ML20041G010

Public Version of Revised Emergency Procedures,Including Procedures HNP-4726 Re General Emergency for Rally Point Leader & HNP-4728 Re General Emergency for Rescue Team

ML20041G010
Person / Time
Site:	Hatch
Issue date:	03/01/1982
From:	Rogers W GEORGIA POWER CO.
To:
Shared Package
ML20041G008	List: ML20041G010
References
PROC-820301-06, NUDOCS 8203190017
Download: ML20041G010 (25)

Text

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GEORGIA POWER COMPAN HATCH NUCLEAR PLANT PROCEDURE General Emergency - Rally Point Leader ~

~~3R5CEDURE TITLE HNP- 4726 PROCE6URE NONeER- .

Lab RESPONSIBLE SECTION NON-SAFETY RELATED ( )

SAFETY RELATED ( X )

APPROVED APPROVED DEPT. PLANT DATE REV. DESCRIPTION HEAD . MANAGER

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r203190017 a20312 PDR ADOCK 05000321 F PDR MANUAL SET

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See Title Page, CENERAL_EMFRGFNCY - RALLY POINT LEADFR NOTE This procedure supercedes HNP-4705, Rev. 5 dated 1-2-83.

A. GONDITION 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.

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B. REFERFNCE ,

HNP-4720.

C. ACTION

1. After the RET assembles in the OSC, the OSC manager will send some RET members to the rally point and designate a Rally Point Leader to take charge of the rally point.

2. Have personnel gather at the rally point. If personnel involved in the incident are present or anyone is dressed in protective clothing segregate them from the others.

3. Check with the Security Force, general contractors, and Georgia Power Construction Department to determine those persons remaining in the plant. If any person (s) is (are) unaccounted for, report this to the Shift Foreman. If the Shift Foreman cannot account for the mi.ssing person (s), form a rescue team (s) and initiate HNP- 4728, GENERAL EMERGENCY -

RESCUE TEAM.

4. Take survey meters and determine habitability of the rally point, and proceed as follows:

a. Dose rate less than O.5 mr/hr or contamination less than 100 CPM above normal background.

(1) Survey or have RET members survey persons involved in the incident first, those wearing protectivo clothing second, and then the remaining personnel at the Rally Point.

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(2) Have any person that is contaminated (greater than 100 CPM above cally point background) remain at the rally point, separated from the others, and notify the Health Physi cs Supervisor. Release uncontaminated personnel to proc,eed off site.

(3) Begin decontamination and expondre evaluation of affected personnel as quickly as possible.

a. Set up change station.

b. Supervise self-decontamination of personnel.

c. Using available information estimate each persons expo'sure and record data.

d. Take TLD badges off persons involved in the incident. Arrange for reading of the TLD badges.

e. Arrange for urine samples and nasal smears from persons involved in the incident to be taken. Evaluate then as time permits.

f. Do not release any person who has received greater than 25 rem whole body dose or is suspected to have ingested significant amounts of racioactive materials. Such persons are to be taken to the hospital for examination and further evaluation of exposure.

g. Confer with the Emergenc.y Director before l releasing any personnel involved in the incident.

b. Dose rate greater than or equal to 0.5 mr/hr or contamination greater than or equal to 100 CPM above background.

(1) Proceed with every one to an area outside of protected area where dose rate less than O.5 mr/hr or contamination less than 100 CPM.

(2) Conduct or assist RET members in conducting individual surveys.

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' ' unsion e im Georgia Power d .. e See Title Page 3 of 3 (3) Any person that is contaminated (greater than 100 CPM above background) have him remain for decontamination and notify the Health Physics Supervisor. Assist the H.P. Supervisor, when time permits, in performing step C.4.a.(3).

(4) Releasa uncontaminated personnei to proceed off site.

5. Report status of the evacuation to the Emergency Operations Facility.

6. Do not release members of the Radiological Emergency Team, except to go to the EOF, directed to do so by the Emergency Director or Shift Foreman if the Emergency ]

Director cannot be contacted. -

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7. Assist in routing ambulance to pick up any injured persohnel. Assure ambulance driver and attendant are provided with TLD badge and pocket dosimeter on entry.

8. Assist Emergency Director in bringing emergency under l control.

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. 3 e , GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PROCEDURE General Fmergency - Rescue Team

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-Gee-T-i-t4e P-age- 1 of 3 GENERAt,FMERGFNCY - RESCUF TEAL 4 UOIE This procedure supercedes HNP-4707 Rev. 3 dated 5-13-78.

A. CgNOITION 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 cite area. ,

D. REFERENCE ,

HNP-4720. .

C. ACTION

1. Form Rescue Team:

a. OSC Manager designated a member of the Radiological Emergency Team to be rescue Team Captain.

b. Radiological Fmergency Team members are assigned to complete Rescue Team as follows:

Survey Man Stretcher Bearer #1 Stretcher Bearer #2 Stretcher Bearer #3 4

c. Rescue Team Captain leads Team in the rescue effort.

2. Dress out in Protective clothing located in the assembly room (Service Building), if time permits.

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Respirator (self-contained)

High Range Pencil Dosimeter ,

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3. Survey Man carri.es GM survey meter and. ">igh range survey meter Team Captain carriers walkie-talkie and remains in contact with Emergency Operations Facility and/or Shift Foreman.

4. Determine probable location of victim from OSC Manager. l S. Proceed with rescue. .

a. Stretcher bearer's carry: ,

Stretcher .

Rope and tackle, if required for rescue Pinch bar, if required for rescue First Aid Kit

b. Start using respirator while approaching building.

c. Retreat if dosimeter reaches 2 R and victim has not teen located.

d. Limit dose to members of Reacue Team to 25 rem whole body in effecting rescue.

e. Perform necessary first aid measures for victim but move rapidly when dose rates are high. Move victim into Medical Room and decontcminate if possible,

f. Inform Control Room of condition of victim. Assure that Shift Foreman has notified hospital that the victim is or is not contaminated.

g. Contact Emergency Operations Facility or Control Room by rad.o or phone and arrange for ambulance pickup of victim in the upwind direction of victim's location.

h. Move victim to ambulance. 4 /

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i. Arrange for a radiation technician to accompany victim to hospital in ambulance.

j. Notify a laboratory supervisor as soon as possible.

6. Take necessary measures to limit spread of contamination and report to the OSC Manager when rescue effort is completed.

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H_NP- 4729 PROCEDURE NUMBER .

Lab RESPONSIDLE SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( )

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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 off site for more than the immediate site area. ,

D. REFERFNCE HNP-4720.

C. ACTION

1. Report to the Operations Support Center, carrying as many l survey instruments, friskers, air samplers as you can.

NOTE It is extremely important that you move as expediciously as possible.

2. The Operations Support Center Manager will choose a Rally l Point Leader.

3. The remaining members of the Radiological Emergency Team will, by assignment of the OSC Manager: l

a. Assist the Rally Point-Leader in performing Rally Point or Personnel Surveys,

b. Serve as Rescue Team Leaders.

c. Serve as Internal or External Survey Team Leaders.

d. Standby to give other assistance as directed.

. 4. Members of Radiological Team come from Plant Hatch, Plant Vogtle, and Corporate Health Physics and Technical Pers 1.

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. PROCEDURE' General Fme_ri1en_c1 - Sh i f t 'SuRe rvi so r PROCEDURE TITLE HNP-4730 ~

PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( )

APPROVED APPROVED DESCRIPTION DEPT. PLANT DATE REV.

HEAD MANAGER

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1 nf i GENERAL FMFRGENCY - SHIFT St IPERVISOR i A. CONDITION Events are in process or have occurred which involve actual or >

imminent substantial core degradation or mel. ting 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 HNP-4720. .

I HNP-4740. -

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C. ACTION .

1. Procede to control room.

2,. Take control of all activities in the control room, ensuring that proper coordination of all activities is carried out.

3. 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.

4. Evaluate. actions of Shift Foreman and operate to bring emergency under control.

5. The Shift 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. l

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 his determination of'close out or reduction of the emerge 4 class. #

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PROCEDURE General Emer_qnncy__- Visitor's Center Director PROCEDURE TITLE

_HNP-4733 PROCEDURE NUMBER' .

Lab RESPONSIBLE SECTION NON-SAFETY RELATED ( )

SAFETY RELATED ( X )

APPROVED APPROVED DEPT. PLANT DATE REV. DESCRIPTION HEAD . MANAGER 2 Page 2 **

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1 of 2 GENERAL _ EMERGENCY - VISITOR'S CENTER DIRECTOR NOTE This procedure supercedes HNP-4716 Rev. 3 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 reaconably expected to exceed PAG exposure levels offsite for more than the immediate site area. .

B. REFERENCE -

HNP-4720. .

C. ACTION

1. When notified, stop exhibits and have all personnel and visitors report to the reception area.

2. Obtain the high range surey 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 the background is 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 plant site in the upwind direction. Take Visitor's Log, high range survey meter, and GM survey meter with you.

5. Halt caravan in a suitable location where dose rate is approximately background. (Less than 200 cpm).

a. Survey persons' hands and feet for contamination if not already done. If contaminated (Greater than 100 CPM above background) segregate for transportation to Emergency Operations Facility.

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6. Obtain vehicle lecense numbers and. names.of persons before releasing. Release persons and vehicles that are not contaminated greater than 100 CPM above background.

NOTE ,

In order to assure that license numbers and names of visitors released from the 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 to assist in this job.

7. Contact Emergency Operation.s Facility for instructions on decontamination of persons and vehicles and obtain necessary assistance. This will normally be done at the Emergency Operations Facility.

8. Report status of evacuation to Emergbncy Director by use of nearest available telephone.

9 Report to Emergency Operations Facility if requested to do so by the Emergency Director.

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' GENERAL EMERGFNCY - EMERGENCY DIRECTOR NOTE This procedure supercedes HNP-4710 Rev. 4.

A. CONDITION ,'

Events are in process or have occured 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 .

HNP-4720 C. ACTION

1. The Plant Manager, or his designee, will assume the position of Emergency Director as soon as he can establish himself in a contrel 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 will generally operate from the EOF. Assign personnel as 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.

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 i prevailing meteorological conditions. This communication l channel is to remain in use for this information as long as l necessary.

, 4. Dedicate an individual for plant status updates to offsite l authorities. This includes meteorological data, dose

! estimates for actual releases, and release and dose l projections based on available plant condition information and foreseeable contingencies.

! 5. Maintain communications with State Radiation Emergency l Coordinator (REC) and/or GEMA and relate the accident diagnosis and prognosis information necessary for the State l, REC to implement their emergency plans. Recommend

protective actions per HNP-4854. Refer to HNP-4851)f<ifj fon

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__Sao Ti+1a Pagn 2 of 3 NOTE Notification and communication of protective action to authorities responsible for emergency measures cannot be delegated to anyone else and must be performed by the Emergenpy Director. .

G. Confirm that call list for' General Emergency has been completed. Assure contact with Region II has been made within one hour after emergency has been declared and an open line is being maintained.

7. Contact company management for outside assistance.

8. Interpret all the radiological data obtained and update the Technical Support Center and off-site authorities with the l 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 eff. ort when required.

11. Direct the survey of personnel reporting to the Emergency Operations Facility from the plant for contamination and possible high radiation exposure.

12. Dispatch external survey team to survey site security fence and other areas downwind.

13. Dispatch GPC representative to State DNR and GEMA Emergency Operations Center.

14. Arrange for any further on and off-site radiological evaluations that are requested.

15. Arrange for and dispatch any special assistance or service requested (e.g. radiological measurement or protection equipment, on-site emergency medical treatment, etc.).

16. Maintain control over personnel assembled at the Emergency Operations Facility and assess and provide for any considerations necessary for their radiation pro tection.

17. Call in assistance as required from outside agencies or groups. 's \(,

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18. Receive any responding representatives from off-site emergency agencies and assist in their information and communications needs.

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19. Supervise collection of emergency data in the Emergency Opurations Facility Log. .

20. Closcout or reduce emergency class by ' briefing of State REC and/or GEMA followed by written summary within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of closecut or class reduction.

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1 of 4 EMRGFNCy_ EXPOSURE _GUIDELIEgg A. EUfjPOSj To outline guidance on acceptable personnel exposures for emergency response personnel. ,

D. REFERENCE Emergency Plan Section K.

C. ACTION .

In performing emergency actions,.the Emergency Director can permit exposures in excess of 10 CFR 20 limits, but every The reasonable effort is maintained to keep exposures ALARA. .

accepted levels of exposure in rem for various emergency conditions is shown in Table 1. Exposure of emergency workers to any level is justified only if it is dete*rmined that benefits to society are being achieved and efforts are being made to keep exposures ALARA. Emergency workers should not include women who

.could potentially be pregnant. Since the health risk associated with dose limits recommended for lifesaving missions are extremely high, the high doses should be received only on a voluntary basis by individuals aware of risks involved.

The Emergency Director will immediately evaluate the risks l

involved versus the benefits to be gained and establish the exposure limit for the emergency response personnel. In as much as possible, the Health Physics supervision will be consulted and will participate in the decision making process.

Health Physics will be contacted immediately;for proper survey instrumentation and dosimetry. Guidance for exposure limit decision making is found in Attachment 1 of this procedure.

Persons who may be involved in establishing these emergency exposure limits will be thoroughly familiar with this guidance at all times in order that expeditious decision making and a reasonable consideration of relative risks may be achieved.

All emergency exposures greater than 10 CFR 20 limits will be thoroughly documented using Figure 2, of HNP-8005 and Form 2 of HNP-8002. .

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IXEg_OF_ EMERGE,'CY RESPONSg ,

UQti-LIEg_SAOING LIFF SAVING Removal of injured persons-Whole Body 25 75 Thyroid 125 NL Undertaking corrective actions .

Wnole Body 12 25 '

Thyroid 60 125 Performing assessment actions-Whole Body 3 6 Thyroid 30 30 Providing first aid-Whole Body 3 75 Thyroid 30 NL Providing ambulance service-Whole Body 3 3 Providing medical treatment services.

Whole Body 3 3 Providing personnel decon-tamination-Whole Body 3 NA Recovery of deceased victims # *

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• HNP.4812

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3 of 4 oII6CH Q T 1 GUIDANCE FOR EMERGENCY EXPOSURE DURING .

. RESCUE AND RECOVERY ACTIVITIES .

A. PURPOSE C. EMERGENCY SITUATIONS ,

I De emergency action guidance promulgated in Specific dose criteria and judgment factors are set this part provides instructions and background in. forth for the three estegcries of risk-benefit con. -

formation for use in determining appropriate actions siderations, i.e., actions involving the sasing of human concerning the rescue and recovery of persons and life, the recovery of decessed victims, and the the protection of health and property during periods protection of health and property.

1 ofemergency. ,

1.'Saving of Human Life j B. GENERAL CONSIDERATIONS s. Attempts to rescue victims of a nuclear inci-dent should be regarded in the same context as any I.De problem of controlling exposure to radis- other emergency action involving the rescue of tion during rescue and recovery actions is extremely victims,regardless of the type of hazard involved.

i complex. Performing rescue and recovery operations b.%here there is reasonable expectation that an requires the exercise of prompt judgment to take into individual is alive within the affected area, the course eccount multiple hazards and alternate methods of of action to be pursued should be determined by the accomplishment. Sound judgment and flexibility of person onsite having the emergency action responsi-

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action are crucial to the success of any type of bility.

emergency actions. Although the guiding principle is c. Ihr amount of exposure for this type of 1 to minimize the risk of injury to those persons emerEency action shall be determined by the person <

involved in the rescue and recovery activities, the ensite having the emergency action responsibility. He control of radiation exposures should be consistent should immediately evaluate the situation and estab ,

with the immediate objective of saving human life, lish the _ exposure limit for the rescue mission ac-the recosery of a deceased victim, and/or the pro- cordingly. lfis judgment should be based upon:

tecting of health and saving of property. (1) Evaluation of the inherent risks by con-2.To preclude the possibility of unnecessarily sidering:

restricting action that may be necessary to save lives. (a)De reliability of the prediction of radia.

these instructions do not establish a rigid upper limit tion injury. His reliability cannot be a'ny greater of exposure but rather lease judgment up to persons than reliability of the estimation of the dose.

In chstge of emergency operations to determine the Therefore consideration should be given to limits -

amount of exposure that should be permitted to of error associated with the specific instruments perform the emergency mission. and techniques used to estimate the dose rate.

3.De officist in charge must carefully examine Dis,is especially crucial when the estimated dose any proposed action involung further radistion ex. approximates 100 rems or more. .g -

posure by weighing the risks of radiation insults. (b)he exposure expected in performing th V actual or potential, against the benefits to be gained. action shall be weighed in terms of the effects Fyposure probability.bmlopcal consequences related acute external wholebody exposure and to dose, and the number of people involved are the radioactive materialinto the body, essential elements to be evaluated in making : risk (2) Current assessment of the degree and na w %'

determination. of the hazard, and' the capability of red / CAf

4. R ese instructions recognize that accident inherent risk from that hazard through appro Mose,-

situations involving the sa$ing of lises will require mechanism such as the use of protective equi ,

separate criteria frora those of acrbns required to remnte manipulat;on equipment, or simi!Jr .

y recover deceased victims or to save property. In the d. In the course of making a decision to perform latter instances, the amount of exposure expected to the action, the risk to rescue personnel should he

, be received by persons should be controlled as much weiF hed against the probabihty of success of the as possibfe within occupational hmits. rescue action. ,

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La E. l. Hatch Nuclear Plant = = == ~o

• HNP- 4812 See Title Page " " * *

- Georgia Power o ~ ~o J on Titto Pnggt 4 Of- 4 ATTACHtgNL1_1CONTINt !EDl

< e. Any rescue action that may involve, substantial individual participating in the recovery should not personal risk should be performed by volunteers.and exceed 12 rem total for the year or 5 (N.18),

each emergency worker shall be advised of the known whicheveris the more limiting.

or estimated extent of such risk prior to participa. .

tion,

,3. Protection of ifcalth'and Property

2. Recovery of Deceased Victims a.Where the risk (probability and rnsgnitude) of the radiation hazard either bears significantly on the

a. Accident situations involving recovery of de. state of health of people or may result in loss of ceased victims require criteria separate from those for property, so that immediate remedial action is re.

saving lives. Since the element of time is nn longer a quired, the following criteria should apply:

critical factor, the recovery of deceased victims (I)% hen the person in charge of emergency should be well planned. The amount of radiation a'etion onsite deems it essential to reduce a hazard exposure received by persons in recovery operations potential to acceptable level > or .to pcvent a shall be controlled within existing occupations! ex.

substantial loss of property, a pisnned exposure _up posure guides. _

to, but not to exceed,12 rem for the year may be

b. In those situations where the bodies are located received by indi*viduals participating in the opera.

In areas inaccessible because of high direct radiation tion.

• fields, and where the recovery mission would result in .

However, the person in charge of emergency exposure in excess of occupational exposure stan. action at the incident scene may ciect, under special dards contained in this appendix, specist remote circumstances, to waive these limits and permit recovery devices should be used to retrieve the volunteers to receive an exposure up to,but not to bodies. exceed,25 rem. -

c. in special circumstances where it is impossible (2)Where the potential risk ofradiation hazard to recover bodiis without the entry of emergency fo!!owing the nuc! car incident is such that life workers into the area, the individual in chstge of the would be injeopardy.or that there would be severe recovery mission may determine it necessary to effects on health of the public or loss of property

. exceed the occupational exposure standards con. inimicable to the public safety, the criteria for ~

tained in this appendix. The plann:d exposures of an - saving of human life shall apply.

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