Text

Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures HNP-4852 Re Offsite Dose Estimations & HNP-4420 Re Notification of Unusual Event
	ML20028C008
Person / Time
Site:	Hatch
Issue date:	12/08/1982
From:	Sorrell E; GEORGIA POWER CO.
To:	;
Shared Package
ML20028C006	List: ML20028C005; ML20028C008; PM-82-129, Forwards Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures HNP-4852 Re Offsite Dose Estimations & HNP-4420 Re Notification of Unusual Event;
References
	PROC-821208-01, NUDOCS 8301050228
	Download: ML20028C008 (199)
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L ^ I. GEORGIA POWER COMPANY s IIATCit NUCLEAR PLANT 3 PROCEDURE OH Site Dnnn Estimations PROCEDUiiE~T55LE ~ HNP-4R52 PROCEDURE NUMBER RESPUNEIUL5 5ECTION Health Phvnics SAFETY RELATED*( X ) .NON-SAFEThRELATED-( ) .._._______.p_____________.t___ APPROVED APPROVI.D REV. DESCRIPTION DEPT. PLANT DATE HEAD f4ANAGER L_____ 1 General Revision _ _ _ A_ e.-.-- _ _ _ _ _.. W_ _ _ _ _ _4_ s, ut _1_ _.. _/ Z_L _ _ _. / 2 G ral R .J. /,h,2 . _ _ _e n e _ _ _ _ _e _v i _s _i o _n _ _ _. g s_ _ _ _ _ _ _. Pages 1-8 11, 13 f__g m__ __g'..p"/_gz... 3 ___r_____. 3 g_ . _ _Y_ _ _v._Q _ g}^Liy_ _..__ _M_ _ h_a_ _I.l.C_I)_ _ _..1 L.2.9. _ V - _ _ -.4_ _ _. _ Den.cza.1_ B c.vis. inn _ _ _. p____... _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _.. _., _ _ _ _ _ _ _ _ _ _ _ _.__ _ _ _ _ _ _ _ _ _ _. _ _ _.. ______. ,._ - _ _ __,a _ _ _.. _ _ _ _ _ _ - _ = _ _.._= = _ =. = =. -..... - , n. =. _. _. ______7A_ _. / s. ...a__________..______-- N '[ Maene Only sNe-o S MANUAL SET I a

,,,,,s. ..... ~.. i g6 i,- CR..ocrn_t t_1E_Rf_A.'..T.G.I.ON GI ti.t_c.'.CY PRDCCDURE N'O. ft.*P _Y[_ b r. Revinion No._*,,,_3.___ _ _ _l DFP ARTi".SNT t-tFr O APPun'.'. a ._______-__R_peo. g.-e.T rp n_y . - - - - - - - - - - - - - - - - - - - - - - - - - - = _. - - _ _ - __u---- Naw; Datn; SAgnature* Date: .-),,2. Y O. { . U _ _u.;L _v_a;(' }. 2. - f {.2._. .-* m-_ -,. _ - - REVISION CthNGED MOCE OF. OPERATION OR INTENT AS DEGCRIDEO JN FSAR: ( ) Yes ( c -P No s

CHANGE INVOL.VES:

( ) An unreviewed Sefety Guestion ( ) Te ch.'Sp e c s. (3-P Neither - (See bacic for Saf ety Evaluation 10 required). Safety Related (

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( ) ) Yes-( c-f' No, Safety /Non-safety Status ChanDe ( . Attach marited up copy of procedure to this f,orm. REASON FOR REGUEST Y !~ F A. -su;;f'.- L.1$i Q.}L'1%c.M- -Q 'd _J , w ; y b_ n-ts.aa.~ A n.1aa.cd $ hd d .[c_ S. . Ss01:. eu 0 a= 0 m - ~ L .a._.e w p p se f s9 ~ D~ rlNY l)) e, --' ' ~7' ~ -_ _m, ~ _ ~ _ - - - ~ ~ - - _g. f l I-l 1 = PRR RECOBW NDG.W RL.V.'.L;.k')Yus ( )No I .s Pitu Gs retary l .Y. ' f.3.2}0 /.1 ~ ~1-/.).-. Date PRl3 Nt'mt,m- '.g ' s *, * '.x. i m.. u. u.~ ~ I.gy p.g c r. e ,.s f e p ~ ~ ' * * *.. *. *. gg -~ t

SA..FE T.Y_..E..*'.,.*/.J U..' T..1.PH 5fet -.e.s-o_t_ con.s..t..i.tu te a..n unreview d_ e.- L ----_- -- do n d T.he. r_evisi.o.n o_f this proce.u.re question as explaine -_ --------- ---- _d b el ow.--_--------------------------------_--ide_n_t___--, ccurrgngs._and_ t.h.s s.q.ns.qnu_en_ces.o. f an acc_ 1 ilit f -. 1.he pro _b.a..b. _y o.. .g --_. _

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._.,..~...*.-...es E. l. Hatch Nuclear Plant e.mn> m ~ %.m.. ItNI8 411'*2R ~T~pc eoigm i ower me8 0.og 10 ..-.,.-~j ,' g see Tiile Paga l 1 of wrM7 _ nee T.u i e enni. ggg_gnr nosr gnTn.it.ngug UDIC ' Tliir. p' roc,e< jure supe r cedes HNP-4C.50 Revisi on.2..,,,J A., Pl.tRPOS15 To describe methodn which may be uned for estimating off site cond'itions at Plant Hatch. radiation dose during emerDaticy D. REFFRENCE Manual bF Proinctive Action Guiden and Protective Actionn 1. for Nuclear Incidents, E.P.A. 2. HNP-4854 3. Reg. Guide 1.145

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Re,g. Guide 1.109, Rev. 1 T 5, Worl<boott of Atmospheric Dispersion Estimateb, E.P.A. ~~s, C. DISCUSF, ION Thin procedure details methods which may be used in the event of an emerDency situation to evaluate radiological conditions in the environment in order to annint plant personnel and r;csponsible agencies (State Dept. of Natural Recources, GEMA, etc.) in mr.hing control the hazard to ..... appropriate decisionn to evaluate and MeteoroloDical data will be passed public health and safety. along to the Gtate Representatives as received but their 34o estimatos of thyroid dosos are expected to be approximately$,3OO timen higher due to tho' differencen in iodine / noble gas ratio. =. =ng-- -..u [ns ='Eq.nd F utili'z e me te o rol og i chi and p lant relense data, ct to\\ cal culateg f*Iiin e x p 6ntyre s. Gections,G, H, an< ?f,use f i c.i d o riot smate ng with graph,n ffom referenge D.,1j ', mp!.,1,arements jr jor.o.x / x .e ~ 's'bwad o% R. G 4.s.ig t dJewsI E " wld s 'The_ mdkoMo i R Gd 6.

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e ~ bw.. Y., N.'-l. E.1. HATCH NUCLEAR PLANT , ~. ~ 4 q. GeorgiaPower os ~g g y W... . ~~' y - L r ' # 'D. Estimation of Offsite Exposures N'OTE The minicomputer system is designed to take various plant > and meteoro- , logical dat'a as 1.nput and calculate of f site dos'e ratos, c.umulative doses, and tabulate these for cach sector at 1, 2, 5 and>10 mile Protective Action Recommendations are also tabulated ~.distanecc. .using the criteria of IINP-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 j field monitoring data is also provided. 1. Set up the minicomputer per checklist No. 1. 2. Enter initial data as requested by the computer. When the " verification run" is complete, assuv e the values match 3. those on checklist No. 1. If they do not match, repeat system setup f ~ using an alternate disk. This information 4. Enter radiation monitor or sample data as requested. is obtained from a communicator / recorder. ?!cteorological data is also provided by the communicator / recorder. s e ~ 5. Three copies of printout are available for use by: 1. Status Board Recorder - and subsequent Posting 2. Dose Assessment Ifanager 3. Field Team Coordinator 4 All data printouts.should be reviewed and initialed by the Dose 6. Assessment Manager.. Periodically perform verification calculations using data from Tables 7. For the appropriate stability a in Appendix A of this procedure. -,iid d ist56cd,- dditiply thecuries'per-second erclease._.____.____..._ clana,_.y3p3_ speed 1 rate by the Table f aEor to citEEte dose rate'.7owpare' virtr printout ~ Inconsistencies must be reported to the Dose Assessment Manager. datn. \\ l 8. Provide all data and Protective Action Recommendations to. State (DNR/EPD) personnel. = NOTE Protective Action Recommendations are based on. cumulative doses plus i Longer projections may be made by simply a tuo hour projection. multiplying the calculated dose ra.tes by the projections time desired. Exposure estimates for field monitoring teams can be made by periodically j 4 9. checking pocket donimcters (whole body) and multiplying stay times by meannecd radioiodine concentrattuns uuing the following conversion f actor: ' ', t rmid) = 1.85 C+9 yCf/cc (I-131) f f).h,,mspm/hrTth)v m.. <.. i. w nri p t,I(d H h QRT I t. Im M n --i _ _2. 7 n

. ~, ~. ~ HlO d3dC E. l. HATCH NUCLEAR PLANT kIE 'b' AO d 6 GeorS a Power A -e ~ cp o,9 i 3 u j Checklist No. 1 .8 '\\ - l . Setup of Dose Calculation Minicomputer e y a \\ !koveComputerConsoleandPrintertoDoseAssessment' Area. 1. Plug both units to 120 A.C. power., Connect printer to computer. 1 2. Turn Printer on (suitch is in back) and press reset button. ~ Tur.n Computer on (switch is on right hand side)'. t.! ' 3.- 4. Insert Diskette and close door. Red light should go on. 5. When red light goes off', press eset but' ton. j,.

NOTE *

\\ Hold at this point until all data needed for initial calculation is available - i.e. source term and meccorology data. -l 6. Type in Date and Time (24 hour clock) as requested and press I Enter key. 7. Type in the following sequence: '(i). Basic (enter key) , ~ 3-(ii) (cnter key) (iii) (enter key) ~ . iv) LOAD " HATCH / PAG" (enter key) (. 8. Type in information as requested. ~ Compareverificationrunwiththefollohgvalues: 9. l - - - m -,_ _ m 9 g-Whole Body Thyroid , Distance 1 mile 1225 3484 ~ 2 miles 503 1431 5 miles 108 306 10 miles 41 117 i NOTE f if the verification run valuca do no match those above, rc.- ern t to step 4 and use an nit'crnate diskette. 9 Referente*0iily ~ ~ ~ - - - ~ " " ~- ~ MMUAl. SET. - i. I

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i i. GEORGIA POWER COMPANY 4 + HATCH NUCLEAR PLANT 1 PROCEDURE Emerg ~rncv Eguinment__Invnntnrv bbCEDURE TITLE HNP-4892 ?- PROCEDURE NUMBER 'L n b RESPONSIDLE SECTION CAFETY RELATED ( X ) ,NON-SAFETY'RELATED ( ) APPROVED APPROVED REV. DESCRIPTION DEPT. PLANT DATE HEAD MANfGER 2 General Revision M _n_.. _- J_ _ As /L. a ._f_1 _( J_-_ _r.,,- _. _ _.~.. / .f Pa 1, 2, 4, 5, 7, -3. _ ges ,, f _- W_ _ _ - _, . S. & f_ __. g M__ m__,[r._t,,s._ _ 0 &.11.. 3 9_ _ _ - _ _ j_ _ > [.Y~ crg. _/_/ Cal ._12 7_g)_ 4_j_ [. p. - _ _4_ - _._G_e n e _r a_l _R_e_v_i_s_i_o.n. _ - _ - ( s -.. ~ _ _ -.=.=.:=.==_==_=.:- = ::=_ _ _ _ :. = _ - - _ _.: = _ _ _ _ _ _ _ _ _ _ _ _ _ _.._______- a \\h I HNP-9 Ie/e MMWAL SET ( a ....... e.q., f,,. ~._-_-

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1. '. g

,_.,2. t r g REVISICrt CH."?:CES MCCE OF.CPERATION 03 INTENT n:3 DESCRIDED IN FSAR: l ( )gYes ( No i 1 l

CHANGE INVOtNES:-

( ) An unreviewed Sr.foty.Guestion (- ) Tech. Specs. ) Neither i (See bacic f or Sa f e.ty EvaJ ustion 10 requi red). l .1 ._N.~on-S..a f et y R. e.i n..t..e d. .(.. -.)-... i, ...S. a f ety R.e l a t e d ( ) ~. .....-:....s; '..n..w. ':....: w :.... .u........:. i...: u.. ..s a v.:.~..,........... .- i . ( -) Yes .I 1 -( 1 No 4 Safety /Non-safety Status C.hange v-g v-c...,,.. F .~ ] -','.. Atta ch marlied up copy of procedure to this.. orm. 4 1,g_cy g -h. } c h-._ e REASON F63 REQUEST - M,.... f.... sjo <s n. /, /.m s.ry 1 t _r,_ lU L M s i. g-e g_ g.% m /s / % g. AnAdz. Aye_._ j .i s ~~%.Ln. wCc i entr.w/.mu _ ,.) /.' i ? , ' / 4 %Ed_ dec.a.bn s b y.2~ Lt'Deld r/ab cdo,I k _ yes_dyb_pL /JeAd_ @t,h dushe A%._ej_<.k_ _ 'k m.,L y _dn um.b b.m. r! 'n'tSQ ac ': ep.mN 6,. O d.pa- _ !,..... __p.u,,/ -u.J ial A., 6J n /7a_M_ k._ _.e f s. s s,, ir i % d sc. i.,_ n__ e_&.& M----._- l :I. ~ h Asp.t a #.2._e.s A altzu # y uga_v.d e / 'lb.__._e N A y { m a_Cf.ci.p.sA d .e.,.___ T__iO Pin if o s. f- $_. '.t .. ~ I.. t Pnn bCCOM:trxrc...rvncv5: ; (-ftas d2x_.___ l c r e t., r y ( )No Pl<0 a _ 2.f..l /.f --__.. _--_/_)_h_. f_ _2 [, ~ PRO Nuitsi,tir Datc g.pp.,,.3 'h -T- - ' l,';,~ '.,,.,..".....*...... ~ -.Y " ~ ~ - - N - - f} ~ .s.. ._. a....:.. . -.. ~. _. ..t_, t

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MGA' Mode 401 nir pacit spar . at ler. locations as appropriate see log shoot 13) "t o , ort other emergency items. n I Visitor's Center. telephone - Ext. 2204,. E 1 PROCEDU,.7E - GUARTEPLY Q Open all trunks and suitcases and inventory each dtom. Check portable survey instruments for brotten dgtectors, bad 1. record data . cables, calib_ ration date and battery condition, on proper data sheet. Check flashlights for operation and low volume air somplers for operation. Record inventory results on the appropriate atteched log shoots. -ar. -- R...., y u. 'm., N e, d i o m. check for proper o S_ cat.4-c4n-b'y-~~. - - " ~ ' - another radio at .n: W.fHc..s transmitting c Record Ecsul ts on the at1. acid. Log a y. 3. Che cic visiwr v.tc r SLve.on r' F'+ P ? n4--c i C CC 5 by-~tri'o l s.n g tlw <-ou ir u i racna number 2244 or 2444 4-rom Ui : 'v' 2 ; i tco Conter. y.ccechknce%00iD" - L -A All missing or inoperable items must be replaced or repaired and noted in the REMARKG column before the log sheets are considered complete. The completed log shocts will be permanently (iled in documentation. U.?6 = u-:--.1

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h ii does not . __ _ _i_s _n_ot__r_e_du c_e_d_du e to th.i_s _r_e_v_i_s i on b ecaus_e._t _e_ =- _c_h a._n.c e__a_n.v. l_i m_i _t e d__s_a _f e t_y_s y s_t_e_n_s_e_t_t_i n_a s_wh_.i_c_h_.w a___- =- ~ l _l,.i.n._i t__t_o be excee_d_e_d _or..t.o__a_l_l_ow a__limi tine __c_o_ndi tion fo sa fet** o_c_e.r. a ti o_n_s to_.b._e _e_x c_e _e d_s_'__i s__s_t_a t e_d__i_n _ P . ~... w...,. ......s..r. _______________f 9 ,s...1 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _,_ _ _ _ _,= .p g i<..,c. r H.NP-9 .~. a.w., ., g.. , y,,g.- .... r.:....,....... -....3 ....s..........._....s.......... ....... ~..,.. ~ ~ '[ g i

eaociou v E. l. Hatch Nucl ar Mant ~a= HNP-4420 l ner uo o GeorgiaPower A 5 e Title Page 1 of 7 ( o... See Title Page NOTIFICATION OF UNUSUAL, EVENT A. CLASS DESCRIPTION in process or have occurred which indicate a Unusual events are level of safety of the plant, such potential degradation of theNo releases of radioactive material as those noted in Table 1. requiring offsite response or monitoring are expected unless further degradation of safety systems occurs. B. PURPOSE (1) assure that the first Purpose of offsite notification is to step in any response later found to be necessary has been carried and bring the operating staff to a state of readiness, information and (2) out, provide systematic handling of unusual events (3) decision making. C. PJANT ACTIONS NOTE The Shift Foreman or Shift Supervisor (or higher-in ranking licensed or certified person present) consultation with the STA, if feasible, recognizes and declares that the plant is in a state of The Shift Supervisor emergency of Unusual Event Class. role of Emergency Director until assumes the relieved by the Plant Manager or his designee. Inform State and/or local offsite authorites of the na.ture 1. of the unusual condition within 15 minutes fol'1owing recognition. Augment on-shift resources as needed. 2. 3. Assess and respond. 4 4. Escalate to a more severe class, if appropriate. O,_B, Close out with verbal summary to offsite authorities; 5. followed by written summary within 24 hours. j i f T" MANURL SET ________._____.O____.__________ o

E.1. Hatch Nuclear Plant aaouwat e

== HNP. 4420 aevision no S e Ti.tle Page GeorgiaPower A 2 of 7 See Title Page D. STATE AND/OR LOCAL OFFSITE AUTHORITY ACTIONS 1.' Provide fire or security assistance, if requested. 2. Escalate to a more severe class, if' appropriate. 3. Stand b'y until verbal closeout. i = 16 f

w. \\g#,~.

w s. MANUAL SET } i l

--~ ~

b. l. HatCn Nuclear t'lant a m ova' HNP-4420 esiou ~o Epe Title Page k

4 Georgia Power s 1 ..mo 3 of 7 Gee Title Pace TABLE 1 NOTIFICATION OF UNUSUAL EVENT INITIATING _ CONDITION EGUIPMENT STATUS PARAMETER VALUE

1. ECCS initiated and dis-Auto initiation of.

-146.5 inches or 2 charged to vessel Core spray, or psig drywell pressure RHR (LPCI mode) -146.5 inches or 2 psig drywell pressure

2. Radiological effluent Main Stack and Reac-Exceeding ETS technical specifica-tor Blog Vent monitors 2.1.3a a

tion limits exceeded Hi-Hi alarm plus I monitor readings Liquid Radwaste Exceeding ETS Effluent Hi alarm plus 2.1.1a monitor readings ~

3. Fuel damage indication

a. High off gas at Pretreat Monitor Hi Hi 500,000p Ci/sec pretreat monitor alarm plus monitor corresponding to 16 isotopes de-readings cayed to 30 minutes; or an in-crease of 100,000 p Ci/sec wi, thin a

, 30 minute period.

b. High coolant Lab sample signifi-

> 100 ft Ci/gm of activity sample cantly greater than I-131 equivalent limit for normal opera-ting 1-131 equivalent

4. Abnormal reactor Reactor Vessel High 2 1200 psig Pressure pressure e

i t 3 e e m M e i y v MANUAL SET i i )

E.1. Hatch Nuclear Plant aoct=as ~o . an HNP. 4420 ams>o= ~o Sch Title Page k 4 T Georg. Power s ia o 4 of 7 See Title Page TABLE 1 (CONT.1 NOTIFIC4 TION OF UNUSUAL EVENT INITIATING CONDITION EGUIPMENT STATUS PARAMETER VALUE

5. Failure of a main steam Failure of valve to' Torus and/or DW line relief valve to close pressure increase Torus Temp > 110'F close following a re-duction of applicable Torus Level High

>153 in. pressure Safety Relief Viv Tail Pipe Temp. High 7 230*F

6. Loss of offsite power 500 and 230 HV system Zero voltage on or loss of onsite AC failure all incoming out-power capability or side lines zero Loss of all emergency voltage indicated diesel generators on all 4.16 kV buses

7. Loss of containment Loss of Primary or See Table la integrity requiring Secondary Containment shutdown by technical Integrity specifications

8. Fire within the plant Fire alarm and obser-Shift Supervisor's lasting more than 10 vation judgement minutes

9. Security threat or Observation or valid Shift Supervisor's attempted entry or initiation of security judgement based on attempted sabatage alarms

, advise of Security Shift Supervisor l

10. Natural phenomenon Observation or Shift Supervisor's being experienced or notification judgement projected beyond usual l

1evels. l e

g../:-

~ MANUAL SET l o e

mauvwa ns ~ t-. I. l'1HICII INUCitsar l'/Ullt HNP. 4420 StjeTitlePage aasionno [j Georgia Power A i ..e. ~o 5 of 7 See Title Page TABLE 1 (CONT.) NOTIFIC TION OF UNUSUAL EVENT INITIATING CONDITION EOUIPMENT STATUS PARAMETER VALUE Any earthquake felt Observation or - Alarm setpoint a. inplant or detected " Seismic Instrumen-is.005 G on plant seismic tation Triggered" instrumentation Alarm on Unit I Con-trol panel. This starts the Time / History Record-ers for Units I & II

b. Any tornado onsite Observation causing significant damage affecting plant operations

c. Any hurricane onsite Cbservation

>75 mph causing significant damage affecting plant operations

d. 50 year flood causing Observation 288. 6 f t. MSL significant damage affecting plant operations

e. Low river water Unit 1: Intake Screen 162/4 ft. MSL or Low Water alarm plus observation of level indicators Unit 2: Plant Service Water Intake Structure Low Level alarm plus observation of level i

indicators Shift Supervisor's

11. Other hazards being judgement experienced or projected i

a. Aircraft crash on-Observation site or unusual t

aircraft activity I over facility i i

b. Onsite explosion Observation h,

MANUAL SET

"wa' C. I. OldLUll INUUltidt l~ldllt Net W HNP. 4420 Sue Title Pag 2 aavisio o k 4 4 Georgia Power o See Title Page 6 of 7 TABLE 1 (CONT.) NOTIFICATION OF UNllSUAL EVENT INITIATING CONDITION EGUIPMENT STATUS PARAb'ETER VALUE

c. Significant onsite Chlorine alarm in

^ toxic gas release Chlorine Bldg. Rupture of chlorine cylinder or chlorine system piping or observation Significant onsite Observation flammable gas release

d. Turbine rotating Turbine trip, turbine component failure internal damage causing rapid plant shutdown 12.Other plant conditions Exceeding any safety Shift Supervisor's exist which warrant in-limit as required in judgement dreased awareness on technical specifica-the part of the plant tions operating staff or State and/or local off-site authorities 1

13. Transportation of con-High contamination to 710,000 dpm/100cm taminated injured in-injured individual dividual from site to offsite hospital

~ A' .s w ." N. D' MANUAL SET

i_. e. e satue s ivut, sed talit Paoccounc ~o H N P-4420 Sao Title Page arm.o= ~o Q 4 Geo . Power n e. la ..e. ~o See Title Page 7 of 7 TABLE la HNP-EP PARAMETER VALUE FOR LOSS OF CONTAINMENT INTEGRITY REGUIRING SHUTDOWN BY TECHNICAL SPECIFICATIONS Unable to meet.one of the following requirements within time limit set forth by technical specifications: 1. All non-automatic containment isolation valves on lines connected to the reactor coolant system or containment which are not required to be open during accident conditions are closed. These valves may be opened to perform operational activities. 2. At least one door in the personnel airlock is closed and sealed. 3. All automatic containment isolation valves are operable or deactivated in the isolated position. 4. All blind flange and man ways are closed. 5. At least one dcor in each access cfpening is closed. 6. The standby gas treatment system is operable. 7. All automatic ventilation system isolation valves are operable and are secured in the isolated position. 0 e . w? - ' \\" g% e f 'G ] ' MANUAL SET

GEORGIA POWER COMPANY .) HATCH NUCLEAR PLANT PROCEDURE At.ERT~ ~ ~ PROCEDUR TITL.E ~ ~~~ HNP-4520 PROCEDURE NUMBER LAB RESPONSIBLE SECTION SAFET'r RELATED ( X) NON-SAFETY RELATED ( ) 4-_--_---- 4----- APPROVED APPROVED REV. DESCRIPTION DEPT. PLANT DATE HEAD MANAGER J///33 2 Page 1 a- - -. ~._.-fh .LLM . /2 ] 1 ]_ag_c - _1 - - -.. ---_-----------_---.r------ 9 / p---_-----_--_--_y-_---_- HnP e x ~.... - g MANUAL SET ^^^^ - _ _ - ~ - - - - - - - - - - - -. _ _ _ _ _ _ _ _ _ _ _ _

f h(l' N' '- J I*.L i P_n..n..cro_t_ _iC_ _r_d_v_ f C_ _f F_:.t_n_!_~d_t_r.*f_.Y_ ~ l. - 2 PROCCCL'RE N'O. HNP _'i'!_~____----_ R w i e n n o. _ _ t_ _ _ _ _ _ _ _ _-

==--_-___ ____ _- R_Feit_.':_:._T F_D__R_ V .__ _ _ _O_' P AR TtE_t_!_T _ 8.'_._4_. _/_,P_P_u_n_'.' _ = Date: - DM e; Si gn., t ur e : NAme;l;, (4;ot, ,y, e> /,/sc~52's't _. ____ _ __,p.y (( W // ~*

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U _ - ~ _ REVISICM CHANGCs MOCE OF.CPr.RATIOM OR INT!.NT AS CEGCRIDED IN F3A (, ) No ( ) Nes CHANGE INVOL.'v'ES*

'(

) An unrevievred Safety Guestion ( ) Tech. Specs. (, '.. ) Neither (See back for Safety Evaluation if required). ( '. ) ft Related ( ) . Safety Related.. :.~..:........- _.N._o n.S a e y 7_. w w. -.. ....... : _.,....:.: w., a.,,) . (, s. No, ( -) Yes ...... Safety /Non-safety Status Change Attach marked up copy of procedure to this form. REASON FOR REGUEST -~~ (;.].Y ' ' ( h. P. r s. !* / J ~

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_T_h e__r_e_v_i s_i_o_n_o_f_ _t_h _i s.._o.r.o.c_e.u._re __':.s s. _ _: _ _ _ _ _ _---_-..__ __.u.e_s_t_i_on__a_s__e x_c_l_a_i n_e_d__b _e l_o_w.____- _____________ q l __1. __T_h_e gr_o_S_aS..i.l_i t.y o..f.._o_ccu_r_r.e.- s _a_n v'._t.h e c.rLn.3.nou_e_n_c_es_. o_f__a .m i t t t to safety are not increased _o_r__c.a.l f_u_n.c.t i_o.n._o__f _e_e_u _r__e_.___.c. o r_ _a_n - --..o_v a _t_h.vLa._a_n.>_1 v7,gd__i n _'_'. _:.~:.3_@ a 10._@Asa_.r,bac Jaa _b.o_r.3l,;.a- _ _ _ __ _ _ a ab a a a ____ t_h_e.re_v_i_s_io_n d_o_es__n_o_t ch'tr._:s. the ourcose or oe_r_f_orm__a_ system.__ - ~. The cossibility of an acc_i_rsat_._or__ mal funct.i.on of a different tvo_e_*_'- 2. t_ha_n_a_nal,yzed in the F_SM cres not r.=esult frc-1 t_h_is__ch_an_c_e _because .c_: _ ~. the system resconds and is ::er_at_e_d _a_s b.e._ fore the chan_ce. - ..a u The _ mar _c._in_of _s_af_e_t_y as_ de"r.ed in the Technical Soecifications s-3. =. is not reduced due t'o th's_revisio_n _b_ec_a_use the revision _does not __,' .n _, ch a_n_c e__a_n.v._l_i_m_i _t e_d__s_a _f e ty syste t_s_e_t_t_in_os_ which would al_l_o_w a ^ -_a.f.e._t*v__1,.*_n_i t__t_o be exce_e_d_e_d_o_r _to allo t a limi tinc condi. tion for s. ooerations to be exceedef as stated in' Technic _a_l_So._e_cifications._ _ _ ,. 1. (,... :. -. A-_- _ _ _ , f.L* _____- 35 -___g _---- -..; 4.--- HNP-9 = t

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aa=== ~o ~~ E. l. Hatch Nuclear Plant -m HNP 4520 g avisaw ao Sqe Title Page k 3 6 Georg. Power n 1 ia ..m ~o 1 of 7 See Title Page ALERT A. CLASS DESCRIPTION Events are in process or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant such as those noted in Table 1. Any releases are expected to be limited to small f ractions of the EPA Protective Action Guideline (PAG) exposure levels. B. PURPOSE Purpose of offsite alert is to (1) assure that emergency personnel are readily available to respond if situation becomes more serious or to perform confirmatory radiation monitoring if required, and (2) provide offsite authorities with current status information. C. PLANT ACTIONS NOTE The Shift Foreman or Shift Supervisor (or higher ranking licensed or certified person precent) in consultation with the STA, if feasible, recognizes and declares that the plant is in a state of emergency of the Alert Class. The person declaring the emergency assumes the role of Emergency Director until relieved. Inform State and/or local authorities of diert status 'and 1. reason for alert within about 15 minutes. Augment resources and activate Technical Support Center 2. (TSC) and OperaH ent Support Center (OSC). Bring Emergency Operations Far(I :y (EOF) and other key emergency personnel to standbv 5' *i u 3. Assess at.1. c 1, ,f, 4.' Mobilize onsite monitoring teaks with associated Communications. Provide periodic plant status updates to offsite authorities 5. (at least every 15 minutes). MANUAL SET

eaoccoun ao - ama ~ ' 1:. l. Hatch NUCicar islant H N P-4520 nveon ao o.,[ Georgia Power A Boe Title Page 2 of 7 See Title Page Provide periodic meteorological assessments to offsite 6. authorities and, if any releases are occurring, dose estimates for actual releases. 7. Escalate to a more severe class, if appropriate. Close o'ut or reduce emergency class by verbal summary to - 8. - offsite authorities followed by written summary within 8 hours of closecut or class reduction. STATE AND/OR LOCAL OFFSITE AUTHORITY ACTIONS D. 1. Provide fire or security assistance if requested. NOAA Augment resources and bring primary response centers, 2. weather radio and EBS to standby status. Alert to standby status key emergency personnel including 3. monitoring teams with associated communications. Provide confirmatory offsite radiation monitoring and ,4. ingestion pathway dose projections if actual release substantially exceed technical specification limits. 5. Escalate to a more severe class, if appropriate.' 6. Maintain alert status until verbal closecut or. reduction of emergency class. 1 / ~ Y <;V v, ~ MANUAL SET ^--

I l i o

1 e

i = a. :- l -4 -4 l TABLE 1 ALERT.' l- + n PARAMETER VALUE EOUTpMENT STATUS _ - INITIATING CONDITIO4' e o ~ I-w w o u 1. '. Severe loss of fuel cladding:

a. High off gas at pre-treat monitor 's Pretreat Monitor Hi Hi

>5 C1/sec alarm plus monitor readings corresponding to.16 isotopes decayed 30 minutes

b. Very high coolant activity sample Lab sattple substantially greater ~

>300 p Cf/cm of than limit for normal opert. ting I-131 equivalent

t

' 1-131 equivalent [T1 2. Steam line break outside containment with Reactor Bldg. ARM H1 alarm >15 mr/hr g Turbine Bldg. ARM 111 alann >15 mr/hr i ng [ significant MSIV leakage High MSL Tunnel Temperature >200 F / 0 3. Primary coolant leak greater than 50 gpm Drywell equipment and/or Floor >50 gpm >lg

rjd, g

C]- Drain Sump Jll lit alarm Z m m v9 mr/hr -i ARH's are off scale on high >104 4. High radiation levels or high airborne 'end and readings confimed contamination which indicate a severe Q degradation in control of radioactive materials N cnsite AC power (see TabTe D-3 kV buses and loss of control 4.16'kV buses voltme'ter 5.. Loss of offsite power and loss of all

Undervoltage alarms on all 4.16

a reading zero and failure ~ room normal lighting and of Diesel Generators cutput O forextendedloss) Inability to energize C16 breaker to close into 4.16

g..

. ~ kV buses with Diesel Generators kV buses. 8 p,m - y. ^~~ D 6. Loss of.all onsite DC power (see fable Loss of all DC buses A ri D-3 for extended loss) R i z F, r-- () M D 7 Complete loss of any function needed Loss of Shutdown Cooling Mode of 'P{ 5 j RilR and all emergency core cooling g QT. for plant cold shutdown 3! o systems o w m Inability to shutdown with Control 4 Rods a e b

.,;s j I o >f m 't m 3 ag..j. e' s d d 4~ TABLE 1-ALERT (Continued) e e 'PARAF!ETER VALUE ' m m EQUIPMENT STATUS ~ ~ m o I IfifTIATING CONDITION Valid scram signal and neutron ' Reactor is indicated I

8. - Failure of the reactor protection system count rate indicates reactor is. ' critical by at least one of the following'neutM.:

to inttfate and cc:::picte a scra:n which critical brings the reactor subcritical monitoring systems: e SR!l. Imts, or APDis Fuel handling accident wf th release of Any of the'.'following plui confirmation by analysis'of. [T1 9. ' radioactivity to reactor butiding air sample:- O ~ ~ I Refueling Floor ARM Hi alarm >15 mr/hr / E -i m >20 mr/hr ~ Refueling Floor Vent Exhaust

M U.9.

O r H1111 Radiation alarm na p >15 mr/hr @,Q Z ' Refueling Floor Vent Filt'er ".,, j [ g

1.. -

Hi Radiation alarm z e Fire alarm and observatfori,, Shift Supervisor's *,, 5 Q ,Firepotentia11faffectingECCS , judgement a [ 10. Observation or failure fit alarm * .3 11. Most or all alarms (annunciators) lost check or transient notice'd with ~ out alarm E

G Exceeding 10 times ETS Main Stack or Reactor 81dg.

to 3::a @. ' Radiological gaseous effluents greater. Vent monitors Hi Hi alarm .2.1.3a than 10 times technical specificatio'n plus monitor readings

Z!!:

instantaneous limits C=ll Shift Supervisor's ac3 2:a R 3 z8 Observation F ~~5,a res Q-Shif t Supervisor H~~

~~.,3 g~~
g. w q-4 ?- ~ b l
~ ~ ~ ~ ~ ~~ 5*Sovat t.. l. r18tCH INUUltful r'lullt HNP. 4920 e tytS40N NO oj Georgia Power ok $9e Title Page 5 of 7 See Title Page T_ABLE 1 A_L_ ERT (CONTINUED) EGUIPMENT STATUS PARAMETER VALUE MITIATING CONDITION Shift Supervisor's
14. Severe natural phenomena judgement being experienced or projected:

a. Earthquake greater 1.
~~" Seismic Instru-Annunciators are than OBE level mentation set at 100% OBE Triggered" alarm level (.089~~
2. Units I and II vertical has been recorders start exceeded)

3. " Seismic Switch Tripped" alarm which is set at OBE level (Unit II)

4. or Unit I Seismic Peak Shock Recorder high g level alarms

5. or Unit II seismic Peak Shock Recorder high g level alarms

6. Peak Shock Annunc-iators set at 100%
OBE have been actuated. NOTE: If any one of the situations in 3-6 above occur, the operator should' play back the Time History Recorder Tapes to determine the actual maximum g acceleration. t gekeJ8N W., MANUAL SET _ _ -- - J
6
~~. l 3 \\ e .m -. o s e d d c c e e m m TABLE 1 ALERT (tontinued) ~ o o ~ EQUIPMENT STATUS PARAMETER VALUE INITIATING CONDITION~~
~~b. Flood near design level High river water elevation~~
~~>100 f t MSL~~
~~c. Hurricane winds near design basis level High winds (300cph)-~~
~~g m~~
~~d. Tornado' striking facility incurring Observation p~~
~~g damage affecting safety systems g I m o R. -i~~
~~e. Low river water -~~
Unit 1: Intake Screen or low <61.7 ft HSL g rg,, i n ~ Water alam plus o a C 7 observation of 1~ vel e indicators @ 5 O Z a O c Unit 2: Plant Service Water intake O' E O- ' Structure Low Level alarm e G plus observation of level o indicators 15. Other hazards being experienced'or. Shift Supervisor's' 3~ judgement projected:
p.
~~3::= W~~
~~a. Aircraft crash on facility Observation g~~
~~a c::: m~~
~~b. Missile impacts from whatever source~~
~~Observation 3::n 3~~
~~on factitty incurring damage affecting F~~
~~.s safety systems A I 1 0~~
~~'O o z c m~~
~~5 o~~
H O tAs ut o ""3 o, (U -t O .-M 4 ~ em d a
8 o @5 -4k. l s Y. Y C C = m m m 6 to c. m e 1 TABLE 1 Al.ERT (Continued) - i INITIATIMG CONDITION _ EQUIPMENT STATUS PARAMETER VALUE_
~~c. Known explosive damage to facility Observation i~~
~~l affecting plant cperation E Control Room Out' side Air Inlet k C) 'd. Entry into facility environs of toxic or flatnable gases j alarm m O~~
~~e. Turbine failure causing casing Turbine components penetrating O~~
[ '4 r3 g . casing penetration Observation . Shift Supervisor's } { m 16. Other plant conditions exist that . judgement y warrant precautionary activation of { y g n TSC and placing EOF and other key su emergency personnel on standby. m Shift Supervisor's O 17. Evacuation of control room anticipated Observation 3 judgement k g or required with control of shutdown - systcas established from local ~ stations g HSL High Radiation alarg >3000 mr/hr D 18. Control rod drop accident llEF. 'pCl5 APRM Upscale 11tp of >120% full power C 8 Channels A and/or 8 m, A $ I" fD 7 ! E.! l3 o x 8 M l$ >i A o -A O Ld U1 o O -ti fu O
===L q 7 t T = m, I
o i GEORGIA POWER COMPANY J- . 1 HATCH NUCLEAR PLANT PROCEDURE ALERT EMERCFNCY - RALLY POINT LEADER PROCEDURE TITLE HNP-4526. PROCEDURE NUMBER LAB RESPONSIBLE SECTION SAFETY RELATED ( X) NON-SAFETY RELATED ( ) APPROVED APPROVED REV. DESCRIPTION DEPT. PLANT DATE HEAD MANAGER d'[~ w J 1[8) 2 Pages 1, 2&3 ( 7 en Lm-- -a' .3 .Page 1 & 2 .-_--------t---- _-----4-_-- _--_- ___---___..____---_____---_..---_--.--------.,------- e e MANUAL. SET
If.*/ ljy~ .I PR..O..CFf_;! t 2C I?! L.'..f.G I't.i;'.t.l.d. ~dt_t ~f T .. ~ -.. s ,j.- D j 8b PRDCCCL'GE. N'O. ICP-ll ).) . c. Revision t!u. d O =- .= ST.rp nY = ---.FP.JiT G;!T MF, O.a.PP:.C'.'.:.:_ HFGt *:: Signature:-. ---.---------.-------- Date: Jt. me ; Ds-t e f ( ' b 4 [MC[o // / /JL / _.)),/M.fz. ^ =- REVISICil CH.2.NGCG MOCE OF.CPERATIOrt OR I4 TENT AS DESCRIDEO IN FSAR: ( ) Yes (/)) ) N3 CHANGE IfMOlNES*- ( ) An unreviewed Safety Guestion (- ) Te c h. Sp e c r... ( %) Neither ' ~ (See bacic for Safety Evaluation if required). J ........ Safety Re ate .. 7...)....... Non-Sa f et y R e l a t.e d.,.(..-.)...~. l d ( ....... ~..... ......--..:.. ' x... c w *....a.........:.::,.. w... x. a....... '. Safety /Non-safety Status Char.Je -) Yes + - ( #) No Attach marited up copy of procedure to this form. ~~' REASON FdR REC!EST // [MN/f h 68t. b "' //'
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E. I. Hatch Nuclear Plant raoa=as ~o ~~~ HNP-4526 a'v'S'o" **o GeorgiaPower d Se Title Page ~e 1 of 2 { om Seg. Title Pace ALERT EMERGENCY - RALLY POINT LEADER A. CONDITION Events are in process or have occurred which involve an actual or of safety of the potential substantial degradation of the level Any releases are expected to be limited to small plant. f ractions of the EPA Protective Action Guideline (PAG) exposure levels. 8. REFERENCE HNP-4520 l HNP-4521 'C. ACTION Once the Rally Point Leader is de,signated by the OSC 1. he should appoint approximately three RET members
~~manager, to report with him to gate 16, which is the primary cally point.~~
2. Determine if the rally point is habitable using survey meters and the following criteria: Area dose rate less than 0.5 mr/hr, and a. contamination less than 100 CPM above background. b. 3. If conditions at the primary rally point ('ga te-16) do not satisfy the criteria in C.2, then proceed to an alternate rally point. The alternate rally point is The Skills Training Building or The Environmental Building. Determine if the alternate rally point satisfies the 4. criteria in step C.E. 5. Return to gate 16. 6. Notify the Control Room of resdits. Prepare for evacuation of plant personnel if the emergency 7. class should escalate, periodically confirming that conditions at the rally point are still acceptable. ge g MANUAL. SET

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~ HNP. 452s A - S.oe, Title Paga 3 o.,; Georg,ia Power n 2 of 2 See Title._ Pace Do not release members of the Radiological Emergency Team, l until directed to do so by the 8. except to report to the EOF, Emergency Lirector or Shift Supervisor if the Emergency + Director cannot be contacted. Assist,in routing ambulance to pick up any injured g 9. Assure ambulance driver and attendant are personnel. provided with TLD badge and pocket dosimeter on entry. Assist Emengency Director in bringing emergency under g 10. control. O e f e O e t 1 i geWgg.e . ~. 4 e .. MANUAL. SET ____________m_e
J GEORGI A POWER COMPANY HATCH NUCLFAR PLANT PROCEDURE Site Area FmerSen__cZ PROCEDURE TITLE HNP-4F.20 PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( ) APPROVED APPROVED REV. DESCRIPTION DEPT. PLANT DATE HEAD MANAGER [ c[th ____,g 1 Page 2 f_.._... we _ - - s _ n. 4_.w t _2_. _.9 _/ t._-_ .2--... Pa e_s 1..& _3 th_r_u_7__--_. _/ e. O HNP-9 e MANUAL SET 9 9 i ____________._n___..__
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E.1. Hatch Nuclear Plant raoa masao - om HNP. 4620 aavisioa ao .Sto Title Pogs Georgia Power d 0. .. ao 1 of 7 See Title Page SITE AREA EMERGENCY 9 A. CLASS DESCRIPTION Events are in progress or have occurred which involve actual or likely major failures of plant functions needed for protection of 5 the public. Refer to Table 1. Any releases are not expected to exceed PAG exposure levels, except near the site boundary. 8. PURPOSE Purpose of the site area emergency declaration is to (1) assure that response centers are manned, (2) assure that monitoring teams are dispatched, (3) assure that personnel required for evacuation of near site areas are at duty stations if situation becomes more serious, (4) provide consultation with offsite authorities, and (5) provide updates for the public through offsite authorities. C. PLANT ACTIONS NOTE The Shift Foreman or Shift Supervisor (or higher ranking licensed or certified person present) in consultation with the STA, if feasible, recognizes and declares that the plant is in a state of emergency of the site area class. The Shift Supervisor assumes the role of emergency director until relieved by the Plant Manager or his designee. 1. Promptly inform State and/or local offsite authories of site area emergency status and reasons for emergency. 2. Augment resources by activating TSC, operations support center and EOF. 3. Assess and respond. 4. Dispatch onsite and offsite monitoring teams with associated' communications. ~ I 5. Dedicate an individual for plant status updates to offsite authorities and periodic press briefings (perhaps in I conjunction with offsite authorities). 6. Make senior technicial and management staff onsite ayailable for consultation with NRC and State on a periodi, 4f(is. h e,m 9 MANUAL SET I
aaoamas ao E. I. Hatch Nuclsar Plant a~~ HNP-4620 . (f a<viso= ~o Georgia Power d S e Title Page ^ .o 2 of 7 o... See Title Page 7. Provide meteorological data and dose estimates to offsite authorities for actual releases via a dedicated individual or automated data transmission. Provide release and dose projections based on available information and foreseeable contingencies. 8. plant condition 9. Escalate to general emeraency class, if appropriate. O__B class by briefing of offsite reduce emergency Close out or 10. authorities followed by written summary within 8 hours of closecut or class reduction. STATE AND/OR LOCAL OFFSITE AUTHORITY ACTIONS D. Provide any assistance requested. 1. If sheltering near the site is desirable, activate public notification system within at least two miles of the plant. 2. Provide public within at least about 10 miles periodic 3. updates on emergency status. centers. Augment resources by activating primary response 4. 5. Dispatch key emergency personnel including monitoring teams ~~' with associated communications. ' Alert to standby status other emergency personnel (e.g., those needed for evacuation) and dispatch' personnel td near 6. site duty stations. DOE and others Provide offsite monitoring results to GPC, 7. and jointly assess them. Continuously assess information from GPC and offsite 8. monitoring teams with regard to changes to protective actions already initiated for public and mobilizing evacuation resources. Consider placing milk animals within 2 miles on stored feed 9. and assess need to extend distance. 10. Provide oress briefings, perhaps with GPC. e 11. Escalate to general emeroency-class, if appropriate. (h closeou Maintain site area emergency status until 12. reduct, ion of emergency class. 6 MANUAL SET TOOSBS
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s -l -{ g y TABLE 1 SITE AREA EMERGENCY P_AR E TER__VALUg y W b EGilIPMFNT STATUS c INITIATTNO CGrOTTTON Greater than 1.8 psig j Drywell High pressure and increasing 1. Known loss of coolant accident greater Initiation alarm, Less than -38 in and than makeup pumps capacity. Reactor Low level Initiation decreasing alarm Hi Flow Drywell Drain Sump alarm o Greater than 148 F and Drywell High Temperature alarm Increasing g ) g) i C Some combination of the M Q C 7, Degraded core with possible loss of following: p coolant geometry (e.g. massive cladding Containment High Radiation x) _g 2. p b. O failure or loss of core flow)
~~alarm, A[>~~
C Fission Product monitor Hi Hi Radiation alarm and N.G. mim 7 2 N.G. El C C Fission Product monitor in-7 E 9. dicator off scale on high end, C Q Reactor Low Level Initiation g alarm 'Z .) y o Some combination of the follow-Greater than 15 mr/hr 4 Steam line break outside containment ing! Turbine Bldg ARM Hi alarm Greater than 120% and 3 3. without isolation MSL Hi Flow alarm increasing Less than 855 psig and p MSL Low Pressure alarm decreasing e 23r Zero voltage indicated 2 Undervoltage alarms on all 4.16 on all 4.16 kV buses C f offsity power and loss of onsite kV buses for more than 15 min-or more than 15 minutes utes and loss of control room A y3 3;;i+. Los normai~51ghting or.more than 15 S 3 z8 F pow M Q minutes and inability to energize 5 9 ?y uJ g g 4.16 kV Eies'from Diesel Generat-M A[ ors for more than 15 minutes, V o fu 01 c M ti 03O -4 d
1 O (n "* (D' ] o e.,e ,il e m H H r. r. <+ <+ e* e-a l m o 1 'O TABLE 1 i SITE AREA EMERGENCY (CONTINUED) o m PARAMETER VAltJE.. EGUIPMENT STATts INITIATING CONDITTON e Loss of DC Dusses for more 5. Loss of all vital onsite DC power than 15 minutes for wore than 15 minutes Inability to Shutdown with g 6. Complete loss of all function needed s Control Rods -4 (T1 for plant hot shutdown m Scram signal present and power 7. Transient requiring operation of not decreasing, Standby Liquid j g T. shutdcwn systems with failure to Control initiated. scram (continued power generation > l U,O o but no core damage immediately evident). N{_q 6 7 8. Major damage to spent fuel in Reactor Observation y 3 Z Less than 8 ft above fuel Spent Fuel Storage Pool Low and decreasing a C c Building (e.g. large object damages fuel or water lost below fuel (level) Level alarm me O Fire alarm and observation Shift Supervisor's [ h ~ (D Q M 9. Fire compromising the functions of judgement safety systems 3 ^ One or more of the following: Shift Supervisor's n C3 /, m
~~10. Most or all alarms (annunciators) judgement lost and plant transient initia.ted loss of feed water 3~~
a. y or in progress l#llP8 b. turbine trip D i:. loss of offsite power E C d. los's of reactor coolant D pump h 5 8 g 8 og DO e.. reactor trip l 1 0 &z m -4 O (U rp c + ru O -4 4 ) 4e d
TABLE 1 f SITE AREA EMERGENCY (CONTIF3JED) I INITIATING CrWDITION EOU!PMFNT STATUS PARAMETFR VALUE 11c. Radiological gaseous effluent monitors Main Stack and Re' actor Bldg. o detect levels corresponding to Vent monitors Hi Hi alarm U3 E 9J1 l greater than 50 mc/hr for 1/2 hour plus monitor readings plus' $~ M ?
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or greater than 500 mr/hr W.B. for dose projection calc.ulations ,d, ,d, 1 two minutes (or five times these plus field measurements 1 levels to the thyroid) at the site ,+ ,+ boundary for adverse meteorology { p 11b. Containment post LOCA radiation Containment Post LOCA T T monitor readings indicating a Radiation alarm plus j j fission product inventory equivalent monitor readings plus e m l to offsite dose rates as described dose projection cal-in,11a. culations 11c. PAGs projected to be exceeded Effluent monitor outside site boundary readings plus dose projection calculations g 12. Imminent loss of physical control Loss of control of vital Shift Supervisor's judge- -l IT1 N of the plant areas ment based on advice of I Security Shift Supervisor g 13. Severe natural phenomena being Observation Shift Supervisor's b ' experienced or projected with plant judgement qy Qd 8 not in cold shutdown: 3 a3 {" T m.~ g f* a. Earthquake greater than DDE 1. " Seismic Instrumentation OBE level is.O.1S g j A i l 1evel Triggered" alarm m-o- Z O P G) 2. Units I and II recorders Q 4 gu start 3. ' Seismic Switch Tripped" ~ b T O E alarm which i's set at DBE Z 3 d level (Unit II) llllN 4. or Unit I Seismic Peak 3 Shock Recorder high g A level alarms C"D 5. or Unit II Seismic Peak F Shock Recorder high g j j -(r 3 level alarms 7 l m 6. Peak Shock Annunciators set at 100% DBE have been o fu rgo actuated O -J 7. The maximum g. level measured by the Time / History Acellerograph Recorders is greater than DOE levels (0.15g) d
3 i e t j t' i 1 m *E 01 I* t o ./ e m' i I H. H. P P r+ r+ w w e e T T m e o to TABLE 1 m o SITE AREA EMERGENCY (CONTINUED) INITTATING CONDITTON EGUTPMENT STATtG PARAM6 8 t-H VALUE
~~b. Low water affecting plant safety Very low river elevation Less than 57 ft. MSL ~~~
~~Plus observation of safety systems ' rJ) systems sH ITI~~
~~c. Flow or hurricane surge greater Very high river water Greater than 120 ft MSL rq C~~
~~elevation than design levels m O 7 m O I m l~~
~~d. Sustained winds or tornadoes Very high winds l~~
in excess of design level (300 vnph) Observation of damage >q g m > Shift Supervisor's 3 W C judgement $ [q T Z-14. Other hazards being experienced or projected with plant not in cold a C C shutdown y# k 9. o O O I
~~a. Aircraft crash affecting vital Observation N,~~
~~s tructures by' impact or fire x. n 0~~
~~b. Severe damage to shift shutdown Observation equipment from missiles or H~~
~~~ explos1on p~~
~~c. Entry of uncontrolled flammable Observation,' Control Room a~~
Sases into vital areas. Entry Outside Air Inlet alarm D 3 of uncontrolled toxic gases into C vital areas where lack of access D to the area'consititutes a safety 2 A I I P pE em k E M o z rvi e 5 >! M E 0 TU Ge t (U
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pa. W w a O 7 7 h b o c a m 6 TABLE 1 SITE AREA EMERGENCY (CONTINUED) KO Il_1 INITTATING CONDITION EOUTPMENT STATUS P AR AMt. 4 LN VAltg l g m O Shift Supervisor's y 15. Other Plant conditions exist that Observation C warrant activation of emergency judgement j I centers and monitoring teams or y M D3
-4 (fd a precautionary notification y*
3-to the public near the site m r-16. Evacuation of control room and Observation ].A g [ m o control of shutdown systems not established from local stations Z O-O O sn 15 minutes 4 a3 i o m. Z 3- -4 e a p
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GEORGIA POWER COMPANY 4 . 1 HATCH NUCLEAR PLANT PROCEDURE S i t e A r e a Eme r 5Lo.n__e.E - Ra i _lZ-Point t.eader PROCEDURE TITLE HNP-4626 PROCEDURE NUMBER 1.a b RESPONSIBLE SECTICN SAFETY RELATED ( X) NON-SAFETY RELATED ( ) L.-----------------...---------------..--------------<. APPROVED APPROVED REV. DESCRIPTION DEPT. PLANT DATE HEAD MANAGER p- - _ - - _ - - _ - - - - - - - - - -.. 2 Pages 1,2, &3 jl g Deletions on A G Pages 1 & 3 . / e.s I .L.2 g),L---. "/' Q 7 / ---/ / r g. .PaJLe I 3 A e1. 4 Pa e 1 thru 3 e 'e <s. l l ...---,----____---_-----_------_-_-------_1------------__-.h-----. eieren<.c ot ~~ HNe-s MANUAL SET
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~~Signature:~~
Name; c- (<jh------.----- // /3 f.---- h f/ l O ll l N =--. --~- w--- REVISICM CHANGED MCCE OF.CPERATIOM OR INTENT AS DEGCRIDED IN FSAR: ( ) Yes ( No g CHANGE INVOt.VES:- ( ) An unreviewed Safety Guestion (- ) Tech. Specs. (/<) Neither (See back for Safety Evaluation if required). s. .w Non..S..a f et y R. e.l a.t e d.. (,m.)..... Safety Related ( ) s. - ~ ).,; ... : /.-:. - -.-- c.r. ::.....e w :-.:....... e s... ;..,. u ~. 2. ( ) Yes ..-( ) No m. .e..;..-.., -, - - Safety /Non-safety Status Change. ' Attach marked up copy of procedure to this form.
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b acceovac = u -- E.1. Hatch Nuclear Plant HNP-4626 Af vissON NO / GeorgiaPower A 1 of 3 ( See Title Page ..m NO See Title Page SITE AREA __ EMERGENCY - RALLY POINT LEADER NOTE This procedure supercedes HNP-4605 Revision 6 dated 1-2-81. A. CONDITION in process or have occurred which involve actual or likely major failures of plant functiors needed for protection of Events are Any releases ar not expected to exceed PAG exposure the public. levels, except near the site boundary. B. REFERENCE HNP-4620 HNP-4621 GENERAL INFORMATION & INSTRUCTIONS C. The primary cally point for personnel inside the primary 1. protected area is gate 16. The primary cally point for personnel outside_ the primary 2. protected area is gate 1. 3. The alternate rally points are: Environmental Building a. Skills Training Building or The Outage Training b. Building. The criteria for rally point habitability are: 4. a. Area dose rate less than 0.5 mr/hr, and b. contamination level less than 100 cpm above cally point. background. the primary The locations of decontaminatiqn showers outside 5. protected area are: Environmental Build'ing a. b. Outage Training Building gg(,6 MANUAL SET ~ ~ g O
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tiNP-4626 ret 1SiON NO 4 SejTitlePage .., J Georgia Power -o 2 of 3 See Title Page Do not release any person who has received greater than 25 rem whole body dose or is suspected to have ingested 6. Such persons significant amounts of radioactive materials. are to be taken to the hospital for examination and further evaluatlon of exposure. Confer with the Emergency Director before releasing any. 7. personnel involved in the incident. and general contr;.ctors, Check with the Security Force, Georgia Power Construction Department to determine those 8. If any person (s) is (are) persons remaining in the plant. report this to the Shift Foreman. If the unaccounted for, form Shift Foreman cannot account for the missing person (s), and initiate HNP-4628, Site Area Emergency a rescue team (s) - Rescue Team. .0: ACTION the OSC manager will After the RET assembles in the OSC, charge of the rally 1. appoint a Rally Point Leader to take point. The Rally Point Leader should instruct all RET members not 16. assigned a specific function to report with him to gate 'E. ~ NOTE . Leave enough RET members in the OSC to comprise an internal survey team and a rescue team (approximately seven individuals). if the primary cally points are habitable using 3. Determine the criteria in Section C.4 If conditions at the primary rally points do not satisfy the proceed to an alternate cally 4. criteria in Section C.4, Determine if the alternate rally point is habitable point. using the criteria in Section C.4. 4 Dispatch an appropriate number of RET members to th 5. Assure personnel gather at the designated rally points for frisking by RET members and collect all personnel dosimetry. 6. individuals wh'o were involved Attempt to separate thosewho were working in contaminated a. in the incident, and those wearing protective clothing from other
~~areas, personnel at the rally point.~~
Reference Only 4 MANU!ll. SET e ^ m
'a= = = E. l. Hatch Nucicar Plant HNP-4626 --t amww w J o.,/ Georgia Power d
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3 of 3 See Title Page Attempt to survey those individuals with emergency b. response assignments as soon as' practical. individuals who were involved in the incident, c. Instruct those found contaminated (greater than 100 cpm above the Rally Point background), and those with personnel dosimeters off scale to remain at the rally point, and notify the Health separated from the others, Physics Supervisor in the TSC. individuals personnel dosimetry to the Forward these EOF and instruct these personnel to report to the EGF d. for further (after checking through the rally point) evaluation of dose received. Dispatch an RET member (s) to accompany contaminated (see C.5) and e. individuals to a decontamination shower supervise the decontamination procedure. site Release uncontaminated individuals to evacuate the f. 1 in the direction specified by the on U.S. Hwy. Control Room. Report status of the evacuation to the Emergency 9 Operations Facility. Do not release members of the Radiological Emergency except to go to the EOF, unless directed to do so h.
~~Team, by the Emrgency Director or Shift Foreman if the Emergency Director cannot be contacted, Assist in routing ambulance to pick up any injured i.~~
Assure ambulance driver and attendant are personnel. provided with TLD badge and pocket dosimeter on entry. J. Assist Emergency Director in bringing emergency under control. Reference ()n! st. _. 6 ~ MANUAL SET A.._.
I I i l I GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PROCEDURE General FmergencL~~~ ~ ~~ Pii6CEDURE TITiE ~~~~ ~~ HNP-4720 ~~ ~ PROCEDURE AOMDER Lab __ RESPONSIBLE SECTION SAFETY RELATED ( X) NON-SAFETY RELATED ( ) APPROVED APPROVED DEPT. PLANT DATE itEV DESCRIPTION HEAD MANAGER 3 t g)-}. - - - -. -,- (-. )------ 1* Page 2 tx A f J r - ----. r g - *7 I' & Lt.t e' y-- 7---- y-a 2 Page 1 / 9 e.-----------

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6 W= E. I. Hctch Nucl::tr Plant ea= =< ~o HNP-4720 mim.o= uo ' gee Title Page Georgia Power z$L 0 .. m. c i op g See Title Pace GENERAL EMERGENCY A.. CLASS DESCRIPTION Events are'in process or have occurred which involved actual or imminent substantial core degradation or melting with potential for loss of containment integrity. Refer to Table 1. Release can be reasonably expected to exceed PAG exposure levels offsite for more than the immediate site area. 8. PURPOSE Purpose of the general emergency declaration is to (1) initiate predetermined protective actions for the public, (2) provide continuous assessment of information from licensee and offsite organization measurements, (3) initiate additional measures as indicated by actual or potentsal releases, (4) provide consultation with offsite authorities and (5) provide updates for the public through offsite authorities. C. PLANT ACTIONS ~ NOTE The Shift Foreman or Shift Supervisor (or higher ranking licensed or certified person present) in consultation with the STA, if feasible, recognizes and declares that the plant is in a state of emergency of the general clasification. The Shift Supervisor assumes the role of emergency director until relieved by the Plant Manager or his designee. l 1. Promptly inform State and local offsite authorities of general emergency status and reason for emergency (parallel i notification of State / local). l 2. Augment resources by activating TSC, Operations Support Center and EOF. 3. Assess and respond. Dispatch onsite and offsite mohitoring teams with associated 4. communications. 5. Dedicate an individual for plant status updates to offsite authorities and periodic press briefings (perhaps joint with l offsite authorities). j 6. Make senior technical and management staff onsite available for consultation with NRC and State on a perio sis. ggge# 1" l MANUAL SET
E. l. Hatch NuCiccr Plant = = ~o ~ ~ ~ H N P-4720 j naveo= =o ,'S$e Title Page Georgia Power d 2 .. m. p op g See Ti tle Paoe Provide meteorological data and dose estimates to offsite 7. authorities for actual releases via a dedicated individual or automated data transmission. Provide release and dose projections based on available 8. plant condition information and foreseeable contingencies. Close out or reduce emergency class by briefing of offsite 9. authorities followed by written summary within 8 hours of closecut or class reduction. STATE AND/OR LOCAL OFFSITE AUTHORITY ACTIONS D. 1. Provide any assistance requested. Activate public notification system promptly, inform public 2. of emergency status and provide updates periodically. Consider sheltering for 2 mile radius and 5 miles downwind 3. Consider advisability and assess need to extend distances. estimated of evacuation (projected time available vs. evacuation times). Augment resources by activating primary respond centers. 4. 5. Dispatch key emergency personnel including monitoring teams with associated communications. Dispatch other emergency personnel to duty stations within 5 6. mile radius and alert all others to standby status. Provide offsite monitoring results to GPC,' DOE and oth'ers 7. and jointly assess them. Continuously assess information from GPC and offsite 8. monitoring teams with regard to changes to protective actions already initiated for public and mobilizing evacuation resources. 9. Consider placing milk animals within 10 miles on stored feed and assess need to extend distance. 10. Provide press briefings, perhaps with GPC. Maintain general emergency status until closeout or 11. reduction of emergency class. d r% MANUAL SET $ $N IO
~ t, >l e @5 I 3 m y 4 d r. TABi.E 1 GENERAL. EMERGENCY C C o o PARAMETER VALUE INITIATING CONDITION EQUIPMEitTSTATUS m m 1.a. Effluent monitors detect levels Main Stack and/or Reactor Bldg. Vent 5 corresponding to I rem /hr W.B. monitors 111 Ili alarms plus monitor or 5 tem /hr thyroid at the site reading plus dose rate projection calculations. Dose measurements off-boundary under actual meteoro-site using portable instruments or logical conditions. environmental monitoring stations. m 1.b. Projected dose rates as above Dose rate projections will be bas'ed based on other plant parameters. on the following: Containment Post O m LOCA Radiation monitors, analysis of lb r[2. l,4 9 I drywell air sample, ARM monf tors in E P.eactor Building, plus possible con-O lr-3 firmation from effluent monitors or
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offsite measurements. Reactor pressure >1325 psig y?" Cg a 2.a. Failure of cladding and contain-See Table 1-a. with failure of safety - c5 ca m containment with potential loss relief valves to open. l3 R of primary coolant boundary. 4160 volts undervoltage. N ) o 600 volts undervoltage. [ g Analysis of activity in a steam and coolant. Reactor water level <352.5 inches. D Failure of ECCS to auto or manual initiate. Indicated loss of primary containment. c:a 03 R 1 3 r-" E 3 28 75 U3 5 61 rn E v# (%.g) g g5 --4 ru o 6
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j TABLE 1 GENERAL EMERGENCY (Continued)' -4 -4 INITIATINGCONDITION . EQUIPMENT STATilS PARAMETER VALUE 7 g 2.b. Failure of cladding and primary See Table 1-b. Containment pressure >25 psig ? I coolant boundary with potential Containment temperature j 's >300 F loss,0f containment Analysis of activity in steara and reactor coolant Reactor water levels 9/64f, inches m Containment Post LOCA 5 Monitor Readings j .m Containment High Range Radia-r O tion Monitor Readings en C y-Main Steam Line Flow >l20 psid ( Q ca Containment atmospheric m i-4 00 E analysis M!$ E 3' ME ? z 1 s E ) 2Jc. Failure of primary coolant See Table 1-c. Containment pressure >25 psig boundary and containment; with Containment temperature g g >3000F g R potential loss of cladding Hain Steam Line Flow >l20 psid 4 b y Indicated loss of primary g g/ g containment t. a Failure of ECCS to auto or ~ g q ,G manual initiate p 4160 volt undervoltage 2 Q'f 600 volt undervoltage c-l: ,g Reactor water level < /k/.f 2:a Va y inches and decreasing a 7; P E a zR 00 3.m Loss of physical control of the. Observation Shif t Supervisor's judge-5 9 ?E 5 >a ment based on advice of H plant .~ Security Shif t Supervisor 4 go N o l l i I
A 1 i , E 5 i TABLE 1 GENERAL EMERGENCY (Continued) 3 ~ PARAMETER VALUE_ INITIATING CONDITION EQUIPMENT STATUS Y Y Judgement of Shif t 3 C 4. Other plant conditions exist Supervisor and STA = = from whatever source that make u m release of large amounts of j j radioactivity in a short time i e period possible (e.g., any core melt situation). Example of sequences: m Transient (e.g., loss of offsite 3 a. power) plus failure of requisite m core shutdown systems (e.g., r g scram). Could lead to core R I melt in several hours with contain-j$a r$. ment failure likely. More severe consequences if pumps trip does not g g g g. function. h b 2 [ b. Small or large LOCA's with failure q o of ECCS to perform leading to core n o o melt degradation or melt in minutes 3 Ei to hours. Loss of containment in-d o~ tegrity may be imminent. E gn ) y R Small.or large LOCA occurs and con-3 E c. J:" tainment performance is unsuccessful 2 affecting longer term success of the- $g ECCS. Could lead to core degradation or melt in several hours without con-g$ tainment boundary. j ! j3 r-2 g g y{ rn --4 d Shutdown occurs but requisite decay m eat removal systems (e.g., RHR) or d nonsafe.ty systems heat removal means - S Ri are rendered unavailable. Core de-O e gradation or melt could occu: in about ten hours with subsequent containment ~ failure.
O >l $. n. -_j \\ a a 7 E-m m u e c c tD 'n TABLE l' GENERAL EMERGENCY (Continued) P INITIATING CONDITION EQUIPMENT STATUS PARAMETER VALUE-c' O r 5. Any major internal or external events m E rO'. Q. khich could cause massive comon l damage to plant systems'Pesulting @ jE E Z in any of the above. o m p Fires Massive dama.ge to ECCS System Loss of ECCS System y k .o o e ~' Earthquake Massive damage to ECCS System Loss of ECCS System @ d m g En3 T1 19 E: m ll2: C" 2:::n
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{ {s.I. / I TABLE 1.sa d d PRIMARY COOLANT BOUNDARY rnUIPMENT STATUS FOR FAILURE OF CLADDING AND CONTAINMENT WITH c a ca ~ ? ? e t STATUS INDICATES ALL CONTAlt&ENT PENETRATIONS GAP ACTIVITY IN NOT VALVED OFF OR CLOSED PR!i%RY COOLNiT = g OR m q l m p Y h CORE utCOVERED ~ ~.. SHIFT SUPERVISOR,S O OPINION Q ~ 9 g GAP ACTIVITY IN STEAM n w R LOSS OF AC A E D C SS OF ECCS k .AND 3 OR I 3 j $ jh / 7 3y.-1GI REACT RESSURE 4 i 4 tTil 1%LFUN NING $5 a m l<ELIEF NO S VALVES GENERAL B4ERGENCY o J
TABLE 1-b I E4DlH1EllT STATUS FOR FAILURE OF CLADDING AND. PRIMARY COOLA d. -4 .4 GAP ACTIVITY IN _l!!G1-_DRWEILEBESSIRE -.n PR11W(Y C00!AllT f lilGH DRYNELL TEMPFJMTURE CORE tL' COVERED H OR AND n OR l g,CTIVITYlti [n GAP ACTIV11Y IN CONTAlfMINT C) PRESSURE IfTS b [ / 1 A (R 5 MD \\ INE BREAK E R y E O. INCREASING O o IASlv ) j( AND ) CONTAllMINT AND LOSS OF / CONTAINMENT a' OR C00LitJG El ST6 Il1E BREAK [- 5 D0rk i 0F SillFT SUPERVISOR ! AND ) m@ i4slV OPifif0N I g ) A 3 MSIV FA E M 0 l I {l r i AND OR ,o ? g h CORE Ut!COV$Ri!!) }\\ ) p; o \\. %../. ? Rj ~ ./ o CAP ACTIVITY IN Y STEN 4 OR J Rie RY C00LANT .._ GENERAL EMERGENCY n
s O i N g g. TABLE 1-c -i -4 EQUIP!1EllT STATUS FOR FAILURE OF PRIllARY CODLANT B00tlD ? ? ? ? HIGH DRWELL PRESSURE g C) STATUS INDICATES O I ALL CalTAlltEtlT HIGH DRYWELL TEMPERATURE Q co F&lt!TRATIOrs TDT h VALVED OFF OR OR F AND OR N } { Y k, h [ 5 SillFT SUPERVISOR'S g l OPill1011 3 /- STEAM LINE BREAK DOWi-2 RTom4 OF MSLV-E OR AND [p, MSIV MALFUNCTION C-- iECSFAlkE Y3 b* D i zg .C 't I l E" I OR J AND I STEAM Lite BREAK BE1NEEN rn WATER LEVdL'lAN) e g CONTAINMENT AND MSIV hI --4 sulu DECREAsltW)/. l N O e GENERAL EIERGENCY LO3S OF AC POWER o )
i 1. GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PROCEDURE General Emergency - Rally Pofnt Leader 'PR5CEDORE T5TLE ~~ HNP-4726 PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( ) APPROVED APPROVED REV. DESCRIPTION DEPT. PLANT DATE HEAD MANAGER ";;11 2 ; " 3 a. cr _________ u _@ i _f C_wd'_____ p _f(l r fl. __3___._P_a1e_1______________ _t -__4___.. _P_a g_e s_ _1_ _th_ r_u_ _3_ _ _ _ _ _ _ _. _.y p_ _ _ _ _.._ _ _ _ _ _1_ ~~ _- L_t _?g * -_/23,d___ k / F_______. y__-__-_. F_______. F_______- F_______- p_______. l 1 p_______. l l p_______. F_______. f y_ \\J e 9d e. F___-__-. _ _ _ _ _ _ _ _ _ _ _ _ _ p w ._____q N, _ _gg l ____________________.________________s_______ ___r________ HNP-9 MANUAL SET I-
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.t G t..01 n. - s a s .3 PRoccCt nE. tio. une-4.7../-4 . ' ~ Revinion tio. .3 .-. ---- - - -.t ! r : tF,4:- ---- -.:- --. C_' '..: - --, R T ..P r>: DFP^.- ^ R.F01.'::S_TFD IW Orie: r":w; D.wte; Signature: ll l h5 // /] g =-___- ______ REVISIC l Cl#.NCbG MCCE OF.CPERATION ORINTE[NTASDESCRIDEDINFS ( ) No ( ) ;Yes ~ CHANGE JNVD'.VES:- ~'( ) An unreviewed Safety Guestion ( ) Tech. Specs. (/C ) Neither (See bacl< for Saf ety Evaluation if required). .i ~ '5. ( t ' Non-Sa f et y R. e.l at e d.,. (...)..~. . /..).....,- Safety Related ..u..- a...w........ ...: ;,. n,, :..... - . w>. ( r. ) No, F .<..,. Safety /Non-safety Status Change ( .) Yes Attach marised up copv of procedure to thi's form. b~ h ' __ ~ ~ REASCN FOR REGUEST ,Oj' jg l R :. ad u,hu is gib w
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Gr..r E...v...E..*./.:.U_.*.T..:.r. f.'.t J '. g ..i T t.. ___ ___________ _ _ _ _ __ _ _ _____ _ _ __ _ _ _ _ _ _s.t i tu t_e a n = _Th_e _r_e_v.i.s i.o._n_o_f.t._h_is.._o_ro_ce_d.u._re__d_;s t _ e_t co_n_ --- _ _ e_s_t_i_on a_s_.e.x_c_l_a.i.n_e_d_.b.e l_c_u_. ___ _ _ _ _ __ l qu d th rgn5anuences.of an accidnnt ________ __.___1_.__T_h_e._ Er_o_b_a.b. i.l_i_ty o..f.._o.qcu r.r..e. "_m a_n. _ _._ e..._... _ _ _ _ _ ____ _ _ __ _ _' _ _i ta t to safety are no t i ncrease_d___ _____. ____ _o_r__c _al_f.u. _n_c t i_o_n o f_ _e_cu _i :~_e. t _ _ _c_o r_ _ _n __ _ _ . 3 du.a 19._t,b.aea.C Wu a.5_ hoc.nA'a_ _ _ _ _ _ __. ___ _a_b..o_v a _t_h.u.o._a.n a _l v r_a_d_i_n_..N._~r e a a u .a ournote or oerfor-'ance of__th_.e__ ___ _ hi. th ___t_h e.__re_v i.s..i o_n__d_o_e s__n_o_t _c- _. r.e_ _ _e __ _ _ _____ ____ _ __ _ ___ _s.X.s_t_em_. __~___ i f _t__or__r.a_l_fu_n_c_t_i o_n__o_f_a__d_i._f fe_ ____2_. _T_he__oo_s_s_i_b.il i ty o f an_a_c_t__s_a ._.........e.....,.._........ ".~
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6 E. l. Hatch Nuclear Pirnt ~xce< ~o HNP 4726 - om j asvision ~o 4 6 dee Title Page k Georgia Power a ..m ~o 1 of 3 om See Title Page GENERAL EMERGENCY - RALLY POINT LEADER N,_QE 5 dated 1-2-81. This procedure supercedes HNP-4705, Rev. A. CONDITION in process or have occurred which involve actual or Events are imminent substantial core degradation or melting with potential Release can be reasonably 'for loss of containment integrity. expected to exceed PAG exposure levels offsite for more than the immediate site area. B. REFERENCE ~ HNP-4720 HNP-4721 C. GENERAL INFORMATIQN & INSTRUCTIONS inside the primary 1. The primary cally point for personnel protected area is Gate 16, The primary rally point for personnel outside the primary 2. protected area is Gate 1. 3. The alternate rally points are: Environmental Building a. I Skills Training Building or the Outage Training Building b. i The criteria for rally point habitability are: i 4. a. Area dose rate less than 0.5 MR/HR and b. contamination level less than 100 CPM above rally point l background. The locations of decontamination showers outside the primary 5. protected area are: Environmental Building a. b. Outage Training Building h MANUAL SET Tnn.80 l
~ O E.1. Hatch Nuclear Plant ra x t = = ~o HNP 4726
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At vision NO Se'e Title Page k 4 Georgia Power a-O 2 of 3 See Title Page Do not release any person who has received greater than 25 6. rem whole body dose or is suspected to have ingested significant amounts of radioactive materials. Such persons are to be taken to the hospital for examination and further evaluat. ion of exposure. Confer with the Emergency Director before releasing any 7. personnel involved in the incident. Check with the Security Force, general contractors and 8. Georgia Power Construction Department to determine those persons remaining in the plant. If any person (s) is (are) If the unaccounted for, report this to the Shift Foreman. form Shift Foreman cannot account for the missing person (s), a rescue team (s) and initiate HNP-4728, GENERAL EMERGENCY - RESCUE TEAM. ' O. ACTION ,1. After the RET assembles in the OSC, the OSC manager will appoint a Rally Point Leader to take charge of the cally point. The Rally Point Leader should instruct all RET members not assigned a specific function to report with him to Gate 16. 2. rJOTE Leave enough RET members in the OSC to comprise an 1 internal survey team and a rescue team (approximately seven individuals). if the primary rally points are habitable using 3. Determine the criteria in section C.4. If conditions at the primary cally points do not satisfy the 4. in section C.4, proceed to an alternate rally criteriaDetermine if the alternate rally point is. habitable point. using the criteria in section C.4. I Dispatch an appropriate number of RET members to thecontamination. l 5. selected rally points to monitor personnel for Assure personnel gather at the design'ated cally points for frisking by PET members and collect all perso,nnel dosimetry. 6. individuals who were involved Attempt to separate thosewho were working in contaminatedg a.
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E. I. Hatch Nuclear Plant ma== ~o -= HNP.4726 mmio ~o See Title Page 4 4 ~ ~ Georgia Power s( ,.m ~o o... 3 of 3 See Title Page b. Attempt to survey those individuals with emergency response assignments as soon as practical. c. Instruct individuals who were involved in the incident, those found contaminated (greater than 100 CPM above the rally point background), and.those with personnel dosimeters offscale to remain at the rally point, separated from the others and notify the Health Physics Supervisor in the TSC. d. Forward these individuals personnel dosimetry to the EOF and instruct these personnel to report to the EOF (after checking through the rally point) for further evaluation of dose received. Dispatch an RET member (s) to accompany contaminated e. individuals to a decontamination shower (see C.5) and supervise the decontamination procedure, f. Release uncontaminated individuals to evacuate the site on U.S. Hwy. 1 in the direction specified by the Control Room. Report status of the evacuation to the Emergency g. cacility. Operations h. Do not release members of the Radiological Emergency do so Team, except to go to the EOF unless directed to if the by the Emergency Director or Shift Foreman Emergency Director cannot be contacted, i. Assist in routing ambulance to pick u'p any injured personnel. Assure ambulance driver and attendant are provided with TLD badge and pocket dosimeter on entry. j. Assist Emergency Director in bringing emergency under control. S
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t. .I 1 GEORGI A POWER COMPANY HATCH NUCLEAR PLANT PROCEDURE Emergency Samplino Of Primary Coolant PROCEDURE TITLE HNP-4825 PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( ) -_____.,____________________s________________., .r________ APPROVED APPROVED REV. DESCRIPTION DEPT. PLANT DATE HEAD MAN GER _ _ _ s t_t_j_ - _.. _ _.. l 5 Page 1,4, &5 _d' (L_-._ M m e _____2__. .__ age ___t__ru___________, _ _y_. _ _ _ _twj pu '_ _ h_ _.. _[ _[ _f_ _;'.. P __ 3 h 7 E 6 _; _y ____ -_7____.. _P_a3_e_s _I_ _t_h_ru_ _6_ _ _ _ _ _ _ _ _/ _____W_____. w.% _T. U_ _.l_W ./ ?, _3 _/_f _ ____________________4 ..____________________a w________________.-_______. r________________. ..,g_____ s__________,_____. ow ( 3v.r w _ _ _ _ _ _ _ _ t g- _ _ _ _. 4 W c. _________________,_________.________________r________________.,________ 4 HNP-9 MANUAL SET 1
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u __3_.__T_h_e_ma rci_n_o_f__s_a f_e_t.y._a_s _d_e_#i_.- e_d_i_n__the ~ / to thi s revision because the revi.s._io_n.d_o.e._s _n_o_t ___ - dd d _ _i_s not re uc_e___ue ________ ______________. hich would allow a -- i - s_te_- s_e t_t_nes w- ~ __. __c_h.a._n_c e__a.n..y l_i_m_i_t ed__s_a f e t_y sy - -- ~ s a fet._l,i_m_i t__t.o._b_e__e.x.c e_e_d.e._f or_.t.o a._l_l_ow a l imi 1 = hi lS ifications _-_o_o_e_r_a _t i o_n_s to__b_e e_x c._e _e d_e_d_a s__s_t_a t e _ _ ~ _ _ --______- -______~_-- ________________-_________t.-__- .t.___-- -A 4 _,a.,.(,.$.:A ~ s 1, H.NP ') r.. 4 ... g. -....; :.Q.. _ ......_._...s........... M,. - - = ee _..- ."P.- O-
=o=~o E. I. Hatch Nuclear Plant .-acm HN P-4825 "*S Georgia Power d S$c Title Page 7 h 1 of R om See Titin page EMERGENCY GAMPLING OF PRIMARY COOLANT A. PLAPOSE To provide a procedure for sampling primary coolant using the Jet instrument rack as sample location for Units I and II. cladding Pump Sampling will be done with the assumptions of a fuel failure accident of the worse degree possible. B. SAFETY Observe Radiation Protection Procedures. 1. l 2. Observe Guidelines in HNP-4866 C'. PRECAUTIONS Due to the high dose rates and contamination levels which are to extreme care and good .be expected with this kind of an accident, sampling techniques must be adhered to and followed. consulted on a11' activities Laboratory supervision shall be associated with sampling and counting any material obtained for post-accident analysis. All attempts to get samples will be followed with the most Constant H.P. monitoring will be restrictive H.P. practices.A minimum of two persons will be provided and adhered to. required while getting the sample. [QT_E At no time during sampling will I personnel be allowed to receive more than 1.25 R unless a lab i Supervisor or his designee signs FORM 2 of HNP-8002, Authorization to Exceed Administrative Exgosure Guides. l D. EGUIPMENT 1. High range survey meter (PIC-6A, Teletector, or equivalent) 2. Count rate instrument (E-120, or equivalent) 9 3. High range dosimeter (10R) and TLD's MANUAL SET (
E. I. Hatch Nuclear Plant -xiwac ~o om = HNP-4R25 "h'5'* "O Georgia Power d Sbe Title Page 7 e o... 2 of 8 See Title Pace _ 4. Assorted poly bags and bottles l 5. Full PC's'- two pair gloves .I 6. Lead shield on wheels Remote handling tools with various attachments 7. Self-contained breathing air (SCBA) 8. 9. Finger ring T.L.D.'s 10. 75 mi sample bomb 11. Remote sampling equipment control panel or 2P33 P3OO (For 12. Key 1P33 P3OO (For Unit 1 Control Box) Unit 2 Control Box) from " Remote Emergency Handling Tool" l Box, found in H.P. office. Absorbant material to be used in case of spill. ' 13. NOTE The equipment referenced in Section D may not be adequate to perform the sampling requirements. All considerations must be given though prior to actual sampling. A.R.M. read outs located in either control room will be read prior to entry into the Reactor Building. Dose rates will be taken while enroute to the sampling station. Air samples will also be taken while getting samples. .I E. LOCATION Unit I instrument rack Sample will be taken off_the jet pump located on the 130' elevation southside of the reactor 3.,g building. r*. fWu The temporary sampling system will be used until t$e(- s permanentsamplingsystemisinstalledandoperg%I4. W e 9 6 4 MANUAL SET WMG 4R E'
E.1. Hatch Nuclear Plant ma=== ~~t HN P-4R25
=
d Georoia Power A C.se Title Page ~m. c5 3 of 8 See Title Pane NOTE The control panels for the emer-gency sampling system (s) are located on the reactor building 164' elevation on the westside by the stairway. Unit II Sample will be taken off the jet pump instrument rack located on the 130' elevation northside of the reactor building. NOTE The control panels for the emergency sampling system (s) are located on the reactor building 164' elevation on the westside by the stairway. F. SAMPLING (PRESSURIZED VESSEL) will be initiated to get a sample. While sample An R.W.P. is being gotten the dose rates will be taken continuously on the sample bomb and other associated equipment. NOTE Call Control Room to check and assure that valves 831-FO19 and B31-F020 are open before proceeding. 1. Connections One team will go to the sampling station to insure that a. the stem valves (two valves) on the sample bomb are in the Open position, and that the flex tubing connections, connected to the sample (two quick disconnects) are bomb. NOTE Verification of the above information should be communicated via the Control Room to the second team which is positioned to activate the valves at the valving control box. h ' ~ ~ - MANUAL SET 1 .. X
E.1. Hatch Nuclear Plant aaoa aae w 0-~ a6 H N P-4825 REUtSION NO o.,l GeorgiaPower A Ege Title Page ~ 4 nf 8 See Title Paqa 2. Flushina Through Bomb on Control Box. Open valve F306 (chiller water demin.) a. Chiller Water will return.to CRW. Refer to Fig 1. b. Open valves F3OO, 302 and 304 on Control box and flush system with Reactor Water for 10 min. 3. Tcking_Samsle Close valve F3OO, F302, and F304 on control box. a. Purge sample lines using demin water using Section H. b. NOTE When purge is complete, communicate this information via the Control Room to the team standing by at the sampling station. Close manual valves on sample bomb (two valves to be c. closed) using remote handling tools if dose rates require it. d. Disconnect flex tubing from sample bomb (two disconnections to be made). NOTE Any water which may have been dripped when the disconnection was made must be covered up or cleaned up as soon as possible. e. After survey of the lead cask has been done, the sample is returned to the lab or other area as required by Lab Supervisor. NOTE Upon the discretion of a lab Supervisor, the sample may be analyzed in the Hatch Lab if dose rates are low enough. %A cp yb*.<s' s e MANUAL SET TM889
E.1. Hatch Nuclear Plant au== ~o a-o= HNP-4825 u muw uo .Eee Title Page d GeoroiaPower A 7 .m.o D 5 of 8 See Title Page C. SAMPLING (DEPRESSURIZED VESSEL) NOTE An R.W.P. will be initiated to get a sample. While sample is being gotten, the dose rates will be taken continuously on the sample bomb and other associated equipment. NOTE Call Control Room to check and assure valves B31-F019 and 831-F020 are open before proceeding. 1. Connections One team should go to the sampling station to insure a. that the stem valves (two valves) on the sample bomb s are in the open position, and the flex tubing connections (two quick disconnects) are connected to the sample bomb. NOTE Verification of the above information should be communicated via the Control Room to the second team which is standing by to activate the valves from the Control Station. 2. Flushino Throuqh Bomb a. Open manual valve (1821 NO33C TVI for Unit 1 or 2921 NO33C TVI for Unit 2) on jet pump rack. The valves are ( painted red and are usually in the open position. Must check to make sure the valve is open, b. Open valve F306 (chiller water), F3OO, F301, F302 and F304 on control panel. Flush system for 10 minutes ( with reactor water, sample may now be taken. Refer to Figure 1. I 3. Taking Sample l a. Close valves F3OO, F301, F302, and F304.on contro ox. b. Purge sample lines with demin water using Sect M H. l
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MANUAL SET e
E. l. Hatch Nuclear Picnt aa=== ~o > > = HN P-4825 at m'oa m 5,feTitlePage Georoia Power ah 7 ..J ..m ~o O 6 of 8 See Title Paqe NOTE When purge is complete, communicate this information via the Control Room,to the team. standing by at the sample station. Close manual valves on sample bomb (two valves to be c. closed) using remote handling tool is required by dose rate. d. Disconnect flex tubing from sample bomb (two disconnections to be made) NOTE Any water which may have been dripped when the disconnection was made must be cleaned up or covered as soon as possible. After survey of the lead cask has been done, the sample e. and cask are returned to the lab or other area as required by Lab Supervisor. l NOTE Upon the discretion of a lab Supervisor, ~the sample may be analyzed in the Hatch Lab if dose rates are low enough. H. SYSTEMS FLUSHING Systems will be flushed upon taking a sample to lower tfee dose rates in the local area. Flushing time will depend upon the amount of crud stuck in the tubing lines and valves and dose rate in the area (Background). 1. Open valve F305, F301, and F303 and flush for 15 minutes or l until Lab Supervision specifies otherwise. for Close valves F301 and flush through pressure regulator 2. 30 minutes or until Lab Supervision specifies otherwise. I 3. Close valve F305 and F303; this' returns system to a ready-to-sample system. 3 ()k y& MANUAL SET
==~ t:.1. M ten NUCIUar Plant
=
H N P-4825 Er:e Title Page 7 Georgia Power s ..- ~o 7 Of 8 See Title Pace NOTE Systems flushing (Section H above) may be used to demonstrate skills in sample taking. NOTE Recommended route is through the railroad airlock, around the CSTs and in through T-16. NO_Tg After obtaining the sample, refer to HNP-4828 " Transferring Primary Coolant from 75 ml Bomb" and HNP-4829 " Analysis of Primary Coolant." s 1 R MANUAL SET
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i I ,3 CEORGIA POWER COMPANY 't HATCH NUCLEAR PLANT PROCEDURE Airborne Radioactivity Concentration Determination for Abnormal or_ Accident Conditions PROCEDURE TITLE HNP-4R26 PROCEDURE NUMBER Lab RESPONSIBLE SECTION t SAFETY RELATED ( X ) NON-SAFETY RELATED ( ) APPROVED APPROVED REV. DESCRIPTION DEPT. PLANT DATE HEAD MANAGE 2 Pages 1,3,5 & 9 g --_- -,._ y 4- - ,r ---

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E. l. Hatch Nuclear Plant >~ma HNP-4826 atws'oa ao Georgia Power d See Title Page b ..e. o 1 of 11 om See Title Page AIRBORNE RAOTOACTTVITY CONCENTRATTON DETFPMINATTON FOR ARNOPMAL OR ACCIDENT COMOIT TONS A. PURPOSE To establish guidelines for an air sampling program for abnormal conditions based on dose rates and sampling conditions. B. S_AFETY Observe Radiation Protection Procedures and Plant Hatch Emergency Procedures. C. GENERAL is recognized that for normal plant operations and maintenance It sampling program outlined in HNP-8013 is adequate. work the air This procedure is intended to supplement HNP-8013 and to specify some suggested additional instrumentation and steps to be used during abnormal conditions. D. FGUIPMENT CIM-CAM located in Technical Support Center. 1. cart supplied with the following equipment either 2. Lab taken out of regular service and reserved dedicated (i.e., for emergency use) or readily available for use near the OSC. One SAM 2/RD-22 calibrated and set at the Iodine peak, a. with detector and sample holder. One low-volume air sampler with cartridges and filters. b. One high-volume air sampler with cartridges and filters, c. teletector or d. One high range survey meter (P C-6A, equivalent.) cartridges for the low-volume' e. One box of extra charcoal and high volume samplers (i.e., two inch Cesco and IC-1 and four inch Mersorb car,tridges). f. Extra filter papers for samplers. A4 At least two silver zeolite cartridges each (tf8 Fit g. low-volume and high volume samplers, b. One complete set of protective covera i. One M.S.A. Model 401 Air Pack Respi c. MANUAL SET
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~~=4 H NP-4826 atwsio= ~o GeorgiaPower A fHe Title Page~~
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2 of 11 See Title Paqe j. One high range dosimeter. k. One E-120 Low r ange instrument. 1. 50 feet of extension. cord (two 25 foot cords). Purging apparatus. m. E. PROCEDURE CAUTION During the initial few minutes or perhaps hours following an abnormal event, the exposure rates and airborne activity levels may not be known and therefore extra precautions may need to be taken. After the conditions become known and extra precautions may be reduced or have stabilized the Refer to HNP-4866 for specific exposure control minimized. guidelines and limits as well as ALARA considerations. NOTE Air samples will normally be taken on directions from the Health Physics Foreman or Supervisor or other responsible individual as the situation permits. The locati~on and type of sample will usually be specified in the directions. 1. Initially, don the protective clothing and respirator. Be sure to get the high range dosimeter. Call the Control Room and obtain A.R.M. readings for the area if you can. Take the low volume air sampler with the c,harcoal and, 2. particulate filter installed, the high range survey meter and one twenty five foot extension cord to designated area. 3. As you proceed to area, observe dose rates taking note of conditions. Try to determine if dose rates are due to piping and equipment or if it is from airborne activity. This can be done by taking several quick measurements in
~~Follow, different places near equipment and in open areas.~~
at all times, guidelines in HNP-4866. When in the designated area tare air sample as described in 4. Place sampler at waist height to shoulder height HNP-8013. for best sample. If dose rate permits, collect sample for thirty minutes. If it is necessary to reduce, sampling t' then care should be taken in data interpretation and a t of sensitivity determined by HNP-8013 D and G. + = MANUAL SET ~
aaoctw as.e E.1. Hatch Nucisar Plant l l-**' H N P-4826 umion o "SheTitlePage Georgia Power s Uf II See Title Paga 5. After sampling is complete, turn off sampler and take all equipment back to location of Lab cart. If the H.P. Office and Counting Room are habitable, then bring all equipment to is normally done. All Counting Room and count samples as equipment should be handled with rubber gloves and wipe tested before it is carried outside the operating If the equipment is contaminated it is to be buildings. left in a controlled area. Remove the charcoal and particulate filters and place in plastic bag. Take the filters to the location of Lab cart for counting and analysis. 6. Be sure to follow correct step-off pad undressing procedure ~ to remove protective clothing before leaving the operating buildings, The above sequence may be repeated until conditions are 7. Thereafter known and stabilized and any trends established. it may be decided that it is unnecessary to dress out for subsequent air sampling. PURGING OF CHARCOAL AND SILVER 7.EOLITE CARTRIOr:S F. 1. After sampling is complete, obtain a breathing air bottle from the Gas Storage Building. Connect the purging apparatus found to the breathing air 2. bottle and set the regulator pressure to 5 (five) P.S.I.G. Extend 50 feet tygon discharge hose to the outside of the 3. building so as not to contaminate room with Xenon. 4. Place radioactive sample (silver zeolite or charcoal) into holder on purging apparatus.' 5. Check gamma dose rate level on outside of sample holder and note radiation levels. or less on Open inlet valve and adjust flow to 80 L.P.M. 6. purging apparatus. (95% retention for I-131). 7. While sample is being purged, keep checking gamma radia ' n levels on sample holder. When radiation levels drop plateau or drop low enough to allow sample to be coun stop purging of sample. 8. Remove sample from holder, wrap in saran wrap a alyze for 1-131 as per section G. e MANUAL SET ' ~..... ~-
~~t== ~o E.1. Hatch Nucinar Plant HNP-Ag2A i-~~
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GeoreiaPower A S Title Page O 4 of 11 om _ Sea Title Page G. COUNTING AND ANALYSIS Record all data on Normally counting may be done per HNP-8013. Iodine cnntentrations HNP-4826 Data Package 1 (Data Sheet,1). in the may be determined by placing the two inch Cesco cartridge t This .CIM-CAM gartridge holder and reading counts per minu e.in the formula on Figure 2 number then would be used for a two inch charcoal cartridge" -10 (NET CPM) (4.5 x 10 ) Solume in liters) (0.939) (Det, efficiency) Iodine concentrations may be determined using the SAM-2/RD-22 set up by the instructions that follow. 1. Operation of Instrument. Verify that the RD-22 detector is properly connected to a. the SAM-2 detector connector. Connect SAM-2/RD-22 to power supply and turn POWER b. switch ON (rear panel). and set Operate STABILIZER switch to ON (rear panel) c. CH1 switches to "IN" and "+". Set Chi THRESHOLD and H.V. ADJUST to settings See label on top of d. determined from last calibration.. instrument. Set CH1 WINDOW to ".72". e. "4.0" and place CH2 WINDOW to Turn CH2 THRESHOLD to setting determined on Data Package 2 (Data Sheet 2). f. for background Place CH2 switches to "IN" and " " g. subtraction. Set desired count time and TIME-STOP-MAN switch to TIME, h. enclosed in plastic, in the proper i. Place the sample, detector and press the RESET-START geometry to the on Data Package 1 (Data switch. Note the shelf number Sheet 1). j. When counting is complete, the value in the display is " net" counts for the Iodine activity. Reference On'y ~ MANUAL. SET
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~~HNP-4826 "GIeTitlePage GeorgiaPower A o... G of 11 See Titin Parle NOTE If negative counts are obtained when counting a CH2 switches must be. set to "OUT" and~~
~~sample, "OFF" causing gross counts to be observed in the display.~~
Recount sample and then subtract background found on Data Package 2 (Data Sheet 2) manually to obtain net counts. k. Using Data Package 1.(Data Sheet 1), calculate the Iodine concentration of the counted sample using the following formulas: (1) Silver Zeolite Cartridges: (NET CPM)(4.5 X E-10) = (Volume in Liters)(.95)(D.E.) Iodine Activity (uci/cc) (2) Charcoal Cartridges: (NET CPM) (4.5 X E-10) (Volume-in Liters)(.999)(D.E.) Iodine Activity (uci/cc) = NOTE -10 a. 4.5 X 10 = conversion factor to get from disintegrations per minute to microcuries. .95 = filter media collection efficiency for b. silver zeolite cartridges. .999 = filter media collection.efficien'cy for c. charcoal cartridge. in liters of sample = sampling time d. Volume flow rate of air sample (LPM). (min) x = detector efficiency at specific shelf e. D.E.
~~height, Net CPM = Net counts per minute of sample; f.~~
net counts divided by count time. 1. Operational calibration must be performed DAILY when instrument is in use, see Section F.2. 2. Daily Operational Calibration Verify that the RD-22 detector is roperly coggegted to the SAM-2 DETECTOR connector. BJerCBCO W.i'l a. MANUAL SET ~
E. I. Hatch Nucl@ar Plant ~ a= = =*"o E== HN P-4826 'SdeTitlePage o../ Georgia Power ah G of 11 Goo Titio Page Connect SAM-2/RD-22 to power supply and turn POWER b. switch ON (rear panel). and set Operate STABILIZER switch.to ON.(rear panel) c. CH1 switches to "IN" and "+". Set CHI THRESHOLD and HV ADJUST to' settings determined d. from last calibration. See label on top of instrument. Place CH1 WINDOW to ".72". Set CH2 window to "OFF" and e. "OUT". Set count time to 1.0 minute and TIMED-STOP-MAN switch f. to TIMED. Record a 1.0 minute count of CH1 background at these g. settings on Data Package 2 (Data Sheet 2). Set CH1 switch to "OUT" and "OFF" and place the CH2 h. switches to "IN" and "+". Place the CH2 THRESHOLD TO 4.0 and adjust the CH2 1. WINDOW until the same background count found with CHI Note this WINDOW setting on Data Package is obtained. 2 (Data Sheet 2). j. Set CH1 switches to "IN" and "+" and CH2 switches to "IN" and " ". Place a Ba-133 source in proper geometry to the k. Counts detector on Shelf # 3 and count for 5 minutes. display window represents the NET observed in the counts of the source with the background subtracted. Record in counts per minute on Data Package 2 (Data Sheet 2). NOTE If negative counts are obtained when counting a sample, CH2 switches must be set to "OUT" and in the "OFF" causing gross counts to be observed Recount sample and then subtract display. background found on Data Package 2 (Data Sheet 2) manually to obtain n.et' counts. Divide the NET counts per minutes of the source by the 1. known disintegrations per minute of the source and multiply by 1.19 to get the efficiency of the detector (D.E.). ,,ge Onh MANEL SET 70e930 - ' - - ~ ~ ~ ~ -~- .________o
E. l. Hatch NuCicar Plant aa x tovat = ^~a"* HNP-4826 neveoa
~~Georgia Power A See Title Page o.et 7 of it See Title Page NOTE The 1.19 factor accounts for the difference in yield of the Ba-133 and the I-131 gammas.~~
R peat steps k and I with shelves 4 and 5 to obtain a m. detector efficiency for each of the three shelves, Complete Data Package 2 (Data Sheet 2) on a daily n. basis, only when SAM-2/RD-22 is in use. 3. Use of Silver Zeolite Cartridges. It may be desired to run two concurrent samples, one with a IC-1 activated charcoal cartridge and one with a silver zeolite cartridge, (when available) and determine both total noble gases and separate Iodine gases. A Staplex or similar high volume sampler may also be used by removing the filter head and inserting the 4" silver zeolite cartridge into the suction opening of the sampler. H. -USE OF OTHER SOURCES OF INFORMATION While in the plant, observe CAM's and CIM-CAM's in the areas traversed. Also be alert for A.R.M. local readouts and alarms. At times it may be desired to roll the entire cart and all equipment to the designated areas and take the samples and do initial counts before returning to the T.S.C. It is intended that the cart be completely equipped to sample pny area and.do complete analysis report back to the T.S.C. what the findings are. l l l l e i 9 l O Gd ~
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E. l. Hatch Nuclear Plant - xtou =~o ~+a~ a HNP-4826 "E v*o" *o 'See Title ~Page Georgia Power d 4 ..e, o 10 of 11 Ann T4+1a Paga PROCC0 tite DATA 5'/.CN/(,E OOCLRTNT fM:JFK8-ARN,-P EER1/L to:J OA-tPL NO: RTYPE _G E Q] XRET: TOTAL SHEETS: _ g FREGUENCV: _A Q ggyired COPPLETED DY: DATE COrfLETED: I HAVE REVIEWC0 THis DATA PACKAGE FrJ1 COMPLETENESS MO AGAirGT ACCU *TM4C CRITCRIA IN ACCORDANCE WITH Hr#-830. ACCEPTABLE LNACCEPTABLE REVIDED BY: DATE REVIEWED: I REMNiks: I Page 1 of 2 StP-4826 R04 i b ~~. FIGURE _2 Page 1 of 2 MANilAL SET w-r-
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a GEORGIA POWER COMPANY a ~ -1 HATCH NUCLEAR PLANT PRDCEDURE DJr unil Containment Samnling t tnder FmeroencL onditions C ~~~~ ~~ ~~ PROCEDURE TITLE HNP-4R31 PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( X) NON-SAFETY RELATED ( ) APPROVED APPROVED BEV. DESCRIPTION DEPT. PLANT DATE HEAD mat GER 1 Page 1 yy yg / l, jy--. 83_'_ ___7_j'f,, _/ 2 .. Pa9_e_s_ _1_&_ _2_ _ _ _ _ _ _ _ _ _. _'y _ _,,_ _/ / /->
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x s REVISIC'l CHAT:GCS MOOE OF.CPERATIOtt OR JNTENT AS CEGCRIDED IN FSAR: ( )gYes ( %) No CHANGE JNVOt.VEC: ( ) An unreviewed Safety Guestic.n ( ) Tech. Specs. ( A,) Neither (See bacit for Safety Evaluation if required). ..n.,... . ~. - .Non-Sa f et y R e l at e d...(, -.).'.. y ..) ( . Safety.Related ...:.n... -..,., - 3......m........ ,.....m...s..m...-. Safety /Non-safety Status Change ( ) Yes .( &) No, Attach marl <ed up copy of procedure to thi's f,orm. REASON FOR REGL'EST______ .v _ _ e - -;..e.- g - _..t _ A,y s %_ 2 m _e u P. 3 W B,,.7 A9.__ D.d,+< " hl.e e r4ts_h..als_msl.w.pf.r.c.+ M1 Yu _cem.t..lbia&d._. Bd.-w "-___----________ a . Cr> e.3.__n_.___.Re_-Icn o_r _b "F ~ 9 " ed&. 4 cit : " _fq) p.p._L.t.__g-3 n %. M a s g_n &. %. L _f i .D_s,.2_v._.11 ,, I we.seth_s_1G_s.$1he.+ - i.,.._h%te.26.d.tedo.h.44_ 1 8.R. M hais. 6 satpy.,.u?s.eEn21.{.vt.=L_"_-__---____ .(s>_R. s. p. 7._-_n.cL&t_-___ _ j e 3_. P. e----------_-o%- g_%__i_t.h 6_-_l_ab_e_le_}._uh A_t_e ~C 4& A g l I'dre., d ~ v [p__ ?b, m ,h..f([-_O S_L* e /d /20U AM ltJ @._-.A.Q-
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6 5.v....E.. _ y. E.../...:. 0_/..T..t.r. M v The revis i on o f this orocedu re d :s s___.e.t._c_o_n.s..t..i.tu t_e_an__u_ 4 question as' exclained belc.s. I f id t 1 T_h e_ gr_o_b_a.b. i_l_i_t_y o..f...g_c cu_r_r e, _- = a.n.d__t_h e..c_o_n e.nc_u_e_n_c_e s_ s= m or mal fur.ction o f ecui:.s-t { _c_or_t_a.n..t. t_o__s.a.f_e_ty_ _a r.e__n_o.t._i_n.c._r_e a abov e Lh..e. s s._a_n_a_l v.l.a. d_i n_.N_ _n io _d.u.a,_.i9._taS..a.c a cb."n.S b_e c uJS a__ aa _a a a r the revision does not ch'ar.:e the_ou_r_c..o.se__o.r._oe_r.f._or_m_a_n_ce syste.m,. _ * .m t -__or mal function of a_ di ffere_n_t v_o.e.. _ ..id t .. ~ -f ~ . ___ 2_. _T_h_e _po_s_s_i_b_i l i ty o _ a..n._a_c_c__s_a n..__~:.-......,w....................,- . than analyzed in the FS_.2.0 c:ss _not re_su_l_t__f.r.o_m_ this chance because_ __
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= - / b. th revision do_e_s_no_t __ _'____i_s__n_ot__r_e_d.u_c_e_d__du_e _t_o_t_h._i_s re_v_i_s i_o_n__b a s i hich would allo _w a_ ____._ _c_h a_n_c e__a_n.y._l_i_m_i_te_d_._s_m_fe_t_y s.ys_t_e, s ett n_es. w i f __s_a f_e_t;/ l,.'_a_i t__t_o_b_e_.e._x_c e e d_e.d._o_r _to__a_l_l_ow a__l.i dsf as stated in Technical Soecifications_. b ____ _o_.oe ra ti o ns _t_o___e _e x_c_e _e _ _______ _____ ___---_- - =- s. s.v .... ~. J _____________________s.__-_._____-.:--_------_--_-- A HNP-9 ~. s _..._.._.~...-.,.:......_..._.e. s
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E. I. Hatch Nucisar Plant aaocioua6 mo a~ ~a H NP-4831 aemio= =o GeorSaPower A Gae Title Page 3 l ..e. o... 1 of 5 See Title Pa00 DRYWELL CONTAINMENT SAMPLING UNDER EM'ERCFNCY CONDITIONS A. PURPOSE To provide a detailed procedure for sampling Drywell Containment during a Site Area or General Emergency. 8. REFERENCES 1. HNP-7215, " Gamma Spectrometer System Ge(Li)" 2. HNP-7407, " Gas vial Sampler" C. SPECIAL EGUIPMENT cabinet. Sample shield-stored in the emergency sample 1. Hood in lab with shielding behind which to unload sample. 2. 3. Special counting shield for 14 mi viel. 4. High range dosimeter, TLDs, Finger Rings, Protective Clothing, Polybags, and air packs. 5. Remote tools to handle sample. 6. Radiation work permit. D. PRECAUTIONS Due to the high doso rates and contamination levels which 1. may be encountered, dry runs of sampling techniques should be performed before doing actual sampling. Laboratory supervision shall be consulted on all activities 2. associated with sampling and counting any material obtained for post-accident analysis. All attempts to get samples shall be executed with the most 3. restrictive H. P. practices. Gonstant H. P. monitoring shall be provided and adhered to. A minimum of two persons is required to obtain a sample. Ek Q, gQ ato MANUAL SET .fW44 98 e
r. E.1. Hatch Nuclear Plant e= c-cea H N P-4831 ac w om ao Georgia Power d W e Title Page 3 ..m ~o 2 of 5 See Title Paae - 4. Be aware of the time it would take to retreat and the fastest way to exit high radiation areas. NOTE At no time during analysis will personnel be allowed to receive more than 1.25 R unless a Lab Supervisor or his designee signs Form 2 of HNP-8002, Authorization to Excead Adminis-trative Exg_osuro Guides. E. SAMPLING DRYWELL CONTAINMENT 1. Obtain a 14 ml viel with rubber stopper, precision sampling needle, and 3/8" male-to-male swagelock connector.- Also have a portable lead pig shield ready for transporting sample when obtained. Notify Health Physics you are ready and need a person to 2. Put on provide radiation monitoring services for you. protective clothing required on RWP. 3. Prior to taking containment sample, the 14 ml vial must be evacuated. This must be done at any of the following locations: Unit 1 147' mezzanine, Unit 1 or Unit 2 Pretreatment Sample station. Evacuation is done by:' a. Checking that the inlet and outlet valves to the vial sampler are open per Table 1 of HNP-7407. Install a sample bottle using the vial handler into the b. sample positioner. Check that the vial is seated so that the limit switch closes. l c. Turn power switch to "ON." d. Turn the vacuum pump on. e. Verify the lights for valves and vacuum pumps are illuminated. Turn function switch to SAMPLE PURGE EVACUATE VI AL. f. indicator is approaching g. Check that the vacuum gauge 29.5. 29.5 After the vacuum gauge indication of approximat h. is attained, and remains at the level at leas turn the function switch to PURGE SA LINE.
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~~MANUAL SET~~
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E. I. Hatch Nuclear Plant caxt=aa~o %= HN P-4R31
~~4 atv$c" No GeoroiaPower A S6e Title Page~~
..mo D 3 of 5 om See Title Pane 1 and Valve 2 lights are lit and Valve i. Check that Valve Check that the vacuum reading is 3 is. closed. remaining constant. j. Remove vial. Turn the power switch to OFF and the function switch to k. OFF. Close inlet and outlet valves. Proceed immediately to drywell containment sample point 4. Use exposure limit taking radiation surveys as you go. guidelines in HNP-4866. connect the Using 3/8" male-to-male swagelock connector,line directly below V3 to 5. tygon sample line extending from V5 or on Unit 2 to the tygon tubing directly below V4. 6. Open valve V3 and V4 (V4 is not on* Unit 1). Turn grab sampler mode switch located on panel above to OPEN. 7. 8. Close V6 and V8. Allow 2 minutes to flush line. NOTE While waiting for 2 minute flush, move away to area with lowest dose rate until you are ready to start sampling. 9. With precision sampling needle, (push green button in and insert into rubber sample cover plunger down to expel air)Now pull plunger handle to 5 m1 end located next to V5.After approximately 30 seconds press red mark on syringe. button to IN position. Press syringe plunger to compress in syringe. Allow p1'unger position to 1, f gas containedRecord volume and time of sample on Data Sheet I stabilize. 10. Insert syringe needle into stopper of 14 ml vial. Push Press plunger to evacuate green button to IN position. red button back to IN position. Remove syringe. Now push syringe. l 11. Load 14 mi sample vial into emergency pig. Leave samp to facilitate additional sam system allignment as is, return systegj o if needed. At termination of emergency, , q, c Normal. W MANUAL SET
E. I. Hatch Nuclear Plant a ==== = -= H N P-4831 aavision w 'Spe Title Page Georoia Power A 3 o o.u D 4 op q See Title P.,np 12. Transport to fume hood in lab. 13. Remove sample from lead pig and prepare for counting. 14. Refer to HNP-7215 for counting. NOIE If sample is too hot ( 20% Dead Time), use emergency sample holder and lead brick with col-lomator hole to count 14 mi vial. F. DISPOSAL OF DRYWELL CONTAINMENT SAMPLE l 1. Remove from Ge(Li) Detector. 2. Place sample in plastic bag labeled with date, time, activity, and location sample was taken. '3. Dispose of sample in accordance with HNP-4832. O 9 9 e b 'e 6 MANUAL SET __________________________}
E. l. Hatch Nuclear Plant -oce=as ao a ~ ovat HN P-4831 arvm'om U<e Title Page Georgia Power A 3 o... See Title Paca 5 of 5 DATA SHEET 1 Name: Date: TIME SAMPLE VOL. SAMPLE ACTIVITY SAMPLE LOCATION (ml) Rema rl< s: 1 I l i ( I o l 1 MAMAL SET I
~ CEORGIA POWER COMPANY 3 HATCH NUCLEAR PLANT PROCEDURE Naturally Occurring Phenomenon PROCEDURE TITLE HNP-48ci8 PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFEIY RELATED ( X ) NGN-SAFETY RELATED ( ) APPROVED APPROVED REV. DESCRIPTION DEPT. PLANT DATE HEAD MANACER .___1- 'l Page 1,2,6,9 & 10 / o s <A ..u, s< vl % 6 e --...9 N. -_ Q ~ ,v s% Y,Y 2 HNP-9 s8 6 MANUAL. SET m.. -..m. -= a
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- de#- 3.- The ma_r.cin o_f safety s'. --_-.---_ot reduced _due t_o th'.s. revision becau_s_e_ the revis_ ion do.e is n = - - -= _t_e ' s etti nes_whi ch wo_ ul d al l owa_- - _---__cha n.c e _a_n.v. l_i.:r._i t e d s a f e ty sys --- -- l,init _to_b_ e _ exceed.e d o_r__to a.l. lo?r a limi tinc condi tion for safet'v ope.r.ations to be exceedef.a.s s.tated_ in' Technical _S_ oecifica.tions._. --- a. a- -- _- -- --.- _ -~-__ .n % 6:- D ?> 4 7... H.NP-9 .f.,'. .t l 'H... F. -e..... 1 wa nL- .... : ~...... ~....%... :.... ......-...m- =--._*... ... ~.
ea = =at~o E. l. Hatch Nuclear Plant A= HNP-485R 4 REVISION NO 'de Title Page-Georgia Power A S ..m No 1 of 12 gf s o.... See Title Pace NATURALLY OCCURRING PHENOMENON NOTE (This procedure supersedes: HNP-43OO, Revision 4 approved 7/25/80; HNP-4301, Revision 4 app-oved 9/18/79; HNP-4302, Revision 1 approved 9/18/79.) A. CONDITION: EARTHGUAKE seismic activity, and ground l The plant accelerographs indicate: motion is felt, or outside sources report ground motion. 8. OPERATOR ACTIONS For a seismic shock with only annunciator D076 (Seismic Instrumentation Triggered) in panel H11-P657 and the RED 1. INDICATOR LIGHT (L51-DSOO1) on the TIME HISTORY ACCELE in panel H11-P701 which is less than OBE (0.08g), (L51-R600)to operate and proceed with plant inspection. continue Declare a NOTIFICATION OF UNUSUAL EVENT Follow Figure 1. EMERGENCY and refer to the applicable HNP-4400 series procedures for the appropriate response. For a seismic shock with annunciation as stated in 8-1 and 2. any of the following: a. Unit I Seismic peak shock recorder high G 1evel alarms. (1) (D070 in panel H11-P657 is set to actuate when-100% OBE of 0.089 vertical has 6een exceeded). NOTE One or more amber lights on peak shock annunciator panel (L51-R620 on panel H11-P701) will be on. These annunciator lights are set for 100% OBE level at 4 (North / frequencies and 3 directions South, East / West, Vertical). This info will be recorded in C.1.A. b. Unit II larms. Seismic peak shock recorder high G~1evel (1) e when (0068 in panel 2H11-P657 is set to actu d. 100% OBE (.08g) vertical has been exce ~, MANUAL SET e
enoct uuwe.o Na C. l. r1dLGil INUGitidt r~ld3It HNP-4858 amw>~ ~o Gee Title Page GeorS a Power d 2 i
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See Title PaGa 2 of 12 NOTE One or more red lights on peak shock annunciator panel (L51-R620 on panel H11-P701) will be on. These annunciators are set for 100% OBE level for 4 frequen-cies by 3 directions (12 total) (North / South, East / West, Vertical) This info will be recorded in C.1.A. (2) " Seismic switch tripped" alarm (0069 on panel EH11-P657) which is set at OBE level of.08g. Shut down the affected unit (s) and declare an " Alert" emergency. Follow Figure 1. Refer to the applicable HNP-4500 series procedures for appropriate response. NOTE If any of the situations in section 2 occur, the operator should play back the Time History Recorder tapes to determine the actual maximum g acceleration magnitude. (For instructions on retrieval of seismic data, see HNP-1-3980 M - section G.2.) (3) For a seismic shock with annunciation as stated'in B.1 and B.2 above and the maximum g level measured by the time / history accellograph recorders is greater than OBE levels (0.15g), shut down the affected unit (s) and declare a site area emergency. Follow Figure 1. Refer to the applicable HNP-4600 series procedure for appropriate response. (4) For a seismic shock resulting in massive damage to the ECCS system, refer to the applicable HNP-4700 series procedures for appropriate response. l (5) Notify Plant Management. C. SUBSEGUENT OPERATOR ACTION 1. A post earthquake instrumentation review will be conducted l as follows: N Record the Peak Acceleration recorder lights (Red,0bnd i l a. Yellow) on Data Package 1. Have three qualififdf l operators verify the lights before resetting panel. b. Check the feedwater to steam flow for a mism h. Q l r,wal SET l
E. I. Hatch Nucicar Plant ~=~a< ao >~,- H N P-4858 nemion wo Georgia Power d Sue Title Page 2 .. m 3 of 12 See Title Paqa Check the applicable neutron range monitors for c. abnormal readings. d. Check all systems for abnormal power changes. C eck the drywell for temperatures, humidity, pressure e. and the sample system for abnormal activity levels. Check the drywell sumps for high level and/or flow, f. Check all other equipment drains and sumps for high g. level and/or high flow rates. Check the torus water level recorder for high or low h. level. 1. Check all area radiation monitors for excessive activity levels. Check the 4160 volt and 600 volt auxilliary equipment J. for trips. Check the turbine generator instrumentation. k. 2. Notify the Test Shop to do each of the following as required by Figure 1. a. Retrieve record plates from the Peak Shock Recorder Install new (L51-N105) per HNP-1-5631 and record data. record plates to record after shocks. Retrieve record plates an'd tapes from' the Teledyne b. PRA-103 Peak Recording Accelerometers per HNP-1-5625 and Engdahl PAR 400 Peak Acceleration Recorders per HNP-2-5626. Install new record plates and tapes to record after shocks. Retrieve magnetic tapes from the Time History Accelecograph recorder, L51-R600, per HNP-1-3980. Make' c. hard copy records and install new tapes. d. Restore all instrumentation to operable status with 24 (Unit 2 Tech. Specs. 4.3.6.2.2), hours. Recalibrate all seismic monitoring instr,uments actuated e. during a seismic event within 30 days. Notify Rinemetrics, Inc. (telephone 213-795-2220) to pe m calibration of the Time-History Accelerograph Sy m and the Peak Shock Annanciator System (Unit 2 T Specs. 4.3.6.2.2). ~ <gP I MANUAL SET
E. l. Hatch Nuclear Plant raou = = "o
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"* *So" *o Sye Title Page Georgia Power d o 4 of 12 See Title Paqa 3. A plant inspection should include but not'be limited to the following* a. Inspect the main steam lines and turbine extraction steam lines for damage. Inspect the condensate piping and pumps for leaks and b. damage. Inspect the feedwater piping and pumps for leaks and c. damage. d. Inspect the turbine oil system for leaks or damage. Inspect the RWCCW and service water for external e. leaks. Check for an internal leak by monitoring the RBCCW surge tank level. f. Inspect the intake structure and associated equipment for damage. Inspect the off-gas stack and equipment for leaks. g. h. Visually inspect the diesel generators and their switchgear to assure the units are intact. Perform the' routine surveillance test to prove the system is operable. Tie each diesel generator onto its bus and isolate its bus from the system one at a time. Minimize operation of the diesel generator in parallel with the system because a major transmission line fault, which is probable during this event, could cause damage to a parallel diesel generator. i. Inspect the switchyard for damage. j. Inspect the turbine pedestal for damage. k. Inspect instrument racks and control p h-'s for damage. 1. Ir.spect CSCS components for damage. m. Inspect fuel pool for damage, Inspect all plant batteries fur damage. n. 4 Inspect instrument and service air system. o. Inspect plant communications for damage. p. 4. Evaluate the post earthquate instrumentation rev' W and plant, inspection. p k MANUAL SET
~ E.1. Hatch Nuclear Plant acmu=
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~~H N P-4858 mvisio'e 'ao gre Title Page Georgia Power d~~
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Completer analysis of seismic data. NOTE The results of the plant inspection will immediately be reviewed by the Plant Review Board and appropriate surveillance testing will be specified. A special report must be submitted to the NRC within 10 days. D. REFERENCES 1. S-40827 Seismic Instrumentation Earthquake Response Manual 2. Unit 2 Technical Specifications - para. 3.3.6.2 3. HNP-1-3980 Seismic Instrumentation F.T.&C., Section G. Restoration of Seismic Instrumentation and Data Retrieval 4. HNP-1-5625 Calibration of Teledyne-GeoTech PRA-103 Peak-Recording Accelerometers 5. HNP-1-5631 Peak Shock Recorder Calibration 4 6. HNP-2-5626 Calibration of Engdahl PAR 400 Peak Acceleration Recorders. 6 j es a 4 MANU!R SET - ^-
.. ~ =.L. " = = = E. I. Hatch Nuclear Plant + HNP. 4858 l "t*oa ho 1 See Title Pago Georgia Power d ~,.o
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_f 6 of 12 See Title Page E. CONDITION: TORNADO The plant shall normally be. alerted by outside communications and/or local indications of a tornado condition in the area which may disrupt the transmission system or present a hazard to the station facilities. The plant will remain at full availability unless dictated to be otherwise by deteriorating conditions. As evaluated by supervision. F. OPERATOR ACTION 1. Thoroughly inspect the plant for loose materials which may be blown about. 2. Instruct contractor personnel of the event and advise them to commence preparations for the securing of construction materials and equipment. 3. Remove or secure all outside scaffolding and swinging stages. 4. Close and secur.e all Reactor, Turbine Building, Switchyard l and Off-Gas Filter Building doors. 5. Plant personnel shall seek refuge within buildings and report to their supervisors for specific instructions. 6. Perform routine surveillance test of the standby Diesel-Generators in anticipation of a potential off site power failure, if a tornado has been sighted in immediate area or known to be headed in direction of, site. 7. Arrange for additional assistance to provide continuous inpections of buildings and roofs. 8. Install door braces on all roll-up doors equipped for braces. 9. Notify plant management. 10. For any tornado onsite causing significant damage affecting plant operations, refer to applicable HNP-4400 series procedures for appropriate respbnse. Foranytornadostrikingthefacilityincurringdamagdakh [ 11. l affecting safety systems, ref er to applicable,HNP-45g6p' l series procedures for appropriate response. So \\ 12. For any tornado or sustained winds in excess of de n level (300 mph), refer to applicable HNP-4600 series dures i for appropriate response. 4 I MANUAL SET O n
E.1. Hatch Nucl::ar Plant -oa== = -~~a HN P-4858 Fif, VISION NO [ Georgia Power ah C<,e Title Page ..m NO 7 of 12 o., See Title Page G. SUBSEGUENT OPERATION ACTTON reactor In the event buildings have been damaged or the 1. internal damage to the power level has become abnormal, Proceed with an process system may be suspected. instrumentation review and plant inspection per HNP-4858 section C. Perform continuous building inspections. 2. If the plant instrumentation review and plant inspection 3. follow evaluation indicates damage to the process system, emergency procedure. the applicable annunciator response or is not damaged and is operationally intact 4. If the plant resume normal operations and inform Load following an alert, Dispatcher. H. CONDITION:_ HIGH WINGS (HURRICANE)_ .The plant shall normally be alerted by outside communications indication of high wind conditions which may disrupt and/or local the transmission system, or present a hazard to the plant facilities. The plant personnel shall prepere for plant load reduction as may be required. In the event winds reach hurricane-near the (sustained wind speed greater than 75 mph) velocities load rejection is imminent, notify the plant site and/or a plant load dispatcher and reduct to load as directed. NOTE After a hurricane warning is received, dispatch an operator. to the plant meteorological station and place the wind speed Note that the transmitter speed selector switch in 100 MPH. indication will have to be multiplied by control room recorder is made. Notify the Laboratory personnel of time change two. I. OPERATOR ACTIONS l 1. Thoroughly inspect the plant for loose materials which may l be blown about. Instruct contractor personnel *of the event and advise them 2. construction to commence preparations for the securing of equipment and materials. Remove or secure all outside scaffolding and' swinging stages. 3. 4. Close and secure all reactor, turbine building, switchyard and off-gas filter building doors. Reterence Only ~ ~ ~ MANUAL SET ~ ,,m.. _g
E. l. Hatch Nucl:ar Picnt eaxt=at ao 'w HNP. 4858 a<vsoaao Sje Title Page ..,l Georgia Power d .m me Sea Title Pagn 8,of 12 5. Plant personnel shall seek refuge within the plant buildings and report to their supervisors for specific instructions. .6. Perform the routine surveillance test of the standby emergency diesel generators in anticipation of a potential off-site power failure when winds reach hurricane velocities near the site. 7. Arrange for additional assistance to provide continuous inspection of buildings and roofs. 8. At the direction of plant management or the Shift Supervisor reduce power to 25% rated when winds reach hurricane velocities near the site and a plant load rejection is imminent. 9. Install door braces on all roll-up doors equipped for braces. 10. Notify plant management. 11. For any hurricane (wind speed greater than 75 mph) onsite causing significant damage affecting plant operations, refer to applicable HNP-4400 series procedures for approp'riate response. 12. For hurricane winds near design basis level (300 mph), refer to applicable HNP-4500 series procedure for appropriate response. 13. For hurricane winds greater than design level, refer to applicable HNP-4600 series procedures for appropriate response. J. SUBSEGUENT OPERATOR ACTION 1. In the event buildings have been damaged or the reactor power level has become abnormal, internal damage to the process system may be suspected. Proceed with an instrumentation review and plant inspection per HNP-4858 section C. 2. Perform continuous building inspections. 3. If the plant instrumentation review and plant inspection evaluation indicates damage to the process system, follow the applicable annunciator response or emergency procedure. 4. If the plant is not damaged and is operationally intact following an alert, resume normal operations and inform Load Dispatcher. Reletemi 03N MANUAL SET ~
E. l. Hatch Nuclear Plant -=== ~o HNP. 4858 a~~ = voo=.e GeorgiaPower d Sue Title Page e 9 of 12 See Title Page K. CONDITION: FLOOD communications The plant shall normally be alerted by outsideindications of river elevation 'and/or local to 88.6 ft Mean Sea Level which may present a hazard to the plant The plant personnel shall prepare for plant load facilities. reduction as may be required. L. OPERATOR ACTIONS flood causing significant damage affecting 1. For (50 year) refer to applicable HNP-4400 series plant operations, procedures for appropriate response. (greater than 100 ft. Mean Sea For flood near design level refer to Applicable HNP-4500 series procedures for 2. Level), appropriate response. levels For flood or hurricane surge greater than design refer to applicable 3. (greater than 120 ft. Mean Sea Level)', HNP-4600 series procedure for appropriate response. M. SUBSEGUENT OPERATOR ACTION 4 event buildings have been damaged or the reactor 1. In the level has become abnormal, internal damage to the power Proceed with an process system may be suspected. instrumentation review and pla section C. Perform continuous building inspections. 2. If the plant instrumentation review and plant inspection follow l 3. evaluation indicates damage to the process system, the applicable annunciator response or emergency procedure. If the plant is not damaged and is operationally intact resume normal operations and inform Load 4. following an alert, Dispatcher. e iteiet*** ~ MANUAL SET ~ t
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1o pf'tDist rJ IN 2'lArs. h 1 C2A .te atutets I tjortry! n : w.ree a t g,,,),m,y 1t.' 3& (-ly.s [ c.3 .tw. net.w i 1%Y&AND s Cdciti$ C.4 f.'&nrfNrs Zr.' la Nj'S ge\\sts#* C@l I %M w uwm MANUAL SET l ~ voosee
U E. l. Hatch Nuclear Plant -= ~. c ~o .~~ m HNP 4858 m v5= ~o 'S.)e Title Page k 1 Georgia Power s 11 of 12 See Title Paqe ePocrew E twv. rArwu.E coeuct4T to:_ofe-anM:1_ _ statat to:_Egi-ret No: RT6'E: _G15t03 xREF: TOTAL sH aTu: _ 7 FREGtK W.Y: _A d gs & & C[M*LETED BY: DATC COMPLETCO: 1 i HWL PEV!rWED THIS DATA PActf AGC r09 COWLETEt4MS NO AGAIN31 ACCCPTAWC Cit 1TERI A Ita ACCC30/JJCF W11H NrP-830. ACCEPTABLE (fiACCEPTABLE REVILVED DY: DATC REVICbED: PEMrV1WS: Page 1 of C Reference Onh FIGURE 2 Page 1 of 2 MARUAL SET
E. l. Hntch Nucl;cr Plant aax.wa.~o 5"~a' H N P-488i8 ,,,.o pee Title Page Georgia Power d See Title Page 12 of 12 DAT A t*,v w/.s;,,( KtJffc*) E3TJgr4 r.. REVISIC" CH. :GF.3 MODE OF.CPERATICH OR INTENT AS DEGCRIDCD IN FSAR: ( /) No ' " ~ ~ ( ) Yes CHANGE INVOL.VF.S: ( ) An unreviewed Safety Guestion ( ) Tech. Specs. ( ') Neither (See back for Safety Evaluation if required). Safety Related ( ) Non-Safety Related. ( ) Safety /Non-safety Status Change ( ) Yec ( ) No Attach mart:nd up copy of procedure to this form. REASONFORREGUEST___),_gg/ [ /J(( p [ y _dg:y.j .a d;r.E ia-e d % z' 46.hs n8?4ddAh A!! X 2 d$i d --.E.nb $. af0&St& 12 ca .sgcoE7.ll-.!e. 7.E.Xse-ra xrzz l b.h A8.2$ ( '.4. /g_ 2 . )/- d e h ~ c / M idh $ rc. o A ; = _ - - - - - - - \\ ---=_- _- - - - = - - - s-4 0 PRR hr. COP.PNDr.t.prnOV.*.:_; ( ya r. '( )No at-ax - PRO :....p'r e t. i r y c 0 4 f.. ). w-eno7.ym.r g p.p, HN.P-9 s ..... MANUAL SET.... \\ .t f
t - G.eFf.*. T. '_/..(.N..*,! l..!,' T...:.n.t..t ~~1 _T.h.e r_e_v_is_i_e_n_o_f_.t.h..i.s.pr_oce_d.u..r.e__d_o_es_ n_o_t co_n_s.t..i._tu_t_e_a.n u.n._re_v_i_e_.w._ed :_.1. question as explaineJ h l ___.______-___e_c.e.s_.___________________.-_______-= I 4 1. The prob a.b._i l_i ty_o..f.._o_cc.u_r_rcnc_e _a_nd _t.h..e c_on.u.a_u.e.n c.e.s.._o_f_.a.n a_c_c.i.d_e_n.t. _ c __ _ _ _o r ma l_f_u_n_c_t i o_n__o f _c_o.u_i p _e_n_t _i_nac r_t._a_ri.t_.t.o__s_a.fe_t", _a re _n_o.t _i_n.c._re.a s_e_d____ abovq_t1m whte.sLin_.ste_(M63te_.tg._tJ.es.c..St.cr.ns_he. cme ______ ____. ___ _ _th_e_.r.ev_i.s._io_n__d_o_es__n_o_t_ch.a._n.c.e__t.h..e. nu_r.n.ose or nerforma nce of the u . _s1 stem.-- 2_..-Th'e nos_s.i..b.ili tl'_o_f an accide_nt,or mal funct.ior __o f a di f fe ren t tv_e_e_.___ -- ----_-_-_=-_ _ -- _ _ __ than ana_l.yzed_ in the_FS_A_P.__does_ not re_su_l_t__f_ rom.t..his chan_c_e.b.eca_u_se se the sys_t_e_m r_esponds and is operated _as before the chance. =- - - - - - = - - = 3. The marcin of safety as defined ia the Technical Snecificat_io_ns. ~ r< ~ is not reduced due to this revis_ ion beca_u_se the__re_ vision do_e.s._no.t. V.. chance anv limited safetv system settinns which would allou a __ sa fet;J._l,.imi t =t_o_be.e._xceeded or to__a_l_lo.r a l imi ti_no. c_ondi tio_ n for ~ -__ _ _o.ec ra t i o_n_s_to _b_e_ex c.e._ed_e_d___a s___s_t a..t.e d_.i..n.' T_e c.hn i_ca l S ne c i f i c a.t..i._on_s_.,. -:=_-__ 1 -= - = = -- n - %./ I cC -9 . MA. N....UAl. S.ET._. ~ -.~.rm.__-.,..,._..... .~ .O
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HNP-4860 uvisio ~o d 5ce Title Page GeorgiaPower d 5 m...e 1 op 7 See Title Pane TESTING OF EMERGENCY COMMllNICATION SYSTFM A. EUEEO$g To provide a procedure for testing emergency communications between the Technical Support Center (TSC), Emergency Operations Facility (EOF), Control Room, State Civil Defense (CO), (ie, Appling County Sheriff's office), H.P. office, and Shift Supervisor's office. 8. TEST SCHEDULE 1. All communication systems will be tested at least once a month. Tests will be conducted in the 2nd week of each month. C$ 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. The individual answering the phone is requested to identify 2. himself, and his name is recorded on the data package in the "Name" column. H.P. Tech requests the answering party to hang up the phone when H.P. Tech hangs up. (Not required for E.N.N. System. Refer to HNP-4S61.) The individual at the other end tests his system by 3. repeating steps 1 and 2. (Not required f or' E.N.N. System. Refer to HNP-4S61.) l l 4. Each party checks the quality of reception. 5. If any line o phone is noted to be lacking in reception i the technician will record the problem in the
~~quality,~~
" Remarks" column next to the appropriate telephone. is terminated and results are recorded in Data Package 6. TestThe H.P. Technician performing the test puts his l 1.initials on the Data Package in the " Initials" column. 7. Necessary corrective action is initiated through the supervisor in charge of communication as and When necessary, p\\a#,h b8 i MANUAL SET C90439 A
C' E. I. Hatch Nuclear Plant ~mww HNP.4860 U e'. ~o See Title Page k 5 ccoroia Power c_. 5 s 2 of 7 ._Se_ e Ti t l e Paqo IAB!E_1 EtjERGENCY COMMUNICATION SYSTEM _OUTLI_NE Location Phone Dedicated As: Testing Procedure Control Room General office Hotline Press power generation on switchboard TSC Syste'm operator Press on switch-board Dial for system operator Division operator Press an switch-board Dial for division operator Ext. Ext.' ENN See HNP-4861 GEMA Shift Supev. Ext. Speal<er Phone Office H.P. Office NRC H.P. Hotline Dial for headquarte,rs Dial for regional office Ext. Ext.
Remove receiver and phone NOTE will ring at dedicated, location The security radio to the Appling County Sheriff's office will
Dial any plant ext.
~~be tested by the Security Department. This phone is in the Control Room. Reference Only ~ PMtWWi!. SET OM..O~~
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HNP-4860 aiv+e o 'S.s Tit 1e Page k 5 G.eoig'ia Power zL. 3 of 7 .mo c... _See Title Page TABLE 1 .(. CONT) EMERGENCY COMMljNICATION SYSTEM OL)TLINE Location Phone Dedicated As: Testing Procedure -_--_-------_- a _------------_-_--_---.;--_--------_--_-_-------_-_--- EOF NRC Hotline Dial-for headquarters Dial' for Regional Office GEMA TSC Control Room ENM See HNP-4861 Baxley emergency line Test Ext. on communicator A, B and emergency director phone, dial plant's Baxley Ext. to test Emergency director ~~ Communicator A 6. 8 Ext. Ext. sPower Generation) Atlanta Dial' TSC General Office Control Room Emergency Operations Facility Appling County Sheriff's Office NRC Hotline E.N.S. Ext. Speaker phone Ext. Speaker phone ~ Ext.' Soeaker phone Ext.t (Atl) dial' , Power Generation)
Remove receiver and-phone will ring at dedicated location
Dial any plant ext.
r Reerence Ody MAN!)AL SET g
E. I. Hatch Nuclear Pinnt axc=a< - HNP-4860
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i 4 of 7 0.. See Title Pane PR(f;l'OthC (MTA PACh't4E 00CtJn[NT I41: I # F-Men-t EEtt!M. to _E09 WL NO: ftTv1'E: G1LR1 rREF: TOTtd DECTS: 4 l RrolENCY: COiPLC10D BY _ (MTE Cn rtITEO: t FWK FEV1FbrU l'Il% fMTA P/#Ws4E F(ft f(TFL.CTf%TS1 /90 ACAlwJT #4CPf ANCF CR11CRI A IN A;CCRWJ4;E WITH 649-BM. f LiuCCt"Ttot E ACCLP7/4?LE ___ REVICLTD CY, DATE f1EVIDCD: = a, leew:1<s: l' age 1 of 4 l#F-4LrA FOS A s FIGURE 1 Rage 1 of 4 EiANUAL SET 900689 -~
E. I. Hatch Nuclear Plant "= = ~u E= HNP.4860 ni m.on o GeorgiaPower A ke Title Page 5 5 of 7 o... See Title Paqe t%TA.J.07!005 1 ft52GL!M.1LM'.tryr en,cif LOCAL lorJ: DATE twf. rtreus INIT. yna n m y =* Os da tated General 08 8 6te s ta t t s ene - *Pc er Gen
~~Dedicated TSC Cystem Operator Dawstion Operator Eat.~~
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==........ F u t". House Pt.cne Cut. House Priene ,..........................L............--- pef er to page 7 f or resste j a,t.etions of EIJJ and alternate phone e mu* tee r s. radio to it.e Appling County. Sher s ee's Of f ice will be ee Tr.e veturity tested by the Security Department. Page 2 of 4 W P
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r.= E.1. Hatch NucIcar Plant ~ocioa a HNP-4860 t. 84tysteON No g Stee Tttie Page 5 Geoq;ia Power n- ..m ~o 6 of 7 3_qe T i t 1 e Pqge cAiA PAruAr.r_ Lig g y t rce.r it-a: i re uctur:y t h*6 ::ATifyd FAr.1LITY DATE WJ4C RCMAni:S I tJI T. (V6ssiers Centeel Dedstated IWC ut.tt,p, siean Dedereted GLMA UYd s tet e d 15C r e. Dedstated Control 5'a va.. Dedstated State / Local CO. 8 t WL* L ette* inyrgency Line lLeeree;;;'ri4 ree ter .,Ccw unscatorN \\ liiTN i Cone-un s c e t er ' es - 6 + LOCA11(N: 1Cr1e41 CAL. Mi.51.01?dKR.
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e, n.,l Georgia Power ai r.m. 7 Of 7 _ Gee Tit 1.g Paae 0^1^ r e R M 1.ist % 1 t(F to ! tt' alt:.LD'el1.%I"JE3 L'^10. fw' 4=9 .ItdlI2 E At 1..s 1.s 3 c.L.H.A. e ti.i s i ew Pel s te (Apt. m _.C.1J. m As.r i e e o Ca.Ja t e Ar P i s e.. Ocoun9 e *t.*ra44 W. 1 e u,,.. t o.... t. u.erife N9"a - I h n e n t..s S t **w i t t e L.'< p t. 14t-s e n t # 1 e t e n a c e liept. N U. saiG:.CTa3?Tib^ ^ cu r.is. g(pI.it.t.p_cttj. cey g__,
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GEORGIA POWFR COMPANY HATCH NUCLEAR PLANT PROCEDURE MANNING OF OPFRATIONN _@ttPPORT CFNTFR PROCFDLYtE TITLE HNP-4FtG5 ~ PROCEDURE NUMBER ~~ LAR RESPONSIBLE SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( ) O __t .____,___i APPROVED APPROVED REV. DESCRIPTION DEPT. PLANT DATE HEAD MAN /,f;ER Ms g-g --y fyg_. O New Procedure p gpf .___ P_ a_ E e_ 1_ _ _ _ _ _ _ _ _ _ _ _. w W-_ 1~ ette Oft Q 1 / .A rhe~ , g g}_g. 2 Page 1 / l f-9 /./@ (72 ./ In s 2:<_ <-. 4*L.. /_L.* A__.. 3 Page 1 & 2 b . _ _. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _.._________e.______.. -e.____. ..____e._ I t i __________e._.__ .__...______,..s_. = m., _ _ e. m. a. a. am. e. _ _ _ _ _ . - _ e. a. e. a. e. _ _ -un
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D 9elt.'Sk im/n -a& ii.g w REVISICil CHANGES MOCE OF.CPERATION Ot INTElyT AS DEGCRIDED IN FSAR: ( p) ( )1Yes No CHANGE INVOt.VES:- ( ) An tinrovi ewed Sef oty Guastic.n (- ) Tech.Specc.. ( ) Neither (Gen back for Safety E. valuation if requirod). .+ ) ._..Non..S.a f e t y R..e l a. t e. d....(. ( ) Safety Related .. :?...
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.. u.. T.... r., e r.............. 4 .,g 6 _d _Th e__r.e..v._i s_i_o.n._o_f__t_h _is...o..r.o_c_e_d.u._re_ d_0_e s _.0_t_co_n_s.t..i._tu_t.e. a..n_ u_n_re_v_i_e_we _ e._a.f.e c. q..u.es t i_o_n a_s_.e.x_pl.a..i.n_e d _b e.l_o_. i_. ___ ___ I and ths..cn.n.w. on_e_n_c.e.r.o.f_a.n _a_c_c_i d_n.n._t _ ____ _ _ 1_. _T_h e_ gr_o.>_a.b. _i l_i_t.y o f o c cu r r.. _.a .v. m i f i t ' :ortant to safety are not increased _o_r__m_a l_f_u_n_c _t o_n_ o_ _ e_c_u _r_ _r_._ _ _ _ _ _ _ _ _a'b..o.v..o. th.nd a _a_n z.l 'q. ns!_.i.n_ N ",_*3 d.u.n 10._tf. ire.a_.fJ' f.0.aa S_b.o.<!J.La __ ~ a r s h h or nerformance of the t_h e re_v i_s.i.on_d_o_es_.n._o_t c.h.:.e _t__e ou_r.no.s_e _ _ _ _____. ___ _ _ ___s.X.s_t.e.m_.___"_ - _ = - - ___________.___._________________m.... 2 The ooss_i_b_il_i_t..y._o_f__a..n._a_c_c.i._t e t__o r _m..a.. u_n_cti on o.f. a _d_i_f_fe_r_e_n_t_tyc_e_J _ lf .....r_a.. .. e.n.... _... f thi h ce because _. ~ - ,___-_ha n a na_l.yz e_d_.i._n the TSM d e s rot res ul_t___re_.m_. ___s__c_ t ~ ~ " '. ". ~. - - = the syste 1 resconds and 'is ::e rated as be_f_o_re__t_h_e_c_h_a_n.ce_.____ ____._. ...... ~.. Th e_m_a_r_c i_n _o_f__s _a_f_e_t.y a s__d_e_#'__e_d__i n _t_h_e _T_e_ ~ 3. t i i i = - ---- do.e.s_no.t ____ _s_.n._ot__r_e.du c_e_d__du_e _t.o._t_h_'_s _r_ev i s i on b_e c_a_u.s._e_t_ c_h_a_n.ce _a_n.v._l_i_. _.i_te_d_s_a_f e_t.y.__s ys_t_e i s ett nos_w- -- _h i_c_h w_o i _ dd t llow a limitine condition for _s a fe t;1._1,.* ni t_-- _to b e__e.x.c e_e__e__o_r__o__a______ a ti ons to.b. e e xce ed e d__a s__s_t_a t e_d_.i._n _T_e_c_h n i_ca_ ._ _ __ _ o _e.r._ p .w. :. e.: .. 4.. i m .e..e.t--_ - ___.r w.- l-c. P 3 ~ 1
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E. l. Hatch Nuclear Plant ~xc=ano ~"a HNP-4865 Evmovo 'dee Title Page Georgia Power d 1 of 2 See Title Page ~ MANNING OF OPERATIONAL _ SUPPORT CENTER NOTE This procedure supercedes HNP-32, Revision 3, dated 1/5/82. A. PURPOSE The purpose of this procedure is to designate the location of and the personnel who shall report to the Operational Support Center (OSC). 8. CENERAL 1. The OSC shall be located in the Unit 1 Service Building, with the headquarters / reporting area.besxg the North end of the break room. The alternate OSC in-tEL Gimulator Training Building. OSC shall be activated for Alert, Site Area Emergency and General Emergency, s C.* PROCEDURE 1. Personnel authorized to report to the Operational Support l Center are as follows: The members of the plant operating organization on site l a. as required by HNP-4521, 4621, and 4721. l b. All oncoming shift personnel. c. Off site personnel, other than GPC, requested by the l Emergency Director. d. GPC plant personnel other than oncoming shift crew who l are requested by the Emergency Director to report to site for support. 2. Personnel arriving at the Operational Support Center shall l remain in the Center unless directed by the Shift Oupervisor or TSC Management to report to specific locations. In the event the Operational Support Center becomes uninhabitable these personnel shall report t'o the alternate OSC unless directed elsewhere by the TSC manager or Emergency Director. 3. Management of the OSC activities will be assumed by the designated Maintenance Supervisor, or his alternate. In the absence of a designated Maintenance Supervisor, the OSC Manager responsibilities will be assigned by the technical Support Center Manager. Reference 04 ~' 9 MANUAL SET
Leva E. I. Hatch Nuclear Plant aa==ai ~o HNP. 4865 uvision o H e Title Page ) Georgia Power d 2 of a See Title Page 4. The OSC Manager shall appoint a Rally Point Leader to tal<e charge of the rally points. The Rally Point Leader should be the senior RET member present in the OSC. 5. HNP-48E.6 should be consulted concerning all repair and corrective actions. 6 I Re4ereme On!! J MANUAL SET
GEORGIA POWER COMPANY 'l HATCH NUCLFAR PLANT PROCEDURE REPAIR AND CORRECTIVE ACTION FOf f OWING A RADIOf OGTCAL FM' RGFNCY PR6CEDUEE~T5TLE ~ ~~ HNP -4RE.E.' ~~~~~ ~ ~ PR CEDURE AUM3ER
~~t. AB RESPONSIf3LE SECTION SAFETY RELATED ( X)~~
NON-SAFETY RELATED ( ) p-- .----------------4--------_------ ..-------_--------.p-_------ APPROVED APPROVED REV. DESCRIPTION DEPT. ' PLANT DATE HEAD MANAGER ---,. h--- ---- - O[g [ // 0 New Procedure 3
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GCC MODE Cr.CPERATION OR INTE 4T AS DESCRIDED IN 'FSAR* ?
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~ HNP-A866 REris'oa ac Coe Title Paga GeorSaPower A l [., < 1 of 7 r. See Title Page REPAIR AND CORRECTIVE ACTTON FOLLOWING A RADTOLOGTCAL EMFRGENCY A. PURPOSE The purpose of this procedure is to provide guidance to ensure that doses to workers performing repair and corrective action functions during an emergency situation are maintained as low as is reasonably achievable. B. REFERENCES 1. NUREG-0654, " Criteria for Preparation and Evaluation of in Radiological Emergency Response Plans and Preparedness Support of Nuclear Power Plants." 2. EPA-520/1-75 001, " Manual of Protective Action Guides and Protective Actions for Nuclear Incidents." 3. NCRP #39, " Basic Radiation Protection Criteria. " 4. HNP-8002, " Radiation Exposure Limits." 5. HNP-4812 " Emergency Exposure Guidelines" C. ACCESS CONTROL During an emergency, access to the protected area _will be 1. controlled. In addition, access to all areas beyond C-52 will require specific authorization and will be limited to ~ in personnel who are needed to provide specific functions the Turbine and/or Reactor Buildings. An bxample of the personnel who will receive authorized clearance to.these areas are: Control Room personnel, personnel on the fire of internal surveys and brigade, RET members for the purpose personnel required for repair and corrective action functions. A list of Control Room personnel requiring access shall be provided by the TSC manager or.his l designee. All other personnel shall require authorization from the OSC manager or his designee after consultation with the TSC manager. Access for personnel to High R$diation Areas shall have more stringent requirements to be discussed in a later section of this procedure. l Or'b geenG l ~ MAMAl. SET
U L E. l. Hatch Nuclear Plant =awas ao H N P-4866 ni m um mo " Sue Title Page Geof8 a Power d l ~e 2 of 7 See Title Paqo D. EXPOSURE LIMITS AtJO AUTHORTZATION 1. All exposures to personnel are to be kept as low as is reasonably achievable. This pertains to all personnel who are required to remain on site during an emergency situation for the purposes of accident recovery, 2. Exposure to the whole body shall be limited to 300 mrem / week. Any expected whole body radiation exposure above 300 mrem in any one week shall necessitate the completion of HNP-8002 Form 2 " Authorization to Fxceed Administrative Exposure Guides" by the indicated parties. 3. Exposure to the whole body shall also be limited to 1,250 mrem / quarter. Any expected whole body exposure in excess of 1,250 mrem in any one quarter shall also necessitate the completion of HNP-8002, Form 2 " Authorization to Exceed Administrative Exposure Guides" by the indicated parties. 4. In some instances during emergency conditions it may be necessary to exceed 10CFR2O Exposure limits. In such instances, refer to HNP-4812, " Emergency Exposure Guidelines" for guidance. The Emergency Director, or his designee, are given the authority to permit these exposures. 5. Exposure of emergency workers to any level is justified only if it is determined that benefits to society are being achieved and efforts are being made to keep exposures ALARA. E. CONDITIONS OF EXPOSURE 1. Percans performing the planned actions sho'uld be volunteers broadly familiar with exposure consequences. 2. Women capable of reproduction shall not take part in these actions. 3. Internal exposures shall be minimized by respiratory protection, and contamination controlled by use of protective clothing. 4. Workers that are to perform thc? required actions should be well trained in the jobs that they will bo performing *a cut down on the amount of time they.need to spend in the area (s), F. RADIATION __ WORK PERMITS 1. Whenever practical, an RWP should be initiated before an work is performed. getet** MANUAL SET _i_.
h E. l. Hatch Nuclear Plant ra== ~o HNP-4866 aansou ~o %ie Title Page ...i Georgia Power A ..mo 3 of 7 See Title Paqe 2. The most current survey information available for the area in which the work is to be performed is to be used unless conditions exist or there are indications that the radiation levels in the area have increased significantly. 3. Area Radiation Monitors (ARM's) are to be used to the extent possible in predicting general area radiation levels. 4. If there is not enough information regarding the radiation levels in the areas (s) to be entered or new up-to-date information is deemed necessary, the TSC Manager, after consultation with HP Supervision, may elect to send an Internal Survey Team, comprised of RET members, into the area to determine the radiation levels. 5. All survey information should be placed on the appropriate Routine or Special Survey Map (See HNP-8012), whenever practical. The use of these maps will aid in the routing of workers in the area, determining stay times and making man-rem estimates. 6. All areas that are surveyed are to be surveyed for Beta dose rates in addition to Gamma dose cates. All smears that are taken are to be counted for Beta activity as well as Gamma activity. 7. It may be necessary, in some instances, that the work needs to be done immediately. In such instances,-the TSC manager, after consultation with H. P. Supervision, may elect to appoint an internal survey team, or member, to accompany the repair and corrective action team, to survey the area while the work is being performed. In such instances, it map also be necessary to complete all documentation at a'later time. 8. Low volume and/or High volume air samplers are to be used to the extent practical in determining airborne concentrations. In addition to these air samplers, CAM's and CIM CAM's will be used where appropriate in airborne concentration determinations. Isotopic compositions should r i also be performed to evaluate radiciodine concentrations. G. EXPOSURE CONTROL 1. No personnel, other than Internal Survey Team members, may enter an area where dose rates are not known, except as stated in F.7 above. 2. Personnel shall not enter areas where dose rates are beyond the range of instruments being used. geje#B MANUAL SET
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HNP-4866 um.o o Stre Title Page GeorgiaPower A e o.,< 4 of 7 See Title Page 3. Personnel shall be equipped with dosimeters capable of measuring anticipated doses. This shall include, but not be limited to: Two direct reading pencil dosimeters for whole body a. exposure: 1. O-200 mR and/or 0-5 R; and 2. O-20 R b. A Thermoluminescent Dosimeter (TLD) to permanently record whole body exposure. rate Extremity dosimeters when the extremity exposure c. is likely to be four (4) times the whole body exposure rate and the extremity exposure rate is likely to be 400 mrem /hr or greater. The extremity dosimeter (s) is/are to be worn on that part of the body that is likely to receive the exposure. d. A digital alarming dosimeter (0-10 R) with a predetermined alarm set point. The digital readout and the alarm will enhance the worker's knowledge of his accrued dose. 4. Protective clothing shall always be worn by workers entering areas for the purposes of repair and corrective action. The minimum dress requirements shall be: One pair of cotton gloves a. b. One pair of rubber gloves c. One pair of cloth booties d. One pair of rubber booties In the event that more stringent' requirements are specified on the RWP,- or by H. P. Supervision, then those requirements shall prevail. In all cases 5. Respirators shall be worn as appropriate. where airborne contamination is anticipated, personnel shall l be fitted with pressure / demand Self Contained Breathing I l Apparatus (SCBA) as a minimum. 6. Potassium Iodine (KI) tablets should be administered to all personne.1 who are likely to inhale 20.0 uCi D.E. , l I-131 or greater. This decision is to be based on the results of HP I previous Whole Body Counts and the projected sxposure. f Supervision shall make the final determination on whether or i not KI should be issued. f geW l MANIJAl. SET I \\ .a
7.. ramn ao t:. I.11alCn INuclear t'lant mova H NP-4866 aimio= =o 5 e Title Page k 1 Georgia Power s ..mo 5 of 7 See Title Page 7. All workers upon leaving a high airborne radioactivity area will be decontaminated as necessary and then given a whole body count. If indicated, other bicassay methods may be used in addition to the whole body count. H. ALARA CONSIDERATTONS In order to maintain radiation exposures to personnel 1. performing repair and corrective action functions during emergency conditions as low as is reasonably achievable, the following steps should be performed, whenever practical: Prebriefing-All workers that are to be sent into High a, Radiation Areas should be made aware of the dose rates in the area, stay times, and airborne concentrations. All workers should be familiar with exposure consequences. An attempt should be made to estimate the total man-rem exposure of the prescribed action, based on radiation levels and man-hour estimates, and all attempts should be made to keep exposures below this estimate. Some of the methods that may be used to accomplish this are as follows: (1) The workers should be informed of the magnitudes and locations of significant radiation sources at the task location or accesses, and should also be informed of low exposure waiting areas, if any, that are to be used when necessary. Using the most current survey information or anticipated levels, the workers should be informed of the best way to reach their destination (i.e., the route that would result in the lowest exposures). Since the workers will most likely be wearing SCBA equipment, consideration should be given to reducing the amount of time.needed to reach their destination since they will only have 30 minutes of supplied air. The personnel in attendance at the pre-briefing should be: the work crew; a Lab Supervisor or Foreman; a Maintenance Supervisor or Foreman; the OSC Manager; and a Shift Supervisor or Foreman. (2) A tool list should be developed prior to entry, such that a worker is well equipped to perform the required actions. Since a lot of time will probably be used in reaching the destination, care should be taken to reduce the number of trips needed. ggsste MANUAL SET i
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F-W~a E. l. Hatch Nuclear Plant -oaouw ao HNP. 4866 1 ams.ou o G e Title Page .2 Georgia Power d 6 of 7 See Title Page (3) Consideration should be given to the use of special tools that~may reduce the amount of time . spent in the area, or that will enable the worker to handle " hot" pipes or valves remotely. These should only be used, however, by workers who are familiar with their operation. (4) Consideration should be given to the prefabrication of systems outside to the High Radiation Areas which would result in less time being spent for the required action. 05) Consideration should be given to the removal of systems to be worked on from high exposure rate areas to low exposure rate areas, if practical, to further reduce exposures to workers. (6) Consideration should be given to the use of communication systems (such as walkie-talkies, headsets, etc.) so that any problems or difficulties that are encountered may be related back to supervisory personnel for discussion or comment. (7) Workers that are to perform the required actions should be well trained in the job (s) that they will be performing in order to cut down on the amount of time they need to spend in the area (s). b. Job Execution-Although prebriefing is an essential step in maintaining radiation exposures to station personnel ALARA, implementation of exposure controls during'the execution of a job is the primary mechanism for maintaining radiation exposures as low as is reasonably achievable. Some examples of exposure controls methods that should be utilized are as follows: (1) In order to reduce internal doses, the proper respiratory protection equipment must be worn by all persons who have the potential of inhaling airborne radioactive materials. (2) Protective clothing needs to be worn to reduce the liklihood of skin contamination. (3) Time, distance, and shielding are the most effective ways of reducing exposures and must be utilized where-and whenever possible. , 'I .,n J ~ O**~ u J 6 MANUAL SET
a-6 & ~ E. l. Hatch Nut,1 car Plant '*oa=* e HN P-4866 aim.wo w o .tse Title Page GeorS a Power A A i 7 of 7 See Title Page (4) Proper communication between workers in high radiation areas and supervisory personnel who are monitoring the operations from other locations is essential in identifying problems incurred during execution of the required actions. This will be enhanced through the use of communication systems such as walkie-talkies or headsets. c. Post-briefing-Performance of this step will help in planning future. jobs by using a type of " lessons learned" approach. The personnel in attendance at the post-briefing should be: the work crew; a Lab Supervisor or Foreman; a Maintenance Supervisor or Foreman; the OSC Manager; and a Shift Supervisor or Foreman. (1) The importance of this step stems from the possibility that it may become necessary to perform subsequent similar actions during emergency conditions. (2) Any problem or recommendations that arise should be documented for the purposes of planning and execution of subsequent actions.- These recommendations should be expressed by anyone involved in the operation. (3) The degree of success or failure should be reviewed upon completion of each job and should also be documen ted f or f urther use. I. EFFLUENT RELEASES NOTE Oue to the increased likelihood of fuel failure during an accident condition particular care must be taken in analyzing all releases. In addition to performing isotopics. l on a GeLi detector, all gaseous effluent filters must be l measured for Beta emitters, particularly Sr-90. Refer to appropriate HNP-7000 series prgcedures for analysis. 9 I e gb f y'* I, + 4 MANUR SET ,}}

ML20028C008

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