ML20077Q115
| ML20077Q115 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 08/17/1983 |
| From: | Clint Jones, Nix H, Rogers W GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20077Q107 | List: |
| References | |
| PROC-830817-01, NUDOCS 8309150363 | |
| Download: ML20077Q115 (90) | |
Text
{{#Wiki_filter:. GECRGIA POWF.R COMPANY HATCH NL' CLEAR PLANT
.o c, ~n-e,UR a e Off Site Dose Estimations PRCCEDURE TITLE HNP-4852 '
PROCEDURE NUMBER I Health Phy,_ sics RESPONSIBLE SECTION SAFETY RELATED ( X) NON-SAFETY RELATED ( ) , i 1
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APPROVED APPROVED RCV. CEEORIPTION DEPT. PLANT DATE t i, RC.AD MANAGER
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4 f See Title Page 1 of 40 CIF SITE DCSIE ESTIMATIONS . NOTE This procedure supercedes HIP-4650 Revision 2. A. PlJRPOjj;t3 To. describe methods which may be used for estimating off site radiation dose during emergency conditions at Plant Hatch. B. PCFEPENCE
- 1. Ebnuel o f Protective Action Guides and Protective Actions
;cr Nuclear Incidents. E.P.A.
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- 5, Workbook of Atmospheric Dispersion Estimates, E.P.A.
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This procedure details methods which may be used in the event of an emergency situation to evaluate radiological conditions in the environment in order to assist plant personnel and responsible agencies (S tate Dopt. of Natural Resources, GEMA, etc.) in making j appropriate decisions to evaluate and control the hazard to , . public heal th and saf ety. Mateorological data will be passed , along to the Sta-te Representatives as received but their . l ' estimates of thyroid doses are expected to be approximately 3 to l 300 times higher due to the differences in iodine / noble gas ratio. The methodology is based on Reg. Guide 1.145 dispersion models and Reg. Guide 1,109, Rev. 1 dose factors. These models have
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been programmed on a mini-computer located at the EDF. The-same program can be run on a miril-computer located near the General .
. Office ( Ailarrt a ) Emergency Cenier.
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See Title Page 4 ' m Georgia Power ah ~~ 2 of 40 m mee Title Page O D. Estimation of Offsite Exposures NOTE ( t The minicomputer system is designed to take various plant and meterological data as input and calculate ottsite dose rates, cumulative doses. and tabulate these for each sector at 1, 2. 5 and 10 mile distances. Protective Action Recommendations are also tabulated using the criteria of HIC-4854. The system is [ designed for updating every 15 minutes and has the added capability to forecast exposure data for hypothetical sets of , c?iene parameters, Tabulation of ticld monitoring data is also , orovideo. Sat up the minicow.puter per Checklist No. 1. 1. L , Cater mitial data as requested by the computer. . When the
- verification run" is complete, assure the values 3.
J match those on Checklist No. 1. If they do not match,
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. repeat system setup using an alternate disk. .
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' i .s 4. Enter radiatica monit'or or sample data as requested. This i information is obtained from a communicator / recorder.
Meteorological data is also provided by the communicator / recorder. 4
- 5. Three copies of printout are available for use by: g f,4
- 1. Status Board Recorder - and subsequent Posting ;j y
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- 2. Dose Assessment Manager I
- 3. 1leld Team Coordinator .
- 6. All data printouts should be reviewed and initialed by th? ;
Dose Assessment Manager. [
- 7. Periodically perform verification calculations using data from Tables in Appendix A of this procedure. For the appropriate stabillty class, wind speed and distance, multiply the curies per second release rate by the Table factor to estimate dose rate. Compare with printout data.
i Inconsistencies must be reported to the Dose Assessment l
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Manager. I i
- 8. Provide all data and Protective Action Recommendations to State-(DNR APD) personnel.
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Georgia J Power aA' 3 oF 40 Sae. Title Page N__OTE a Prote ctive Action Recottonenda-t ions Longer are based on cumulative projections may be 9 doses plus a two hour projection. ! made by simply multiplying the calculated dose rates by the projections time desired.
- 9. Exposure estimatos for field monitoring teams can be made by periodically checking pocket dosimeters (whole body) and (
multiplying stay times by measured radiciodine i concentrations using the following conversion factor: 4pi/cc (I-131)
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".ren/hr (ihyroid) = 1.85 E19
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HIMP-4852 E. l. HATCH NUCLEAR PLANT -ow~w . Ece Title Page g\ 4 4 :ce Sea ritle Page 4 of 40 CHE('!< LIST _ NO. 1 I St-TUP ..C.F DOSE C ALCU.L...ATION MINIC.OMPUTE..R. I
- 1. Move Computer Console and Printer to Dose i
Assessment Area. Plug both units to 120 A.C. power. Connect printer to computer.
- 2. Turn Printer on (switch is in back) and press ,
reset button.
' Turn Computer on (.sw i t c h is on right hand , i side).
4 Insart Diskette and close door. Red light should go on. S. i.Jnen red light goes off, press reset button. ,
}, j ,,,,_,E.. Type in Data and Time (24 hour clock) as
- requested and press Enter '< e y .
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- 7. Type in the following sequence: 3
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(i) Sasic (Enter key) (ii) (Enter key) . f*- (iii) (Enter key) ; (iv) LOAD " HATCH / PAG" (enter key)
- 8. Type in information as requested.
- 9. Compare verification run with the following values' .c I
VERIFICATION RUN_ VALUES (mrem) DISTANCE WHOLE GODY THYi3OID 1225 3484 1 mile - 503 1431 2 miles , 5 miles 108 306
.I 41 117 10 miles
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NOTE If the verification run values do not match those above, re turn to Otep 4 and use an alternate diskette. o
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m .\ Georoia D Power al ,3 of 40 _w ne Page APPENDI_X A VERIlICATION TABLES
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_ Sue Title Page .oiw.w , o.ra 4 Georgia Power d ~~ O See Title Page 40 of 40 APPENDIX A , VERIFICATIQN TACLES . l
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PROC 56Uii5 NbMGER Lab _ - . - - - _ . - _ - . - - RESPONSIBLE SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( , ) REV. APPROVEO APPROVED DESCRIPTION DEPT. PLANT DATE ______ HEA O MAN? ER 13 Pqos. 2,11,12, & 19
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. PROCCOUTE NO. HNP- - b.k.__ SHEET 1 OF_Q_ (
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gc5G5Bf6~67-~~ DEEZ5W.FNT l-E 5"EFbRO'J'AL Name: Date: Signature: , Date: . 0 , A ? Q -} N'3# b hD bt-Ql / l REVISION c.HANGEC MODE O' CFERATION OR INTENT *S DESCRICED IN FSAR: i No I ( ) Yes ( I CHANGE IN'JOLVES: ( ) An unreviewer: Gafety Guestion ( ) Tech. Specs. ( ) Neither (See t acl< f o r- Saf ety Evaluation J4 required). PRESENT STATUS: Safety Related ( /) Non-Safety Related ( ) The above Sae ety/Non-Safety Status has chenged ( ).Yes to (Gk _ Attach marked up copy of procedure to this form. NM% M W REASCN FM REGUEST: t$h \Q , . vDMA h
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SdFETV EWLU6 TIC.?.j . . . . . . _ . . . _ - - .- _ . . . . . . v. y ':. This revision does not const_I_ttl.t_e__an unreviewed safety question as explained
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- 1. The orobability of occurrence and the consequences of an accident or .
malfunction of eoniment incortant to safety are not increased above
-i those analyy_ed in the FSAR due to this revision because thd revision d.o_e.3 not chance the___curcose_ _oi performance of the system.g-de M 2.
_ 2._ The msibility of an accident or malfunction of a different type than analyzed in the FSAR does not result frca this revision because the M'
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*m c~ ~o See Title Page 26
- GeorgiaPower A _ ~o 9
men T;+1e pnn" 1 of 22 PERSONMPL DOSIMLTRY PROGRAM A. PURPOSE Tc describe a procedure for the issuance and use of personnel dosimetry equipment for plant personnel, visitors, and construction workers while within the operating buildings. B. Rint-::RENCES Code of Federal Regulations, 10CFR2O A.P.T. Computer Exposure Records System C. DESCRIPTION OF DOSIMETRY ECUIPMENT
- 1. Thermoluminescent Dosimeter (TLD Badge)
The TLD Badge is a small badge containing two or more lithium fluoride TLD chips for measuring external beta gamma radiation. These badges are supplied by a TLD badge vendor and will be processsed at monthly intervals during normal operations, and at more frequent intervals during maintenance outages or when conditions require. The TLD badge vendor will read and evaluate the badges and report the r.esults to a Laboratory Gupervisor. The record of accumulated external radiation exposure received by individuals is obtained principally from the interpretation of the TLD badge.
- 2. Direct reading pocket dosimeter The direct reading pocket dosimeter is a pencil shaped ion chamber used primarily to provide day-by--day indication of external gamma radiation exposure. A dosimeter with a range of 0-200 MR is provided for normal use. For special requirements higher range dosimeters will be issued as necessary by the Health Physics staff.
- 3. Neutron Dosimetry The Healih Physics staff will review the R.W.P.'s each dosimetry period for personnel who may have become exposed to neutron radiation. The TLD badges for these individuals will be mailed to the TLD badge vendor requesting that the badges be read both for beta gamma exposure and neutron exposure. The report for these badges will be handled the same as in paragraph C.1.
' manual set
~** E.1. Hatch Nuclear Plant = awn =
HNP- 8004 See Title Page m'*
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- Georgia Power m ~~
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- 4. Other As deemed appropriate the Health Physics staff will issue other personnel monitoring devices, i.e. finger rings, TLD
. bracelets, chirpers, etc. for monitoring personnel radiation exposure.
D. ISSUANCE OF TLD BADGES AND POCKET DOSIMETERS
- 1. Prior to issuance of any TLD badge or dosimeter Form 1, TLD BADGE AND DOSIMETER ISSUE must be completed. See Section G.
for details.
- 2. Issuance of any TLD badge may be made only by a member of the Health Physics staff.
- 3. Issuance of pocket dosimeters may be mace only by a member of the Health Physics-staff.
- 4. Prior to entering -the operating buildings where radiation exists all individuals assigned TLD badges'and dosimeters will pick them up and wear the devices as in Section E.
Daily dosimeter reading will be logged as in Section G.
- 5. Dosimeter and TLD's are also required to be worn at the WS-TSF.
NOTE Dosimeters that have been used, and then placed in the "OUT" rack, will be re-zerced prior to the start of the next work day, if a reading of 5 mrem, or greater has been reached. l E. WEARING AND USE OF TLD DADGE AND DOSIIT TER The TLD Badge and dosimeter are to be worn adjacent to each other between the waist and neck on the front part of the body. As per Health Physics discretion, an individual may be instructed to wear the dosimeter and TLD on another part of the body, if it is determined the dose rate at that part of the body is likely to be higher than that between waist and neck. When wearing protective clothing, the TLD badge and dosimeter are clipped inside the b r ea s-t pocket (Outside pocket) of the coveralls and pocket closed. The TLD badge shall always be worn with the face of the badge tacing out. Each individual should examine his dosimeter periodically while in a radiation controlled area. No individual should allow the dosimeter reading to exceed 150 mR or 75% of full scale regardless of any prescribed exposure allowance, without having his dosimeter recharged and reading recorded. Personnel finding self reading dosimeters off-scale shall immediately leave a Radiation Control Area unless involved in controlling an emergency and shall notify the Heaglj'l-gsics
=o= E.1. Hatch Nuclear Plant act== ~o HNP.8004 See Title Paqa mwsiou ~o
- Georgia Power A - ~o See Title Page 3 of 22 Staff. The loss of any personnel monitoring device requires the immediate notification to the Health Physics staff and a note signeu by a supervisor requesting another TLD badge be issued. f NOTE If at anytime the dosimeter is dropped or erratic readings are noted by the user, the Health Physics Staff should be notified in order that another dosimeter can be issued if deemed necessary.
F. WEARING AND USE OF EYTREMITY DOSTTMETRY The following criteria should be used for the use of extremity dosimetry:
- 1. Extremity dosimetry is defined as finger rings, or as per H.
P. discretion, TLDs taped to one of the extremities. The extremities of the body are hands, forearms, feet, and ankles.
- 2. Health Physics shall determine the need for extremity monitoring on an individual job basis. Factors involved in making this determination are dose rates, stay times, etc.
Extremity dosimeters will be provided for those individuals requiring this coverage.
- 3. Guidelines for using extrem ty dosimetry are as follows:
i
- a. When the extremity exposure rate is likely to be four timos the whole body exposure rate AND the extremity exposure rate is likely to be > 400 mrem /hr.
- b. When performing primary systems sampling, manipulating high-intensity calibration sources, or perfarning any task for which extremity dosimeters are required by H.P.
- 4. Extremity dosimetry will be issued and returned on a daily basis, unless specified differently by'H.P. If personnel
_need extremity dosimetry more than once a month, they will be issued the same extremity dosimeter (finger ring, etc.) for the duration of the month. Form 5, Extremity Badge Issue Log will be completed as needed. G. ESTIMATING NEUTRON EXPOSURE
- 1. Until an individual's TLD is read and the actual neutron exposure determined, an estimate will be generated in the following manner: Form 11, NEUTRON DOGE EST1 MATES _will'be used to record neutron dose.
manual set 6" **'eW ' " * - @
"- * === E.1. Hatch Nuclear Plant mocwuae ~o HNP- 8004 See Title Page "tvreo* ~o
- Georgia Power m ~~e
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- a. As per survey data, calculate a neutron-to gamma ratio by dividing the neutron dose rate by the gamma dose rate.
- b. ' Multiply the neutron-to gamma ratio times the gamma dose recorded by the pocket dosimeter.
- c. Add this product to the gamma dose to obtain the total whole body exposure.
- d. Example of above method:
(1) Gamma dose rate: 60 mR/hr Neutron dose rate: 30 mR/hr Dosimeter reading: 80 mR (2) Neutron-to gamma ratio: 30/60 = 0.5 (3) Estimated neutron dose: (80 mR)(0.5) = 40 mR (4) Total whole body dose: 80 mR t 40 mR = 120 mR
- e. Input the total whole body dose to the computer via CDUDAT Program or use Form 2 of this procedure if the computer is disabled. .
s H. RADIATION PROTECTION CRIENTATICN All new employees shall receive a radiation protection , orientation prior to their assignment of work in Radiation Control Areas or have an escort by someone who has demonstrated understanding of radiation protection practices and procedures. See HNP-0018. The orientation will cover all pertinent radiation protection practices and procedures to a degree sufficient to allow an employee to perform his assignment without incurring unnecessary radia tion exposure or contamination. Each employee-will be required to demonstrate an understanding of these procedures prior to being allowed to enter a Radiation Control Area unescorted. I. PERSONNEL. DOSIMETRY RECORDS
- 1. Form 1, TLD Badge and Dosimeter-Issue
- a. The preparation of this form is the responsibility of the Health Physics Departmant. The purpose of the form is to record all information required by 10CFREO for personnel wearing monitoring devices.
- b. Procedure for recording information on Form 1.
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""**""0 See Title Page f - Georgia Power 1 ~ ~o Ana Ti+1n punn 5 of 22 (1) The individual shall complete the upper part of the form down to the heavy black line.
(2) Health Physics Department shall complete the , bottom part of the form. (3) The form shall be filed and maintained in the dosimetry office until termination.
- 2. Form 2, Weekly Pocket Dosimeter Record
- a. This form provides a means for recording personnel pocket dosimeter results daily and will assist in evaluating each person's integrated dose to keep exposures as low as reasonably achievable and below exposure limits of 10CFR20.
The form will be used if the computer exposure record system described in I.'3 becomes disabled and when visitors are issued dosimeters and TLD's.
- b. Procedure for recording information of Form 2 (1) Form 2 for the current week will be maintained by the Health Physics Staff.
(2) Separate sheets of Form 2 will be kept for each type of personnel. (3) The individual whose name appears on Form 2 will record or have recorded his dosimeter reading on entering the operating buildings (IN GLOCK) and on exiting the operating buildings (CUT CLCCM) at the end of the work day. It will then be calculate or have calculated the indicated exposure by determining the difference between the IN and GUT blocks and will log the result in the NET block. (4) The Health Physics staff will log each~ individual's accumulated quarterly exposure in the GTR block at the beginning of each week. (5) The Healih Physics siaff will determine total daily exposure by adjusting the indicated exposure with exposures determined From Form 3, Dosimeter Re-zero Record and other methods as necessary. These adjustments will be logged in the ADJ. block and will be added io the NET exposure to determine manual set
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l i the total exposure for the day and recorded in the TDT block. (6) The Health Physics staff will determine the accumulated weekly exposure for each individual by summing the TDT block for the day and the WK block for the previous day. (7) The Health Physics staff will adjust the quarterly (GTR) exposures 10 reflect-official exposures as determined from the processing oF TLD badges during the current quarter.
- 3. Form 3, Dosimeter Re-Zero Record This form is used when an individual's pocket dosimeter is re-zerced while within the operating buildings. DOUDAT cards may be used in lieu of Form 3. The form will be located at each dosimeter charger station It shall also be used when zeroing special pocket dosimeters as issued by the Health Physics staff (Indicate special in the Remark Column).. Exposure data from Form 3 shall be entered on Form
.2 or in the computer record system from each individual.
See I.2 or I.9 of this procedure.
~
- 4. Current TLD Dccupational Radiation Exposure Report
- a. This report will be furnished by the TLD vendor at a frequency based on badge exchange intervals. The report is approved for use in lieu of NRC Form 5.
- b. Results of TLD exposure analysis will be entered into the ccmputer exposure record system on a monthly basis or with gr",ter frequency, as this data is provided by the vendor. Current NRC Form 5 information may be obtained fium the computer system at any time on an individual or departmental basis' by .using the INDDRP or the DDLIOi ;rogram respectively.
- 5. Form 4 Replacement Exposure for Lost or Damaged TLD Dadge This form will be completed as necessary to estimate personnel exposure during a period when a TLD badge has been lost or damaged. Exposure determined on this form will be entered on the Current TLD Dccupational Radiation Exposure Report through the use of a letter to the TLD vendor as shown in Form 13 and inio the - computer exposure record system.
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G. Form 5, Extremity Badge Issue Log Form 5 will be filled out as needed and completed by the end of each montn. The extremity desimeters will be mailed to the vendor at the end of the month for analysis, and the results are supplied by the vendor on the Current TLD Occupational Radiation Exposure Report.
- 7. Form 6, Request for Employee's Previous Radiation Exposure A letter shall be written to an employee's previous empicyer(s) if the employee does not have his previous exposure record and indicates that he may have received occupational radiation exposure while employed there. The letter shall be provided on Georgia Power Company stationary
- and in the general format as shown on Form 6, Request for Previous Radiation Exposure.
- 8. Form 7, Report to Former Employees and Visitors of Exposure to Radiation.
On request by former. employees a report. showing exposure to radiation shall be furnished within 30 days from the time the request is made, or within 30 days after exposureThe of the individual has been determined, whichever is later. report shell cover each calencar quarter of the individual's time within the Protected Area involving exposure to radiation or such lesser period as may be requesied. .The report (Form 7) shall be xeroxed from individual's file and shall be transmitted with a cover letter (form 9) on Georgia Power stationary and in the general format as shown on Employee and Visitor Radiation Exposure Report, Form 9. When an individual terminates employment or an individual assigned to work in Radiation Control A. eas '- thecompletes Hatch Nuclear Plant, but not employed by ueorgia Powei his work assignment the individual and the Nuclea. Regulatory Conanission will receive a report on his exposure to radiation and-radioactive material incurred during the period of employment or work assignment. Such report shall be funished within 30 days after the exposure of the individual has been determined or 90 days after the date of termination of employment or work assignment, whichever is earlier. The report shall be provided on Georgia Power stationary and in the general format as shown on Form 7, Employee and Visitor Radiation Exposure Report. The original report may be obtained by accessing the computer exposure record sysicm using the TERMNS program, or from the Curreni TLD Occupational Radiation Exposure _ Report (para. I.4). manual Set
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- 9. Computerized Personnel Exposure Records !
>l A computer for up-dating personnel exposure data on a I day to day basis has been developed. Pocket dosimeters a.
3 are read by a Health Physics technician and the reading entered in the computer. The computer updates the individual's exposure record to reflect the latest dosimeters reading. Daily, weekly, monthly, quarterly, yearly and lite time exposure information is made ' available to the Health Physic staff, plant supervision, and the individual through the use of See APT Automated various computer printout formats. Personnel Dosimetry Records System Manual. b, Schedule of input and output of exposure information via the computer exposure records system. (1) Daily - Pocket dosimeter will be read on a daily basis. . Entries will be recorded by the computer on a daily basis using the DDUDAT program. Where dosimeters are re-zerced in the Primary Protected Area, the dose recorded on Form 3 shall also be entered into the computer using the DDUDAT program. (2) Weekly - A listing of daily exposures for all personnel on site for each day of the week will be obtained at the end of each week using the DDPRNT program. (3) Monthly - The net dose indicated for each worker listed in the " Time Record" section of all Radiation Work Permits issue during a given month shall be entered into the computer exposure record system prior to entry of the TLD data for'the respective period, using the CWPUDT program. TLD data will be entered into the computer exposure record system each month using " the CLDUDT program as this information is provided by the vendor. Corrective or supplemental TLD data may be entered into the' computer exposure record system using the HLDLOT' program.
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-. Georgia Power a ~ ~o n,s o T4 H o Paoa 9 of P2 NOT.E Programming has been es-tablished to determine the discrepancy between the TLD and pocket dosimeter. A discrepancy greater than 25% for exposures over 300 mR l will be evaluated. An investigation shall be conducted and documented on Form 10, Dose Discrepancy Investigation. The TLD reading will be retained as the record exposure unless the investigation justifies use of pocket dosimeter totals.
Data files will be removed from the TMPDOS exposure record file each month for personnel terminating their stay at the plant whose final TLD data has been provided by the vendor. The TERMNB program will be used to accomplish this and will produce the original letter of notification of exposure for the individual,,as well as a copy of his final dosimetry file contents. (4) Ann _ual - The NRCRPT program will be run after the TLD results for each year has been entered into the computer. A . compilation of information to satisfy 1CCFR2O annual reporting requirements will be provided by the program after the exposure information for an entire year has been recorded. (5)As required The PDFMAK program is. utilized to enter new personnel inf ormation in-t o the computer exposure records, to add identification or prior exposure information. The DELETE program is used to transfer a personnel record from the active files + to the TMPDOS file at the end of his stay. The record is retained in this file pending receipt of final TLD data from the vendor. manual set
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} Goa T!+1a Pane 10 of 22 t The 'F DUDT program allows the entry of I L TLD information for individuals at times '
- other than the regular monthly entry of ,
TLD data on a plant basis. The individual dose reports covering all NRC Form 5 information can be obtained using the INDDRP program. The DDLIST program can be used to provide on a plant basis the same information that the INDORP program supplies for a particular individual. Whenever required, particularly during an outage, the DDPRNT program may be utilized to obtain a listing of dose for each dhy of the current week and the margin between the cumuulative exposure and the most restrictive exposure limit, for each person on site. The Applied Physical Technology Auiomated Personnel Dosimetry System Instruction Manual may be referenced for information on organization of data files and operation of programs.
- 10. Form 9, Reply to Request for Previous Radiation Exposure When a request is received by Georgia Power Company from a previous employee or visitor for the purpose of providing his new employer (or facility being visited while in the employinent of his new employer) with a record of occupational radiaiion exposure received at Plant Hatch, Form 9, Reply to Request for Previous Radiation Exposure, shall be used to supply this information.
J. MANAGD.ENT REVIEN OF RADIATION EXPOSURE DATA The H.P. Superintendent will be responsible for preparing a Radiation Exposure Repori for the inanagement meeting. As a min iminn, the report will consist of a tabulaiion of exposures by department, including the average dose received per worker and the maximum dose. Also to bei included will be a tabulation if of exposures on specific maintenance work during the monih, significant work has been performed. Dther significant exposure infortnation will be discussed during the meeting as appropria t 9. manu:I set
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( C.1. McLUll INuclUUf I'larlt nioctrunr no l HNP- 2004 - See Title Page~ a+ vi:> ion nu om Georgia Power es _ ~o mo T4+1o pm." 12 of 22 FORM 1 1 TLD PADGE AND OnSIMETER ISSUE TLD OAcct Ano DOSIMETCR Insir DATE: 19 1.D. GADCE NO. NAME IN FULL (PRINT) FIRCT M.DDLC LAST SOCIAL CCCURITY NO. - - DIRTil DATC:~ MON DA,Y 1H YCAR HOME ADDPCCC: HCMC PlCNC: ( ) STREET CITY GTATC ZIP j JC3 CATCCORY INTRA. PLANT CEPT. C,OMPANY OL9CRVICCR f, ENGINCCRING ( ) GA. ;ND CO. PLANT HATCH ( ) CMICC GTAFF ( ) MAIhT. MICH. ( ) GA. PO'sCR CC"PANY
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Ctd. STAFF ( ) MAINT. CLCCT.( ) COUGtCRN CERVICCS INC. ( ) OPC.7ATIONC ( ) TECT DEPT. ( ) A.D.A. ( ) LAO /PP ( n OPERATIONS ( ) T f. G ( ) r*AINTENANCE ( ) LADC.7ATORY ( ) C O '. I ( )
- CTHER ( ) CFFICC ( )
- C.E. ( )
+ PLEACE CCSCRICE:
- CONTRACTCR ( )
- GIVE NAME CF CCMPANY:
- Have you worked at or vtssted a Nuclear Fac tity other than Hatch in the last three months'
- YES ( ) NO ( )
- If YES, what faciltty SIGNATU9C Have you treen at Plant Hatch an the last thr e month 'CS( ) NO( )
If vasttor, escort's name _ TLD Dadge No._ NRC Form 4 completed Authorized Quarterly Euposure mrem
- Issued Oy _
Reviewed Oy LEG If 18 years old 1 smit exposure to 7EO mrem / quarter.
- If current quarter exposure as unknown, l a t- s t is 300 mrem.
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od'. Georgia Power da 1 r_., op ;,a sem r:e,, omge i FORM 4 '. t RFPLACEMENT EXPOEURE FOR LDST Tl_D GADGF l RJPJACEMEt4T CXPOCURC FOR LOGT TaLotDCE I.D. Gadge No.:___ Date: TLD No.: .- Name: Sec. Sec. No.
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- If "Other" Explatn:
TLD Last Worn: Ftrst Day of Current TLD Portod: __ DO3E A;;CCTCMT -_ Yes ( ) No ( ) Did Indsvadual enter a radiation area today? I (- "No", complete items 1 and 2; if "Yes" ccmplete all stems. mR
- 1. Sum of Dostmeter readings recorded during period:
HNP-8004, Form 2: __
- 2. Source of above Dose Data:
CCt. OAT: ___________ COMPUTER _____ DOPANT:
.e today?
- 3. What Radiation areas did the individual i
- 4. How long was the indsvidual in each area?,,
S. What were the Dose Rates in these areas?__ What RWP No. was the individual working ur. dor? _ _ _ _ 6. What exposures were received by others an the area? 7. Name: Dose: . _ Time in area: . _ _
,,_. Dose: ,,,_ Time an area:
Name: B. Based on the abovo information, what is tree individual's - mR. estimated esposure for today? H.P. Representatsve Employee HNP--GOO 4 R 16 FOHM 4 manual set
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RMMS EXTREMITY BADGE ISSUE LOG EXTRCMITY DADCC_ISCUC LtjQ MONTW: YEAR
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6 oan Georgia Power t$a ,.m ~e wu *r ? + 1 o puno 17 op 22 FORM 6 REGUECT FOR PREVIC !S RADI AT ION EXPOSUllE Georgse Power Company Pcal Office Boa 439 Bas.ey, Georgia 31513 Te whone 912 361 7751 912 537-9444 L GeorgiaPower Ek.a 1. Match NucIser P! sat D M E: Sutnect: Agiat:en Exposure ibcerd Gentlemen: The fottowing Individual has inc!cated that he reco.ved red!stion exposure wnste working for your organization. We would appreciate receiving copies of your exposure records for this urnployee. Name of Employee SS/No Dates: (Top (Frorn) Voy truly yours. Laboratory Forernan I hereby autnortze the re! ease of the above information. G.gnsture of Empicyue (Dato)
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Jr . . Georgia Power Corepany Post Othce Boa 09 Baslev. Coors= 31513 Tesopone 912 "AF-7781 912 537 G'44 h nh GeorgiaPower Edwin 8. Maten Nucteer Plant DATE: l'A 2: SS /140: ADDRESS: DATC OF BIRT 11: SU5 JECT: CADIATION EXPOSURE REPORT DEAR SIR: PLEASE BE DVISED T. TAT *illLE C: PLOYED OR VISITING AT T"Ja EININ I. !!ATCit NUCIIAR Pl.ViT DUat:G ThE iCLL;Jt. C EGrx PERIOL(S), YOU PECCIVr.:) T!!E FOLLC'.11!:0 EXF05URE TO IONIZI!;C ILSDIATION. DATES .'!CNIT31: D F RECOEJD EXPOSURE (IG.M)
- T3 tilfCLE BODY SKIN EXTREMITIES FROM
- EXPOSURE DETCR:11:;ED hY TLD BAOCZ C;LESS ODIEWISE 'iOTED P:.?MRS BIO-ASSAY RESULTS:
?.IIS REFORT IS FURNISHED TO YOU C; DER Tile P:t0 VISIONS OF T.lY. ItUCLEAR FIGULATORY CO'CtISSION RECULATIOtt 10 CFR PART 19. YOU StiOULD PFtsrRVE TlilS kEPORT FOR FURT11CR -
FIFEREt4CE . IABORAlen Sut*ERVISOR XC: DIRECTOR, MV; ACE}2NT AND PK0 CRAM ANALYSIS U.S. t;UCLEAR REGULATORY CU.'utISSION WASHINGTON, D.C. 20555 FILE ItNP-8004 RI6 l Form 7 l mantial set q- y-- , + T- - - r - - - y
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4 I Eberline Instrument Corporation P. O. Box 2108 Santa Fe, New Mexico 37501 Attention: Dosimetry Services Centlencn: Ths Georgia Power Company Plant E. I. Hatch TLD Occupational y. Radiation Exposure Report does (or willi not reficot exposure received by the following person for the indicated period because of lost or damaged TLD badge. Based on plant exposure records, we estimate the individual'c exposure to be: S.S. NO. DATES COVERED EST. EXPOSURE TLD H3 NAME (REM) Fron: W.B n Skin Ext To: Please adjust this individual's record to re flec t the above estimated exposure. Yours truly, Health Physics cc: Individual's File HNP-0004' Form 8 R16 manual set 9 y3-, - - - . , -y 9
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FORM 9 4 i Georgia Power Company Post utlice Dos 439 Baaley. Gerag a 31513 Te#ephone 912 367 T791 312 537 6444 m GeorgiaFbwer Edwin 8. Hatcts Nwsleer Pleal
SUBJECT:
RADIATION EXPOSURE REPORT DEAR SIR, ATTACl!ED IS A COPY OF Tite EXPOSURE REPORT FURNI511DJ dLutE) ~ < (SSAN) UPON TERMINATION OF VISIT OR Et*JI.0UtENT AT PIJdT HATCM. 4 ALL EXPOSURE IS DETEP. MINED BY TLD DADGE UL.ESS OTHEKKISE NOTED CN ATTACHED. THIS REPORT IS FURNISHED TO YOU UNDER THE PROVISIONS OF 10 CFR 19.13. a i LAbORAI0 sty FOREMAN i xc: File I
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- Georgia Power $1 ..m ~e h r. T4+12 P a n s. 21 of 22 FORM 10 DOSE DIGCREPANCY IbMIGTIGATIQ1 2-4 DO5E DICCREPANCY IPNCGTICATION Individuals Name:
/TLD# _/ID#
Period of Exposure to _ Reported TLD Cose nr Recordec Dosameter Oose mr DWECTIGATIC+4 FIFOINGG:* s Investigating Technictants) Record Exposure Accepted __ _mr, Individual's Supv. nottfied / Lab Foreman Review /Cate approval / Exposure entered into computer by: tumc/Date Eberlane notafied via Form G Name/Date
- Investigation may include the following;
- a. Survey Results
- b. Exposure. Time
- c. Ooses of other performing sims).'r . work.
- d. -Location of devices worn on tt.e body.
- e. . Type of Dostmeter, High liange er Low Range.
- f. RWP totals.
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III l GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PROCEDURE Handlina Ex20 sed And/Or Contaminated Casualties PROCEDURE TITLE , i HNP-4801 . PROCEDURE NUMBER l i Lab i RESPONSIBLE SECTION i t SAFETY RELATED ( X ) NON-SAFETY RELATED ( ) l t., APPROVED APPROVED REV. DESCRIPTION DEPT. PLANT DATE HEAD MANAGER
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PRESENT OTATUS: , ( ) Yes to __ _ _ _ _ _ _ The above SMety/Non-Safety Status has changed - 1 Attach marked up copy of procedure to this form. j'h_jyH & 5 &.i'g.ay_fjff_yfb ih_ lif7 REABCN rGR REGUEST: _ %,. _ . .
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. REASON FOR REGUEST: 22 N@ mas /2021PJf!A>/ /
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_ _ - -_ e. __ _ t below. . l' . The probability of occurrence and the consequences of an accident or r.1alfunction of e_qu,iyment important to safety are not increaded above those analy_ zed in the FSAR due to this revision because the revision dccs not cl5an_a.Le 'the pur_ pose oi performance of thystem. 7[a
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f;' Ron T4+1m Pans 1 of 14 HANDLING EXPOSED ANO/OR CONTAMINATED CASUALTIES , A. PU9 POSE 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. I B. SAFETY { Under all circumstances, unnecessary esposure to radiation should i 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 I great) he is making toward the health and safety of the casualty. I C. REFERENCES i HNP-4810 HNP -BOC6 FSAR, Section 13.5, unit II 10 CFR 20.103. 10 CFR 20.405. D. DEFINITIONS 1 For the purposes of this procedure, the following definitions j-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 aems.
- b. Hands and forearms; feet and ankles 3/4 rems;
- c. Skin of whole body - 7 1/2 rems.
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*=om E. l. Hatch Nuclear Plant aaou =~c~o HNP.4801 Sso Title Pega arao= ~o 7
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- 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, measured with beta detecting GM survey meter, shows greater than 100 l "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;
- e. Inhalation or ingestion of radioactivity in quantities known or suspected to exceed 10 D.O.B. as given by the whole body count.
- f. Inhalation or ingestion of unknown quantities of radioactivity.
- 5. Off-site Medical Support - Care, treatment and/or consultation provided by Company Medical Consultant, staff of Appling General Hospital, or Radiation Management
'l 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 paiient'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. It 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".
manual set i
aa m m E. l. Hatch Nuclear Plant =camac ~o HNP- 4801 Sas Title Psgo aav*oN ao 7
.... Georgia Power d . . ~o Sep Title Pace 3 of 14 F. INJURY /EXPOCURE CAJECORIES
- 1. Excessive Radiation Exposure - No serious injury (See Section H) (Normal Hospital Admission).
NOTE Monitor the p'atient for incidental, but detectable contamination. It coniamination is detected, he will be admitted through Radiation Emergency Area.
- 2. Excessive Radioactive Contamination - No serious injury (See Section I) (Admission ihrough Radiation Emergency Area, i except if contamination is exclusively internal deposition). I
- 3. Excessive Radiation Exposure and Radioactive Coniamination -
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 l Section K) (Normal Hospital Admission)
NOTE Monitor the patient for incidental, but detectable contamination. It contamination is detected, he will be admitted through Radiation Emergency Area. S. Excessive Radioactive Contamination - With Serious Injury (See Section L) (Admission through Radiation Emergency Area, except if contamination is exclusively internal deposition). l
- 6. Excessive Radiation Exposure and Radioactive Contamination with Serious Injury (See Section M).
(Admicsion through Radiation Emergency Area, except if i contamination is exclusively internal deposition) G. GENERAL PROCEDLtREG
- 1. Ir. any accideni, 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, ihen make immediate contact with the Company Physician and Radiaiion Management Corporatints (if radiation is involved). In the event that an individual is known or l
suspecied to have been seriously injured, it is better to stmmion the ambulance needlessly than to j eopardize a man's l 1 life.
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- 2. All exposure, contamination, or injury incidents, or combinations coming within the scope of this procedure, warrant off-site medical support. In some instances (e.g.,
a 4 rem whole body e:oosure) the support may simply consist l of telephone consultation with the Company Physician and Radiation Management Corporation. In other instances (e.g., a burn case), the need for support may be far more urgent. l Accordingly, the Shift Supervisor will obtain a prompt evaluation of the. urgency for off-site medical support.)
- 3. In all cases covered by this procedure, first priority will always be given to serious injury. After a victim has been removed from a hazardous area, care and treatment for excessive radiation or contamination exposure can be deferred without significant harm to the victim, but failure to administer prompt first aid may jeopardire his life.
- 4. The Plant General Manager will assure 15at each accident / incident is investigated, lis causes determined, l and action taken to prevent its recurrence.
- 5. After each accident or incident in which first aid or Medical Room supplies were used, the Laboratory Foreman will assure that these supplies are replenished.
H. G M EGIVE RADIATION _EX_ POST!RE - NOT SERIOUG INJURY
- 1. Immediate Action
- a. Exposed individual will take immediate action to protect himself from further exposure.
- b. Erposed individual will notify Shift Supervisor without delay.
- c. Shift Supervisor will alert member of the Health 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. l manual set ; l
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""o= E. l. Hatch Nuclear Plant acce=ai ~o HNP 4801 '
moo = ,.o G2e Title Pega 7
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4p T4+1p Pano E of 14 (2) Advise Shift Suparvisor of the urgency for medical support. (3) Allay fear and relax the exposed individual.
- 2. Follow-up Action
- a. Shift Supervisor will notify General Manager, Operations Supervisor and Health Physics Superintendent.
- b. The Plant General Manager will:
(1) Notify or authorize notification of Company and Plant Medical Consultants and Radiation Management Corporation. (2) Immediately notify NRC Regulatory Operations, Region II, by telephone and telegraph if: (a) Personnel whole body exposures suspected to be 25 rem or more; (b) Personnel skin e'xposure is 150 rem or more; (c) Personnel extremity exposure is 375 cem or l 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 of accident.
- c. Exposed individual will be observed for symptoms, such as nausea, vomiting, fatigue, skin redness, or diarrhea, while awaiting results of consultation between Health Physics staff, 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.
NOTE There is no need for first aid or fer 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. manual set
- . -aam E. l. Hatch Nucicar Plant awe =a< ~o HNP- Agot
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c73 vi +j u nuqm n nf 14 I. EXCESSI_VE RADI_OACT y CONTAMINATION - NO GERIOUS INJURY
- 1. Immedia te Action
- a. Contaminated individual will withdraw from the immediate area of contamination, take elementary steps to decontaminate himself (e.g. remove clothes and wash exposed skin), notify the Shift Supervisor and await member of Health Physics staff. .
- b. Shift Supervisor will alert member of the Health Physics staff and will direct him to contaminated individual.
- c. Member of Health Physics staff will:
(1) Determine the level of external contamination using a G.M. survey meter. (2) Initiate personnel decontamination procedures (Refer to HNP-8006). (3) Estimate extent of internal contamination by assaying noseblow sample if necessary. l (4) Advise Shift Supervisor of the urgency of need for off-site medical support. (5) Recover contaminated individual's personnel dosimetars.
- 2. Follow-Up Action
- a. Shift Supervisor will notify General Manager, Operations Supervisor and Health Physics Superintendent.
- b. Plant General Manager will:
1 (1) Notify or authorize notification of Company and Plant Consultants and Radiation Management Corporation. (2) Assure that report required by 10 CFR 20.405 (if 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 EMERGENCY processing.
- d. Health Physics personnel will perform analyses of contamination to determine its isotopic composition (if internally deposited). ,
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- e. 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 if necessary. [.
- f. Subsequent treatment to accelerate reduction of internal contamination may result from consultation between Plant and Company Medical Consultants and Radiation Management Corporation.
- g. If contaminated individual is evacuated to hospital, he will be admitted through the Radiction Emergency Area.
Refer to HNP-424 and HNP-4420 for notification to authorities within one hour. J. E_X,Q.ESSIVE RADIATION EXPOSURE AND RADIOACTIVE CONTAMINATION NO SERIOUS INJURV
- 1. Immediate 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.
- d. Member of Health Physics staff will:
(1) Determine the level of external contamination using a G.M. survey meter. (2) Estimate extent of internal contamintion by assaying noseblow sample, if necessary. 1 (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. 1 massal set l I 1
- - ^~ E. l. Hatch Nuclear Plant aou=a ao HNP- 4801 S2o Titio Paga $*5*a ac 7- '
-. Georgia Power n .. ~o mn. T4+1. Anna 8 of 14 (5) Initiate personnel decontamination procedures (Refer to HNP-8006).
- 2. Fdilow-Up Action
- a. Shift Supervisor will notify General Manager, Operations Supervisor and Health Physics Superintendent.
- b. General Manager will:
(1) Notify or authorize notification of Company and Plant Consultants and Radiation Management Corporation. (2) Immediately notify NRC Regulatory Operations, Region II, by telephone and telegraph it: (a) Personnel whole body exposure is 25 rem or more; (b) Personnel skin exposure is 150 rem or more; (c) Personnel extremity exposure is 375 rem or more. (3) Notify NRC Regulatory Operations, Region II, by telephone and telegraph within 24 hours if l 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.
- c. Exposed individual will be observed for symptoms, such as nausea, vomiting, fatigue, skin redness, or diarrhea, while awaiting results of consultation between Health Physics staff, Plant and Company Medical Consultanis and Radiation Management Corporation.
- d. Health Physics siaff 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 if necessary. '
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- ma' E. l. Hatch Nuclear Plant **aou ~o HNP- 4801 revmon ~o See Title Pag'e 7
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- g. Subsequent treatment to accelerate reduction of 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-424 and HNP-4420 for notification to authorities within one hour.
K. EXCESSIVE RADIATION EXPOSURE - WITH SERICUG INJURY
- 1. Immediate Action
- a. First person who becomes aware of a serious injury will notify Shift Supervisor.
- b. Shift Supervisor will 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 mcaber of Health Physics staff will:
(1) Administer first aid consistent with nature and extent of injuries. (Refer to HNP-4810). (2) Advise Shift Supervisor of urgency of need for off-site medical support. (3) Recover injured's personnel dosimetry. (4) Remove injured from area of risk in accordance with HNP-4802.
- d. Shift Supervisor will summon Plant Medical Consultant (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. ) l NOTE l l Unless injured has incidental detectable contamination, he will not be admitted though the Radiation Emergency l Area. Refer to HNP-424 and FbP-4420 for one hour l l notification to authorities. sumul set
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- 2. Follow-Up Action l
- a. Shift Supervisor will notify General Manager, Operations Supervisor and Health Physics Superintendent.
- b. General Manager will:
(1) Notify or authorize notification of Company and Plant Consultants 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; (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 of accident.
- c. The Health Physics staff will:
(1) Determine nature and degree of radiation exposure by: (a) Discussion with injured; (b) Survey of accident / incident area; (c) Read exposed individual's pocket dosimeter. (2) Send the injured's TLD badge to the vendor for EMERGENCY processing. L. EXCESSIVE RADIOACTIVE _ CON 1 AMINATION - WITH SERIOUS INJURY
- 1. Imn.ediate Action.
- a. First person who becomes aware of a serious injury will notity Shift Supervisor.
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-ama' E. l. Hatch Nuclear Plant HNP- 4801
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- b. Shift Supervisor will 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 with nature and extent of injuries. (Refer to HNP-4810). (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) Advise Shift Supervisor of urgency of need for off-site medical support. (4) Recover injured's personnel dosimetry. (5) Estimate extent of internal contamination by assaying a nose blow sample if necessary. l
- d. Shift Supervisor will summon the company physician, ambulance or, on 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 Appling General Hospital.
NOTE 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-424 and HNP-4420 for one hour notification to authorities.
- 2. Follow-Up Action:
- a. Shift Supervisor will: [
(1) Notify General Manager, Operation Supervisor and i I Health Physics Superintendent.
- b. The Plant General Manager will:
I manual set
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<*aca E. l. Hatch Nuclear Plant aou w a ~o HNP- 4801 LEY @ON NQ S$:2 Title Paga 7
o-. Georgia Power n . . . 12 of 14 e_ _m_ v _s + 1 " """' (1) Notify or authorize notification of Company Physician and Radiation Management Corporation; (2) Assure report required by 10 CFR 20.405 is sent to NRC within 30 days.
- c. The Health Physics staff will:
(1) Assign member (s) of the Health Physics staff to accompany the injured and provide complete health physics support to ambulance and hospital staff. (2) Assure injured's TLD badge is sent to vendor for l l EMERGENCY processing. (3) Initiate analysis of samples of contamination to p determine its isotopic composition (if internally deposited). (4) Be responsible for recovery of all radioactive l waste from " Radiation Emergency Area" at Appling i 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 g contamination may result from consultation between Company Physician and Radiation Management Corporation.
NOTE Any radioactive material (shrapnel) removed from the injured will be recovered, if feasibic, and used as an aid in determining the ultimate exposure suFtered by the injured. M. EXCESDIVE_ RADIATION EXPOSURE AND RADIOACTIVE CONTAMINATION WITH SERIOUS INJURY ,
- 1. Immediate Action
- a. First person who becomes aware of accident / incident will notify Shift Supervisor.
- b. Shift Supervisor will alert individual trained in first aid and member of the Health Physics staff and direct them to injured.
> manual set 6
- . == E.1. Hatch Nuclear Plant ax =a.~o HNP- 4801 k'*5'o" "o Sco Ti+1e Page 7'
-. Georgia Power n ~. ~o mu T4+1p Pan. . 13 of 14
- c. Individual trained in first aid and member of Health Physics staff will:
(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 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) Advise Shift Supervisor of urgency of need for off-site medical support. (4) Recover injured's personnel dosimetry. (5) Estimate extent of internal . contamination by assayin3 a nose blow sample if necessary. l NOTE-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". Re f e r t o H43-424 and HNP-4420 f o r on e hour notification to authorities.
- 2. Follow-Up Action:
- a. Shift Supervisor will: !
(1) Notify General Manager, Operation Gupervisor and Health Physics Superintendent.
- b. The Plant General Manager will:
I (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; (c) Personnel extremity exposure is 375 rem or more. manual set i l
ao= E.1. Hatch Nuclear Plant aximas~o HNP 4801 See Title Pega anisio= ~o om Georgia Power A ... _o Sep Title Pacte 14 of 14 (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. .
- c. The Health Physics staff will:
(1) Assign member of the Health Physics staff to accompany the injured and provide complete health physics support to ambulance and hospital staff. (2) Assure injured's TLD badge is sent to vendor for EMERGENCY processing. (3) Initiate analysis of samples of contamination to determine its isotopic composition. (4) Be responsible for recovery of all radioactive waste from " Radiation Emergency Area" at Appling l General Hospital. (5) Determine nature and degree of radiation exposure by: (a) Discussion with injured; (b) Survey of accident / incident area; (c) Read exposed individual's pocket dosimeter.
- d. When injured's condition has been stabilized, j decontamination efforts will be re-initiated so that patient can be moved to conventional part of hospital.
- e. Subsequent treatment for internal radioactive contamination may result from consultation between l Company Physician and Radiation Management Corporation.
- f. Any radioactive material (shrapnel) removed from the injured will ha recovered, if feasible, and used as an aid in deiermining the ultimate exposure suffered by the injured.
manual set
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Revision No. -- i ' ~ DEP,*.RTMENT HEAD APPROVAL i
~' . .Name: EC5U5_5'TkD- 89~
- Date:
, . Date: Signature:
C u) . l*lWI [*-)[I/ EVISION CHANCES MODE OF OPERhTION ( dOR NoINTENT AS DESCRIBED IN FSA
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r CHANGE INVOLVES: ( ) An unreviewed Safety Guestion ( , ) Tech. Specs. ( /) Neither (See tiack for Safety Evaluation if required). -
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Safety Related ( ) Non-Safety Related ( M ESENT STATUS: --
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._T .he above Saf ety/Non-Saf ety Status has changed (
n'.' Attach marked up copy of procedure to this form.
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.C REASON roR REGUEST:
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. .~it.)ESCRIPTION OF CHANGES: ~ ~
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A L __ PRD RECOMMF.NDS APPROVAL: (dyes ( )No - V
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The revision of this procedure does _not constitute an unreviewed s_afety _ _I __ _ __[ j questian as p_ plain,egelow. . -. . - - . - - -
- 1. ~The er,).ahi,1_i_ty_gf_gqtu_rrgnte_gd_t.h l .qqns.gouences of an accident
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or malfunction _ of equipment _igmoortant to safety _ are not increa_s_ed __ ab.pve_.tho.ig._Analy.ud_la, the 'FSAR'dyg_.to thes.e3f.nces benuse the revision .does not change ,,t,he purpose _ or performance of__the _ _ , _ , _ _ _ system. -
- 2. The oossibility of 'an accident or malfunction of a different tyoe ,_,
than analyzed in the FSAR does not result from this change because ' the sy_ stem resconds and is operated as before the chance. .
- 3. The rtrain of safety as defined in the TechnicaT.Soecifications
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is not reduced due to this revision because the revision dc_es not I.
- chance any ifmited safety system settings which would allow a - -
l safet'y limit to be exceeded or to allow a limitino condition for < operations to be exceeded as. stated in' Technical Specifications. f
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om , _. = - GeorgiaPower A _ f. .. __ g See Title Pace . . , , . . - _- - .. 1 of-2
. 22-DRYWELL FIRE
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.A. CONDITION- 7 - " ~
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-1. " During normal: operation the drywell.is inaccessable and may-have an inert atmosphere. Z .
- 2. During shutdown when the inert atmosphere is purged-and
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' Maintenance personnel are at work in the drywell, possibly --
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of_, fire exists. -
- 3. A drywell fire could be identified And reported to the control room by maintainence personnel inside the drywell, or
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- 4. . Increased drywell temperatures lindicted on temperature Wecorders 2T47-R626 or R627 could also be indicative of a
. drywell fire, or -
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- 5. A drywell fire annunciator alarms on panel EZ43-POO1 or i panel H11-P655.
! 8. ACTION ,
g , l 1. Confirm that fire exists.
- 2. Initial response of control room personnel and fire team members should be described in FN'-2-42OO " GENERAL FIRE
' PROCEDURE" . /'
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- 3. The following action 'should be taken,for a maj or fire: __,,
'a. Control room personnel. -
(1) ' Dispatch personnel to move portable fire fighting equipment to the drywell entrance. ~ 4 (2) . Cease all refueling operations and place reactor-
' mode switch in SHUTDOWN as soon as possible. -' (3)
- Prepare RHR system for containment spray mode upon
- : . . orders by Shift Foreman.
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+b. Fire Team -
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Georgia Power A ._ . . _ . See Title Page -- - 2 of 2 ' (1) Clear all personnel from drywell except fire fighters. _
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(2):' Determine if fire is smal.1 enough to be handled with hand held ' extinguishers.-
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--( 3 ) - Fire fighters entering drywell must use
- self-contained breathing apparatus if fire is not _
localized.
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7 (4 ) -- Assign one man to keep tally of all personnel inside~ drywell so that none will be locked in if it becomes necessary to close the drywell.
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(5). Order" control'. room to:in'itiate containment spray'-
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---:-1.F.necessary to control fire.
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, (6) Clear hoses, cords, cables, and equipment not used .
for fire fighting from all hatches (include ventilation hatches at top of drywell) in preparation for possible decision to close drywell. - (7) If fire cannot be controlled, proceed as follows: (a) Clear all personnel from drywell. .. (b) Order control room personnel to secure all drywell ventilating and purge equipment (2T48-COO 3, 2T48-F207, .RT48-F319, 2T48-F309, ' - 2T48-F318).~'-- - W ' ~ ~
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~ f (c) CIose all drywe'1'l batches ~ tci~ permit fire to burn itself out. -
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(d) Shut down containment spray after drywell is closed. .,
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C. SUBSEGl.5 NT ACTION .
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- 1. Monitor dyrwell pressure and temperatures and vent via 58GTS ducts. Monitor stack radioactivity.~. .
- 2. Do not re-enter drywell until temperatures have ' returned to ,
normal. -
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- 3. De-energize all electrical circuits '.bef ore re-entering '
. _ . -drywell. -
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_ _ . . 4. Proceed per HNP-2-42OO. - 5 . ....l~ t I
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