ML20041G039
| ML20041G039 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 03/01/1982 |
| From: | Clint Jones, Rogers W GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20041G037 | List: |
| References | |
| PROC-820301-08, NUDOCS 8203190089 | |
| Download: ML20041G039 (31) | |
Text
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. . . GEORGIA POWER COMPANY I
s HATCH NUCLEAR PLANT } PROCEDURE. SITE _ AREA FMERGFNCY - VISITOR _'S CFNTER DIRFCTOR PROCEDURE TITLE HNP-4633 PROCEDURE NUMDER . LAB
- RESPONSIBLE SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( )
______a____________________..________________..________________.________ APPROVED APPROVED REV. DESCRIPTION DEPT. PLANT DATE - HEAD MANAGER
-_____~ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _.________ _ _ _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ..________
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______ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ..________________a______________.__..________
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______ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _.________________m.________________..________ l l 4 s e l
- _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ..________ 1 1
_ _ _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _l.s i l. _ _ l \ N) h i \
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I of 2 l SITE AREA EMERGENCY - VISITOR _'_S CENTER _ DIRECTOR NOIE I This procedure supercedes HNP-4613, Revision 3 dated 12-12-80.
- l 1
A. CONDITION i Events are in progress 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. 4 D. REEERFNCE , HNP-4620. l C. ACTION l
- 1. When notified, stop exhibits and have all personnel and !
visitors report to the reception area.
- 2. Obtain the high range survey meter and determine the dose rate.
- 3. Obtain the G.M. survey instrument and determine background.
If less than 200 CPM, survey persons for contamination as in step 5.a. If greater than 200 CPM evacuate immediately per step 4 and survey persons for. contamination following evacuation per C.S.
- 4. Form a caravan of vehicles and exit the pkant site in the upwind direction. Take Visitor's log, high range survey meter, and GM survey meter with you.
l
- 5. Halt caravan in a suitable location where dose rate is j approximately background. (Less than 200 cpm).
I a. Survey persons' hands and feet for contamination, if l not already done. If contaminated (grea+er than 100 CPM above background) segregate for transportation to Emergency Operations Facility,
- b. Check vehicles for contamination. E.(
of persons befor)e
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- 6. Obtain vehicle license numbers and names releasing. Release persons and vehicles that are not CCd$ t Ef; F *y ,
'* contaminated greater than 100 cpm above background.
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i NOTE In order to assure that license numbers l and names of visitors released from the i center will be obtained both a security officer and an R.E.T. member will be sent to the visitors center as soon as possible 1 to assist in this job. .
- 7. Contact Emergency Operations Facility for instructions on i decontamination of persons and vehicles. This will normally l be done at the Emergency Operations Facility.
- 8. Report status of evacuation to Emergency Director by use of l l!
nearest available telephone.
- 9. Report to Emergency Operations Facility if requested'to do ,
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HATCH NUCLEAR PLANT , PROCEDURE . SITE AREA FMFRGENCY - FMERGFNCY DIRFCTOR SiOCEDURE TITLE i i HNP-4640 PROCEDURE NUMBER - i f t LA_B RESPONSIBLE SECTION . f I SAFETY RELATED ( X ) NON-SAFETY RELATED ( ) i 4 I APPROVED APPROVED REV. DESCRIPTION DEPT. PLANT DATE - HEAD MANAGER
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' ' Q om Georgia Power n -- No V' Oee ritto page t nf 7 SITE AREA EMERGENCY - EMERGENCY DIRECTOR l NOTE . This procedure supercedes HNP-4610 Revision 5. - A. CONDITION i Events are in process or have occured 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 neer the site boundary. B. REFERENCE i HNP-4620 * ' C. ACTION l 1.. The Plant Manager, or his designee, will assume the position of Emergency Director as soon as he can establish himself in a control center (TSC or EOF). A Corporate Manager will assume the role of Emergency Director as soon as he can ' travel to plant site. The Emergency Director is responsible ' for the overall management of the emergency response and j will generally operate from the EOF. Assign personnel as I necessary to perform the duties below. '
- 2. Determine if the Emergency Operations Facility is in a safe area through the use of portable. survey instruments located in the Emergency Kit.
- 3. Establish communications with the Control Room and the Technical Support Center and obtain information on the ;
diagnosis and prognosis of the accident condition, the estimates of radioactive material releases, and the prevailing meteorological conditions. This communication channel is to remain in use for this information as long as necessary.
- 4. Dedicate an individual for plant status updates to offsite authorities. This includes meteorological data, dose estimates for actual releases, and release and dose EdbA projections based on available plant condition informa#tioh and foreseeable contingencies. "
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- 5. Maintain communications with State DNR (EPD) and/or State C.O. and relate the accident diagnosis and prognosis information necessary for the State DNR (EPD) to implement their emergency plans. Recommend protective actions per HNP-4854. Refer to HNP-4861 for notificatibn messages.
NOTE Notification and communication of protective action to authorities responsible for offsite emergency. measures cannot be delegated to any-one else and must be performed by the Emergency l Director.
- 6. Confirm that call list for Site Area Emergency has been completed. Assure contact with Region II has been made within one hour after the emergency has been declared and an open line in being maintained. .
- 7. Contact company management for outside assistance. j 8.. Interpret all the radiological data obtained and update the Tech Support Center and off-site authorities with the results, in terms of both real-time measurements and, to the extent possible, projected radiological exposures. !
- 9. Account for all plant personnel and visitors from Security Force and confirm that call list has been completed.
- 10. Coordinate rescue effort when required. ,
- 11. Direct the survey of personnel reporting to the Emergency Operations Facility from the plant for co'ntamination and possible high radiation exposure.
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- 12. Dispatch external survey team to survey site security fence and other areas. Ascertain whether or not a General -
l Emergency should be declared by confirming with the T.S.C. and Control Room. ;
- 13. Dispatch G.P.C. representative to State D.N.R. and GEMA /
Emergency Operations Center.
- 14. Arrange for any further on and off-site radiological gggy evaluations that are requested. g ,
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- 15. Arrange for and dispatch any special assistance or servtce? %,
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- 16. Maintain control over personnel assembled at the Emergency Operations Facility and assess and provide for any cont.idenstions necessary for their radiation protection.
- 17. Call in assistance as required from outside agencies or groups.
- 18. Receive any responding representatives'from off-site emergency agencies and assist in their information and communications needs.
- 19. Supervise collection of emergency data in the Emergency Operations Facility Log. '
- 20. Escalate to General Emergency class (refer to HNP-4720), if appropriate ,
or closecut or reduce emergency class by briefing of State DNR (EPD) and/or GEMA followed by written summary within 8 hours of closecut or class reduction. [ - ka W > %. f,, rw --
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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT
. PROCEDURE General Fmer_qency PR5CE5URE TITL5 HNP-4720 -
PROCEDURE NUMBER. . Lab RESPONSIBLE SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( ) __-- ,.--___----__--_-__ --.,_---_--_-_______. . _ _ _ - - - _ - _ _ - - - - - _ . ._----- q APPROVED APPROVED DESCRIPTION DEPT. PLANT DATE REV. HEAD . MANAGER 1 Page 2 & 4 f 1 J *r, - -_-- . - _ - {-Q. - - - - _ 3ltl8,1---. __--.
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' GENE 866_EMgGGENCY
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GLOSS _DESGBICI1CN Events are in process or have occurred which involved actual or imminent substantia 1' core' degradation or melting with potential l 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. . 1 s B. PQRPOSE f Purpose of the general emergency declaration is to (1) initiate r, redetermined protective actions for the public, (2) provide . continuous assessment of information from licensee and offsite .
- organization measurements, (3) initiate additional measures as t indir.ated by actual or potential releases, (4) provide g consultation with offsite authorities and (5) provide updates for -
the public throush offsite authorities. { C. ELANT ACTIONS t
- 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 apd 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 joint with i
offsite authorities).
- 6. Make senior-technical and management staff onsite available for consultation with NRC and State on a periodic basis.
- 7. Provide meteorological data and dose estimates to offsite authorities for actual releases via a dedicated individual
. or automated data transmission. &J,J Provide release and dose projections based on available eko f 8.
plant condition information and foreseeable contingencies. y*3wn e f C2 h c
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- 9. Close out or reduce emergency class by briefing of offsite authorities followed by written summary within 8 hours of closeout or class reduction.
D. SIATF AND/OR l OCAL OFFRITF_MTL40RITY_ACTIOL4@ ,
- 1. Provide any assistance requested. .
- 2. Activate public notification system promptly, inform public of emergency status and provide updates periodically.
- 3. Consider sheltering for a mile radius and 5 miles downwind and assess need to extend distances. Consider advisability of evacuation (projected time available vs. estimated evacuation times).
- 4. Augment resources by activating primary respond centers.
- 5. Dispatch key emergency personnel including monitoring teams 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 l monitoring teams with regard to changes to protective actions already initiated for public and mobilizing evacuation resources.
- 9. Consider placing milk animals within lO, miles on stored feed and assess need to extend distance.
- 10. Provide press briefings, perhaps with GPC.
- 11. Maintain Deneral emergency status until closecut or reduction of emergency class.
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, TABLE 1 GENERAL EMERGENCY ; *;
INITIATING CONDITION EQUIPMENT STATUS PARAMETER VALUE
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1.a. Effluent monitors detect levels Main Stack and/or Reactor Bldg. Vent j
- ccrresponding to I rem /hr W.B. monitors ill lli alarms plus monitor or 5 rem /hr thyroid at the site reading plus dose rate projection bcundary under actual meteoro- calculations. Dose measurements off- .
logical conditions. site using portable instruments or environmental monitoring stations. 1.b. Projected dose rates as above Dose rate projections will be bas'ed P O based on other plant parameters. on the following: Containment Post. M .- LOCA Radiation monitors, analysis of drywell air sample, ARM monitors in 3 m @ su I-Reactor Building, plus possible con- D,. o firmation from effluent monitors or !E!{ C 7 lml-offsite measurements. l@jm cor y Z
- n 2.a. . Failure of cladding and contain- See Table 1-a. Reactorpressure>1325psigj@ *Q g containment with potential loss with failure of salcty jg , y of primary coolant boundary. relief valves to open. K h y 4160 volts undervoltage, g 600 volts undervoltage.
~
. a Analysis of activity in ~
. steam and coolant. Reactor water level <352.5. inches.
Failure of ECCS to a'uto or manual initiate. Indicated loss of primary containment. ; 3 ; 2 3 z8 5 h 7E 5 o $ g Dr~
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4 e ; e n= tn o i e. e m y H -4 TABLE 1 GENERAL EMERGENCY (Continued)~ ; ; INITIATINGCONDITION . EQUIPMENT STATUS PARAMETER VAtUE f 2' 2.b. Failure of cladding and primary See Table 1-b. Containment pressore >25 psig e o Containment temperature P coolant boundary with potential loss of contair. ment >300 F Analysis of activity in steam and reactor coolant to Reactor water levels 1,/64f l2 inches im Containment Post LOCA .A Monitor Readings f O .- Containment liigh Range Radia ,y @ t tion Monitor Readings A o MainSteamLineflow>120psid5!Y D,. E
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Containment atmospheric analysis d@jm y Z
- n 2)c. Failure of primary coolant See Table 1-c.
Containmentpressure>25psigl8 $ E boundary and containment with~ , containment temperature 9 ' potential loss of cladding >3000F j3 m Main Steam Line Flow >120 psid g . g
. Indicated loss of primary lh 3 containnent l9 Failure of ECCS to buto or manual initiate .
4160 volt undervoltage 600 volt undervcitage Reactor water level 1 166f l : a 7;
. inches and decreasing c
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- 3. Loss of physical control of the Observation Shif t Supervisor's judge- ~
5 nj sp'lant ment based on advice of S
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Security Shif t Supervisor 0 np o , C ,
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g TABLE 1 GENERAL EMERGENCY (Continued) : m . E:!. p;e PARAMETER VALUE E 'l EQUIPMENT STATUS -4 s INITIATING CONDITION -4
.ludgement of Shif t %- ;
- 4. Other plant conditions exist Supervisor and STA *
- from whatever source that make release of large amounts of j 2 radioactivity in a short time o e ,
P period possible (e.g., any core melt situation). Example of . sequences: ' to
- a. Transient (e.g., loss of offsite l@
power) plus failure of requisite Q core shutdown systems (e.g., p in scram). Could lead to core I C) :- jm o melt in several hours with contain-ment failure likeiy. More severe jh k g consequences if pumps trip does not ini> tmna D.c o r
- function.
- b. Small or large LOCA's with failure
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$ 5 melt degradation or melt in minutes - !@ Q
-4 to hours. Loss of containment in- y tegrity may be imminent. 5 l :s
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- c. Small or large LOCA occurs and con-j.
tainment performance is unsuccessful . affecting longer term su:: cess of the ECCS. Could lead to core degradation - or melt in several hours without con-tainment boundary. : a x; E 3 z8
- d. Shutdown occurs but requisite decay heat removal systems (e.g., RHR) or
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nonsafety systems heat removal means S. $5 O E P n are rendered unavailable. Core de- e
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grad 5 tion.or, melt could occur in about
-ten hourslwith subsequent containment C
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- 10 TABLE 1 im GENERALEMERGENCY(Continued) ($
INITIATING CONDITION EQUIPMENT STATUS '$ P
- 5. Any major internal or external events PARAMETER VALUE F G -.-
m (3 which could cause massive common 3 O [ damage to plant systems resulting -:01-4 63 in any of the above. @@ 5
, ET 7 Fires SIm ~C Z Massive damage to ECCS System
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EDUIPMENT STATUS FOR FAILURE OF CLADDING AND CONTAINMENT WITH POTENTIAL LOSSo OF EPRIM
? E r GAP ACTIVITY IN STATUS INDICATES ALL COllTAlt!MEllT pet 4ETRATIO!!S PRli%RY COOLNIT I40T VALVED OFF OR CLOSED CORE utCOVERED _ q OR R AND 7 OR n SillFT SUPERVISOR'S lP C GAP ACTIVITY IN SE N4 0 FIN 10N jm y Z' T ~
c5 o O.
' El LOSS OF AC
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[ a, LOSS OF ECCS . OR - AND l ) : a zu
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lilGil REACTOR PRESSURE 111Til 1%LFut;CT10111NG HELIEF A!;D SAFETY /
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GENERAL B4ERGENCY p .1 Lt a F /'}. & " .,
TABLE 1-b - EQUIPMilT STATUS FOR FAILURE OF CLADDING AND. PRIMARY COOLANT 800tlDARY llITH POTENTIAL g LOS ; ,
?~ $ $
e m. GAP ACTIVITY Irl _lllGH DRYWELL PRESStDE PRilWlY C00tAfiT
/ lilGH DRYiELL TEMPFJBTURE U o CORE UtE0VERED OR AND m OR l g CTIVITY IN GAP ACTIV11Y IN .lT1
_ Dir(rELL CONTAlfMENT PRESSURE O - O
/ S Gf 1 Ts s @ E' AND C0t1TAltNENT b
STt'N4 LIffE BREAK dETnEErl OR I
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- PRESSURE INCREASING iG CI 5
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CO:JTAlllittlT AND M51V ) ,[ AND \ LOSS OF OR Cot 1TAltNEllT $ t C00LillG j . ~ STtMii LillE BREAK f' D0dlSTRENi 0F - '- -
. i4SIV AND SillFT SUPERVISOR ! ~.
OPINION I" A 14SIV FAILURE N - i i j Ei ,
?E AND OR l
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CORE U11 COVERED '
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i C p.,. GAP AC'Dy ,YlIN[ / - GENERAL EMERGENCY
$1 PRI: 4ARY C ENIT -4 . __
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TABLE 1-c -l
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EQUIP!!EtiT STATUS FOR FAILURE OF PRIt1ARY C'00LANT BOUNDARY AND CONTAINMEtIT WITH POTENTIAL LOSS d Of CLADDIt 3 m
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i HIGH DRYWELL PRESSURE STATUS IrlDICATES P ALL C0tlTAllicitT C -- ! PEr!ETRATiorG IDT VALVED OFF OR N HIGH DRYWELL TEMPERATURE g 7 , CLOSED I OR n AND I OR iy Q,9. El o I ig Z i SillFT SUPERVISOR'S t-OPillioll
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E STEAM LINE DREAK D0iff-l OR AND NEAM OF MR!V ~' l s' MSIV MALFUtlCTION SCSFAILURE .
, g hg OR u AND l STEAM LilE BREAK BETWEEN b i
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- LO3S OF AC POWER m.m GENERAL EIERGENCY o 5
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' GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PROCEDURE.
Actions for All Personnel -- in General EmerDencien----- PROCEDURE TITLE--------
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HNP-4721 PR6CEDURE NUMBER - Lab ~ RESPONSIBLE SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( )
------ .------------------- u APPROVED APPROVED REV. DESCRIPTION DEPT. PLANT DATE HEAD MANAGER 2 Pages 1, 2&3 Deletions on Pages 1 and 3, Delete Fig. 1 d eA$ 3fif82 I
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_Sae Ti+1= h ge 1 of 3 AC_IlONS_FOR ALL PERSONNFL IN_GFLTRAL_Er_1ERGENGIES NQIE This procedure supercedes HNP-4700, Revision 6.'ated d 9-5-79. A. C_QNOITION 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. BEEERENCE HNP-4720. . C. ACTION
- 1. Persons discovering an emergency condition shall immediately notify the Control Room by the most expeditious means avail-able.
- 2. Control Room operatoi , shall announce the nature of the l emergency on the public address system and specify that personnel initiate general emergency procedures.
Control Room operators shall place the plant in a safe con- ! 3. dition as the emergency warrants.
- 4. If possible, person (s) in immediate area take appropriate, rapid action to limit the extent of the incident with avail-able means, and then retreat to the rally point.
- 5. Persons involved in the incident report to Health Physics at the Emergency Operations Facility as soon as possible after decontamination for further evaluation of dose received.
- 6. Persons called in from offsite should report to the Emer-gency Operations Facility unless specifically directed otherwise.
- 7. (EOF) Eha ,
Staffing of the Emergency begin immediately. Operations FacilityThe normal EOF is r: the Visitors l the alternate EOF is the Appling County Sheriff's Office in the courthouse. , i
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,. Seo Title Paga um'o= ~o om Georgia Power A .m ~o Ann Title Page. ,
2 of 3
- 8. If the emergency occurs during a regular day shift, members of the plant operating organization on site will report as follows:
- a. Control Room Operations Supervisors, all on shift dperators, Shift Foremen, Shif t Supervisor and Shif t* Technical Advisor
- b. Emergency Operations Facility (EOF) t The following persons will report to the EOF after checking through the Rally Point: Assistant Manager, Health Physics Superintendent, Administrative Superintendent, RET members, 4 communicators. Three RET members will be dispatched immediately by the OSC Manager. -
- c. Techni. cal Support Center (TSC) ,
The following persons will report directly to the TSC follewing notification of a General Emergency. I Assistant Manager, Superintendent of Engineering Ser-vices, Superintendent of Maintenance, Superintendent of Operations, Reactor Engineer, Engineering Supervisors, Laboratory Supervisor (Health Physics).
- d. Operations Support Center (OSC)
The following persons will report directly to the OSC following notification of a General Emergency. ' 1 Shift Supervisor or Foreman, 1 Maintenance Supervisor, 1/2 crew instrument tech- nicans w/ foreman (pre-designated), 1/2 crew electri- cians w/ foreman (pre-designated), 1/2 crew mechanics w/ foreman (pre-designated), all R.E.T. members and four laborers l with foreman (pre-designated).
- 9. All personnel who have not been assigned to the control room, TSC, OSC or EOF will evacuate the site per step 12 or 13.
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- 10. Members of the plant organization will comply with appli 3 cable procedures to effect orderly coordinated actions i n'. ,
the emergency.
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- 11. Members of the Radiological Emergens.y Team (RET) report to '""
the OGC immediately if on site when the emergency begins. , cci , If team members are called in, they will report to the OSC. ,p e t for assignment.
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MANUAL SET
yo- E. I. Hatch Nuclear Plant ra==ae *o
. HNP- 4721 See Title Paga ""So* *o 2
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- 12. Fvacugtion_grocedure for_gersonnel inside the Primary Protected Area.
- a. Proceed to the area just inside the fence at the exit designated by the announcement over the Public Address system.
- b. Proceed to drop off all identification badges at the Security post and continue to the Environmental Building or the Skills Training Building as directed by the Control Room. All personnel that were involved in the accidnet or are wearing PC's will not leave the protected area.
- c. Frisking and decontamination will take place at either of these locations as directed by the TSC Manager.
Once this is completed the RET will direct personnel to leave the plant site.
- d. Personnel should leave the site vicinity in personal vehicles using US 1. Direction of travel (north, south, either direction) will be announced by the Control Room and will be based on wind direction.
- e. If required, company vehicles will be used to supplement transportation needs.
- 13. Evacuation _grocedure for personnel outside the grima_ry
, grotected area:
- a. Proceed to rally point indicated by Control Room personnel over the Public Address System.
NOTE If the rally point must be moved because of high back-ground radiation follow instructions of the RET member.
- b. Get checked for contamination by GPC Radiological Emer-gency Team personnel.
- c. If contaminated, go to area designated by surveyor and await decontamination.
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- d. Personnel in section C.B.b report to the EOF. (g3 "S:' n,
- e. Personnel will leave the site vicinity using U.S. 'l.7 c""
Direction of travel (north, south, or either) will be 3c,J announced by the control room and will be based on wi'ndyp direction. 2
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. , L' 0 MANUAL SET
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a i, GEORGIA POWER COMPANY .! I i HATCH NUCLEAR PLANT - PROCEDURE , General Emergency - Control Room Ogerators
~~~ PROCEDURE TITLE !
- . H.N_ P - 4 7 2 2_
PROCEDURE NUMBER .
~ ~
Lab RESPONSIBLE SECTION . SAFETY RELATED ( X) NON-SAFETY RELATED ( ) i
._____p____________________- '
_____PPROVED A APPROVED REV. DESCRIPTION DEPT. PLANT DATE , HEAD . MANAGER !
._____+ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . ______ ________ ._______
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L.. _ a f . MANUAL SET
a amw E. I. Hatch Nuclear Plant aaoctouae ~o HNP- 4722
'Smo Title Pago ""' S' "
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Georgia Power n .. . o Cet Ti t4 r age . 1 M P _. GENERAL EMERGFNCY - CONTROL ROOM OPFRATORS NOTE This procedure supercedes HNP-4701 Rev. 4 dated 5-13-78. A. COrjDITION 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. D. REFERENCE I i HNP-4720. . C. ACTION
}
- 1. Take appropriate action to place the plant in a safe condition in accordance with operating emergency procedures, -
Tech. Specs., and annunciator response procedures. ;
- 2. Check wind direction and speed on panel H11-PG58 to determine location of emergency operation facility (EOF).
t WINDJIRECTION USE f
. All wind directions except 22 -122 Normal EOF i 22 - 112 Alternate EOF Calm Normal EOF ,
- 3. Determine evacuation route - base on wind direction as follows:
i WIND DIRECTION ROUTE 315 -90 North on U.S. 1 g,pg 91 -225 South on U.S. 1 g
, 226 -314 Either direction on U.S.fis, f j%
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- 4. Make the following announcement over the PA:
ATTENTION, ATTENTION: A GENERAL EMERGENCY E.XISTS. , REPORT TO THE RALLY INITIATE GENERAL EMERGENCY PROCEDURES. POINT LOCATED AT (FNVIRONL4 ENTAL /SKItLS TRAINING _BUIt. DING) BEFORE LEAVING SITE. EVACUATION ROUTE WILL BE (NORTH / SOUTH /EITHER DIRECTION) ON US. 1 HIGHWAY. (NORMAL / ALTERNATE) E.O.F. WILL BE ESTABLISHEO. , Sound the general emerger.cy tone on the gai-tronics system. Then repeat announcement. S. Notify Security Force as to the location of the Emergency Operations Facility. ! If Shift Foreman has not reported in to the control room,
- 5. '
initiate his actions per HNP-4723. 4 5
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, GEORGIA POWER COMPANY ,
1 HATCH NUCLEAR PLANT PROCEDURE GENERAL FMERGFNCY - SHIFT FOREMAN
~~~~~~~~~ -----
PR5cE50RE TITLE HNP-47P3 PROCEDURE NUMBER LAR - RESPONSIBLE SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( )
------~----------_---------------------------..-----------------.-------.
APPROVED APPROVED - REV. DESCRIPTION DEPT. PLANT DATE HEAD MANAGER s---------------.---_---- 2 Page 1 s' - - -. .
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MANUAL SET
ama E. l. Hatch Nucl:ar Plant moa=6 ~o i HNP 4723 g
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tem.o~ ~o Georgia PowerQn a po. ... @Q l See Title Page 1 of 1 l l GEllERAL FMERGENCY - SHIFT FOREMAN i i NOTE ; This procedure supercedes HNP-4702, Revision 4 dated 5-13-78. A, QQLJQITION - 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. REFERFNCE HNP-4720 HNP-4850 - HNP-4851 C. ACTION
- 1. Proceed to control room immediately.
- 2. Ensure that correct operator action has been taken to bring emergency under control.
- 3. Estimate extent of off site activity conditions using procedures HNP-4850 and 4851.
- 4. Assure call list for General Emergency has been initiated. I
- 5. Activate Internal Survey Team by contacting Operations Support Center Manager when staffed. Direct Internal Survey l Teams to areas to be surveyed as appropriate.
- 6. Activate Rescue Team as necessary by contacting Operations l Support Center Manager when staffed.
- 7. Establish communications with the Security Force, Technical Support Center and the Emergency Director as soon as l possible and discuss the need for outside assistance. LJM
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- 8. Direct on site actions to bring emergency under c
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MANUAL SET
, . r GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PROCEDURE' C_.ENERAL EMERGENCY - FXTERNAl. SURVEY TFAM HNP-4725 ~ ~
PROCEDORE NUMBER LAR RESPONSIBLE SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( ) APPROVED APPROVED REV. DESCRIPTION DEPT. PLANT DATE HEAD MANAGER _ _ _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ - _ _ . _____ _ _ _ _ _ - _ - . a___--__ _ _ _ _ _ _ _ .. -_____. 3 Pages 1, 2&3 M. _ _/ _ _ _f g J[t[g).
. . _ - _ _ _ . _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ . _ w _. ________. ._______.
u________________. . _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ . .________ ______ ___-________________ r________________. ______ ____________________ 7________________. _ _ _ _ _ _ ..________--__________ r_______________.
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. - -9
'I MANUAL SET
"~~ c E. I. Hatch Nuclaar Plant -oct = <~o HNP. 4725 Sse. Title Pcga temio o See Title Page Georgia Power A -.o 1 of 7 k
GENERAL EMERGENCY - EXTERNAL SURVEY TEAM NOTE This procedure supercedes HNP-4704 Rev. 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 for loss of containment integrity. Release can be reasonably expected to exceed PAG exposure levels offsite for more than the immediate site area. B. REEER_EK E HNP-4720. . C. ACTION NOTE This action to be taken by the Health Physics Supervisor or designated alternate and technicians whenever possible or by other trained personnel.
- 1. Obtain a survey team kit at the Emergency Operations Facility.
- 2. Turn on survey instruments, allow them to warm up, and check response with source provided. .
- 3. Install glass fiber filter and charcoal (or silver zeolite, if directed) filter in sample holder of air sampler. Turn on sampler and confirm proper operation. Turn off.
- 4. Acquire transportation and stand by for instructions from Dose Assessment Manager. f
! S. Proceed to area specified by Dose Assessment Manager. l
- 6. While in transit, take continuous background readings with i survey. W V
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MANUAL SET
maom E. l. Hatch Nuclear Plant **awas ao HNP 4725
'S2o Title Pcg2 - atv+o= ~o e -
3 om Georgia Power h a.- ~o 2 Of 7 See Title Page
- a. Indicate observed readings on survey map.
- b. If dose rate in excess of 5 mr/hr is indicated, report reading to E.O.F.
- 7. Take air sample at designated area as follo'ws:
t
- a. Place charcoal (or silver zeolite, if directed) and '
glass fiber filters in air sample holder (fiber filter outside). ;
- b. Start air sampler and record time on Data Package 1 :
(Data Sheet 1). t
- c. Check air flow indication and record flow rate.
I
- d. Run air sampler 10 minutes, observing flow rate during the sample period. .
- e. Make radiation survey as in Step C.8 while running air sampler.
NOTE If levels are greater than 10 mr/hr (approximately 40,000 CPM) report reading to E.O.F. Discontinue sampling and move on to the next location specified by Dose Assessment Manager. Remove filters, place in l envelope and record total sample time and flow rate.
- f. Remove filters. ,
- g. Insert G.M. survey meter probe (HP-210) into sample holder (SH-4A) and record background reading.
- h. Place glass fiber filter in SH-4A holder and obtain reading (CPM). Calculate airborne concentration per Data Package 1 (Data Sheet 1).
- i. Place charcoal or silver zeolite cartridge in plastic and put directly against probe (HP-210). Obtain reading (cpm) and calculate airborne concentration per Data Package 1 Data Sheet 1.
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, J. Place sample filters in envelopes and record on (e3 envelopes time, location, flow, sample time, CPM, ,j n background, and air activity. Hold for further c 3 n, analysis at plant E.O.F. !
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~~ovd E. l. Hatch Nuclear Picnt
== = = ~o HNP. 4725
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Sao' Title Paga uvision ~o o... Georgia Power A ..mo See Title Page 3 of 7
- 8. Take count / dose rate survey as follows:
- a. At waist level, hold G.M. probe on G.M. survey meter with the detector window facing horizontal, read meter and record results in CPM.
- b. Repeat above, but with detector window facing the ground.
- c. At 2" above the ground, hold G.M. probe with the detector window facing the ground, read meter and record results.
- d. At waist level, hold high range survey meter horizontal, read and record dose rate in mr/hr. -
- e. Repeat Step C.B.c above but at 2" from ground.
- 9. Collect soil, vegetation and water samples as follows:
~
- a. Take bag marked soil and small scoop, fill with surface '
. soil from a bare spot, tape closed, and tag with the date, time, and location.
- b. Take bag marked vegetation and scissors. Cut vegetation approximately two (2) inches above ground, fill bag, tape closed, and tag with the date, time and location.
- c. Fill poly bottle with surface water, close and tag with date, time and location.
- 10. Report all results to E.O.F. and await further instructions.
- 11. When directed by the Dose Assessment Manager, proceed to TLD l and air sample cabinet locations. Change out TLD and filters at the stations noting time and date of change out.
Return samples to E.O.F. I-A,4
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"a"'
E. l. Hatch Nucl cr Plant mxiou. ~o , S m Title Pega HNP.4725
' i EYlS80N NO p
o"' . Georgia Power d .. . O See Title Page 6 of 7 a PROCEDURE DATA PACMACF. , i DOCUMENT PO:.Jff_ DIE 5d , i' CERIAL NO: RO]- ffL NO: RTYPC:JhQ3 XREF: , TOTAL I4EETS: 2 FRCOLENCY: C0ffLETED BY: { DATC COMPLETED: }
! DW/C REV!rWED THIS DATA PACHACE FOR COMPLETCPERS j AND ACAlt6T ACCF.PTNaCE C7ITCRI A IN ACCOROMrE WITH HNP-830.
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I - Georgia Power A .am ~o f See Title Page 7 of 7 t DeIA.EeCEeGC.1 * (DATA utET 1) { UEEd11E_Et%BGEKY.tTJJIITIM.IEeM QeTA f*CCI - I DATE: } TIME: TEAM # t i SAPPLE LOCATION: SAMPLE TIME fN: f FLOW RATE: OFF: } FM)W RATE: LPM f GST2_elEETZ_e 11Y11Y (class freer FILTER) (SAPPLE t BACK CROlJO CPM) CPM (BACK CRCtM) CPM) CPM (SNfLE t BACK CROLFO CPM) - (CACK CROUr0 CPM) = CORRECTED CPM f FROM F1CLEC 1 PARTICLLATE AIRDORPE COr4CEt4TRATION uc/cc 1 r AISBe g _s Ily111 (CHARCOAL FILTrR) , (CAtFLC t DACM CROtto CPM) CPM (BACK CROtto CPM) CPM (SAMPLE t BACM CROtta CPM) - (DACM CROtto CPM) = CORRECTED CPM FROM FIGURE 2 1 AIRBORtf CONCENTRATION ut/CC GQWIlW RATg,ftJJy[y:
. CO t4T/OOCE RATE WHILE IN TRAtSIT CPM mr/hr Cftt4T RATE - WAIST LE%EL (WIPOOW FACING FORI2ONT/L) CPM COLT 4T RATE WA!GT LE%EL (WIPOOW FACING CROUr0 CPM Ca t4T RATE - 2* FRCN GROuro (WirOOW FACit#. CROUND) CPM OOCE RATC - WAIST LE%EL (Str1%EY METER HORI2ONTAL) mr/hr DOFE RATE - 2* FROM CRours trut%EY METER HORIZONTAL) mr/hr e
Page 2 of 2 ter-4725 R03 *) )
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