ML20080E209
| ML20080E209 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 07/28/1983 |
| From: | Nix H, Rogers W, Zawadoski R GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20080E206 | List: |
| References | |
| PROC-830728, NUDOCS 8308300845 | |
| Download: ML20080E209 (80) | |
Text
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l i PROCEDURE l I Use and Calibration of the Lab Dwyer Ma,qnehelic Gaqe_ l I PROCEDURE TITLE f HNP-8157 l PROCEDURE NUITER Lab i RESPONSIBLE SECTION NON-SAFETY RELATED ( ) SAFETY RELATED ( X) APPROVED APPROVED DEPT. PLANT DATE REV. DESCRIPTION HEAD MANAGER 0 New Procedure L f--%g-- a,.,, -- .t::--
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) An unreviewed Safety Guestion- ( ) Tech. Specs. ( ) /s condi tion not addressed in FSAR (4 79ane of those -__ _
(See back for Safety Evaluation if required). .
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- O 1 au 1 of 4 See Title Page LT AND CALIBRATICN OF THE LAB DWYER MAGNEHELIC GAGE i
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a A. PURPO"4 j 1. To provide method for calibration of Dwyer Magnehelic Gages. j This procedure is applicable to Health Physics and Lab Gages 2. 040-NOO7 and D40-NOOB only. 3! B. SAM L Observe safety rules outlined in Georgia Power Company, SAFETY, Section "O".
. C. REFERENCE i
SX-26415 Dwyer Magnehelic Instruction A-27 D'. TEST EQUIPPENT Dwyer inclined manometer 0-10" or equivalent
, E. DESCRIPTION OF INSTRUPENT s
The instrument is a magnehelic gage measuring from 0-10" of water j pressure across the flow path of a laminar flow element. It is
- used to measure air flow through the Health Physics air samplers.
F. DESCRIPTION OF CCNTROLS There are no adjustable controls. Simply place the instrument in I line with the sampler and it measures the flow.
! G. CALIDRATION - SEM I - ANi .e- ,
5 i 1. Connect the magnehelic gage and inclined manometer together l3 with two leads from a "T", connect tubing to the third leg l3 of the "T" and impose the pressure slowly. Record O, 25, lt .- 50, 75, 100% values on Data Package 1. 8 If the As Found values are not within 2% of fu11 scale remove ,j 't 2. l j plastic cover and perform steps G.3 thru G.5. i :' . . Remove two screws holding scale and slide scale out, using 3. care not to damage pointer. i
$- Loosen two set screws in range spring clamp and move toward l 4.
the helix to increase the range and back to decrease. Secure the clamp with the set screws, replace scale, check zero and compare reading as described in step G.2. MAHAL SET
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HNP-8157 E. I. HATCH NUCLEAR PLANT . .e w See Title Page
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- 5. To replace cover the cover must be tight and leak proof for accurate readings on high pressure side. Observe following procedure.
I Place cover in position with notch engaged with "O" a. ring properly seated, f
- b. Jockey zero adjustment screw into position so its hex end is inserted in the socket set screw which actuates the zero adjusting mechanism.
- c. Hold cover in position and screw bezel down snug. Note that "O" ring must take some squeeze in order to effect an air tight seal.
- 6. If instrument calibration is acceptable, place a sticker bearing the proper calibration due date on the instrument.
H. INSTRUPENT MALFUNCTION If any difficulty is encountered with gage, see Dwyer Magnehelic Gage Instruction A-27 1or operational instruction and parts list. e l t
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g,,71,1,p,g, Georgia Power 3 ,, . PROCEDURE DATA PACHACE DOCthENT NO: Fw -8157-1 SERIM. M): ROO-ffL NO: RTYPE: C15.14 XREF: 1TITAL GFEETS: 2
. FREGUENCY: Semi-Annual I
CDPLETED BY: DATE CDPLETED: ,
% l I HAVE REVIEWED THIS DATA PACHAGE FCR COfLETDEG3 - AfD AGAINST ACCEPTANCE CRITERIA IN ACCORDANCE WITH FN-830.
ACCEPTABLE LNACCCPTABLE i REVIEWED BY: l DATE REVIEVED: ._ REMARMS: i l~ a'
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FIGURE 1 Page 1 of 2 BAH AL SET
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l DATA PAC'd AGE 1 DWYER MACPUELIC CACE . PFL No. Test Equipment No. !, Service TEST PERFORMANCE
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CFr?PATICN OR INTEL:T AG CIECCICED If J F3AD: DEV!DION CHANGEG NGOE G' l-( ) Yes (/s ) No 1 CHAN';E Il *./OLVES: ( ) Tech. Specs. (8 ) Neither' ( ) An unrevieve<; Gafety GrJestion (See ti a ct< f o r-Gaiety Cualual:;on if required). i l Non-Gaiet,s Related ( ) l PRESENT STATUS: Befety Gelated (fK) changed ( ) Yes to ___,____.__ The above Safoty/Non-Safeiy Status has ' Attach marked up copy of procedure to this form. O ~~d W.C i' hlf'l t- - i -'l f kl S FI' (Mt
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oiv'ia w .e - 1 of G _gn: T t 41 e . rann HICH D AD f Kf,T f,1N AREA Et IT!? ANCE CCW TPCI . A. Pt JRFC/'t? To provide assurance that entrances to high radiation areas are locked and positive control in maintained as required by the applicable provisions oF 10 CFP Part 20. O. GAFETZ Observe radiation protection procedures. C. REFERENCES 10 CFR 20.203.C.E., Toch Spec G.12.1, Tech Spec G.12.2. D. PROCEnt1RE
- 1. All entrances to high radiation areas shall be checked at
, ...;f/ least once every 24 hour period.
- v. '
- 2. These checks as a minimum will inc1'ude the following:
Verify the door is locked.
"'!$ a.
- b. The door may not be opened _unless an individual using the door has a key.
- c. Integrity of the lock on the doors has no t been impaired.
- 3. The checks'will be logged on Data Package 1 (Data Sheet 1) or Data Package 2 (Data Sheet 2), indicating any discrepancies-in positive access control on each door.
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GEORGIA POER COMPANY HATCH NUCLEAR PLANT . PROCEDURE SITE AREA EMERGENCY - OPEFATIONS SUPERVISOR
~
~~ PROC 5 DURE TITLE HNP-4630 PROCEDURE NUMBER
_ LAB RESPONSIBLE SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( ) APPROVED APPROVED REV. DESCRIPTION DEPT. PLANT DATE FEAD MANAGER Y 2 Page 1
, /'
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6% g 't. 3 ______.F ____ ______ ______.._______ ________..___________ __ ..________ VtP-9 MAHAL SET
-~~ E. l. Hatch Nuclear Plant lHNP, 4630 mua ~o
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- Georgia Powerkn 4 "
.. ~o 1.1 See Title Page 1 of 1 i
SITE AREA EMCRGENCY - OPERATIONS SUPERVISOR A. CONDITION Events are in process or have occurred which involve actual or likely major failures of plant functions needed for protection of the public. Any releases are not expected to exceed PAG exposure levels, except near the site boundary. B. REFERENCE HNP-4620. HNP -4720. l HNP -4740. HNP-1. C. ACTION
- 1. Proceed to control room.
- 2. Take control of all activities in the control room, ensuring that proper coordination of all-activities is carried out.
- 3. a. Assume the duties of the Emergency Director until relieved. Assure that those actions in i+JP-4640 which can be performed from the control room are accomplished.
- b. Assure correct emergency classification has been de cla r e d as p e r 1+F-4620.
- 4. Evaluate actions of Shift Supervisor and operator to bring emergency under control.
- 5. The Operations Supervisor is responsible for notification of l Plant Management and NRC as per emergency call list and
- the orr.it, agen ci a in 2 ,--- 9 m ,e.th m ti'ication procedure HNP-4861. The actual nofitication process may oe delegated to other, specifically trained, shift personnel. l
- 6. Consult with the Technical Support Center and Emergency Director to determine any outside assistance needed. ?
i
- 7. Assure that personnel are assigned to maintain an open line j i to MRC, T.S.C. and E.O.F. and inform these groups of I
- g. significant plant changes.
d
- 8. Escalate to general emergency class ( ref er to 1+F-4720 and 4853), if appropriate.
- 9. Provide information to the Emergency Director to assist in his determination of close out or reduction of the emergency class.
MAHAL SET
r 1 I i GEORGIA POWFR CCFANY HATCH NUCLEAR PLANT i
; PROCEDURE I
i e__-- S i t e A r e a Em e r _9_e n_eY__- R a i _lZ Point Leader PROCEDURE TITLE HNP- 4E2E-PROCEDURE NUMBER Lab RESPCNSIBLE SECTICN SAFETY RELATED ( X ) NON-SAFETY RELATED ( ) 1 i l m_____ --___________________, .________________m_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ , _______, APPROVED APPROVED I REV. DESCRIPTION DEPT. PLANT DATE l-EAD MANAGER ______ p_____e.__e.___________. . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . .__________m._____. ._______e 2 Pages 1,2, & 3 Deletions on Pages 1 & 3 fa. 7____________________. _ __ /___ ._____ _ _ _ _ _ _ _ _ .._______e 3 !
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li l - HNP. 462{. l S*p Title f' age . < . . s.cw. , 5
.... Georgia Power d ..om Gee Title Page 1 of 3 4
SITE AREA EPETtGENCY - RALLY POINT LEADER NOTE This procedure supercedes 1+P-4605 Revision 6 dated 1-2-81. 1 A. COPOITION l Events are in process or have occurred which involve actual or likely major failures of plant functions needed for protection of the public. Any releases ar not expected to exceed PAG exposure levels, except near the site boundary. I D. REFERCNCE HM3 -4620 HNP-4621 C. GENERAL INFORMATION & INSTRUCTIONS
- 1. The primary cally point for personnel inside the primary protected area is gate 16.
- 2. The primary rally point for personnel outside the primary protected area is gate 1.
- 3. The alternate rally points are:
- a. Environmental Building
- b. Skills Training Building or The Outage Training Building.
4 4
- 4. The criteria for rally point habitability are: I'
- a. ' Area dose ra tie less than 0.5 mr/hr, and I.;
I'
- b. contamination level less than 100 cpm above rally point background.
i:;
. 5. The locations of decontamination showers outside the primary ,
protected area are: _, a. Environmental Building (*. : 4
- b. Outage Training Building MANU AL 3ET 1
__ ___________._______________.________________.____.__)
Pua m4626 . E. I. Hatch Nuclear Plant s i
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~ l See Title Page Georgia Power n 2 of 3 See Title Page 6.
Do not release any person who has received greater than 25 rem whole body dose or is suspected to have ingested Such persons significant amounts of radioactive materials. are to be taken to the hospital for examination and further ; evaluation of exposure. ! l Confer with the Emergency Director before releasing any personnel involved in the incident.
- 7. l general contractors, and ,
8. Check with the Securityplant. Force,IfGeorgia any person Power (s) isConstruction (are) i De If l
' personc remaining in thereport this to the Shift Supervisor. g ;
I unaccounted for,the Shift Supervisor cannot account for the missingand in . person (s), form a rescue team (s) Area Emergency - Rescue Team. D. ACTION the OSC manager will
- 1. After the RET assembles in the OSC, appoint a Rally Po point.
- 2. The Rally Point Leader should instruct all RET NOTE Leave enough RET members in the OSC to comprise an internal survey team and a rescue team (approximately seven individuals).
3. Determine if the primary rally points are habitable using the criteria in Section C.4 relly pcznts du i.u t satisfy s+ 4 If conditions criteria at the pr in Section imaryproceed to an alternate rally C.4, if the alternate rally point is habitable { point. Determine i using the criteria in Section C.4. 3
- 5. Dispatch an appropriate number of RET members 3
h l? I
- 6. Assure personnel gather.at the oesignated rally l$L ,d" . .
u
- a.
Attempt to separate.those individuals who were involved ,2 j in the incident, who'were' working in contaminate areas, 2 personnel at the rally point. , e
't MANUAL SET
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l"*+ E. l. Hatch Nuclear Plant i-io i HNP- EN- ! j .ies se, j
, see Title Page Georgia Powerko i 5 i c...
~. ~o See Title Page 3 of 3 .
I ! b. Attempt to survey those individuals with emergency ' response assignments as soon as practical.
- c. Instruct individuals who were involved in the incident, ;
l those found contaminated (greater than 100 cpm above the Rally Point background), and those with personnel I dosimeters off scale 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.
- e. Dispatch an RET member (s) to accompany contaminated g 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.
- g. Report status of the evacuation to the Emergency Operations Facility.
- h. Do not release members of the Radiological Emergency Team, except to go to the EOF, unless directed to do so .
by the Emrgency Director or Shift Supervisor if the !
' Emergency Director cannot be contacted.
- i. Assist in routing ambulance to pick up any injured personnel. Assure ambulance driver and attendant are provided with TLD badge and pocket dosimeter en entry. {
. Assis' S eeqancy Di m- - in bringino emeraency under control. s 1 1 MANUAL SET
l CEORGIA POWER COMPANY 1r HATCH NUCLEAR PLANT
- 3. c.
e PROCEDURE Site Area Emergencv ~ Shi f t Supervisor ~ e PROCEDUN~TiTCE HNP.-4f.23 PROCEDURE NUMBER Lab
, RESPONSIBLE SECTION l
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SITE AREA __ EMERGENCY - SHIFT SUPERVISCR_ .
. NOTE
.This procedure supercedes HNf"4602 Revision 6 dated 8-1-80.
~-
A. CONDITION Events are in process or have occurred which involve actual or l likely major failures of plant functions needad for protection of the public. Any releases are not expected to exceed PAG exposure levels, except near the site boundary. i B. Ry-t-i<ENCE , HNP-4620 HNP-4853 e, * . C. ACTION
"%', 1. Proceed to control room immediately. -
- 2. Classify and declare emergency using HNP-4620, ensure that correct operator action has been taken to bring emergency under control.,
- 3. Evaluate' conditions and findings of the control room operaior to see if a General Emergency should be declared.
based on performance of HNP-4853 and criteria in HNP-47EO. 4.- Assure call list for Site Area Emergency has been initiated.
- 5. Activate Internal Survey Team by contacting Operations Support Center when staffed. Direct Internal Survey Teams to areas to be surveyed as appropriate.
- 6. Activate Rescue Team as necessary by contacting Operations
~ ~ ~ ' " ~ ~ ~ " ' Support Center Manager when staffed. - - - - --- -
- 7. Establish communications with the Security Force, Technical Support Center and the Emergency Director as soon as possible and discuss declaring a General Emergency and/or the need for outside assistance for the Site Area Emargency.
- 8. Direct on site actions to bring emergency under control.
l . Assume the duties and responsibilltles of the Operations
# , 9.
,e Supervisor, if he does not report to the Control Room or is
- incapacitated, as per HNP-4630.
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. 4 .. GEORGIA POWER COMPANY
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HATCH NUCLEAR PLANT v . . PROCEDURE . e Site Aran _Fmpr_gency PROCEDURE TITLE - HNP-4620 m. PROCEDURE NUMBER im J Lab - RESPONSIBLE SECTION SAFETY'RELATED ( X ) NON-SAFETY RELATED ( ) e
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ScM.. Title'Page Georgia Power s k - 3 L... 1 of 7 - e _h e Tit 19 Paun i l SITE AREA FMERCENCY i w A. CLAGS DESCRIPTION ' Events are in progress or have occurred which involve actual or likely major failures of plant functions Any needed releases arefor not protection expected of to the public. Refer to Table 1. l .1 exceed PAG exposure levels, except near the site boundary. ,
- 8. PU9PO13
( '1' ) assure Purpose of the site area emorgency declaration is to 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 sta tions if situation becomes more serious, (4) provide consultation with offsite authorities, and (5) provide up' dates for the public through offsite authorities. C. PLANT ACTIONS NOTE . ,, 'T. The Shift Supervisor or Operations Supervisor ' (or higher ranking licensed or certified person present) in consultation with the STA,isif feasible, in a recognizes and declares that the plant The state of emergency of the site arearole class. of emergency Operations Supervisor assumes the director until relieved by the General 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. ..
- 5. Dedicate an individual for plant status updates to offsite authorities and periodic press briefings (perhaps in =
conjunction with offsite authorities).
- 6. Make senior technicial and management staff onsite available for consultation with NRC and State on a periodic basis.
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g= t:.1. MCICn Nucicar Plant oa maa~o a HNP.4G20 Q:0 Title Pcga aemio= ~o 4.,d. 3
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f See Title Page 2 of 7
- 7. Provide meteorological data and dose estimates to offsite authorities for actual releases via a dedicated individual or automated data transmission.
- 8. Provide release and dose projections based on available plant condition information and foreseeabic contingencies.
.9. Escalate to general emechehey class, if appropriate.
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- 10. Close out or reduce emergency class by briefing of offsite authorities followed by written summary within 8 hours of clo,secut or class reduction. -
D. ' STATE AND/OR LOCAL OFFSITE Al.tTHORITY ACTIONS
- 1. Provide any assistance re' quested.
- 2. If sheltering near the site is desirable, activate public notification system within at least two miles of the plant.
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- 3. Provide public within at least about' 10 miles periodic a updates on emergency status.
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- 4. Augment resources by activating primary response centers.
- 5. Dispatch key emergency personnel including monitoring teams with associated, communications.
G. Alert to standby status other emergency personnel (e.g., those needed for evacuation) and dispatch personnel to near site duty stations.
- 7. . Provide offsite monitoring results to GPC, DOE and others cod jointly assess them.
- 9. Continuously assess information from GPC and offsite monitoring teams with regard to changes to protective actions already initiated for public and mobilizing evacuation resources.
m_ ._ . . . .. . . . . . --- .~
- 9. Consider placing milk animals within 2 miles on stored feed and assess need to extend distance.
10, Provide press briefings, perhaps with GPC.
'1.
Escalate to anneral emeroency class, if appropriate.
- 12. Malatain site area emergency status until closecut or reduction of emergency class.
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. SITE AREA DERGENCY
- 1 PARAPETDt VALLE T T EOUTPPENT STATUS i INITIATING CCPO!TICN 3 .3
. Greater than 1.8 psig -
Known loss of coolant accident greater Drywell High pressure and increasing 5 3
- 1. Initiation alarm, than makeup pumps capacity. Reactor Low level Initiation Less than -38 in and decreasing .
- alarm '.
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- 3. Steam line break outside contaltunent Ang: Turbine Bldg ARM Hi alarm Creater than 15 me/hr 7rq Z ' M without isolation . . . . ,_
MLL Hi Flow alarm Creater than 1201 and O
. .- increasing Less than 855 psig and _
< 3 MGL Low Pressure a) arm CJ
_ decreasing * "3 e+ Undervoltage alarms on all 4.16 .Zero voltage indicated 4.' Loss of offsite power and loss of onsite kV buses for nore than 15 min- on all 4.16 kV buses , power for more than 15 minutes utes and loss of control room normal lighting or more than 15 minutes W inability to energize
- 4.16 kV buses from Diesel Generat- .'
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.j INITIATING COPO!TitN EQUIPMENT STATIE PARAPCTER VALLE *
- 5. Loss o+ all vital unsite bC power for more than 15 minutes Loss of DC Busses for more than 15 minutes C. Complete loss of all function needed Inability to Shutdown eelth ~.-
for plant hot shutdown Control Rods a gj e 7., Transinnt requiring cperation of Scram signal present and power .
. . shutdown systems with failure to not decreasing, Standby Liquid C
F'. scram (continued power generation Control initiated. > - 2 g but no core damage issnediately evident). f* g a 1 - C. Major damage to spent fuel in Reactor Observation y -- g D3 i Building (e.g. targe object dan. ages Spent Fuel Storage Pool Low Less than B ft abovg fuel * !T1 > D 8y fuel or o.ater lost below fuel (level) Level alarm
- and decreasing yf $*
- 9. Fire compromising the functions of Fire alarm and observation Operations Supervisor's i bP T 2 safety systems judgement g- O, c ,
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- 10. Most or all alarms (annunciators) One or more of the following: Operations Supervisor's < Q (D '
judgement M lost and plant transient initiated loss of feed water ^ % or in progress a. O
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. SITE NtEA DERGENCY (COPHIPAED) '
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- COU1PtTNT STAT 1r, PARAPETER VALLE .
E IT1ATING C0rC1710r4
- b. Low water affecting plant safety Very low river elevation t.ess than 57 f t. PEL '
*Plus observation of safety systems '
systems - U3 Very liigh river water Greater than 120 f t PEL
- c. Flow or hurricane surge greater than design levels elevation M g
~~ Very high winds
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- d. Sustained winds or tornadoes .
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g $l O 14 judgement E h projected with plant not in cold . I
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- a. Aircraft crash affecting vital Observation O b structores by impact or fire ,
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- b. Severe damage to shift shutdown Observation h-l l equipment from snissiles or
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- TABLE 1 SITE NtEA DEI 1GENCY -(CONTIIED) j C -{
I' } , a i EOUIPMENT STATUG .PMtAKsER VALLE Q Q INITIATING COPO! TION Observation Operations Superviser's b d
- 15. Other Plant conditions esist that warrant activation of emergency judgement *
- G3 I $* _T centers and monitoring teams or a
- a 2 i a precautionary notification ** ,
h_
' to the public near the site ,
< G 4 (D Observation k
- 16. Evacuation of control room and '
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. HATCH NUCLEAR PLANT s
'* PROCEDURE .
General Emergency ~
. PROCEDURE TITLE .
HNP-4720
. PROCEDURE NUMBER .
Lab
. RESPONSIBLE SECTION NON-SAFETY RELATED ( )
SAFETY RELATED ( X)
. - t
______,.____________________,,________________.________________o ' APPROVED APPROVED DEPT. PLANT DATE REV. DESCRIPTION - HEAD MANAGER _ _ {_Ql f
- 3ll 8) 1 Page 2 & 4
___________________ r* _ _ _ _ _ . . _ . __ ____. A~ *
/ 71_ _ _ _ _._ _it.
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~~f= E. l. Hatch Nuclear Plant aaou =acNo HNP- 4720 Mg}.y{tig pggg g mussoN NQ 3-dg(..
om GeorgiaPower s .. me= T44to p _2 n . s i of 7
- GENERAL EMERGENCY
^
A. CLAGS DESCRIPTION . Events are in process or have occurred which involved actual or imminent substant,ial 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. B. PURPOSE Purpose tif 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 measuremenis, (3) ' initiate additional measures as indicated by actual or potential releases, (4) provide consultation with offsite authorities and (5) provide updates for the public through offsite authorities.
. ss
.. .9 . C. PLANT ACTIONS
- NOTE ~
D.v' The Shift Supervisor or Operations 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 Operations Supervisor assumes the role of emergency director until relieved by the General Manager or his designee.
- 1. . Promptly inform State and local offsite authorities of general emergency status and reason for emergency (parallel notification of State / local).
- 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.
- 5. Dedicate.an individual for plant status updates to offsite l authorities and periodic press briefings (perhaps joint with offsite authorities).
- 6. Make senior technical and management staff onsite'available s ,g/' for consultation with NRC and State on a periodic basis.
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GeorgiaPower d . 1 n.. . r m . ~,. Providemet[tocologicaldataanddoseestimatestooffsite authorities for actual releases via a dedicated individual 7. or automated data transmi.ssion. Provide release and dose projections based on available
~
8. plant condition information ,and foreseeabic contingencies. h 9. Close out or redu'ce emergency class by briefing of offsite authorities followed by written sunnary within 8 hours of closecut or class reduction. . D. STATE AND/OR LOCAL OFFSITE AUTHORITY ACTIONS
- 1. Provide any assistance requested. 6
(
' inform public
- 2. Activate public notification system promptly, of emergency status and provide updates periodically.
3. Consider sheltering for 2 mile radius and 5 milesadvisability Consider downwind and assess need to extend distances. of evacuation (projected time available vs. estimated evacuation times). l ,'*. - 4. Augment resources by activating primary respond centers. including monitoring teams
- 5. Dispatch key emergency personnel with associated communications.
6. Dispatch other emergency personnel to duty stations within 5 mile radius and alert all others to standby status. 7. Provide offsite monitoring results to GPC, DOE and others
. and jointly assess them.
8. Continuously assess-information from GPC and offsite monitoring teams with regard to changes to protective actions already initiated for public and mobilizing evacuation resources. l
---- -- ~ ~ 9. Consider placing milk animals within 10 miles on -
stored feed and assess need to extend distance.
- 10. Provide press briefings, perhaps with GPC.
- 11. Maintain general emergency status until closecut or reduction of emergency class.
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Effluent monitors detect levels EQWE9E M STA M PWMN WLig
. t t o*7 corresponding to I re m/ter 14.8. _g
- Main Stacle and/or Reactor Bide. -i monitors Hi Hi alarms plus mosen tr.PVent e
or 5 rym/hr ' ~ w thyroid at ti.e site boundary under actual meteurg- reading plus dose rate projet.tiott * + e6 19s t M L.KW'!!!(llE!i3 calculattuns. I
- M.
site usts.g porta.bleDuse uneasuremeests att. D % instreament s or s - 1.D. envirosus. ental neonitoring stations. l Projected dose sales as ebeve
- 1 based on other pI4nt parasmeters. Duse rate projections teill be based * .
.} ..
on ll.a followinal Containsuunt Post ! D t_OCA Radiation smonitors, analysis of drywell dir sampts*, ARM s.unitors in . I '
- Reactor Duilding, pitas possible con- l
. 8*
firmation fruna effluent monitors or
- l 2.a. of f st te measuressent s. 4
- Fallure of cladding and contain- _ Gee T.ble 1-4. s containment with potential loss of primary coolant boundary, d. Reacter pressure 7 1325 'p si s t with failure, of safety re-lief valves to open. 4100 volta 3 '$./ j' undervoltage, 000 volta under-voltaqu. g p
*,, in steem and coolant.Aamlysis of activity O Reactor ,s? ; , s wa ter level f_.,35!.5 inthus.
- t Failure of LCCS to auto or ,
O manual Q ] 2.b. Failure of rindding and primary of primaryinitiate. Indicated loss conteirament. yq g coolant boundary with potential Ses Table 1-b - y @9 - loss of contairment. O Containment pressure 1.5 pois C3 U
~ *
- 3
. Containment temperature pq r-( .2300
- F. Analysis of &ctivit' 7 m g ,,,
g in steem and reactor coolant O a e* O C Reactor water levels k-104.5 O f.* g inthem. Con tatawnen t Post.LOCA R Monitor Readings Contairment d C. lHgh Rande Radiaison Monitor Z q U Readirigs Maan Steam Lane O " l
. Flow '/ IE;O psid Contalrument 4 g
2.c.
~ Fa!!ure of primary coolant ,
atmumpheric snelyssa. -{
' boundary and contaisument witts See Table 1-c.
l potential loss of cladding ' Containment pressure ,2jt5 psig %_ g Containment temperature " t
.2 300* F. Hain Stewie Line Flow *? ICO psid Indicated loss I of pram.ary containment. Fa&Iure f
of ECCU ate to auto or manual iritti-4100 voll *
' 3 undervoltage 600
/ volt undervultage. Reactor
- i 3.
I Loss of physical centrol of the water level J.-164.5 inches and decreasing. as* plant. Observation ,
. }
Operations Supervisor's judge- !' (( F i z
' ment based on advice of 2 6 "J '
t - , Security Shift Supervisur. gC Z '
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- 4. Other plant conditions esist Judgement of Operattens t from eshatever source that make B.apervisor and STA. [
releans of large .smounts of e radioactivity in a short time 3 fC period possible (e.g., eny core . melt situationl. Esample of * . sequences: 4,
- a. Transient (e.g., Rose of off-
- site powerl plus tallure of
, d requisite core shutdooms systems i s. g. , scrael. Could lead to e' core melt in several hours with contairmient f.ailure likely. ..
- More severe consequences if
- D pumps trip does not function. * * . *
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ph I * *. * *f b. Small ne large LIX:A's with O 1 failure of ECCS to perfo'sa leading to core melt d. Q W {
. . gradation nr melt in min-.
utes to t.ours. Loss of . . . n g
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y containment intergrity may
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- c. Small or large Li1CA occurs e i - O c and contalrunent perf ormante is unsuccessful affecting
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O y$ longer term success of the
,, (D ECCS. Could Ipad to cure y m
-s degradation or melt in g seves el hours without con- -y _
tainment bouisd.ory. g Shutdooms occurs but recul-M "3
. d.
site deray heat removal e O e+ v systems (e.g., filHI nr nunsaf ety , . systems heat rewiuvat samans are . rendered unavailable. Core de-
- gradat tors or melt could occur in 1 about ten hours with subsequent ,
contalement f at ture. , g 5. Any major interral or esternal
- j 2 y]
e events which could cause massive comenon damage to plant systeins
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$ ag sa cc resulting in any of the above.
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, Fires MasAlve damage to ECCS Bystem 4.oss of ECCS Systeen O (J.! Jr p
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-4 Earthquake Maestve damage to ECCS System .l.oss of CCCS System .
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L d [ 2 0 EDDIPMEtiT STATUS FOR FAILURE OF CLADDING A!!D - C0tlTAltiMENT o
- a. ;
WI
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1
- 1
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;: - STATUS INDICATES ALL '
GAP ACTIVITY IN CONTAlHMEllT PENETRATI0flS NOT VALNED OFF OR CLOSED
- Pdli%RY C00LRIT . .- - -
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CORD UICOVERED #{ ,
% 'Y -
o OPERATIONS SUPERVISOR'S $ @ "g "I"E " iE 6 # m y z c GAP ACTIVITY IN STF.Ni ;
- O a w q a ru m W 1 .; .
3 LOSS OF AC m
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n 3
.?. .
LOSS OF ECCS . ., . s i m MS . ( j jj i.
! l
/k'
*j E ya j >j E1 111G11 REACTOR PRESSURE -- -- ...
"UlIll 1%LFuliCT10IllHG / '
*1MLIEF AfD SAFETY / - .
' W 0
M VALVES -- y
" GENERAL EMERGENCY j -
i t . i .
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3 I . EQUIPl!Elli STATUS f0R FAILURE OF CLADDING AND.PRifMRY C001.AtiT 000tlDARY ll!TH POTENTIAL l ng"* aOF CONTAl LOSS ;
,I * . Ts ls '29 :
1
-i -4 *
- ~-
- GAP ACTIVITY lil 5
, tilGH D @ fLL PRES $1M 1 C PallWlY C00LAllT . .
. =
1
. / llIG1 DRdlELL TENPliRATURE j [*
Cone tilCO'KRED -m OR r AND m OR I P ,CTIV11Y IN S- - f i
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+ (MP ACTIVITY IN I -
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C) ' 1 PRESSURE
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- C STt?Ali LillE BREAK PRESSURE I "
E 9 l[/'. N) ( / l dETdEll -
' OR -
. IliCREASillG .
a e CO:lTAllitEllT AND fiSiv - I AND f
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h LOSS OF C0flTAlllMEllT og .
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! C00LitlG STEN 4 LillE Bl?EAK .
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! D0.elSTRENi 0F lislV '
AND l OPERAHONS !'
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- I A . _ SUPERVISOR.OPINTOk o .
14slV FAILURE ( - - L
.T 'i c8 E i ll 9 7g
- l pD OR I , ,
w-CO:tE U:lCOVERED
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C . ./ ~ , ./ - B* I GAP ACTIVITY lli 7 i - - l .511:311 .} OR t l .i l l ' Gh? ACTIVITY IN 'j GENERAL El4ERGENCY i_,,FJp!WY C00UllT , 1
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. TABl.E 1-c i . .
3 2 . ':. %
< . '3 LOSS Of Ct.A00!!!G!
En lp N tTATUS FOR FAILURE Or PRIMARY C'00LANT B0UNDARY AND CONTAINI$E . . d N
+ . .
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STATUS Ir:DICATES . , . . I m
, HIGli DRYMELL TSTERATURE.
. ALL.CGITAll2 EllT -
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@ I VALVED OFF OR F- #1D OR , m OR .
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t - m zl I EltlFT SUPERVISOR S ,
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. r,u m, 4 o J i' [ STF.AM LINE DREAK DOMi- o
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. og j glo <:mFm OF us1E HSIV MALFUttCTION .
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p ECCS FAILURE ,- . f. [ .
@ATEli LEVil LCd OR .
O NID
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STEN 1 LilE DREAK BETHEEll C0tlTAll;MEllT AtlD MSiv l' ;: 2
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CEORGIA POWER COMPANY e t
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HATCH NUCLEAR PLANT
~~
PROCEDURE GENERAL FMERGENCY - SHIFT SUPERVISOR
.' PROCEDURE TITLE .
A HNP-472.3 PROCEDURE NUMBER LAB
. ~ RESPONSIBLE SECTION SAFETY RELATED ( X) 'NON-SAFETY RELATED i* )
_____e_______.___________..____________.. . APPROVED APPROVED . REV. DESCRIPTION -DEPT. PLANT DATE HEAD MANAGER 2 Page i
/
_ _ _$_ _ _ _s'_ _ __J __ f[i 8.2. a
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. _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ .r _____ ______ .
.______________ ...____g._____...I._ _ _ =
6____ 4 __________W______eq ___ g._ ___ ____.. .u.___ .d 6__. _d EE.._____________qu.__. .____..m...___.i..> 6 - . __ ..____.m. .f.. ..
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& E. l. Hatch Nacicar Plant aoa=as ~o HNP 4723 3
dro Title Pcg3 umio o
$m GeorgiaPower d ..
See Title Page 1 of 1
~~
CENERAL EMERCENCY - SHIFT SUPERVISCR NOTE , This procedure supercedes EtP-4702, Revision 4 dated 5-13-78. A. CONDITION , . .. Events are in process or have occurred which involve actual or imminent substantial core degradation or melting with potential i for loss of containment integrity. Release can be reasonably ( )
- expected to exceed PAG exposure levels offsite for more than the i
' - immediate site area. , B. REFERENCE . , FBP-4720 ' FeP-4730 FtP-4853 .
~ ~
g C. ACTION
,,"N 1. Proceed to Control Room immediately.
- 2. Classify and declare emergency using HNP-4720, ensure that correct operator action has been taken to bring emergency under control.
- 3. Using HNP-4853, perform dose assessment calculations, report results to Operations Supervisor.
- 4. Assure call list for General Emergency has been initiated.
l i 5. Activate Internal Survey Team by contacting Operations Support Center Manager when staffed. Direct Internal Survey Teams to areas to be surveyed as appropriate. I 6. Activate Rescue Team as necessary by contacting Operations i .,. ... . ._... Support. Center Manager when staffed.
- 7. Establish communications with the Security Force, Technical Support Center and the Emergency Director as soon as possible and discuss the need for outside assistance.
B. Direct onsite actions to bring emergency under control.
- 9. Assume the duties and responsibilities of the Operations Supervisor if he does not report to the Control Room or is
., f. incapacitated, as per EtP-4730.
[ , ,2 L '
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e4 GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PROCEDURE General _Emeroency u - Ralir Pofnt Leader
. PROCEDURE TITLE .
HNP- 4726
. PROCEDURE NUMBER Lab
. RESPONSIBLE SECTION SAFETY RELATED ( X) NON-SAFETY RELATED (' )
APPROVED APPf<OVED REV. DESCRIPTION
- DEPT. PLANT DATE HEAD MANAGER
______._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . .______ _________ y___--___
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- y. ______ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . .__. _ ,_ .____ .____ __________
F___ ___.
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, .. . _3___ ._P_ age _1_____________ ,_ /_ _ _ , _ _ _ _ . ._ _ _ . , _ __ _____ p___ ___
p / _ _ 4_ _ _ . . P_ag_e s_ _1_ _th_ r_u_. ,)____ _ _ _ . _-F' _ _ _ _ . . _ _ _ _ _M_ v _ _4_ e /2 J M.. W F
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_ _ _5_ _ _ .. _P_aE e_s_ _2_ _a n_d_ _3_ _ _ _ _ _ _ _ _ ._ __. f/_ .,4' # ______.. _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .._________ ______ p________ _ _ _ _ _ _ . .______________a___. . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ..________________ F______ . _ _ _ _ _ _ ..___________________ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ ..____________ ___ F_______. F__ __ . F ____ _. ______- _ _ _ _ _ _ _ _ _ _ . . . _ _ _ _ _ _ _ . _ _ _ _ _ . .________________ F_______.
.. . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . . _ _ _ _ _ _ _ _ _ _ _ . .______ _________ F_______.
______q _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . .________________a ________________ h________ ______< ____________________. . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ________________ p_______.
._____q ____________________..________________- ____________ ___ F________
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g-- w. s. e su6ve s nuvious e iones 8 HNP.4726 3 Sea Titio Peg 2 nuono r U Georgia Powerks 3 e- 5 G. . 1 of 3 i
, See Title Page
- r. .
-. . GENERAL EML9GENCY - RALLY POINT LEADER NOTE .
This procedure supercedes [ HP-4705, Rev. 5 dated 1-2-81. A. COPOITION ,
~
Events are in process or have occurred which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity. Release can be reasonably expected to exceed PAG exposure levels offsite for more than the
. immediate site area. ,
~
B. REFERENCE 6 HP-4720 HP-4721 . C. GENERAL IPFORMATION Br INSTRUCTIONS , i
- 1. The primary rally point for personnel inside the primary
. .,e- protected area is Gate 16. .
.. 4*
~
'- 2. The primary rally point for personnel outside the primary protected area is Gate 1.
- 3. The alternate rally points are:
- a. Environmental Building
- b. Skills Training Building or the Outage Training Building
- 4. The criteria for rally point habitability are:
- a. Area dose rate less than 0.5 MR/l-R and
- b. contamination level less than 100 CPM above rally point background.
- 5. The locations of decontamination showers outside the primary protected area are:
- a. Environmental Building
- b. Outage Training Building g .
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E. l. HetCh Nuclear Plant oc- ~o it = HNP.4726 i / . jhb Titio Pags o.ws.o~ ~o 5-
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See Title Page R of 3
- 6. Do not release any person who has received greater than 25 rem whole body dose or is suspected to have ingested significant amounts of radioactive materials. Such persons i
are to.be taken to the hospital for examination and further i ! evaluation of exposure.
- 7. Confer with the Emergency Direretor before releasing any l personnel involved in the incident.
l 8. Check wi$h the Security Force, general contractors and Georgia Power. Construction Department to letermine those persons remaining in the plant. If any person (s) is (are) . unaccounted for, report this to the Shift Supervisor. If the Shift Supervisor cannot account for the missing I
- person (s), form a rescue team (s) and initiate HNP-4728, ,
GDERAL EERGENCY - RESCUE TEAM. - D. ACTION , ! 1. After the RET assembles in the OSC, the OSC Manager will 4 ,
- appoint a Rally Point Leader to take charge of the rally *
.' , point. ,
. ,! 2. The Rally Point Leader should instruct all RET members not '
assigned a specific function to report with him to Gate 16.
,. 46 ,
~'
~
Leave enoug'h RET members in the OSC to comprise an internal survey team and a rescue team (approximately seven individuals). j
- 3. Determine if the primary rally points are habitable using the criteria in section C.4.
- 4. If conditions at the primary rally points do not satisfy the criteria in section C.4, proceed to an alternate rally point. Determine if the alternate rally point is habitable
! using the criteria in section C.4. 1... . . . . . - . . 5. . Dispatch an appropriate number of RET members to the
- 6. Assure personnel gather at the designated rally points for frisking by RET members and collect all personnel dosimetry.
I" a. Attempt to separate those individuals who were involved in the incident, who were working in contaminated areas, and those wearing protective clothing from other - personnel at the rally point. Q -
, .f .
b , }. 'l - , h , _,,,. , e' ..i 4 M SU l _ _ _ , - _ --- _ _.__u
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See Title Page Georgia Power A .... 3 of 3
- 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 EDF and instruct these personnel to report to the EDF (after checking through the rally point) for further evaluation of dose received.
- e. Dispatch an RET member (s) to accompany contaminated individuals to a decontamination shower (see C.5) and supervise the deconthmination procedure.
- f. Release uncontaminated individuals to evacuate the site on U.S. Hwy. 1 in the direction specified by the gff Control Room. .
E' g. Report status of the evacuation to the Emergency
, ,, Operations Facility. .
s6 [. h. Do not release members of the Radiological Emergency Team, except to go to the EGF unless directed to do so by the Emergency Director or Shift Supervisor if the Emergency Director cannot be contacted.
- i. Assist in routing ambulance to pick up 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.
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l . GEORGIA POWER COMPANY
- . .s<..
eo HATCH NUCLEAR PLANT PROCEDURE
~
General Empr_qency Operapians supervisor
. PROCEDURE TITLE HNP-47 40 PROCEDURE NUMBER Lab !
1
. - RESPONSIBLE SECTION !
l SAFETY RELATED t X) NON-SAFETY RELATED 'O )
. 4 APPROVED APPROVED REV. DESCRIPTION DEPT. PLANT DATE HEAD MANAGER 2 . _ _ _[_ _f~ ,,,w- _ _ _ _ _ _ .
Page 1 f__ g
. .3l:
_ _ _ _f 83_. f.*3
?! _ _ _3 _ _ ._P_ _ . __ age __1______________. _ _ _ _ _ n_ _-r e::tE
- _ _4 _ -,_Page
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- _ _ _ 1
.o - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . .
______..______________ _____. , _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . .______________.__l'_______.
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HNP-9
. 9 M W SET
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1 of 1 GENERAL EMERGENCY - OPERATIONS SUPERVISOR A. CONDITION . Events are in process or have occurred which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrLty. Release can be reasonably expected to exceed PAG exposure levels offsite for more than the immediate site area. B. REFERENCES . HP-4720 , HNP-4740 - HNP-1
- C. ACTION
,avv 1. Proceed to control room. ,
b$ -
- 2. Take control of all activities in the control room, ensuring
, ,. that proper coordination of all activities is carried out. -
p
- - 3. a. Assume the duties of the Emergency Director until the E.O.F. is established. Assure that those actions in HNP-4740 which can be performed from the control room are accomplished.
- b. Assure that correct emergency classification has been declared as per HNP-4720.
- 4. " Evaluate actions of Shift 50pervisor and operators to bring emergency under control.
- 5. The Operations Supervisor is responsible for notification of Plant Management and NRC as per emergency call list and other offsite agencies in accordance with notification procedures HNP-4861. The actual notification process may be delegated to other, specifically trained, shift personnel.
- 6. Consult with the Technical Support Center and Emergency Director to determine any outside assistance needed.
- 7. Assure that personnel are assigned to maintain open line to NRC, T.S.C. and E.O.F. and inform these groups of significant plant changes.
- 8. Provide information to the Emergency Director to assist in
, p- his' determination of close out or reduction of the emergency class, as per HNP-4720.
)
I 4
'. 3 d" GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PROCEDURE H_andlin'S_E_xEosed And/Or Contaminated Casualties PROCEDURE TITLE HNP-4801 PROCEDURE NUMBER
, Lab
. RESPONSIBLE SECTION NON-raAFETY RELATED ( )
SAFETY RELATED ( X) APPROVED APPROVED
, DEPT. PLANT DATE REV. DESCRIPTION HEAD MANAGER p?g y---
6 Pages 3-7, 9-13 ,
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See Title Page 1 of 14 y HANDLING EXPOSED AND/OR CONTAMINATED CASUALTIES A. PURPOSE , To provide procedures for assuring that prompt and effective first aid, medical attention and health physics evaluation is afforded to excessively exposed,and/or contaminated casualties. D. SAITTY , Under all circumstances, unnecessary esposure to radiation should be avoided.. Under emergency conditions, the risk of exposure (usually slight) to the rescuer, the first-aid man, or the health physicist, should be balanced against the contribution (usually great) he is making toward the health and safety of the casualty. C. REFERENCES . HNP-4310
'. o',gd IW -BOO 6
# FSAR, Section 13.7.5 7 10 CFR 20.103. -
10 CFR 20.405. D. DEFINITIONS , For the purposes of this procedure, the following definitions will apply:
- 1. Serious Injury - Injury warranting off-site medical support.
- 2. Acute Exposure - Exposure received over a period of 12 consecutive hours or less.
- 3. Excessive Radiation Exposure - Acute exposure known or suspected to have exceeded the following limits:
- a. Whole body; head and trunk; active blood forming organs; lens of eye; or gonads - 3 rems.
- b. Hands and forearms; feet and ankles 3/4 rems;
- c. Skin of whole body - 7 1/2 rems.
, ., /
- l
Po= E. l. Hatch Nuclear Plant aaoa= = ~o
, . HNP. 4801
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-- .. o See Title Page 2 of 14
- 4. Excessive. Radioactive Contamination - Any of the following:
- a. Detectable radioactivity on or near a wound;
- b. Radioactivity on exposed skin of individual, measured with beta detecting GM survey meter, shows greater than ;
10 "mR,"/hr at 1" from, radioactivity;
- c. Radioactivity on clothing of individual, maasured with l
beta detecting GM survey meter, shows greater than 160 "mR"/hr. at 1" from radioactivity;
- d. For purposes of admission to Appling General Hospital -
- Any external contamination detectable with a beta detecting G.M. survey meter; ,
1
- e. Inhalation or ingestion of radioactivity in quantities '
known or suspected to exceed those allowed by 10 CFR 20.103;
', M f. Inhalation or ingestion of unknown quantities of y radioactivity. ,
, . . . 5. Off-site Medical Support - Care, treatment and/or
. >$ consulation provided by Company Medical Consultant, staff of '
Appling General Hospital, or Radiation Management Corporation. E. APPLING GENERAL HOSPITAL CONTAMINATION CONTROL POLICY
- 1. Policy Appling General Hospital is prepared to provide care and treatment for patients who are externally contaminated with radioactivity in their Radiation Emergency Area only. The hospital defines " external radioactive contamination" as any detectable radioactivity deposited on the outer surface of the patient's body or apparel.
- 2. Procedure In conformance with the Appling General Hospital policy, all
. patients considered for transfer from the plant to the hospital will be monitored by a member of the Health Physics staff. If detectable contamination remains on the patient's body or apparel, the Nurse Shift Supervisor at the hospital will be informed that the incoming patient is " contaminated".
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'. Gds' Tit 1ePsy*n 6 1 om Georgia Power n 3 of 14 ;
See Title Page F. INJURY / EXPOSURE CATEGORIES
- 1. Excessive Radiation Exposure - No serious injury (See
- Section.H) (Normal Hospital Admission *).
2. Excessive Radioactive Contamination - No serious injury (See Section I) (Admission through Radiation Emergency Area, Except if contamination is Exclusively Internal Deposition). 3. Excessive Radiation Exposure and Radioactive Contamination - No Serious Injury (See Section J) (Admission through Radiation Emergency Area, Except if Contamination is Exclusively Internal Deposition) 4. Excessive Radiation Exposure - With Serious Injury (See - Section K) (Normal Hospital Admission *) Excessive Radioactive Contamination - With Serious Injury (See Section L) (Admission through Radiation Emergency Area, 5. Except if contamination is Exclusively Internal Deposition). p
-.,. Excessive Radiation Exposure and Rad,ioactive Contamination 'y 6.
with Serious Injury (See Section M). (Admission through Radiation Emergency Area, Except if .
- r
# Contamination is Exclusively Internal Deposition)
G. GENERAL PROCEDURES
- 1. In any accident, incident, or unusual occurrance, when there is a reasonable probability that an individual may have been seriously injured, exposed and/or contaminated, provide first aid, then make immediate contact with the Company (if radiation Physician and Radiation Management Corporation is involved) in the event that an individual is known or
, suspected to have been seriously injured, summon the ambulance needlessly than to jeopardize a man's life.
All exposure, contamination, or injury incidents, or 2. combinations coming within the scope of this procedure, (e.g., In some instances warrant off-site medical a 4 rem whole body exposure) support.the support may simply consist of telephone consulation with the Company Physician and(e.g., In other instances Radiation Management Corporation.the need for support may be far more urgent. a burn case), i
' Accordingly, Shift Supervisor will obtain a prompt 8 evaluation of the urgency for off-site medical support.)
- Monitor the patient for incidental, but detectable contamination. If contamination is detected, he will be admitted through Radiation Emergency Area. .
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? , HNP 4801 umiou uo AdbTitlePago 5
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4 of 14 See Title Page first priority will
- 3. In all cases covered by this procedure,After a victim has been always be given to serious injury. care and treatment for removed from a hazardous area, excessive raediation or contamination exposure can be deferred without significant harm to the victim, but failure to administer prompt first aid may jeopardize his life.
- 4. Tne Plant Manager will assure that each accident / incident is investigated, its causes determined, and action taken to prevent its recurrence.
- 5. After each accident or incident the in which first aid Laboratory or Foreman will Medical Room supplies were used, assure that these supplies are replenished. ,
H. EXCESSIVE RADIATION EXPOSURE ,NOT SERIOUS INJURY
- 1. Immediate Action
,pv a. Exposed individual will take immediate* action to protect himself from further exposure. ,
'",{p ' ,
- b. Exposed individual will notify Shift Supervisor without l
~
delay.
." 7 Shift Supervisor will aler,t member of the Health l
- c. I Physics staff and direct him to exposed individual.
- d. Member of Health Physics staff will:
(1) Attempt to determine nature and degree of radiation exposure by:
- (a) Discussion with exposed individual; (b) Survey of accident / incident area; (c) Read exposed individual's pocket dosimeter.
(2) Advise Shift Supervisor of the urgency for medical l support. (3) Allay fear and relax the exposed individual.
- 2. Follow-up Action i
- a. Shift Supervisor will notify General Manager, l Operations Supervisor and Health Physics Superintendent.
- b. The Plant Manager will:
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**gva' E. HatCn Nuclear Plant aaoctouat ~o HNP.4801 aavisic~ ~o 5 e Title'Page
.* '9 6
- o. . Georgia Power s .. . ~o 5 of 14 See Title Page (1) ' Notify or authorize notification of Company and Plant Medical Consultants and Radiation Management Corporation.
(2) Imediately notify NRC Regulatory Operations, Region II, by telephone and telegraph if: (a) Personnel whole body etposures suspected to be 25 rem or more; (b) , Personnel skin exposure is 150 rem or more; (c) Personnel extremity exposure is 275 rem or more. (3) Notify NRC Regulatory Operations, Region II, by telephone and telegraph within 24 hours if exposures are 20% of the above values. (4) Assure report required by 10 CFR EO.405 is sent to j titC within 30 days of accident. e,.g .
*# - c. Exposed individual will be obselved for symptoms, such as nausea, vomiting, fatigue, skin redness, or
~
[. diarrhea, while awaiting results of consultation ,
'. between Health Physics sts.ff, Plant and Company Medical Consultants and Radiation Management Corporation.
- d. Health Physics staff will send exposed individual's TLD badge to vendor for EMERGENCY processing.
POTE There is no need for ficst aid or for urgent transfer of exposed individual to hospital. If determined by medical consultation that hospitalization is indicated, individual will be transfered to Appling General Hospital. Unless exposed individual has incidental detectable contamination, he will not be admitted through Radiation Emergency Area. Refer to HNP-424 and HNP-4420 for one hour notification to authorities. I. EXCESSIVE RADIOACTIVE CONTAMINATION - NO SERIOUS INJURY
- 1. Imediate Action
- a. Contaminated individual will withdraw from the immodiate area of contamination, take elementary steps to decontaminate himself (e.g. remove clothes and wash exposed skin), notify the Shift Supervisor and await i I
member of Health Physics staff.
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a d* E.1. Hatch Nucicar Plant === = ~o HNP. 4801 Qe,,$'Titio Pago uwsou ~o Georgia Power fn(
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See Title Page 6 of 14
- b. Shift Supervisor will alert member of the Health l Physics staft and will direct him to contaminated individual .
- c. Member of Health Physics staff will:
(1) Determine the Iqv91 of external contamination us'ing a G.M. survey meter. (2) Initiate personnel decontamination procedures (Refer to FN8-8006). (3) Estimate extent of internal contamination by
- assaying noseblow sample. .
(4) Advise Shift Supervisor of the urgency of need for off-site medical support. (5) Recover contaminated individual's , personnel dosimeters.
. W'
- 1[ 2. Follow-Up Action -
, .. a. Shift Supervisor will notify General Manager, d' Operations Supervisor and Health Physicist Radiochemist.
- b. Plant Manager will:
(1) Notify or authorize notification of Company and Plant Consultants and Radiation Management Corporation. (2) Assure th7t report required by 10 CFR 20.405 (it any) is sent to NRC within 30 days.
- c. Health Physics staff will assure contaminated individual's TLD badge is sent to the vendor for EPERGENCY processing.
- d. Health Physics personnel will perform analyses of contamination to determine its isotopic composition (if internally deposited).
ec The Health Physics staff, with assistance from Radiation Management Corporation, will initiate bioassy program to help determine level of internal contamination and to follow its reduction.
- f. Subsequent treatment to accelerate reduction of internal contamination may result from consultation between Plant and Company Medical Consultants and
' N' p -
Radiation Management Corporation. - e I
1
**ao= E. I. Hatch Nucinar Plant aaocio#e~o.
HNP 4801 a.. o~ ~o
< 3-4..ee Title Page om Georgia Power d ..
See Title Pace 7 of 14.
- g. If contaminated individual is evacuated to hospital, he will be admitted through the Radiation Emergency Area.
Refer to HNP-424 and HNP-4420 for notification to authorities within one hour. J. EXCE M IVE RADIATION EXPOSf)RE AND ** RADIOACTIVE CONTAMINATION NO SERIOUS INJtA1Y ,
~.
! 1. Insnediate Action
- a. Exposed /' contaminated individual will protect himself from further exposure / contamination by leaving the hazardous area.
- b. Exposed / contaminated individual will notify Shift-Supervisor without delay.
- c. Shift Supervisor will alert member of Health Physics staff and will direct him to exposed / contaminated individual.
l V d. Member of Health Physics staff will:
- v (1) Determine the level of external contamination .
using a G.M. survey meter.
~
(2) Estimate extent of internal contamintion by assaying noseblow sample. (3) Determine nature and degree of radiation exposure by: (a) Discussion with exposed individual; (b) Survey of accident / incident area; (c) Read exposed individual's pocket dosimeter. (4) Advise Shift Supervisor of the urgency for off-site medical support. (5) Initiate personnel decontaminatian procedures (Re f e r to Hlf-8006) .
- 2. Follow-Up Action
- a. Shift Supervisor will notify General Manager, l l
Operations Supervisor and Health Physics Superintendent.
- b. General Manager will:
%NM IU
E.1. Hatch Nucicar Mant m our.~o af*= HNP 4801 3. j Titl'e Pago a.da um o,,,,o 6
*
- o;. .
GeorgiaPcwer n .. 8 of 14
' See Title Page (1)' Notify or authorize notification of Company and
' ' Plant Consultants and Radiation Management l Corporation.
(2) Immediately notify NRC Regulatory Operations, Region II, by telephone and telegraph if:
' ~
(a) Personnel who1e body exposure is 25 rem or more;
~',-~~
~
(b) Personnel skin exposure is 150 rem or more; l
.' (c) Personnel extremity exposure is 375 rem or more. .
(3) Notify bEC Regulatory Operations, Region II, by > telephone and telegraph if exposures are 20% of the above values. . (4) Assure report required by 10 CFR 20.405 is sent to NRC within 30 days of accident.
" 8' -
- c. Exposed individual will be obsbrved for symptoms, such as nausea, vomiting, fatigue, skin redness, or
~
f' diarrhea, while awaiting results of consultation ,
-- between Health Physics staff, Plant and Company Medical Consultants and Radiation Management Corporation.
l
- d. Health Physics staff will send exposed individual's TLD badge to vendor for EMERGENCY processing.
- e. Health Physics personnel will perform analyses of contamination to determine its isotopic composition (if internally deposited).
- f. The Health Physics staff, with assistance from Radiation Management Corporation, will initiate .
bioassay program to help determine level of internal contamination and to follow its reduction.
- g. Subsequent treatment to accelerate reduction of
. -. 4
.-..w..... .. internal contamination may result from consultation ..
between Plant and Company Medical Consultants and Radiation Management Corporation.
- h. If exposed / contaminated individual is evacuated to hospital, he will be admitted through the Radiation Emergency Area. Refer to HNP-4400 for notification to authorities within one hour.
- s. e .y / " ,
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~ ~o om GeorgiaPower n 9 of 14 See Title Page K. EXCESSIVE RADIATION EXPOSURE - WITH SERICUS INJURY
- 1. Inunediate Action
- a. First person who becomes aware of a serious injury will notify Shift Supervisor. l b.
Shift Supervisor'wili alert individual trained in first aid and member of the Health Physics staff and direct them to injured.
- c. Individual trained in first aid and member of Health Physics staff will: .
(1) Administer first aid consistent (Refer to HNP-4810). with nature and - extent of injuries. l (2) Advise Shift Supervisor of urgency of need for off-site medical support.
. (3) Recover injured's personnel dosimetry. .
;is, # .
3 (4) Remove injured from area of risk in accordance
- n' with HNP-4802.
P Shift Supervisor will summon Plant Medical Consultant l
' d.
(Company Physician) and ambulance or, on the advice of the Plant Medical Consultant, will arrange to transport injured to hospital via company or personal vehicle.
- e. Shift Supervisor will inform Nurse Shift Supervisor at {
Appling General Hospital that an injured individual will be sent to the hospital for treatment. NOTE Unless injured has incidental cetectable contamination, he will not be admitted though the Radiation Emergency Area. Refer to HNP-424 and HNP-4420 for one hour notification to authorities.
- 2. Fo l l ol w up A c t i o n ' ' ' '~ ~"' ' '"' - ' " ' *' * ~- ~ -- --~ ~- -
- a. Shift Supervisor will notify General Manager, Operations Supervisor and Health Physics Superintendent.
- b. Ge$1eral Manager will:
(1) Notify or authorize notification of Company and Plant Consultants and Radiation Management '
* ,- Corporation.
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~ . . . . . . .
- -- _ ~ ~ - - - - - - - - - - - - _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ __
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Georgia Power s k .
- om 10 of 14 See Title Page (2) Immediately notify NRC Regulatory Operations, Region II, by telephone and telegraph if:
(a) Personnel.whole body exposure is 25 rem or
,p,;
- ~' ~~
(b) Personnel skin e'xposure is 150 rem or more;
.(c) Piersonnel extremity exposure is 375 rem or mo f* e.
(3) Notify NRC Regulatory Operatiuns, Region II, by telephone and telegraph within 24 hours if exposures are 20% of the above values. (4) Assure report required by 10 CFR 20.405 is sent to bRC within 30 days of accident.
- c. The Health Physics staff will: .
' (1) Determine nature and degree of radiation exposure yy.
i
- s' (a) Discussion with injured; ~
.. J' (b) Survey of accident / incident area; (c) Read exposed individual's pocket dosimeter.
(2) .Sent the injured's TLD badge to the vendor for EMERGENCY processing. L. EXCESSIVE RADIDACTIVE CONTAMINATION - WITH SERICUS INJURY
- 1. " Inunediate Action:
- a. First person who becomes aware of a serious injury will ,
j notify Shift Supervisor.
- b. Shift Supervisor will alert individual trained in first l
. .---- . aid and member of the Health Physics staf f and direct _
them to injured.
- c. Individual trained in first aid and member of Health Physics staff will:
(15 Administer first aid consistent with nature and (Refer to HNP-4810). extent of injuries. e s
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- See Title Page 11 of 14 (2)- In accordance with HNP-4802, move injured to
- Medical Room in Control Building and initiate decontamination procedures (Refer to HNP-8006)
- while continuing first aid. If injured cannot be
- moved safely make him comfortable and await
. arrival of Plant Medical Consultant or ambulance.
(3)- 6dvise Shift Supervisor of urgency of need for l off-site medical support. (4) Recover lujured's personnel dosimetry. (5) Estimate extent of internal contamination by assaying a nose blow sample. ,
- d. Shift Supervisor will summon the (Company Physician), l I
ambulance or, en the advice of the Physician will arrange to transport injured to Appling General Hospital via company or personal vehicle.
- e. Shift Supervisor will inform Nurse Shift Supervisor at
. j . . Appling General Hospital. , t i E
#' _ Emphasize that the injury does involve radioactive
- contamination and that injured is to be admitted to Radiation Emergency Area according to special hospital
" Procedures for Handling Radiation Accidents". Refer to HP-424 and HNP-4420 for one hour notification to authorities.
- 2. Follow-Up Acti'on: .
. a. Shift Supervisor will: l (1). Assign member of the Health Physics staff to accompany the injured and provide complete health physics support to ambulance and hospital staff.
(2) Notify General Manager, Operation Supervisor and
..-. ....... ... ...~, ..A . Health Physics Superintendent. . . . . . . , , , ..
- b. The Plant Manager will:
(1) Notify or authorize notification of Company
. . Physician and Radiation Management Corporation; (2) Assure report required by 10 CFR 20.405 is sent to MtC within 30 days. ,
9
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- C See Title Page Georgia Power d ....
12 of 14
- r. . . ',
- c. The Health Physics staff will:
(1) , Assure injured's film badge is sent to vendor for EPERGENCY processing. (2)- Initiate analysis of samples of contamination to determine its isoltopic composition (if internally de'p os ii:ed ) .
~
(3) Be responsible for recovery of all radioactive waste from " Radiation Emergency Area" at Appling
. General Hospital.
- d. . When injured's condition has been stabilized, decontamination efforts will be re-initiated so that patient can be moved to conventional part of hospital.
- e. Subsequent treatment for internal radioactive contamination will result from consultation between Company Physician and Radiation Management Corporation.
.c - - -
y _ Any radioactive material (shrapnel) removed from '
~
I.
- injured will be recovered, if feasible, and used as aid
_ in determining ultimate exposure suffered by injured. M. EXCESSIVE RADIATION EXPOSURE AND RADIDACT1 2 CONTAMINATION WITH SERIOUS INJURY ,
- 1. Inunediate Action
- a. First person who becomes aware of accident / incident will notify Shift Supervisor. l
- b. Shift Supervisor will alert individual trained in first l
aid and member of the Health Physics staff and direct-them tu injured.
- c. Individual trained in first aid and member of Health
...-. ..-... Physics staff will:
. . . - . . - . . . . . . . . - . .........--...._.....4 (1)' Administer first aid consistent with nature and extent of injuries. (Refer to HNP-4810).
(2) In accordance with HNP-4802, move injured to
- Medical Room and initiate decontamination procedt.res (Refer to HNP-8006) while continuing first aid. If injured cannot be moved safely, make him comfortable and await arrival of Plant
., f Medical Consultant or ambulance.
14, ;
*' (We' SET 1, <
at= E. l. Hatch Nuclear Plant aaoawai ~o HNP.4801 misio~ ~o 3
, g. :C.00 Title Paqa 6 om Georgia Power n ...~.
13 of 14 See Title Page (3) . Advise Shift Supervisor of urgency of need for off-site medical support groups.
~
(4) Recover injured's personnel dosimetry. (5) Estimate extent of internal contamination by assaying a nose , blow sample.
. yayg
'~~
Emphasize that the injury does involve radioactive
~
contamination and that injured is to be admitted to Radiation Emergency Area according to special
- hospital " Procedures for Handling Radiation Accidents". Refer to HNP-242 and HNP-4420 for one hour notification to authorities.
- 2. Follow-Up Action:
- a. Shift Supervisor will:
(1) Assign member of the Health Physics staff to
${f accompany the injured and provide complete health
,p physics support to ambulance and hospital staff. .
/*
~~
(2) Notify General Manager, Operation Supervisor and l Health Physics Superintendent.
- b. The Plant. Manager will:
(1) ' Notify or authorize notification of Company Physician and Radiation Management Corporation; (2) Immediately notify NRC Regulatory Operations, Region II, by telephone and telegraph if: (a) Personnel whole body exposure is 25 rem or more; (b) Personnel skin exposure is 150 rem or more;
-~ ~ ~ "' "~ "- " " ~ " ~ ~ ~h "- ( c ) Personnel extremity exposure is 375 rem or more.
(3) Notify NRC Regulatory Operations, Region II, by telephone and telegraph within 24 hours if exposures are 20% of the above values. (4) Assure report required by 10 CFR 20.405 is sent to NRC within 30 days. -
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14 of 14 See Title Page .
- c. The Health Physics staff will:
(1). Assure injured's TLD badge is sent to vendor for I
. EPERGENCY processing.
l (2) Initi, analysis of samples of contamination to determine its isoltop'ic composition. ; (3) Be responsible for recovery of all radioactive waste from " Radiation Emergency Area" at Appling
' General Hospital. .
(4) Determine nature and degree of radiation exposure
~
by" i (a) Discussion with injured;
~ (b) Survey of accident / incident area; (c) Read exposed individual's pocket dosimeter.
'$ d. When injured's condition has been satbilized,'
; decontamination efforts will be re-initiated so that
.e patient can be moved to conventional part of hospital. .
2*
~'
e.- Gubsequent treatment for internal radioactive contamination will result from consulation between Company Physician and Radiation Management Corporation.
- f. Any radioactive material (shrLpnel) removed from injured will be recovered, if feasible, and used as aid in determining ultimate exposure suffered by injured.
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HATCH NUCLEAR PLANT ,
- PROCEDURE Security Alert - Security Force
, PROCEDURE TITLE HNP-4902 PROC 50URE NUMSER
( 8 Lab - I . RESPONSIBLE SECTION
)
NON-SAFETY RELATED ( SAFETY RELATED ( X) . ___________ _____p ________
.____..____s_______________.._______________.. APPROVED APPROVED 'DATE DEPT. PLANT REV. DESCRIPTION MANAGER HEAD _ _ _ _ _ _ _ _ . . ___ ___.
y g g _y _ ,. 4D' 4 Page 2 4_ _ _ _ _ . _______ __f__..- e
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7** E. l. Hatch Nuclear Plant =towi ~o
, HNP.4902 3 #so Titio Pags xtwoon ~o C. Georgia Power d ..
g See Title Pace 1 of 2 . f .
. SECURITY ALERT - SECURITY FORCE
~
A. CONDITION, . Notification has been received of a security alert involving: A bomb, other over' t threat, oc a ci'vil disturbance. B. ACTION .
- 1. Security Post.200 Delta (Monitor /Consnunications Operator).
- a. Notify the Appling County, and/or Toombs County
. Sheriff's Department, and/or the Georgia State Patrol (depending on the nature of the cause for the alent) giving them the conditions causing the alert. ,
- b. Initiate provided up to date call list for security alerts giving to the persons on the li,st the conditions for the security alert.
- Q", #
. c. Notify Gate 1 (Construction) that a security alert has 5' -
been called and to admit no persons or vehicles until the alert has been terminated or access granted by , h, plant management.
- d. If the security officer on'200 Charlie (Access) has
.been committed to the Response Force, admit no persons or vehicles to the protected area until the security alert has been terminated or access is granted plant management.
- e. Verify communication radio and telephone communication with the Control Room.
- 2. Shift Supervisor (Security) ,
- a. Have all non designated vehicles removed from the protected area.
... . .. - ....._ ~. .
- b. Recall all visitors and have them leave the protected ... .
,p,,,
- c. If unauthorized entry or intrusion is discovered or suspected, notify the Shift Foreman, and begin a search for the intruder. If necessary, activate the Response Force and call in additional security personnel.
Search the exterior of all buildings and structures. The Shift Foreman will conduct the necessary interior searches. .
, , ., / '
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- ... GeorgiaPower d Gee Title Pace 2 of 2 If a' bomb is suspected or discovered, refer'to HNP-302, Bomb dnd Other Overt Threats. .
- d. Assist Operations Supervisor in determining if further emergency actions are required.
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l GEORGIA POWER. COMP AN~y 4 HATCH NUCLEAP PLANT PROCEDUPE General Emer._qency w __ - Savannah Rive r _Op_e rations 04i ce PROCEDURE TITLE hNP-4734 , PROCEDURE NUMDER Lab RESPCNSIBLE SECTICN SAFETY RELATED ( X ) NON-SAFETY RELATED ( )
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. _ _._ ___ ______ _______..________________. _ _ _ _ _ _ _ _ _ _ _ _ _ . ._______ . j APPROVED APPRO'ED .
l REV. DESCRIPTION DEPT. PLANT DATE HEAD MANAGER
- _ _ _ _ _ .._____.m____________. .________
i 2 Page 1 _ _ . -y_g4g. y_________. g7 _ _ _ _3_ _ _ _ . . _ _ _P_a.JLe _1 _ _ _ _ _ _ _ _ _ . _#____ _ . _ _
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. _ _ _ _ . . _____ __ .. ____ q__ .__ ___ _ _ ..___ _ ________. ____ e
. _ _ . . ,_________________q,_______________._.._______________._.,_______.,
HNP-9 MAH AL SET
_ - ___.._ L__. _ _._ _,m _ _ dd 6 2c/t3 - a ,e r. PROCEOtr5 NO. H. .:: > __p! _i_#,.- .*i i. 4 . t
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) An unrevice d Safety Co stic.n ( ) Tach. Specs.
( ' (See b;.ch for Safety Eva)ustic.n if rc-quired). ,
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- REASON FCG RECT.EF,T- _ ._
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. . _ --_---_T 2.h e co s s.i.b _i l-~~-----_a result frc- tnis ch.'nce because -_---___
th-e- n- .a - n a_l v e d _ _ _ _i -n- t h_e_F_S_A_ _ _c _s _ _r e_: - -.--_ _------------------. f _--_t_h_e__s ,v s t e _re s c_on d_s__a n_d__i s ------- - - _ -- :: s_r_a t_ed ----_a - _s b e-----------f o re th e ch t n c e_. d_e_".e_d_i n__t_h_e _T_e_ch n_i_c_a_l S c e ci f i c a t i eni-s_ -- _3_.__Th e._: a_re "--.,._o_f_ s.a.f_e_t -_a_s_ y - bm is not- =redu.c_ed__due _ - . - -- -- _to t_h_is rev_is icn__b_eca_u_s_ e the re_vi_s_ien does _not .-- chan_ce__anv_l_i_._.i_ted_ saf a_t_v_s sts-' s_e_t_ tines whi_ch woul d al.l_ow a_ a__l im_i_t_i -- ne---- _condi t_i e_n fe,r _ s_a_f.et'v - _l,.i.m.i t t_o
- -----_ be ex c e_s_i.d.- o_r to_ all m., -- - -- -
__ -__o_o_e_ra .-t i e_r_s tc_ b e _e x c.e. s c i_f_ i s _s t a t e d _i _n _T_e_c_h n i _ -- -
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- t. _ _ _ _ - - _ _ - . _ _ _ _ _ _ - _ - - _ _ _ - _ - - - - - _ _ - _ - _ _ .-- - _ . - _ _ _ _ - - _ _ _ _ _ .
+
. H.m 3 MANU AL SET -
^ -- -- ------- _ _ _ - _ _ _ ._ _ _ _ _ _ _ _ _ -a
1
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HNP-4734 ; E. l. HATCH NUCLEAR PLANT w* -
, )
See Title Pace "
~~
GeorgiaPower d 1 of 1 App T4 tie Pace GENERAL EMERGENCY - SAVANNAH RIVER CPERATICNS OFFICE l WE This procedure supercedes HP-4714 Rev. 4 dated 9-7-79. A. COtOITION Events are in process or have occurred which involve actual or 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. ;
- 8. REFERENCE HP-4720 C'. ACTION Respond in accordance with the Interaaency Radioloaical 1.
Assistance Plan for Region 3.
*- 2. Radiological Assistance Team reports in to the Emergency Operations Facility specified. - Normal Emergency Operations Facility - Simulator Building at Plant E. I. HATCH (Telephone: 367-7863, 367-7864 or 367-7851, ext. 2701). l 1
0L r uility - Annling Cno-'- t . . '. - 4. m Emory n,y nnor --- i (Telephone: 3 6 ( - m .o W .) Sheriff's office at the courtncuse. 3ra.~. l MANU AL SET l
____-___-____ - __ _______ __ _ _ _ _ _ ~ - l 1 - - -- 1 I 9 GEORGIA POWER COMPANY HATCH NUCLEAR PLANT
/ PROCEDURE REPAIR AND CORRECTIVE ACTION FO! LOWING A RADI_Ot.OGICAL FMFRCFNCY PROCEDURE TITLE HNP-4R66 PROCEDURE NUMBER LAB RESPONSIBLE SECTION NON-SAFETY RELATED ( )
SAFETY RELATED ( X) ______.p________________..__ ______ _____:..y________ ______y______ ______ APPROVED APPROVED - DEPT. PLANT DATE REV. DESCRIPTION q
- HEAD MANAGER
-_______________r (w
O New Procedure /7 _J_[_ ___. g
._____ ._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . .; _ _ _ _ _ _ _ . .___+ ..4._____..
/ f .
__L__ .__f_ age __4_____________.. _ _ _ _ _ . . __ _m__ _a_ _& _ h_ i_E _- __ I_t 2 Pages ._f
, _ _ _ _ _ _ _5_ _a_nd_ _7_ _ _ _ _ _ _ _ . g _ _ _ _ . _ _ _ _ f_e_-(
_ _-pc e (//_fg_jT __ ______4___________________ ,________________. .________________ r__ _____ ______4______________-_____ p________________. .____ .__________- 4________________.. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .,__ _____
.________________4________
._____ F____________________. . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .
______ r____________________. . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . ______ 4-___________________.r________________.
- - - _ _ _ .r
- -_. r____________________ .. _______________
------.--___ ______________ ..________________..________________+________
HNP-9 HANUAL SET
=so= ~o l
- a' E. I. Hatch Nuclear Plant HNP.4866 'l l
See Title Page tavmo= ~o
-t 'gI GeorgiaPower d .. . ~o 1 of 7 See Title Page I REPAIR AND CORRECTIVE ACTICN l FOLLOWING A RADICLOGICAL EMERGENCY A. PURPDGE 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 Evalua-tion of Radiological Emergency Response Plans and Preparedness in 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. l*F-8002, " Radiation Exposure Limi_ts."
- 5. 1+P-4812 " Emergency Exposure Guidelines" C. ACCESS CONTROL
- 1. During an emergency, access to the protected area will be controlled. In addition, access to all' areas beyond C-52 will require specific authorization and will be limited to personnel who are needed to provide specific functions in the Turbine and/or Reactor Suildings. An example of the personnel who will receive authorized clearance to these areas are: Control Room personnel, personnel on the fire brigade, RET members for the purpose of internal surveys and personnel required for repair and corrective action functions. A list of Control Room personnel requiring access shall be provided by the TSC manage r or his 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 Radiation Areas shall have more stringent requirements to be discussed in a later section of this procedure. MANUAL SET
eaon== = a== E. l. Hatch Nuclear Plant HNP. 4866 um o,. ,o S o Titis Peg 2 om Georgia Power n . 2 of 7 l See Title Page D. EXPOSURE LIMITS AND AUTHORI7ATION
- 1. All exposures to personnel are to be kept as low as is reasonably achievable. This pertaine 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 a " Authorization to Exceed Administrative Exposure Guides" by the indicated parties.
- 3. Exposure to the whole body shall also be limited to 1,250 mrem / quarter. Any expected whole body exposure in excess of 1,250 nRem 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 l 1. Persons performing the planned actions should be volunteers broadly familiar with exposure. consequences. l 2. Women capable of reproduction shall not take part in these actions.
- 3. Internal exposures shall be minimized by respiratory protection, and contamination controlled by use of protective clothing.
- 4. Workers that are to perform the required actions should be well trained in the jobs that they will be performing to cut down on the amount of time they need to spend in the area (s).
F. RADIATION WORK PERMITS
- 1. Whenever practical, an RWP should be initiated before any work is performed.
MANUAL SET
*= E. l. Hatch Nuclear Plant ~xt=a ~o HNP.4866 unsio~ ~o 1 S2a Title Peg 2 '
k
-. Georgia Power s .. ~o 3 of 7 See Title Page
- 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 rates. All smears that are taken are to be counted for Beta activity as well as Gamma activity.
- 7. It may be necessary, in some 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 may 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 also be performed to evaluate radiciodine concentrations.
. G. EXPOSURE CObrTROL l
- 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.
MANUAL SET i
**:< = n ~o
*-om E. l. Hatch Nuclear Plant HNP 4866 S;c Titlo Paga "
Georgia Power d . . . . , 4 of 7 See Title Page . Personnel shall bq equipped with dos 3 meters capable of measuring anticipated doses. This shall include, but not be 3. limited to:
- a. Two direct reading pencil dosimeters for whole body exposure:
- 1. O-200 mR and/or 0-5 R; a'nd
- 2. 0-20 R
- b. A Thermo1'minescent u Dosimeter (TLD) to permanentIY record whole body exposure.
- c. Extremity dosimeters when the extremity exposure rate times the whole body exposure is likely to be four (4) rate and the extremity exposure rate is likely to be The extremity dosimeter (s) 400 mrem /hr or greater.
is/are to be worn on that part of the body that is likely to receive the exposure.
- d. A digital alarming dosimeter (0-10 R)digital The with areadout and predetermined alarm set point.
the alarm will enhance the worker's knowledge of his accrued dose. Protective clothing shall always be worn by workers entering 4. areas for the purposes of repair and corrective Action. The 1 minimum dress requirements shall be*
- a. One pair of cotton gloves
- b. One pair of rubber gloves
- c. One pair of cloth booties
- d. One pair of rubber booties i
In the event that more stringent requirements are specified on the RWP, or by H. P. Supervision, then those requirements shall prevail.
- 5. Respirators shall be worn as appropriate. In all cases where airborne contamination is anticipated, personnel shall be fitted with pressure / demand Sc1f Contained Breathing Apparatus (SCBA) as a minimum.
- 6. Potassi.um Iodine (KI) tablets should be administered to all personnel who are likely to inhale 20.0 uCi D.E. I-131 or greater. This decision ic.to be based on the results of HP previous Whole Body Counts and'the projected exposure. '
Supervision shall make the final determination on whether or not KI should be issued. MANUAL SET l x
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- 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. Note that radiciodine contamination of the skin will be handled the same as any other skin contamination. Existing survey and decontamination procedures will be followed. See HNP-8005 and HNP-BOO 6. .
H.. ALARA CONSIDERATIONS
- 1. In order to maintain radiation exposures to personnel performing repair and corrective action functions during emergency conditions as low as is reasonably achievable, the following steps should be performed, whenever practical:
- a. Prebriefing-All workers that are to be sent into High Radiation Areas should be made aware of the dose rates in the area, stay times, and airborne concentrations.
All werkers should be familiar with exposure consequences. An attempt should be made to estimate i 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 riach their destination (i.e., the route i 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 Operations Supervisor.
(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 l 1 probably be used in reaching the destination, care should be taken to reduce the number of trips i needed. MANUAL SET l 1 -
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om Georgia Power n k ... 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. (5) 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, J 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 ,iob 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 respiratcry protection equipment must be worn by l all persons who have the potential of inhaling l 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. l I l MANUAL SET l
**~om E.1. Hatch Nuclear Plant *
. -ou=at ~o HNP 4866 unio = ~o S o Titio Pago 2
om Georgia Power n ... o 7 of 7 See Title Page l (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 ster 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 Operations Supervisor. (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 j involved in the operation. (3) The degree of success or failure should be reviewed upon completion of each job and should also be documented for further use.
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I. EFFLtENT RELEASES NOTE Due to the increased likelihood of fuel failure during an accident condition par-ticular care must be taken in analyzing all releases. In addition to performing isotopics on a GeLi detector, all gaseous effluent tilters must be
- measured for Beta emitters, particularly Sr-90. Refer to .
appropriate HNP-7000 series procedures for analysis. 9 e MANUAL SET}}