68E+41 2.E 41 2.68E41 2.6BE+91 2.6E41
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- 43 9.38E42 44 9.tKC 3.9M42 2.87E+02 1.27E+82 8.61E41 6.24 41 4.74E41 4.82 41 3.62 41 3.29E41
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1.98E42 1.2 E42 8.2X41 5.97E41 4.5X+01 3.84E41 3.46E41 3.15E41 44 477E42 3.7%+02 1.94E+82 1.19E42 8.86E41 5.84E41 4.44E41 3.76E41 3.39E41 3.tBE41 47 8.5E+02 3.71E+92 7.89E41 5.72 41 4.35E+01 3.6E41 3.31E41 3.82 41 48 8.4E42 3.64E+02 1.9tE+02 1.16E+t2 1.14E42 7.73Eatt 5.62E41 4.26E41 3.61E+t1 3.25E41 2.96E>t! 49 8.23E42 3.56E42 1.86E42 1.12+02 7.57E41 5.49E41 4.17E+0! 3.52 41 3.18E+t1 2.9tE41 58 8.87E42 3.49E42 1.82 42 m n w Em
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, APPOOIX A VERIFICATION TABLgg VERIFICAflM TAILE
$7A0( LEVEL RELEASE S'A!!L17V CLASS D N3 FL?IGAtt0N MILLIREM /HR PER Cut:E/SEC OF 10DI!GE ILE1. EASED UPPE9 W!1 DOWGiDC DISTANCE FACM THE FLANT sne um 1 Mt 2 MI 3 MI 4 R! 5 MI 6 M1 7 M! 8 PI 9 MI is MI
! 6.1E43 1.9:E44 1.BE44 1.61E+e4 1.zE+04 1.14 44 9.69E43 8.3n43 7.32 43 6. n43 2 - 3.09E43 9.55E43 9.42 43 8.84 43 6.N43 5.68E43 4.85E4J 4.1E43 3.66E43 3.2X+s3 3 Ltd43 6.37E43 6.2BE43 5.32 43 4.49E+t3 3.79543 3.23E43 2.79E43 2.44E43 2.12 43 4 1.5M43 4.7E43 4.7tt+33 4.82 43 3.37E+83 2.84E43 2.42+83 2.09E+83 1.83E43 1.62 43 5 1.N 43 3.82 43 3.7A43 3.22 43 2.69E+43 2.2'E43 1.94E+23 1.67E43 1.46E43 1.29E43 6 1.8X43 LIBE43 3.14983 2.68E43 2.25E43 1.89E43 1.62+83 1.48E43 1.22 43 1.29E43 7 8.8X+t2 2.E 43 2.69E43 2.3OE+t3 1.92 43 1.E+03 1.3E43 1.2K43 1.85E+43 9.N 42 8 7.7X42 2.39E43 2.35E43 2.81E43 1.68E43 1.42 43 1.21E43 1.tM43 9.!!E42 8.t3E42 9 6.84 42 Lt243 2.09E43 1.7E43 1.58E43 1.2M43 1. tee +23 9.3:E42 8.11 42 ?.19E42 18 6.!E42 1.91E43 1.9E+03 1.61E43 1.EE43 1.14E+t3 9.69E42 8.3N42 7.32E+22 6.4N42"
!! 5.62 42 1.74E43 1.71E43 1.46E43 1.22 43 1.E43 8.812+B2 7.61E42 6.66E42 5.22E42
- 12 5.12 42 1.59E+E3 1.57E43 1.34E+03 1.12E43 9.46L42 8.tE42 6.9E42 6.!E42 5.39E42 . -
13 4.76E42 1.44 43 1.4M43 1.2E+03 1.84 43 8.74E42 7.45E42 6.44E42 5.E+C 4.97t+02 14 4.42 42 1.3E43 1.35E43 1.15E+83 9.62 42 i.itt 82 6.92+82 5.9E42 5.2I 42 4.62'42 15 4.12 42 1.27E43 1.26E43 1.8M+83 8.98E42 7.57E+t2 6.4E+t2 5.5E42 4.88E+t2 4.31E42 16 3.8d42 1.19E43 1.18E43 1.81E+43 8.42 42 7.:E42 6.86E42 5.2X42 4.58E42 4.84 42 17 3.64E42 1.:2 43 1.!!E43 9.46E42 7.92+82 6.68E+22 5.78E42 4.93E42 4.31E+02 3.BE+s2 18 3.44E42 1.86E+t3 1.cE43 8.92 42 7.46E42 6.31E42 5.38E+e2 4.65E+32 4.87E+32 3.59E42 19 3.25E+C 1.t!E43 9.9:E42 8.46E42 7.29E42 5.93E+t2 5.ttE42 4.41E42 3.EE42 3.4E42 28 3.09E42 9.55E42 9.42 42 8.84E42 6.74 42 5.68E42 4.8M42 4.19E42 3.66E42 3.21 42 21 2.94E42 9.:E+42 8.97E42 7.66E42 6.42 42 5.41E42 4.61E42 199E42 3.4?E42 3.8E*S2 22 2.8:E42 8.68E42 8.56E42 7.31E42 6.12 42 5.16E42 4.41E42 3.8:E42 3.33E42 2.94E42 23 2.69E42 8.31E42 8.19E42 6.99E42 5.86E42 4.94E42 4.2:E42 3.64E+t2 118E42 2.8 E42 24 2.5SE42 7.96E42 7.EE42 6.72E42 5.6 E42 4.73E42 4.84E+82 3.49E*B2 3.5E+02 2.69E42 3 2.47E42 7.64E+82 7.53E42 6.43E42 5.39E42 4.54E42 3.82E42 3.3E42 2.E 42 2.59E42 26 2.35E42 7.35E42 7.24242 6.19E+32 5.18E42 4.37E42 3.73E42 3.22+t2 L32+t2 2.49E+s2 27 2.29E42 7.tBE42 6.9M+02 5.96E42 4.99E+t2 4.2:E42 3.59E42 3.:2E42 2.7tE42 2.4E42 29 2.2:142 6.82 42 6.E42 5.M+t2 4.8:E*t2 4.86E+22 3.4E+t2 2.99E42 2.61E42 2.31E42 29 2.13E42 6.59E+t2 6.49E42 5.!!E42 4.65E42 3.92 42 3.34E42 2.99E+02 2.52 42 2.21 42 38 2.tM42 6.TE42 6.2SE42 5.36E42 4.49E42 3.79E42 3.23E42 L79E+t2 2.44E+B2 2.16E+t2 31 1.99E42 6.!M42 6.EA+t2 5.19E42 4.EE*02 3.66E42 3.13E42 2.72E42 2.3d42 199E+42 32 1.93E42 5.94+82 5.E+42 5.22+82 4.21142 3.55E42 3.E42 2.62 42 2.29E+82 2.22 42 33 1.87E42 5.79E42 5.71E42 4.87E42 4.38E42 3.44E42 2.94E42 2.54E42 2.22 42 1.96E42 34 1.82 42 5.62 42 5.54E+t2 4.73E+C 3.96E42 3.34E+t2 2.85E42 L46E42 2.15E+C 1.9E42 35 1.77E42 5.46St2 5.38E42 4.62E42 3.25! 4 2 3.24E42 2.77E42 L39E42 2.2'E+t2 1.25E42 36 1.72 42 5.3:E42 5.23E42 4.47E42 3.N42 3.15E42 2.69E42 L33E+C 2. E 42 1.BE42 37 1.6M+22 5.16E+42 5.09E42 4.EE42 3.64E42 3.87E42 2.62 42 2.26E42 1.98E42 1.'5E42 38 1. E 42 5.E42 ~4.ME42 4.23E42 3.55E42 2.99E+02 2.!!E42 2.2tE42 1.93E42 1.7E42 ' 39 1.59E42- 4.9E+t2 4.E42 4.12 42 3.45E+82 2.91142 2.4E42 2.15E42 :.88E+t2 !.66E+02 l 48 !.55E42 4.72E+82 4.71E42 4.t242 3.37E42 2.84E+C 2.42 42 Lt'E42 1.82+02 1.62 42 , 41 1.51E 22 4.6d+42 4.59E42 3.92 42 3.29E42 2.77E42 L36E+82 LM42 1.79E42 1.5EE42 ( 42 1.44 42 4.55E42
- 4.48E+42 3.8X42 3.21E42 2.73E42 2.3:E+t2
- 1.99E42 1.74E42 1.N42 43 1.44E42 4.44E+02 4.3BE42 3.N 42 3.13 42 2.64E42 2.5E42 1.95E42 1.72E+t2 1.5E42 l
44 1.41E42 4.34E42 4.2E42 3.66E+82 3.86E42 2.5SE+t2 2.2E42 1.9E42 1.66E42 1.44 42 45 1.34 42 4. E42 4.tE42 3.57E42 2.99E+t2 2.52+t2 2.15E42 1.86E42 1.E42 1.44E42 , 46 1.34E42 4.1M42 4.89E+t2 3.58E42 LE+t2 2.47E 82 2.1tE42 1.82+82 1.59E42 1.41E42 l 47 1.32+82 4.83 42 4.81E+02 3.42 42 2.87E42 2.42 42 2.36E42 1.7E42 1.56E42 1.3E+42 l 48 1.29E42 3.98E42 3.92+42 3.ZE42 2.81142 2.37E42 2.t2+t2 1.74E42 1.5X42 1.DE42 l 49 1.2d42 3.9eE42 3.84E+42 3.29E42 2.75E+02 2.32 42 1.98E+82 1.7:E42 1.49E42 1.32 42 l 58 1.24E42 3.82 42 3.77E+t2 3.22 42 2.69E42 2.27E42 1.94E42 1.67E+82 1.46E42 f.29E42 _A . 4 %,WE $ l I tooeso *'
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. APPEICIX A VERIFICATICN TAl&gg S'A0( LEVEL RELEASE STAT *LITY C. ASS E No FtMISAT!0N PILLIEM/HR PER Cut!E/SEC OF 10 DIVE RE!. EASED l
LMA g:q DOWi!ND DISTANCE FROM TIE PLANT )
' 88EE: l gqpm - g pt 2 p1 3 M1 4 M1 5 MI 6 Mt 7 M1 8 Mt 9 EI 13 MI i 1.7E42 5.48E43 1.83E44 1.22 44 1.3 Di4 1.21E44 1.15E44 1.IBE+44 1.82 44 9.!!E43 2 8.m+01 2.74+83 5.16E43 6.99E43 6.3E+43 6.t'E43 5.77E43 5.G+23 5.8E43 4.7E43 3 5.92+41 1.51 43 3.44 43 4.06E43 4.17E43 4 EE+03 3.85E43 3.Q 43- 3.3"E43 3.17E43 4 4.44E+41 1.3'E43 2.*JE+03 3.35E+83 3.12 43 3.24E43 2.28E43 L71E43 2.54E43 2.3SE43 5- 3.5M*01 1.1E43 2.86E43 2.44E43 2.52 43 2.43E+03 2.3:E+33 2.17E+83 2.II43 1.9E43 6 2.96E+41 9.13E42 1.72+83 2.23E43 188Dt3 2.82 43 1.92+03 1.8:E+43 1.69E43 1.59E43 7 2.34E41 7.82+42 1.47E43 1.74E+03 1.79E+03 1.74 43 1.65E+81 1.55Dt3 1.45E43 1.36E43 8 2.22 41 6.64E42 1.29E+83 ' !.52 43 1.56E43 1.52 43 1.44E43 1.36E43 1.27E43 1.19E+03 9 1.97E41 6.tBE+82 1.15E43 1.35E+03 1.39E43 1.Z!+03 - 1.2E+83 1.21E+83 1.11 43 1.06E43 15 1.7E41 5.48E42 1.M+03 1.22E43 1.25E+03 1.21E+03 1.15E+03 1.IK43 1.82+83 9.51E42 It 1.6:E+01 . 4.9E42 9.38E42 1.11E43 1.14E43 1.1E43 1.85E43 9.8E42 9.24E42 8.6M42 12 t.4E41 4.56E42 8.59E42 1.82+03 1.84E43 1.8 D83 9.61E42 9.04E+02 8.4N+42 7.9I 42 ,
13 1.3'E41 4.2:E42 7.9I 42 9.37E+42 9.62 42 9.ZE+02 8.88E+02 8.35902 7.82 42 7.32 42 14 1.2H41 3.91D32 7.37E42 8.71E+02 8.H+02 8.68E+02 8.24E42 7.75E42 7.26E+82 6.80E+02
'S 1.1E11 3.65E42 6.88E42 8.12+82 8.34E42 8.1K42 7.69E42 7.22 42 6.78E+02 6.34E+02 16 1.11E41 3.E42 6.4M42 7.62E42 7.8 E42 7.59E42 7.21E42 6.78E42 6.35E+02 5.9M42
.17 ' !.94E41 3.22E42 6.87E42 7.17E42 7.35E+42 7.15E42 6.79E42 6.3E+t2 5.98E42 5.68E42 18 9.86E4B 3.84E42 5.73E42 6.77E42 6.95E42 6.7M42 6.41E+02 6.22 42 5.E 42 5.29E42 19 9.3M4 2.88E42 5.G42 6.4tE42 6.5E42 6.39F+02 6.17E42 5.71E42 5.35E42 5.t E+82 28 8.88E+0B 2.74E42 5.16E+42 6.89E42 ' 6.2E+42 6.37Dt2 5.77E42 5.E42 5.8E42 4.7E42 21 8.45E4I 2.61142 4.9:D82 5.SIDt2 5.95E42 5.79E42 5.49E42 3.17E42 4.64E42 4.5E+02 22 8.37E*N 2.49E42 4.M+02 5.54E42 5.68E42 5.52+82 3.2*E42 4.93E42 4.62+02 4.32E42 23 7.72 4I 2.3E42 4.48E42 - 5.30E+02 5.44E42 5.28E42 5.92 42 4.72 42 4.42 42 4.14E42 24 7.40E4 2.28E+82 4.JE42 5.8E42 ' 5.21E+42 5.8d42 4.81E42 4.12 42 4.2I 42 3.9d42 3 7.laE4 2.19E+82 4.1X+02 4.83 42 5.NE42 4.86E42 4.62 42 4.34E42 4.87E42 3.81E42 26 6.81 4 2.11E+02 3.97DB2 4.69E42 4.81E+02 4.67E+42 4.44E42 4.17E42 3.91E42 3.66E42 27 6.58E40 2.82 42 3.82+42 4.51E+82 4.E+32 4.52E42 4.2M42 4.82+22 3.76E42 3.52 42 28 6.3d+4B 1.96E42 3.6E+02 4.35E42 4.47E+42 4.34E42 4.12 42 3.87E42 3.E+02 3.43E42 29 6.13 4 1.89E42 3.56E42 4.2E+42 4.3:E+t2 4.19E42 3.98E+t2 3.74E+02 3.58E+82 3.2E42 .
l 38 5.92 40 1.S'Dt2 3.44E+02 4.06E42 4.17E42 4.25E42 3.35E+82 3.3 42 3.39E+02 3. 7E42 ! - 31 5.73E4 1.77E+t2 3.3X+02 3.E42 4.83E42 3.92 42 3.72 42 3.!K42 3.28E+t2 187E+02 32 5.!!E48 1.71E42 3.22+02 3.81E42 3.91E42 3.62E42 3.61E+32 3.3% 42 3.18E42 2.97E42 l 33 5.3aE+20 1.66E42 3.13Dt2 3.69E42 3.79E+I2 3.68E42 3.!2 42 3.29E42 3.2BE+t2 2.8aE42 ! 34 5.22 % 1.6:E42 3.83Z42 3.*8E42 3.68E42 3.57E42 3.399t2 3.19E42 2.992+02 2.8E42 (~ 35 5.87E+0B 1.56E.+32 2.95D42 3.48E+42 3.57E42 3.47E42 3.32E42 3.!E42 L9E42 2.72E+02 i 36 ' 4.9I+00 1.52 42 2.86E42 3.39E42 3.47Z42 3.3'E42 3.22 42 3.t:E42 2.22 42 2.64E42 l 37 4.8BE48 1.48E+82 2.79E+02 3.29E42 3.38E42 3.28E+82 3.12 42 2.93E42 2.75E42 2.57142 !- 38 4.61DGI 1.44E+t2 2.71E42 3.21E42 3.29DB2 3.23E42 3.84E42 LEE 42 2.6N+42 15E42 [ 39 4.55E+30 1.40E42 2.64E42 3.12 42 3.21E42 3.12 42 19d42 L7E42 2.61E42 2.44E42 l 44 4.44E4 1.37E42 LSE42 3.EE42 3.11 42 3.04E42 2.EEE42 2.7:E42 2.36E42 2.:8E42 41 4.33E49 1.34E42 2.52 42 197E42 3.t!!+t2 196E42 2.SIE+t2 2.65E42 2.48E42 2.32E42 i 42 4.21 4 1.3E42 . 2.46E42 2.9EE42 19K42 2.89E42 2.75E+82 2.58E+02 2.M 42 2.27E42 l 43 4.13E4B 1.27E42 2.40E+02 2.83E42 2.9 E42 2.83E42 2.68E42 2.52 42 2.36E+82 2.2iE42 to 4.8I 48 1.24D42 2.34 42 2.77E42 2.84 42 2.7M42 2.62+82 2.47E42 2.3:E42 2.16E42 l 45 3.95E4 1.22 42 2.29E42 2.71E42 2.78E42 2.78E42 2.56D82 2.41E42 2.26E42 2.!!E+02 l 46 3.8d48 1.19E42 2.2d+02 2.65E42 2.72 42 2.64E42 2.51E42 2.36E+02 2.21E42 2.14 42 47 3.7E+50 1.1E42 2.19E42 2.59E42 2.66E42 2.59E+t2 2.45E42 2.3:E42 2.16E42 2.82 42 i 48 3.78E*00 1.14E42 2.15E+02 2.54E42 2.64Dt2 2.53E42 2.4E+42 2.26E+02 2.12 42 1.98E42 l 49 3.62D00 1.12+32 L!E+t2 2.49E+02 2.5M42 2.48E42 2.35E42 2.2:E42 2.87E42 1.94E42
*8 3.!!D05 1.1E42 2.86E42 2.44Dt2 2.*JE+02 2.42 42 2.31E+02 2.t?E+32 2.82+32 1.9E42 I
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. APPEPOIX A VERIFICATI@l TABLES m: car:a EE
$7ACK LEWL PELEASE STA8!L!7Y CLASS F NO FWIGM10N MILL!EM/HR PER CUR!E/SEC OF 10 DINE REI. EASED DOINd!ND DI$fANZ FROM TE PLANT SPSD wm : Mt 2 MI 3 MI e n! 5 MI 6 RI 7 MI B PI 9 M! is Mt t 8.3 3 -83 6.7E41 5.88E42
- 4M43
. 2.37E43 3.14E43 3.74E43 4.19D83 4.53 43 4.75E43 2 4.1d-83 3.35E41 2.94E42 7.34 82 1.19E43 1.54 43 1.87E43 2.tE 83 2.2d43 2.38E43 3 2.77143 2.:I+41 1.96D42 4.89E42 7.90E42 1.85E43 1.3E43 1.4aE43 1.51E B3 1.58D43 4 2.08E-23 1.67E41 1.47E42 167E42 5.9I 42 7.85E42 9.3d42 1.EE43 1.1X43 1.19E43 5 1.66E-82 1.34 41 1.1E42 2.94E42 4.74E42 6.2E42 7.49E42 8.39E42 9.25E42 9.51E+82 6 1.391-93 !.13 41 9.80E41 2.45E42 195D32 5.21 42 6.24E+02 6.99E42 7.54E42 7.93+02 7 ~ 1.19E-83 9.57Dt3 8.4E41 2.!!E+02 3.39E42 4.49E42 5.35E42 5.99Dt2 6.46E42 6.79E42 8 1.04E43 8.3H48 7.35E41 1.84Dt2 2.92 42 3.93 42 4.68E+t2 9.04E42 5.65E+t2 5.94E+02 9' 9.24E44 7.44E43 6.53E41 1.6X42 2.E+32 3.49E42 4.!6E42 4.66Dt2 5.81 42 5.2SE42' II B.3344 6.7E48 1.88E41 1.4E42 2.3H42 3.14E42 3.74E42 4.19E42 4.53 42 4.ME42 '
11 7.56144 6.t9148 5.34E41 1.31 42 2.16E 82 2.ME42 3.42E+42 3.8:E42 4.11E42 4.33 42 .
- 1 12 6.92 44 5.3SE45 4.9tE41 1.23 42 1.98E42 2.63 42 3.13 42 3.5E42 177E42 3.96Dt2 13 6.42E44 5.15Dee 4.33 41 1.11 42 1.83 42 2.42E42 2.88E42 3.2X+t2 3.48E42 3.6d482 14 5.94 44 4.72E40 - 4.22D2' l.05E42 1.E42 2.24E42 2.67E+02 3.2tE+82 12X+02 3.4aE+82 15 5.55!-t4 4.44 80 3.92E41 9.79E41 1.50E42 2.t9542 2.!aE42 2.8tE42 3.83 42 3.17E+42 16 5.22E44 4.19E4e 3.6M41 9.18E41 1.48E+t2 1.96D42 L34E42 2.63+42 2.83E42 2.97E42 17 4.89E-34 3.94E4e 3.4d+0! 8.64E*01 1.39E E2 1.95E42 2.22E+02 2.47E+t2 2.66E42 2.8E42 10 4.63 44 3.73 48 3.27E41 8.16E41 1.33 42 1.74D82 2.88E42 2.3X+02 2.5:E42 2.64E42 19 4.3E44 3.51 40 3.99E41 7.71 41 1.25E42 !.65D82 1.97E42 2.21142 2.3BE+02 2.5E+82 28 4.16E44 3.35E+40 2.96E41 7.34 41 1.19E+82 1.57E42 1.87E42 2. tee 42 2.2d42 2.38Dt2 21 3.96E-24 3.19E+Is 2.8E+0! 6.99E41 1.E+22 1.5K42 1.7E42 2.CaE42 2.15E42 2.2d42 22 3.7EE-44 3.84+90 2.6N41 6.67E41 1.38E42 1.43E 42 1.7E42 1.91E*02 2.8d+F2 2.16E42 23 3.6 3 -84 2.91E+te L56E41 6.38E41 !.fjDt2 1.34 42 1.E 82 1.83 42 1.97E+t2 2.8M+42 24 3.47E44 2.79D98 2.45E41 6.13 41 9.82E41 1.3:E+t2 1.56E42 1.75E42 1.8EE*02 1.98E42 25 3.3 I -84 2.E40 2.35E41 5.87E41 9.49E41 1.2d42 1.5aE+t2 1.69E42 1.81DB2 1.9E42 26 3.:tE44 L58E48 2.26E41 5.E41 9.13+0! 1.2:Dt2 1.44E42 1.61E42 1.74E42 !.8X42 27 3.88E44 2.46E+00 LIE 41 5.44E41 8.71 41 1.16E42 1.39E42 1.35E42 1.68E42 1.7d42 28 2.97E44 2.J'E4e L!E+01 5.24E41 8.44 41 1.13 42 1.34E42 1.52Dt2 1.63 42 1.7aE42 29 187E44 2.3:E40 2.83E41 5.86E41 8.18E41 1.8BE42 1.29142 1.45D32 1.56E+42 1.64E42 38 2.77E44 2.22 40 1.96E41 4.89E41 7.9tE41 1.cE42 1.25E42 1.40E42 1.51D82 1.5E*42 31 2.6et-04 2.1d48 1.9E41 4.74E+0! 7.65E41 1.21E42 1.2:142 1.35E42 1.46E42 1.52 42 32 2.6E44 L 2*E+08 1.84E41 4.59E41 7.41D81 9.81E41 1.1E42 1.3 E42 1.4tE+42 1.49Dt2 33 - 2.53 44 2.81 00 1.78E41 4.45E41 7.19E41 9.53 41 1.iK+82 1. 'E42 1.37E42 1.44Dt2 34 2.45E44 1.97Det 1.73D81 4.33 41 6.97E41 9.24E4: 1.1t!42 1.21 42 1.33E42 1.4K+t2 35 . L38E44 1.9:Dat 1.65Dt1 4.23 41 6.MDt1 8.97Dt! !.27E+a2 1.22!+t2 1.29E+02 1.3d42 36 2.311-84 1.Ed+4B t.E+81 4.29E41 6.59E41 8.7:E41 1.84E42 1.13 42 1.:6Dt2 1.33 42 37 2.3E44 1.E1DE8 1.59E41 3.97E41 6.41E41 8.49E41 1.t:E42 1.11 42 1.23 42 1.29E42 38 2.19544 - 1.76 Des 1.53E41 3.82 41 6.24E41 8.26E41 9.E5E41 1.;tE42 1.19E42 1.:5E42 39 2.E44 !.73 48 1.51E41 3.77E41 6.23E41 8.c5E41 9.6E41 1.28E42 1.16E+82 1.23 42 48 2.tX44 1.63 40 1.47E+41 3.67E+81 5.93D81 7.85D31 9.36E+41 1.EDt2 1.12E42 1.19E+42 41 2.8 2 -04 1.E48
- 1.E+41 3.58E41 5.71 41 7.66E4: 9.12 41 1.23 42 1.18E42 1.td+t2 42 1.99544 1.59E+40 1.4E41 3.5tE41 5.65D41 7.4EE41 8.9tE41 9.ME*01 1.98E42 1.11 42 43 1.93E44 1.3d45 1.34 41 3.41E41 5.51E41 7.3K41 3.7K+21 9.75E41 1.eE+t2 1.11E42 44 !.89E-44 1.53+at 1.34E41 3.34E41 5.39D01 7.14 41 0.51E41 9.53E41 1.81 42 1.8EE42 45 1.85E44 1.49E+4e 1.3:E+41 3.2d41 5.27E+31 6.9eE41 8.33 41 9.33 41 1.3:E+22 1.3d42 46 1.t:E44 1.46D88 1.NE+0! L19E41 5.15E41 6.83 41 s.14E41 9.13 41 9.83E+31 1.tI+42 47 1.77E44 1.E*28 1.25E41 3.13 41 5.cE41 6.68E41 7.96E41 8.92E+61 9.63 41 !.IIE42 48 1.7 1 -24 1.42E48 1.23 41 3.26E41 4.94E41 4.54E*81 7.80E41 8.74E41 9.43+91 9.9E+0!
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. APPOOIX A VERIFICATION TABLES vent::AtI:s tar.I .
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! NO FWl'aATICN Y. M1.:.!Ewel MR cts:Zi3IC 0F N0LE GES E;.EA3E3 W E3 .
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'6 ' t.9241 1.EE-31 7.3E42 5.64E42 5.64E t 5.14E42 5.N42 5.64E42 5.6042 5.M-42 7 1.E41 8.9EE-C2 6 ZE-22 4.83E-E2 4.5 2 -22 4. 5 12 ~4 EE-82 4.E-22 4.E-T2 4.8K-t2 8 1.47E C 7.2E42 5.45142 4.2I 42 4.2142 4.21 42 4.21 42 4.2I 42 4.2X42 4.:1-E 9 1.2;E 31 L9E42 4.f.E-22 3.7tE-22 3.?n-22 3.7&I 22 3.7E-:2 3.7dC 3.7d42 3.76E-22 18 1.;3E41 6.2E42 4.3E-U 3.IE42 3.3E42 3.3E-22 3.3E42 3.2E42 3.3E{ 3.73E42 *
!! t,:7E41 5.7:E42 2.9:E-t2 3.t7E-c LI7E42 3.1;'E42 18A-t2 3.37E-32 3.FEC 3.27E-32 -
12 9.7:142 5.:4E42 3.63* 4 2 2.8242 2.8"I42 2.8 2 -32 2.EZ42 2.2 3 -12 2.I2 42 2.22 42 13 9.34E42 4.51-t2 3.35E-t2 2.6E42 2.63E-32 2.63E42 2.63EC 2.eE42 :.61 42 2.6ti-t2 14 3.FE42 4.411-32 3.11E42 2.42 42 2. c 42 2.4:242 2.43 42 2. c 42 2.43 42 2. d 42 15 L EI-22 4.19Z-22 2.92 4 2.ZE-22 2.5E-82 2. 2 1-22 2.SE42 2. 2 5-22 2. 2 2-21 2.2EC 16 7.3.E42 3.71 42 2.7 2 -22 2.ILE42 2.1tE42 2.1IZ42 2.I!!42 2.1II42 2.11E-32 L11E42 6.9;E42 17E-22 2.hE42 1.9'E-22 1.99E-E 1.9022 1.99E-32 1.9EE-:2 1.9CE C 1.9eE42 17 6.5E42 3.4*E-22 2. E 42 6.tE-42 1.82E-22 1.SE42 1.53E42 1.BE42 1.8EI42 1.EE42 19 19 L !ic 3.3;I-22 L2?E-t2 !.7EE-E t.7EI-21 1.7E42 1.7EE42 1.7EI 22 1.*I{ !.'IEC
~3 5.EE-32 3.14E-M 2.15-32 1.6'E-C t.6 5 2 1.45t2 1.tM-32 1.6E42 1.6?t C 1.69E42 3.12-2 2.95E-C 2.t?!-C :.61E 22 1.6:E-U !.61E-C 1.t'.142 1.61E-32 1.t:EC 1.6tF42 3.35E-32 2.I!C t.fiE-E 1.54E W l.542-C 1.54E- 1.54E42 1.54E-32 1.54I-32 1.:.E4 1.47E-22 1.4?E-32 1.47142 1.47E42 23 5.ut-E L7 E42 1.ETE-U t.47E-E 1.47E-32 1.47E-32 26 4.WI 12 2.62C 1.92E42 1.41E42 1.41I 4 2 1.4tE42 1.41E-32 1.4tE4) 1.4t!42 1.4*E42 25 4.7 5 -22 2.1;E42 1.M42 1.ZE-:2 1.ZE-22 1.ZE4 1.ZE-t2 1.ZE-22 1.2:I-C 1.2I42 3 4.5242 2.42 42 8.63E42 1.38E-82 1.38Z42 1.3E42 1.2E42 1.3tE42 1.33E { 1.2X42
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See Title Page 29 of 40 APPEFOIX_A, VERIFICAT1gN TABLES VERIFICA7!ON 7AILE WMD LE'4L ELEASE
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- dLPPgtGIX A VERIFICATION TABLES VEUt:A717; 743.E EWC LET. 9ELIASE
$*43:Lt?Y CLASS 3 M:LLIEm2 PER Cllt:Elg: OF IODINE ILE!. EASED
*NES ute DOW6i!!Q 5:574hG FRA M PLAN 7
$ PEE 3 4 "! SM 6M 7M 8 "I 9M 18 M UN IM 2M 3M 1.nE44 8.93 43 7.7E43 f 4.t!!44 2.76E*t4 2.23 44 1.17E44 1.27E44 1 6.'5E44 4.4d43 3.2143 2 f 72145 46E44 3.67E44 2.ts+M !.34 44 1.3;E*34 7.EE+13 6.33 43 5.:6E43 6.71 43 5.:X+83 4.0143 3.5 E43 2.97E43 L5?E (3 3 5.6d44 2.33 4 1.EE+44 9.11 43 4 4.N+M 1.76Em 1.8:ES 6.EE43 5.25E43 3.92 43 3.17E+l3 L E 43 2.21 43 1.93 43 5 3.5d* !.4X* 8.:9E43 5.!K43 4.tE43 3.18E43 :.52 43 2.tX43 1.8E43 1.!M43 6 3.22E M 1.3E44 7.16E43 4.7EE43 3.49E43 2.72E43 2.17E43 1.8tE43 1.5243 1.3:E43 7 2.93
- 1.11144 6.29E43 4.19E43 3.EE+C3 2.ZE43 :.99E43 1.56E43
- 33 43
. 1.11 43 8 2.72E44 1.8144 !.E43 3.73I 4 3 2.71E43 :.EE+23 1.64 43 1.2E43 1.16E43 1.tE43 9 2.!!E* 9.:K43 5.12143 3.3d+t3 2.43E43 1.87+23 1.12I 23 1.N+23 1.:4E43 8.95E42 2.34E4 8.44E43 4. 4+H 3.26E43 2.2:143 1.73 43 :.36E43 1.13 43 9.4*E42 E.18E42 18
!! 2.':ES 7.82 43 4.29E43 2.8:E+tJ LG43 1.15143 1.M43 1.33C 8.G42 7.4t142 12 2.86E44 7.:9E+0 3.9EE43 2.6tE43 1.84 43 1.43E43 1.14E43 9.E42 7.96E t2 6.8:E42 13 1.9E*M 6.75E+83 3.69E43 2.4:E43 1.74E+U t.33E43 1.26E43 0.73E42 7.35E+82 6.3:E+02.
14 1.77E44 6.27E43 3.4;EC LN43 1.6tE43 1.E43 9.EEC 8.llE+C 6.33E+t2 5.8d42 * . 15 1.6:E+44 5.EE43 3. E43 2.39E-U !.5:143 1.11! 4 3 9. tE+t2 7.5N42 6.34C 5.4'E+t2 16 1.!!E+M 5.48E43 3.25 43 1.96E43 1.4 E43 1.t2E43 8.GC 7.M42 5.97EC 5.13 42 17 1.46E+34 5.16E43 - 2.22 43 1.S!E+23 1.32 43 !.C143 8.1 E42 4.E42 5.c42 4.33 42 1.38E44 4.83 43 L67E43 1.74E43 1.M 43 9.EC 7.66EC 6.3:E42 5.3;E42 4.!!E+82 18 19 1.3E+44 4.G43 L5X43 1.65! 4 3 1.19E43 9.;EI42 7.24E42 5.97E+82 5.E42 4.33+02 23 1.N* 4.39E*23 2.42143 1.5443 1.12 43 8.6+E42 6.93E42 5.E+82 4.7E42 4.lE42 21 1.155
- 4.18E43 2.'9E43 1.49E43 1.28E43 E.E42 6.5'EC 5.4aE42 4.55E42 3.9eE42 22 1.1I 44 3.99E+t3 - 2.12! 4 3 1.42 43 !.t3E43 7.S6E42 6.27E+22 S.12 42 4.34EC 3.73E 82 23 1.23E44 3.8;E 83 2.29E43 1.3d43 9.83 82 7.53 42 6.22542 4.93E42 4.16E42 3.5d42
- 4 1.G44 3.6d+23 2.22 43 1.3;E43 9.4:E42 7. 2EC !.7!E42 4.E+32 3.9SE42 3.45+t2 3 9.9tE+83 3.51143 1.93 43 1.26E43 9.84EC 6.92 42 5.53 42 4.54E42 3.82 42 3.:SE+02 26 9.13 43 3.34 43 1.85E43 1.::E43 8.69E42 6.6!EC 5.3:142 4.37! 4 2 3.68EC 3.t*E42 27 9.lH43 3.3E+33 1.?EE43 1.16E43 8.37EC 6.EC 5.1:142 4.2tEC 3.5442 3.t*E42 28 8.84E43 3. X43 1.7:E43 1.13 43 f.t?E42 6.:7E42 4.E42 4.t'E42 3.4tE42 :.E 42 29 8.54E43 3.E 43 1.66E43 1.t3E43 7.79E+22 5.96E42 4.7d42 3.9:EC 3.32E42 2.E42 32 8.3E43 2.92 43 1.62E43 1.EE*03 7.!EC !.76E42 4.6 +22 3.79E42 3.19E+t2 L72 82 31 7.92E43 2.81 43 1.5!!43 1.B:E43 7.29E42 * .*SE+22 4.45E+C 3.66E42 3.t E42 L64E+42 32 7.74E43 2.74E43 1. E43 9.8;E42 7.2d+22 !.E42 4.3:142 3.15I 4 2 :.99 42 2.52 42 l
33 7.55 43 2.66E43 :.45E43 9.3:E42 6.85E+22 !.NC 4. EE42 3.44E42 L92EC 2.48E42 l 34 7. EE*t3 2.33E43 1.4:E43 9,23I 4 2 6.64+22 5. tdt 2 4.2dC 3.34E+22 2.8:142 2. 4 E+t2 l l 35 7.t343 2.!:143 1.33 43 8.9EC 6.45EC 4.94E+22 3.94E42 3.26E42 2.E42 LN42 36 6.88E43 L9E+83 1.32 43 8.72 22 6.08E42 4.CE+t2 3.EC 3.15EC 2.66E42 '.E42 37 6.69E43 2.33 43 1.2E43 8.E 42 4.!!!+22 4.64 42 3.E 42 3.ZN42 2.!!E42 L:242 38 6.5:143 2.3:143 1.26E+43 8.26E42 5.95E42 4.!!E42 3.E 42 L9'E+22 2.5242 L t6E+t2 39 6.31E43 2.3I43 !.'I43 8.t*!42 5.79EC 4.43EC 3.54E42 :.9tE42 2.45E42 2.:K42 l 2.19E43 1.:2E43 7.34EC 5.65EC 4.33+t2 3.4 E42 2.94E42 2.39E+22 2.25E42 44 6.19E43 l 41 6.t4E43 2.14143 !.:7E43 7.61542 5.5:142 4. IC 3.36E42 L7342 2.32 42 2.M 42 42 5.69E43 2,t'E43 1.14E43 7.47E42 !.3SE42 4.13C 3.23E42 2.E+22 2.29E+t2 1.95E42 2.24E*83 . 1.13+23 7.32E42 5.3 C 4.22 42 3.::EC L64E*C 2.:2 42 :.9:E42 ! 43 5 76143 l 44 5.E43 1.99E43 1.8'E43 7.1E+22 5.E42 3.9:I42 3.14EC LSSE42 2.17E+22 1.86E+02 45 5.!E+t3 1.9"E+43 1.83 43 6.97E42 5.22 42 3.64EC 3.25 42 L5242 .2.12 42 1.82 42 46 5.39E43 1.9tE43 :.8+E43 6.82 42 4.91E42 3.76142 3.:2E42 L47E42 2.3EE42 !.7E42 1.83 43 1.22 83 6.6SEC 4.8;E42 3.6SE42 L94E+32 2.4:542 2.E+82 !.N42 47 5.2A43 48 5.M+03 1.E+03 1.22E43 6.54E42 4.7tEC 3.63E42 L87E42 2.36E+82 1.99E42 1.7142 49 !.22 43 1.79E+03 9.8tE 82 6.4tE42 4.611 4 ? 3.53E42 LS342 2.32 42 1.95E42 1.G42 4.95E43 1.72 43 9.65 42 6.3E+42 4.52 42 3.46E42 2.76E+42 2.27E42 1.91E42 1.64E+02 58 l t
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See Title Page 33 of 40 APPDOIX A YgRIFICATION TABLES vet:7!CA710N 7AILE 90VND LEVEL RELEAE S'AILI7V CLASS E P!LLIleMt PER CLA!E/SEC OF TODINE RE1.dASED wet W4 D0lms:N3 D!$7ANCE FACM M PLAN 7 8'EE2 (MPH) 1 P: 2 MI 3 MI 4 MI $ M1 6 MI 7 ft! I P! ' M1 1t M!
! 2.5eE* 1.21E45 7.69E44 5.5I* 4.2d44 3.G* 2.9d44 2.44 44 2.11E44 1.8d*
2 1.M45 6.84 4 3.95E44 2.7d44 2.11 4 1.72 44 1.E44 1.22 44 1.06E* 9.3E43 3 8.We 4.E!* 2.56E44 1.bE 04 1.G44 1.14E44 9.51 43 8.13 43 7.94E43 6. E+43 4 6.48E* 3.81 44 1.93 44 1.3E44 1.0d44 8.!E43 7.14E43 6.t9E43 5.28E+43 4.4SE43 5 5.64 4 2.58E44 1.61E44 1.1H* 8.79E43 7.82 43 5.8d43 4.9K43 4.31E43 3.79E43 6 5.3E44 2.2E4 1.44
- 1.I!E+84 7.68E43 6.11 43 5.8d43 4.29E43 178E43 3.5E43 7 5.14E4 2.!d44 1.38E44 9.G43 6.82 43 5.c43 4.4d43 3.7d+03 3.24E43 2.84 43 8 4.92 4 2.8E4 1.:8E44 8.17E43 6.2 43 4.EE43 3.99E+23 3.2143 2.BBE43 L5343 9 4.71E44 1.Bd* t.89E44 7.45E43 5.54 43 4.39E43 3.dE43 3.83 43 2.68E+43 2.27E43 18 4.53E4 1.M44 1.gES 6.81 43 5.IIE+83 4.t:E43 3.29E+t3 2.75E43 2.36E43 2.8d43
- L5243 2.tM43 1.8483
- 11 4.2144 1.E44 9.35E43 6.M+43 4.7eE43 3.69E43 3.3:E43 12 4.8+E44 1.51 44 B.74E43 5.9tE43 4.34 43 3.42 43 2.79E+43 LM43 2.829 83 1.74E+43 . .
13 171
- 1.41ES 8.IE43 5.4M43 4.85E43 3.1H 83 2.5E43 2.17E+83 1.85E43 1.61E43 14 3.46E* 1.31E44 7.51E43 5.8eE+03 3.7d43 2.95E43 2.4E43 2.81E43 1.72 43 1.52E43 15 3.21 4 1. 3 44 7.81E+43 4.N43 3.5tE43 2.75143 2.24E43 1.88E+83 1.61E43 1.4E43 16 3.H 44 1.m* 6.57E43 4.44E43 3.29E43 2.2E+03 2.1E43 1.4E43 1.51E43 1.3*E43 17 2.85E4 1.seE44 6.1E43 4.1E43 3.!K+33 2.G+83 1.93E+83 1.6d43 1.42 43 1.22 43 18 2.69E* 1.82 44 5.94+43 3.95E43 L9243 2.:9E43 1.84 43 1.56E43 1.34E43 1.17E43 19 2.5M44 9.64 43 5.52 43 3.M43 2.77E43 2.14 43 1.77E43 1.49E+03 1.27E43 1.1E43 28 2.G44 9.19E43 5.:d43 3.55E+03 2.E43 2.3d43 1.6M43 1.41E43 1.2tE43 1.lii43 21 2.3:E4 8.72 43 5.IIE43 3.3SE43 2.51E43 1.96E43 1.6E43 1.M43 1.15E43 18.30E42 22 2.:IE44 8.3H43 4.7E+03 3.21 43 2.39E43 1.8'E43 1.5X43 1.29E43 1.tBE43 9.54 42 23 2.11E44 7.99E43 4.5H43 3.89E+83 2.29E43 1.79E43 1.4d43 1.22 43 1.25E43 9.3 42 24 LCES 7.65E43 4.38E+03 2.96E43 2.19E43 1.72 43 1.42E43 1.!?E43 1.80E43 8.75E42 3 1.94+04 7.3M43 4. tE43 2.PE+43 L11E43 1.65E+33 f.3443 1. 2 43 9.64E+02 8.48E42 26 1.83 44 7.I3 43 4.kE+83 2.73E43 2.83 43 1.59E43 1.29E43 1.23E43 947E42 8.3442 27 1.8tE* 6.88E43 3.89E+83 2.E 43 1.15E43 1.52 43 1.N43 1.24 43 8.93E42 7.7E42 25 1.71 44 6.54 43 3.75E43 2.54E43 1.8E43 1.47E43 t.::E43 1.2;t43 8.6tE42 7.5tE42 29 1.67E+H 6.33E43 3.G+83 2.45E+83 1.81E+t3 !.4:E+t3 1.16E43 9.7;E42 8.3 E42 7.24E42 38 1.6244 6.12 43 3.5E43 2.3A+43 1.75E43 I.3A43 1.!3 43 9.39E+02 8.34E42 7.ttE42 3: 1.3d44 5.E43 3.39E43 2.29E43 1.78E43 1.33 43 1.tSE43 9.t9E42 7.79542 6.77E42 32 1.52 44 5.M43 3.25E+43 2.:E43 1.64E+33 1. 9E43 1.t'E43 8.8:E+42 7.51 42 6.5d4:
33 1.44 44 5.57E43 3.1E+t3 2.15E43 1.59E43 1.3E43 1.t243 8.53E42 7.31E+t2 6.3d42 34 1.G44 5. 4 43 3.89E43 2.t?E43 1.52 43 1.: E43 9.SSt+82 9. !E42 7.t9E42 6.17E42 35 1.39E44 5.3!43 3.IIE43 2.83E43 1.!E43 1.19E43 9.64E+t2 8.t3E42 6.39E+82 6.IIE42 36 !.ZE44 5.13E43 2.92 43 1.97E43 1.46E43 1.15E43 9.33E42 7.82 42 6.7E42 5.8I 42 37 1.31ES 4.97E43 2.84+83 1.92 43 1.G4' l.11E43 9.tSE+82 7.61E42 6.53 42 5.6M42 38 1.:EE44 4.81 43 2.77E43 1.844Q t.39E+t3 1.t9E43 8.84E42 7.41E42 6.34E42 5.52 42 39 1.N* ~ 4.7tE43 2.69E43 1.82+03 1.ZE43 1.td+43 8.62 42 7.22 42 6.19E42 5.3EE42 44 1.21ES 4.59E43 2.E43 1.72E*83 1.32 43 1.E+83 8.42 42 7.84 42 6.33E+42 5.3E*t2 41 1.1E44 4.4K43 ,2.56E43 1.7X43 1 :E43 1.t:E43 8.:E42 6.87E42 5.8E+22 5.12 42 42 1.15E44 4.3A43 .52E43 t.6'E43 1.5E43 9.82 42 8.t242 6.7tE+42 5.74E+42 5.8E42 43 1. 2 44 4.24+83 2.44E43 1.65E43 1.rE43 9.59E+32 7.8;t42 6.55E42 5.61E42 4.8BE42 44 1.!OE44 4.1E43 L39E43 1.62+03 1. tE43 9.3'E42 7.64E42 6.48E+02 5.48E42 4.77E42 45 1.88E44 4.88E43 2.M+03 1.5E+03 1.17E43 9.17E42 7.4H42 6.26E42 5.36E42 4.67E42 46 1.35E44 3.99E43 2.28E43 1.55E43 1.14E43 8.94 42 7.31 42 6.12+42 5.24E42 4.56E42 47 1.81 44 3.91E43 2.24E43 1.51143 1.12 43 8.79E42 7.1H+32 5.99E42 5.13E42 4.47E*t2 40 1.81E44 3.83E43 2.19E43 1.48E43 1.!OE43 8.59E42 7.BOE42 5.84 42 5.83 42 4.3X42 49 9.9E43 3.7H43 2.14E+83 1.45E43 1.t443 8.42+82 6.86E+02 5.75E42 4.92+42 4.2EE42 56 9.7E43 3.63+03 2.tE43 1.42 43 1.82 43 8.3E+42 6.73 42 5.E42 4.82 42 4.2E42
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See Title Page 34 of 40
- oEP.p_M X_6 VERIFICATION TABLgg 7
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VER!r!CA71:M TA8LE
- k. 00U4 LEVEL RELEASE 8?A81Ll7f CLA38 F MILLIBEMMt PER CLRIE/SEC OF IODINE ILEl. EASED UFF89 W!W Don!4 0157mCE FROM M PLM7 SPRB (Mmo 1 Mt 2 P! 3 MI 4 MI $ MI 6 M1 7 M! I M: 9 MI 18 M1 1 4.57EC 2.M* 1.SM45 1.17ES 9.31E+M 7.69E44 6.33E46 S.6SE+04 4.98E*M 4.44
- 2 2.29E45 1.17E45 7.85E44 S.82
- 4.6d44 3.84 4 3.2d44 2.8X44 2.44
- 2.22E44 i 3 1.53
- 7.8E44 S.2X* 3.91E* 3.!K4 2.5d46 2.tCE* 1.8K44 1.6d* 1.44ES 4 s.14E45 S.8KS 3.M* 2.91 4 2.33E44 1.93
- 1.m* ' l.41E* t.N* 1.11ES S 1.83+0S 5.M* L3d* 2.4E* 1.M44 1.68E4 1.3d44 1.17E44 !.8X44 9.14 43 6 1.83 45 4.83
- 3. PES 2.25E* 1.75E44 1.43 44 1.19E44 1.3X44 8.92 43 7.94E43 7 1.81E45 4.55E44 2.8K* 2.84E4 1.5K44 1.24 44 1.8d44 9.!K43 7.9X43 7.B:E43 8 9.9d
- 4.M* 2.64E+M 1.8MS 1.G* 1.!!E+84 9.59E43 0.1E43 7.11E+83 6.24 43 9 9.7E* 4.8d* 2.4d* 1.7XS !.31E44 1.85ES 8.73 43 7.43 43 6.G43 S.6M43 18 9.SE44 3.8K* 2.29E44 1.6ES 1.21E44 9.6d43 7.99E43 6.79E43 3.84 43 5.tN13 it 3.7ES 3.64 44 2.!M44 1.49ES !.13* 8.G43 7.34 43 6.25E43 S.44E43 4.75E43 ,
12 8.5M44 LM44 t.99E44 1.38E44 1.M+04 8.2H43 6.83 43 S.7BE43 S.88E+83 4.M43
- 13 7.4X* 3.8E4 1.83ES 1.27E44 9.68E43 7.64 43 6.3E43 S.34 43 4.41E43 4.8X43 14 6.98E+84 2.8d* 1.7K44 1.:ES 8.91E43 7.29E43 5.DE43 4.9d+43 4.28E+43 3.76E+03 -
13 6.44E44 2.67E+84 1.59E44 t.tES 8.33 43 6.c 43 S.66E43 4.63E43 4.8K43 3.5:E43 16 4.8.E44 2.5E44 1.49E$ t.83E44 7.aE43 6.NE43 S.13 43 4.M* 3.75E43 3.M 43 17 S.68E4 2.3d* 1.48E44 9.7X43 7.M43 S.84E43 4.83 43 4.88E43 3.SX43 3. t E+03 18 S.33 44 123 4 1.33 44 9.19E43 6.E 43 S.51E+83 4.55E43 3.85E43 3.3X43 LH43 19 S.89E44 2.11E+M !.3E* 8.78E43 6.57E43 S.23 43 4.31E43 3.6*E43 3.16E43 2.T7E43 28 4.83E44 2.8E44 1.19E44 8.2'E43 6.24 43 4.9d43 4.89E43 3.47E43 3.88E43 2.E43 21 4.68E44 1.91E* t.14E* 7.87E43 S.94E+03 4.7X43 3.9:E43 3.38E43 2.86E43 2.51E43 22 4.M44 1.83 44 t.89E44 7.53+03 S.67E43 4.5:E+03 3.73 43 3.15E+43 2.7X43 7.M43 23 4.25 44 1.74 44 1.NG 7.19E43 S.43 43 4.33 43 3.5d43 3.3 43 2.6:E43 2. 9E+03 9.U 43 6.89E43 S.22+03 4.16E43 3.41E43 18ag43 ;,5g43 2, g,E13 24 4.23 44 1.67E44 3 3.Bd44 - 1.6K* 9.53E43 6.61143 4.99E43 3.94 43 3. E43 2.79E43 LE43 Lite 43 26 3.7:E44 1.M44 9.17E43 6.3d43 4.98E43 3.83 43 3.!!E+33 2.67E+23 :.31E43 2.8X+33 27 3.59544 1.E44 3.83E43 6.13 43 4.63 83 3.63E43 3.M 43 157E43 2.3+83 1.95E43 28 3.45E44 1.G 44 8.51E+83 !.9:E43 4.46E43 3.5:E43 2.U 43 2.4SE+03 2.14E43 1.8E43
~ 29 3.3X44 1.3X44 8. 5 43 S.78E*C 4.38E43 3.43 43 183 43 2.M 43 2.8'E43 1.83 43 38 3.23 44 1.3X* 7.95E43 !.StE+43 4.12 43 3.3:E43 L73+83 2.3:E43 2.8K43 1.7d43 31 3.13+84 1.29E46 7.69E+83 1.3X43 4.83 43 3.ia43 2.64E43 2.N 43 1.H43 1.73 43 32 3.t344 1.:5E44 7.45E43 S.lR+43 3.9CE43 3.tE43 2.!6E43 2.!N43 1.87E43 1.65E43 33 L E 44 1.2 E44 7.23 43 S.8:E43 3.73E*83 3.8:E43 L42E43 LtE43 1.83 43 1.6E43 34 2.84E44 !.*.E44 7.81E43 4.86E43 3.64 43 2.9:E43 L41143 LN43 1.72 43 1.55E43 35 2.76E* t.14E* 6.8:E43 4.73+83 3.52 43 2.84 43 L34E+83 !.9E43 1.71E43 1.58E43 36 2.E44 1.11Q44 6.63 43 4.59E43 3.44 43 2.76E43 2.:M+0 1.93E43 1.67E43 1.42 43 37 2.6:E44 1.8SE44 6.44E43 4.47E+83 3.37E43 2.6E+83 2.2:E43 1.3E43 1.63 43 1.43 43 38 2.54E44 1.85E+M 6.27E13 4.EE43 3.29E+43 2.6:E43 L16E43 1.53E43 1.53E43 1.M43 39 2.48E44 1.83E44 6.1:E43 4.24E43 3.NE43 2.55E43 L18E43 !.72E+33 1.M 43 1.2543 48 2.4tE44. 1.8K+ 5.92 43 4.13E43 3.13 43 2.45E43 2.85E+43 1.73E43 1.WE+83 1.33 43 l 4.E43 3.84E43 2.43 43 2.82E+83 1.69E43 1.42 43 1.29E43
- 41 2.36E44 9.77E43 S.81E43 42 2.3K44 9.53E43 5.6E43 3.94E*t3 2.97E43 L3d+43 t.95E43 1.65E43 1.G43 1.3E43 43 2.3E44 9.3
- E43 . 5.54E43 3.85E43 L98E+03 2.31E43 1.9?E43 1.6:E43 1.M+43 1. 3 43 44 L19E44 9.:K43 S.43 43 3.7d+03 2.84E+43 2. 6E43 1.86E43 1.58E+83 1.36E+83 1.:E+43 45 2.15E* 8.9t!43 S.38E43 3.64+93 2.77E43 L2:E43 1.83 43 1.54E43 1.3X43 1.17143 46 2.1K44 8.7K43 S.tE+83 LM43 2.71E43 2.!d43 1.71 43 1.S:E+43 1.38E43 1.14 43 8.53 43 3.8E43 3.53 43 2.65E43 2.11E43 1.N43 1.48E43 1.28E43 1.13 43 47 2.85E44 48 2.B:E44 8.34 43 4.93 43 3.45E43 2.6E43 2.8'E43 1.71E43 1.45E+03 1.EE43 1.18E43 49 1.9N+84 8.17E43 4.8eE43 L37E43 2.55E43 2.8X43 1.6'143 1.43+03 1.:3 43 187E43 28 1. Gat 4 B.8:E*83 4.77E43 131E43 2.58E43 1.9W43 1.6 E+03 1.M43 1.28E43 1.N43
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See Title Page 35 of 40
- APPEPOIX A VERIFICATION TABLES
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! 3 2.5547 I.9156 3.49:5 8.3229 8.2332 8.1784 8.1424 8.1171 5.t?!? 3.05:6 3 . 2.4:M I.9757 8.4h5 B.t:4 0.2242 8.1716 8.1E? I.1126 3.8949 8.II:4 27 2.3654 I.8335 I.4580 B.M99 I.2;59 L1652 0.1318 B.1385 I.t913 I.f7M 3 2. 3 13 B.5885 I.H24 8. 3 12 8.23I2 I.1593 8.12n 0.13 % 3.2591 S.I'%
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HATCH NUCLEAR PLANT PROCEDURE Eme r o en c y Og.e.. r a. t i on s Fa..c i l i ty Activation _ Procedure PROCEDURE TITLE HNP-4869 .._ PROCEDURE NUMBER La._b RESPONSIBLE SECTION SAH:.I Y RELATED ( X ) NON-SAFETY RELATED ( ) _ _ _ _ _ _ ..-_---__-_- ____-__-_q_____-___-__-_--..--__---__-___-- 3____-_-. APPROVED APPROVED REV. DESCRIPTION DEPT. PLANT DATE HEAD MANAGER
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REQUESTfD DV OEPARTMFNTlE S' cn, sture: f Date* Date: DN Name: -
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ws A) -)- O AS DESCRIGEO IN FSAR: REVISIOM CHANGEG NODE OF ) Yes CFERATION GR( INT ) No ( CHANGE INVOLVES: Neither ( ) An uncoviewred Gafety Guestion ( ) Tech. Specs. ([ ) (See back for- Gafety Evaluation if required). CafetyRelated([) Non-Safety Related ( ) ! t PRESENT STATUS: - i-
) Yes to ..__,_
The above Safety /Non-Safeiy Status has changed ( .
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Attach marhed up copy of procedure to this form. H Q d __ h ct (p> /.h _ O/7 REASON FOR REGUEST: O_ ff ~ fkN L_h N 55 t0 AhL >h_4t_.5.S'LvbOf c ~
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O PROCEDIFE REVIGION REGUEST SHEET 1_OF 1 , - PROCEDU9E P'O. HNP- hh REVISION MO. A REAGo. OR REGUEST: _ @hd__ #1 /k - 4 lh - ( _1 '
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See Title-Pace 1 of 29 , EMERGENCY _ OPERATIONS FACILITY
- ACTIVATION PROCEDURE NOTE
-This procedure is intended to be guidance for activating the Emergency Operations Facility (EOF) in emergency situations. Deviation from the listed sequence is permitted when plant conditions warrant a more expedient order of completion.
A. PURPOSE The EOF is an onsite or nearsite support facility for the management of overall licensee emergency response (including. coordination with federal, state, and local officials), . coordination of radiological and environmental assessments, and determination of recommended public protectiv' actions. This procedure addresses and delineates the actions required to bring the EOF to a state of functional readiness. O. CRITERIA FOR ACTIVATION The EOF shall be activated at a Site Area Emergency, General Emergency, or when deemed necessary. All or portions of this procedure will be implemented as appropriate based on the desired function of the EOF. Activation is achieved when, in the judgment of the EOF Manager and/or Emergency Director, staffing and equipment are sufficient to carry out the purpose of the EOF facility. C. RESPONSI0I_LITIEG The first person (s) responding to the EOF will be responsible for initiating this procedure. The EOF Manager or his/her designate, upon' arrival, will be responsible for ensuring completion of this procedure. D. ACTIONS The person (s) implementing this procedure shall perform the following actions:
- 1. Obtain keys to Simulator Building from glass key box or from Security and as necessary have Security unlock appropriate doors in EOF and to lock doors to all entry points except the west end entry point. Ensure that two classrooms in north side are locked.
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See Title Pace. 2 of 29
- 2. ' Establish personnel-sign-in to provide accountability to EOF. Place a table, sign-in' sheets, and baoges next to double _ doors at the west end of the hallway between entry and first classrooms. Have incoming personnel sign in on the sign-in sheets and wear-the appropriate badge. (See Data Package 1 for sign-in sheets.)
- 3. ' Ensure arrangement of the physical facilities per Figures 1 through 4.
- 4. Onsure arrangement of the communications equipment per Figure 5 through 7. . Telephones are stored in cabinets on north wall of classrooms and in HP lab ~ cabinet. Tape cords to floor.
- 5. Remove the portable status boards from behind the false wall in Classroom 1 and place per arrangement in Figure 8 and 9.
G. Check status boards for correctness per Figure 10 through 15..
- 7. Make HVAC filter system operational by pushing red butto~n located in the Simulator Duilding HVAC room. This action will put the system in the abnormal condition.
- 8. Ensure adequacy of supplies and equipment per Data Package 2.
NOTE
. Contact responsible group if discrepancy is noted.
I i
- 9. . Set up dose assessment computer per Data Package 3.
- 10. Perform communications checks per Data Package 4.
l 11. Have Health Physics personnel check operability of HP instruments and take general area dose rate readings and air samples and record on Data Package 5.
- 12. Ensure minimum staffing of the following positions:
- a. EOF Manager
- b. Dose Assessment
- c. Public Information
- d. Security
- e. Health Physics s
mand set ,1
, , x; @
~
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- 2
.... Georgia Power .. .
See' Title Pace 3 of 29
.'f . Administration g.. Communicators / Recorders.
- 13. Review sign-in sheets for accountability check. Ensure control-has been established.
- 14. -Ensure that key personnel are starting a log.
- 15. Inform Emergency Director, and as appropriate TSC and General. Office, EOF is activated.
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' LOCATION Or j'9
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. FIGURE 4 ARRANGEMENT OF TABLES _IN STATE AND LOCAL AREA MM #' s es, 7tsF Wis to. gg g,. ,
l seeuemt stwr To w. W MuepWNT' w mf MMames. 1
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~
FIGURE _5 ARRANCEMENT OF PHONES IN_ COMMAND CENTER To WEL 94 Am , Y% 4 l') l PG'ca1
- CON *C facgge cagooggmL
#2b # 16 dr2d #6 I20 ggy NA taeuVf cv p m
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. EIGURE_@
ARRANGEMENT_ OF PHONES IN_ DOSE _ ASSESSMENT AREA
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- . NR INDICATES PHONE SET WITHOUT RING DOWN LINES R INDICATES PHONE SET WITH RING DOWN LINES NOTE
# INDICATES PHONE SET IDENTIFIER ON BOTTON OF PHONE SET mused set
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See Title Page 10 of 29 FIGURE _7
, ARRANGEMENT OF PHONES IN STATE _AND LOCAL AREA TATT)%LA (0- Tecm6S co.
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See Title Page 11 of 29 FIGURE _8 LOCATIONS QE PORTADLE STATUS _80ARDS__IN DOGE _ ASSESSMENT AREA U usiI
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, LOCATIONS OF STATUS BOARD IN COMMAND CENTER Tb N$em MET MTA
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,- FIGURE 10 STATUS _ BOARD #1 t DERGEY STAM tDF ActivATID DA1E TIE M C1AS DATE TIE AtlT STA1US OF Onest taet?
_ -->.n. 2 MSIN Ast31AIG YES le PlIE AretAAM2 POLIG lairt1E JneR SITE EVACunTIGs YE3 10 LIMITED ter!FTED: DATE TIE tec STA1E OF GA DATE/TTE AEDITIGIAL IIWUMATIGI I SECORDED Of: 3% meneet set a 700080
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-- FIGURE 11 STATUS BOARD # 2 2 Ok3*lrrtue 0F tMNr5 M / TIE e
CCORDEO GV: _ l M Set :: !d
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o... . See Title Page 15 of 29 FIGURE la STATUS BOARD # 3 F 1 MAstr sinTus Onit/itf( IGS 1 NtenTER t__" "_ IN-h NEIBimE r$IC _y= 19F % W ISEL IN. HIEsemE PSIC __,.9., tis GEC 1 NOs GBIC 1 E - a HIE m mE PSIC 159 8, 4 _t 5 t coasto er l e
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See Title Page 16 of 29 FIGURE 13 STATUS BOARD # 4 i 4 NICAL MTA MIE/TDS runatinT a""
" ** T F
.- y m 155E Wise WED ,
M DIM'f1GI FMDI RADI0tfr1 CAL IIWGPATIG8 MIE/TDE aF= F1hm PG1113 @S De 16 er/br - Efam M C3DI . II M Wir git II Stag M CIDE EM Z GA5 MM RATE C1/E rerumm r_ sin, Slam IANL
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CCOROtt ST: l i l l l i I l l asemal set voce:o .
aa aova' E.1. H;tch Nucl:::r Picnt a=ce=as ~o HNP- 4869 neve o= ,.o . See Title Page o.,e GeorgiaPower A .. e . See-Title Page 17 of 29 FIGURE 14 STATUS BOARD # 5 g osaner amenAn 2 mm rannts cose 2 01E 00Dr er/hr 1Myst010 mint . I wgxz 300f a/hr TWVROID w /hr 10 SIERR 1 2 5 10 t t 5 10 m 1 2 S 10 1 2 S Y
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. FIGURE 15 STATUS BOARD # 6
, FIELD TEAM DATA REF # PROJFCTED DOSE FIEl62 RESUL 9' LOCATION ^ WB Ihyroid WB- Thytold IODINE DOS.
TEAM (S. Mi, #1 ETA TIME (mR/hr) (mR/hr) (mR/hr) (mR/hr) uC1/cc mA REMARKS t e e e O O
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. PROCEDURC DATA PACHAGE DOCUMENT NO: HNP-48Q2d SERIAL NO: RO1-MPL NO:
= - .
RTYPC: C15.03 XREF: _ TOTAL CHCCTS:__g FREQUCNCY: , COMPLETED DY: DATE COMPLETEO: I HAVC REVICWCD THIG DATA PACHACC FOR COMPLETENEGS M O AGAINCT ACCEPTANCC CRITERIA IN ACCORDANCE WITH Hr4 -830.
~
I j- ACCEPTADLC UNACCEPTABLE REVIEWED BY: DATE REVIEWCD: RCMARHG: l Page 1 of 2 FNP-4863 RO1 i i FIGURE 16 Page 1 of 2 l ! asensi set b m
S a~om E. I. H;tch Nucl=r Plcnt aaou== = HNP- 4869 See Title Page esioa ao
... GeorgiaPower A .... ~o Gee Title Pace- 20 of 29 y ,
QATA PACKAQg_1 GQC.91CN-IN.gl.g Q ' Date:
. Dadge Time Time Time Time Time Time Name No. In Out In Out In Out
._v..... ._-._-__......_- ........
l 1 I l l 1 i l b
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- i. _
Page 2 of 2 FN'-4BES RO1 s FIGURE 16 Page 2 of 2 mesed set s
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HNP- ' 4869 Sao Titio Pega aevmoa m om. GeorgiaPower d ... 2 See Title Pace 21 of 29 PROCEDURE DATA PACKAGE. DOCUMENT NO: HNP-4Q{2;Q SERIAL.NO:J Q1-MPL NO: - RTYPE: G15.03 XREF: TOTAL SKETS: 3
- s FREQUENCY; ,
COMPLETED BY: ex DATE COMPLETED: I HAVE REVIEWED LIIS DATA PACKAGE FOR COMPLETENESS Ato AGAINGT ACCEPTANCE CRITERIA-IN ACCORDANCE WITH HNP-830. t i ACCEPTAOLE UNACCEPTABLE REVIEED BY: DATE REVIEWED: i ! REMARKS: I
- =
Page 1 of 3 Hrf-4869 RO1 - FIGURE 17 Page 1 of 3 meessi set 700080
. k aa-o= E. l. Hctch Nucl cr Plcnt aaocs= =
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. See Title Page wwsionno o., Georgia Power d .. s ,.o See Title Pace 22 of 29 i
EATA P $H_AG_E 1'. G9C_GLIO.1GQJ.13I j
.............u..._-.... -_... .... _....... _ ... .-_..__.......
SUPPLY CADIPCT EGUIPMENT
-........ ...... --.. . ,._--~. ... . . ... _.... ..... _... _ . . . .
Pencils and pencil sharpener Typewriter Staples and staplees H.P. instruments Tape end tape discentare Air sampler Hole punch Respirators
- . . . . . . . . . . . . - . . . . - . . ~ . - . .. . . . . . . .._...._..__..:_. ......._.
Watercolor markers Telecopier
. . _ . . . - . . . . . . ~ . . . . . .. . . . . . . . _ _ _ . . . . . . . . _ _ . . . . . . . . .
Dry Markers Contamination ssgns and l barriers . Rulers Gem clips- Field Team Monitor . Instruments . . Rubber bands DOCUMG4T ROOM Ctaple pullers Located in Simulator
. . . . . . . . . . . . . . . . . . . . - . . . -. - . . . . . ~ . . - . . . . . . . . - - . . .
Cxpanding folders
. . . . . . . . . . _ . . . . . . _ - . . . . ~ .... . . . . . . . . . . . . _ _ . . _ - . . _ . ..
Label maker
. . . . . . . . . . . - . . . . . . . . _ . ~ . . _
Letter trays
......_..__ ..-. ..-.-_.. --. . .. . . . . . . ~ - - - - - . . . . . . . . - - - .--.-
Calendar stands and refills I ~ Local phone books Scratch pads
. . . . . . . . . . . . . . . . . . _ - . . .. . . . . . .~ -... .......... -.. . - . . - . .
l Phone call logs l Logbooks .._.. Typing paper ..---
..........-... ... --..- --.--.. ..... - - - - - . . . - . . - - - - - - . - - - ~ . - . -
GPC Ictterhead paper
. .. ..-.... . . . ..... .-.. . . . . . . ..-.~-- ---...... ~.---.- . - --
Inte'roffice papee Name tags . Ashtrays ,
.. ........-. a_..... ... .-..--
l' Waste baskett .-._.- l- ......... .. _- .... .. ...... ..... Page 2 cF 3 HNP-48CS RO1 FIGURE 17 Page 2 of 3 mensal set
.- w ,r- -~. -., . , ew-- -e , - - , , . ,-e-. . . , , - ---. , .- ,,.-- , , ,
- E. l. H;tch Nucl:Cr Pirnt aaociova= +
HNP- 4869-a<wsio'* **o Sao Title Pcga 2 om Georgia Power A . >. See Title Paae 23 of 29 QATA PACKAQQ,Q,1QQtg d
. i G9C 9WCCLIG9 619I I CUPPtY CADINCT EQUIPMENT Coffee supplies-Coffee pot Cmergency call lirt Cmergency telephone numbers ..___..___..:.-__._.... _ . .
Maps for Field Teams _ ...._ __ .. ...._ . -.-_.._ .... ,..._ -...._-_ -__. ________.. _- J Signature Date l i I 1 t .: l Page 3 of 3 HNP-48C'3 RO1 i FIGURE 17 ' Page 3 of 3 mesed set , ,;
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HN P- 4869 Sao Titlo Paga aevim e-o.1. Georgia Power d .. See' Title Pace 24 of 29
~
PROCEDURE DATA PACKAGE DOCUPENT NO: HNP-4g69-3 SERIAL NO: RO1-PFL BO: RTYPE: C15.03 XREF: . TOTAL SFEETS: 2 FREQUENCY: COPPLETED BY: DATE COMPLETED: I HAVE REVIEED THIS DATA PACKAGE FOR COPPLETEPESS APO AGAINST ACCEPTANCE CRITERIA IN ACCORDANCE WITH HNP-830. ACCEPTADLE UNACCEPTADLE
. REVIEWED BY:
DATE REVIEWED: REMARKS: 4
=
Page 1 of 2 FNP-4869 RO1 FIGURE 18 Page 1 of 2 U2 mesual set -
.. s 700819
~
- == E.1. H'.tch Nucirr Pl nt ====
HNP- 4869 Sho Tit 1e Pcg2 uvisio*e *.o
' 2 o.r. Georgia Power A ..r.s ,.o See Title Pace 25 of 29
- DATA PACKAQ W DOSC ASQG2SMENT COPPUTER START-UP
- 1. HARDWARE CONNECTIOPE- INITIAL
- a. Ensure that printer and computer are switched off.
- b. Connect Input / Output cord (thin blue cord) from computer.
- c. Feed paper into printer and lock down.
. 2. POWER-UP
- a. Flug printer and computer power cords .
into outlet.
- b. Turn printer on.
- c. Push printer reset button.
- d. Turn computer on. ,
-3. PROGRAM LOAD
- a. Red light illuminates. .l
- b. Insert disc into disc drive unit after g red light goes out.
- c. Press reset
- d. Enter - Date-and time (24 hour clock)
- e. Enter - Dasic
- f. Enter - 2 (files) l
- g. Press - Enter Hey
- h. Load "DOCE" .
l l~ 1. Remove disc from disc drive unit when red light goes off. J. Enter - Run
- k.
- Proce%d as prompted by computer l
Page 2 of 2 M -4869 RO1 FIGURE 18 .-4 l Page 2 of 2 menesi set
g; - u a m at E. l. Hatch Nuclocr Pl nt aaoceaan ao HNP- 4869 Sao.Titlo Paga atvis'oa ao-
~
.... Georgia Power d .... o See' Title Pace _ 26 of 29 PROCEDLRC DATA PACHAGE DOCUMENT NO: HNP -43(2-4
. SERIAL NO:__RO1-MPL NO:
RTYPC: -G15.03 XREF: TOTAL SHECTS: 2 . FREQUCNCY: . COMPLCTED BY: DATE COMPLETED: I HAVC RCVIEWCD THIS DATA PACKAGE FOR COMPLETEtESS APO AGAINST ACCEPTANCE CRITERIA IN ACCORDANCC WITH HNP-830. ACCEPTADLE UNACCEPTABLE REVIEnED BY: DATE REVIEWED: REMARMC:
'c ~
~
i ; Page 1 of 2 FeP-4869 RO1 I FIGURE 19 t Page 1 of 2 menest set L. _
l a== E. li H:tch Nucl:ar Pl:nt aaocioua m HNP- 4869
- See Title Page am**"o 2
..,s Georgia Power r.os Gee Title Paae 27 of 29
.~ . QATA PAQgAQQJ QOMMUNICATIONQ_QtgQdQ t!9IE 1
Check radio operability. Cnsure that a minimum of one of- the below listed telephone lines is functioning. These checks may be
' - completed on a single telephone set. Functioning as defined for normal and ring down lines to be as follows:
Ring Down Lines - When the receiver is lifted a ringing of the-other phone is heard. Normal Lines - When the receiver is lif ted a dialtoIie is heard. TELEPHOE LIFE OPERABLE INDPERADLE Ring Down to (Control Room) ... ........ __.._ .._...... Ring Down to (OCC) .... _____ __ .._........_
.. ........_ . . .........................~
- Ring Down to (TSC) ........._ . __..._ ......._
Ring Down to General Office ...._.........- 1 of 2 Local Outside Lines ..-- ------- ----..--------- l Any 2 Plant Extensions ... .............._......- L_.__.......... .................._....... _ Gagnature Date
?
Page 2 of 2 FNP-4869 Ro1 j FIGURE 19 . Page 2 of 2
- 4. mesed set y-i.
- - - , _ ,e---
r- g a=va' E.1. H:_tch Nucl; r PI:nt aa=<ouas ~o HNP- 48G9 See Title Page aevis.om uo oar. GeorgiaPower A .. See Title Pace' 28 of 29 PROCCDURC DATA PACHACE DOCUMENT NO: HNP-4869-5
-SERIAL NO: RO1-PfL NO:
= - .
RTYPE: G15.03 XREF: TOTAL SHEETS: 2 , FREQUENCY: . COMPLCTCD DY: DATE COMPLETED: I HAVE REVIEWCD THIS DATA PACHAGE FOR COffLETEFESS APO AGAINCT ACCEPTANCE CRITERIA IN ACCORDANCE WITH HNP-830. ACCEPTADLC UNACCEPTABLE REVIEWCD OY: DATE REVIEWED: REMARMS:
..~
~
Page 1 of 2 M -4869 RO1 EIGURE 20 Page 1 of 2 C mensel set
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- E. I. Hatch Nucizr PI:nt aaocioua. o HNP- 4869
- nemio c.
See Title Page 2
-. Georgia Power A .
See Title Pace 29 of 29
. .QATA PACKAGE _5 GURVEY REGULTS DATE TIPC GEERAL AREA DOGE RATES - -----. ACTIVITY ---------
AIRBOR!t INITIALd
? ---.---.--..... --.. ----- ------------- ---
l i i l-1 r ------------------------ ..----------------- i
.s
.m-4 I %
I l Page 2 of 2 FN2-4869 RO1 1 f' r 2 FIGURE 20 Page 2 of 2 meneet set
f 4 A GEORGIA POWER COMPANY o HATCH NUCLEAR PLANT PROCEDURE Qfis.if.e .Radiningira1 Envirnamenta1 Monitating Dur.ing FmA9.nc.ies PROCEDURE TITLE
~
HM)-4827 PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( )
- ___ _ p____________________. _______________ ________________p_______.
APPROVED APPROVED REV. DESCRIPTION DEPT. PLANT DATE HEAD MAN ER ______ r________________..__ ________ ______ __ ____ _____ _ p_______. O New Procedure q q_. g ,y _ 4_. ______.p____________________. ___ ___ _ _ .p__ ___ ____ __ p_ _ . j 1 Pages 1 thru 15 . .o g . r____________________ _ _. _ _____ _ ___ (_ _ _ _ _ _... 2_ _ _ _. _ _P_a.g g s. _4_ _a n _ d_ _1_3_ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . p_____ __________
$/
r_____________.r_______. r________________ p________ ______ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . ________________ p________________ r_______. ______ ____________________ ________________ p________________ p_______. e_____ ____________________i f________________ ________________ _______e
._____ ____________________ r________________ p________________.r_______.
r________________ p________________._ _ _ _ _ _ _ _ . ____ ______ _______ ____ ________________ p________________. _ _ _ _ _ _ _ . ______ r____________________ r________________ p________________ ---____. __.___ p____________________ p________________ p________________. _______. r____________________ p________________ p________________ r_______.
._____ ____________________ p________________ p________________ _ _ _ _ _ _ _ ..
______._-__________________p________________p________________ p_______- HNP-9 . A set 9
. _ _ _ . . . . , _ . __.e. .
. ~ . _ _ _ . .. sc-....__.. ..__..u___.
M IO/II Yb/# A j r:acEG5c REVIstow PEGuE9T hI M
, , PROCEDISE NO. HNP _ _7 _ _ _ _ SHEET 1 OF___
Revision No. / ___ ggouggy;o_gv ..-. -.. DE r _. MEN
- - _. g_ge - - Q.- . . .-,g m__
Name: Date: Signature: Date:
/D- //- f3 '
hfrNhh[h i { REVISION C.HANGES MODE Oc CPERATION OR INTEt,JT,AS DESCRIBED IN FSAR:
) ( ) Yes ( M No I CHANGE INVOLVES:
( ) An unreviewed Safety Guestion ( ) Tech. Specs. ( ithee (See tack for Safety Evaluation if required).
.PRESENT STATUS: Safety Related ( Non-Safety Related ( )
The abovs- Safety /Non-Safety Status has changed ( ) Yes to __ _ Atta ch ma r - ' ed up copy of procedure to this form.
* - ~
- REASON FOR REGUEST: / M' o /WN '#41/ e7
- Anness.w's Ar2 LAAwk w/A
%efw jjais nr 7%~ adA/s
^
/' /
DEscRIPTTcN OF CHANGES: // g_,f,f jh / eh7 u2Aff K_" L iD m . _./ ( tids MyJr fd _0__/lN l.0%__ & ' __'~;,5 i m fQ,. ._i__?_ j d8__' $r_b_,__ radzo- _ t ifa_ WWr - - - -_ __ _____ _
/ / _ _ ___ _ _ _
PRB RECOMMr.NDS APPROhAL: ( )Ves ( )No l PRB Secretary
?3- l 8't Jo w-r.2 l T'RB Number Date i
l HNP-9 l
, s.
l! & ' ., j
Tv = S_e_#_w_AMLUAT I CN e _ an unreviewed safetv This revision of this procedure does not constitute - _- - _ . , _ _ , _ _ l z-_ nue ntan.las_txalni n u stes__.
- l. T_he ornbabil117._2L.ASMMIIL9 SSHI1qugggis of an acci_d_ent .,,__,,_
a
- 6 ne um1 funggioui_gguinmant 4enarIgnt tci tha salR12.4IS_DRt..iDELt.a.gd, _
e ___ghnve rhnse,_anniv_ red in_ghg,,,E Mjkdge to these changes _because the -- 6 __
raylei n"_ dna.nor eh2n&& rhe_ptirpase or performance o f thg.,,Ay.pteln.
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a == E. l. H;tch Nucl::r Plcnt- axswam HNP-4827 / Sco TitlO Pcg3 mmsoom p 2 om Georgia Power d ..om See Title Page 1 of 15
. OFFSITE RADIOLOGICAL ENVIRONMENTAL ~ MONITORING DURING EMERGENCIES NOTE
'This procedure supercedes HNP-4625 Rev. 5 and HNF-4725 Rev 5.
A. PURPOSE.
. To provide a' method for the determination of radiological conditions in the plant environs, due to the release of radioactive materials from the plant under accident conditions.
Also, this' procedure will provide instructions for integrated offsite survey teams consisting of some combination of state, local, and GPC personnel. B. DEFINITIONS AND TERMS
- 1. EOF - Emergency Operations Facility
- 2. REC - State Radiological Emergency Coordinator . _ .
3.. RET - Radiological Emergency Team
- 4. Dose Assessment Management - Integrated state, local, and GPC personnel collectively consisting of the Dose Assessment Manager, the REC, and lead personnel from local civil defense organizations.
C. SCOPE
- 1. The activities of the offsite monitoring teams will generally be performed in the Emergency Planning Zones
, (EPZ), from the plant to distance of approximately (but not
- limited to) 10 miles.
- 2. Offsite monitoring teams will be under the direction of the Dose Assessment Management in the EOF.
. NOTE t
It is understood that the ultimate responsibility _ for offsite radiological environmental monitoring rests with the State. D. REFERENCES
- 1. HNP-4620 " Site Area Emergency"
- 2. HNP-8142 " Stabilized Assay Meter SAM-2 Operation and Calibration" s
need set
^~am a' E. l. H:.tch Nucirr Plznt **awas o HNP-4827 Sco. Title Pcg3. asesio,. m 2
om Georgia Power d . See Title Page 2 of 15
~
E. ORGANIZATION
- 1. - Team Composition
'a . The teams are expected to generally consist of 3 or 4 persons, depending upon the avilability of personnel and the nature of the mission to be performed.
Functions to be performed may-include: (1) Driver (2) Navigator (3) Data Recorder (4) In-transit Instrument Reader (5) Field' Sampler (6) Communicator
-(7) Sample Taker (8) Sample Analyzer
~
- b. The Dose Assessment Management shall designate a team captain for each monitoring team. The team captain.
shall assign responsibility for each of the above . . functions (as applicable) to individual team members." Team members may be assigned responsibility for multiple functions. The team captain is responsible for assuring that all necessary actions are performed.
- 2. Team Responsibilities
- a. Collect environmental media.
- b. Conduct radiological field measurements (plume monitoring) with readings by location.
- c. Conduct air monitoring by location.
- d. Communicate sample analysis data, dose rate information, and personnel dosimetry to the EOF.
f F. ACTIONS l
- 1. Radiological Emergency Team personnel should meet in the EOF to get instructions, find out the events that have taken place, and to be assigned to a monitoring team.
l 2. The Dose Ascessment Management is to divide personnel into l teams using combinations of state, local, and GPC l personnel. Teams should consist of a max of 4 people (avg. 3). s l , 33330L SGI l
,w
at 4**' E. I. Hitch Nucirr Plt:nt
~
a ao= - =a=== HNP-48 27 SCO Tit 10- PEga aswso. o " 2 om Georgia Power d ~..
-See Title Page 3 of 15
'3. 'Offsite teams may use vehicles equipped with two-way communication devices belonging to GPC, the state, or the locals as appropriate. In addition, portable radios and it
-antennas _obtained from the EOF will be~used as alternative communications. If personal vehicles are used, the portable radios and antennas will be the primary communication system
' and.the Bell system as an alternative.
- 4. The Dose Assessment' Management shall designate a' team captain ~for each team.
- 5. Once the teams and team captains have been designated, each team captain will be responsible for assigning each member of his. team certain tasks, ie, driver of the vehicle, navigator, data recorder, in-transit instrument reader, field sampler, communicator, sample taker, and sample 1 analyzer. ,
- 6. Upon the classification of an ALERT level emergency, the-offsite teams may be activated at the discretion of the Dose -
1
-Assessment Management. If the classification is a' SITE AREA
- or GENERAL-Emergency, teams shall be activated. The Dose Assessment Management directs the staffing and deployment.
- 7. Obtain a survey team kit at.the EOF.
- 8. Complete the checklist in Data Package 1, Data Sheet 1.
- 9. After the' equipment is checked for operability, the monitoring team will establish communications'with the EOF.
10.- Turn on survey instruments, allow them to warm up, and j , verify response with the check source providad.
- 11. Install glass fiber filter and' silver zeolite cartridge in
- - sample holder of air sampler. Turn on sampler and confirm proper operation. Turn off.
- 12. Proceed to area specified by Dose Assessment Management.
- 13. While in transit, survey meter for measuring dose is turned 1 on. The instrument is positioned for continuous viewing and ready access for recording readings. If readings above background are detected, record appropriate information on Data Package 2, Data Sheet 1.
- a. Indicate observed readings on survey map. (Report any c indication of a plume to the EOF). Record on Data i
Package 2, Data Sheet 1. b.- . Record time entering the plume as indicated by the s survey meter reading on Data Package 2, Data Sheet 2.
. mand set ,,, , . - - , _ _ , - ~ . . ___,..,,.,_,,,__..,__m,.. _..m__,--. __,,,,,,.--,,,--,,,,,_,_,,_m., _ _ _ , . _ _ _ , . . . . . , . _ , , . . _ , , _ , , , _ ,
- - aaaaovat E. l. Hatch Nuciser Plant- aa==a< ~o HNP- 4827 Sss Title'Pcg3 aevisum mo 2
oa,, GeorgiaPower d aa. See Title Page 4 of 15
- -c. If dose rate.is in excess of 5 mr/hr, report reading to the EOF.
NOTE Minimize traversing of the plume as much as practical to maintain exposures ALARA. Contact
.the EOF prior to exceeding any administrative exposure guidelines. Provide periodic. personnel exposure updates to the EOF when exposures are considered significant. Record personnel exposure data in Data Package 2, Data Sheet 1.
- 14. Upon arrival at the sampling location, perform a dose rate survey in the following manner:
- a. At waist level, hold GM probe HP-210 or GM survey meter (or equivalent), read meter, and record results on Data Package 2, Data Sheet 2.
- b. At 2" above the ground, hold GM probe with detecton -
window facing the ground, read meter and record results on Data Package 2, Data Sheet 2.
- c. At waist level, hold high range survey meter horizontal, read and record dose rate on Data Package 2, Data Sheet 2.
- d. Repeat step c above, but at 2" from the ground.
- 15. Take air sample at designated area when requested by Dose Assessment Management as follows:
- a, Place a silver zeolite-(AgX) cartridge in the sample head, and mark the cartridge to specify the inlet side of the cartridge. Place a particulate filter upstream of the AgX cartridge, and place the sample head in the air sampler.
- b. With the engine running, connect the air sampler power 4
leads to the vehicle battery, tak ng care to connect the positive and negative cables to the positive and negative battery terminals respectively.
- c. Start air sampler and record time on Data Package 2, Data Sheet 2.
- d. Check air flow indication and record flow rate.
- e. Run air sampler 10 minutes, record flow rate from calibration sticker on Data Package 2, Data Sheet 2.
s
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om . Georgia Power d ~m See Title Page 5 of 15
. NOTE
' Dose Assessment Management may request other sample. times.
- f. Make radiation survey as.in step 14 above while running the air. sampler.
NOTE If. levels are greater than 10 mr/hr report reading to the EOF and await instruction from the Dose Assessment Management.
- g. Remove the AgX cartridge.and particulate filter from the sampler head, and place in separate plastic bags.
- h. Air samples should be labeled and a log entry made in the-log book of the following information:
Date and start time of sample - Duration of sample Flow rate of sample Location of sample point (map location, landmarks, etc.) Survey team name Air sampler number SAM-2 Analyzer serial number (if used) NOTE During air sampling, monitoring teams should observe the dose rate instrument for significant changes in dose rates. Report any significant changes to the EOF. Record personnel doses on Data Package 2,-Data Sheet 2 while sampling. l i. Insert GM survey meter probe (HP-210) into sample holder (SH-4A) and record background reading.
- j. Place glass fiber filter in SH-4A holder and obtain reading (CPM). Calculate airborne concentration per Data Package 2, Data Sheet 3.
~
- k. Place silver zeolite cartridge (which has been placed in plastic bags) directly against probe (HP-210).
Obtain reading (cpm) and calculate airborne concentration per Data Package 2, Data Sheet 3. (pci/cc) q mood set
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HNP- 4827
-SO3 Titlo PCg3 womm =o ' 2 om Georgia Power d .. .
See Title Page 6 of 15 NOTE If SAM-2 Counters are'available, cartridges may be counted using HNP-8142 and HNP-4826. Record data on Data Package 2, Data Sheet 2
-as CPM (net).
- 1. Place sample filters' in envelopes and record on-envelopes time, location, flow, sample time, cpm, background, and air activity. Hold for further analysis at place EOF.
- 16. Collect soil, vegetation and water samples when requested by the Dose Assessment Management, as follows:
- a. Take bag (mark it soil) and small scoop, fill with surface soil from a bare spot, tape closed, and tag with the date, time, and location. -
- b. Take bag (mark it vegetation) and scissors. Cut, ,
vegetation approximately two (2) inches above groun'd, fill bag, tape closed, and tag with the date, time and location. (If possible, choose vegetation that might be ingested by animals),
- c. Fill poly bottle with surface water, close and tag with date, time and location.
- 17. Record time out of the plume on Data Package 2, Data Sheet 2, and determine total stay time.
- 18. Report all results to ECF and await further instructions.
Document all results in Data Package 2. l 19. When directed by the Dose Assessment Management, proceed to l environmental TLD and air sample cabinet locations. Change out TLD and filters at the stations noting time and date of change out. Return samples to the EOF.
- 20. Return all data sheets to the EOF for review, analysis and temporary storage. These data sheets shall be permanently stored in Document Control upon termination of the emergency condition.
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See Title Page 8 of 15 FIGURE 2 IODINE DETERMINATION
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..,. Georgia Power d ..
See Title Page 9 of 15 PROCEDURE DATA PACKAGE DOCUMENT NO: BNP-4827-1 SERIAL NO: R02-MPL NO: RTYPE: G15.03 XREF: TOTAL SHEETS: 2 FREQUENCY: , COMPLETED BY: DATE COMPLETED: I HAVE REVIEWED THIS DATA PACKAGE FOR COF.DLETENESS AND AGAINST ACCEPTANCE CRITERIA IN ACCCADANCE WITH HNP-830. ACCEPTABLE UNACCEPTABLE REVIEWED BY: DATE REVIEWED: REMARKS: Page 1 of 2 HNP-4827 R02 FIGURE 3 Page 1 of 2 gge,g ,,g g , - - - - _, . , _ , , , , , _ . , , , , . _
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HNP-4 827 See Titio PCg3 ansio o 2 o.,s Georgia Power A ... See Title Page 10 of 15 DATA PACK 7GE 1 MONITORING TEAM JRfDKLIST Data Sheet 1 A. ' Inventory Kit and Verify Necessary Items
- 1. SAM-2 Analyzer (optional)
- a. Battery and source check .
- 2. Survey Instruments
- a. Battery and source check
- 3. AgX Cartridges
- 4. Particulate Filters
- 5. Calculator
- 6. Stop Watch
- 7. Log Book
- 8. Sample Bags
- 9. Pocket dosimeters
- 10. TLDs
- 11. EOF Telep One Numbers (in log book) _ _ _
- 12. Aitborne Activity Calculation Form
- 13. Cloves
- 14. Tweezers
- 15. Labeling Materials (labels, pens, etc)
- 16. Maps and Procedures
- 17. Spare Batteries
- 18. Blank Smears
- 19. Portable Air Sampler
- 20. Sample Bottles
- 21. HP 210 Probe / Bolder B. Prior to departing the EOF, verify the followingt
- 1. Survey instrument in cab and on lowest scale _ _ _ _ _ _,
- 2. Team members equipped with dosimetry
- 3. Maps in cab
- 4. Vehicle radio check completed Page 2 of 2 ESP-451' ?02 FIGURE 3 Page 2 of 2 g set I
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, , , Georgia Power - ,.o See litle Pace 11 Of 15
. PROCEDURE DATA PACKAGE DOCUMENT NO: ENP-4327-2 SERIAL NOs___R02-MPL NO:
RTYPE: G15.03 XREF: TOTAL SHEETS:__ 5
., FREQUENCY:
- 2 COMPLETED BY:
DATE COMPLETED: I HAVE REVIEWED THIS DATA PACKAGE FOR COMPLETENESS AND AGAINST ACCEPTANCE CRITERIA IN ACCORDANCE WITH HNP-830. ACCEPTABLE UNACCEP TABLE REVIEWED BY: l
~
DATE REVIEWED: l , l REMARKS: b i I Page 1 of 5 HNP-4827 R02 l ~ I FIGURE 4 Page 1 of 5 set i t - _ . - - - , . _ -
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See Title Page 12 of 15 _ DATA PACKAGE 2 Data Sheet 1 saunatoceng Teae. - Page ed Oate EEPCEAIE RATE AoS $3PERAIE DEASfBWreff f)ATA FUIst
............ .. ...... .. . ... ....- ---- .......... ~
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CGG1TIG6 ACTItse
- 84. la. Peteessum sedade quis recommeended. **Lacatian.to, setter.
Esp'esure este 25 sft/he and redtened6ne 468 Il ese a s not kneenn. unless directed ethecessee er Dese male moeter, daeostaess. Accessment stonegement. eastence. esed s6yne, tenamnets. Deer e*e. ets. da. Total eveesues 100 est. #a. Cantact Dese Assessment stenagement
- eeed advase.
l D. Total espesure 3 A. D. Evetuataan recommended, unless
. dieetted othecessee er Dese Assessment management.
l 1 .. v.t.: es,eeue. et A. e. e...u.t..n .end.t.e,. .nt.., o.ee
- assess.ent mer.,e.ent.
i l 8A33 anrtsee espesuco este seestae e* egual to at spine teeseedless es ese attawatyp. Dese Assessment sieneemment must to tentacted. t a e gestee se a male P e Sample Posnt 43,33 4 1 l l Page 2 of 5 HNP-4827 R02 l s
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FIGURE 4 Page 2 of 5 g set
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- 2
-. Georgia Power d .. e See Title Pace 13 of 15
~ DATA PACKAGE 2
. Data Sheet 2 OFFSITE EMEPGENCY MONITORING TEAM Team Date-
-Time entering plume Time Exiting Plume Plume Stay Time Sample: Location Sample Time Cn Sample Time Off Flow Rate: LPM Sampler Type 3er141 Number GROSS AIRBORNE ACTIVITY (Glass Fiber Filter)
(Sample + background CPM) CPM (Background CPM) CPM (Sample + background CPM)-(background CPM)= Corrected CPM CPM (net)* Prom Figure 1 particulate airborne concentratien= pei/cc** . Instrument Type Serial Number . IODINE AIRBORNE ACTIVITY (AgX Filter) (Sample + background CPM) CPM (Background CPM) (Sample + backy ei.r.d CPM)-(Background CPM)= Corrected CPM CPM (net)* From Figure 2 Iodine Airborne concentration = pei/cc'* From Data Sheet 3 Thyroid Dose Rate cr/hr Instrument Type Serial Number COUNT / DOSE RATE SURVEY Count / dose rate while a transit CPM Mr/hr Count rate 6 waist level CPM Count rate e 2* from ground (window facing ground) CPM Dose rate e wai,st level Mr/hr Dose rate e 2' from ground Mr/hr Instrument type Serial Number Instrument type Serial Number Page 3 of $
!!NP-4 927 R02 s
FIGURE 4 Page 3 of 5 y . ggged set W-
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- 2
- o. . Georgia Power A ..
See Title Page 14 of 15 DATA PACKAGE 2 (CONT) Data Sheet 2 OFFSITE EMERGENCY MONITORING TEAM PERSONNEL DOSIMETRY *** Time , Team member Dose at Team member Dose er Team member Dose ar-Team member Dose er SAMPLES COLLECTED Direct radiation TLD's Milk Vegetation Well Water Soil Drinking Water from surface source t Other (specify) Other (specify) ,
- Note: If SAM-2 used record CPM (net) as instrument reading. ,
" Note: If activity (CPM), flow rate (LPM), or sample times (min) are different from information on Figures 1 & 2, use Data Sheet 3 for calculations and record results on Data Sheet 2 (pci/ce).
*' Note: Read and record personnel doseimtry at least one time while at each sample location. (More frequently if does rates are high).
I i l i Page 4 of 5 HNP-4827 R02 s i . FIGURE 4 Page 4 of 5 ,
.- mened 80 9;. ., }. '
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HNP- d a 27 . SCO Tit 10 PCgo a<v+oa =o 2 o-. Georgia Power d ..om See Title Paaa iq np -3q
. DATA PACKAGE 2 Data Sheet 3 ENVIRONMENTAL AIRBORNE ACTIVITY CALCULATION FORM
- 1. Net Particulate (CPM) (from Data Sheet 2)
- 2. Net Iodine (CPM) (from Data Sheet 2)
- 3. Sample time min. (from Data Sheet 2)
- 4. Flow rate LPM (from Data Sheet 2) s Particulate
- 5. Gross Airborne Concentration =
Particulate ( CPM (net) (4.5E-9) =
------------------------- = pel/cc .
( LPM) ( min. ) ' . Iodine
.6. Airborne' Concentration =
Iodine ( CPM (net) (4.5E-8)
------------------------- = pei/cc
( LPM) ( min.) -
- 7. Thyroid Dose Rate =
(line 5 Sci /cc) x (1.85E+9 mr/hr/pci/cc) = mr/hr s .
*If a SAM-2 is used the graphs are not usable. The formula following must be used:
(Net CPM) (1.5 E-9)
-------------------- for charcoal cartridge (volume ,in liters) l (Net CPM) (1.58 E-9)
-------------------- for silver zeolite
-(volume in liters)
Page 5 of 5 HNP-4827 R02 s FIGURE 4 Page 5 of_5 get
L w, .. ,
- GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PROCEDURE Determination.of the Extent Of Core Damace Under-Accident Conditions-
. PROCEDURE TITLE HPF-4848 PROCEDURE NUMBER .
Lab RESPONSIBLE SECTION . SAFETY RELATED ( X) NON-SAFETY RELATED ( ) APPROVED APPROVED - REV. DESCRIPTION DEPT. PLANT DATE* HEAD MANAGER . O New Procedure 2 ._ ___ _
. I I 8,3.
1
. _ _Pa_9.e. _s_ .3_t_h_r_u_6_ _ _. _____ _ _ __ _ ______'_. ._______ _______. . _Al_L &_
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t .______ . r i I f . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ..________ i l _ -____4.w . _ _ _ l . _.. _ _ _ _ _ _ . _ _ . . _ . r I i 1 ( '.
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[> t mensel Set I t -- . . t
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. PROCEDURE DEUTGION REGUCAT PROCECURE NO. HNP- Mf [ _ _ _
SHEET 1 OF / Revision No.__ _ O
~ ~
S. S.EG_y$hIID_hS~['[ [.,~[ ~_,.~[ __ _ _Ogf[d[@[5 [ 5I5h_5[hdh55L
~
- Date:
Name: , Date: [ - g f' /6-b~[] s REVISION G ANGES kOCE OF CF ERATION GR ( WNoINTENT AS DESCRICED IN FSAR: ( ) Yes CHANGE INVOLVES: ( M either ( ) An unreviewed Safety Question ( ) Tech. Specs. (See tiack for Safety Evaluation if required). PRESErlT STATUS: Safety Related ([ Non-Safety Related ( ) The above Safety /Non-SafC y Status has changed ( ) Yes to _
~ -
Attach marked up copy of procedure to this form. , REAGON FOR REGUEST: r>hr gd 01'47 N fy;f ./ L'. A/ #[ _ D' b'Y* ? 7 A2'.' --
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_ _ _ _ _ _ . _ = - =-_ -- DESCRIPTICN OF CHANGES: ], hWg [ 'o d_ _ f[- .J
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.riF.NOS APPROVAL; (j,/)Ves ( )No y .
PRB Secretary 23 -/88 ,s__fii J_g3___-- Date PRB Number HNP-9
~
- menest set
- - - - -- .. .. . . ... .. .... .\
- - - - - - - _ _ _ _ - - - - - _ _____ .J
QAEETV EVAlyAI,I,QN . . . . _ _ . _ _ . . _ _ . . . _ . . . . . ThhI.gygion does not constitute _an unre_vidwed safety -- question as explained bf.12L_.._i _
- 1. Tb.L.R_ro_b.a_b.i.l..i_t_y of occurrence and the consequences _o_f an ac.cident
_ _ _ _ or _ mg.lfung.tj.g.n._qf equipment _important to safety _,are not increased above tbg3fe_ anal.yzed in_ the FSAR due to this revision because the revision p,qeJ_ng.t cha_nge'the purpose o tyerformance of the +gatom.py d ,; _ _ , V r w b _ i*t..:b2 _ C S E :&...h$a _.R.1 lJ n _c_.gy & a g,,___
-- _ _ P
__ __.V t' _4.2..G. ' $w b'db_V -= L-The.possibi.lity of an acci.de.nt or ma_l_f_ unction of a different type than i
.an_al.y_ze__d in the_ FSAR does not r.e_s.u.lt from this revision because the
""*-% ht5 J n t.G _Etir.2f.@_ d la v 5 N $ 93 h^f0 N th9
.,_.-___. h &_m e of_Ryuee.de w - A'r w-c- .--
_ _ _ A _< bl .2 ,NL s2fy.i_3 Dn _ i L.Jhe margin _,of saf_ety._as defined in the Technical Specifications is l . reduce _d due to this revision because the revision does not change . . _ _ _ __..__.._.no_t L __.._ __...a.n.y_1.imited safet.y_sys_t_em settings which would allow a safety limit 9 i' to be exceeded o_r allow a limiting condition for operations to be p !- exceeded as stated in Technical Specifications. --- HNP-9 menest set
-. . < - E. l. Hatch 'Nucirr Picnt a===am HNP-4848 ff:
1;. 'SCO Titlo'Pcg3 uv*moc Georgia Pbwer d .. See Title Page 1 of 11 j DETERMINATION OF THE EXTENT :
~ OF CORE DAMAGE UNDER ACCIDENT COFDITIONS A. . PURPOSE. ,
~
'To provide' instructions for determining the extent of core. damage t
- under accident conditions.
B .- REFERENCES-NEDO-22215 ' Procedures for the Determination of the Extent of Core Damage Under Accident Conditions" by C. C. Lin t j .C. SAFETY l Observe good radiation protection practices when handling samples to minimize personnel exposure. - D.. PROCEDURE- . Obtain a reactor water sample and a drywell atmcaphere sample by using the installed' Post Accident-Sampling System (PASS). . Determine the corrected activity concentration in micro-curies per gm (uci/gm) decay corrected back to time of reactor
' shutdown. This correction can.be done by entering the time of
.the. reactor' shutdown into the computer for the sampling time.
Det' ermine the corrected concentrations of the indicator isotopes I-131, Cs-137,-Xe-133, and Kr-85. Multiply the concentrations of I-131 and Cs-137 that are in the reactor wateriby 1.22. Multiply t the Xe-133 and Kr-85 in the drywell atmosphere sample by 0.786 ! .for Unit I and 0.795 for Unit II. After multiplication, the i i resulting concentrations.are the' normalized concentrations and j can be compared to the charts developed by General Electric and ' . included'in this procedure as Figures 1 through 4. Any damage to the fuel in.the core can be determined directly from the graphs by reading percent ' of damage versus corrected concentration in ;
-uCi/gm or uCi/cc.
E. OTHER FACTORS For further. refinement of the core damage estimate, consult the
, reference in Section B. Some other factors that may be useful in -
determining core damage are summarized as follows.
- 1. Containment Radiation Levels Containment radiation level provides a measure of core damage, because'it is an indication of the inventory of
- a. .
"; amed set
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..i.",.___.,._,..L,- _ ..._,__.._.....__.,,...._,--_....._..m.,._,__.,,_.........._..__,._....,,-m_.~, ,.
- E. l. HLtch Nucic:r PlentL aaoc = =.=o l HNP-4 g 4g Sco' Title.Pego mve m =o o... Georgia Power d .
s See Title Pace 7 og ji l airborne fission products (i.e., noble gases, a' fraction of the halogens, and a much. smaller fraction of the ' 4: particulates) released;from the fuel-to the containment. 1 Containment hydrogen levels,'which-are measurable byLthe PASS or. the containment gas analyzers, provide a measure of
-the, extent of metal-water reaction which, in turn, can be used'to estimate the degree of clad damage. -
- 2. Reactor Vessel Water Level Another significant parameter for the estimation of core damage 'is reactor vessel water ' level.- This parameter is used to.establishLif;there has been an interruption of l adequate core cooling. Significant periods of core L uncovery, as evidenced by reactor vessel water level
- 1. readings, would be an indicatoruof a situation'where core damage is likely. Water ~1evel: measurement would be particularly useful-in distinguishing between bulk core',
damage situations caused by;1oss of adequate cooling to the . I entire core and localized core damage -situations caused by a . flow blockage -in some portion of the core. i- 3.- ' Main Steam Line Monitors There are other parameters-which may provide an_ indication that a core damage event has' occurred. These are main steam line radiation level and reactor vessel pressure. The usefulness of main steam line radiation measurement.is limited because-the main steam line radiation monitors are downstream of the main steam isolation valves (MSIVs) and would be unavailable.following. vessel-isolation.
.4.' Reactor Vessel Pressure Measurement l
, Reactor vescel pressure measurement would provide an , ambiguous indication of core damage, because, although a l high reactor vessel pressure may be indicative of a core l: damage event, there are;many non-degraded core events which could also result in high reactor vessel pressure. 5.
~
j Detection of the Less Volatile Fission Products ,
-There are other measurements besides radionuclide measurements which are obtainable using the PASS which would further aid in estimating core damage. Detection of such elements in the reactor coolant as Sr, Ba, La, and Ru is evidence of fuel melting. These indications could be factored into the final core damage estimate.
l ; mesed set f{l 1 - ._
9- .~om E. l. H;tch Nucl::ar Picnt - ao HNP- 48 48 Sas Title Pags awa> =o
.. Georgia Power A ..
See~ Title Page 3 of 11 ,
- 6. Metal-Water Reaction of Hydrogen in the Conta'inment. -
-The extent of fuel clad damage as evidenced by the extent of metal-water reaction can be estimated by determination of
'he-hydrogen concentration in the containment.
t That concentration is measurable by either the containment hydrogen monitor or by the post accident sampling system. A correlation has been developed which relates containment hydrogen concentration to the percent metal-water reaction
- for Mark I type containments. That correlation is shown in the curve below. Steps 1 and 2 below indicate the method by which Plant Hatch can use the correlation to determine the extent of' clad damage.
Step 1: Obtain containment hydrogen monitor reading, (H),
- in 4. -
- Step 2: Using the curve below, determine the metal-wafer *
'- reaction for the reference plant, NW ref . . i 4 4 m T 4 esmed set
, , - . , - - , , - , , - . - , , , , . . . , .,-nra > , ,,- ,,---.---e,-----~,--,-,--r-+. ,,,,-an.- - -- , e-,-, . ,-n- ,,,--.-,,,w,.-,n-,,
- =om E. l. Hatch Nucl::ar Plcnt axiouat ~o HNP- 4 848 2.awsio so Sc3 Title Pega o.,e Georgia Power d ....
See Title Page 4 of 11 METAL-WATER REACTION OF HYDROGEN CURVE
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i t METAL.- WATER RE ACT1086 assesi set
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u
.~om E. l. Hatch Nucl=r Picnt aaon== =
HNPagag
. See Title P093
.m Georgia Power ...
See Title Page 5 of 11
- 7. Containment Radiation Level Readings ;
'An indication of the extend of core damage is the containment radiation level which is a measure of the inventory of fission products released to the containment.
The purpose of this step is to present that correlation and provide a method whereby Plant Hatch can use the corr' elation-to determine the degree of core damage. The procedure for determination of fraction of fuel
. inventory released to the containment is as follows:
Step 1: Obtain containment radiation monitor reading, (R), in Rem /hr. Step 2: Determine elapsed time from plant shutdown to the containment radiation monitor reading (t) in hours. Step 3: Using the curves below, determine the fuel - - inventory release of airborne radioactivity to the containment in percent. l l l l essesi set l
-~~~
*= vat E. I. Hctch Nuciser Picnt a x t=ar
- HNP- 4 848 Sco Title Pago ' ev'5ca w
.... GeorgiaPower A . a. -
See Title Page 6 of 11 PERCENT OF FUEL INVENTORY AIRBORNE IN THE CONTAINMENT CURVE q 2004 Fuel Inventory = 1004 Nehle Genes
. + 254 2odine
+ Il particulates D
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j # o.cott d ! m' '10" 2 J ' h 67tr]g 2 .J i s 473F10' ) J e $ 6 78r10' 2 J A h 67ti'10 # 4 Time After Shutdown (Hrs) mensel set 1 -
~
-- = *- E.1. Hatch Nucl br Plant aaocio o.
HNP- A A A A ,, Soo Titlo Pago aews.o o
- w. GeorgiaPower A ....
See Title Pace 7 of_33 8.- Application of Other Significant Parameters to Core Damage Estimate As noted previously, procedures have-already been developed shich-provide an. estimate of core damage based on radionuclide measurements. Based on these procedures, an initial assessment of core damage is made. Based on.a clarification provided by the NRC, that assessment would appear in a matrix as follows: Degree of Minor Intermediate Major Degradation ((10%) (104 - 50%) (>50%) No fuel damage t-----------l-----------3 Cladding failure 2 3 4 Fuel Overheat 5 6 7 p Fuel Melt 8 9 . 10 ! As recommended by the NRC, . there are four general classd's of damage and three degrees of damage within each of the * . classes except.for the "no fuel damage" class. Consequently,.there are a total of 10 possible damage assessment categories. For example, Category 3 would be descriptive of the condition where.between 10 and 50 percent of the fuel cladding has failed. Note that the conditions i of more- than one category could exist simultaneously.- The objective of the final core damage assessment procedure is to narros down to the maximum extent possible those categories'which apply to the actual inplant situation.
-s
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See Title Page 8 of 11
~
FIGURE 1 NEDO-22215 w* M t,uft h WPPER RELI A&E Last? SEST ESTrMAtt /
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t
*== E. l. Hatch Nuclear Picnt aaocr=a= =
HNP 4g4g SO3 Titlo PCg3 ""'S'oN * ' o... GeorgiaPower A .... ~o See Title Pace 4 of 11 FIGURE 2 NEDO-22215 Y. *
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- Figure 2
- Relationship between Cs-137 Concentration in the l Primary Coolant (Reactor Water + Pool Water) and the Extent of Core Damage in Reference Plant i
menest set
~
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- > ~ oval E.1. Hatch Nucl cr Plant amocavai ~o ;
HNP- 4848 SOO TitlO Pcg3 mewsio i.o
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See Title Page 10 of 11 FIGURE 3 NEDO-22215 Y.
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,I r % Futt ut LTD3wn Figure 3: Relationship between Xe-133 Concentration in the Containment Gas (Drywell + Torus Gas) and the Extent of Core Damage in Reference Plant menest set cr~m
hvat E. l. H tch Nucl:cr Picnt 1 aoce=ai ~o HNP- a g a n Sco Title PEga
.... Georgia Power P. o 1 See Title Pace 11 of 11 FIGURE 4 NEDO-22215
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l Figure 4: Relationship between Kr-85 Concentration in the Containment Gas (Drywell + Torus Gas) and the Extent of Core Damage in Reference Plant menest set
U
. GEORGIA POWER COPFANY HATCH NUCLEAR PLANT PROCEDURE
___Testina Of Emgr,_2ency qmgmunication System _,
- PROCEDURE TITLE
~
bt@-48EO . PROCEDURE PA. PEER Lab RESPONSIBLE SECTION SAFETY RELATED ( X) NON-SAFETY RELATED ( ) p.____.____________________. . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ,._______. APPROVED APPROVED REV. DESCRIPTION DEPT. PLANT DATE FEAD MANAGER . W
/
Pages 1, 3, 4 & 5 . 3
. _ _ _ _ _[ _g ____ _. .g/g . ___.
_g _ _ _ '_ _ y_.((_ Q 4
. _Pages
_ _ _ _ _1_ _ _ _3_,_ 5_ _&_6_ _ _ _. __ ._ _ _ __. _ . . __5. _ _ _ . 2.n n l,_1_s_ b_ _ _ _ _ _ _ _ . . _ . . _ _. ._ ___ ____o____. W 3 f_L_. .___
~
6
.P_a am e _s_ _1 _2 ,_ _5_6_ _&_ _8_1_0_ _ _ . ._.P uQ_' - b_ ,- _ ___ _ [ P 6J' Pages 1 3 and 7 9 %
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S. iEET 1 CF_1.,_, i e Revision N o ,, ,,,_ _ _ ,,Q, 1 _ _ ,,,,,,,_
- d. ._- g ggEngg_gv Date: DEFARTMENT iAD APPROVAL r; .,: a.u Signature:
- Date:
~i xttiv/,hp{ /c-7f.3 QQ) 10 tol8)
.. 2--_.------ . ----
a p _-- !Effl23 > FEVISION (*.HANGES MODE Oc CPERATION OR INTENT AS DESCRIBED IN FSAR: t 1 ( ) Yes ( X) Ne i CHANGE INVr) LUES: ( ) An uneeviewert Safety Guestion ( ) Tech. Specs, (K ) Neither (See t.a c k for Safety Evaluation if required). PREEENT e,TATUS: Safety Related (,% ) Non-Safety Related ( ) The above. Safety /Non-Safety Status has changed ( ) Yes to ___'_. _ Attach marked up copy of procedure to this form. REASON FOR REGUEST: YI J, ___We do U e_M f / Nuen 0 6 dN.1 xeY t .n.db r(gf/G_&'._ a & _ dox'Zp ~ 4, s in '. 'n : s Lee AQgina eoc0 s I
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i PRS Secretary 9 3 -l8'? _ so///.r.7 .-= - NRB Number 'Dafe HrJ'-9 l l e i < v e at
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. - =_____________
is ion of t_h_i_s procedure does . sot constitute a n_u_n r_e v i_e_we_d _s a _________ f._e_ty _,T_h e__r_e_v_ - _m.u;iao as_tulaint4 balw___- - L__t.hs nuhabuity_ntsssuunss_ansLibs ssnssausnas sI_an ass _1.stsat_._______ _______a ouneuon.st-mimnt_imuun.us_che_acss2_au_ sat.insausst.___ ______auaxa_thase.anaima..ia_the_tsa_aus_ta thes- chanaan..hasauu_s 7~ BirTrif s dess..not IMur '- _- n_" y rurry s psrEnt A ypc 1 ' f ^ -- _ _-- 9 - _____
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y .. _- i M ;/ier_ 6 __4 ~ tih u__ J h r e nie m,n c v, ,o Anie.s. - e.i a t _ne..rn-4h4,4 ev or..an..accia ac..ar_mauunction no.autmausa ______ j rk* Ie An .dmemt._tAAult fr.cs this_chantre _beeAun__h# _, _ t.u . ., en,172 4 4n
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/ / /
_.d._. h _, ;4n-of sa.fary == daF4na d 4" tha Technical.SgecificRinna -- - : __,.1 nor , A"ced._A"a en *h4c ra'*=4nn harn"ca "ha rev.111ca dces not _,, _ _ % a any 14 ' rad ca f a ry. syste::..ser.e 4 n o wh 4 ch veutd_n11oH_a.J'Ef e.Ly_11$ __ r2 s ., ., -madeA n- *n al'nu a 14-4 ring-conditian_Lu_nacIA11Cn..Is_ha _ _ _ _ _ _ _. m eedeA 5.taind in..TAE.DIdSal J.PsS.ifications
\ _ _ _ _ _ _ _ _ _ . -- _ _ _ _
~
i _ _ _ _ - S - - - - . _-=_ - _- __- -._ - t s _-___.e.m_e.__..-__s_m__m.______e=____-_i.em_ _ HNP-9 useast set O .
. - E. l. H:tch Nucl:2r Pl:nt ocio= ~o HNP.4860 SO3 Titic Pcga ev m mo.
' 7
.... Georgia Power d .
See Title Page 1 of 9 TESTING OF EMERGENCY COMMUNICATION SYSTEM A. PURP6SE
.To provide a procedure for testing emergency communications between the Technical Support ~ Center (TSC), Emergency Operations Facility (EOF), Control Room, State Civil Defense (CD), (i".e.,
Appling County Sheriff's office), H.P. office, and Shift Supervisor's office. B. TEST SCHEDULE
- 1. All communication systems will be tested at least once a month. Tests will be conducted in the 2nd week of each month.
^
C. TEST PROCEDURE
- 1. H.P. Technician picks up the phone and identifies himself -
and states "this is a test of the Plant Hatch Communication Systems" Refer to Table 1 for specific test procedure on each phone.
- 2. Each party checks the quality of reception.
- 3. If any line or phone is noted to be lacking in reception quality, the technician will record the problem using the Communications Repair Form (Figure 2). Also note Figure 2 being completed in column 4 of Data Package 1.
- 4. Test is terminated and results are recorded in Data Package l
- 1. The H.P. Technician performing the test puts his initials on the Data Package in the " Initials" column.
- 5. The~HP Supervisor in charge of communication will assign a l tracer number to each Communication Repair Form. He will also maintain a log of these forms using the Communication Repair L'og (Figure 1).
D. CORRECTIVE ACTION TO BE COMPLETED BY COMMUNICATT.ON PERSONNEL l. l 1. Necessary corrective action is initiated through the L supervisor in charge of communication as and when necessary through the use of Figure 2. l
- 2. Return filled out Communication Repair Forms to the HP Supervisor in charge of communications when corrective action has been completed.
i s amed set
+ ,,
,,-,.y,
* . = *' E.1. Hatch Nucl:ar Picnt = = = = =
HNP-4860 Sco Tit 10 POgo "ve> =o 7 Georgia Power A See Title Page 2 of 9 TA_BLE 1 EMERGENCY COMMUNICATION SYSTEM OUTLINE Location Phone Dedicated As: Testing Procedure Control Room EOF TSC OSC SIM GPGO System Operator Press 480 nx #1 on switch-board Dial 01 for system operator Division Operator Press 480 nx #2 on switch-board Dial 15 for division operator ENN See HNP-4861 - GEMA *
- OSC Con. Rm TSC EOF SIM
. NOTE
- Remove receiver and phone will ring at dedicated The security radio to location. Check one phone the Appling County at each location as all Sheriff's office will multiple line sets are be tested by the Security extensions.
Department. This phone is in the Control Room. O e s t i<
" ( .g.
momed set q.mL;; i_ . ..
- E. l. Hatch Nucl:ar Plcnt ,aoa== =
HNP-4860 "Ev'**
- Sco Titlo Pcg3 7
Georgia Power A . . . . See Title Pace 3 of 9 TABLE 1 (CONT) EMERGENCY COMMUNICATION SYSTEM OUTLINE Location Phone Dedicated As: Testing Procedure EOF Con . Rm. TSC OSC SIM GPGO ENN See HNP-4861 NRC Hotline E.N.S.
- NRC Hotline H.P.N. Dial 22 for headquarters Dial 23 for Regional Office Bexley line 367-7864 Dial plant's Baxley Ext.
(367-7781) TSC Con. Rm. EOF OSC SIM GPGO ENN See HNP-4861 NRC Hotline E.N.S.
- Baxley line (367-7997) Dial plant's Baxley Ext. ,
(367-7781) Baxley line (367-7998) Dial plant's Baxley Ext. (367-7781)
- Remove receiver and phone will ring at dedicated location. Check one phone at each location as all multiple line sets are
. extensions.
s a menest set
u . a = at E. I. H:tch Nucl:Cr Plant aa x io = = HNP-4 860 asesia w
. Sco Title PCgo 7
.... Georgia Power . . . .
see Title Pace 4 of 9 FIGURE-1 EMERCENCY C000fDNICATIOW REPAIR LOG _ TRACER DISCOVERY L.A. COIELETION- REMARKS NUMBER DATE DATE
- e e
O 4 l
.e.
en HNP-4860 R07 named set 4 .- e
c o { E.1. H tch Nucl: r Plcnt a== ra= = = == =- HNP- 4350 SOO TitlG PCgo mensio o 7
....- Georgia Power d .. .
See Title Page 5 of 9 FIGURE 2 EMEMENCY COMfUNICATIONS REFAIR FORM TRACER INTISEE DAIK TO: LOCATION OF F501E FRONE NUMBER DESCRIPTION OF F208LEM:
/
SIGNED / DATE DESCRIPTION OF CORRECTIVE .WIION: l' l l
- CORRECTIVE ACTION COMPLETED /
SIGNED / DATE RETURN TO H.F. SUPERVISOR 1AIEN COMPLETED. e o RN*-4860 R07
, ze mamasi set
'. Om E. I. H tch Nucl:Cr Pir.nt ===a**
HNr*4860 REveSiON NO-SCO Titlo P0go DATE Georeia y Power -- See Title Pace 6 of 9 PROCEDURE DATA PACEAGE L DOCU)RNT NO: HNP-4860-1 SERIAL NO: R01-MPL Nra RTYPE:_ C15.03 EREF: TOTAL SHEETS: 4 . FREQUENCY: COMPLETED BY: DATE COMPLETED: l l I HAVE REVIEWED THIS DATA PACEACE FOR COMPLETENESS AND AGAINST ACCEPTANCE CRITERIA IN ACCORDANCE WITH HNP-830. ACCEPTABLE UNACCEPTABLE
~
l REVIEWED BY: ? DATE REVIEWED: REMARES: Page 1 of & HNP-4860 R07 FIGURE 3 Page 1 of 4 , , . 1 EEE8d 88I 1 , ,- .
p aa ovai. E.1. H*tch Nucl;;r Plcnt **=a= HNP4860 SO3 TitlO PC.g3 nev. o o o... GeorgiaPower A .m .
.See' Title Page 7 of 9
. DATA PACKAGE 1
. EISRCENCY TELEPHONE CHECE LOCATION: DATE FIGURE 2 INIT.
- CONTROL ROOM FILLED OUT EOF TSC OSC SIM GeorCia Power General Office System Operator ,
Division Operator ENN CEMA
~LOCATIGN OSC Con. Rs.
TSC EOF l SIM l
- Refer to page 7 for remote locations of ENN and alternate phone l numbers.
s Page 2 of 4 HNP-4860 R07 FIGURE 3 Page 2 of 4 mensel set m . _ - _ . - .
c u e at E.1. H:tch Nucl: r Plcnt ax==a= = HNP-486 C SCO Titlo PCgo neymou o. 7 oa,t Georgia Power d o. See Title Page 8 of 9
~
DATA PACKAGE 1 E'ARGENCY TELEPHONE CHECE
' LOCATION: DATE TIGURE 2 INIT. -
EOF - FILLED OUT Cont. Ra. TSC OSC SIM Ceorgia Power General Office ENN . NRC Hotline ENS _ NRC HPN 22 Hot Line 23 Barley Line 367-7864
- LOCATION:
-TSC Con. Ra.
EOF CSC l ! SIM l Georgia Power Ceneral Office l ENN NRC Hotline ENS Baxley Line 367-7997 l- Baxley Line 367-7998
- Refer to page 7 for remote locations of ENN and alternate phone numbers.
I Page 3 of 4 l ' HNP-4860 R07 i l PIGURE 3 l Page 3 of 4
- mesesi set L- _-_ }
e- ,
'* *, om E. l. H tch NucI r PI:nt aa===an ao HNP-4 860 aavision o SO3 Titlo Pcga 7
om Georgia Power d ,ao. Sea Title Pace 9 of 9 DATA PACEACE 1 (CONT) EOF to FIGURE 2
- REMOTE LOCATIONS _OF EIN DATE NAM FILLED OUT INIT.
G.E.M.A. (Atlanta) (404) 656-6401 * -. Realey Police Dept. , (912) 367-2403
- Appling County C.D.
(912) 367-4698
- Appling County Sheriff (912) 367-2086
- Toombs County Sheriff (912) 526-6350
- Hazelhurst Police Dept.
(912) 375-3311
- Reidsville Police Dept.
, (912) 557-4340 *
'CONTROI. 200M TO FIGURE 2 *
- REMOTE LOCATIONS OF EIGI DATE NAME FILLED OUT INIT. . .
G.E.M.A. (Atlanta) - (404) 656-6401
- Baxley Police Dept.
(912) 367-2403
- Appling County C.D.
(912) 367-4698
- Appling County Sheriff (912) 367-2086
- Tooebe County Sherif f (912) 526-6350
- Hazelhurst Police Dept.
(912) 375-3311
- Reideville Police Dept.
(912) 557-4340
- l l
, TSC To FIGURE 2
- REMOTE LOCATIONS OF ENN DATE NAME FILLED OUT INIT.
!- G.E.M.A. (Atlanta) i (404) 656-6401
- Baxley Police Dept.
(9121367-2403* l Appling County C .. l (912) 367-4698 * ( Appling County Sheriff
- (912) 367-2086
- r Tooabe County Sheriff l (912) 526-6350 *
! Hazelhurst Police Dept. (912) 375-3311
- Reidsville Police Dept.
t (912) 557-4340 *
- These Phone Numbers are to be called only if no response is obtained over the ENN.
Page 4 of 4 HNP-4860 R07 i , FIGURE 3 l Page 4 of 4 mesed Set l _}}