ML20040E063
| ML20040E063 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 01/12/1982 |
| From: | GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20040E059 | List: |
| References | |
| PROC-820112, NUDOCS 8202030059 | |
| Download: ML20040E063 (600) | |
Text
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B6R16IION_EEDIECIIDN_BESEONSIBILIIIES A. EUEEDEE To delineate responsibilities of personnel at the Edwin I. Hatch ' Nuclear Plant (HNP) in regards to radiation protection procedures. O. B6016IlON_EBOIECIIQU_EBOGEad The primary objective of the HNP radiation protection program is to provide effective protection against exposure to radiation and radioactive materials for plant personnel, visitors, and the general ~ public. The protection measures are designed to effectively limi l- all exposures to as low as reasonably achievable levels and to comply with all requirements as specified in the United States Code of Federal Regulations, Title 10, Parts 19 and 20. C. REEEONSIBILIIIES
- 1. General 1
' Safety is each individual's responsibility. The radiation protection procedures provide guides, limits, and O recommendations to their responsibilities assist for all the personnel economical in and carrying safe out operation of the plant. Supplementary and revised procedures covering specific radiation protection subjects will be issued as needed.
- 2. Laboratory Staff
- a. Responsibility for the operation of the radiation protection (Health Physics) program is delegated to the l
laboratory staff and transfers to Shift Foreman in the i absence of the laboratory staff. This does not !' preclude the overall safety responsibility of the Plant l Manager. The laboratory staff consists of a Health Physics Superintendant, two or more Laboratory Supervisors, three or more Laboratory Foremen, and 20 or more Chemical Radiation Technicians.
- b. The principle responsibilities of_the laboratory staff are to: .
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See Page 1 2 of 3 p,_/ (1) Establish limits and standards for radiation protection, including permissible dose levels, contamination levels, and limits for the release of radioactive materials to the environment. (2) Recommend measures and procedures for dealing with actual and potential radiation hazards and to evaluate and report on the effectiveness ;F the radiation safety program. . (3) Provide consultation and other assistance- as required for the proper administration of the radiation safety program. (4) Perform effective monitoring and maintain adequate records of radiation exposure and contamination levels. (5) Recommend any individual's radiation exposure to cease when known .or estimated exposure is approaching allowable limits as set forth in 10 CFR 20. (6) Recommend curtailment of any or all operations when judged necessary to avoid exposure beyond () allowable limits set forth in 10 CFR 20. (7) Provide, calibrate, and maintain radiation detection and measurement instruments. (8) Periodically up date applicable plant procedures and retrain plant personnel in radiation protection measures.
- 3. Plant Supervisors Plant supervisors assist the laboratory staff in meeting the radiation protection program objective. Their principle responsibilities are to:
- a. Ensure that those under his direction are properly instructed in radiation problems associated with their duties and that they comply with all rules and 4, regulations governing radiation safety, en sd b. Ensure that all equipment and facilities are so f4f designed, installed and operate'd as to minimize the p
p-{ }' 'y*s hazards to personnel. x. 4/ 9 *8 < Q(fD,# d'a* % c. Know the location and extent of the radiation hazards in the areas under their jurisdiction and ensure that (*p?% all such areas are properly marked and controlled to d ("4 - limit exposure and the spread of radioactive ~ material.
. _ . _ _ _ MANUA!. S_ ET
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- d. Be informed of the exposure status of those for whom they are responsible.
- e. Consult with the laboratory staff on radiation protection matters.
- 4. Plant Personnel
- a. It is the responsibility of each individual to obey all radiation control procedures and r: port to his supervisor any circumstances where there are any doubts as to correct procedures or to the safety of the operation. Each individual working at the plant shall be required to demonstrate a working knowledge of the rules and procedures for radiation protection,
- b. The success of the program depends primarily on the cooperation end understanding of all plant personnel.
NOIE RADIATION SAFETY IS EVERYONE'S RESPONSIBILITY. Thus by its nature it shall be a cooperative effort involving every member of the plant organization. O
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RADIATION EXPOSURE LIMITS A. PURPOSE To provide limits of exposure for the protection of personnel i' against radiation hazards arising from work associated with the operation of the Hatch Nuclear Plant. The limits of exposure as set forth in this procedure are based ( i upon applicable limits as described in 10 CFR 20, Standards for Protection Against Radiation. A continuous effort will be m.ade ! i to reduce levels of rndiation and radioactivity in order to maintain radiation doses as 1cw as reasonably achievable below ! these established limits. l I B. MAXIMUM PERMISSIBLE EXPOSURE-(10 CFR 20) !,
- 1. The maximum quarterly exposure to the whole body, head and trunk, blood forming organs, and lens of the eyes shall be limited to 3,000 mrem / quarter. ~
- 2. The maximum quarterly exposure to the skin of the whole body shall be limited to 7,500 mrem / quarter.
- 3. The maximum quarterly exposure to the extremities, hands and forearms, feet and ankles, shall be limited to 18,750 mrem / quarter. .
NOTE All limits of exposure are based upon individuals 18 years of age and older. No person under 18 years of age shall be - occupationally exposed to ionizing radiation.
- 4. The limits as set forth above are subject to the following conditions: ,
- a. The dose to the whole body, when added to the accumulated occupational dose, shall not exceed 5(N-18) rem, where "N" equals the individual's age in years on his last birthday.
- b. The individual's accumulated occupational dose to the whole body has been determined and recorded on Form 1, ,
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- c. No individual will be permitted to receive a whole body ,
exposure in excess of 300 mrem / quarter unless he has submitted a signed statement indicating the amount of occupational exposure received during the current quarter from sources of radiation possessed or < controlled by other licensees and a reasonable effort to obtain the individuals prior occupational exposure has been made. In the event an individual is unable to provide exposure information for the current quarter, and his duties are likely to result in an exposure in excess of 300 mrem before such information could be obtained, authorization to 2500 mrem may be granted using Form 2 of this procedure, by the Plant Manager and the Health Physics Superintendent provided: (1) a current quarter exposure of 1250 mRen is assumed, (2) prior quarter exposures are known or have been calculated in accoraance with 10 CFR 20.102 (c) (1) , ar.d (3) the Plant Manager has declared the individual critical to start-up or continued operations. . C. MAXIMUM PERMISSIBLE CONCENTRATIONS IN AIR (10 CFR 20) No individual will be permitted to inhale a quantity of radioactive material in any period of one calen i quarter greater'than'the quantity which would result fron inhalation for 40 hours per week for 13 weeks at uniform concentrations of radioactive material in air as specified in Appendix B Table I, Column 1. If the radioactive materials are of such form that intake by absorption through the skin is likely, individual exposures to radioactive material shall be controlled so that the uptake of radioactive material by any organ from either inhalation or absorption or both routes of intake in any calendar quarter does not exceed that which would result from inhaling such radioactive material for 40 hours per week for 13 weeks at uniform concentrations specified in Appendix B Table 1, Column 1 of 10 CFR 20. Refer to 10 CFR 20. 103 for further details. ! D. ADMINISTRATIVE EXPOSURE GUIDES
- 1. Administrative exposure guides are established to provide guidelines for plant operations in order that personnel exposures will be maintained within the maximum limits as established in 10 CFR 20 and Section B of this procedure.
- 2. Exposure of the whole body shall be limited to 300 mrem / week. This administrative limit, however does not relieve the individual or his supervisor from their responsibliity to keep all radiation exposure as low as reasonably achievable ( ALARA) .
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- 3. Whole body radiation exposure above 300 mrem in any week will require written approval from the immediate supervisor and a Lab Foreman on Form 2, Authorization to Exceed Administrative Exposure Guides.
- 4. Exposure of the whole body shall be limited to 1,250 mrem / quarter.
- 5. .Whole body radiation exposure above 1,250 mrem / quarter will require written approval from the immediate supervisor and a Lab Foreman on Form 2, Authorization to Exceed Administratiave Exposure Guides. In no case, except for conditions as specified in Section G, shall a whole body exposure exceed 2500 mrem / quarter as measured by pocket dosimeter or estimated by portable Health Physics instruments.
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- 6. All female employees working in the Protected Area will be required to acknowledge in writing that she has received instruction concerning prenatal radiation exposure on Form 4.
For purposes of administering a program for. limiting exposure to pregnant women, the following administrative guides will be established: Radiation exposure to female employees will be limited to 500 mrem per two month period unless a higher limit is specifically requested in writing by the employee on Form.4. Radiation exposure to pregnant women will be limited to 500 mrem during the entire gestation period unless a higher limit is specifically requested in writing by the employee on Form 4. E. ADMINISTRATIVE CONTROL OF INTERNAL EXPOSURE
- 1. Exposure to airborne concentrations approaching the MPC's of 10 CFR 20 should be prevented. If exposure above the MPC's are necessary, the rearing of properly fitted re itatory protectiveequipmentorotherappropriatemetho'dgwillbe o required as determined by the Health Physics staff.
HNP-8010 specifies administrative controls for use of respiratory equipment.
- 2. Plant personnel normally traversing Radiation Control Areas should have a whole body count annually.
F. EXPOSURE LIMITS FOR NON-PLANT PERSONNEL
- 1. Vendors, subcontractors, and other non-plant personnel who are likely to receive a whole body radiation exposure in excess of 300 mrem in any calendar quarter shall be required to furnish current radiation. exposure. records.
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- 2. The quarterly exposure to the whole body shall be limited to 1,250 mrem. Any occupational exposure received at another
- facility during the current quarter (whether actual, based on TLD or film badge results, or estimatede based on pocket dosimeter results, or a combination thereof) shall be considered in the maintenance of this limit. However, if mutual agreement between Georgia Power Company and the pertinent outside organization exists, and provided that the requirements of 10 CFR 20, Section 20.101 have been satisfied, this limit may be exceeded. Refer to Form 2, Authorization to Exceed Radiation Exposure Guides.
Subcontractor personnel must have received the Radiation Protection Orientation lectures or demonstrate knowledge covered in the lectures, and must agree to abide by the regulations and policies of the Georiga Power Company prior to gaining access without escort to areas where radiation exposures may be received. G. EMERGENCY AND ACCIDENTAL EXPOSURE Although an emergency situation transcends the normal requirements of limiting exposure, there are suggested levels for exposure. Refer to HNP-4812 for guidance. H. ABNORMAL PERSONNEL EXPOSURES
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Whenever a situation occurs involving the suspected or known exposure of personnel to ionizing radiation in excess of 10 CFR 20 limits specified in this procedure, the_ incident will be promptly investigated and personnel exposur's e evaluated. Personnel monitoring results that are either excessively high or" excessively low with respect to the work that an individual has been known to be doing, will also be immediately investigated. . All such incidents will be immediately reported to the H.P. Laboratory Foreman or his alternate. A committee consisting of the Laboratory Foreman, Health Physics Superintendent or his designee, and supervisor of the group in which the abnormal l exposure occurred, will conduct an official investigation and issue a written report of its findings and recommendations to the concerned individual, his immediate supervisor and the Plant Manager. Every effort will be made to determine if the suspected exposure is actual exposure using, as necessary, special bio-assays, whole body counting, radiation surveys, and reviews of work assignments and working procedures. The written report submitted will consist of the investigation, the evaruation of results documented on Form 3, Abnormal Radiation Exposure, and a Radiation Occurrence R? port (Figure 2 HNP-800 5) . huL;,;aLL U.ll T MANUAL SET
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I. RELATIVE BIOLOGICAL EFFECTIVENESS (R.B.E.) OR QUALITY FACTOR [ (O.F.) R.B.E. OR Q.F. VALUE* TYPE OF RADIATION 1 l X-ray, Beta, Gamma 5 ) Neutrons, Thermal 10 i' Neutrons, Fast 20 Alpha and Heavy Particles l l 4 1
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OCCUPATIONAL EXTERNAL RADIATION EXPOSURE HISTORY , 4 I roRM 1 , t OCCUPATIONAL EXTERNAL RADIATION EXPOSURE HISTORY M AME (PRINT-LAST, FIRST, AND MIDDLE) 2. SOCIAL SECURITY NO.
- 3. DATE OF BIRTH (MONTH, DAY, YEAR) 4. AGE IN FULL YEARS (N)
OCCUPATIONAL EXPOSURE - PREVIOUS HISTORY l 2REVIO_US DOSE HISTORY
- 9. RECORD
- 5. PREVIOUS EMPLOYMENTS 6. DATES OF 7. PERIODS OF]8. WHOLE BODY OR CAL-EMPLOYMENTS INVOLVING EMPLOY- EXPOSURE MENT (REM) CULATED RADIATION EXPOSURE - (INSERT LIST NAME AND ADDRESS (FROM-TO)
ONE) OF EMPLOYER e LO. REMARKS 11. ACCUMULATED OCCUPATIONAL DOSE-TOTAL
' DATE NET DOSE (CIRCLE ONE)
DJRRENT OUARTER ESTIMATED / RECORD EXPOSURE FROM TO (mrem) YES l NO
- 13. CALCULATIONS - PERMISSIBLE DOSE 12. CERTIFICATION: I l CERTIFY THAT THE EXPO-l WHOLE BODY:
SURE HISTORY LISTED IN i COLUMNS 5, 6, & 7 IS CORRECT & COMPLETE TO (A) PERMISSIBLE ACCUMULATED DOSE = 5(N-18) THE BEST OF MY KNOW-
= REM (B) TOTAL EXPCSURE TO DATP, (FROM ITEM 11) LEDGE AND BELIEF.
REM (C) UNUSED PART OF PERMISSIBLE ACCUMULATED EMPLOYEE SIGNATURE DOSE ( A - B) ' = REM DATE 14,
- NAME OF LICENSEE HHP-8002 RO9
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IS AITTHORI*ED TO RECEIVE AN TO THE FOR EXPOSURE OF TO THE PERIOD i e EMPI4YEE'S CURRENY EXPOSURE IS: QUARTERLY WEEKLY e i REASON FOR EXPOSURE IN EXCESS OF GUIDE LIMITS IS: DATE APPROVALS EMPLOYEE EMPLOYEE'S SUPERVISOR LABORATORY SUPERVISOR O I e G HNP-8002 RO9
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FIGURE 3 FORM 3 ABNORMAL RADIATION EXPOSURE { l FORM 3 ABNORMAL RADIATION EXPOSURE DATE l INCIDEfff NO. 6 NAME DEPT. l JOB TITLE SUPV. IN CHARGE INVESTICATION DATA DATE AND TIME OF INCIDENT I4 CATION NATURE OF INCIDENT j. PROBABLE CAUSE SURVEY INFORMATION RECOMMENDATIONS COMPLETED BY DATE TLD BADGE READING PROBABLE ACTUAL DOSE DOSIMETER READING "I CERTIFY THAT THE ABOVE INFORMATION IS ACCURATE TO THE BEST OF MY KNOWLEDGE". SIGNATURE OF MAN EXPOSED SICNATURE OF SUPERVISOR SIGNATURE OF LAB SUPERVISOR / FOREMAN
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FIGURE 4 FORM 4 l RADIATION EXPOSOT.E LIMITS FOR FEMALES FORM 4 RADIATION EXPOSURE LIMITS FOR FEMALES A. I have received oral and written instructions concerning prenatal radiation exposure. I have read the Appendix to Regulatory Guide r 8.13, "Fossible Risks To Children Of Women Who Are Exposed To Radiation During Pregnancy". , 1
/ / l SIGNATURE DATE ,
i B. I request that my radiation exposure be limited to the following: ,
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- 1. Same as for male workers.
Limits as specified in Sections B and Para. D.1 - D.5 of RNP-8002 SIGNATURE DATE / / EB
- 2. Limits as specified in Para. D.6. of HNP-8002 1.e., 500 mrem l
per two month period. For pregnant women, limit of 500 mrem for the entire gestation period. SIGNATURE DATE / / 4 l . l 1 HNP-8002 RO9 t l MANUAL SET
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1 ,, s RADIATION CONTROL _ARFA CLASSIFICATIOrjS PURPOSE A. To classify areas within the Protected Area for the purpose of ' controlling access to minimize radiation exposure and radioactive contamination. Movement of personnel into and within the plant is controlled to minimize the exposure to radiation'and to prevent inadvertent entry into areas where radiation levels are high. B. REFERENCES Code of Federal Regulations 10 CFR 20. C. RADIATION CONTROL AREA _ S A Radiation Control Area is any area within the Primary Protected Area in which radioactive materials and radiation are present in quantities sufficient to require protective measures. Each Radiation Control Area is classified as a Radiation Area, High j Radiation Area, Contaminated Area, Airborne Area, and/or , Radioactive Material Area. The basic entry requirements are the wearing of the TLD badge, self-reading dosimeters and appropriate protective clothing, if required, by all individuals. Entry to ! and exit from Radiation Control Areas for individuals, shall be through designated access control points only. There will be no eating, drinking, or smoking in any Radiation Control Area. D. RADIATION AREA
- 1. A Radiation Area is a Radiation Control Area in which the radiation level to the whole body is greater than 2.5 .
mrem /hr but less than 100 mrem /hr or which a person could , receive a whole body dose of 100 mrem in five (5) g consecutive days.
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j 2. Each Radiation Area shall be conspicuously posted with a : sign or signs bearing the radiation caution symbol and the words below. Also see Section L. i j (; CAUTION OR DANGER
, RADIATION AREA RADIATION AREA l'
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- 3. Radiatic,n Areas are entered only when necessary to perf orm a specific job. When radiation areas are entered, the time [
spent in these areas should be kept to a minimum, especially in areas in which the radiation level is near the high end of the 2.5 to 100 mrem /hr range. E. IJIGH RAD MTION AREA
- 1. A High Radiation Area in a Qufiation Control Area in which the radiation level to the G ole body is greater than 100 mrem /hr.
- 2. Each High Radiation Area shall be conspicuously posted with j a sign or signs bearing the radiation caution symbol and the ,
words below. Also see Section L. s CAUTION OR DANGER HIGH RADIATION AREA HIGH RADIATION AREA
- 3. Each High Radiation Area in which the intensity of radiation is greater than 100 v '=d'.. Nt less than 1000 mrem /hr shall be barricaded and ccaq ' v: . ly posted as a High Radiation
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Area. Entrance to a High Radiation Area shall be controlled f by issuance of a Radiation Work Permit per HNP-8008. l ' l i NOTE ' f Health Physics personnel, or personnel escorted by Health ! Physics personnel in accordance with approved gmergancy f procedures, shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties, provided they comply with i approved radiation protection procedures for entry into high radiation areas. p.- Any individual or group-of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following.
- a. A radiation monitoring device which continuously indicates radiation dose rate in the area.
- b. A radiation monitoring device which continuously integrates the radiction dose rate in the area and alarms when a preset integrated dose is received.
Entry into such areas with this monitoring device may be made nFter +w. h e rate level in the area has been o n 01 have been made knowledgeable established ane ;. of them. REFERENCE
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- c. An individual qualified in radiation protection procedures who is equipped with a radiation dose rate 4 monitoring device. This individual shall be ,
responsible for providing positive control over the j activities within the area and shall perform periodic radiation surveillance at the frequency specified by the Laboratory Supervisor or his designee in the Radiation Work Permit. . Each High Radiation Area in which the intensity of radiation is greater than 1000 mrem /hr shall be subject to the above, and in addition locked doors shall be provided to prevent unauthorized entry into such areas. The keys shall be maintained under administrative control of a Laboratory Foreman. (Operations Department has a master key, however) s F. ROPED AREAS If process conditions create a temporary Radiation Control Area, the area is normally designated by roping it off with yellow and f magenta rope or tape and posting it with the appropriate sigp or signs. G. AIRBORNE RADTOACTIVITY AREA
- 1. An Airborne Radioactivity Area is a Radiation Control Area in which airborne radioactive material exists in concentrations in excess of the amounts specified in Appendix G, Table I, Column 1 of 10 CFR 20, or in which concentrations exist which, averaged over the number of hours in any one week during which individuals are in the area, exceed 25% of these values. >
- 2. Each Airborne Radioactivity Area shall be conspicuously posted with a sign or signs bearing the radiation caution symbol and the words below: (Also see Section L)
CAUTION OR DANGER i AIRDORNE RADIOACTIVITY AREA AIRBORNE RADIOACTIVE AREA H. RADI__OACTIVE MATFRIAL ARFA
- 1. A Radioactive Material Area is a Radiation Control Area in which licensed material is used or stored and which contains any radioactive material (other than natural uranium or thorium),in an amount exceeding 10 times those given in Appendix C of,10 CFR 20.
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- 2. Each Radioactive Material Area shall be conspicuously posted ,
with a sign or signs bearing the radiation caution symbol and the words below: (Also see Section L) CAUTION OR DANGER RADIOACTIVE MATERIALS RADIOACTIVE MATERIALS I. RADIOACTIVE __MATFRIA L CONTAItjERS Each container in which radioactive materials (other than natural uranium or thorium) is transported, stored or used in quantities exceeding those given in Appendix C of 10 CFR 20 shall bear a durable clearly visible label bearing the radiation caution i symbol and the words below: (Also see Section L) CAUTION OR DANGER RADIOACTIVE MATERIALS RADIOACTIVE MATERIALS h. J. CONTAMINATED AREA
- 1. A Contaminated Area is a Radiation Contral Area where
- surface contamination levels exceed the limits as specsfied below:
- a. Smearable surface radioactive contamination 2
Beta-Gamma 1000 dpm/100 cm 2 Alpha 50 dpm/100 cm
- b. Fixed surface radioactive contamination Beta-Gamma 100 cpm /G.M. probe area Alpha 50 dpm/ detector area
- 2. Each Contaminated Area shall be conspicuously posted with a sign or signs bearing the radiation caution symbol and the words below: (Also see Section L)
CAUTION OR DANGER CONTAMINATED AREA CONTAMINATED AREA
- 3. Access control points to contaminated areas will be provided with step-off pads and, when practical, with at least one RM-14 or E-120 with an HP-210 probe attached.
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NOTE . lJhere radiation levels are too high for personnel contamination survey, wo r):e r s ,~wi l l be instructed to remove protective clothing at the' step-off pad (s) and proceed to the nearest RM-14 or E-120 for a whole body l frisk. , s N. RADIATION _CAUTIQ'l SYMOOL s xi f s. Except as otherwisp authorized by the'N.R.C. symbols prescribed by this procedure shall use the conventional radiation caution colors, magenta or purple on yellow background. The symbol prescribed by this procedure is the conventional three-t#1aded design. *
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(1) Cross-hatched area is magenta or purple. (2) Background is yellow. (3) Wording.may employ black or magenta letters. L. ADDITIONAL INFORMATION_ POSTED In addition to the contents of the signs described above,
- additional information which may be appropriate in aiding individuals to min,imize exposure to radiation may be provided on or near such signs.
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- PERSONNEL DOSIMETRY PROGRAM A. PURPOSE .
To 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. REFERENCES Code of Federal Regulations, 10CFR20 A.P.T. Computer Exposure Records System C. DESCRIPTION OF DOSIMETRY EQUIPMENT V
- 1. Thermoluminescent Dosimeter (TLD Badge)
The TLD Badge is a small badge containing two or more lithium fluoride TLD chip. 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 d
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badge vendor will read and evaluate the badges and report ( the results to the Health Physics / Laboratory Foreman. The record of accumulated external radiation esposure received by individuals is obtained principally from the interpretation of the TLD badge. ; 1 \
- 2. Direct reading pocket dosimeter 4 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 d 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 D7simetry The' Health 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 requenting that tne 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.l. , e
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- 4. Other As deemed appropriate the Health Physics staff will issue other personnel monitoring devices, i.e. finger rings, neutron pocket chambers, chirpers, etc. for monitoring personnel radiation exposure.
D. ISSUANCE OF TLD BADGES AND POCKET DOSIMETERS e
- 1. Prior to issuance on any TLD badge or dosimeter Form 1, TLD BADGE AND DOSIMETER ISSUE must be completed. See Section G.
for details. f
- 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 made 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. i Daily dosimeter reading will be logge6 as in Section G. NOTE . i
)
Dosimeters that have been used, and then placed in the "OUT" , rack, will be re-zeroed prior 0 to the start of the next work l day, if a reading of 40 mrem, l or greater, has been reached. lg l E. WEARING AND USE OF TLD BADGE AND DOSIMETER The TLD Badge and dosimeter are to be worn adjacent to each other b between the waist and neck on the~ front part of the body. As per l: 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 breast pocket (Outside pocket) of the coveralls and pocket closed. The TLD badge shall always be worn with the face of the badge facing out. It is required that each individual 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 Health Physics s REFERENCE ONLY mailual set
Nb Y ~~~ E. I. HATCH NUCLEAR PLANT HNP-8004 See Page 1
- ve> w o^'= 12 See Page 1 3 of 19
..- Staff. The loss of any personnel monitoring device requires the immediate notification to the Health Physics staff.
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 EXTREMITY DOSIMETRY 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 extremity dosimetry are as follows:
- a. When the extremity exposure rate is likely to be four g times 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 performing 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 h 1
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. Fotm 5, Finger Ring Iss':a 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: 1 REFERENCE CULY a
E. . 1
- -n -
HNP-8004 h E. I. HATCH NUCLEAR PLANT j See Page 1
- m** w ;
o.n 12 i See Page 1 4 of 19
- 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. - I
- 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 Keutron dose rate: 30 mR/hr Dosimeter reading: 80 mR/hr (2) Neutron-to-gamma ratio: 30/60 = 0.5 (3) Estimated neutron dose: (80 mR) (0.5) = 4 0 mR (4) Total.whole body dose: 8.0 mR + 40 mR = 120 mR !
- e. Input the total whole body dose to the computer via DDUDAT Program or use Form 2 of this procedure if the computer is disabled. .
]
H. RADIATION PROTECTION ORIENTATION { All new employees shall receive a radiation protection orientation prior to their acaignment of work in Radiation Control Areas or have an escort by someone who has demonstrated understanding of radiation protection practices and procedures. , See HNP-8018. 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 radiation exposure or contamination. Each employee will be required to demonstrate an understanding of these procedures prior to being allowed to enter a Radiation Control f Area unescorted. I. PERSONNEL DOSIMETRY RECORDS
- 1. Form 1, TLD Badge and Dosimeter Issue
- a. The preparation of this form is the responsibility of I the Health Physics Department. The purpose of the form '
is to record all information required by 10CFR20 for personnel wearing monitorin,g devices.
, ," b. Procedure for recording information on Form 1.
REFERENCE'ONLY manual Set I
-y
-ao* .aoctovao.o E. l. HATCH NUCLEAR PLANT HNP-8004 See Page 1 - anve.o are 12 See Page 1 5 of 19 (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. !
- 4 (3) The form shall be filed and maintained in the dosimetry office until termination.
(4) Upon termination and completion of accumulated dose report, file will be moved to documentation.
- 2. Form 2, Weekly Pocket Dosimeter Record I
- a. This form provides a means for recording personnel i 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.9 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. , i (3) .The individual whose name appears on Form 2 will ' record or have recorded his dosimeter re& ding on entering the operating buildings (IN BLOCK) and on exiting the operating buildings (OUT BLOCK) at the end of the work day. It will then be calculate or I have calculated the indicated exposure by - determining the difference between the IN and OUT 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 QTR block at the beginning of each week. (5) The Health Physics staff will determine total ! daily exposure by adjusting the indicated exposure i with exposures determined from Form 3, Dosimeter f Re-zero Record and other methods as necessary. i These adjustments will be logged in the ADJ. block and will be added to the NET exposure to determine
, REFERENT ONI.Y manual set I
~. _ ~ ~ ~o E. l. HATCH NUCLEAR PLANT HNP-8004 See Page 1 * *'5*" "o See Page 1 6 of 19
- v. .
the total exposure for th day and recorded in the TOT, block. . (6) The Health Physics staff will determine the accumulated weekly exposure for each individual by summing the TOT block for the day and the WK block for the previous day, except for Saturday, where the WK exposure will equal the Saturday TOT . exposur?.g c.,. (7) The Health Physics staff will adjust the quarterly (QTR) exposures to 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-zeroed while within the operating buildings. DDUDAT cards may be used in lieu of Form 3. The form will be located at each dosime.ter charger' station. It shall also be used when zeroiny mpecial 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 Occupational 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 computer exposure record system on a monthly basis or with greata"f requency, as this data is provided by the vendor. Current NRC Form 5 information may be obtained from the computer system at any time on an individual or departmental basis by using the INDDRP or the DDLIST program respectively. ,
- 5. Form 4 Replacement Exposure for Lost or Damaged TLD Badge 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 i entered on the Current TLD Occupational Radiation Exposure I Report through the use of a lett;er to the TLD vendor as shown in Figure 3 and into the computer exposure record l system. - REFERENCE ONI.Y mailltal set _ s
6 WPHOV4 PROCIOUHk NO E. l. HATCH NUCLEAR PLANT HNP-8004 See Page 1 aivuw =0 om 12 See Page 1 @ 7 of 19 ,
~
- 6. Form 5, Finger Ring Issue Log Form 5 will be filled out as needed and completed by the end of each month. The extremity dcsimeters 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. Figure 1, Request for Employee's Previous Radiation Exposure A letter shall be written to an employee's previous employer (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 Figure 1, Request for Previous Radiation Expc sure.
- 8. Figure 2, 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 exposure of the q~ individual has been determined, whichever is later. The report shall cover each calendar quarter of the individual's i l time within the Protected Area involving exposure to i radiation or such lesser period as may be requested. The report shall be provided on Georgia Power stationary and in F the general format as shown on Figure 2, Former Employee and } Visitor Radiation Exposure Report. When an individual terminates employment or an individual ,I assigned to work in Radiation Control Areas at the Hatch ( Nuclear Plant, but not employed by Georgia Power, completes his work assignment the individual and the Nuclear l1 ' Regulatory Commission will receive a report on his exposure to radiation and radioactive material incurred during the l l period of employment or work assignment. Such report shall , ) be funished within 30 days after the exposure of the , l individual has been determined or 90 days after the date of termination of employment or work assignment, whichever is I earlier. The report shall be provided on Georgia Power stationary and in the general format as shown on Figure 2, Former Employee and Visitor Radiation Exposure Report. The original report may be obtained by accessing the computer , , exposure record system using the TERMN8 program, or from the Current TLD Occupational Radiation Exposure Report (para, j
, I.4). ,
e
" " malmal Set REFERENCE ONI.Y . - -
y
., om - ,.o E.1. HATCH NUCLEAR PLANT HNP -8004 See Page 1 atv m [
om 12 - See Page 1 8 of 19 e
- 9. Computerized Personnel Exposure Records
- a. A computer for up-dating-personnel exposure data on a day to day basis has been developed. Pocket dosimeters i are read daily 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 life time exposure information is made available to the Health Physic staff, plant supervision, and the individual through the use of l various computer printout formats. .See APT Automated j Personnel Dosimetry Records System Manual. j
- 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 j basis. Entries will be recorded by the computer f on a daily basis using the,DDUDAT [ program. Where dosimeters are re-zerced
*' in the Primary Protected Area, the dose l recorded on Form 3 shall also be entered i into the computer using the DDUDAT program.
(2) Weekly - A listing of daily exposures for all j personnel on site for each day of the
--. week will be obtained at the end of each :
i week using the DDPRNT program. (3) Monthly - The net dose indicated for each worker . listed in the " Time Record" section of l all Radiation Work Permits issue during a given month shall be entered into the computer exposure record system prior to l entry of the TLD data for the respective [ period, using the CWPUDT program. TLD : data will be entered into the computer l exposure record system each month using i the CLDUDT program as thi.s information g is provided by the vendor. Corrective , or supplemental TLD data may be entered r into the computer exposure record system r using the HLDUDT program. Data files will be removed'from the ;
. TMPDOS exposure record file each month
- for personnel terminating their stay at
- REFERENCE ONLY Manuals 0t
sf m% muctovat no l E. I. HATCH NUCLEAR PLANT HNP-8004 J See Page 1 ataca ~o I om 12 See Page 1 9 of 19 the plant whose final TLD data has been , provided by the vendor. The TERMN8 l-program will be used to accomplish this [ and will produce the original letter of g notification of exposure for the U individual, as well as a copy of his final dosimetry file contents. (4) Annual - 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
' 10CFR20 annual reporting requirements !;
will be provided by the program after h the exposure information for an entire 'j year has been recorded. (5)As required The PDFMAK program is utilized to enter a new personnel information into the computer exposure records, to add identification or prior exposure information.
- 9
*- The DELETE program is used to transfer a f 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. 4 The HLDUDT program allows the entry of j TLD information for individuals at times , other than the regular monthly entry of I TLD data on a plant basis. h 1 The individual dose reports covering all l 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 INDDRP program supplies for a particular individual. Whenever required, particularly during e an outage, the DDPRNT program may be l utilized to obtain a listing of dose for I each day of the current week and the
,. ~
margin between the cummulative exposure I and the most restrictive exposure limit, l
. for each person on site.
s REFEPENCE ONLY manual set
- -m%
E. I. HATCH NUCLEAR PLANT HNP-8004 See Page 1 e** un 12 See Page 1 10 of 19 The Applied Physical Technology Autonated Personnel Dosimetry System Instruction Manual may be referenced for information on organization of data files and operation of programs.
- 10. Figure 4, Reply to Request for Previous Radiation Exposure When a request is received by Georgia Power Compan from a previous employee or visitor for the purpose of prr-viding his new employer (or facility being visited while .n the employment of his new employer) with a record of cccupational radiation exposure received at Plant Hatch, Figure 4, Reply to Request for Previous Radiation Exposure, shall be used to supply this information.
J. MANAGEMENT REVIEW OF RADIATION EXPOSURE DATA The H.P. Superintendent will be responsible for preparing a Radiation Exposure Report for the management meeting. As a minimum, the report will consist of a tabulation of exposures by department, including the average dose received per worker and the maximum dose. Also to be included will be a tabulation of
, exposures on specific maintenance work during the month, if significant work has been performed. Othe~r significant exposure information will be discussed during the meeting as appropriate.
Weekly updates of personnel exposure are provided to each department. These records provide supervisors as well as workers , information on radiation exposure accumulation and will aid in d minimizing exposure to individuals by more efficient worker utilization. 4 2 <
. .y REFEREIKE ONI.Y magggl Set
~ ---
E. l. HATCH NUCLEAR PLANT HNP-8004 See Page 1 nev e w oa's 12 See Page 1 11 og 19 FORM 1
~~
FORM 1 l TLD BADGE A'4D 00SIVETER ISSUE DATE: 1.D. BADCE NO. NAME IN FULL (PRINT) FIRST MIDDLE LAST , SOCIAL SECURITY NO. BIRTH DATE: MONTH DAY VEAR HOME ADORESS: HOME PHONE: STREET f
; GITY STATE ZIF I
.J05 CATEGORY INTRA. PLANT DEPT. COMPANY -
SUPERVISOR & ENGINEERING C3 GA. POWER CO. PLANT HATCH Q OFFICE STAFF p MINT. MECH. O GA. POWER COMPANY O ; ENGINEERING STAFF Q MAINT. ELECT. O SOUTHERN SERVICES INC. O
- OTHER O TEST CEPT. O
- CONTRACTOR O
- PLEASE DESCRIBE
. OPERATIONS O
- OTHER O
- LABORATORY O
- GIVE NAME OF COMPANY:
OFFICE O i Have you worked at or visited a f;uclear Facility within me it.st three months? SIGNATURE YES NC If visitor, escort's nare TLD Badge No. NRC Fom 4 completed Dosimeter No. Authorized Quarterly Exposure mrem
- Dosimeter Readin9 Issued By Reviewed By
*If current quarter esposure is unknown, limit is 312 mrem.
~
HNP.8004 A012 I I REFERENCE ONLY
, mailual Set b lL
e " ****M** PHQCggyRt No E. I. HATCH NUCLEAR PLANT HNP-8004 } See Page 1 , , , , _ See Page 1 Georgia Power A ~~ 12 of 19 FORM 2 FORM 2 WEEKLY P0CKET 00!It'ETER RECORD Color of Badge , Type o' Personnel Dates: . 19 thru . 19 TLDcr20l SUNDAY M0!.0AY TUESCAY EONESCAY THURSOAY FRICAY tadce t;o. NAME C00E SATUROAY l' A3) . OTR CUT TOT tE T t 'v. 1:1 A D) . j l0TR _.Q9T TOT f I f:ET JM l *l A03, j' i CtlT TCT i jul, - - 0 _09T ini f:F T t?". 1 *1 }C1 l GiR __ C'!T TOL 1 t'FT J'*
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. REFERENCE ONLy mailual set l l
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APPHQyA( PHOCtDuHt W E. l. HATCH NUCLEAR PLANT HNP-8004
- See Page 1 Ht. s.0,, %
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see Page 1 13 of 19 FORM 3 . i ' '
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DO5! METER RE-ZERO RECORD DOS! METER READING AFTER ZERO
- 5. BEFORE ZERO I'
I r l I . < l HNP-8004 R012 J,
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- - -- -- -- - - _ _ ~
- m. -
Pf(X2DyHt peQ ePMeQv L E. l. HATCH NUCLEAR PLANT HNP-8004 See Page 1 at mo. % oare 12 Georgia Power ~~ See Page 1 0 14 of 19 FORM 4 MPt.Act! TNT tros"RE FOR LOST OR DMtActD TLD B A.0CE_ . af
. l Date: 1.D. Badge No.t_.
Names Tim Badge No.t 'j Soc. Sec. No.I For period from to l TIA Badga was: Lost .Dasagad Other - l Samarks: Focket dosiceter reading. recorded during periodt Dste Dose reeerded (er) Source of data 1 m Total estimated maximun exposure received during the period Seearks:
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15 of 19 FORM 5 - FINGER RING ISSUE LOG 4 FINGER SUE LOG , MONTHr NAME TLD 4 BADGE # DATE OF ISSUE REMARKS I5 SUED BY
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y APPHQVAL PROCEDURL PeQ E. I. HATCH NUCLEAR PLANT HNP-8004 ' ; See Page 1 wa ww. .so oAri 12 See Page 1 16 of 19 i FIGURE 1 REQUEST FOR PREVIOUS RADIATION EXPOSURE. . 1
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go tu ica n e,.,pians bhilNW re nween touc :,re.n DLTE: i Subjects Radiation Exposure Record Centlement The following Individus1 has indicat'ed that he received radiation eroosure ville working for your o sani.tstion. We would aooreciate P receivina costes of you= exoosure recor1s for this emo'ovne. Name'of Emp1 oven SS/Mo _ _ _ __ _ _ Dates e (From) 7To)
- Tory trette ynuag.
4 Lahowetory foremsn I hereby authorise the release of the above info =mation.
~ ~ ~ISignature of EmployeeT (Oste) r
- 1,
#0U0IS0t 1
REFEREHCE ONLY l
Y I ~ APPHQvAL E. l. HATCH NUCLEAR PLANT HNP-8004 See Page 1 , om ~
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See Page 1 Georb i
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ADD!!ESS: . ,
* . DATE OF BIRTil: . .
.SUDJECT: R ADI ATIO:t EkP00U$E REPottT ,
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, DEAR SIR: , ,
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- PLEASE EE ADVIIED TH AT "!!ILT. E!! PLOT?.D 05 VISITI!!G AT THE EDt!III II ATCil flCCL'l:A3 PLA':T DU2I :C TP.E TOLLO*41"!G WO3% PERIO:XS), TOU RECCIYED ,
Tl!E FOLLo*Ji%C EI:'OSU::E TO ID::IZII;C R ADI ATIOu. P. DAY.:S.1 0i T:..:Z:1 nECL2MO E:: 03 U ?. 5 ( s ?.7 ) a
'FROM - TC '.fi' OLE 50DT strif EITRiff1 TIE 0 e
. e i IIPCS321 DE*iERMINED BY TLD B ADCZ Ut:LESS OTHER*4ISE NOTI:D
' BEHA;:ES B,IO-A33 AT RELULTS:
71I13 .ft EI'OX T IS t*'J't!!I:;3 3") TO TC'J Ul:D*;3 Ti!E PSO','I310:!O OF Tit t liUCLEAR REGULt.T03T CD:::lI5510:* nnocLATIO:! t o CF*t PAET 19 T LU S!!OU LD Pa t:SCE 't?. T515 R1:PCitT .70n fil3 Til:3 :t Zr EM E!ir E . *
, t iTJiWoHTMETG5a IC: tiTc tCTCs, MA:: ACE ! . rT i.::o Proc:1 A:s A:: ALT ts , .
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- 1 APrHQv4 PROGkUUH4 M)
'~ E. l. HATCH NUCLEAR PLANT HNP-8004 [
See Page 1 aeve m) om 12 3 see Page 1 O@a Power 1, ,, 1, FIGURE 3 . Wo,'M.9;7'"' L7 4 T..ar #m .'L, m Edwin L hah belear mas CCOgii:Ptynty . ev e.s.- ... s.>- Eberline Instrument Corporation P. O. Box 2108 Santa Fe, New Mexico 87501 Attention: Dosimetry Services Centlement f The Georgia Power Company Plant E. I. Hatch TLD Occupational Radiation Exposure 9eport does (or will) not reflect exposure received by the following person for the indicated period because of lot's or damaged TLD badge. Based on plant exposure records, we estimate the individual's exposure to bet TLD NO NAME S.S. 50. DATES C07ERED EST . E X P O S'J R E fREM) From: W.B. skin Est Tot $ Please adjust this individual's record to reflect the above [ estimated exposure. V Tours truly, 4 Realth Physics j een Individual's File I.
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x REFEllEHCE ONLY MBBU8ISet
o 7. a d I A' 1 APPHOV-4 PHQCEDUHL NQ E. l. HATCH NUCLEAR PLANT HNP-8004 , See Page 1 Heveo= ~o oArt 12 See Page 1 @ 19 of 19 FIGURE 4 .
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SUBJECT:
RADIATION EXPOSURE REPORT I DEAR SIR: S. S. NO. 'i RECORD OF REQUESTED BY 15 PROVIDED BELOW: , DATES MONITORED RECOR DLD EXPOSURE tREM)
- FROM TO WHOLE BODY SKIN EXTREMITIES i
L
- EXPOSURE DETERMINED BY TLD BADGE UNLESS OTHERWISE NOTED.
REMARKS BIO. ASSAY RESULTS l
~
l I I. m o REFERENCE ONI.y manual set
3 7 E. l. Hatch Nucinar Plant
~== =crouas ~o HNP- 8005 gl gg navision so f- o..< Georgia Power b ..-
/~ $l 1 of 22 RADIATION AND CONTAMINATION CONTROL A. PURPOSE To outline the procedures which will be used by Health Physics ;
personnel and by all plant personnel t o" ensure that potential i radiation hazards are adequately defined, that adequate controls l are instituted so that radiation exposure to personnel working in Radiation Control Areas or working with radioactive materials is minimized, and that each person carries out his work in a radiologically safe and economical manner. B. GENERAL MONITORING
- 1. External radiation measurement. <
- a. All individuals entering a Radiation Control Area are required to wear a TLD badge and pocket dosimeter at )
all times. A record of accumulated external radiation I exposure received is obtained principally from the t interpretation of the TLD badge. Direct reading pocket , dosimeters provide an "on-the-spot" reading for the i individual.
- b. Radiation Control Areas within the Primary Protective Area a,r e classified and identified as to levels of N radiation and for contamination. Strict procedures will be enforced for access to these areas.
- c. There are numerous area radiation monitors located '
throughout the plant which alert personnel to abnormal radiation levels.
- d. In addition to the measurements made by the area radiation monitors, the measurement of external dose 1 rates is accomplished by portable survey instruments. )
The operation of survey instruments will be in I accordance with the operating instructions outlined in each particular instrument procedure. Instruments
' covering high, intermediate, and low ranges are ^
available in the plant and in emergency kits. A
- 2. Loose surface contamination nieasurement {
- a. In Radiation Control Areas loose surface c'ontamination is normally determined by wiping a disc smear over a 100 square centimeter area of the surface being a R52TCE ONI.Y mailual set
a == E. l. Hatch Nucicar Picnt aaoctova< ~o HNP- 8 0 0 5 Sao Pago 1 REWSCN ho 11 om Georgia Power n . - ~o See Page 1 2 of 22 monitored. Detailed procedures for contamination surveys are found in HNP.-8012, SURFACE RADIOACTIVE CONTAMINATION SURVEYS. The smear is then counted using a beta-gamma (G-M) count rate meter. Alpha activity of a smear is determined by means of a gas proportional detector.
- b. In areas not normally expected to be contaminated, the loose surface contamination will be determined by wiping a disc smear over a 100 square centimeter area and counting the smear in the laboratory with a proportional or G-M counter for gross beta-gamma.
3 Airborne contamination measurement In addition to the area radiation monitors particulate airborne activity will be determined as needed by utilizing portable air samplers with filter paper and mobile continuous alc monitors (C.A.M.'s). Filter samples from portable air samplers are counted for gross beta activity using a laboratory gas-flow proportional or G-M counter. Alpha activity of a sample is determined by means of a gas-flow proportional counter. The continuous air monitors are self contained and therefore record sie activity continuously on a strip chart recorder. Operation of these air samplers will be in accordance with HNP-8013, 8109, and 8128. C. ROUTINE AIR MONITORING
- 1. Health Physics personnel will perform surveys that are necessary for the designation of Radiation Control Areas. ;
Surveys will include routine checking of areas for external t radiation hazards and contamination, as well as for airborne radioactivity.
- 2. Routine surveys will be conducted in the plant to establish q radiation, airborne, and contamination levels throughout the j facility. Whenever practical, Health Physica personnel will !
make the first entry i n t o- areas of unknown radiation l levels. Otherwise, licensed opersting personnel entering areas of unknown radiation levels will carry survey meters to determine radiation levels. { D. SPECIAL AREA MONITORING .
- 1. Special radiation, sirborne and contamination surveys in addition to routine surveys, will be made when necessary.
Examples o f situations requiring special surveys are.
- a. During any test or work itegs involving ,
B
, REFERENG ONI.Y mailual Set
u=o <= E.1. Hatch Nucinar Plant mouwam j HNP- 80 0 5 " Sso Page 1 REvissOPereo
.... Georgia Power A me.
See Page 1 3 of 22 (1) Installation or removal of in-core fission chambers. . (2) Installation or removal of core s t'a r tu p sources. (3) Installation or removal of reactor co'mponents. - (4) Loading and unloading fuel elements. (5) The opening of a primary coolant system (conducting a special survey of the surrounding 3 area for contamination after the opening or removal operation has been completed and b e fore other work is resumed). (6) The removal of any material which has been in - contact with the primary coolant (i.e., valves, j pumps, sections of piping, demineralizer resin, C etc.). (7) During reactor operation after the intial installation of, and after repairs or I modifications to, radiation ahielding.
- b. Following any situation which may result in radioactive contamination.
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~
- c. Before and af ter any decontamination operation. l
- d. Checking shop areas in which contaminated equipment is being worked on.
- e. When rupture of a radioactive -
material container i occurs, or when spills are reported.
- f. When handling spent fuel.
- g. Unconditional release of items to unrestricted areas. l E. CONTAMINATION LIMITS
( 8
- 1. Personnel, material and ~ equipment released from Radiation k Control Areas shall be free of significant radioactive contamination. Release surveys 0111 be made and will include alpha, beta and gamma radiation detection unless it is known that a given type is not present. Release surveys must be performed where the background does not exceed 200 cpm on beta-gamma detection meters or c0 dpm on sipha detection meters. The procedure for suaveys is f r.u n d in H h' P -8 012 SURFACE RADIOACTIVE CONTAMINATION SUdVEYS.
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See Page 1 ' 4 of 22
- 2. Surface contamination limits. -
) a. Clean areas , For areas outside the boundary of a Contaminated Area, t surface contamination will be kept at a minimum and' maintained below the linits set for Contaminated Areas in HNP-8003 RADIATION CONTROL AREA CLASSIFICATIONS.
- b. Contaminated areas frequent access.
For areas which become contaminated and which require frequent access, e f fo rts will be made to clean up the contamination as soon as possible, provided the clean-up operation will not result in unnecessary exposure to clean-up personnel. For f r e q tie n t access areas in which it is impractical to decontaminate immediately, contamination levels will be maintained below the following: (1) Smearable surface radioactive contamination Beta-Gamma 50,000 dpm/100 cm Alpha 50 dpm/100 cm (2) , Fixed surface radioactive contamination Beta-Gamma 10 mR/hr at 1" using a R0-2A or R0-3A , Alpha 50 dpm per detector area
- c. Contaminated Areas -
Occasional Access. For contaminated areas which may require occasional 4 access, the values in E.2.b may be increased by a factor of 10-100. NOTE When the above values in E.2.b. and E.2.c. are exceeded, the areas involved should be decontaminated as soon as possible. -
- d. Regulated Equipment. -
Eq u i pme n t of a portable nature, such as hand tools, samil pumps and motors, of such design which makes decontaminstion impractical, will be considered . regulated equipment and stored in a designated area, ( which will be labeled sa a Radioactivo Materiil Area. 5 The department using this equipment will be responsible for proper storage of this equipment. ' REFER ?NcF nm v manual set
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HNP- g o o c; Sas Pago 1 """ " l .... Georgia Power o .. - o. i See Page 1 5 of 22 Regulated equipment may have smearable contamination on exposed surfaces up to 50,000 dpm/GM probe area beta-gamma and 50 dpm/ detector probe area alpha, and may have radiation levels up to 10 mR/hr at one inch. This equipment must remain in a' designated storage area within a Radiation Control Area, and can be used only in Radiation Control Areas by workers wearing protective clothing. Workers requesting to remove ragulated equipment from a designated storage area must first notify Health Physics. Health Physics will determine the radiation and contamination levels on the regulated equipment and determine if it is acceptable for this equipment to be used in the requested work area. Equipment having radiation levels higher than 10 mR/hr may be used after consideration of all factors involved, i.e., the nature of the equipment, the frequency of use, and the length of time it may be in use. Movement of regulated equipment will be controlled.such that highly contaminated equipment will not be used in relatively clean areas.
- e. Personnel Contamination Limits (1) Personnel contamination levels shall be kept as low as possible at all times, the re fore the
'follo win g limits may be used as a guide to eclease phi's o n n e l to clean areas:
Beta-Gamma SKIN CLOTHING INTERNAL l Fixed Removeable Fixed Removeable __,1000 DPM/ No Detectable Probe Area L 1000 DPM/ No Detectable 5% MPBB Activity Probe Area Activity Aljha SKIN CLOTHING , INTERNAL Fixed Removeable Fixed Removeable _$_ 5 0 DPM/ No Detectable L 50 DPM/ No Detectable N/A Probe Area Activity Probe Area Activity NOTE d All Beta, Gamma measurements are using a pancake probe G.M. detector with ccunt rate instrument. . i i REFERENCE ONI.Y mallual Set
PEE M o ao= E.1. Hatch Nuclear Plant *= =ac ~o I HN P- 800ci
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s or 22 (2) All Alpha measurements are using a PAC-4G and a MS-2 Counter set up for alpha detection. (3) Personnel with contamination levels greater than the above values shall notify Health Physics and decontamination shall be attempted. If contamination levels cannot be reduced below the above values a Health Physics Supervisor or his l designated alternate will determine the release. (4) Movement of Material and Equipment from a Radiation Control Area. Any component, item of equipment, or tools having ! been used in a Radiation Control Area, will require, as much as practical, a beta-gamma dose rate and contamination survey prior to or after coming out of a Radiation Control Area. All ; released items will be classified by IIealth l Physics personnel as either an unconditional i release or conditional release. i l (a) Unconditional release item.
. Material and equipment will be given an
.. unconditional release by Health Physics
~
personnel for use outs,ide the boundary of a . Radiation Control Area if no smearable I beta-gamma or alpha contamination is found ! using a smear technique and radiation levels i at one inch are less than 100 CPM abo,ve l background using a GM count rate meter with HP-210 Probe or equivalent. NOTE Material and equipment which contain inaccessible and/or porous surfaces will not be released until the material or equipment is known not to be contaminated.
- 1 (b) Special Releases 1
An assistant Plant Manager may authorize the unconditional release of certain radioactive f material when it has been determined that the l total activity of the material is less than g that specified in 10 CFR Part 20 Appendix "C". ,- (c) Conditional Release Item: .
~
~ Removal of material and equipment from I Radiation Control Area with radiation and q contamination levels in excess of those 'l limite specified for uncondition- --je.--
Q must be approved for conditional re.. NOOly a^ REFERENCE ONUf a
-Om E. l. Hatch Nucl:ar Plant =c=ac ~O HNP- 800 5 Sse Paga 1 REv8SION NO o... Georgia Power n .... No See Page 1 7 of 22 Health Physics personnel. Contaminated material and equipm,ent will be placed in containers, when practicable prior to removal from a Radiation Control Area and tagged with Figure 1 tag or labeled with a radioactive material label. These labels will contain the levels of radioactivity, description of material, initials of individual performing the survey and date.
When it is not practicable to place contaminated material and equipment in containers movement out of an RCA will be controlled to prevent contamination spread. No conditional release item will be allowed to leave the Primary Protected Area without the express approval of the Health Physics stafe. (d) Contaminated Equipment Control: Certain items of material and equipment used during maintenance activities may, from time to time, become contamina*,ed, and prior to return to the maintenance shop store room, must be stored until decontamination can be performed. In this event, Figure 3 may be completed by Health Physics, if requested by Maintenance, and may be forwarded to the f Maintenance Department and the equipment will ! be stored under lock and key until such time decontamination can be performed. (5) Laundered Protective Clothing: q (a) Returned laundered protective clothing shall-be surveyed by Health Physics personnel for the following acceptable limits of contamination: Fixed contamination Beta-Gamma 1.0 mr/hr above background at one inch with an E-400. (b) Clothing in excess of the above limits but not greater than 5 mrem /hr may be retained for limited use in highly contaminated areas or hela for decay. This clothing will not be available for general use.
, (c) Procedures for handling and surveying
_ protective clothing is detailed in HNP-8007, i 1 L*.UNDERING OF PROTECTIVE CLOTHING.
, RERRENCE OtRY mailual Set
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E.1. HEtch Nucl::ar Plant ea= =ae >= \ HN P- 8005 Sos Pago 1 """**"* o.1, Georgia Power n .. . s.. pnga 1 8 of 22 O d F. RADIATION WORK PFRMIT
- 1. The Radiation Work Permit ( RWP )' (HNP-8008) is a procedure used to provide radiation safety and an awareness of significant exposure radiation levels in areas where personnel will be working. .
- 2. Procedures for issuing and using an RWP are found in HNP-8008, RADIATION WORK PERMIT.
G. PROTECTIVE APPAREL AND EQUIPMENT ,
- 1. Location:
Protective apparel and equipment are kept in the warehouse and in other areas as judged necessary by the Health Physics Supervisor. A minimum supply of clothing and equipment is kept in the Radwaste Building 132' elevation, Reactor Building 228' elevation, Turbine Building 112', Reactor Building 130' elevation and Reactor Building 158' elevation.
- 2. Protective Apparel:
Coveralls, shoe covers, hoods and gloves are available for use. This apparel is distinctively colored (yellow) and
) should be ,used only as anti-contamination clothing.
3 Use of Protective Clothing: . The following procedure will be used by personnel required to wear full protective clothing in Radiation Control areas.
- a. Entry Procedures.
(1) Obtain coveralls, gloves, head covers, shoe covers, rubbers, and other equipment as required by the Radiation Work Permit. (2) Follow HNP-80ll, PROTECTIVE CLOTHING DRESSING AND UNDRESSING. NOTE - When working in contaminated areas, personnel l should periodically check levels in contamination ! on protective clothing with a G . 'i . survey meter or i count rate meter. If gross contamination is j detected, i.e., radiation lovels in excess of 5 mR/hr at one inch, the prctective clothing should ' be removed and clean protective clo;hing put on. ' O'd b. Radiation Control Area Exit ' Procedure.
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a aao u E.1. Hatch Nucl ar Plant aaxt=ai ~o HNP- 8 00 5 Sne Pago 1 a.7@ON NO
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See Page 1 9 of 22 O D (1) Follow HNP-80ll, PROTECTIVE CLOTHING DRESSING AND UNDRESSING, to remove clothing to prevent contamination of the skin' or articles of clothing underneath. (2) Place articles of clothing in' the proper containers as they are removed. (3) Monitor self and personal clothing with count rate meter be fore leaving the access of the Radiation Control Area. - (4) If no contamination exists, exit the Radiation Control Area. (5) If contamination is present, notify Health Physics personnel immediately.
- 4. Additional protective clothing requirements.
. As the conditions warrant, additional protective clothing may be required for operations involving high levels of contamination or in situations where a splash hazard from contaminated liquid may exist.
O s. Respireterv protection
~
- a. Respiratory protection devices may be required in any situation arising from plant operations where the potential for airborne radi~oactivity exists.
- b. In such cases, the air will be , sampled by Health Physics personnel and the necessary protective devices specified according to the concentration and type of airborne contaminants present. It is the j
! responsibility of the individual and his supervisor to notify Health Physics personnel when working with radioactive materials that are likely to become d airborne. Every precaution should be taken to keep the air contamination to a minimum through use of proper l ventilation and prior decontamination of equipment or work areas.
- c. Issuance and use of all" respiratory protection equipment is described in HNP-8010.
H. SHIELDING e G
- 1. Shield installation requirements on piping and equipmcnt.
i
- a. The addition of shielding on piping an3 equipment must be done using a Maintenance Request (MR).
- b. The person requesting the shielding must first contact the Engineering Dept. Engineering Dept. will make or have made an evaluation as to how the shieldig g REFERENCE ONLY
b wom E. l. Hatch Nuchar Plant awa=ae = j HNP- 80 0 5 Soo Pago 1 aEvsoa w o.m Georgia Power d .. .
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V affect the seismic or design loading of the piping or equipment to which it is applie,d. All evaluations will l be documented.
- 2. Types of shielding
- a. Alpha and Beta radiation l
Alpha and beta radiation can be stopped or shielded l with a sheet of paper and a small piece of steel, (' respectively. Gamma and Neutron radiation require considerably more material for shielding.
- b. Gamma radiation (1) For gamma radiation, various thicknesses of dense {.
material such as steel, lead, or concrete can be p used to reduce the radiation to desired levels. I; (2) A convenient concept to use for roagh gamma shielding estimates is the tenth value thickness. j This value is that thickness of material which ; will reduce the radiation level by a factor of ten i (10). As shown in the following table, the t e- h I value thickness differs with different shield f materials and with gamma energy. The tenth value ; thickness for 6 Mev should be used for lines and ! equipment containing steam "o r reactor water. The j 1 Mev Values should be used for irradiated fuel, i equipment I for isolated equipment and for all during plant shutdown. TABLE 2 TENTH VALUE THICKNESSES APPROXIMATE TENTH VALUE THICKNESS MATERIAL , 1 MEV GAMMA 6 MEV GAMMA i Lead 1 5 inches 2 inches i Steel 4 inches 5 inches Concrete 12 inches 20 inches
- 24 inches 40 inches 4 Water a
NOTE The half value thickness for the listed materials is one-third of the tenth value thickness. , i p) s._ c. Neutron radiation -
. Neutron radiation can be shielded best by using a hydrogenous material such as water, plastic, or paraffin to thermalize the neutrons and by surrourdin7 l or impregnating this hydrogenous m'aterial~ wit Q g ,3 )
REFEREIKE ONLY l
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Sn Pago 1 j om Georgia Power n me ,,o t See Page 1 11 of 22
/7 V cadmium or lithium to absorb the thermal neutrons. An approximate half value thickness for 1 Mev neutrons to 1 3 inches of pa :-a f fin and approximately 2 7 inches for f 1 Hev neutrons. .
I. RADIATION OCCURRENCE REPORTS ,
- 1. In order to assure that conditions adverse to radiological (
safety are properly identified and corrected, the use of a l Radiation Occurrence Report has been established. l
- a. Radiation occurrence.
NOTE The requirement for the use of this report will be j determined by the Health Physics Supervisor or ! designated alternate. 3 Radiation occurrence may be reported to plant management for corrective action and may be documented by use of Figure 2, REPORT OF RADIATION OCCURRENCE. Q Types of radiation occurrences are described as follows: (1) External exposure: In,cludes: (a) Uncontrolled personnel exposure from external sources. (b) Uncontrolled personnel exposure from contamination on protective clothing. (c) Uncontrolled dose rates existing outside of Radiation Control Areas. I (d) Dose rates inside a Radiation Control Area , greatly exceeding normal levels. h (e) Exposure of personnel to dose rates such , hat [ a weekly permissible dose of radiation could be received in less than 6 minutes. (2) Personnel contamination control i Includes- .
- (a) Skin contamination. i I
(b) Any contaminated injury. U(~N. - f
; * (c) ,Any significant personnel exposure to l
- contaminated air without adequate protection.
s REFERENCE ONLY mailual Set - . - - a -m
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E. l. Hatch Nuclear Plant = = = ~o Sss Paga 1 HNP- 8005 nvisio= ~o om Georgia Power A ... See Page 1 12 of 22 (d) Personal clothing contamination. (3) Surface contamination control. Includes . (a) Any contamination transported' outside of GPC controlled boundaries. (b) Spread of contamination outside Radiation Control Area. , woeu (c) Spread of contamination in the immediate work area beyond that which was planned or might normally be expected. (d) Any fire or explosion in a Radiation Control Area. (e) Release of contamination to the air, ground, or water which greatly exceeded normal conditions. (4) Administratfts-control.
) . Includes:
.- )
(a) Employee working in a . Radiation Control Area without adequate time keeping. (b) Employee working in a Radiation Control Area without required or adequate monitoring. (c) Employee working in a Radiation Control Area L without wearing required or adequate protective clothing and equipment.
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(d) Employee. working in a Radiation Control Area in violantu of an RWP. (e) E11ployee working in a Radiation Control Area i without personnel meters. 1 (f) Employee working in a controlled area beyond , estimated permissible weekly exposure. j Procedures for completion of the report is as follows: 6 c (1) The individual initiating the Radiation Occurrence will use the complete Figure S. Figure 4 will be O V used as a monthly tab,ulation for the Occurrences. He will ccmplete the report through' the section, 3 " Action taken At Time of Occurrence". He will then forward the report to the Health Physics Supervisor or his designated alternate, a m00u0fS0t REFERENCE ONLY
HNP- 8005 S90 Pago 1 "'"5' ** om Georgia Power n .. Roo ongo 1 iA of 22 i (2) The Health Physics Supervisor or his designated alternate will review the report, and, if further action is required, will forward the report to the appropriate supervisor. keeping .the pink copy for a temporary record. If. no further action is-required, he will complete the form, sign at the bottom, and distribute the copies to the Plant Manager, appropriate supervisor and Health Physics file. The pink copy will be placed in the individual's exposure record file. (3) If ^ further action is required, the appropriate supervisor will review the report and specify what specific action is being, or was taken to prevent a similar occurrence, when the action will be completed and by whom. He will then return the report to the Health Physics Supervisor or his designated alternate. (4) The Health Physics Supervisor will review the report, and sign at the bottom. He will then distribute the copies to the Plant Manager, appropriate supervisor and Health Physics file. The pink copy will be placed in the individual's exposure record file. O - [ O . 1 manual set
;:- : . , . . . REFERENCE ONLY
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RADIOACTIVE MATERI AL DESCRIPTION OF M ATERI AL CONTMIIN \ TION D \T \
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_CONTAMINATEDEQUIPMENTC0]! TROL FIGURE 3 i CONTAMINATED EQUIPMENT C0!! TROL - TO MAINTENANCE SHOP STORE ROOM: Ti!E FOLLONING N/.MED INDIVIDUAL HAS LEFT THIS EQUIPMENT AT llEALTH PHYSICS DUE TO RADIOACTIVE CONTAMINATION: NAME DATE ITEM 1. 2. 3. 4. 5. 6. 7. 8. 9. 10.
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, MONTH YEAR FIGURE 4 REPORT OF RADIATION OCCURRENCES
_ TYPE OF OCCURRENCE PERSONNEL CONTAMINATION CONIAMINATION IN UNCONTROLLED AREAS UNEXPECTED HIGH RADIATION HINOR INJURY CONTAMINATED ITEMS IN UNC0!! TROLLED AREAS i HIGH AIRBORNE ACTIVITY OTilER i
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1 of 9 DECONTAMINATION A. PURPOSE To establish a basic technique for decontamination of equipment, floors, and personnel that 'may become contaminated during operation of a nuclear facility. B. SAFETY Observe Radiation Protection Procedures. C. REFERENCE Radiological Health Handbook. D. GENERAL During operation of a nuclear facility, equipment, floors, and personnel become contaminated. Decontamination should be done prior to maintenance work or release from a Radiation Control Area. Decontamination may be done at the work location or it may be brought into a decontamination room or area as necessary. O O E. EQUIPMENT DECONTAMINATION
- 1. Equipment decontamination at work location:
- a. Place plastic sheeting under the equipment to be decontaminated. This sheeting should be extended enough in each direction to assure that floors are not contaminated,
- b. Soak come absorbent cloth with water and squeeze out excess water. (It may also be desirable to wet absorbent cloth with a detergent such as Alconox.)
- c. Using an individual cloth rub an area approximately 6" X 6" and then place the used cloth in a plastic bag.
NOTE Soaking wet rags should not' be placed into a radwaste container. Contact a Health Physics Foreman for proper disposal methods of wet articles. Always work from the least contaminated areas toward the most contaminated areas to minimize spreading. j Oe " b c REFERENCE ONLY manual set
<>*aoza' E.1. Hatch Nucitar Plant a = =aa = 1 HNP. 8006 !
S;O Page 1 news o,. o om See Page 1 Georgia Power o ... 2 of 9 im U -
- d. Using a dry cloth, wipe up the detergent - water residue, and place the cloth in.a radwaste container.
- e. Repeat E.1.c and E.1.d in a new area. (Intermittent surveys with an appropriate radiation detecting instrument will show which area the decontemination must be repeated.)
- 2. Equipment decontamination in decontamination areas:
Equipment which is difficult to decontaminate at work location is wrapped or sealed in plastic and carried to the ., decontamination room or area for clean-up. See Radiological Health Handbook or Figures 2 through 2d for other decon l methods. q F. FLOOR AND AREA DECONTAMINATION NOTE See HNP-8005 section E.2.b for floor decontamination limits. The techniques used for the decontamination of floors or areas : vary with the level and extent of contamination. For high-level, or spotty contamination, the technique described in E.1 above is used to avoid spread of the contamination. For low-level contamination of large areas, a scrubbing machine or mop are used with water and detergent. Masslin cloth used with a sweeping pad may also be used for decontamina'ing large areas. The types of material used for decontamination till vary with the activity and ' area, therefore Health Physics personnel will determine the materials to be used prior to decontamination. NOTE ! When using vacuum cleaner for contamination removal, exercise extreme care when removing the filter from the cleaner for disposal. Follow procedure as in Figure 1 to minimize airborne activity. G. PERSONNEL DECONTAMINATION NOTE See HNP-8005 section E.2.e for personnel contr.mination limits. O 1. Decontamination shower (s) are supplied for decontamination of personnel; Superficial hand contamination can be washed off by the person involved after notifying H . P. After washing, the hands and arms must be monitored carefully to
- REFERENCE ONI.Y
I- u= = E. l. Hatch Nucl ar Plant eaoce=ac ~o l H N P- 8006 g i S n Pego 1 neos.o= ~o i Georgia Powerkn l 4
.... ..m ~o See Page 1 3 of 9 l
\ _J
{ assure that the contamination is removed. If the contamination involves parts of the body other than the hands or if the hand l contamination cannot be removed by simply soap and water washing, Health Physics personnel must be notified.
- 2. The following procedure is used for the cleanup of skin contamination.
l
- a. If the contamination is spotty, the spots are cleaned I up using cotton swabs dipped in a thick mixture of l detergent. This mixture is removed using clean cotton
~
swabs.
- b. If the contamination is general, the skin area must be i I
washed with soap and water. (If the contamination is widesprecd the decontamination shower may be used.)
- c. After washing, the skin area is surveyed with an E-120 or RM-14 count-rate meter. If detectable contamination is found, the area must be rewashed. ,
- d. After two washings, if the contamination is still O
V present, the skin area should be scrubbed with a brush using a thick solution of detergent, such as Tide). Use light pressure with heavy lather. (Do not scratch ~ or erode the skin.) NOTE Only if steps G.1 through G.2.d are unsuccessful 'are steps G.2.e and G.2.f to be attemped.
- e. After repeated scrubbing, if the contamination is still present, a thick paste of titanium doxide and water is applied to the area and kept moist. After the paste has stayed on the skin for approximately two minutes, it is removed and the skin area washed with soap and water.
- f. If tt.e titanium doxide paste does not remove the contamination, the skin area is painted with a 4 percent solution of potassium permanganate. The area is painted three times, allowing eaca application to dry. The skin discoloration is removed with a 4 percent solution of sodium bisulfite.
- g. Decontamination around eyes, in nasal passages or other body orificies, is done under the supervision of the p) t Health Physics staff.
- NOTE Serious cuts or wounds should ot be de on :n d
~~
-om E. l. Hatch Nuclear Plant aoctouas ~o 8006 l H N P-Sn Page 1 ,a,m l1 Georgia Power d. m See Page 1 4 of 9 )
D 0 unless done so by a Doctor.
~
Whenever it is suspected that personnel could have ingested radioactive contamination, a scan for internal contamination should be performed using a whole body counter as soon as possible. ,
- h. Anytime personnel decontami..ation is performed, the Health Physics staff must be notified. The Health l Physics Supervisor or his designated alternate will determine the necessity for documenting the decontamination of Form 1 of HNP-8009.
I FIGURE 1 I/ VACUUM CLEANER FILTER REMOVAL TECHNIQUE !
- 1. Place poly bag liner over top of cleaner as in sketch below. Tape t.o cleaner.
( i f . y Poly bag liner ( o ) .. g Tape bag liner opening
- to vacuum cleaner to seal q j opening completely I I i
l
- 2. Invert cleaner and liner to remove filter. ;
- 3. With most of debris in bottom of liner, tape liner shut as )
in figure below. l l l F ) b I l t i Cut here Tape Shut here l l 0 ,
- 4. Carefully cut tape and liner.
- 5. Carefully remove remaining half or liner from cleaner and tape open end of poly bag liner shut.
s 6. Place all material in proper co ,ggggio a .
- ' ^ ~=v a' E.1. Hatch Nuclear Plant ~octou~t~o HNP. 8006 See Page 1 ,,y c o ,
4 oart Georgia Power A .a. ~o See Page 1 5 of 9 1 FIGURE 2 PERSONNEL DECONTAMINATION l 1 F._.......__..__.............__...__.... Method
- Surface Action Technique Advantages
- -- _ .==
Disadvantages l
' soap tnd water Skin and hands 13aulsifies and Wash 2-3 minutes Readily available Continued washing dissolves contaa- and monitor. Do and effective for will defat the i' inate. not wash more most radioactive skin. Indiscrim-than 3-4 times contamination, inate washing of other than af-fected parts may spread contami-i nation.
Soap End water Hair Sames as above Wash several 4 times. If con-tamination is not lowered to accept- l l able Icvels, shave
; the head and apply l skin decontaminat-ton methods.
, i 4
,1. ave soap, soft Skin and hands Emulsifies, dis- Use light pres- Same as above Continued w' ashing
. brush, and water solves, and sure with heavy will abrade'the erodes. lather. Wash for skin.
2 minutes, 3 i times. Rinse and i monitor. use i care not to
' scratch or erode '
the skin. Apply k lanolin or hand g cream to prevent 6 5 chapping it' s/^)\ ct other Same as above Same as above Make into a paste. Slightly more Will defat and tatstgInt (plain) . Use with addition- effective than abrade skin and at water with a washing with must be used witt m!'d scrubbing soap. care action. Use care not to erode the
, skin.
- Bigin with the first listed method and then proceed step by step to the more severe methods, as necessary.
t I e e
" lil110al Set
' REFEREtKE ONI.Y
ace = a' E. l. Hatch Nuclear Plant eaoct =at e S:e Pago 1 H N P- 8006 nt o ,,o ) oa,t See Page 1 Georgia Power o e. 6 of 9 J
, (#)' FIGURE 2a PERSONNEL DECOiF/ AMINATION - CONTINUED
. . . . . . . . . . . . . . . . ...----.................==...................--- _
_. = _ - ......- methode Surface i Action Technique
, ................... ...-.............................=--- Advantages Disai$wantages
=......................---_- - - = - -
Pisture of Son Skin and hands Emulsifies, dis. Make into a paste. Slightly more ef- Will defat and vs.le end 506 corn- solves, and Use with addi-pesi erodes, fective than abrade skin and l tional water with washing with soap. must be used witt j a slid scrubbing care. ! action. Use care ' not to erode the skin.
'6
. water solution Same as above. Same as above. Ur.e with water. Same as above.
af a etsture of Same as above. 305 Tide, 65% Cal- Rub for a minute en, St Carbose and rinse. t e a t bo s pe et h yl rettutose)
$ preparation of Same as above. Same as above.
[ ( p t Car bose, Jn Use with addi. Same as above. Same as above.
, Tt42, Il Versene, tional water.
emt 48% water Rub for 1 minute and wipe off. W oor;tnited into a esea2. Follow with lano-i lin or hand cream. Jtttntus dioxide Skin, hands, and Same as abc*e. Work the paste piste. Prepare entremities. Do Removes contami- If lef t on too pasts by minir:g into the affected nation lodged long will remove not use near f ace area for 2 min- under scaly sur-ipitated tita- or other body skin.
. dioside (a openings.
utes. Rinse and face of skin. e thick slurry, wash with soap Good for heavy r permitted to and warm water. surface contami-
=sth a small Monitor. nation of skin.
; e.t of lanotin.
u t euccessful,
, ei to next step.
- kgtn with the first listed method and then proceed step by step to the more severe methods, as necessary. ,
t l e b n%' . FEEE ONLY mailual Set '.
-u t
a = vat E. I. Hatch Nucluar Plant aaoct =at e H N P- 8006 ,l S:o P:;ga 1 stm.o o Georgia Powerkn 4 s.,t .. o See Page 1 7 of 9 O FIGURE 2b V PERSONNEL DECONTAMINATION - CONTINUED l
..............-. ....----............~...... ... _.. -.--..... . - - - . . . . . . . . . - . . . . . . - - - . . . . . - - . . . . - - - - - - - - . .
Method
- Surface Action Technique Adva'tages n Disadvantages ,
...................-..... ---...........~ - - - . . . . . . . . . . - - . . - - . . . . . . . . . . . . . . . . - - . - ................... .-- . ......
Mas segual volumes Skin, hands, and Dinsolves contami- Pour over wet Superior for skin Will remove a ; pf e esturated so. cattemities. Do nant absorbed in hands, rubbing the contamination. laytt of skin if
- lutten of potas. not use near face the epidermis. surface and using May be used in in contact with stuo permanganate or other body hand brush for not conjunciton with the sain far morg b d 0.2 N sulfuric openings. more than 2 min- titanium oxide. than 2 minutes.
2: d. (Saturated utes. Rinse with poistion of kMnO4 water.
)s 6.4 grans per l 400 cl of H20.) l continue with next r s ts p. (
W ly a freshly Same as above. Removes the per- Apply in same man. Same as above. 6 prep 2r ed 51 solu- manganate stain. ner as above. Ap-tion of coitum ply for not more acid sulfite. than 2 minutes. (Solution made by The above proce- l dissolving 5 gm of dure may be re- I 4HS03 crystals peated. Apply [ En 100 c1 distilled lanolin or hand l wits t . P cream when com-pleted. riuching Eyes, cars, nose, physical removal Roll back the eye. If used immedi- When using for and. mouth by flushing, lid as far as pos. ately will remove nose and mouth, sible, flush with contamination. contamination in-large amounts of May also be used dividual should water. If iso- for ears, nose, be warned not to tonic irrigants and throat. shallow the are available, ob- rinses. ]
,O tain then without 3 (j
- delay. Apply to eye continually and then flush with large amounts of water. f s
..........................................__--___.____.-_...J_..._..___...._-___- - -
s 5? gin with the first listed method and then proceed step by step to the more severe methods, as necessary j l l - \ 1 l I ( f . ( 1 I 4 e t l n x - 1 manual set 4 W -. - - - . - _ - =_ ___ _ = -__ = REFER 9KE ORY m- -- ~ - - = - ~ n
. ,e ova E. l. Hatch Nuclear Plant eaoccouaa ~o H N P- 8006 S:3 Pago 1 nus,o,. uo ra,e Georgia Power n ,ao.
8 of 9 See Page 1 m O FIGURE 2c PERSONNEL DECONTAMINATION - CONTINUED negnoge Surface Artion Technique Advantages Disadvantages
===== - ==- ................... ...-----=====-
pg ;gn, geont'd) (Isotonic f eri-g gant (0.9% Nacl 's solution): 9 grams Nacl in leaker, fill ot 1000 cc with water.) Can be purchased from drug suppliers, etc. Further decontami-nation should be
.donc under medical rupervision.
I i Floahing Wounds Physical removal Wash wound with Quick and efft- May spread cont-i by flushing. large amounts of cient it wound ination to other water and spread not severe. areas of body it. edges to stimulate not done care-bleeding, if not fully. profuse. If pro- # fuse, stop bleed. ' ing first, clean edges of wound, bandage, and if any contamination remains, it may be removed by nermal O#
- cleaning methods,
,, as above.
- a. eating Skin of hands and Physical removal Place hand or foot Cleansing action if glove or boot) feet by sweating. In plastic glove is from inside is not removed or booty. Tape out. Hand does shortly af te pro-shut. riace near not dry out fuse sweating source of heat for starts and part 10-15 butes or washed with soap
.................J....==-----__- -
_- -- -- . = = - - -
- Seilm with the first listed method and then proceed step by step to the more severe methods, as necessary. ;
i 6
~
r
. b.
i s 6 0 * . 1 REFERENCE ONI.Y mallual Set i
- --_-- - - - - - -- - u
k.. i - ovat ! E. I. Hatch Nuclear Plant eaociouac ~o H N P- 8006 Src Paga 1 s tvisiou ~o oa t Georgia Power d .am ~o
)
See Page 1. 9 of 9 O P100aE 2a l PERSONNEL DECONTAMINATION - CONTINUED
.... ......... .....- - __...........===_- __ _
....................... ..... ...~...........
Method Surface Action Technique Advantages Disadvantages Swerting (Cont'd)
--............=-.=----.otuntil hand or fo is sweating pro and water ir.medi-ately, contami.
fusely. Remove nation may seep 91ove and then into the pores. wash using stand.
' ared techniques.
or gloves can be i worn for several
- hours using only body heat.
i 1 AREA AND MATERIAL DECONTAMINATION
=..-- - _ ......-
Ih............--
-- __- _ =
,MJthod'
~
, .................... . _ - _= --
Surface. Action Technique- Advantages Disadvantages {
. . . . . . . . . _ _ __.... ==-- ===_ _......- - -
l acrum cleaning Dry surfaces Removes conta:ni. Use conventional Good on dry, por. All dust must be
, nated dust by suc. vacuu:n technique ous surfaces. filtered out of Lion. with efficient Avoids water exhaust. Machine filter. reacations. is contaminated. p ! Water All' nonporous sur. Dissolves and For laroe surface All water equip. Drainage must be face (setal, erodes. Hose with high- ment may be uti. controlled. Not painted, plastic, pressure water at lized. Allows suitable for po.
etc.) an optimum dis. operation to be rous materials. tance of 15 to 20 carried out from 011cd surfaces feet. Spray ver. a distance. Con. cannot be decon. tical surfaces at tamination may be taminated. Not O(j . an angle of incl. dence of 300 to reduced by 50%. Water equipment applicable on dry contarainated sur8 400s work from may be used for faces (use vacu.
' top to bottom to solutions of other um); not app 11 avoid recontamina. decontaminating cable on porour tion. Work upwind agents. surfaces such as to avoid spray. wood, concrete.
.....................==-=_-- - __==__ _... - -----_ -
Segin with the first listed metho'd and then proceed step by step to the more severe met. hods, as necessary. S J g f REFERENCE ONI.Y mallual Set . .~
-- -w- -
l
%_. m ,. - , E. l. HATCH NUCLEAR PLANT m,n -
HNP-8007 C, p g.g GeorgiaPower A ~~
, l, l
LAUNDERING OF PROTECTIVE CLOTHING A. PURPOSE To establish a standard procedure for handling radioactively contaminated protective clothing. 1 l B. SAFETY Observe Radiation Protection Procedures. I i C. GENERAL Radioactive contaminated protective clothing equires special ! handling totinsure that such clothing is not inadvertently sent ; to an unlicensed commercial laundry or that contamination on the I dirty clothing is not spread to an uncontrolled area. Clean laundry returned for re-use by a licensed facility requires special monitoring to insure that it presents no significant hazard to personnel. It is the responsibility of the Health hs Physics staff to insure that all protective clothing used in Radiation Control Areas is properly monitored, packaged, and shipped to a licensed laundry for decontamination. When clean laundry is returned to the station, the staff insures that it is properly monitored and made available for use by personnel entering Radiation Control Areas requiring protective clothing. i l D. HANDLING PROTECTIVE CLOTHING
- 1. Preparation of contaminated protective clothing for shipment )
to laundry.
- a. As contaminated laundry containers are filled, the !
assigned personnel will close and seal the inner f plastic bag and close and seal the shipping container. I b. Health Physics will survey the outside of the container l in accordance with Procedure HNP-8016, SHIPMENT OF l RADIOACTIVE MATERIAL.
- c. Each drum lid should have the words " Radioactive LSA" or a Radioactive Materials tag (Figure 1) affixed. [
Il V l O- . 1 J REFERENCE ONLY mailual set
i E. l. HATCH NUCLEAR PLANT a=
- HNP-8007 See Page 1 cm 6
~~
Georgia Power c) (_ See Page 1 2 of 2 I I d. Store filled containers awaiting shipment in designated ll storage area (s) . Areas should.be posted or roped off. [
- e. Refer to HNP-8016, SHIPMENT OF RADIOACTIVE MATERIALS h i
for shipping information.
- f. When loading of the laundry containers is completed for g
{ return shipment, the door to the truck will be sealed ll with a lead seal by the HP technician.
- 2. Receipt of Decontaminated Protective Clothing i
Survey the outer surface of the containers containing the decontaminated laundry as it is unloaded from the truck with a rate instrument (E-400 or teletector). Any drum reading - greater than 2.0 mr/hr at the surface will be set aside and j checked. The drum will be opened and the protective clothing will be surveyed to insure it meets the limits for decontaminated protective clothing.
- 3. Surveying Decontaminated Protective Clothing
/~)
All protective clothing will be surveyed after decontamination. The commercial laundry is responsible for ' surveying each piece of protective clothing after decontamination. This responsibility is written into the purchase order by GPC, and the commercial laundry has also j insured Georgia Power Company they will meet the radiation levels for protective clothing for reuse in a Q.A. program. , This written Q.A. program is kept on file at Plant Hatch. l
- 4. Radiation Limits on Protective Clothing (
- a. Coveralls, hoods, cloth booties, rubber shoes less than 1.0 mr/hr beta, gamma, and no smearable contamination. :
l
- b. Rubber gloves less than 2000 cpm above background per r probe area with an HP-210 probe, fixed radioactive ;
material and no smearable contamination. All rubber , gloves will be air tested for leaks by the laundry. j
- c. Protective clothing greater than 1.0 mr/hr but less than 5.0 mr/hr will not be reused but placed in storage at the plant until a convenient time exists to send it ,
i back to the laundry for rewashing to reduce levels to less than 1.0 mr/hr. All protective clothing greater than 5.0 mr/hr will be disposed of as radwaste. () .. . e s REFERENCE ONLY nlanual Set i r -- - .
, n
' E. l. Hatch Nucl ar Plant aoccouas ~o HNP- 8 0 0 8 RLYt$tCN NQ s.
6...
'g Georgia Power m- ... o 1 of 11 (3
V RADIATION WORK PERMIT A. PURPOSE To provide instructions for the issuance of and implementation of Radiation Work Permits (RWP). The Radiation Work Permit procedure is designed to provide radiation exposure control by controlling and recording conditions under which Work in Radiation, High Radiation, Contaminated, and Airborne Radioactivity areas is p e r fo rme d , and by recording radiation exposures of personnel involved in work under the RWP. B. CONDIT.T.0NS REQUIRING RADIATI'ON WORK PERMITS
- 1. Entry into a High Radiation Area, Airborne Radioactivity Area, (as required by Health Physics), or any area posted with a " KEEP OUT - Radiation Work Permit Required" sign.
- 2. Entry to the dry well.
3 Maintenance or inspection of contaminated or radioactive g equipment in excess of the following limits: U -
- a. Smearable contamination in excess of 1000 dpm/100 cm2 beta-gamma. -
NOTE THE HEALTH PHYSICS SUPERVISOR OR DESIGNATED ALTERNATE MAY DETERMINE THAT A R.W.P. IS NOT NECESSARY TO DO INSPECTION OR MAINTENANCE OR EQUIPMENT WITH CONTAMINATION LEVELS IN EXCESS OF 1000 DPM/100 CM2 IF THE JOB IS OF A NATURE THAT CAUSES NO HAZARDS OF CONTAMINATION TO THE INDIVIDUALS PERFORMING THE J0B.
- b. Radiation levels at 18 inches in excess of 100 mR/hr or ,
where a whole body exposure of 100 mR/hr is likely. j
- 4. Neutron exposure. '
i l
- 5. Entry into an area of unknown condit' ion.
C. ISSUANCE OF THE RWP (Refer To Figure 1)
- 1. The supervisor in charge of the work requirir.g the RWP will ,
originate the RWP. He will enter the date, location, Unit l number, description of job and names of personnel performing ! ('; the work on the RWP and enter his signature in,the Requested By section. The RWP will then be forwarded to the Health Physics Supervisor or his designated alternate. manual set REFERENCE CNLY
~, , a naovat t;.1. r1aIGIl NUGlear e iarit oc<oe e ~e HNP gnnp S2o PcgG 1 I c... Georgia Power n ...o 12 Scc Pagc ' 2 cf . { ()
~
- 2. The Health Physics Supervisor or his alternate will review the work to be performed for any conditions which may j
i adversely affect the safety o f' the plant or personnel He will log the required { involved. informatiJn into the : Radiation Work Permit Log Book and enter the permit number I from the log book on the RWP. He will check the appropriate work category on the RWP. NOTE The Radiation Work Permit Log Book is a notebook kept in the , Health Physics office and contains Form 3, Radiation Work Permit l Log. 4 The Shift Foreman may complete the RWP for Health Physics provided the following criteria are met: 4
- 1. A qualified member of the Health Physics staff is not l on site, AND !
- 2. The safety of the plant warrants immediate action which would preclude calling in a Health Physics staff member 9 from off site, OR ;
3 Authorization is received from the Health Physics 1 Supervisor or his designated alternate.
/]
v
- 3. The Health Physics staff will review the RWP and assure that the area has been adequately surveyed ' prior to entry or will 6 be surveyed at time of entry, check the items of protective I, clothing required, specify the type of monitoring required, {
write in any special instructicns and hazards involved, and .,. review exposure records of personnel involved to assure exposures will remain within permissible limits. The Health , Physics Supervisor or designated alternate will review the , RWP, enter the expiration date and time, sign the RWP for Health Physics approval, and remove the Health Physics copy for filing. The RWP is then forwarded to the Shift Foreman. 1
- 4. The Shift Foreman will review. the RWP for any operations or l conditions which may adversely affect the safety of the i plant, enter the approved date and time .and sign the RWP. [
The Control Room copy of the RWP will be placed on file in i the Control Room. . c NOTE Approval to start work will be in effect after the RWP is signed by Health Physics and Shift Foreman. See C.6 for exception. :
/N * ! l
- v,
( REFERENCE ONLY malmal set n . ' ~ . .- . - . + + ~ - .- + .- ,. ,
. r weao = E.1. Hatch Nucicar Plant noceouci a o HNP- a g o g See Page 1 o... Georgia P6wer n ..
See Page 1
~4 nr 11
- 5. The Supenvisor requesting the RWP will review the RWP to familiarize himself with all requiremonts. The original RWP will then be taken to the jobsite and posted at the entrance to the jobsite on the clean side of the step-off pad.
- 6. In some situations where the plant needs immediate attention due to an emergency condition, a job may commence prior to the sign-off approvals of an R.W.P. by the Health Physics Supervisor or his desigr.cted alternate and the Shift Foreman. The approval to work, in these situations, will be .
contingent on the policy that a Health Physics person will accompany the workers, will perform the necessary radiation monitoring at the wei K place to protect the workers, and will give the workers proper instruction in radiation protection. The approval to work will also be contingent on the proper clesrance and tagging of the affected equipment by the Shift Foreman and his staff. D. ADDITION OF PERSONNEL NAMES TO RWP's While an RWP is in force, the addition of names of personnel to the RWP may be made only on the approval by the Health Physics staff. The work assignment of the person being added must be directly related or associated with the job description on the ; O awe- whe" aprov 1 1= 8r== tea. the Per oa'e ae=e witt we eaterea on the original RWP at the job site and on the Health Physics I copy in the Health Physics Office, k E. PERSONNEL RESPONSIBILITIES l
- 1. Supervisor in charge of work. l
)
- a. The Supervisor is responsible for assuring that personnel working on the job know the clothing requirements.
- b. If Health Physics monitoring is specified on the RWP, he must notify Health Physics Staff when the job is to l
( start. -
- 2. Personnel performing work '
I
- a. Each person entering and exiting the RWP area must enter data on the RWP Time Record (Figure 2) or Supplementary Time Record (Form 1) Form 1 will be used when Figure 2 is filled up.
- b. Each person must be familiar with all r eq u i r eme r. t s and instructions written on the RWP.
- 3. Heatlh Physics staff
- a. The Health Physics staff will provide radiation l surveying and monitoring as required by the RWP.
^
manual set
. REFERENCE CNI.Y p
a == E. I. Hatch Nucl ar Plant a= =a ~o HNP- g o o g . Sos Page 1 "'* ** o... Georgia Power h .. _e . ._ e ,e ,. ._ 1 ti nr 11
- b. The Health Physics staff will assist Supervisor-in-charge and personnel by the f providing ,
guidance in radiation protection matters to minimize exposure. F. TERMINATION OF THE RWP -
- 1. When the job is to be terminated, the RWP with supplementary sheets attached, must be returned to the Health Physics Office by the Supervisor-in-charge of the work.
- 2. An RWP will be terminated for the following reasons:
- a. Completion of the job.
- b. Cancellation of the job or RWP.
l
- c. Expiration of the RWP.
(1) Twenty-four hour limit. (2) Time limit as noted on RWP.
- d. Change in radiological conditions.
/3 NOTE U g
[ Daily radiological surveys will be mad.e in all RWP areas and i more often as necessary, and appropriate action will be taken if necessary. No further work will be performed under the RWP once the permit is terminated or expired. 3 The Health Physics Supervisor or his alternate will mark the RWP as terminated by checking the appropriate reason for termination, entering the time and date of termination, and signing the RWP in the Terminated By section. He will then mark the time and date terminated in the Radiation Work Permit Log Book, and file the original RWP. The Hec 1th i Physics copy is then removed and destroyed. L G. ROUTINE RADIATION WORK PERMIT 1:.
- 1. Jobs that continue for more than 24 hours such as in outages, (i.e. turbine overhauls, etc.) a routine R.W.P. may j be issued for the duration of the job. Routine R.W.P.s will only be issued to areas with constant H.P. coverage or an H.P. assigned to the control point unless approved se by an H.P. Supervisor or Foreman. Ro" tine R.W.P.s w i '.1 have
-s " Routine" written at the top anq bottom to distinguish them
( from R.W.P.s that expire after 24 hours. manual set REFERE!!G ONl.Y
h mao = E.1. Hntch Nucinar Plant ~= =a t ~o HNP AnnR Sao Pago 1 o... Georgia Power d ..- ~o 12 q See Page 1 5Of V
- 2. Routine R.W.P.s will be issued according to section C.
except it will be stapled to a folder with dosimeter sign 'in sheets -and a recent survey. Each dosimeter sign in sheets must have the R.W.P. number, date, and work category filled out. 3 In areas where work continues 24 hours a day the routine R.W.P. Will be left at the control point for the duration of the job. At the end of each shift change the dosimeter sign in sheets will be pulled and new ones attached. The completed dosimeter sign in sheets will be sent to dosimetry for dose recording.
- 4. The minimum survey frequency for routine R.W.P.s is every 24 hours. The H.P. Supervisor or Foreman will review all routine R.W.P.s and may set a more frequent survey requirement, according to radiological hazards associated with certain areas and the type of work being performed.
Once the survey is performed and is written it is sent to the H.P. office for review and a copy is made. The copy is , sent back to the control point to be attached to the routine l RWP. NOTE D U ~ If a routine R.W.P. is not used, a current radiation survey will not be updated and attached until the l R.W.P. is put back into effect. H. BLANKET HADIATION WORK PERMIT
- 1. For certain routine or repetitive work, a Radiation Work Permit Form may be issued to Operations, Health Physics and Radiochemistry groups, Plant Supervisors and designated ,
inspection and surveillance groups, and marked BLANKET at ; the top and bottom of the form. The Blanket RWP must be j approved by a Shift Foreman, the Health Physics Supervisor i or designated alternate and an appropriate member of supervision of the group to perform the work. The Blanket RWP will be valid until cancelled by Health Physics or u r. t il { the last Friday in each month. ,
- 2. The approved permit is stored in a protective holder in a book in the Health Physics Office. Exposure rates and a log ,
of personnel doing the work are not entered on the Blanket RWP form. Such records are kept on Form 2, Blanket Radiation [i Permit Entry Log. After personnel complete work under the I Blanket Permit, the information required on Form 2 MUST BE recorded. j A V
- NOTE -
1 . Record information for each'RWP area entered.
a unao = E. l. Hctch Nucl ar Plant ==ar ~o l' HNP gggg Soo Page 1
.... Georgia Poiver n . . ~o 1
Occ Page 1 6 Of I. REQUIREMENTS FOR ENTRY INTO HIGH RADIATION AREAS
- 1. All personnel entering a High Radiation Area where the field i dose rate' is expected to be greater than 1000 mr/hr must obtain a high range dosimeter from the Health Physics Office before entry.
- 2. All personnel entering any High Radiation Area (greater than or equal to 100 mr/hr) must notify the Health Physics Office before entry. This applies both to regular RWP holders and Blanket RWP holders.
3 The purpose of these two requirements are to assure adequate t-dosimetry is provided to assess radiation exposure, to assure that personnel entering these areas are properly informed as to the radiological conditions of the area, and to assure that the required equipment for entering has been provided. NOTE
' Field dose rate is referred to as the dose rate I approximately 18 inches from a point or line source, or any area dose rate greater than 1000 mr/hr.
O - J J l ' l l [., 1 I O . R1RilU3lSet
' REFERENCE ONLY t - -
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( ~a= A' E. l. Hatch Nucicar Plant aociouai ~o HNP- 8 0 0 8 i aemio o Sao Page 1 c . .. Georgia Power o .. . i
---36 0 P0"O ' 7 nr 11 FIGURE 1 RADIATION WORK PERMIT (FRONT SIDE)
RADIATION WORK FIRMIT cAtt # "O' "'*C'5"*** Pt. ANT E I. HATCH . 1 LXXAtaON LarttAllCN DAf( & TIM 4 I;M( ApptQvgg , 1 A5O'*a *I O PROT (CTIVE EQUtPMENT , REQUIRED f. ( ) Of4E COVERALL l ( ) TWO COVERALLS I 5p.6.! Hazards.
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( ) CLOTH MOOD , ( ) CLOTH BOOTIES f bruorin2 3:*15d3 ( ) PLASTIC 000 TIES J ( ) FW8BERS ( ) COTTON ClovCS SU2VEY MEASUEEMENT5 ' ' ^ ( ) GOGGLES SUUACE l LOCATOd CCNTAMIN A TON l () FACE WSK L p,vem/hr.or remlhr. DMM100 cma , p C fCC ( ) HALF FACE MASK ( ) MSA AIR PACK ! ( ) CONSTANT FLOW AIR MASX
, g ( ) FRESH AIR HOOO l i .-
l ( ) HIGH RANGL DO%t%tLTLR GINERAL INSTRUCTIONS
. l.. U:stasa r:rnmsson of sbft foreman befort entry to control areas. M TLD BADGE t
- 3. OWs pretr< tion fcr cuse er abras.eas from H P, be otes start of sob. M COSIVETERS
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( ) SEE SPECIAL INSTRUCTCNS
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--lREFERiNG Otll.Y
APPROVAL PROCEDURF NO
, ge.. N E. l. HATCH NUCLEAR PLANT _au.r atm o~ soas g g ,, ~o b l9-70 ocorgia Power n = ~o -
1 of 6 fERSONNEL CONTAMINATION SURVEY A. PURPOSE To provide instructions for the monitoring of personnel for radioactive contamination. B. SAFETY Observe Radiation Protection procedures. C. GENERAL This procedure contains the methods for monitoring personnel for radioactive contamination by utilizing sensitive portable survey instruments, hand and foot monitors, and/or portal monitors. Also included is a procedure for taking a nasal smear following suspected inhalation of radioactive material. It is the responsibility of each individual to monitor himself as per Section E of this procedure before leaving a Radiation Control Area. If contamination is detected, Health Physics should be notified. O ' Each time contamination is found on the hands or shoes or when leaving any area where protective clothing wa s worn a whole body contamination survey must be peformed. D. EQUIPMENT
- 1. Portal Monitor.
- 2. Hand and Foot Monitor. -
- 3. Beta -
Gamma Rate Meter (RM-14 with HP-210 probe or equivalent).
- 4. Portable Alpha Survey Meter (PAC-4G or equivalent).
E. PERSONNEL CONTAMINATION SURVEY -
- 1. Portal Monitor:
- j
- a. Step into the portal monitor. !
k
- b. Insure the white counting light on the console is on.
- c. When the Green Safe Light comes on, step out of the monitor. ,
t s manual set i
.m ,_ m.c _ _ _ . .
REFERENCE ONI.Y - - o
\
a mama' eaoctovae no l E. I. HATCH NUCLEAR PLANT HNP-8009 See Page 1 REVISION NO oaf t O See Page 1 Georgia Power A ~ ~o 2 of 6
- d. If the red Alarm light comes o n ,' push the reset button and notify Health Physics immediately: ,
NOTE Do not leave area before Health Physics has surveyed area.
- 2. Hand and Foot Monitor: *
- a. Step onto the base of the instrument and insert your hands into the slots. A white counting light will come on.
- b. Stay in this position until the green safe light comes on. When it does, you are free to go on.
- c. If an alarm light comes on notify Health Physics immediately. Begin a complete thorough survey of the entire whole body surface area with the external probe or an E-120 or RM-14 frisker. Do not leave the area before Health Physics has released you.
Q (_/ 3. Radiation Monitor RM-14:
- a. Operate the RM-14 as per HNP-8114.
- b. At various locations inside the protected area we have monitors located for tool and personnel survey. At each location is a sign such as:
" FRISK YOURSELF BEFORE PASSING THIS POINT"
)
You should frisk yourself in accordance with the instructions on the sign. These monitors are located , at key spots to control spreading of contamination. When you approach a monitor you should insert your hand - underneath the probe to see if it is contaminated. If your hand is clean then pick up the probe and go over your body, clothing, and shoe s ,very slowly about 1/4 inch away. ' In the event that you have some contamination on you { the meter deflection will increase and the alarm will sound. If this happens stay where you are and have someone contact Health Physics. If you are at a .phonc, call i
, Health Physics and get instructions what to do. [
, Remember two things, do not spread the contamination and get in touch with Heal;h Physics. If you check out 0.K. then go on about your business.
1 REFEREIKE ONI.Y mallual Set ____ _ _ _ _ _ _ _ _ _ _ _ - . _ _ _ o
AssnovAt PROCEDURE NO E. l. HATCH NUCLEAR PLANT
~ _uNP-anna See Pare 1 " ' " * " "
n i. g' . S c.e _ P.a g e_1 Georgia Power n ~ ~o 3 nr 6 F. PERSONNEL CONTAMINATION SURVEY BY THE HEALTH PHYSICS STAFF
- 1. Count Rate Me te r Model E- 120 or equivalent.
- a. Operate E-120 as per HNP-8120.
- b. Observe the meter and determine the background. (Must be less than 100 CPM).
- c. Move the probe very slowly over the entire body, paying particular attention to the hands, feet, hairy portions, and exposed portions of the body.
- d. If a reading 'that is twice background is noted, resurvey the suspected area. If the high reading is repeated, proceed to Section G.
- 2. Gas Proportional Alpha Counter Model PAC-4G.
- a. Operate the PAC-4G as per HNP-8105.
- b. Move the probe very slowly over the entire body paying attention to the hands, feet, hairy portions, and O e Pe ea- Pertte - er the sea r.
NOTE l The detector face is very thin and easily punctured. Do not bring the detector into contact with sharp j objects. The detector must be held within 1/2 inch of ! the surface being checked in order to detect alpha. [
- c. If any needle deflection is noted, resurvey thE l suspected area and if the deflection is repeated, proceed to Section G. {
g
- 3. Nasal Smears (performed following suspected i
inhalation of I radioactivity). a. Probe external surface of the nose with an RM-14 with I 4 HP-210 probe or equivalent.
- b. Remove any extensive contamination near nostrils, i
- c. Wet two cotton tip applicators (Optional Step).
- d. Have subject himself smear the inside of each nostril with an applicator. j e.
Check each applicator by taking a near cont'act reading with an HP-210 probe connected to an RM-14 or equivalent. Record results on Form 1, Personnel Contamination Report. REFERENCE ONI.Y mailual set
gg*pegyygg PROCEDURE NO E. l. HATCH NUCLEAR PLANT HNP-8009
"'*S' ""
See Page 1 liiii 3 O LS ee Page 1 Georgia Power n ~ ~o 4 of 6
- f. If results are detected above background, report it immediately to a laboratory foreman or supervisor.
C. FOLLOW-UP PROCEDURE -
- 1. All personnel contamination shall be immediately reported to the Health Physics staff and shall be documented on Form 1, Personnel Contamination Report, when determined necessary by
- the Health Physics Supervisor or designated alternate.
- 2. If a Whole Body Count indicates greater than 5% body burden or if the Health Physics Supervisor deems it necessary, all personnel considered. as serious inhalation cases shall be given two plastic containers and told to collect urine output over the next 72 hours. Containers shall be '. a b e l e d with the person's name, type of specimen and date.
- 3. The Health Physics representative attending to the contamination incident shall initiate Form 1 if the presence of contamination is verified. ,
- 4. The Health Physics representative will proceed with i decontamination measures in .tecordance with Procedure CJ HNP-8006, Decontamination.
- 5. After completion of Form 1, the original will be filed in a Personnel Contamination Report file, the pink copy in the Individual's Exposure Record file, and the yellow copy sent to the individual's supervisor.
NOTE The Personnel Contamination Report shall be logged in on Form 2, PERSONNEL CONTAMINATION LOG. l l O .
\
l manual set
. 1 l
As e *)oAs PROCEDUnF No E.1. HATCH NUCLEAR PLANT HNP-8009 lSee Page 1 ncvisic,s uo I fi, 3 O ,see Page 1 Georgia Power A ~~ 5 of 6 , l FORSI 1 NUMBER
~
PERSONNEL CONTAMINATION REPORT J
. DATE OF ISSUANCE TIME OF ISSUANCE Name Dept. *
!- j
! GPC Employee 0 0
NON GPC Employee O
, (Company)
Reason for Suney i
! Cause of Contamination (if known) l
! InitialSuney Results:
(Beta-Gamma) j location oI Contamination: Instrument (s) Used: (Alpha) (Calib. Date) (Beta Gamma) (Calib. Date) I' Suneyor: Decontamination Measures Taken: l' 1 4 HP Representative: Final Suney Results: (A'oha) (Beta Gamma) (Alpha) (Calib. Date) . (Beta 4amma) (Calib. Date) [ f.
, Suneyor: 1 Action Taken To Preclude Future Occurrance:
p i Additional Comments: Orig.. II.P. Office s Pink . Indisidual's Eyesure Itecord File - Yellow . Indisidual's Supenbor Reviewed: Laboratory Supervisor ilN P.1-8009 REFERENCE ONLY .
[. . . PROCEDURE NO E. I. HATCH NUCLEAR PLANT HNP-8009 See P.ge 1 REvlSION NO !O S.. v.. 1 Georgia Power A ~m ~/ 6 of 6 FORM 2 PERSONNEL CONTAMINATION LOG CONIAMINATION INDIVIDUAL (S) DATE ISSUED BY REPORT # NAME l 1 O . . U"O REFER 9MG ~ny
APH40y Ai nim 4W HNP-8010 X E. l. HATCH NUCLEAR PLANT
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1 of 38 : USE AND CARE OF RESPIRA'f0RS A. PURPOSE h To provide instructions for the proper selection, use, maintenance, control and storage of respiratory equipment. . This procedure covers the following respiratory devices: ( MSA Custom Comfo Aerosol - Filter Respirator MSA Ultra Filter Respirator MSA Pressere Demand Apparatus (Air Pack) MSA Constant Flow Air L'.ne Respirator MSA Pressure Demand Air Line Respirator (Bottle Air) B, SAFETY Observe Radiation Protection Procedures. [ C. - REFERENCES
- 1. 10 CFR20 para. 20.103
,y V 2. Regulatory ~ Guide 8.15
- 3. MSA Respirators Instructions for Use a6d Maintenance
- 4. NUREG-0041
- 5. ANSI-88.2 D. MANAGEMENT POLICY It is the Georgia Power management policy to minimize the inhalation of airborne radioactive materials to all personnel assigned or visiting Plant E. I. Hatch. For this reason it is mandatory that personnel at Plant Hatch adhere to all procedures, and policies relating to the respiratory protection program.
The management policy will be normally accomplished by the application of engineering controls, including process, containment, and ventilation equipment. Periodic evaluation of l/ ' the respiratory protection program will provide the management 8 with the means for determining what additional measures, ( equipment and controls may be necessary, where practical, to further meet the objective, while in turn reduce the need for l wearing respiratory equipment. I (3 . V,- . e
., REFERENCE ONLY M811U8lSet
l - I
- - 1 E. l. HATCH NUCLEAR PLANT HNP-8010 h See Pace 1 o^'t 12
~~
O See Page 1 Georgia Power 2 of 38 Routine plant operations are planned activities that are [ generally repetitive and occur with various frequencies. Operations of this nature have been considered in the design of the plant and appropriate equipment installed to minimize most airborne situations. ( The use of respirators as a substitute for practical engineering [ controls in routine operations is inappropriate. Therefore the ( installed process, containment, and ventilation equipment will be , utilized, in addition to preplanning of work, to minimize the use L of respiratory equipment. I Nonroutine operations are activities that are either nonrepetitive or else occur so infrequently that adequate limitation of exposures by engineering controls is impractical. For operations of this type respiratory equipment will be used where needed to provide protection. Emergency operations are unplanned events characterized by risks sufficient to require immediate action or mitigate an abrupt or , rapidly deteriorating situation. Procedures have been issued for : handling most emergency situations and are contained in procedure ! pd series HNP-4000-4999. Adequate quantities of and locations for I respiratory protection equipment are provided to handle emergency i situations. Training and retraining of personnel in emergency j situations requiring respiratory protection is provided. Prior to issuing a respirator to an individual, he/she will be I informed of the following policy: Persons wearing respirators l may leave the area at any time for relief from respirator use in i the event of equipment malfunction, physical or psychological l t [ distress, procedural or communication failure, significant ' deterioration of operating conditions, or any other condition that might require such relief. l l E. REGULATORY REQUIREMENTS ld t [ 10 CFR20 paragraph 20.103 specifies regulations regarding l l exposure of individuals to concentrations of radioactive j materials in air in restricted areas. This procedure has been I written to carry out the regulations. l F. DESCRIPTION OF RESPIRATORS b
- l. Ultra Filter Full Facopiece Respirator l l i This respirator is a full facepiece unit with a single or O aoub1e oertria9e eroviaine reseiretory erotectioa e92iase I
,, dust, fumes, and mists having a time weighted average less t than 0.05 milligram per cubic meter where the contaminant I concentration does not excced 50 times the concentration !
limit for the radionuclides involved. The respirator with l
, manual set , RErc.RENCE ONLY I
._ -~ ,
E. I. HATCH NUCLEAR PLANT HNP-8010 l See Page 1 atve w l' o.ra 12 O See , age 1 emphe - 3 of 3e 1 the oval ultra filter cartridge has an approval No. TC l 21C-150. The respirator with the round ultra filter Type H cartridge has an approval No. TC 21C-155. NOTE This respirator removes only dispersoids from the air. It gives no protection against gases, vapors, or oxygen > deficiency (less than 19.5% 0 2)- i
- 2. Pressure Demand Apparatus (Air Pack) l The Pressure Demand' Apparatus (Air Pack) consists of a high ,
pressure cylinder, a pressure demand regulator connected by ! a high pressure tube to the cylinder, a facepiece and tube ! assembly with an exhalation valve, and a harness assembly for mounting the complete apparatus on the body. The unit maintains a slight positive pressure inside the facepiece t during inhalation, thus minimizing potential air in-leakage ; into the facepiece. The unit contains an audible signal ; device to indicate when the breathing supply has dropped to i q a point where the user must return to fresh air. The unit i b is rated for 30 minutes service. Actual service time will ; depend on the user and his level of exertion. The unit has an approval No. TCl3F-29. It can be used in oxygen deficient and in toxic atmospheric conditions and has a $ protection factor of 10,000 for particulates, gases and , vapors. i
- 3. Constant Flow Air Line Respirator - Full and Half facepiece '
The Constant Flow Air Line Respirator is a respirator approved for use in atmospheres not immediately hazardous to life or health. The unit consists of a facepiece and tube assembly, low pressure control valve, from 25-300 feet of air hose, and a portable air filter and regulator. Breathing air for this unit is provided by the plant service air compressors. The service air is filtered and reduced in pressure to 35-40 psig by the portable air filter and regulator to meet the requirements of the respirator. With this respirator, a cor inuous flow of breathable air is b supplied to the f acepi':e and provides a cooling ef fect as l It meets the respiratory requirements of the searer. The unit has an approval No. TC19C-78 and provides a protection I? factor of 2000 for particulates, gases and vapors. l
- 4. Pressure Demand Air Line Respirator O', .
2
, The Pressure Demand Air Line Respirator is a unit approved for use in atmospheres not immediately hazar_dous to life or
, health. It consists of a facepiece and tube assembly, pressure control valve and from 25-300 feet of air hose.
, manual set
~ REFEP3KE ONLY . -~
= -
u ,4.u m eauaw* w E. I. HATCH NUCLEAR PLANT HNP-8010 See Page 1 -umm % om 12 O, Georgia Power m&A ~~ See Page 1 0 4 of 38 Breathing air is supplied by high pressure breathing air bottles located away from the user. A pressure regulator on the air bottles reduces the air pressure to 80-100 psig to meet the requirements of the respirator unit. The respirator provides approximately 1.0 inch of water positive pressure in the facepiece, thus minimizing inward air leakage during inhalation. The unit has an approval No. TC19C-93 and provides a protection factor of 2000 for particulates, gases and vapors. ,
- 5. Hoods and Suits No allowance can be made for wearing hoods and suits for protection against inhalation of radionuclides at present.
G. SELECTION OF RESPIRATORS FOR USE NOTE Respiratory protection devices may be required in any situation arising from plant operations where the potential for airborne radioactivity, oxygen deficiency, or toxic (JS s atmospheres exists. In such cases, the air will be monitored by Health Physics or other qualified personnel and the necessary protective devices specified according to the concentration and type of airborne contaminants present. It is the responsibility of the individual and his supervisor to notify Health Physics personnel when working with radioactive or hazardous material that are likely to become airborne. Every precaution should be taken to keep air contamination to a minimum through use of proper ventilation and prior decontamination of equipment or work areas. g 1
- 1. Regulatory limits and rules.
)
Respiratory protective equipment will be selected to provide a protection factor greater than the multiple by which peak ; concentrations of radioactive materials are expected to ' exceed the values specified in Table I Column 1 of Appendix ' B to 10 CFR20. The equipment selected is to be used so that the average concentration of radioactive material in the air that is inhaled during any period of uninterrupted use in an airborne radioactivity area, on any day, by any individual using the equipment, will not exceed the values specified in Table I, Column 1 of Appendix B to 10CFR20. For purposes of this procedure, the concentration of
/~T radioactive material in the air that is inhaled when I 7, respirators are worn may be initially estimated by dividing l
. the ambient concentration in air by the protection factor i specified in Table 1. If a respirator user's intake of I radioactive materials is later determined by other
- n1anual set REFERENCE CIRY
~ .
4 awHoyAL PHUCtDUM NO E. l. HATCH NUCLEAR PLANT HNP-8010 See Page 1 ain.u~ w uui 12 O, Georgia Power ~~ See Page 1 o 5 of 38 measurements to have been greater th'an that expected from initial estimates of radioactive materials in the air the user inhales, the greater quantity is to be used in evaluating exposures. If it is less than that initially estimated, the lesser quantity may be used in evaluating exposures.
- 2. Administrative rules and limits.
- a. Section E and paragraph G.1 prescribe rules and regulations which shall not be exceeded. For administrative purposes Table 2 will be used for selecting respirators.
- b. If airborne conditions exist which require consideration toward exceeding the administrative limits in Table 2, a laboratory supervisor must be consulted and his approval received before using greater values.
- 3. Selection procedure (3 a. Determine the radiological (external radiation and s/ airborne) conditions in the work area using the procedures HNP-8005, 8012, 8013. Air samples should be taken as near the breathing zone ~where the work will be performed as possible. (Also if the worker has to pass through an airborne area to get to. the work place) .
- b. If air sampling confirms that an airborne condition, as defined in HNP-8003, exists in the work area, respiratory protection equipment, increased surveillance, or limitation of working times is warranted.
- c. Consider the type of work, work hazards and locations, time to complete the work, ambient conditions at the work location, equipment to be used by the worker, end the potential for airborne conditions to develop during l the work period (i.e. highly contaminated areas and equipment, opening of equipment during the work, air movement in the work location, cutting and welding work, etc.),
- d. Consult with a laboratory supervisor or designated alternate and select the proper respirator for the work-conditions using Table 2 and paragraph 5 and c above.
() e.
~
Issue the respiratory equipment per Sect 1on H. The worker, after proper training will wear the respirator using Section I as guidance for donning the equipment. s onanual set
- REFERENCE ONLY
}
i appgat Ps*UGtOvHt No k E.1. HATCH NUCLEAR PLANT HNP-8010 { See Page 1 aeve w
"^"
C) See Page 1 Georgia Power d "" 6 of 38 I llj
- 4. Determination of Airborne Radiation Exposure'. l
- a. Anytime an individual is likely to inhale, for any two. !
hours in a day or ten hours in one week, radioactive l materials in uniform concentrations as specified in Appendix B. Table 1 Column 1 of 10CFR20, the following l calculations shall be made to determine levels of h airborne radiation exposure.
- b. From the data on HNP-3013 Figure 2 and HNP-8008 Figure d 2, calculate the exposure to airborne radioactive ) '
materials as follows: K MPC - HRS = Hours in Area multiplied by Activity (PF) NMPCN j WHEPE e K = Number of nuclides in the air j th ,j Activity = Activity of the N Nuclide in uci/cc ()3
% N * >
*' th PPN = Protection factor of the respirator for the N i Nuclide (See Table 1) th MPCN = MPC of the N Nuclide in u ci/cc lj Hours in Area = Stay Time in the airborne area in hours h
- c. Log the airborne exposure in MPC HRS for the )
appropriate day on Form 5 using the results obtained from G.4.b. I{ l NOTE l If an individual's airborne exposure exceeds 2 MPC HP.S in any one day or 10 MPC - HRS in any one week then l; that individual's intake will be assessed by p appropriate methods as outlined in Section M and all ! his exposure to airborne radioactive materials will be I documented on Form 5 for the current calendar quarter including those amounts of exposure below 2 MPC - Hrs. l in a day or 10 MPC - Hrs. in a week.. f I H. CONTROL, ISSUANCE, PROPER USE AND RETURN OF RESPIRATORY EQUIPMENT im '. Q l. The Health Physics staff controls the issuance,. proper use, inspection, cleaning and repair, training of personnel, [ j
. spare parts, and quantities of respirator equipment ,
required. (The Regulatory Specialist handics special training for the fire brigade and team on SCBA) . a manual set
. REFERENCE CNLY l t
i> WA)vLL PH(.LLDUML PeV See Page 1 E. I. HATCH NUCLEAR PLANT HNP-8010 ; Mt vthaO'e teO om 12 o) q, See Page 1 Georgia Power ~~ 7 of 38
- 2. Respiratory equipment will be issued only to.
- a. Those persons who have been trained, fitted and tested for that type equipment.
- b. Those persons whose facial hair does not interfere with the seal of the respirator.
- c. Those persons who have received medical approval by a physician to wear respirators.
- 3. . Only BM/N10SH approved equipment will be used when taking credit for the use of respirators in protecting personnel from airborne activity.
- 4. Respiratory equipment will be issued using a Radiation Work Permit procedure, except during emergency conditions.
- 5. Adequate surveillance and surveys of the work activity by the Health Physics staff will assure proper use of the equipment.
(~) 6. The Health Physics staff will conduct an adequate number of air surveys during the work period to verify and assess radiological conditions and exposure to personnel.
- 7. Facelets will not be used for protection against airborn radionuclides.
- 8. Equipment will be used within the limitations for its type and make of use as described in this procedure.
- 9. Only the SCBA equipment is to be used as emergency devices.
- 10. Where required, spectacle kits will be furnished to permanent plant personnel.
- 11. Where required, goggles, anti-fog compounds and !
communication gear will be furnished to respiratory users.
- 12. Contact lenses are not to be worn wi~th full-facpiece ,
respirators.
- 13. Air purifying respirators are not to be used in oxygen deficient atmospheres or atmospheres immediately hazardous to life or health. .
(~T 14. No credit will be taken for use of sorbent cartridges
\-) against radioactive materials.
{
' naanual set
\. nspro n ucc ~ ....
444Huv&L W4UL&DUHt NO E. l. HATCH NUCLEAR PLANT HNP-8010 See Page 1 *****v om 12 O See Page 1 Georeia v Power ~~ 8 of 38
- 15. Only high efficiency cartridges, as describbd in Section F will be used in air purifying respirators when. making allowance for the use of respiratory equipment in estimating exposures of individuals to airborne radioactive materials.
- 16. Filter cartridges on air purifying respirators must be replaced with a fresh cartridge after one work day's use by one individual. -
- 17. Respiratory equipment except emergency equipment, will be issued by and returned to the Health Physics staff.
Issuance will be controlled through an RWP permit, a Respirator Clearance List (or Respirator Clearance Card), and the use of Form 6. The normal method of issuance will be through the use of the clearance card unless exempted by the H.P. Superintendent or designee. In lieu of Form 6, Health Physics may control issuance and return of respirators at established control points by the worker surrendering the respirator clearance card to the Health Physics technician upon issuance. This card will be retained until the respirators are returned. I. USING THE RESPIRATORS
- 1. Health Physics will issue the proper respirator for the work j to be performed.
NOTE
- a. Each respirator user is emphatically advised that he should immediately leave the area for relief from respirator use in case of equipment malfunction, !
physical or psychological discomfort, or any other j condition that might cause reduction in the protection l afforded the user. f l b. Respiratory protective devices should never be worn when a satisfactory face seal cannot be obtained.
- c. Custom Comfo Aerosol - half fac.e respirator will not be used for respiratory protection.
- 2. Full facepiece w/ type H Ultra Filter Cartridge. ;
y
- a. Perform Steps I.2.a. and I.2.b. above.
I
- b. Check for adequate seal per subsection K.2.
, c. Remove th.e facepiece after use per subsection I.9. l
, REFeum OM mailual Set
! t
s 44+++vvAt PHUL& OUHt **O E. l. HATCH NUCLEAR PLANT HNP-8010 See Page 1 to om 12
' ~~
('~-) See Page 1 Georoia o Power 9 of 38 <
- 3. Constant flow air line respirators. (full and half facepiece). -
- a. Inspect equipment as per Step 0.5. '
- b. Connect the portable filter and regulator unit to a house service air line, using the air hose provided.
Attention should be made to keep the unit out of the contaminated area; but if this is not possible, it should be wrapped in plastic.
- c. Tag the service air outlet with a "To Be Operated by .
H.P. only" Tag.
- d. Adjust the regulator for 35-40 psi. Bleed off the 1e' filter trap for moisture.
- e. Place the control valve on a belt or loop on the left j side of the body. j i
- f. Put on the test facepiece as in subsection I.6.
()- 9 Connect 25-300 ft. of MSA air hose from portable filter regulator unit to the control valve. Then connect facepiece breathing tube to the control valve.
- h. After leaving the airborne or work area, do not remove the facepiece until outer pair of gloves, coveralls and shoecovers are removed. (This may not be possible in all cases).
- i. Disconnect breathing tube and air line hose from the control valve. Disconnect air line hose at outlet of -
filter regulator unit.
- j. Remove facepiece as in subsection I.7.
- k. Shut of air supply to filter-regulator unit and disconnect hose. ,
1
~
NOTE Do not perform this step until all persons ar e through using the filter-regulator unit.
- 1. Place all equipment in designated place for surveying and cleanup.
G
- 4. Pressure Demand Air Line Respirator (Bottle Air)'.
k~. ). i i t
- a. Inspect equipment as in subsection 0.6.
m UJ(manual Set j
. s
_ ~.mu, ~ E. I. HATCH NUCLEAR PLANT HNP-8010
. See Page 1 % *m w
~
O - See Page 1 Georbia Power d
~~
10 of 38
- b. Place the regulator on a belt or loop on the left side r of the body. .
- c. Put on the test facepiece as in s'ubsection I.6.
- d. Assure that the high pressure bottle regulator is adjusted to 45 - 60 P.S.I.G. outlet pressure.
- e. Connect 25-300 feet air line hose from high pressure regulator to regulator mounted on body. Then connect facepiece breathing tube to the regulator.
- f. After leaving the airborne area, do not remove the facepiece until outer pair of glove, coveralls, and shoecovers are removed. (This may not be possible in ;
all cases) . i 11 9 Disconnect breathing tube from regulator on body. Disconnect air line hose at high pressure regulator 2 outlet and then at regulator (on Body) inlet. Shut off air cylinder. () h. Remove facepiece as in subsection I.7. ,
- i. Place all equipment in designated . place for survey and cleanup.
- 5. MSA Air Pack Model 401-pressure demand
- a. Check the pressure gauge in the cylinder valve to insure that the cylinder is full (2216 psi pressure) . }
If there is less pressure, the service life will be 'A reduced accordingly.
- b. Put on the apparatus using either of the following methods:
(1) Open the lid of the case and extend the shoulder straps to their full length. Lean forward; grasp the cylinder and backplate firmly, with both hands, between the cylinder clamp and the waist belt. Lift the apparatus straight up and over the head and rest it on your back. The shoulder straps will fall into place over the shoulders. , Adjust straps before straightening up. Fasten waist belt snugly. Should further adjustment be necessary, lean forward and adjust straps. Use of (,) chest strap is optional, ,
-m -~
E. l. HATCH NUCLEAR PLANT HNP-8010 See Page 1 m uum w em g 12 See Page 1 Georgiao Power al ~~ 11 of 38 (2) Extend narrow shoulder straps. Don the apparatus like a vest. Lean forward while the shoulder straps are being adjusted. Fasten waist belt securely and snap chest strap if desired,
- c. Open the cylinder valve handwheel fully (at least 3 turns) and close the By-Pass (red) handwheel on the Demand Regulator.
- d. Place palm of hand over the pressure Demand Regulator outlet firmly to block it leaktight. This is necessry as the pressure Demand Regulator is spring loaded and air will flow automatically if the outlet is not blocked.
- e. Open the Main Line (yellow) handwheel fully and observe the pressure gauge on the Regulator. This gauge indicates the pressure in the cylinder and should read approximately 2200 psi if fully charged. If there is less pressure in the cylinder the service life will be reduced accordingly. Turn off the cylinder valve and watch the pressure gauge on the regulator. There should be no drop in pressure if the equipment is leaktight. If there is noticeable deflection of the needle the equipment should be checked and the leak corrected before entering a toxic atmosphere. Shut off Main-Line Valve.
- f. Put on respirator as per subsection I.6.
- g. Connect mask hose to regulator. Open Main-Line Valve fully.
- h. Breathe normally as the apparatus automatically satisfies any breathing requirement. ,!
t NOTE i It is necessary to periodically check the pressure gauge on the Pressure Demand Regulator as it . continually indicates the pressure in the cylinder. . When the needle reaches approximately 540 psi on the a pressure gauge, the Audi-Larm Signal will begin ! ringing. When the bell starts ringing, or when the & pressure reaches 540 psi, it is time to return to fresh 1 air. t
. I I
1 I
' naanual set REFERENCE CMLY
1 amegyAL PNUCtL'sJHL W E. I. HATCH NUCLEAR PLANT HNP-8010 See Page 1 atve w out 12 Georgia Power ~~ See Page 1 O 12 of 38 NOTE During normal use the By-Pass (red) valve is closed and is used only if the Pressure Demand Regulator becomes inoperative. It provides a continuous flow and should - be opened and the By-Pass valve adjusted.to provide the flow desired. Leave hazardous area immediately since life of apparatus is greatly diminished when By-Pass { valve is being used.
- i. After leaving the airborne area, remove the tank and harness but do.not remove the facepiece until outer pair of gloves, coveralls and shoecovers are removed.
(This may not be possible in all cases) . Assistance - will be required to hold the cylinder and harness while j removing coveralls.
- j. Unlock the lever on the cylinder valve and close the ,
valve. Do not use excessive force as the valve closes i leaktight with little effort. '
- k. Release pressure in high pressure hose by breathing until air is exhausted.
I NOTE Do NOT use By-Pass valve to exhaust ' air pressure.
]
- 1. Remove facepiece as in subsection I.7. l 1
- 6. Donning the facepiece I l a. Inspect the facepiece to be sure that all parts are in l good condition and installed properly. Rubber parts l should be pliable and.not cracked. See section O for details. .
- b. Pull out the facepiece headband straps so that the ends are at the buckles and grip facepiece between the thumb [
and fingers. Insert chin well into the lower part of [ the facepiece und pull the headbands back over the head. To obtain a firm and comfortable fit against the i-facepiece at all points, adjust headbanda as follows: [ (1) See that straps lie flat against head. f (2) Tighten lower or neck straps.
. . (3) Tighten the side straps (do not touch forehead or l
,' front strap). (For half facepiece the upper strap ,!'
. is positioned just above the ear).
REFERENCE ONLY
WUCtOUHg W l 48'P**JV4 E. l. HATCH NUCLEAR PLANT i:NP-8010 l See Page 1 aiviseu w , um 12 Georgia Power ~~ l See Page 1 o 13 of 38 1 t (4) Place both hands on headband pad and push in [' toward the neck. - ( (5) Repeat Steps I.8.b (2) and I. 8.b. (3) . ll (6) Tighten forehead or front straps a few notches if b necessary. , l, (7) Check for proper seal using the field testing procedure in subsection K.2.
- 7. Removing the facepiece
- a. After using the respirator remove the outer pair of contaminated gloves. Bend your body forward at the waist until the chest is parallel to the floor. Then remove the facepiece by grasping the cartridge housing l and lifting outward. (For airline respirators and SCBA's, grasp breathing tube connection at the j facepiece), i CAUTION Care should be taken when removing respirator to insure i that opan areas of the face do not become contaminated ;
from contact with the equipment. AVOID UNNECESSARY i JERKY MOTIONS WITH THE FACEPIECE AS ANY CONTAMINATION l MAY BE SHAKEN OFF AND ON TO YOU. [
- b. Place facepiece along with all associated respiratory
- equipment in a deisgnated location for survey and cleanup. DO NOT pla'ce in contaminated clothing storage f
l I l drums. I l WARNING 1 Raspiratory equipment is a personnel safety device and l should not be mistreated (i.e. thrown, kicked, dropped, [. mutilated). Personnel found abusing this equipment will receive disciplinary action. b ! y
- c. Survey yourself for contamination, making a very ,
j thorough survey of the face and head. If contamination I is found contact Health Physics immediately. h t l , l ., REFERENCE OHLY
~ -
1 arPMovAt PHULLDUHt NO E. I. HATCH NUCLEAR PLANT HNP-8010 See Page 1 mvan w can 12
~~
See Page 1 Georeia v Power 14 of 38 s . J. TRAINING OF PERSONNEL ;
- l. Initial Training j All personnel will be trained in the use of respiratory equipment prior to being allowed actual use of the equipment 8 in work conditions. The instructor for the training will have a thorough knowledge of the application and use of respiratory protective equipment and of the hazards associated with radioactive airborne contaminants.
- a. Contents of the instruction (1) Training in the use of respirators will consist of '
covering those items as specified in NUREG-0041 Section 8.3 CONTENTS OF TRAINING PROGRAM. i (2) Video Tape (s) on respiratory protection will be h viewed by personnel, where practical. Oral instruction will be given using a Plant Hatch lesson plan supplemented by an Instructor's Discussion Guide.
- b. Docum5ntaion s
(1) Training will be documented on Form 1, Respiratory Protection Training. 2.- Retraining i . It is the intent of the respiratory protection program to -
- ~ insure a high degree of proficiency with the respiratory l protective equipment.
'A periodic evaluation will be made to assess an individual's I knowledge of the' equipment and its use. This assessment l will be in the form of a written examination concurrent to l the annual Health Physics review and will be based on those l l , items'in paragraphs 8.3 a-i of NUREG-0041 and the l l Instructor's aids as described in J.l.a. (2) . After this f' periodic review those persons that require additional inntruction will attend a lecture based on the criteria /
described in HNP-6018E. and HNP-203C 1 K. FITTING AND TESTING
- l. Initial Fitting and Testing l
- a. Each person requiring the use of a respirator will be I individually fitted for the particular facepiece prior I
- to being allowed use of the respirator equipment. No '
person with facial hair interfering with the respirator seal area will be fitted and tested. n1anual set . Lt ' REFERENCE ONLY !
m am.vvd4 PROCEDUM PeO See Page 1 E.1. HATCH NUCLEAR PLANT HNP-8010
%,um w am 12 See Page 1 Georgia o
Power ~~ 15 of 38
- b. Anthropometric measurements (face length, face width, and lip width) will be taken to identify persons who fall outside of the 95% limits of facial measurement.
Any facial abnormalities will also be noted. This information will be documented on Form 2 and will assist in identifying those persons who might have more difficulty in obtaining a good seal with a respirator. >
- c. A qualitative test will be performed for each type of facepiece as follows:
(1) The person dons the respirator with an organic cartridge attached. (2) The person checks the facepiece seal using the negative pressure test as described in NUREG-0041 paragraph 8.5.2.3.3. (3) The instructor will test the fit during normal treathing by waving a cotton or stencil brush tilled with isoamyl acetate gently near the periphery of the facepiece. Smoke tubes, when hvailable, may also be used. [ If odor is detected, . the wearcr must re-adjust the facepiece and the ' test redone. NOTE
\
When practical, a test chamber will be used in lieu of the cotton or stencil brush. Evaporate about 173 i milliliters of isoamyl acetate for each 1000 cubic feet f of room volume. (Do not use heat for evaporation) . (4) The instructor may then have the wearer perform the following movements: (a) deep breathing ~ (b) moving head from side to side (slowly) (c) moving head up and down (slowly) (d) frown (for full face masks only)
, (e) talking (e.g. , speaking a short passage aloud) '
(f) normal breathing. (5) The instructor will then re-check the seal with [.,. isoamyl acetate or smoke tube. i c REFERENCE ONLY rnanual set I s I
ugg P640CLDU6*L PeQ E. I. HATCH NUCLEAR PLANT HNP-8010 : See Page 1 aavun ~o ou, 12 h Georgia Power - i See Page 1 o 16 of 38 (6) If the tests are accepta'ble (no leakage) it will L be documented on Form 2. . I
- 2. Field Testing .
- a. Where practical, respirators will be tested in the field using either amyl acetate or irritant smoke (Half l face masks must be tested prior to use each time it is (
donned using irritant smoke.
- b. Where it is impractical, a negative pressure test will 4 be performed as follows:
(1) Close off the inlet opening of the canister or g breathing tube by covering it with the palm of the j hand (2) Gently inhale so that facepiece collapses slightly. l (3) Hold breath for 10 seconds. (4) If facepiece remains in slightly collapsed 1 condition and no inward leakage of air is l detected, the tightness of the respirator is satisfactory. ! (5) If unsatisfactory do not use the respirator and [ contact Health Physics. l t L. MEDICAL REQUIREMENT I All personnel who wear respirators will be evaluated by competent i medical personnel prior to an assignment requiring such use. The evaluation will determine if the individual is physically able to perform the work and use the respiratory protective equipment. A (! l physician will determine what health and physical conditions are ' pertinent. The medical status of each respirator user will be reviewed annually. . M. BIOASSAYS AND SURVEYS -
- 1. Air sampling and contamination surveys ,
A comprehensive air sampling and contamination survey program is in effect to identify radioactive hazards to n' evaluate individual exposures, and to permit proper selection of respiratory protective equipment. Surveys are performed on a routine and special basis per r.he use of procedures HNP-8013, 8012, 8008, 8005, 8050 and applicable , instrument operating procedures. High-efficiency (greater l than 99%) filter media are used to measure airborne ! particulate concentrations. Activated charcoal is used to - determine radio-iodine concentrations, nianual set . REFERENCE ONLY
l l. m.,g wwt %J ! E.1. HATCH NUCLEAR PLANT HNP-8010 See Page 1 -e.u - ~u me 12 GeorgiaPower A -
~
See Page 1 o 17 of 38 l
- 2. Bioassays NOTE Refer to HNP-8021 and 8009
- a. Whole body counting -
(1) It is the intent to obtain a whole body count or urinalysis on each G.P.C. employee who may have exposed to airborne radioactivity at least once each year. (2) Whole body counts will also be made where suspect I internal contamination has occurred.
- b. Urinalysis (1) A fission product and tritium analysis will be performed routinely on selected personnel who may have been exposed to airborne radioactivity.
(2) The above analysis will also be made, when deemed necessary, where suspect internal contaaination L has occurred.
- c. Nasal, throat swabs or washings and breath samples will !,,
be performed as necessary on suspect inhalation cases i to serve as a qualitative exposure index for radionuclides.
- d. Follow up sampling (Whole body, urinalysis, nasal p throat swabs, breath samples, etc.) will be performed o and will be frequent enough to evaluate the uptake of i radionuclides after an incident. The sample collection i will be appropriately timed to permit accurate evalization of the total intake and the resultant dose. ,
l NOTE . It is noted that there are extenuating circumstances which may prevent whole body counting of all personnel affected by this procedure. Such situations as persons leaving the plant site without proper notification to - the management, whole body counting equipment malfunction at critical counting times and schedul.ing impossibilities will prevent a 100% wholo body counting program. The frequency of these events, should not diminish the overall effectiveness of the bioassay 3
- program however.
J
"~ ~ "'!C~
' ' ' ~
'GNLY i:
R1anual Set
. ._n a
-~
E. l. HATCH NUCLEAR PLANT HNP-8010 l See Page 1 ate w wa 12 <
~~
See Page 1 Georgia Power 18 of 38 g N. RESPIRABLE AIR REQUIREMENT
- l. All breathing air supplied by air compressors and bottled (
g air will meet the minimum requirements of Grade D air as Q prescribed by the Compressed Gas Association or better. f Refer to NUREG-0041 page 5-19 for limits.
- 2. Samples of air from air supply sources will be taken on a 45 day frequency and mailed to an outside laboratory for testing.
- 3. Oxygen and breathing air are not to be used in the same apparatus.
- 4. Proper fittings will be used with supplied air equipment. '
- 5. Oxygen shall never be used with air line respirators.
O. INSPECTION AND MAIN'rENANCE ] All respirators shall be inspected routinely before and after f each use. A respirator that is not routinely used but is kept [ ready for emergency use shall be inspected after each use and at , least monthly to insure that it is in satisfactory working I condition. All routinely used respirators shall be inspected before and after use and at least monthly and shall have an inspection sticker. I An inspection sticker shall be attached to each emergency respirator container and respirator and a record of inspection l kept en Form 3, Respirator Monthly Inspection Report. Any , respirator not meeting inspection acceptance shall be repaired or replaced. Respirators will be repaired only by personnel designated by a laboratory supervisor. l
- 1. Facepiece and breathing tube (SCBA & Constant Air Flow)
- a. Inspect the facepiece and breathing tube for signs of mechanical damage, deterioration, cracking or rupture.
Tears occur most frequently about strap attachments, outlet valves and hose. Discard equipment damaged in this manner.
- b. o Check the protective tape and metal ~and bindings for I:
, deterioration. Replace as necessary. l
- c. Inspect the tab assemblies on the facepiece used for i attaching head straps. All buckles should.be present i
. and in good operating condition. l I -
- d. Check the lens for looseness and damage. Discolored or damaged lens should be replaced.
l . x manual set
- i. o REFERENCE ONLY
l
/M MU d4 PI*UCkUVH1 NO E. l. HATCH NUCLEAR PLANT HNP-8010 See Page 1 we%.v o
~
Geobia Power d 4 See Page 1 19 of 38
- e. Inspect the exhaust valve for proper sealing of the rubber diaphragm. Replace as necessary.
- f. Check breathing tube connections'for deterioration and damage and tightness. Repair or replace as necessary.
- 2. Custom Comfo Aerosol-Filter Respirator In addition to Step 1, just prior to use check that the type of cartridge is correct and that the cartridges are screwed into the respirator securely. Examine the cartridge for damage.
- 3. Ultra Filter Respirator-Full facepiece. In addition to Step 1, just prior to use:
- a. Check that the type of cartridge is correct and that f the cartridge is coupled to the respirator securely.
- b. Examine the cartridge for damage and check that the ,
inlet seal has not been removed. [
- 4. Pressure Demand Apparatus (Air Pack)
In addition to Step 1, perform the following: P .
- a. Check for proper operation of cylinder valve assembly,
- b. Check main pressure gauge for proper operation and that air cylinder is full.
- c. Inspect condition of hose connection and hose to cylinder valve assembly. If hose is cracked replace it. )3
- d. Check operation of Main Line (yellow) valve by operating it.
- e. Check operation of low pressure alarm monthly by closing cylinder valve and cracking the Main Line (yellow) valve open. This should let the pressure decay off so-the alarm should sound at about 540 psi.
- f. Check operation of regulator bypass (red) valve by l operating it. l l
- g. Inspect all belts for signs of fraying. Inspect around b side strap buckles. l f
S. Constant Flow Air Line Respirator-In addition to Step 1 I l perform the following:
- j . a. Check the operation of all couplings by mating them to
- working couplings. ,
REFERENCE ONLY manual set rm _. _ . _ . _ _ _ -#
.c .
L i, mg PHOLEDUHt NO E. l. HATCH NUCLEAR PLANT HNP-8010 See Page 1 at <** w o.n 12 Georgia Power ' ' ' ' ~ See Page 1 o 20 of 38
- b. Check all hoses for cracks and leaks.
- c. Connect the portable air filter regulator to an air supply and check operation of the gauge, filter, i regulator and inlet and outlet couplings. Check the filter trap for moisture. Pressure gauge should read
- 35-40 psig.
NOTE 4 Filter media for filters will be changed after each refueling outage for the units used during the outage. t
- 6. Pressure Demand Air Line Respirator (Bottle Air) ;
i In addition to Step 1 perform the following: ,
- a. Check the operation of all couplings by mating them to working couplings. .
- b. Check all hoses for cracks and leaks.
- c. Connect the high pressure regulator on the high !
pressure air cylinder to be used and check operation by [ turning air on and adjusting regulator for 80-100 psig.
- 7. MSA 401 aCBA Inspection Checklist
- a. Check lists are inluded in each 401 SCBA Air Pack Unit.
i b. Refer to the checklist while performing the monthly inspection. Comply with each item listed. See Form 5. I
- 8. S.C.B.A. Breathing Air Tanks (Model 401 Air Pack).
[
- a. Each steel tank will be hydrostatically tested to 3360 !
psig, on a 5 year frequency. i
- b. Each aluminum and fiberglass tank will be
! hydrostatically tested to 3360 psig on a 3 year frequency. l c. Form 4 will be used as a master list for determining I i when the testing will be performed. d l
- d. Testing documents will be filed in the Document Room.
- 9. Semi-Annual MSA 401 Regulator Testing. .
. a. Each regulator will be tested every six months using the MSA Portable Regulator Testor.
i, REFERCHec ^'ny nianual set
. - , . - o- -
E.1. HATCH NUCLEAR PLANT HNP-8010 See Page 1 aiv w . w om 12 Georgia Power ~~ See Page 1 0 21 of 38
- b. Once the regulator passes all the tests as described in the MSA Portable Regulator Testor Manual an inspection sticker will be place on the regulator bearing the date it was tested.
- c. In the remarks section of the monthly respirator inspection sheet FORM 3 for the particular MSA 401 that is being tested, note it was tested and that it passed or failed its test.
NOTE Only personnel trained and certified by MSA will be approved to test or repair MSA 401 Regulators. P. CLEANING AND SANITIZING
- 1. Monitor entire equipment as soon as possible after use to determine level of contamination. Pay particular attention to filters, exhaust valve housing and straps.
NOTE If necessary, facepieces may be re-issued to the same person on the same day if the following limits are not exceeded on any surface of the facepiece. Beta-gamma-0.2 millirad per hour above background at contact. Alpha-100 d/m/100 cm2 i l
- 2. Facemask and breathing tube.
The facepiece and breathing tube assembly of respirators l must be cleaned, sanitized, dried, surveyed and inspected ' after eact. day's use as follows: l
- a. Add one package of powdered MSA Cleaner-Sanitizer per gallon of warm water (about 120. degrees F.).
]
- b. Immerse equipment in the solution and scrub ~ gently with a soft brush until clean. Take care to clean the exhalation valve in the facepiece and all other parts
, that exhaled air contacts. A dishwasher may be used in lieu of hand cleaning.
- c. Rinse in plain warm water (about 120 degrees F.) and
, then air dry.
O
- t. REFERENCE ONLY
I Awnuv4 PHQCtQU54t NO E. I. HATCH NUCLEAR PLANT HNP-8010 See Page 1 sev w . w o.,t 12 Georgia Power ~~ See Page 1 o 22 of 38 NOTE Do not fold head straps in front of face piece for storage.
- d. Survey the equipment for radioactive contamination.
The facepiece and breathing tube (s) must be decontaminated to levels not exceeding 50 dpm/100 cm2 fixed alpha and 1000 dpm/100 cm 2 of beta-gamma above background at contact on any accessible surface using a standard smear survey technique. Fixed Beta-Gamma radioactivity at contact shall not exceed 0.2 millirad / hour. l e. Place routinely used facepieces after inspection in a l clean plastic bag and store in their assigned storage ! locations. (During periods of high usage it will be ! acceptable to delete the clean plastic bag storage requirement) . Place respirators assigned for emergency use only, after inspecting, in the compartments built for them and return them to their storage locations.
- NOTE
? Respirators should be packed or stored so that the facepiece and exhalation valve will rest in a normal position and function will not be impaired by the elastomer setting in an abnormal position.
- 3. Other equipment (harness, regulator, air cylinder, hose) .
- a. Remove the used air cylinder from the Pressure Demand
! Apparatus (Air Pack) and decontaminate by wiping with a wet pad of Cleaner-Sanitizer solution and then with a dry pad. l l b. Wipe down harness, breathing bags, regulator and hone with wet pads as necessary to reduce the transferable i contamination to less than 1000 dpm/100 cm2 l beta-gamma and 50 dpm/100 cm 2 alpha. l l c. Survey equipment after drying to verify contamination i levels do not exceed those in Step P.3.b. l
- d. Attach a fully charged cylinder to the harness and regulator assembly of the Pressure Demand Apparatus (Air Pack).
- e. Store equipment in their designated areas' .
REFERENCE ONI.Y
- ri a m ~o See Page 1 E. l. HATCH NUCLEAR PLANT HNP-8010
_.Riv@QN NO See Page 1 GeorgiaPower A ,
~~
,3 ,,
Q. REVIEWS AND RECORDS ,
- 1. A laboratory foreman will routinely review respiratory practices and procedures to assess the program effectiveness.
- 2. Timely assessments of a particular individual's intake will be made if and when required and adequate records will be maintained for summary review and evaluation. ,
- 3. If an individual's intake exceeds 40 MPC hrs. in seven consecutive days an evaluation will be made and action taken to assure against recurrence. Records of the occurrence, evaluations and actions taken will be kept in a clear and readily identifiable form suitable for summary review and evaluation. Radiation Occurrance Forms (HNP-8005),
Personnel Contamination Report (HNP-80 0 9) , Radiation Work Permits (HNP-8008) in addition to survey records, bioassay results, etc. make up most of these records. O* I l e 9 t 6* e REFERENCE ONLY
e _, u+aon mctovat no 1
^
E.1. HATCH NUCLEAR PLANT HNP-8010 See Page 1 "" * * "o i me 12
~ ~o See Page 1 Georgia Power 24 of 38 l APPENDIX I SECTION TITLE PAGE NO.
A Purpose 1 B Safety 1 . C References 1 D Management Policy 1 E Regulatory Requirements 2 g
^
F Description of Respirators 2 4 I G Selection of Respirators for Use H Control Issuance, Proper use, and Return [ of Respiratory Equipment 6 3 I Using the Respirators 8 J Training of Personnel 14 K Fitting and Testing 14 L Medical Requirement 16 M Bioassays and Surveys 16 N Respirable Air Requirement 18 L O Inspection and Maintenance 18 P Cleaning and Sanitizing 21 Q Reviews and Records 23 Tables:
- 1. Protection factors for respirators 26
-__-_____ _____-______________________________n__-___________ ___-______
f
- 2. Airborne concentration limits for 28 Forms:
1
- l. Inspections of 401 SCBA 29
- 2. Respiratory Protection Training -_____-___
30 5 9 6 l l REFERENCE CNI.Y
--- NDUM PeQ E. I. HATCH NUCLEAR PLANT HNP-8010 See Page 1 Geo la Power d ~~
25 of 38 See Page 1 APPENDIX I (CONTINUED) SECTION TITLE PAGE NO.
- 3. Respirator Monthly Inspection Report 31
- 4. MSA Respirator (Model 401) SCBA (Tank Hydrostatic Test Master List) 33
- 5. MPC-HR tracking (Yearly) 35
- 6. Respiratory Issuance 37 a ___________________________________.. _______________-_______________
l e e b e S 4
- e O-o mailual set
- REFERENCE CNLY _ _
g g PROL&QUHt W E. l. HATCH NUCLEAR PLANT HNP-8010 See Page 1 atve w
~
See Page 1 Geo ia Power d ~~ 26 of 38 TABLE 1 . PROTECTION FACTORS FOft RESPIRATORS 8 - - PROTECTION SELECTION OF TESTED FACToltSd A CERTirirD TOl'IPalt:NT PARTICU- l'A R T IC L,*- lxRLAU OF .\ltNI.S NN180NAt. l.ATrS !.All S. GASES INST 11L'1E FOR OCCLVATIONAL DFSCRIPTION b BIODrSC O Nt.Y A VAPORS < STri TV AND Ill'AI.lt! APPROVAI.S
- j. AIR.PL*Rll YING RTSPIRATORS -
Facepiece, half maska NP- 10 Facepiece, full NP 50 30 CTR Part,Il Subpart K racepiece, half mask, full, or hood PP 1000 li. AT3f0SPitrRINSL'PPLYING RTSPIR \ TORS
- 1. Air bne respirator racepiccc, half-mask CF 1000 facepiece, half-m ast D 10 racepiece, full CF 2000 Facericce full D 30 30 CFR Part 11 Subpart J racepiece, full PD, 2000 llood CF 20008 Suit ' CF h j l
i 2.Scif<ontained breathing apparatus (SCBA) Facepiece, fu11 D SO Facepiece, full PD 10,000) 30 CFR Part !! Subpart !! Facepiece, full R 50 l ~ l III. CO\fillNATION RTSPIRATOR ' l Any combination of air purifying Protection factor for
, and atmosphere-supplying type and ruode of operation respirators 30 CTR Part i1 I II.63(b)
; as listed above I
i
-For use irt the selection of respiratory protective devices to be 2. The protection factors apply:
used where the contaminant has been identified and the j concentration (or possible concentration) is known. (a) Only for trained indisiduals wer ing Froperly fitted
,b respirators used and maintained under supervision in a Only for shasen faces and where nothing interferes with the well-planned respiratory protectise program.
, wal of tiyht-fittirg facepieces against the skin. (floods and I suits are excepted.) (b) For air purifying respirators only when high efficiency
, particulate filters [ abase 99.97% removal efficiency by
, 'The anode symbols are defined as fo!!ows:
I thermally generated 0.3 um dioetyi ;hthalate (DOP) testj ' are used in atmospheres not deficient in osyren and not l CF = continuous flow containing radioactise gas or vapor respiratory hazards. D= demand I NP= negative pressure (i.e., negative phase during inhala. } (c) for atrnosphere surplying respirators only w hen j l tion) supphed with adequate respitable air.. I PD = pressure demand (i.e., always positise pressure) FF
- Positne pressure ' Excluding radioactive contaminants it at present an absorption '
R* demanJ, recirculating (closed circuit) or submersion hazard. For tritium oside, aPrrosimately one g half of the intake occurs by absorption through the skin so i
- 4. The rrotection factor is a measure of the degree of prote'e. that an oseralt proteetton f4eter of less than 2 is appropriate l l tion afforded by a respirator, defined as the ratio of the when atmosphere suppl)ing respirators are uwd to protect concentration of suburne radioactive material outside the against tratium oude; for example:
8e 'rtr J tor) protectne equipment to that inuJe the equip.
- ment (i.sually andde the IJeepiecel under conditions of ,
'"c it 85 ap;ihed to the ambient airberne concentratwn to If the protection factor PF overall for tritium ,
estete the concen tration inhaled b) the wearer ac. for a dence is: ox,ide is: evideng to the follo* mg formula: { 10 1.82 Conceauation Inhaled . Ambint Airborne Concentration 100 3.98 ) Protectwn Factor 1,000 l.99 manual set
~
REFERENCE ONI.Y
PPPHWAt PHOGtDUHL NO E. I. HATCH NUCLEAR PLANT HNP-8010 See Page 1 ,,ivw, ,,o om 12 Georgia Power - See Page 1 0 27 of 38 TABLE 1 (CONTINUED) be overcome if a short cape.like estention to the hood is worn under a coit or coveralls. Other lunitalwns specified by fr purifying respirators are not suitab!c for protection fc appr val agency snust be considered twtore uung a bootl 8" against tritium o xiJc. See also lootnote g concerning turers tam supphed air suits. rectymmended Ns of atmospheres (see fqtnore pressure settmes hL air for the Stanuf.sc. supply cannot always be rehed on to ensure a mmimum 6 cfm air IUnder chin type only. This type of respirator is act satisfac, fl w. Equipnient ruust be operated in a manner that ensures tory for use where at might be possible (e.g.,if an acodent or pr per flow rates are mamtamed, emergency were to occur) for the- amtnent anborne h Appropriate protection factors must be determined, taking concentration to reich inuantaneous values greater than 10 nto Jccount the des
- 1 of the suit and its permeabahty to the times the pertinent values m sause i,to&mn I ot' Appendtx contaminant under conditions of use.
B to 10 CIR Part 20, " Standards for protestion Agamst Radiation." This type of respif,4 si not suitable for protec. I No approval schedules are currently availab!c for this equip. tion against plutomum or otiu: ryt.tosicity materuls. The ment. Equipment is to be natuated by testarig or on the baus snask is to be tested for fit wit .. tant smoke, prior to use s of reliabic test information. each time it is donned. . Ifhis type of respirator may provide greater protection and be 8The design of the supplied. air hood or helmet (with a used as an emergency deviec m unknown concentrations for minimum flow of 6 cfm of air) may determme its overall protection agamst mhalation haza rd s. External radution efficiency and the protection it proudes. For example, some hazards and other hmitations to permitted exposure such as hoods aspirate contaminated air into the breathmg zone when skin absorption must be taken into account in such circum-the wearer works with hands-over. head. Such aspirstwn may stances. { v l e-a i i Note I: Protection factors for respirators, as may be approved respirators for such circumstances should take into account by the U.S. Ilureau of Mines / National Institute for Occupa. apphcabic approvals of the U.S. Bureau of Mines /NIOSil. tional Safety and llcalth (NIOSil) accordin;; to applicable , approvals for respirators to' protect against airborne radio. Note 2: Radioactive contaminants for which the concentration ' muclides, may be used to the extent that they do not exceed values in Table I of Appendix 11 to 10 CFR Part 20 are based the protection factors listed in ttus table. The protection on internal dose due to inhalation may, in addition, present factors bsted in this tab!c may not be appropriate to circum. external exposure hazards at higher concentrations. Under such stances where chemical or other respiratory hazards exist in circumstances,, limitations on occupancy may have to be addition to radioactive harards. The selection and use of governed by external dose limits.
- 4
. i i
s i 1
. l
[ e REFEREHU om,y
- t my ee wum w HNP-8010 See Page 1 E. I. HATCH NUCLEAR PLANT *vem
- 12 wt
~~
Georgia Power 28 of 38 See Page 1 o TABLE 2 AIRBORNE CONCENTRATION LIMITS FOR RESPIRATORS AIR PURIFYING RESPIRATORS
- AIRBORNE CONCENTRATION Full facepiece w/ type H Particulate activity less than Ultra filter cartridge 40 times MPC ATMOSPHERE SUPPLYING RESP.
- 1. Air line respirators Full facepiece-constant flow - Particulate, gas, and vapor activity less than 1600 times ,
MPC Full facepiece-pressure demand- Particulate, gas and vapor , activity less than 1600 times MPC Hood-constant flow - No credit allowed unless hood , is BM/N10SH approved. See the laboratory foreman. Suit - constant flow - No credit allowed unless suit is BM/N10SH approved. See a laboratory supervisor {
- Air line and air purifying respirators can only be used in atmospheres not immediately hazardous to life or health.
- 2. Self-contained breathing apparatus (SCBA)
MSA Air Pack Model 401 pressure - Particulates, gas and vapor activity less than 10,000 times MPC. However, may be used in emergency conditions
- in unknown concentrations of airborne activity. Must also consider external radiation hazards and other limitations (skin absorption, etc.) .
O O e
- Rsrsngnce egy manual set
&W MQWat PHf.LtDUM NO E.1. HATCH NUCLEAR PLANT HNP-8010 See Page 1 %,y, uo a.u 12 See Page 1 Georgia Power ~~
l 0 , 29 of 38 FORM 1 INSPECTION OF 401 SCBA
- 1. Items of inspection on facepiece and breathing tube.
- a. Insure facepiece is a 401 mask with spring loaded exhaust valve.
- b. Mechanical damage.
- c. Cracking or ruptures.
- d. Tears around strap attachments, outlet valve and hoses,
- e. Deterioration metal band bindings.
l f. Stuck exhaust valve.
- g. Damaged exhaust valve.
- h. Deterioration, damage, tightness of breathing tube,
- i. Missing clips on face lens.
- j. Cracking or deterioration of gaskets between facepiece, hose, regulator and hose.
- k. Insure all straps on facepiece or adjusted fully out.
- 2. Items of inspegtion on Pressure Demand Apparatus (Air Pack) .
- a. Insure cylin' der is full. ~
! b. Inspect cylinder for physical damage. l c. Damage and proper operation of cylinder valve assembly.
- d. Damage and proper operation of low pressure alarm. (540 PSI)
- e. Damage to connections on hose from cylinder to regulator.
- f. Damage and proper operation of pressure gauge on tank.
9 Cracks in hose from regulator to cylinder.
- h. Operation of main line (Yellow) .
- i. Operation of bypass line (Red).
- j. Check air tightness by pressure drop (see section I.6.d.&
- e. ) .
- k. Unusual sounds in the regulator (whistling, chattering, clicking, or rattling).
- 1. Damage and proper operation of the pressure gauge on the regulator.
- m. Physical or mechanical damage to the regulator.
- n. Fraying of belts and straps on harness.
- o. Insure all belts and straps are adjusted fully out.
- p. Insure all buckles will work properly.
- g. Insure cylinder is in the harness correct.
Q O e
- 01anual Set (3 REFERENCE OtHN
,,- . ~wn -
E.1. HATCH NUCLEAR PLANT mp-nolo eno pano 1 " " ' * " "
.. -- ~
Georgia Power o g ~~ See Page 1 3n of 7n FORM 2 RESPIRATORY PROTECTION TRAINING DATE: The following person has received instruction in Respiratory Protection covering the subjects specified in section J of HNP-8010 for respiratory protection equipment as indicated below: NAME I.D. BADGE NO. FITTED & TRAINED TESTED ACCEPTABLE
- 1. MSA ULTRA FILTER (Full Mask with cart- /
ridge) 1. 1. 1.
- 2. MSA PRESSURE DEMAND APPARATUS (AIR PACK)
- 2. 2. 2.
- 3. MSA CONSTANT FLOW AIR LINE RESPIRATOR
- 3. 3. 3.
I have been advised that I may leave an area when using a respirator at any time for relief from respirator use in the event of equipment malfunction, physical or psychological distress, procedural or communication failure, significant deterioration of operating conditions, or any other condition that might require such relief. TRAINEE SIGNATURE
- Trained: Student initials indicate instructions have been received. )
** Fitted and tested: Instructor initials indicate student has been fitted and tested in a challenge atmosphere with acceptable results.
*** Acceptable: Instructor initials indicate student has been classroom trained, fitted and tested in a challenge atmosphere with
! acceptable results, and has successfully passed the written exam. Anthropometric Facial Measurements: Medical Approval on File k L Initial Face length mm i Face Width mm *
/
- Lip Width mm Facial Abnormalities !
- 1. Facial hair
- 2. Shape & size of nose
- 3. Weak jaw without a clearly defined menton l 4. Hollow temples or cheeks, scars, excessive wrinkles
- 5. Missing dentures -
l COMPLETED BY DATE l
' manual set
(. ame.no oiny . -. _
PEEggyK1Ng MMAL E. l. HATCH NUCLEAR PLANT HNP-8010 See Page 1 Atv4M NO see Page 1 GeorgiaPower A ~~ 31 of 38
* ~'
+
PROCEDURE DATA PACKAGE
)
1 ~ i DOCUMENT NO: HNP-8010 1
' SERIAL NO: R12 .
MPL NO: N/A RTYPE: G15.14 1REF: N/A TOTAL JHEETS ,2 FREQUENCY: Monthly COMPLETED BY
? ATE COMPLETED:
I HAVE REVIEWED THIS DATA PACKAGE FOR COMPLETENESS AND AGAINST ACCEPTANCE CRITEPfA IN ACCORDANCE WITH HNP-830. , ACCEPTANCE UNACCEPTABLE i i REVIEWED BY: i DATE BEVIEWED: REMARKS: l
,--=........
l l
- Page 1 of 2 M*
I ,HNP+8010 l i FIGURE 1 Page 1 of 2 REFERENCE ONLY manual set
AWHOV AL NUuMt PeO See Page 1 E. l. HATCH NUCLEAR PLANT HNP-8010 eevism uO o^'t 12 See Page 1 Georeia U Power ~ ~o 32 of 38 DATA PACKACE 1 FORM 3 RESPIRATOR MONTHLY INSPECTION REPORT Respirator No. Respirator Type
! Location DATE A3 FOUND AS LEFT REMARKS INITIAL (NOTE lj (NOTE 2) e s.
l I i NOTES 1. A- T.cceptable
, N- 4 . Acceptable (If not acceptable, explain in l
REMARKS. Also give corrections / repairs made).
- 2. A- Acceptable (This is the ONLY Condition these respirators must be left in). j l
Page 2 of 2 ,~ HNP *010 P l I FIGURE 1
, manual Set I
_ REFERENCE ONLY_
dJV680VLL SHUl.t DUHL NO E. I. HATCH NUCLEAR PLANT HNP-8010 See Page 1 ,,i ,,, ,,o uut 12 See Page 1 Georgia o Power ~ ~o 33 of 38 PROCEDCTRE DATA PACKAGE DOCUMENT NO: HNP.8010-2
' SERIAL NO: R12 MPL NO: N/A RTYPE: C15.14 XREF: N/A
( TOTAL SHEETS ,2 FREQUENCY: Month 1y 4 COMPLETED BY DATE COMPI.ETED: e, I HAVE REVIEWED THIS DATA PACKAGE FOR COMPLETENESS AND AGAINST ACCEPTANCE CRITERIA IN ACCORDANCE WIT;! HNP-830. ACCEPTANCE _ _ UNACCEPTABLE REVIEWED BY DATE REVIEWED: 6 REMARKS:
~
4 1
~
=_- _ --- - - = . . . .
Page 1 of 2 . I 1. FIGURE 2 l Page 1 of 2
' manual set l i
REFERENCE ONLY
/- ., PROctDVHLPeo E. I. HATCH NUCLEAR PLANT HNP-8010 See Page 1 HtVISK)N NO See Page 1 Georgia Power d ~~ 34 of 38 DATA PACKAGE 2 FORM 4 , MSA RESPIRATOR (MODF* 401) S.0.3.A. TANK HYDROSTATIC TE.it MASTER LIST FIVE YEAR TEST TEN YEAR TEST RIMARKS TANK HYDROSTATIC DATE HYDRO. HYDROSTATIC ' DATE HYDRO NO Test Date Req. Test Date IReq. l s f i 6 4 j 1 l
~
s Page 2 of 2
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[ FIGURE 2 Page 2 of 2
, manual set REl'ERENCE ONLY
.- --~
E. I. HATCH NUCLEAR PLANT HNP-8010 See Page 1 y ,,o w o st 12
~~
See Page 1 Georoia 0 Power 35 of 38 i
......................- _- _- . =
} , _----
t PROCEDURE DATA PACKAGE DOCUMENT NO: HNP 8010 3 l SERIAL NO: R12 MPL NO: N/A RTYPE: G15.14 XREF: N/A I TOTAL SMEETS: 2 FREQUENCY: As Required COMPLETED BY: DATE COMPLETED:
' I HAVE REV!EhED THIS DATA PACKAGE FOR COMPLETENESS ~,
AND AGAINST ACCEPTANCE CRITERIA IN ACCORDANCE WIYE HSP-830. ACCEPTANCE UNACCEPTABLE REVIEWED BY: DATE REVIEWED: l l RE%RKS : h r . 1 ! l 0 l
----__-- - _.......= _---- _ ---- - .................._
. Page 1 of 2 -
HNP-8010 R12 { k FIGURE 3 Page 1 of 2
' manual set - REFERENCE ONLY -_--._s
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E. l. HATCH NUCLEAR PLANT HNP-8010 See Page 1 ,,,,% oa't 12 See Page 1 Georgia Power ~~ 0 36 of 38 Nf/$" 3 .
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AWHO'fAL PHULt DUHg NO E. l. HATCH NUCLEAR PLANT HNP-8010 See Page 1 sey,o so uAre 12 See Page 1 Georgia Power ~ ~o 0 37 of 38 u -. ..._ . _ _ . PROCEDURE DATA PACKAGE I, DOCUMENT NO: HNP-8010-4
' SERIAL NO: R12 MPL NO: N/A l
l RTYPE: G15.14 I XREF: N/A TOTAL SHEETS: 2 I FREQUENCY: As Required COMPLETED BY: I s' DATE COMPLETED: i e-I HAVE REVIEWED THIS DATA PACKAGE FOR COMPLETENESS . AND AGAINST ACCEPTANCE CRITERIA IN ACCORDANCE WITH HNP-830. [ ACCEPTANCE UNACCEPTABLE REVIEWED RY: DATE REVIEWED: REMARKS:
~
e Page 1 of 2 w p-sero U2 FIGURE 4 Page 1 of 2
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, REFERENCE ONI.Y
w- - ,
. . . ~ 6'HUC&DUHt NO E. I. HATCH NUCLEAR PLANT HNP-8010 see Page 1 '* ve ~o Georgia Power d ~ ~o i- .
s,o page 1 38 or 38 L 1 DATA PACKAGE 4 *
- I F5iiM 6 1 RESPIRATOR ISSUANCE l :
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==_- -
-- - ==--
j RESP. NO. ISSUED TO BY RETURNED "O
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C 1 FIGURE 4 y Page 2 of 2 l manual set m m. _ REFERENCE 0NI.Y _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
l } GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PROCEDURE Protective Cloihing Drs=nning and Undressing ' PROCEDURE TITLE HNP-RO11 : PROCEDURE NUMBER Lab ! RESPONSIBLE SECTION - t t, SAFETY RELATED ( ) NON-SAFETY RELATED ( X ) i. I K I ( APPROVED APPROVED ! REV. DESCRIPTION DtiPT. PLANT DATE ', HEAD MANAGER ______m____________________._________ ______ .____ _____ __ _. __ __ __ 4
. _General
______ Revision _ _ _ _ _ _ _ _ _ _ _ _ _ ..p __ i,_______ g-
. j _ jg _ _f_l__
( ______s ____________________ _________________.. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ________ (n
- l m
______- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ..________ g c L l'!, 4 ______~ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . .________________.. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ..________ iH if ______ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . .________________.. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ..________ t;- 4 l-
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il J _-____-____________________._________-______ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . ________ I i 1,
" P E" F '} ?" Q /* P HNP 3 R16 i dCl"ChChtC <
2 ONLY MANUAL SET i
Ca+*4Jpt *MCt DUHt W E. l. HATCH NUCLEAR PLANT- W 11 See Title Page to w aus 4 'Q Geo iaPower ~~ 1 of 3 b See Title Page
- h PROTFCTIVE Cl OTMN2_0RFSSING AND UNDRi~ShTNG A. PURPOV To establish a standard technique for dressing and undressing with radiological protective clothing when required by Radiation Work Permit.
B. SAFETY
- 1. Observe Radiation Protection Procedures.
- 2. Observe Requirements of the Radiation Work Permit.
C. DRESSING s
- 1. Remove all outer clothing including watches and tape loose fitting finger rings. Exceptions to this step must be approved by the H.P. Superintendent or his designee.
- 2. Put on canvas shoe covers (booties) over shoes.
- 3. Put on coveralls so that the bottom of the legs are over the shoe covers.
- 4. Place the TLD badge and dosimeter in the outside pocket of the coveralls with the TLD badge window facing away from the body. (The TLD may be clipped to the edge of the pocket).
Close the flap securely.
- 5. Put on hood.
NOTE When the RWP requires a half or full facefrespirator the straps of the respirator should be worn on the inside of the hood. In no case shall the hood be worn between the face mask seal area and the face.
- 6. Put on cotton gloves. ,
- 7. Put on rubber gloves, put up over sleeves of coveralls and tape to coveralls. 1
- 8. Put on rubber boots or rubber overshoes over the' canvas shoe covers. ,
REFERENCE 1 ONty . . o MANUAL SETj
w . oum ~ ; HNP-8011 See Title Page E.1. HATCH NUCLEAR PLANT ,,m... um 4 See Title Page GeoroiaO Power
~~
2 of 3 'I
~
{i NOTE Protective equipment requirement will vary depending on the I type of work in an area, and the contamination present. I Therefore prior to entering the Radiation Control Area check j the Radiation Work Permit to ensure that the required -1 protective-equipment is being worn and that you are properly j dresse.d for-the job. D. UNDRESSING (LtSING DOUBLE STEP OFF-PAD) 4
- 1. Upon approaching the " Remove Rubber Footwear and All Tape i Before Stepping Here" step-off pad, remove all tape and then I renove the rubber boots placing them in the proper receptacle and stepping on the " Remove Rubber Footwear and ,
All Tape Before Stepping Here" , step-off pad. CAUTION Do not put canvas shoe covered foot back on the contaminated floor before placing it on the stepoff pad. M %*, . e, ,g,y ,-
- 2. Remove hood and place ~ it in the proper receptacle.
- 3. Renove rubber gloves and place in the proper receptacle.
- 4. Untie coveralls.
, NOTE Cotton gloves should still be on. At this time if you are wearing a respirator remove it and place it in the proper receptable.
- 5. , Remove your TLD badge L d pocket dosimeter and lay them on the outer edfe of the,5 ten-nff pad or on a table provided.
Handle these devices with finger tips to minimize contamination. I
- 6. Take off coveralls inside-out as not to contaminate the skin or under garments, and place it in the proper receptacle.
NOTE s Canvas shoe _ covers should also be removed at this point while stepping out of coveralls and onto ihe " Remove Protec ti ve Cic th.i ng De f ore Stepping Here" step-off pad.
- 7. nemove cotton gloved und ,, lace in the proper receptacle.
REFERENCE
~
k. ONI.Y MANUAL SET I
7 Mt'64QVAL ,
'%Kl&L ku HNP-SO11 see ritie Pego E. l. HATCH NUCLEAR PLANT <i mio,. w o^'t ^
see Titie eege Georgia Power d ~~ 3 of 3
- 8. Perform a whole body frisk (and your TLD badge and
' dosimoter) with the RM-14 Frisker or equivalent to ensure , that you are not cont amina ted. An instrument. reading 1 greater,than 100 countu per minute above the background count rate indicates contamination. If this occurs, stay l where you are and notify Health Physics. i NOTE ' When frisking youself you should be in a background of less than 300 cpm. ;j s
,' x w
I
' \,
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,f REFERENCE I
/
ONtY MANUAL SET ,
t- .. . m. s ,' m. um c ph m, y.) , E. l. HATCH NUCLEAR PLANT ITNP-80] 2 An g 7
/d - b [/ Georgia Power rA( -
, 1 of 66 RADIATION AND CONTAMINATION SURVpYS A. P
_URPOSE . To provide a procedure for the detection, 'identi fication, and level of activity of surface radioactivity and radiation fields within and outside a Radiation Control Area (RCA). The procedure will be used to define the area involved and to cscertain whether contamination is fixed or removable, so appropriate control meatures can be taken to prevent its spread, thus minimizing the potential exposure of personnel. Instructions are also given for general radiation surveys for determining dose rates. B. SAPETY Observe Radiation Protection Procedures. C. PERCAUTIONS
- 1. Care should be exercised when making direct raeasurements for contamination not to contaminate the instru.nent probe. Hold the probe in near-contact with the area bei'ng surveyed, particularly when surveying for alpha activity, but not in direct contact.
~
- 2. When taking 'a smear survey in a %ghly contaminated area, occasionally check the accumulated smear papers significant build-up of radioactivity. If there is a detectible beta gamma increase, do not carry completed smears in the hand, or close proximity with your hand or body.
D. GENERAL
- 1. Any source of radioactivity introduced inside a person's body becomes an internal radiation hazard. Such exposures can result from loose radioactive material, and they are particularly significant since:
- a. The radioactive material ingested is in direct contact with body cells. -
- b. There is no shielding of the emitted radiation.
- c. The period of exposure becomes continuous until the effective half-life in the body reduces the source strength to an insignificant level. (p ff,GE S01
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wum o HNP-8012 E.1. HATCH NUCLEAR PLANT -own w See Page 1 7
, um See Page 1 2 of 66 Exposures from internal sources may result form such activities as eating lunch with contaminated hands, smoking contaminated cigarettes, or being wounded by a contaminated object, among others. Thus uncontrolled spread of loose radioactive material must be prevented to eliminate any unnecessary internal exposure.
- 2. Radioactive material fixed on surfaces represents a less significant internal hazard, unless such operations as grinding or welding releases it into a spreadable form.
However, fixed radioactive material must be safety controlled to minimize the potential personnel exposure hazard.
- 3. Routine and special radiation and contamination surveys are conducted by Health Physics personnel for the purpose of determining:
- a. The level of radioactivity present in counts per minute or disintegration per minute for the area checked.
- b. The type of radioactive material present (alpha, beta or gamma).
- c. Whether it is fixed or removable or both.
j d. The extent of the area contaminated. i. I e. The dose rate of the area and/or equipment surveyed.
- 4. Routine surveys are conducted with the same frequency and at the same general locations as indicated in Procedure HNP-8050. Direct instrument surveys determine the types of activity present, the extent of surface area involved and the gross level of both the fixed and smearable surface l
l contamination. Smear surveys determine the types of radioactivity being emitted from the removable surface f contamination, and the amount of loose, or smearable, radioactive material. Doce rate surveys determine exposure levels of beta, gamma, and neutron radiation. E. EQUIPMENT .
- 1. Appropriate survey forms as determined by type of survey.
l I I 2. PRM-4A, E-120, or equivalent
- 3. E-400, Teletector, PIC-6A, RO-3A, or equivalent I
- 4. PAC-4G
- s. PNC-4 or PNR l .
- 6. Smear paper or mazzlin cloth
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Georpia Power A ~~ i See Page 1 o 3 of 66 F. DIRECT INSTRUMENT SURVEY FOR GROSS ALPHA AND BETA-GAMMA
- 1. Alpha survey I
- a. Check that the PAC-4G gas proport'ional meter is l operating properly as described in Procedure HNP-8105. r
- b. Place the probe not in contact but within 1/2" of the U
. surface to be surveyed.
NOTE r l The range of the alpha particle in air is generally
- less than 1/2".
- c. Record the results on the appropriate survey maps as ,
- alpha ( ) readings (see Figure 1) or on Figure 3, Radiation survey record.
- 2. Beta and/or gamma curvey i
' ~
- a. Check that the PRM-4A or E-120 is operating properly as described in Procedure llNP-8102 and HNP-8120.
- b. Place the probe (with the beta window open for PRM-4 A) not in-contact, but within 1" of the surface being surveyed,
- c. Record the instrument readings on Figure 1 or Figure 3 as beta-gamma (B- ).
j NOTE j t: l If the instrunent response exceeds 10,000 cpm / probe j dE(g area, the surface should be checked with a dose rate j j meter. ! i I d. In the event contamination is greater than 200 cpm l above background is observed in Steps F. 2.b and F. 2.c, j *%gg then proceed with the following steps.
- e. Close the >Jta shic-ld on the probe, if using PRM-4A.
I (Qg, f. Place the probe in near contact over the same surf aces j surveyed in Step F.2.b. j g. Record the instrument reading on Figure 1 or Figure 3 , as gamma radiation ( ). l I i G. BETA-GAMMA CONTAMINATION SURVEYS USING DISC SMEARS
- 1. Obtain enough disc smears to survey the area involved and clearly mark each for identification.
'2. Gloves should be worn when smears are taken in known contaminated areas. -
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See Page 1 0 4 of 66 I
- 3. Wipe approximately 100 cm 2 of surface area (approximately j 4" X 4") unless otherwise specified.or physically impossible.
- 4. Place smears in sample container bag.or envelope. Smears a must be kept separate from one another.
1 NOTE Wet smears should be placed in separate container bags and dried prior to counting. . 5. High radiation icvels from smears taken inside primary
- system components may be found and caution should be observed.
- 6. Count the radioactivity levels of the smears and record on Figure 1, 2 or 3 as appropriate.
H. AREA RADIATION SURVEYS
- l. Beta and/or gamma survey
- a. Check that the dose rate instrument is operating properly by the appropriate procedure.
- b. Determine type of reading taken; for example, field i reading or contact reading and record on appropriate forms.
NOTE 4 Field readings are those where the instrument readings are nearly uniform at knee, waist and head measurements.
- c. The contact readings distinguish beta radiation f rom the gamma contribution to dose by subtracting the window closed reading (gamma) from the window open reading (beta + gamma) and record the results on the appropriate forms. .
- 2. Neutron Survey ,
- a. Check that the PNR-4 is operating properly by the appropriate instrument procedure.
- b. When using the PNC-4 with the detector in the moderator jhg, the instrument detects fast neutrons; ' *,
cf the moderator, slow neutorns. The scale ie rtad incpm and converted to mrem /hr using the conversion factors on the side of the instrument.
- c. The PNR-4. reads directly in mree/hr.
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HNP-8012 See Page 1 E. l. HATCH NUCLEAR PLANT --
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Power ca ' ~ ~ 5 of 66 See Page 1 I. DAILY AND WEEKLY ROUTINE SURVEY MAPS
- 1. These survey maps indicate the routine surveillance for radiation and contamination control.
- 2. All of the survey maps are completed each week and some on a daily basis (see HNP-8050 for reference).
- 3. Routine survey maps are shown in Forms 1 thru 46.
J. SPECIAL SURVEY MAPS
- 1. These special survey maps are used on special occasions (such as a refueling shutdown or a maintenance shutdown) as determined by Health Physics.
- 2. All npecial survey maps will be completed on a routine basis as specified by a Laboratory Foreman or alternate.
- 3. Special survey maps are shown on Forms 47 thru 54.
K. REPORTING AND LOGGING
- 1. Survey results which indicate newly contaminated areas shall be immediately reported to a Laboratory Foreman.
- 2. When contamination is found in a normally uncontaminated area, Health Physics will P.erform surveys in adjacent rooms or areas in order to evaluate the extent of the contamination and attempt to determine its source.
- 3. Records of all Surveys will be kept on file in the Health Physics office in the Control Building or in the permanent plant f13 es.
L. COMPLETION OF DATA PACKAGE COVER SHEETS
- 1. Document Number l Complete the DOCNO by adding the appropriate dash number.
l Dash numbers are as follows:
- a. Rx Bldg. 130' 8012-1
- b. Hot Machine Shop 8012-2
- c. Rx Bldg. 158' 8012-3 >
- d. Rx Bldg. 185' 8012-4 g
- e. Rx Bldg. 203' 8012-5
- f. Rx B2dg. 228' 8012-6 r - -! sct .
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- h. R/W 103' Unit 2 8012-8
- 1. R/W 132' 8012-9
- j. R/W 144' Unit 1 8012-10
- k. R/W 148' Unit 2 8012-11
- 1. R/W 156' Unit 1 8012-12
- m. R/W 164' Unit 2 8012-13
- n. TB and Control Bldg. 112' 8012-14
- o. TB and Control Bldg. 130' 8012-15
- p. TB and Control Bldg. 164' 8012-16
- q. Drywell 8012-17
- r. Torus 8012-18
- s. Condenser Bay 8012-19
- t. Diagonals 8012-20 - . .
- u. Miscellaneous 8012-21
- 2. A Data Package cover sheet shall be completed for each of the Data Packages as indicated in the NOTE below. The cover sheet shall be prepared as follows:
NOTE
- a. The Rx 130 can include Figure 1, 2 or 3 and Form 7 for Unit 1.
The Rx 130 can include Figure 1, 2 or 3 and Form 38 for Unit 2. , The Hot Machine Shop can include Figure 1, 2 or 3 and b. Form 43 for Unit 1 or 2.
- c. The Rx 158 can include Figure 1, 2 or 3 and Form 6 for Unit 1.
The Rx 158 can include Figure 1, 2 or 3 and Form 39 for Unit 2. .
- d. The Rx 185 can include Figure 1, 2 or 3 and Form 5 for Unit 1. m ~ . . . { q f. A.
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a.it 7 See Page 1 Georgia Power M^ 7 of 66 The Rx 185 can include Figure 1, 2 or 3 and Form 40 for Unit 2.
- c. The Rx 203 can include Figure 1, 2 or 3 and Form 4 for Unit 1.
The Fx 203 can include Figure 1, 2 or 3 and Form 41 for Unit 2.
- f. The Rx 228 can include Figure 1, 2 or 3 and Form 3 for Unit 1.
The Rx 228 can include Figure 1, 2 or 3 and Form 42 for Unit 2. 9 The Rx 100 can include Figure 1, 2 or 3 and Form 15 for Unit 1.
- h. The RW 103 can include Figure 1, 2 or 3 and Form 34 for Unit 2.
- i. The RW 132 can include Figure 1, 2 or 3 and Form 14 and 17 for Unit 1.
The RW 132 can include Figure 1, 2 or 3 and Form 42 for Unit 2.
- j. The RW 144 can include Figure 1, 2 or 3 and Form 13 for Unit 1.
- k. The RW 148 can include Figure 1, 2 or 3 and Form 36 for Unit 2.
- 1. The RW 156 can include Figure 1, 2 or 3 and Form 12 and 6 for Unit 1.
- m. The RW 164 can include Figure 1, 2 or 3 and Form 37 for
(.. Unit 2.
- n. The TB and Control Bldg. 112 can include Figure 1, 2 or (g 3 and Form 11 for Unit 1.
- o. The TB and Control Bldg. 112 can include Figure 1, 2 or
%, 3 and Form 30 for Unit 2.
% p. The TB and Control Bldg. 130 can include Figure 1, 2 or
*b 3 and Form 2 and 10 for Unit 1.
The TB and Control Bldg. 130 can i nclude Figure 1, 2 or f[ 3 and Form 31 for Unit 2.
- q. The TB and Control Bldg. 164 can include .'i c u r e 1, 2 or 3 and Form 9 and 32 for Unit 1.
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- r. The Drywell can include Figure i, 2 or 3 and Form 48, 49, 50, 51, 52, 53, 54 for Unit 1 and 2.
- s. The Torus can include Figure 1, 2 or 3 and Form 8 and 27 for Unit 1 and 2.
- t. The Condenser Bay can include Figure 1, 2 or 3 for Unit 1 or 2.
- u. The Diagonals can include Figure 1, 2 or 3 and Form 28 for Unit 1.
The Diagonals can include Figure 1, 2 or 3 and Form 44 and 45 for Unit 2.
- v. The Miscellaneous can include Figure 1, 2 or 3 and Forms 1, 19, 20, 21, 22, 23, 24, 25, 26, 29, 46, 47 for Unit 1 and 2.
- 3. Remarks: Indicate Unit number and location or category.
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. See Page 1 ,
7 , out GeorgiaPower a ~ * ~ " , ,, ,, See Page 1 PROCEDURE DATA' PACKAGE DOCUMENT NO: HNP-0-RPP-08012-SERIAL NO: RO7-MPL NO: N/A s RTYPE: C15.14 XREF: N/A TOTAL SHEETS: _ FREQUENCY: AS REOUIRED COMPLETED BY: c- t
- DATE COMPLETED:
I HAVE REVIEWED THIS DATA PACKAGE FOR COMPLETENESS AND AGAINST ACCEPTANCE CRITERIA IN ACCORDANCE WITII mIP-830. ACCEPTANCE UNACCEPTIJLE REVIEWED BY: DATE REVIEWED: REMARKS: UNIT 1 and/or 2 (Circle correct unit) . I/ CATION: 4
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- 1. Dose rate readings are at .41st l< vel unless ettwwise specified.
- 2. Unit of eessurement, i.e. C."M/100 cm2 PR/hr. etc.
Surveyed By: wie I 5eviewed Ry!
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FORM 13
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7 See Page 1 Georgia Power n_m 29 of 66 ; FORM 17 FORM 17 fe - llNIT 1 l Plf."T F, f . r*?cM . I:0, ROUT!*,t- Of,T! Suxvtf!."# i Tik, SK2WAlfER
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- 32 or es I l.
FORM 20 l. l ItaM 20 ., PLMT E.1. HATCH Routine f 0. ! Survey M3p y DATE:
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L CCATICli: PL ANT SITr t' I'.51Tr" MIS: l roserse Tyre SER.c , t ** * ' ~ j a.un w
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FORM 22 i FORM 22 , . FLA.*IT E.I. HATCH Routine fi3.
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LCCATIC:!:V!G T 105'
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- P
~'
* ,9 9 f 6 4 e- f, M I.
LG i I
'e, sneers c m t en ou r,
. M , , , ,.c . , , . . .c , J I I I
~
\ t .- J l i 1
[ .L.-. , , , , , , 's e f 5 I I i
.e=.... ..
b ', 8 j d 6 l l 7 _ , ys s - ^ -s. / ss. . - , i3 s I i Remarks: e i t,0!b in ti. C.UE i 1. Ns= rates are t2.en 5 at waist level micss CC'0I?t*$ S #: a I j ctSer. vise 5:e;ifted.
- 2. lattis CF 7:E?.5GE: C??'/1CCc .2. cR/hr. etc. pg.vi,3 ce te _j HP:P-8012 Ro?
l 6 A [,.y. ,~.. .. .. -, .I g.
.L
- ~~~ o cu.. ,o s HNP-8012 See Page 1 E. l. HATCH NUCLEAR PLANT mm. a DATE , }
~^"*
See Page 1 Georgia Power nA 3s or es FORM 23 PORM 23 FLRIT E.I. IIATCH M u tine NO.
- 4 Survey Map CATE:
g AN l T D'E:- N s s- + co s .- .sc, LCCTI C W.G.T. 12 4' p s.) 4 s=== ? !!.577/J:1:315: SER.i
@ ,, p l T)FE
.s /c 3
,' - fj
/ {
3 y Q j 3 P.EA50:1 FC2 504YEf: [L lly O Weekly G
'A .
(_' N I
-2 s _---s c,, . s .. s MEA lf!TA & weekly TOTAL 1
= ,, S'JtEY U.*!C !;e;trc:.
h w 'i h0. (r.Vhr),(rR/hr) (:-2/hr) 6 I l
'
- j g orawcrs i. r her as,mensees 9 s 3; : i
. Et F2 ,, '
N; 4 I e
,I ~ ID .DN \' ', ? 5 t i cII . \, ;'; y ;
o
~ c , ,
IJ l srear (;/s c r' t . c. { .,, I I )
- s cv z .
@ a i U
h L-
" = * * * = 4 6 5 e i 1
l 5 , 1 a ' i rg I *
! l
> l '
a e e s 1 ' u,r q g g g 19 8 l l Remarks: l r l 1:317. CATE
.NG:E S~
- 1. Cose rites are t:ke U t waist level unicss COI'M 31: -
othervise s;ecified.
- 2. t1115 CF ::IASUE: 0;c/100c,2. rR/hr. etc. t v t r.,4 a f; 11NP 8012 fcO7
~
T. . .~.. _. . *4 c r.'L
g we940 vat '%.X.'L Lru'<t NO HNP-8012 See Page 1 E. I. HATCH NUCLEAR PLANT aiv,w. uo DAlt. See Page 1 Georgia Power n "^" ~o 33 oc ss FORM 24 FORM 24 M rt 1::T F._1_. Pr.104 13 Roultr.! D**If SWiEY l'!? T U grog,n unk1% l its=.tas; mt a su.. ra.) ap37;I7: rr.YEY c:nv r vrr n , .e-- 4 -
- w. .,prty 6v.tc;1 i:in' I i
lulx. 6 Lt't.i!G:: "## *#."*b.s 1 I i 2 e s i 9 [ 4 Y 1 t , tlkT Cf;T.EtiHT ~ T? vi n t =4. ,. o- ' g ,r ,. TT, - Lt **" ( Ltzu.G f l ( : OC , 4 _i
< 4 4 4 1 4 6 I I ! l I t !
I ^l i _] FEr/siti:s: .
' t.'Ris
- 1. Oxe rate r c:f f.~. . ec I! t.* fit 1,ccel alcis c;Scr,.!:e s,-- if ten
- 7. ttait sf e eatuie,1. 3 ;'/it3 c - r?./tr, c;; .... . . . .
Cf ~DICted h , j e .y . - e 3.. l F
- Mo
[ . +r - _4IenI
I, s ',,,,o.< mue.no IINP-8 012
. E. I. HATCH NUCLEAR PLANT tv w 4ra See Page 1 7
unu ( - " ~ See Page 1 GeoroiaPower 2) ri 37 of 66 FORM 25
- e.s.
FORM 25 N t?"T r. 1. I!* Tty f:f' . ,_, OUT!!:f EfIE i sx;crin ,,.g it;- i;r
- Mit*: 5'It.C e ! M a 1 ;5iff.I*.Ef:Ti( TYq 15:11. g:5, I A } El("** FC:t 5"MIT CAf tf -
strev n MTA . ii q r e CJ:7.:s L L's;.. ' i' itk .
,,g,; e.r/t.r nrn/h et e, tr i
n o 2 - I u k'ORKt::; FLC^R 8 IFJCK m O _.__..__2___ :- a (p g % n""4 rpli.;.g,:c .cl;c.-ij I
-.--2 C --
3 LA :' L
.l_ , O I I I F.U*.41:5: l l
EEil
- 3. Case ret _e r.*3 'ir , , . -t irrist 1,-3ect or.less c,rien:ise .n gf;c,;, a.-
- 2. L' nit 0; r.0 ".n. it.
- r/ MG c . - e ft/:i . e ,, '-
I (c. oleted t.y l r....... l _...t
. I s _ ,.m HNP-8012 !'
'. See Page 1 E. l. HATCH NUCLEAR PLANT .
*="*"'" l A.
am " " ~ See Page-1 Georgia Power nA , 38 or es FORM 26 . FOPM 26 , pf.3,s ,CJi'i re0'-e - P3:1!*. 1 5'J.ZI IN 1rn I, f __tE.*JJG.fl. '' " l
!! air.';315( I!i-E L ER. R.) {
((fM*I F"3 E.'MT DILY n LTO't T rL N,g - E!!. A .: . J.7 Li.'. 5. 2 L U:."I T;T:4],
" ~#
;;trTm "*/I'"
[_*[#) I I I l
==- , }
o O it .7 h- I 1 e I g..,.,.., u< s u. E~.C*~ em I
\' l
,"=1 i
o- ' l I
.. g g- ,
I i ( l i } t t l l 1 .] tm? :s: I
' MTES I 1. (*ase rate re: Jigs ;-r gt 3 2it' - el cnic;s c 53reise si.ecified.
- I ?. L'ait c." r usse e. it. f;4'!;.' c: - r# .r. etc. * '. a...
Cc pictes of ;
. . . ~ . . . . I IINP-8012 E07 l %
9
+a I." .,.r . . .. % 4 owl
s- b ..
. E.'t. HATCH NUCLEAR PLANT IINP-8012
. See Page 1 ,
,,y6,os ,,o om 7 See Page 1 Georgia Power ob ~ ~o 39 of 66 j
i l FORM 27 . i
.' l
~
l 1 FORM 27 '. FLt:ti E.I~ HATCH l C' 1T f
- Routtr.a7 tiO.
- Survey Pap 'f>
. CATE:
I T D'!:' , LOCAT IC*i. TORUS '
' W A l. K W A Y Rf il.1 1:1517C ais:
TYTE SER.#
./ RkA50?f FOR 5.ur,VEY:
Call / O veekly 0 3
/ EA EETA & weekly TOTAL SUM E T'GA!!".A Neutrca t
!;3.
(r2/hr.}(mR/hr) (r.R/hr) b J g i
\ 2 l 34 4 6 5
O*s\ ' ww4rs s s s srear c::a ett c: I
+ fa l / ( l S i i i
e , , 7 I i 8 8 4 1 9 I i l i 13 1 I I l l Renarks: 1 i ~ l i . I .,o:05 l'11 ! . C.*.! E l 1. Cese rates are takcG.aist level unless Cc oletef Sy: othersise 5:ectif ed. Revi*,4 ty: ! 2. ("I tis CT FI
- S'.t.I : C??/100C32. ri/hr. e :.
itNP-8012 PO7 f i 1 t l......J
.. .... ; S0t
i f *I Kv /A( ns.o cur so k IINP-8 012
- See Page 1 E. l. HATCH NUCLEAR PLANT mor v. w mit See Page 1 Georgia Power rA ~~
40 of 66 FORM 28 FORM 28
~j FL!n1 E.1, PAT;il trilT I f;3 bu tir.e Survey ?:3p D17E :
T!?:E: Y'
-< LCCATIC:i:p g*
IT.5i0'J:I..i$ :
- 1) Ti, SG;.1
's G Q f' gyg r.EA573 FC?. $U n IY:
RN& ,# N s CJIly G L*M il v [1 f
\ h fAEA SETA 5 ' st:ily T0ut
@ ,' i
's s SLTtEY CfrA Ceutre.
/ 8
's f.3. l(rJ./cr[.(v.2/t.r) ( ?/hr) l i t f N .
e 1 l 6 ) 2 ( i i
; / , J t t (
f 1 I i i l _ ---~f-- -- - - -
"5 i 4 l
~ 6 I i t l i 7 I I i i 6 I I y I
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'e ' 10 l 4 ~
's
's
(# l , ye e -1 cn i et ca i
/ p 1 I
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\
CRO s ' /:Cic 's s e g 5 6 I (
' -/
i- e _6 i s l 7 I L 3 i i i 9 I I i !' 4 # to a Frcr%s :
~-
9 9 O d - cc-* 4: L . . -
. ; ec.w a = m u g
c.o.w t. - ___
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%QW A
ES a 9.J.wSet a
mmm .44aou oo HNP-8012
. See Page 1 E.1. HATCH NUCLEAR PLANT -w.o. w uut 7 See Page 1 Georoia D Power en.
41 of 66 FORM 29
?
FORM 29 PL F E 1. HATCH P.ou d r.2 !O. Survey t'ap CATE: l tit'.E :
' #U l @p ( c "- . ' I C"" f_'ip t', A tif 4 E X
[4 * !!:577,'R AT 5 : l _ _ , TYPE SE2.! cansur Kcos - Cina > - F. EAST,*: f C $LP.'.EY : T - I"ily O . Pcei.ly O (c ) W l fr.IA' CrTA 5 s:ectly TOTA!.
. . utron f.U.
[ St."'.VCIlC' (rT:/t.r)- (r2/h:t4 r) ( ./'/n r) I 11 2 I i CETIG23 OFTIO:3 j _ _ _J 4 t ~ 5 { 6 l l 4 f- 7 l l
! } 4, I
' [
I
- _V e- l -_10 ,_[ !
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; 4 7
, 5 1
! n 6 i
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F:.;*E3:
~
'3 J rf il . P.*.:E
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, , ", ' , ,- l l o *.ar.n t 5;?cifi.d. - - '
l 2. t?;t; Or * .W '.! C?F/IO ,. rT/i.r. e:: kn . .e d 3 r : j_,_,_I l IINP- 8012 R07 I r eQ4 n. l k l 1
, , e l pd r.e3..
6 e. abi OGL
~ ~ , . ~
n w n ~o HNP-8012 See Page 1 E. I. HATCH NUCLEAR PLANT
- tr. YtS:UN NU UAft ) l See Page 1 Georgia Poweri ~ ~ "
42 or es l l FORM 30 l FORM 30 PLIJ;T E.l! HATCH 011T II
>N T
Routine Survey f2p No.
. CATE:
i=- m w , -_= 7;; g: j I j $ 1 l < L,+. . , i ! k'T ---a;, V:v "*inn p(_
- co.;3,I;,' r g
_ _ _ j ,lj - - - . - - pu t _
,) L ae ,y ,
y.su.u:E:: s-du c, SER.i ta ', C @ - EEASO.i FC.15;T.'EY:
-'I y miiy o veeay n 3
h h p I /AEA CEIA ?. wws= un, e nly TCTAL f i;U. (rJjir r ' (r-R/n:-} (: 7. /57) l e 8
) [- -7 '
l l o L,, 2 , , , l '/ 3 ! l
- c : i h k*
6 i
~
l ,. :;u f]2/f. Ii ! i rq=wCh Ij f m yh '7 h 13 l
,a l
f~ih 00 mg y *g ~~
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- mri un a e- c-b g m,3,
'N ' 2
- i
, v == t,m ' ' '
uro. aw a ene 4 I i p j k:.3 F L'.5s 5 l l ampN. h dj h hk_ }~If'II'~II " ' ' l
- I 8 I 3: gh.t_s; -U% p ;.
o i e i
. 9 I I l
- = 2- - - - - ,
_i3 , ,i Remarks l
~
- 1. Nse rat:s cre *2tNb.ais: 1,..c1 unters MII EU ctNr.it s-2 s r::i e '21, cc leaf 3<: l- l
- 2. n: s c.= :w.m ce: mu 2, c.y.,, cc . 7,,,, , . , y , , ; -j n:ip-so s no7
.zphs w
l v@ r rel Qw{ pdh..u.I ep
6'64GLt.CUHf. NO b A6N4 HNP-8012 See Page 1 E. I. HATCH NUCLEAR PLANT w;,.ou uo g 7 om
~~
3,, y,y, 1 Georgia Power m 43 ce se FORM 31 .
\ rom 31 ,
I;0 : t, hit II itntirn Survey inp CATE-g TU2:' ,j LCCAT IC'i:IEEWE 13 O' AA A O 3 !!GiRLr'. ::i$: SER.I O V e q e -/ ' TTPE
~s.
25 0' G 2 REA50*i FC*t SU:JIIY:
,,i %' Oaily O weekly O
".T i.0 r E-=v v ~ <
U ., A?IA E EI A 1 wieuf Tciit
^
SU.VE1 :::= ::r.::r: :
- f.3. (rJ;/A r) (r.R/iir) (tJ./h r) 1
{ . 'T t-4 l i j 5 ( 6 i d dg rl 7 l li. ..n JnI .-.Q Q lj [_s 6 i i i i
% A r 9 i l I
(
'y-~=3
.J - % ; L 10 l I i o^
f t 7, i m s- e r i c c. . eir i c:ci v v ! t t TiU. i .~zl
,, r A _"I J 4
5 l
~I l l 8 i i .
9 l l
.o 1. 1 p { {j pgQ
- 1. Ces r:tes are tden n *:Ist levc,i calc 55 g,g sc ' l i M1-)_CS*~.
c:un,ise n o ned.
- 2. L-stis Cr t'! ACEC: Ch'!IC:m,. e:/hr. c::: ,
,__r .,i; 3 ev* . _j ,_.1_
I!NP-f 012 RO7 etc lila....-g e
..a SGI
.. %- -un,-
IINP-8 012 See Page 1 E. l. HATCH NUCLEAR PLANT - ,o 7 om A
~~
See Page 1 GeorgiaPower c1 44 or 33 FORM'32 FORM 32 g Fifli E.I. IL*.TCH 4 ' h '.f r.e EO.. surny n p C*iE: 7, s b ! s, TDI:
' g '
L0cf.T:t1:CO?:Tdb5oLDG.
* ; !!iSTF.U.N E .TS:
s g TTFE SIR.!
~ @,,,,,.., s REA50:1 F02 imEY:
~ 'r u e* " tally O tt2ekly 0 Sctti tly ' T]TA:.
-6b
- TIA S ET *. 2
- d4D;
.T.TY CM *J. h att:r IQ. . (cR/irl (=1/hr) j (a.Vhr) 2 1 l
- 2 1 O 3 1
~@ 5 I i
= ,a._.
s r p, u e i 7 l l i l g 'N ' b l l {
. 9 i j oi i i 2 532 P CT 4 l ei l C "~i 1
O s 2 J j 4 I i l 5 i l l 3 . . -- , y _g. o e e 1
--\' un-) / LDI 7 l l l M .k._ Q '#'
h k. d I i l
;C 9 I I
..r.--a,:l l. h:. e. _.
.. ' 7 { :' , u, , , t 1
,.=-1 E: .u.. %._d ,3
<.w I.~_,..
- p -
, l _f} g i F.c* tria l f;j ll / i;
, . _ . - . . . ... --- - ..- .c.
- ..M 's h l T. C'.!E_ _
- 1. :: c retts are t & G ~>.aist le ul eIf55 g'_g,.,,,...
l I C: :. wife >;. '101. , 2 t~: .1 OT T2;;C: F?t/!02C* . rlytr. etc. Fewi.. M 3<: l HNFSol2 R07 9 M9$O Fs h em o swees www
~" ~ .,-u,,,,
E. l. HATCH NUCLEAR PLANT IINP-8 012 See Page 1 .n .v,. o e.it 7 See Page 1 Georgia Power Nh " " " " 4s or cs FORM 33 FOP.M 33 U: TIT II) Routine tic . ! Survey }.sp f CATE: l 1 l l TIMI: 3 1 I I a il' .l LC0Allt;; TUP 3'.NE ELOG.15 If;Si f.20.!5 : [ TYPE SEE.! I O PIAST: 7;?. m "!Y: j <-(3. e C Cally C ittekly 0
, II.EA T". 1. aedly it.i; .
RMEYW:1. . cu:ra!
!! :o). b-1.'t. rl
/ .2 c G eo _ _1-(:2/hr)l(rn/.5r)I 1
n$ yf
' , 2,_j ( {
w e I- t J l
- ,S[
[ r 4[) [- a . mC ; ; _L! 4 i _e. _ i
.h ES.li'l- 1 l 7
8 i I
-"gb--
t r 9 .l~ 4 i la i __l l-c;> se '; a r l < _.- l ci > C~ l l l _3 t. 3 1
+
l
@ @ ~ 6 i I l l l
~E l l l
-9 l 1 l 7i l j__ !
cen:rks t.V I H ge:ti. c m
- 1. rese ra:es zre :Ls7i wais; Icvel unless Cen1c" ??: 1 i '- ~ -]
otreruiss v :cificd.
- 2. C;!il 07 i;it.5U.E: GF;'/IChr.2, on/Sr. c:c. p, y ;, ,.; ,,. __j 3
02-8012 907
+e+s r,.
Lu,..~.
.... A gg{,
oL
k
- t. sw avam nu
~~^^'
HNP-8012
. See Page 1 E. l. HATCH NUCLEAR PLANT "t ao" um Dg
~
See Page 1 Georgia O Power t.r.i 46 or es FORM 34 POPJ1 34 ' PL;;iT E.I. ttAics CIIT II Eoutine f.0. . t, i Survey rap
,1 N CATE:
TIC t.CCU:G:1:R ADW ASTE 103'
.b --\ \ \ \ \ \ \ ,\ \ O ' \ \ i \,l_ g ...g ,.,...g,.g g .
w.e rucxam wm r, t
] 79- gog"-
m:ar staa sa:; .t ru:z s, Trea T'.X *sK rs'.K \* ur.s _. y .w % s a.4 %, \)c kild'/i3,TOR SU?3. EY: ,
\: 10: I i red.ly TCT;.L
,\ r' ca l c;: N. .H.EVl3ETAE ;:7M3 :Onr::n l
~ ~~
{' t C i W3 ::2. l(r.2/hr)- (r.d/h r) (c?/>.r ) of @ 1 r;3 ! rsz
*',. I t
. s '
i j l l ,wa- ~.lom ve.: .. 'gi ; 2 i e C mn { LFAIII c,if h N ,} J j l-ram
)
33..f.
'ra ( -l )g,g.
M...a (! gj- 4 e i p
<an=3 lg .-Jjj~~~
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T7te. , C r- .l g , _u[g ' slj lrc' S"51 !. g;i ta-*
="
Ris [ wma + Q := g epT' h 1N\\\g* * '
', re , , , . , gya '
_., c\ T\jC- gf 13 1 1 .' r ! C * -7 c: a [ eri cua st , l *[* l
- Uf etI' \ 'r 'N l 1 l ser:
simA:t a , .;
..\.. rw f .Mr;.g\ i g g J l
*a* 5~4d @ gj f.
, s s .: j ., 'Ns\\\\ 3 4 i anz=: :, : i
;:.3 @ rm _ . _ .
b, I to em 1 3' ' J neu sFym 1 jr.
,,1,1*Ii. ;; -- 7 j l . u: \,
L'_ ru x-i, 7 i ,
<- # T i _._.__ ._?_._!
- i. _ _ i- G. . ". .---- '. s s s -C\ !
3 , , 13 . ! I l E: arks:
*$ ,m c u r.
- 1. r s
,.' tes m sare :: mtCcn.a . t aist level it7b:s a n n en
] .,
- 2. CMI5 C M M DI: U1/I?OcE, t'0/he, e t:. P. i- ,.W Cv l IINP-8012 RO7
#+4 F.n ,.~.,, aIl c,q{l.
vvL
,, - .m ~m .u.o m -co12
. See Page 1 E.1. HATCH NUCLEAR PLANT .y,.,.,,,;,
om (, 7 See Page 1 Georgia Power al 47 or 33 FORM 35 l'OPM 35 [d UNIT I! f;0. -
< Reutine Survey P.ap DATE:
TI!2 :-
\ ((
LOCATIC1: R/.D'L' ASH gn' l
\ !fiSTR'y INTS:
b ' TYFC SER.; ,
\'j LQl~E\ \ \ \ \ \ \ \ \ \ \ \ \ \ \ \,I \
REl.501 FC2 SU'l: FEY: gj mxc;rrn3 ant ir:rr,2 s 3 -
.-hp caily O k;eek1> Q
.\g ' ' '1 N I
\ !!.
3\..\. .y
, g ran cap::a trat Au:: 1 g met, j3 ETA & '.eet:ly TOTAL
\f \k'\\M\ \.[ \ '\\ f . /r } r (r.2/P.r)
=5F 1 \
\!,4 ] ;')Q@l\t_\n!\Y\ \l\\R\ [\'\ \s!i, i
) y g, t -
at AJrm Tt.P& J in p
\ *
\ - Vint tE:ST ; 4 ,g
\
\. il l m
\l ,_N&
E 0 0 l I
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\d
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g THr c .;i g eit. cc. g \g\ g
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l ;
, i i Gl r s s E ! 4 i i d]ta b. j "Tdf" \\\\\lk!
\
\q \\\\
l' f., s ,ss,, s. .s \ s ms -~\i l 9 l 4 f J. 70 i i i Jj l Rct. arks: l.hil b~ ['.17. C' '. .
- j
- 1. D>se ret s are t: tent ..sist icvel viles CCI md 4: ,l.
ctr.:rvice s:c:if'ed.
- 2. t":t T! C : * : 'Dir0;;48".C0rd,r:'/hr.tte. t ... i . 1 Q- I r.N P-6 312 KO7 [
t 4+ f'
- 8"* .
- e sub #
L . . - . . . .. J wwl 9
_ _m .- . _ _ , . _ __ _, . . . , _
*WHQvAL N 40C1 LMJ+<t P.O
' IINP-8 012 See Page 1 E.1. HATCH NUCLEAR PLANT .0,, ,.y
. 3.u - 7 ,
See Page 1 Georoia 0 Power
~ " -
48 of 66
. i FORM 36 l I_
i ronM 36 l FLI,'iTTT. P.ATCH I L"ili !! -- 1
, h tine ric. :
- Survey rap TD;Er f
A LC.AT Zl: R AD'it/ ASTE 148'
. a- n , !?.5TELG EUTS:
} L TYPE SG. f
.I l
..EA5'0?! FOR SUP.rf.Y .
Caily O Vrekly 'O c-. ' 1 MA MTA E e_2kly T3TAL l
')I O SURYI) CA:M c:cutrcn l
y,
\ \\;g.,d
; (_ - . .:0. (t.*t/hr) (r+./h r) (rt/hr) i
- T.,\,,_db\} 6 l
' 'l* I^*
.. r g f
'. a n gigm.r.a i J O un \: 2 i
] 999 4 F
- \ '"' ie "" \
\\s\ND\\s\,!
3 i l
.! .) i $
j 5. j
.j coc.r f'-[M.
.J 7
8 i l ! 0 3 , gl sre:r c, J .,
- . i__ <! cri. cm i
__ . g, i L \\.L. r . ' a
!J !.
i e ql 4 3 I s'\ \ \\ -- t _, ; 6 e i 7 l 6 : 9 l 30 t I i F4 .r(s: t li air s I:;il. Ct!I
- 1. tese rates are t.Ha at wist Icv 21 taler , i~ ~~,
ctacruite s n :sfied. (c sletSd di: g , 1 ._, l 2. (*.17. C7 :I ail:I: Ci:'/ ttt:2, 3;p/hr , c t . rt.v o.,ed Sv:
} l 1
$14 .
l l r*".>...... L. *.a! d Lc . I
.' m:k t ? ont. tiJ vyg34 mP-8012 See Page 1 E.1. HATCH NUCLEAR PLANT .
,u >s.w.a 7
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Drywell Plan ficvation: 114' to 127' FE". ARKS
- 1. Doge Rate readir.gs are at waist level unlest other wise s ecified, p
- 2. Unit of !!ctsure ent. i.e. DF"t/lC3 C;'.11't/hr. etc.
Surveyed by: f DXt'l Reviewed ty: tie.!actY frL DA!C . liNP-8012 RO7 O 4:t* i liia. .,e.amiSGI
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FORM 49 . FL A'It E.1. HATt9 3
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- 1. Dole Rate readings are at waist level unless otherAse specified.
- 2. Unit of r.easurement. i.e. OP"/100C:2,!!R/hr,etc.
SURVEYED Bf 0I. T E RP!lfutD BY ' tsgar;;r r:7t 2:s (>hlt
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SURYtVED BY: DATI~ REVIE':ED BY:
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~
RCMRLS:
- 1. Oc:e Pate reading are at watst level unicss otherwise specified.
- 2. Unit of measureacnt, i.e. OrM/100C F I:R/hr. etc.
SURVEYED BY: caTE-l REVIDlED BY: l 'hs"mczyr;atm iIII'
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- 1. Dose Date readings are at waist level unless otherwise specified.
- 2. Unit of reasurc ent, i.e.. Drit/100Cla, i:R/hr, etc.
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- 2. Unit cf ncasurtaent, f.e. , CT-it/100Ct', l'R/hr. etc.
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- 1. I'cse Rate readings are at waist level ,cnte : otherutse specified.
- 2. Uni t cf r easurenent. i.e. . CM'/103C:1'. !G/hr. etc. !
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HNP-8013 V' '
E. l. HATCH NUCLEAR PLANT n .w.o l 0 Georpia Power d ~~ l ll - ((, "gl O 1 of 8 l. AIRBORNE RADIOACTIVITY CONCENTRATION DETERMINATION A. PURPOSE h l' To establish a method for taking air samples and determining the concentration of airborne radioactivity. l B. SAFETY Observe Radiation Protection Procedures. l C. GENERAL l Although the plant is designed to operate within the limits set ! forth for airborne activity by 10 CFR20, there is a possibility that some event may cause a release of airborne radioactivity to the immediate local plant environment. Such an occurance could be the result of routine operations or maintenance; for example, welding, grinding or opening a system to the atmosphere. In order to increase protection to plant personnel, routine air samples will be taken in conjunction with area radittion surveys and when any operation or maintenance work is being performed on radioactive material on systems where loose radioactive material may be present. D. DATA ANALYSIS - Due to naturally occurring Radon and Thorium gases in the atmosphere and their particulate daughters being carried directly or indirectly on dusts, air samples normally show significant activity from these isotopes alone. Radon daughters, whose longest half-life is 30 minutes, may be considered as completely decayed four hours after completion of sampling. Thoron daughters, whose longest half-life is 10.6 hours, will take ; approximately 72 hours to be considered completely decayed. It l is seen, therefore, that for the measured count rate without I regard to the delay time between stopping and counting the l' sample, will give highly variable results. l Long lived activity can be estimated by counting the sample four [ hours after sampling (count C 1 ) and again 24 hours after j j sampling (count C 2). The estimated long lived activity count rate (CLL in counts / min) may then be determined from the I following formula. s s%$o e U, Y l g5kD"Gr l o%
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E. l. HATCH NUCLEAR PLANT !!NP-8013 See Page 1 u.swa om 9 Georpia Power d. - See Page 1 o 2 of 8 r CLL= C2 - 0.271 C1 u.223 l The use of this formula imposes a delay in obtaining data on the i I concentration of activity immediately. Therefore, for routine I operations the filter samples will be counted immediately after [, collection and the air contamination estimated, assuming all counts on the filter are due to the contaminant. I NOTE Where an emergency exists, the concentration of activity of the contaminant is well above normal background trends and j can be readily recognized. , i. When air samples are taken and the concentrations are used to set r ' stay times for MPC hours for personnel, then if the results are greater than or equal to 3.0 X 10-9 uci/cc, the sample activity should be identified for specific radionuclides. A decay count may be conducted to determine if the sample half-life is two hours. The sample may also be recounted at four and twenty four hours for further evaluation. E. EQUIPMENT
- 1. Selected air sampler. o
- 2. Appropriate filter media.
F. PROCEDURE l_
- l. Install either a 4" or 2" diameter glass fiber filter, i depending on the air sampler used, by removing the outer ring and placing the filter paper over the cross-grid i support. Where radiciodine or gases are suspected to be i present, install a charcoal cartridge in addition to the h glass fiber filter. I L
i
- 2. Replace the outer ring by threading clockwise until seal is f i
made between the outer ring, filter paper, and the "O" ring 4 seal. I I
- 3. Carry the unit to the designated air sampling location and l plug into a 115 VAC outlet. For locations where 115 VAC is unavailable, a battery operated sampler may be used.
1
- 4. Turn on the air sampler. p
- 5. Record the applicable information on an Ai 1 (shown in Figure 1) or-other suitable conta ner
- 6. Turn off the air sampler af ter a minimum time o s 10 minutes (or until 100 cubic feet is. reached) - HigD volume air sampler (Staplex)
. 1 J
. r E. I. HATCH NUCLEAR PLANT IINP-8013 See Page 1 m ,3,v, %
em 9 See Page 1 Georgia Power d ~~ 3 ,, g t n 30 minutes - Low volume air sampler (Eberline) 35 minutes - Low volume air sampler (Radeco at 3 cfm) !
- 7. Removs filter nnd place in Air Sample Envelope or other j suitable container. Take to laboratory for co'unting. -
3
\
- 8. 'For 4" filter samples, punch out a 2" sample for counting i
from the center of the filter paper. l
- 9. Count the filter sample for a minimum of 5 minutes and note i the total counts on the Portable Air Sample Log shown on '
Data Sheet 1.
- 10. Transfer all data from the air sample envelope to the Portable Air Sample Log. Be specific about sample point location.
- 11. Calculate the activity using the appropriate equation and data on Data Sheet 1.
- 12. If the results of the particulate filter exceeds 25% of the MPC for unidentified air concentrations or 3 X 10-9 uCi/ml for all radioactivity, also if the results of the MSA or CESCO Charcoal cartridge exceeds 25% of the MPC for unidentified air concentrations or 3 X 10-9 uCi/ml for all radioactivity, the Health Physics Supervisor or his designated alternate should be notified immediately. The particulate filter and charcoal cartridge will be counted together using GeLi detectors to sum the total MPC values and to identify each radionuclide present.
- 13. If determined necessary by an evaluation of the result, count the sample again, 4 hours after the sampling period for 10 minutes and calculate the activity on Data Sheet 1.
- 14. Repeat step F.13 twenty-four hours after the sample period.
I
- 15. The results may then be further evaluated as determined necessary by the Health Physics Supe ~rvisor, or his :
designated alternate. ! I G. LIMIT OF SENSITIVITY l i The limit of sensitivity for the appropriate air samples may be determined by the formula below. A 25% relative error at 2 g-- i s assigned to errors made in sample flow rate, sample time, collection efficiency, and mean collection surface, i a 2 o-- = 2 +b (ts+tb ts t s tb
- E Where: ts = sampling gi g, counting time (m tM b = background (cpm) tb = background countinq time t NU!I
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Thus, for a counter background of 25 cpm, a background counting time of 10 minutes and a sample counting time of 5 minutes, the results are as follows:
~
l 2 =2 1/5 + 25[_(5 + 10)]'l
. , (5)(10) .
=2 2 + 25 [h-] I
=
2[7.7]5 i 2 = 5.55 cpm or 9 2 background = 25 + 5.55 cpm. LOS (limit of sensitivity) at 2 and 25% relative error:
; LOS = 2 [1 +/1 + bt s (RE)2(ts+tb)3 ! (RE) 2 ts ts !
i Where: LOS = limit of sensitivity i RE = Relative error (25%) b = background (25 cpm) . ts = sample counting time (10 minutes) tb = background counting time (5 minutes) Thun: LOS = 2 [ 1 + /1 + 25 (5) ( .25) 2 (5 + 10)] ( . 25) 2 (5) . 3
= 6. 4 [1 + /1 + 2 5 (5) ( .0625) (3) ]
= 6.4 (5.94)
LOS = 38.04 cpm Substituting a high volume air sample of 10 minutes sampling duration at 10 cfm and counting 25% of the collecting surface, we can determine the minimum detectable air concentration:
- (For a high volume sample where the filter paper is cut to a
- 2" diameter sample size) uCi/cc = (.16 X 10-10) (1/e) (cpm) . e = counter officiency .
Volume ( . 2 5) (fraction) ' I (area of filter counted) uCi/cc = ( .16 X 10-10) (3.125) (38. 04) = 7.60 X 10-11 uCi/cc 100 (.25) For a low volu.ae sample where the filter paperELE EE'@f71'terfa$d i the sampler flow rate 50 1/m for 30 minutes, then: 3 E= 2 U=s Pd % L uCi/cc = (4. 5 X 10-10) (3.125) (38. 04) = 3. 57 X 10-ll'"bdi74:c5j 4 (1,500) U b E= I manual set
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'*P-8013 See Page 1 E. l. HATCH NUCLEAR PLANT ..,_..,.o i
n ,, 9 i I See Page 1 Georgia l'ower zz = ^"'" s of a The above air concentrations are then the minimum detectable particulate activities for air samples collected in accordance with the minimum requirements of this procedure. As volume increases or sample counting time increases, the detection limit ' becomes lower. As backgtound increases, or the above mentioned , variables decrease, the sensitivity is reduced. e
!!OTES
- 1. Always try to obtain a breathing zone air sample if possible.
- 2. Do not lay air samplers on the floor.
- 3. Do not tie off air samplers with the power cord. Use a rope to tie off the air sampler.
- 4. Survey the air sampler and cord upon completion of sampling.
- 5. Attach the " HASP" printout to Data Sheet 1 or Data Package 1 if needed.
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- Sample Taken By
Sampfer Typei O High Volumo O Franchet C Low Volunic Co!!ccior: Filter Paper O Stac!: O Charcoal Sample Name-- - Cc!!cction " Time: Mcni,to.- Reading
- Date Time ,
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- n. O O DA*Es PORTABLE AIR SAMPLE IDC CWIT NO. 1 er 2 N3:
S.v.P L IA".PLE LOCATION AIR TV CSTj CwmDL .E^TA (I) SMPL FLOW PATE W D
- 10. CAMPLE PQ1NT $9PL TN fF VCLL'ME COLLECTED SIAd TIME Q Q TIME (P.IN) (CFM OR LPM) (FT CR L) 37 hot;pS Q Q R ILTV 1 WV/LV (3)
TEF EM TAL BKG NET ACTIVITY PECA'r ACT. CALC MfC MPC PPC MPC H N
%"tTINC DATA SCALER (CST) COUNT MIN]
CTDg CPM CPM FFFt WCi/cc
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w%s 1931T A or B {_i.# A:.QA~ rot.LLCT ON PATA IdPL 45SECE D'AT1ual AIR 2) SMPL FLOd RATE STA B IMi, O. SAMPLE FOINT $*1PL f f M*: QN 35fC' OF# TIME (MIN)(Cllt OR LPM) W)l.UME (FT OR L) COLLECTfD BT N0'193 e 2 QEV 1 kV/LV (3) _ TIDI'lI.rfA L MIit TRfIET AC '[V!Ti bi7Af ACT. CALC MPC MPC P 4-C MPC FOUMTIC DATA SCALER (CST) COUNT CTD CPM CPM KFFt uCi/cc 6'HRl4 'HN Bf RATIO INERT RATIO DATIO II) INIT 10D!NE~ CASFS PAPT. TO*AL
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TRI 'fbiKI." *ITN~ litG NET KE FM F@f AYT. ~ CALC MFC MPC MFC MP; 703MTING DATA SCALER (CST) COUNT CTD CPM CPM EFFt uCl/cc 4 HR 24 15 BT RATTO INERT PATIO RATIQ 1A J5 3.LTA (1) INIT 100TME CASES PART. TOTAL p d' $$ 5'Y60 2-E A of 9 masAtiuA Y # HIG4 Vdt.UME STA LF HIGil VOLUME CFApmAL (STAPI FX)
$ BETA ACTIV!TT e (NET ^C d {I T E d I )_g, IODINE ACTIVITI e (NET CPM) (1.6 E 10"II
- IN uCs/cc (v0Lt+ME IN FT 3
)(.25)(Err. FRAC.) la uCt/co (VOLUME IN FT 3 (.50) (Err FPAC) w 1.Ott YOLUME tRA?T7 On ERERLIME) LOW VOLffME CM APP *** L (RA0rX"O CM E3F*'.71tT) y OR * (WET'CPMIT4T5 T 1g=20) et = (WET CeM)<4.5 z~T5"ICs O (VOLU"X IN LITERS)(EFF FRAC) (VOLUME IN LITERS)(0.999)(EFF FRAC) e (1) MINIMt'M COUNT TIME $ MINUTES 9
- f. 3 4
(2) MINIMUM SAMPLE ?!ME: LOW V0:.tm2, 30 MINUTES: WIGN VCLUME 10 MINUTES OR 200 CURIC rEIT. (a) Eber1tre Lv 30 minates (3) Radeco (
- P bg 35 minates at 1 cra (No greater than 3 efs with charcoal)
(c) stapteen 10 einstes or 100 cunic feet ' { @ c W% (3) R0W0 UP W tut NEAREST so::R MOTE 8 3 cfm = 85 Lpe F 5 2 h 6*$s (k
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', HAllDLIllG 0F USflRC LICEllSED RADI0 ACTIVE f4ATERIAL 1 i
- A. PURPOSE j a
To prescribe procedures for the storage, use and transportation of standard ' ! radiation sources. B. SAFETY ' j Observe Radiation Protection Procedures C. REFEREtiCE HNP-8017 D. PROCEDURES l 1. All sources and/or source containers are labeled with radiation signs with the following information: i
- a. Source type.
- b. Quantity
- c. Date quantity measurement was made, i
- d. Source number.
! 2. Sources are controlled by the Counting Room Supervisor and will be in a ' locked container or cabinet. These sources will be stored at a location designated by the Counting Room Supervisor. l 3. Form 1, In Plant Source Sign Out Register will be used to record the use of various sources and to authorize such use by the Counting Room Supervisor, i The user's signature is required on this record. , 4. Sources are to be used, transported and stored in such a way as to minimize . l personnel exposure to them. The sources shall be kept in their shielded I ! containers except when they are in use. Sources without shielded containers ( shall be properly nandled so that undue exposure does not result.
- 5. fio protective clothing is required for source handling, except as may be required in the Radiation Work Permit and/or work area involved.
- 6. The loss of any radioactive source will be reported to the Counting Room Supervisor immediately. l l
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d e %A</ 1J G,eorg,a l)ower m. k ...<m i t _Q-f9-?j _ l _ , l LEAK TESTING OF SEALED SOURCES A. PU R POS 5? To provide a standard technique for Icak testing of a licensed, non-fissionable sealed source containing alpha, beta and/or gamma emitting vadionucitdes pon essed, used and stored at Plant Hatch. To insure the detection of leak 1ge of the radionuclide before it becomes a major health hazard. B. SAFETY Observe standard radiation pro tec tion procedures. C. REFEREUCES 1, Unit 1 Technical Specificat ion 3.8.
- 2. Unit 2 Technical Specifiention 3.7.5.
D. EOUIPMENT
- 1. Cotton tipped anolicators.
- 2. Pair of long tweezers or forceps.
- 3. Rubber gloves.
- h. Appropriate radiation actection instrument.
S. Smear disc. E. SOURCES TO BE LEAK TESTED
- 1. Scaled sources, other than Hydrogen 3, with a half life greater than thirty days and in any form other than gas, shall be leak tested at intervals not to exceed six months.
- 2. Startup sources and fission detectors shall be tested within 31 days prior to being subjected to core flux or installed in the core and following repair or maintenance to the source.
- 3. Notwithstanding the periodic leak test required, any licensed sealed source is exempt from such leak tests when the source contains 100 microcuries or less of beta and/or gamma emitting material or 10 microcuries or less of alpha emi t t i ng material.
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- h. The periodie leak test required by this condition does not apply to scaled cources that are stored and not being used.
The sources excepted from this test shall be tested for leakage prior to any use or trans fer to another oerson unloss they have been leak tested within six months prior to the date of use or transfer, i
- 5. Sealed Sou"ce means any radioactive material that is enclosed in, or is to be used in a container in a nanner intended to prevent leakage of the radioactive material or any of its daughter products.
NO_T_E_ Radioactive material which leaks from a source is a major health hazard in that it eny become airborne or transported in some other way to becoma inhaled or ingested by personnel in the vicinity. In the conduct of all leak testing personnel must be constantly aware of the techniques of safe handling and limit radiation exposure by considering distance, shielding, length of exposure, and t o t a 't activity of the sealed source to be leak tested. F. LEAK TESTING PROCEDURE
- 1. Unless otherwise indicated by the Laboratory Foreman, all alpha, beta and/or gamma sources will be tested by taking a cotton tipped apolicator on smear disc and obtaining a swtoe of the source holder in which the sealed source is mounted.
- 2. Break off cotton tip about an inch aboy; the cotton if applicator is used.
- 3. After performing the swipe test, place the swipe in and envelope and/or polyethylene bag with tweezers. DO NOT CROSS CONTAMINATE.
- 4. Take all swipes to the Counting Room for appropriate analysis with croper identification as to the radionuclide, serial number, location at time of samole, date and time.
l S. Place cotton tip on smear disc, contaminated side up, in a planchet.
- 6. Count each sanple for along enough time to attain good i counting statistics with an appropriate detector scaler combination which has a minimum detection sensitivity of at least 0.005 uc.
! y,, 5 , ,' n l
- 7. Calculate the activity as follows: -
.C b, p_.c.6
~": '
l , U" uci = (Net epm 1 (4.50 x 10-7 uci/ dom) ----- 2. Counter e7Ticiency < 7% n { ~ N%0 m y d ent
, ma E. l. Hatch Nuclear Plant ~Eu" ~ e l HNP E*0I6 t See Page 1 .ui:,,0 .o O .
air G, Coly' lil POWCT I7is ,m , o So- Page 1 3 of Il ',
- 8. Recond resulta and complete all information as required on data sheet 1, Radioactive Sealed Souren Leak Check Record.
9 If the test reveals tha presence of 0.009 mi c rocu ries or more of removeable contamination, the Labora tory Foreman shall immediately withd"aw the source from use and nhall decontaminate or dispose of the source as required by N.R.C. recu3ations.
- 10. A reoort shall he prepared and submitted to the N9 C on an annual basis if scaled source or fission detector leakage tests reveal the presence of 2 0.005 micro curies of removal con ta mi nati on .
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See Page 1 13 of 4 I DATA SHEET 1 R ADIO ACTIVE SE AL56~s561fCf~CRAK CHECK __R_EC_O_RD P L A !! T _ ____ _ _ ______ _ RADIONUCLIDE SOURCE LOCATION ACTIVITY SOURCE NUMBER SOURCE MANUFACTURER MODEL NUMBER NO_TE BETA SOURCE LEAK TEST MUST BE BETA COUNTED ALPHA SOURCE LEAK TEST MUST BE ALPHA COUNTED DAlb bMEAR UY CALC. UY CUUNikH 7~1Mti Ntil wr1 LEAM CHECK NhbULib ACCEPTA6fLb __bSL J'Ed un utMHffE4 H_99 k memee *** l
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NOTIFYSUPEHVISUNIddtUloI(Lik}FNOT.ACCEPTAF?C.E l - vna s ;f. . 1 a' \e \ W I L
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/pg GeorgiaPower d ~~ i SHIPMENT OF RADIOACTIVE MATERIAL A. PURPOSE .
i To assure that all shipments of radioactive material meet the Department of Transportation (DOT) and Nuclear Regulatory Commission (NRC) requirements. B. SAFETY Observe Radiation Protection. Procedures. C. REFERENCES
- 1. 49 CFR 100-199
- 2. 10 CFR 71
- 3. A review of the Department of Transportation (DOT)
Regulations for Transportation of Radioactive Materials, August 1976.
- 4. Control and Accountability of Radioactive Material, HNP-8017
- 5. Health Physica Journal, Vol 31, No. 5, November 1976. l
- 6. Barnwell site Disposal Criteria, HNP-8401.
D. SPECIAL EQUIPMENT
- 1. Appropriate survey instruments.
- 2. Appropriate DOT labels and placards.
- 3. Radioactive Shipment Record (RSR) form.
CAUTION f The technician is to visually inspect each package for integrity, dents, loose caps, or ruptures. All packages MUST BE approved by a Laboratory Foreman, Laboratory Supervisor, or Health Physics Superintendent. These persons must be knowledgeable in NRC, DOT regulations, Chem Nuclear requirements, and Georgia Power Company procedures for radioactive shipments. i E. MATERIAL CLASSIFICATION AND TYPE OF PACKAGE DETERMINMQat l REE D l 00 manual set
Aj'l'6%)w AL 1%R l()(/H% Ntj [ E.1. HATCH NUCLEAR PLANT nNP 8016 l See Page 1
"'" I' Georgia Powerkn 11
~ * " '
See Pag 2_1_ 2 mf 46 NOTE This procedure specifies steps to consider witen preparing any-i radioactive material for shipment. Shipment of fissile material
- requires special consideration to ensure against nuclear
- criticality due to the fissile nature of.the materials.
- 1. Determine what isotope (s) is to be shipped and' whether
! fissile or non-fissile.
- 2. Determine what quantity of each isotope is to be shipped and the total aggregate quantity. _ If a counting room quantitative analysis is impractical, estimate the aggregate i quantity using radiation surveys and Section N.
- 3. Determine what is the form of t'he isotope, i.e., NORMAL FORM
- or SPECIAL FORM. See Figure 1 and Section R, Definition.
a .' If normal form, determine which transport group the radioactive material is classified by referring to 49 CFR 173.390 or the Table 1 below. TABLE 1
- RADIONUCLIDE TRANSPORT GROUP Cesium 137 III ,
Cobalt 58 IV Cobalt 60 III Chromium 51 IV Iodine 131 III Mixed Fission Products (MFP) II Manganese 54 IV Plutonium 239 I Strontium 90 II Uranium 235 III Zinc 65 IV Zirconium 95 III
- For mixtures of radionuclides see 49 CFR 173.390 (c).
- b. Special form material is not classified by transport group.
- 4. Determine the package type as follows: l l
- a. Determine if the material is a small op exempt quantity, low specific activ_iAy or radioactive device by Table 52 s T56iowk.g < jIf rufttt'eElal,.
Mth does not exceed the limitsfid( Table 5 2 7 'p, material proceed to Sections F, G, or H. ,. g}f y 9
%) 'f
{ -
.....,,,.. ~ . ov. o E. I. HATCH NUCLEAR PLANT HNP R016 See Pa'ie 1 " *
- 6 11 s , g,9, 1 Georgia Power oA -
Tr.ntt ' . ACTIVITY L T '!I TS FOR S!II.LL Ot! A!!TITIEh DEVTCES A !!D _ 1. O ' .' S PCC fl'IC ACTIVITY MATERIALS
. r ,- o r t. Sna11 or Manft Articlec and Radioactive Low Spncir!'
, ,,,n
~~ ~
Exempt Devi,cea Mnximon Quantitica Activity O u , n t. i t i c s Per Device Per Pa c l:a g e Materiale
- 0.01 nCi 0.0001 Ci 0.001 Ci 0.0001 nC1, 0.1 nCi 0.001 Ci 0.05 Ci 0.005 mci /;
- 1 uCi 0.01 Ci 3 Ci 0.3 mC1/r'
-l 1 uCi 0.05 Ci 3 Ci 0 3 oci/cn c 1 mci 1 Ci 1 C1
-l : 1 nCi 1 Ci 1 Ci
*/ r i 25 C1 25 Ci 200 Ci rrit!un (Sec n '. n o llo t -
aride (2) 0.5 mci /ml (2) (1) below)
'p
. clal rne. 1 mci 0.05 C1 20 Ci U.235 15 gas 15 cms (fissile material)
NOTE (1) Also objects of non-radioactive material externally contaminated with radioactive material, if the radioactive material is not readily dispersible and the surface contamination does not exceed 0.0001 mci /cm2 Group I or 0.001 mci /cm2 all other groups. Such objects must be suitably wrapped when shipped in a closed vehicle (except aircraft; see Section p) (2) Aqueour. solution. Total activity per package not more than 3 curies.
- b. If the radioactive material does exceed the limits in Table 2 determine the package requirement from Table 3 below, then proceed to Section I.
TABLE 3 TYPE A AND TYPC- 3 PACKAGE OUANTITY LIMITS TRANSPORT TYPE'A PACKAGE TYPE B PACKAGE i GROUP QUANTITY (CURIES) Quantity (Curies) *
- I 0.001 20 II 0.05 e e m ,t.
, q -w;'5 c
III 3 IV 20 0"(~k ,i., C'[1 a O' V - 20 5000 % ,',7 kj ?W,i.' 4 VI, VII 1000 50,000 Special Form 20** 5000 i nnmm] got i
,m ..~.,w E.1. HATCH NUCLEAR PLANT "*"
HNP 8 01 r, g See Page 1 l 4' m.i - A 11 Snc_Rgg_1_ Georgia Poweri ~~ 4 of 46 Quantities exceeding type B are "large quantity (large r adioac tive~ ' sour ce) . These quantities involve all of the Type B package requirements plus other provisions unique to
.the specific package design. Refer to 49 CFR 173.395 (c) or
, 49 CFR 173.394 (c) for packaging requirements.
** Exce'p t- for Californium 252, wherein the limit is 2 C1.
F. SHIPMENT OF SMALL OR EXEMPT QUANTITY MATERIALS (Table 2 and 49 CFR 173.391) -
- 1. Package the material to meet the following conditions:
x
~
, ac Strong tight package to prevent leakage during transit.
- b. Surface dose rate not greater than 0.5 mrem /hr at any s
point.
- c. No contamination on external surface of package. Refer s to Section M.
- d. Mark outside of inner container " Radioactive".
i
- 2. n Complete a Radioactive Shipment Record (RSR). Refer to s ~ , _ . . Section K. Mark the RSR with "No Label Recjui red" y'
- x immediately following the description.
G. S,HIPMENT OF MANUFACTURED ARTICLES (Table 2 and 49 CFR 173.391)
-}
- 1. Package the material to meet the following conditions:
- a. Strong tight package to prevent leakage during transit.
n
- b. Dose rate for any unpackaged device not greater than 10 mrem /hr 0 4 inches from device.
i
- c. Surface dose rate not greater than 0.5 mrem /hr at any point if shipped as mixed cargo.
- d. Surface dose rate not greate Ehan 2 mrem /hr at any point for exclusive use shirib. 1.
- e. No-cotitamination on extyr e cface of package. Refot i, to Seltion M.
2
- 2. Complete a Radioactive Shipment Record ( P.S R). . , -Mark'ithe RSR with "No Label Required" immegfatply[fjfollowing the ,
{ descripti6n. Refer to.Section K. ((3 W ' ( II . SHIPMENT OF LOW SPECIFIC ACTIVITY MhTERIALS i and 49 CPR e T73. 392) , ((Y515Ec hW U d
- 1. Mixed Shipments (173.395)
~ s ,
- e - [x. .~,-. ... .- _ l _
^8 i
I t
. . . . . . , . ,--,,2 E. l. HATCH NUCLEAR PLANT " " "
- nnP 8010 Soo Page 1 -
Georgia Power k u^'t 11
~~
See Page 1 as 5 of 46
- a. Package the material to meet the following conditions for normal form material.
(1) For L.S.A. quantities which do not exceed Type "A" quantities (see Table 3) use Specification 7A container (49 CFR 178.350). Refer to Figure 2. Refer to section 49 CPR 173.393 (g) for liquid radioactive material. (2) For L.S.A. quantities which do not exceed Type "B" quantities, refer to 49 CPR 173.395 (b) for container requirements and Figure 2. (3) For quantities greater than Type "B" quantities refer to note in Table 3. (4) A package must be used so that the external dose rate is not greater than 200 mrem /hr at any point on the surface and the transport index is not greater than 10 (i.e. 10 mr/hr @ 3 feet) .
- b. If package weight exceeds 110 pounds, mark the weight plainly and durably on the outside of the package (49 CFR 172.310 (a).
i NOTE . Not required for exclusive use vehicle. See 49 CFR
- 173.392 (b).
- c. Assure that the package has been labeled " Type A" or
" Type B" with letters at least 1/2 inch high and that i the letters are durable and plain. (49 CFR 172.310 (a)
(2).
- d. Survey the package for dose rate and contamination to assure acceptability for shipment. (Refer to Section M).
! e. Label the package as specified in Section J of this procedure. i'
- f. Complete the radioactive shipment record (RSR) per .
Section K. l l , 9 Placard the vehicle in which the package is to be , shipped if a Radioactive Yellow III label i,g V> rpgMa k ed . See Figure 3 for placard design. For shipping via aircraft see Sectio e special ! details. . r s- w , - , , - - - - - -----v- . , , , . , a . ~ , , - - - , ,- - - - , .,,e,.,-, --
i
. . . . . . .~ m ~ ..m q i E. I. HATCH NUCLEAR PLANT nne nn1rJ j See Page 1 l
^4 4 ~~
11 l Georgia Power an Son Paco 1 6 of 46
- 2. Sole Use Vehicles Except Aircraft (49 CFR 173.392 c)
- a. Package the material to meet the following conditions:
(1) Strong tight package to prevent leakage during transit. Type B and large quantities must be shipped in Type B containers per 10 CFR 71. NOTE When shipping material in special casks, refer to the handling and loading procedure for that cask. (2) No contamination on external surface of package. Refer to Secton M. (3) External dose rate does not exceed: (a) 1000 mrem /hr @ 3 feet from external surface of package, (closed vehicle). (b) 200 mrem /hr at external surface of vehicle (closed vehicle). (c) 10 mrem /hr at 6 feet from vehicle surface. (d) 2 mrem /hr in any nor[nally occupied position in vehicle. NOTE After the truck is loaded and the final radiation survey is to be performed a Laboratory Foreman will accompany the technician to survey the truck. The radiation level can not exceed the DOT limits of 200 mr/hr contact, 10 mr/hr at 6 feet and 2 mr/hr in a normally occupied position in the cab. For administrative purposes the following limits should be adhered to: Surface at vertical plane of truck - 165 i mr/hr i Surface at truck underbelly - 165 mr/hr l Six feet from ver tical plane- rof f t"r%ck - 8 mr/hr gy'jICh.,')9i w.~ g# NOTE
-.[
! m " l [i I, aJd ' './ M. c 3 For casks, meas urp:1 d n tt ( must be 1 made 6 feet from the cask curface. k
li 1
~m. ~ o m. ~ ,
1 E. I. HATCH NUCLEAR PLANT ~~ HNP 8016 :. See Page 1 ! u^ " Georgia Powerks 11
~~
see Page 1 _ 7 of 46 Surface at rear of truck cab - 1.6'mr/hr Exceeding the administrative limits must be approved by a Laboratory Supervisor or higher i authority. The radiation measurement in the cab shall be surveyed with an E-400 or teletector which reads less than 2 mr/hr and is calibrated at ! a point less than 2 mr/hr.- The shipment l-should also be surveyed with two different instruments to insure you do not have a low reading instrument. Final measurements for the truck will' be made using instruments assigned solely for radwaste shipments.
- b. Stencil or mark the outside of the package ~ with
" Radioactive - L.S.A.". ,
I
- c. Survey package as required for RSR.
- d. Perform survey of vehicle before loading. Refer to Section M. There must not be any _ loose radioactive material in vehicle. Also refer to Section Q for vehicle used full time for transporting radioactive materials only. +
- e. Load vehicle with package (s). See Barnwell Site Disposal Criteria, HNP-8401.
- f. Brace package as necessary to prevent shifting or leaking during transit.
- g. Survey outside of vehicle to confirm requirements of Section H.2.a. are not exceeded. Record results on Data Sheet 1 of Data Package 2 or Data Sheet 2 of Data Package 3 and file the data sheet with the pink copy of the R.S.R.
- h. Placard the vehicle with radioactive placards on the front, rear, and on each side. See Figure 5 for placard designs.
NOTE For shipping via aircraft see Section P for special i details. I
- i. Complete the radioactive ship. See Section K. -
OMIN i i ! manual set
i
..r,-, ,,, an, n ,
E. I. HATCH NUCLEAR PLANT nNP 8016 See Paqo 1 " " " ^ " i
"^"
11
~~
See Page 1 Georgia Power m 8 of 46 I. SIIIPMENT OF TYPE A AND B 00ANTITIES NOTE Refer . to Figure 2 for typical Type A and B packaging. All packages must be approved by a Laboratory Foreman or a higher classification. These persons must be knowledgeable in NRC, DOT regulations, Chem-Nuclear requirements, and Georgia Power Company Procedures for radioactive shipments.
- 1. Package the material to meet the following conditions (49 CFR 173.393):
- a. The package must be a DOT specification Type A or B container and so labeled. Also see handling and loading procedure for the specific cask.
- b. The package must incorporate a seal which is not readily breakable and while intact, will be evidence that the package has not been illicitly opened.
- c. The smallest outside dimension must be at' least 4 inches.
- d. Shielding efficiency and leak tightness under conditions normally incident to transportation must be maintained.
- e. For large quantities see 49 CFR 173.394 (c), 173.395 (c).
- f. For pyrophoric materials see 49 CFR 173.393 (f).
j g. For liquid materials see 49 CFR 173.393 (g) and (n) (7).
- h. No contamination on surface of the package (Refer to Section M).
- i. For mixed loading shipment, dose rate must not exceed:
(1) 200 mrem /hr at the surface. , (2) 10 transport index (10 mr/hr at 3 feet) . l t l j. For sole use shipments, dose rate must not exceed: l
. me l prCDChhe pg; s pad W e
k .i ' , ~ . _ - - _. -- - E N[ bt - - .
i l
........~, .~.,,m E.1. HATCH NUCLEAR PLANT HNP 8016 l See Page 1 - - - , . ., o '
11 See Page 1 9 of 46 (1) 1000 mrem /hr at 3 feet from package surface (closed vehicle) . (2) 200 mrem /hr at the surface of the vehicle. (3) 10 mrem /br at 6 feet from surface of vehicle, 2 mrem /hr in any normally occupied area of vehicle. NOTE After the truck is loaded and the final radiation survey is to be performed a Laboratory Foreman will accompany the technician to survey the truck. The radiation level can not exceed the DOT limits of 200 mr/hr -contact, 10 mr/hr at 6 feet and 2 mr/hr in a normally occupied position in the cab. For administrative purposes the following limits should be adhered to: Surface at vertical plane of truck - 165 mr/hr Surface at truck underbelly - 165 mr/hr Six feet from vertical plane of truck - 8 mr/hr NOTE For casks, measurements must be made 6 . feet from the cask surface. Surface at rear of truck cab - 1.6 mr/hr Exceeding the administrative limits must be approved by a Laboratory Supervisor or higher authority. The radiation measurement in the cab shall be surveyed with an E-400 or teletector which reads less than 2 mr/hr and is calibrated at a point less than 2 mr/hr. The shipment should also be surveyed with two different instruments to insure you do not have a low reading instrument. Final measurements for the truck will be made using r instruments assigned solely for radwaste shipments. ! 1
- 2. Survey the package for dose rate and contamina ign. to '
assure acceptability for shipment ( p. t-orSb"7,;D oh 14) .
=
JP'yg t % $a
- 3. Label the package as specified in S .
L..%.., 1
- 4
- uo, , j m 4.u -<
E. I. HATCH NUCLEAR PLANT .~~_ENP 9016 ; See Pane t . we 4 -~ 11 See Page 1 Georgia Power na 10 or ari
- 4. Complete the radioactive shipment record (RSR) per Section K or Section L.
- 5. Placard the vehicle in which the package is to be shipped if a Radioactive Yellow III label is required.
See Figure 3 for placard details. NOTE
- For shipping via aircraft see Section P for special details.
J. PACKAGE LABELING NOTE )i Not required for L.S.A. exclusive use vehicle. See 49 C.F.R. 173.392 B. Each package of radioactive material must be labeled,
- unless exempt, on two opposite sides, with a distinctive warning j label. ,
- 1. Refer to Figure 4 for label description, t
- 2. Select the appropriate label from Table 4 below using the radiation survey. ,:
- 3. Insert on two labels the applicable information as required by using legible printing with weather resistant marking.
4
- 4. Affix the labels to the package on opposite sides, j,
'; TABLE 4 .
RADIOACTIVE MATERIAL PACKAGES LABEL CRITERIA g (172.403) 1 DOSE RATE LIMITS l [ AT ANY POINT ON AT THREE FEET FROM I LABEL ACCESSIBLE SURFACE EXTERNAL SURFACE OF 'l OF PACKAGE PACKAGE (TRANSPORT l
, INDEX) 1 " RADIOACTIVE-WHITE I" 0.5 mR/hr 0 ._
; " RADIOACTIVE-YELLOW II" 50 mR/hr 1.0 mR/hr l
" RADIOACTIVE-YELLOW III"* 200 mR/hr 10 mR/hr l
- Requires Vehicle Placarding . m er l (This label mandatory for any fissile Class JIIr(173 v389A) or -j i large quantity package (17 3. 38 9B) , regardl35sfrof.'.doseO' rate These limits in table come f rom 17[g"93 T(i)".' ' l-levels.) 3 .,
%f j' l
- Q.q"SB q r
_ R10HUal Set. _ - - -
~ mvm ~
See Page 1 E. l. HATCH NUCLEAR PLANT HNP 8016
~^*
See Page 1 Geor la Power d ~~ 11 of 46 K. COMPLETING THE RADIOACTIVE SHIPMENT RECORD (RSR) NOTE An RSR will be completed for every shipment of radioactive material whether it is " exempt" or not. Refer to HNP-8017, Control and Accountability of Material. Radioactive
- 1. Non-Fissile Material Enter the following information on the R.S.R. Refer to figure 5 and_6.
- a. Block #1 - Enter name of' company, addresses, license number, and individual's name if sent to anyone's attention. Enter ' a phone number if it is known. Enter name of freight line or truck company as carrier.
- b. Block #2 - Specify type of waste; generally it will be compacted waste and resins,
- c. Block #3 - Identify shipment as to whether is is normal form or special form (section R of this procedure).
Usually it will be normal form. If it is normal form then indicate the physical form.
- d. Block #4 -
Indicate class of material by checking appropriate box. See block 16 line 6. E
- e. Block #5 - Indicate the type of quantity by checking the appropriate box. k
- f. Block #6 - Indicate type of vehicle.
- g. Block #7 - Indicate if any special instructions are included. p!
l
- h. Block #8 - Indicate if prior notification of shipment has been given.
- i. Block #9 - Indicate if placards have been affixed to vehicle.
- j. Block #10 -
Indicate if labels are affixed to i containers. '
- k. Block #11 -
Indicate container tcb 7A or special permit !, etc.) si . ;,%[M
$ B a,%y
- e. c MNM
[" b @ !< DO -
- , _. - ,_ _ , ,_.~. - ,__ - _ .,.-- . - . _ m.-- - - -
' ' ~
A6114t h AL 6% L.i DVH L, NV E. l. HATCH NUCLEAR PLANT imp 8016 See Page 1 um 11 See Page 1 Georgia Power 6 12 of ' 46
- 1. Block #12 -
Indicate that we do have a copy of the receivers license and that it does cover this type of
- material. Must be signed by shipper.
- m. Block #13 -
Have driver read and sign exclusive use statement.
- n. Block #14 - Give driver his copies of the appropriate papers and have sign block #14.
- o. Block #15, line 1 - Indicate transport group number and list all radioisotopes identified.
Line 2 - Use correct section and list the measurements indicated. In section "d" list the survey instruments used by model and serial number. Line 3 - Give the contamination level measurements. Use the average reading found.
- p. Block #16 -
Indicate that the packages have been correctly labeled and marked.
- q. Block #17 - The technician controlling this shipment will verify that the certificate statement is true and then sign the statement.
- r. Block #18 - Af ter the technician is satisfied that the shipment is correct he will sign the first line authorizing the release of the shipment. Before the.
final release, an authorized, knowledgeable laboratory foreman or higher supervision must review all aspects of shipment for compliance to applicable regulations and then sign and date the release.
- s. Block #19 - Indicate that the shipment does not exceed the limit of 10 nanocuries per gram of transuranics.
i t. Figure 11 - List package numbers as they are loaded. If this is a drum shipment then list the drum numbers. ! If other items, then list the items sequentially (if i they are not already numbered) as they are loaded. In the second column record the contact dose rate as ! measured directly with an instrument. The third column i is for the dose rate at three feet from the.,, package j surface (this is the tr anspor t- gindex - orb T. I. ) . Estimate the activity of each drt@i[.bysse'cti'o(n tNhof this procedure using the graphs, or tables and the dose appr opr ia)Mformtil' tis," [hecor d the l rate at contacta 't Perfo dipp smears on activity in.the fourth column. the drums or packages and recor d(t.f,rm@ " con tamin a tion i l h ! levels in the fifth column. List the quantity of the package in the appropriate units (ie. cubic f eM . I liters, etc.) in the sixth column. See item 11 on , _ _ _ Blal!!!Td F d _
~~~ - ,uu , o f
E. I. HATCH NUCLEAR PLANT nNP a016 i See Page 1 + e ~o l: um 33 [ See Page 1 Georgia Power A. ~ ~o 13 of 46 figure 9. Determine the total weight of each package and record the weight in the seventh column. If the weight is over 110 pounds and the shipment is mixed freight the weight must be labeled on the package (see 172.310 (a). The right side of figure 7 is- a , continuation of the left side. Total columns 4, 6 and-7 and list these totals in the spaces provided.
- 2. Fissile Material Enter the following information in the appropriate space on the RSR.
Refer to Figures 14, and 15. Figure 15 is to be used as a continuation sheet along with Figure 14 when shipping large numbers'of containers.
- a. Shipped To -
receiver's name, address and license number. See HNP-8017 for instructions on verification of license,
- b. Number, Date - number and date of shipment.
- c. Shipped Via - motor freight, air express, etc. Give name of carrier.
- d. Remarks / Description -
describe (i.e. six irradiated fuel bundles, L.P.R.M. assemblies, T.I.P. drive. parts etc.) Include remarks such as fissile class if needed or Type A or B or Large Quantity shipment. NOTE More than one item or type of material can be shipped on the same RSR.
- e. Physical State -
check physical state, identify SN material type and isotope (s) .
- f. SNM Net Wt., Enrichment Isotopic Wt., Curies, Specific Activity, Concentration -
complete if SNM is being shipped. 9 Container, No. of Containers, DOT /BE No., Serial No., Weight, Seal No. - complete for all radioactive , shipments. If not applicable put NA.
- h. Transport Group - chack appropriate 15 ,
- i. Radiation Survey Data - enter data r quirgd., ga 4 1g if l
- j. Surveyed By - signature of surveyor. ' . h il b u e I
= -
- .= - - - - - __
-p1m19d co} %
t
. ,m, ,- --c.-
E.1. HATCH NUCLEAR PLANT nNP 8016 See Pace 1
- o^ n 11
~~
see Page 1 Georgia Power a 14 of 46
- k. Radiation Units - complete if shipping fissile material. ,
- 1. Placard Required - Check block if_ shipping a yellow III label package.
- m. Shipment Approval --a Laboratory Foreman or a - higher classification must sign here. The person approving the shipment must be knowledgeable in the NRC and DOT regulations, Chem Nuclear requirements and Georgia Power Company Procedures for radioactive shipments,
- n. Method of Shipment - identify carrier.
- o. Marking and Labeling - record the type of label and marking on the package.
- p. Shipment Originator - place of origin of _ the package, normally it will be Plant Hatch,
- q. Date -
- 2. Distribute the RSR copies as follows:
- a. Original - to package destination.
F
- b. Yellow - to driver of vehicle transporting package.
- c. Pink - File in H.P. office.
- 3. If a shipment is not exempt from packaging and labeling,.the shipment receiver must be notified _ by telephone or letter,-
before the shipment arrives. Some exceptions are, (1) if the shipment receiver expects a shipment at regular time intervals or (2) if he knows_it is coming.
- L. RADWASTE SHIPMENTS TO CHEM NUCLEAR 1
- 1. When shipping radioactive waste to Chem Nuclear complete an RSR form (Figure 5 & 6) , the Chem-Nuclear Record Form (Figure 8 and 9) and (Figure 10 & 11) and the South Carolina Prior Notification Form and Shipment Certification Form, (Figure 12, 18, and 19).
4 { CAUTION I NOLIQUIDWASTESARETOBESHIPPEDTOBARNWIjLL.hn ,., - r b. W 7 hY(2 gQ NE # NOTE 39 p D "a f.
- frLVy0 be(4 complete It is very important that these forms and [
instructions for completion followed. {
- 2. Assure that Barnwell Site Disposal / Criteria in complied with. l
)-
i - . . - - - - - - _ - _ - - - - __ _ -_ manual set
...... ~ m.. m E. I. HATCH NUCLEAR PLANT HNP 8016 See Page 1 " v*
,m 11 See Page 1 15 of 46
- 3. Distribute the Chem-Nuclear Record Form as prescribed below:
- a. Original - To Chem-Nuclear
- b. Yellow - To Chem-Nuclear
- c. Pink - File in H.P. office.
- 4. Distribute the RSR as prescribed for other shipments.
NOTE When shipping radioactive waste to
'I . S . Ecology, Inc. complete a Radio-active Waste Shipment and Disposal Farm (Figure 13).
M. SURVEY FOR CONTAMINATION CONTROL (49 CFR 173.397)
- 1. The following are permissible levels of removable (non-fixed) radioactive contamination.
- a. Package for mixed cargo shipments:
Beta-gamma not greater than 2200 dpm/ 2 Alpha not greater than 220 dpm/100 cm}00 cm
- b. Packages for exclusive use shipments:
Beta-gamma not greater than 22,000 dpmg 100 cm2 Alpha not greater than 2200 dpm/100 cm
- c. Transport vehicles -
accessible surface (49 CFR 177.843): Dose Rate not greater than 0.5 mrem /hr 2 Beta-gamma not greater Alpha not greater than 220 dpm/100 cm than 2200 dpm/g00 cm NOTE A vehicle for transporting radioactive material as exclusive use must be surveyed prior to loading of packages for shipment from Plant Hatch and after removal of radioactive packages shipped to Plant Hatch. ,
- d. Transport vehicle used solely for transporting !
radioactive materials (4 9 CFR 17 7. 84 3) : l Dose rate (interior surface) not greater th rg0 g Dose rate (3 f t. from interior f5QhWC suqfihee) ^ not, ,pgeaterl than 2 mrem /hr. ,
,t 3y
\ %%
These vehicles must be stenciled with the words, "For Radioactive Materials Use Only" in lettering at least 3 inches high in a conspicuous place on both sides of th" exterior of the vehicle. The vehicle mu~t be closed all times other than loading and unloading. I ~ m --- -_. ..: m ,. a. mwsic! c n!- ~ i
.:,,_a,.,. . - . n., .s.,,,. .-.-x . r nw - - - --m
. . . - m ,- o IINP 8016 7 E. l. HATCH NUCLEAR PLANT See Page 1 -~
.e 11 See Page 1 16 of 46
- 2. Perform smear survey on packages using a sufficient number of smears to assure a representative assessment. Refer to IINP-8 012. Results must meet criteria in M.1 before shipment can be made.
- 3. Perform a smear and dose rate survey on the transport vehicle (exclusive use) prior to loading package (s) . Use a sufficient number of smears to assure a representative assessment. Refer to IINP-8 012. Record results on Data Sheet 1 of Data Package 2 or Data Sheet 2 of Data Package
- 3. Results must meet criteria in M.1 before packages can be loaded. Notify IIealth Physics supervisor if limits are exceeded.
N. ESTIMATING CURIE CONTENT OF PACKAGES
- 1. Resin in a 55 gallon drum.
- a. Obtain a grab sample from each batch of resin and perform an isotopic analysis.
- b. Determine the average weight (lbs.) per drum for each batch of resin. ie. weight of the resin after subtracting the weight of the empty drum .
- c. Sum the specific activities of all the radionuclides present to obtain the specific activity of the drum contents (uCi/g).
- d. Estimate the activity of the drum contents as follows:
Activity (mci) = specific activity of drum contents uCi/g x 453.6 g/lb. x Average drum weight lbs. x 1 mci 103 uCi
- e. To determine the quantity of Transport Group II isotopes normally found in spent resin, a sample of primary coolant shall be sent to an outside vendor (Teledyne) for Strontium analysis once per quarter. j' When significant fuel leaks are identified, as specified by the Ilealth Physics Radiochemistry l Superinten(ent or his designated alternate, this l
analysis will be done more frequently. The i contribution of Transport Group II isotopes, which is 3-determined from the ratio of the Csl37 activity to l the activity of Sr90, must be added to the to,tal . . curie content of the shipment.
;m gr ) [- m Egv a.'
The following example calculation illusttates thic'mdtihEid: ~ 1 n j j Given: Total curie content = 150 mci [1 (excludingcongibution f rom Group IT" isbl, opes) Activity of Sr = 1.5 E-07 uCi/ml Activity of Csl37 = 3.0 E-04 uCi/ml pD *?W'l p n f I L _ .__ _ _ _ _ .__ - __ _ __
I l
~.~ ..,_e ,
E.1. HATCH NUCLEAR PLANT . HNP 8016 See Page 1 -m e l
,. a 11 !
See Page 1 17 of 46 Ratio: Activity of Sr90 = 1.5 E-07 = 5.0 E-02 Activity of Csl37 3.0 E-04 Contribution from Group II Isotopes: 150 mci x 5.0 E-02 = 7.5 mci e Tot--l Curie Content: 150 mci + 7.5 mci = 157.5 mci
- f. Sum the specific activities of the radionuclides present with half-lives longer than five (5) years (uCi/g).
- g. Calculate the volume of the resin accounting for any settling in the container (cm 3),
- h. Estimate the concentration (uci/cm3) of the radionuclides present with half-lives longer than five (5) years as follows:
Concentration uCi = cm3 (Specific activity of radionuclides x (453.6 g/lb) x (Average drum with T 1/2 5 yrs. uCi/gr) Weight LBS) (volume of resin cm3)
- 2. Trash
- a. Measure the exposure rate at contact of each accessible side and top of the container in mR/hr.
- b. Average the highest readings collected at each point (mR/hr).
- c. Estimate the Curie content using the formula below:
j a (i) mci (avg. mR/hr) 6 E(i) n (i) i=1 where,
- 6 = constant
- avg. mR/hr is obtained from Step b.
a (i) is the fractional abundance of the ith isotope
- E(i) is the energy (ies) of the predominant gamma (s) emitted by the ith isotope (Mev) n(i) is the branching ratio of the predominan gamma (s) of the ith isotope. q c r = g "*
j isthenumberofisotopespreset.{ gy
.ss e e n i. y O. SHIPMENT OF EMPTY CONTAINERS (49 CFR 173. 29) ([h i, [
- 1. Containers originally used to ship radioactivo material w, be shipped as Empt y containers if the following requiremen+
are met: pqg gp
a
.-....., mm .. . ._ ,
E.1. HATCH NUCLEAR PLANT nne s o i r, ' See Page 1
"*" l Georgia Powerk6 11 4 See Pace 1 18 of 46
- a. Containers must be securely closed so that no residual material can leak out.
- b. Radiation level must not exceed 0.5 mrem /hr at any point on the external surface of the package.
- c. Contamination on the surface of the package must not exceed values as specified in Section M.
- d. All shipping labels and all stenciled, painted, or engraved markings showing original contents must be removed, obliterated, or covered.
- e. An " Empty" label must be placed on the outside of the package. This label must be a square 6 inches on a side with the word " Empty" printed in black letters at least 1 inch high on a white background.
- f. The Bill of Lading must be marked " Empty Container, which originally contained radioactive material" immediately following the description.
P. SHIPMENT BY AIRPLANE Packages to be shipped by airline must meet the following DOT regulations: 49 CFR 175.75 (a) (3) 49 CFR 175.85 (b) 49 CFR 175.85 (d) 49 CFR 175.700 49 CFR 175.710 49 CFR 173.393 (n) (7) 49 CFR 173.393 (p) Q. INCOMING EMPTY VEHICLES (49 CFR 177.843)
- 1. Once a vehicle used for carrying Low Specific Activity radioactive material in truckload lots arrives, the vehicle must be surveyed. The vehicle cannot be loaded for normal use until:
- a. In the case of a common carrier, (1) Radiation levels at any accessible surface must .
not be more than 0.5 mrem /hr. l em l (2) Contamination on any accessible, ;sur f ac6 Sp,,us tin not j exceed: ;. ; ' . ., ib s Beta-gamma- 2200 d/m per 100 cm2 ,. >
- '~~
Alpha - 220 d/m per 100 cm2 ; ., p ; f;,"* b .-w_. ..- . - _
. _ _ _ _ _ _ _ _ . - ~ . . _ . . _- - _ - - _ . - .
_ m _ _ ____ - . , 2
~ - ..
. . ~ , ~ ~ .. m ov o j E.1. HATCH NUCLEAR PLANT * *vm HNP 8016 See Page 1
"^"
11 See Page 1 Georgia Power r.(1 - 19 of 46
- b. In the case of a vehicle which is used only for the transportation of radioactive material ~ and is marked For Radioactive Materials Only.
(1) Radiation levels must not exceed 10 mrem /hr at any accessible interior surface and 2 mrem /hr at 3 feet from any interior surface (2) There are no smearable contamination limits. R. DEFINITION (49 CFR 173.389)
- 1. Fissile Material Fissionable material, typically U-235 and Pu 239. (U-233, Pu-238 and Pu-241 are other less frequently encountered fissionable material). Less than 15 grams. ~
U-235 is q considered non-fissile.
- 2. Normal Form Radioactive material not in Special Form. Normal Form radioactive materials are grouped into Transport Groups.
Normal form materials are typically liquids and powders.
- 3. Radioactive Material Any material which spontaneously emits ionizing radiation.
Materials in which the radioactivity is uniformly. distributed and which has a specific activity less' than 0.002 uCi per gram are not considered to be radioactive materials. )
- 4. Special Form Radioactive material in a form which if released from the package might present some direct radiation hazard but would present little hazard due to radiotoxicity and little possibility of contamination. To be classified as Special Form material, the material must meet the following requirements:
- a. Must be in massive solid form or encapsulated.
t
- b. Must have no overall dimension less than 0.5 mm or have
- at least one dimension greater than 5.0 mm. ==
E
- c. Each item must not dissolve or convkAW'Y,Drb 3tdaty isperriEl form to the extent of more than 0.000% Ltly Wei h when:
f?. 7 (1) I amer s ed for 1 week in water at (%m.B pH 680F, and a maximum conductivity of 10 umhif7c/6h8 mani!2! se! i
t!
..m,m .mm..o.o ;
E. I. HATCH NUCLEAR PLANT HNP 4 ~ ~.v 8016 l gge pg, 1 ,
- en 11 GeorgiaPower A ~~
p ,,, (2) Immersed for 1 week in air at 860F.
- d. Each item must not break, crumble or shatter if a steel rod 1 inch in diameter, weighing 3 pounds, and having a flat end is dropped from a distance of 40 inches into the item.
- e. Each item must not melt, sublime or ignite at temperatures below 10000F.
- f. If the material is encapsulated, it must also withstand a free drop thru 30 feet on to an unyielding surface and it must withstand heating to 14750F for 10 minutes.
- 5. Transport Group:
One of seven groups into which Normal Form radionuclides are classified according to their radiotoxicity and their relative potential hazard in transportation.
- 6. Transport Index:
The number placed on a package to designate the degree of control required for transportation. This number is the larger of the following: ,
- a. The highest radiation level in mrem /hr at 3 feet from any accessible external surface of the package.
- b. For Fissile Class II packages only, the number obtai'ned by dividing 50 by the maximum number of packages that may be transported together.
- 7. Type A Quantity:
That quantity of radioactive material which requires Type A or general packaging requirements.
- 8. Type B Quantity:
That quantity of radioactive material which requires Type B packaging. Type B packaging must meet all the requirements that Type A packaging does plus it must meet the standards for hypothetical accident conditions in transportation 49 CPR 173.398c). , ,, p y g g* jsee ; n e'{,t 9*y Q ( %13 l. S. Semi-Annual Report of Solid Waste and Irradiated ~FuellShipments. l k+ 7 Record, every semi-annual period on,' Figure 20 of; Data' Package " 5, . the following information. '" v w !
- 1. Cubic meters and total curies of spent rmins, filter sludges, evaporator bottoms, etc. for 6 month p"riod.
_ . _ _ - __ _ ._. .-_-- _ __m Inomri en f ' *
.. . .e. s .o um.uo Se<? Paqe l E. I. HATCH NUCLEAR PLANT IINP
"'"*o 8016
,A
,g 11 See Page 1 Georgia Power en -
21 of 46
- 2. Cubic meters and total curies of dry compressible waste, contaminated equipment etc. for 6 month period.
- 3. Cubic meters and total curies of irradiated components, control rods, fuel channels, etc. for 6 month period.
- 4. Other items that contain licensable amounts of radioactive materials not covered above for 6 month period.
- 5. Breakdown of percent and curies of major nuclides for each of the four categories above.
- 6. Number of solid waste shipments, mode of transportation and destination of the shipments.
- 7. Number of irradiated fuel shipments, mode of transportation and the destination of the shipments.
b [ .
, w igs o A, U i
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, [2 } FLASilC BAG h.' YETAL CChTAIER N3 A ,, '; -
IGE RES:St AhX E POWDER IN CLASS
=
LOWWILimC. COMEUST2tE Aho.02 ir.ANCl3tL 50 LID f,,g,<'] 8 L4 . PLASTIC COTTLE #
"SPECIAL FORM" R.A.M. (173.389(G) AND 173.398(A)) .
1 l + l MAY PRESE!!T A DIRECT RADIATION HAZARD IF RELEASED FROM PACl' AGE, BUT LITTLE HAZARD DUE TO C0:'TAMINATICH i "SPECIAL FORM" R.A.M. MAY BE "?!ATURAL" Cl! ARACTERISTIC, l 1.E., MASSIVE SOLID METAL., OR " ACQUIRED" THROUGH lilGil liiiEGRilY EHCAPSULATION U. A SS r.'E 00T SPEC. 2R* lilC!l INTECRITY SOLID !.tETAL (178.341 EIMPLt A110M A As A SEMED SOURCE a
- p. . :in n nu
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*Sr[C. 2R CCNTA!!i'AE'il COES liOT AUICY AT!: Atty OUAlliY AS "STEC L For.t.r SrEt!itt EVALUAliON IS NICES5t.a AGAihst 173 333:Al I
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..a 11 Georgia Power aA ' ' " ~
g, FIGURE 2 TYPICAL TYPE A PACKAGWG PACKAGE MUST WITilSTAND NGR!.iAL COND.: tid:lS (D3.393lB)) . OF TRAMSPORT ONLY WITliOUT LOSS OR DISPERSAL OF TliE RADIDACTiVE COMTROL CONTE?iTS.
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E.1. HATCH NUCLEAR PLANT m,-~ HNP 8016l - sec page 1_ k ~~ 11 Georgia Power om .___SSr._Paqo 1 24 of 46 FIGURE 3 VElilCLE PLACARD FOR RADl0 ACTi'!E T,i ATERl Al.S
-[172. CEl. (A)).)]
9 ' MO '%?' sp s % . e%q} . 2 PLACARD IS 10 DE 0:5 PLAYED ON ECOMT. REiR. AHO Ei,Cli S!DE
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-i See Page 1 Georgia Power ca 26 of 46 FIGURE 5 OL Qi.G; A l'OV/f n C O*dP A 8:V "80.*.'.'..'[ C.I'SD e n i , tm.*a r uro r s c ir *. g; ' " 1. e,m*"*** v1 e4
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- Emsky. Ga. .$ 413 Ort.'uw' ac t.' iw ' 's'.,'"n , , ,,
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- 10. _ - Oce'se 8 gv;/G (LMs; Radioattive t'atertal tv".cy. y x t pipenan' g 7- a ge;}
GLSA DTire A Ova * ?y/Conu ner L CIM1ER CL' A-Butst* CTpe B C.W ty #Canre:ner CL5A-LK UID CLarco Cam.f r w,meri t o .cg* anPne' ors us #M DDFVCE Guetted Quantity DEnporator C:rsv; trues CReses 2. CCompsetc8 Wasta CT, ice;o 1F THMC AAE CHECKE D. WPE A. D. OR LAME Ohm me OUANillf PiUST ALSO E E Cri[CK[ D. Other s VEHICLE 148 0MA ATO:4-Cr4ECK A7PA0PRiA1E T C) T *. , 769*r t n e'eeear f repof5m 4Tr etMTil _. 6 Crriva:a 9.tcrc,r Crrier LPwal F orm 1 Cfisd $6e Lse Cf:stmal I or m* CALJ f. t S pe L*!e Ufgre:aa i cir.) doc;.0 D Lr ra.d GPass.nc er Cavry. rig Tra"5rori Veh:c a OGa s UCver.nl Fo m CN totesa i CClos.2 Traq.p.v. t 03pilr 's+t GPi.e spna't e COu% s CU C P. Lad DCarLonales Other CT gyg, rud. g '/an,
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- Any Special instrbCttaes for Sa'ely opertleg thl3/the peC6 4)ot is/are atisered to t%is CVe s CNet An;. tear.ie shfpriot (c m.
8 p ny re p _a_y_ - .s.+ e n ge 1 r of ret 9 gl e l:b 'r The consM;nen has tm rio ihee n ta om, ci s's rw t ario tt nos t -e ci cecivas i OW9 O*P4 Arohran* 44
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- 1. Tr.AMPoRT Giat7 I II III tv v vg C) ryt?fr pres p37 FALOClhC $rLCS.
Eastouur.lides-l.bbreviatiens /.utteorised a.__ b. c. d. e. f. F. h.
- 1. J., _ L. 1 m. n. o. p.
- 2. So?'.TT PATA-t'5r. AP"T&,tt AT F. T ECTICr. S'!RVTY 17itTS To sg !*g3/i1 1:tM*Eyj 13 I AIThTL;LSE3 /RZ TIC L1;11TS It:R THO*I 1* A5R.'a.h15.
- a. Sole t!se-clos d Trawport b. sole tHe-Onn Trans;. ort 3' Ett horf are l'kg (1000) Contact l'at Ykg (24)
Lat f ur! tc Vi.itele/Gr (2C3) C' Out er !.stes si Sur f aces. Vehicle (69) 6' 4%cer Edges Vehicle (10) Notaally Occuned Positica (2) Nortally Occupied Positico (a)_
- c. Koss Sola Use-Ope-o or Clored Transport d. Eurvey Instru ents ,
Costaet Ext Surf ace Phr. (700)_ inst. Ser. No. I 3' tar sur fwe tks (10) Inst. Se r . Eo., I
- 3. COiTAFINATIC:* DATA F,ata-Cnesa (22.CU0r:!/10CCt2) term /1Cm:2
- Alpha (2.700W/td) m /103CM 2
*EfLESS l'/.TIF.IAL IS A!J" A EMIT!ER OR Pl.CK.ALi. iiAS I.EEN SU3 JECT TO AIIHA CJ. TAM 15AT104 II SE9.T NA C4 AtJ'dA Ll!.E.
W .O . -se c: AP . . .%I A r. g in
- 3. Weig ht
- O vee a r:ot Appiscahre
- 2. Cansi,rnes !!a*= 5 Address ** O Yes O Hot Appliuble
- 3. t ype P a. ka r.s a: Ma rh i n st (Tspe A or Type c) O v , O 1:ot. A .plicable 3
- 4. LSA Patiages lh th d "Ladioac tive f. A" Q Tes O Ect AJolicable
$. Liittl ed Qem.t t t y P-2 k.is.s * . Intertor Parka.te tiarked %dicactivo" O Yes O Not Applicable
- 6. Shippi.ig Essa Itatiken *** O Yes O Not Anitcable
- PIQLIE!D ON EAGt PMTJ/:2 O*.U 110 L35., FlCEPT IF ISA SOLE USE ee M4C El D L :Li.55 W'IciI 13 SOLE L3E ese ggt gtgxx pg 1
p 4 Le illit n e r. - s This is to certif y that the Alovo r. e4 au.torials are properly el.ssified. described, pactated, eaiked. an1 labeled, and ..re h prove conditica Icr t ra,$portatic.o according to the applicable segulatioas cf the t<part*.ent of Ir.uwtortation, bhlprer's $1gnatuna P tr. w 15 s les L6 Tkte record cospleted by 1,A L L Survey .!sta. packetinr. I Aling and tusking checked f or ace p11ance with applicaSle regulations torn an higheturc 4pA L L t w. . o .- . . th is Itueles t p.=<er t;enerstIns f acilities do not esteed transurantee liette of 10,, NANO C1/ CRAM. to thte statement app!tcable? O Y.. O so p 7en , g c4 7. x
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28 ef 16 FIGURE 7 DATA U:{ lip TYPE WASTE U:llT# TYPE WASTE n l n c d a o c FLg. t con t at.t TI Contam- Qty Pounds [Pkg..* Contact TI ACT. ACT. Centam3)d ty Pounds (Ur/hr) (rmM r' frCi) inatnr ' [nr/hr) (rr/nr1(rCi) i ution 3 ! s I I I e i i I i I
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. y 73 fiolFS a. Contact reading for bill mg purposes.
- b. TI to be filled out if packaqM bear Yellow II or Yellow Ill labels.
- c. Conta:aination levels in ta';t/100 us? See section M.
- d. Qty-Enter <1uanti ty u;ed in cubic f eet,gallnns :aillili ters as . , ;;repria t<-
- e. f or ni>cd f reicht shipments TI cannot exceed W.
- f. L% n usinq yellow 111 1.ibels '.ehicie r:ust he placarded. CD"I'" C 'l !'
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Georgia Power al. - SrM_Paga 1 30 of 46 FIGURE 9 CilEli-MUCL E A'E SYS FEMS lt'C. RAD 10/tC H VL LIM.jH RLCORD FORM CHEF /i-NUCLEAR SYSTEfiS, INC. INSTRUCTIONS FOR CO?APLLTING RADIDACTIVC SHIM'ENT RECORD TORM - t;OTE SWf y NT W v M rm nr O if COW [ NTS 9 g crynTIN'i DOCl".tf W ATION AtO PM CN'iRf OviO.*ENTS
/M t,OT I . CO!.H IAt:C W lH C 6 h M fn:CLI Mt S'i Fil f,'S r4 ? '; ST ATE AND i! C; hAL LIC:!UES, lHE l'Af 0fAiI L SITt' CHIT! hits /ND AWilC/[u.E DDI AND NaC SttirihNG HECULATIO:il CEfCRAL Cu tomer cr thwr rnust prov:de (pnted or 1 ped) 3 intorn;at.c.n in afi numbered cc:u nn heedings.
Ind caf e comacov nan'e. con'ar1 addie:s r.nd phone numbcr, company name of c.arner who is transpo'iiag the rr.atcrial cfsd the d e of the sh p:r cr.t sa rpaces p:ovind.
/.n authonzt d rr presen';t.vc ct it.e company miM sign and date the State of Sou:h Carol.na and DOT Cett!. cat:on str.tcments.
Cofaran f.ead ng cnhos are to be made as fonows: (1) Item o* conta:ner numbcr - list each conta ncr scpdrctely. Identficaijon on pa;kage itsc t shal mcich nun bcr in this cc!umn . (2) Pad onocMe - t -t cach ratoco'opo contant:1in cach container (See Note t'3). Tho ic ms FATP cnd tACP are-nd perm!tted. Use es snany t.ncs as are veau. red. (3) Pr'ys c21 Date - ind;cate state - sohd. gas, tiological. (4) Chemical form - reference sect.on 172.203 cf 49 CFR. examp!cs: m ete cheml::.I form
- 1. solid +cd liquid urea formaidehyce (UF) (schdificMon men)
- 2. - resin metah c oxido deposited on recin
- 3. laboratory trath Na or KI, Sri . etc.
(5) Waste desentcon corhpfrs: (evaporator bot! cms). (Mer rncterials). (sold,f.ed f csins) (. rtdated meta:s), (animal cPrca%CS). ct c0lmd. (0) SNf.1 (Soc.ral Nec har Malenah cranc . werght n orams of mat &ol as dehncd in 10 CFR Part 20 3 (S.C. Title A 1.2.24) cannot enceed 50 grams per 4 0 cut c feet or larger container. (7) f.avrce Pounds - we ght in pounds cf rnaterial as cetned in 10 CFR Pvt 20 3 (SC. Ti'!c A 1.2.24 (8) Record the actmty (mdliturie) qucnhty of coch iacicpc in each container (includ.ng the acbvity cf the SN'A cnd fxsurco Poends). (9) Gross Wethi - weenht in pounds c' IV d. nor5'e containcr (includ ng contena) A! p2ckages in excets cf 110 pounds rnust have we.gni ana.cated (see 49 Ci H 172 310). (10) See Section 173 3?] of 49 CFR (11) Record external volume of conte,nce (7.5 fP Icr a 55 ga:hn drum. 4 0 fP for a 30 gMion d um. and 0 ES :P Ior a 5 gatton pad) (12) Ind cate DOT /NRC container spt cificaSon if apptcab!e. sudi as Spec 7A, Type B package, stiong tGht contener et . ceterJ. (13) Record ihn tanhmt rr cae.uted rMa%n inc9 fcr each or potable conta:ncr t.t the specibed distances. Transportat.on Index Numttr (iI)cauais n H/hr reaang ut 3 feet. p
-s (14) Remowe contannahen lavets c, conta.ncrs sha'i not exceed lev <t r.ct forth in rect on 17 (15) Pockages shN! be lab +d as reqmn<1 by Sectons 172101,172.300.172 4C0,172A03 tre Mat' 173 yg ofl49 CHU
[ $f , s t .. s e 'g - - (10) Record cask #dentheat.on number 1 rom name p!ste on cask. kh
- i-
, c. E
, s (17) Record t'.e l'a :er *ntihcabon number in trace proeded. g ,; 'A :
s .. ,u2 y ' Note 1) The t..tal1.no at the bnMom of each rw mrt tie com;A red for co'emns 1,6. 7,8 and 11 by1h5 customer. 2; rach ican shome nt rnmi n.. acenmn en.e bv a,,%1one nnsyr. reprrtennna tnis ch:pment win n includes cacs , 15obipe. Ihe elbunn tr;Ctf 01 e.sCrt ,sn.1 th* kHiri cube COf tlent.
- 3) If rMrP tf Lin ne b; eOnni rCF in 1% sh l5'""P,! C(se f.gm stry, s ;.rpr* f ptre tit ;.hs%d'iqrp .-f path f;. Snqpt l< p, the t's 3P P[nt),
Of r ihl . '* 1m I . ' 30;l l' .8 nr (k !( f 4 3 s' d,U l ? t ilP F. f t +1 p't d 0 9 , ? J t ' .I CC' .!,t n. f Of3 r , E g n y.,+,4 4 ( OrN b 'l \ t d sf TIC'e till #I k id
. I n d' ',0. ll1 if I h' . ! ' N] [ r r18 ',F M ) I!'.f I'.Ieyt }d [ lll I. AfUflen N 2, I.') [p r. )'l (hif l' total t.aiLC urie t nottnt fut t .it h c nota net n the u nt % tKmd be ic,lt d in G0lumn 4.b.
- 4) Ad t.torai !.to;png pagrs raay to requiraf - er ter to C.) CTH 172 201 in au ,h 172 203 M e M R.olnTcal r heprnents rnost cr>muis w.tn 4'J Cl!! 173 MG throunh 173.%3 in t.Jdibon to Itwi E.la CWor- h b hN
w x
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% 1 sE;IJHATCH NUCLEAR PLANT HNP 8016 j See Page 1 t
um ' 11 1
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See Page'1
-Georgia Power om f
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- 31 of 46 _
FIGURE 10-CHEM NUCLEAR SYSTEMS. INC. /
- 7 e o. cox n6
.". D.AH, f4Wf tt. S C. 29812 l' PHP FORM '
. .- . 'l-
's?.h icfcpioca (sp3) 259-35't7 or 259 3570
. , t
., s+
S 1. Categosy or Shipment: 2. -Date: ~
.x, Reviced Date:
. V o
., 3. Shipper's Name: ' Street Address:
l City: ; _ -State: Ep:
, . g .
!. -e
- 4. Emerg ncy Contact Person: Emergency Telephone No.
( 'Catricr's Nacie: Street /.ddress: 3 e Cityr ,, State: Zip: y
;fiq, 1.uargency contact Person -
Emergency *ielep.hune No. s ,
- 7. Volume ot Shipment: Cubic Feet: 8. Estimated Total Activity (f or Tyne 11
~ & Large Quantity)
-e j
- 9. i
- Estimated Date of. Shipment
- '
I V i
- 10. Estimated Date of Arrival of Shipnent:
l l {; 11. Routes Shipment 11111 Follow In State Of South Carolina (Le Specific): I ? i 3~ ,l
._. c,e h68 t
'W as U" V'>,fM
+
'4 s via f p> e ,
. , 1 12.
- t. b .
i Signaturu/tirse et Person Cor7'leting L.. ,: Forta is.Dji bE%r4 " t' rt 13. xf Copy #1: CSem-Nuclear Systemi. Inc. Tcicphone Number l Copy #2: State of South C.irolina. DpEC i, Copy #3: Attach to itSli rom - ,l
.. Copy #4 -; shlpper's Cury L v e mam!al snL-
i
..,n r,u t uun, e.o q
E. :, HATCH NUCLEAR PLANT ime 8016 m,y p ,1 .m.~., n d 11 Georgia Power al - _Jm rr Pace 1 32 of 46 FIGURE 11 IT.F I S t 110M'". TI e Prior ::otificatien Plan (P:.P) is re;uireJ by the State of South Carolina. Prior notification is required for shipment.s falling into the folleuin; cater,ories: 3 Category of Shipments: , i CatcCory I: Shipnent . cont 11nin:; Type B er Larger Quantity Packages (twelve days notice requir(d). Category II: All Cosk Shiprents (Five day a netice required). Category III: Ion-Cank shi;ecnte greater than 75 cubic fcet (ten 55-gallon druns) (Five days notice required). Specific itens as per frcnt of forn:
, Item (1) Category of shioncnt (see above).
(2) Date the date this forn is filled out or revised. (3) Shipper's name: Specific corpany and plant nato, location b/ name of street, city, ntate, and zip ccdc. (4) Sane of person to be contacted in case of an energency with the ship =ent, with the approprir.tc R:EAGE:'CY telephone nutber. (5) ::ane of transportation company picking up this shipment for delivery with street address, city, state, and zip code of major hone office. (6) Name of the pernon to be contacted in case of an cectnency with the shipnent, with the appropriate EMEECE.NCY telephone number. (7) External volume of the 11ncr. box, container used to contain the radio-active material during shipncnt. (The actual volume of the package to be disposed of). (8) The esti=ated total activity f or Category I (Type B or Larger Quantity l packages). The actual cerputed activity must be telephoned to Chem-h*uclear Sys tees, Inc. on the day of actual shipment. (9) The " estimated date of ship =cnt". The actual date will be provided by , telephone on tbo date of _hipment. ' (10) The " estimated date of shipnent AhP1V.\L". This date will be revised when the " actual chip.ent date" is deternined and telephoned to Chen-Nuclear , Systems, loc. Additionally, if the shipment is delaved enroute and will , not arrive on t he entire. tut date, C*EI will be advised by the shipper l of the " revised estimated arrival date". 4 i
.(11) Specify the route that the shipment vill follow during its travel in the I State of South Carolina.
, (12) Signature and name (printed) of the person corpleting tfits form with offico telet. hone number.
l i SPECIAL 1:OTC: F.ce ci p t of mailgram or letter nust be twelve (12) business days prior to ( E lpnent of Category 1, and five (5) business days prior to shipmeut of I Category II and 111 s.hipr.ents. Send to: CHtM-NUCLE AR SYSTEMS, If1C. Post Of fice Cox 776
.Cornwell, South Corchno 29012 j3f
#M h
, gy, tanIts Telephono No: (033) 259 3577 or 259 3578 (+
w l l e 1 o, ,_ P1?"tt*]l r.ot
.. i
........ . _ ~~
E. l. HATCH NUCLEAR PLANT ime solc See Page 1 " "'s G. 11 See Page 1 Georgia' Power m s - 33 of 46 FIGURE 1__2 Cano n i inctruction; and information
- 1. '1his f orn in to be used to provide the Department with price notification of radioactive waste unir: ents trancpcrttd into er within the Gtate of Scuth Carolina. This notificat: 'n is to Le nade 72 hours before the expected date of arrival in the State. All written notices should Le mailed to:
Pureau of Fadiological 1:calth radioactive '.laute Management Section S.C. D:pt. of Health and Envircnmental Control 2600 Dull Street Columbia, Couth Carolina 29201
- 2. A separato forn shall te submitttd for each radioactive waste chipment.
- 3. prior notification ic requirM cf all radiotetive waste shipments as defined in paragraph 2 of Interi:a Ecquiatienc for the Transportatien of Padioactiva Wacce into or within South Caro]ina e:: cept as provided in paragraph 4.1.2 of the Ecculation.
- 4. The " Manifest Summary pnt tion of thic for.n will caticfy requirenants of providing the Department with a shipping *anifect, hrwever, it does not catisfy the recuircments of chipping dccunents which shall accompany the chipments as required by CCr2 F.egulatio:.
and thu dicpecal facality's licence and critcria.
- 5. A copy of this ccupleted fora chall be provided to the carrier and all drivcrc of the radioactive waste chirment.
- 6. Upon delivery of the chipment to the consignee,,acknowledgenent of roccipt chall be obtained, and a copy of thic forn and the shipper / carrier's certification fora chall be returned to the Department.
Specific Inntructionc 2 ten Mumber
- 1. Self Explanatory
- 2. Self Explanatory
- 3. This iten applien to all chirr.ents of radioactive waste t ansported to and within the State of South Carolina.
- 4. Each chiprent of radioactiv2 wacte shall be identified in scme manner hy the chipper.
Thi s number can be a radioactive chipment record nunter, bill of lading nu-ter, allo-cation number, etc. The identification nurber shall only be used once to identify the onc chipment for whien notification ic being made.
- 5. Self c:glanatory
- 6. Indicate in thin iten the dispccal facility, compan*/, organization, etc. , to which this shi@ent has been coricigned.
- 7. ScIf Explanatory ., ., ,=
D. For through shipnents, indicate in thic iten eatinated date chiprent vil17p,a,ss m through the state. $?' .. .'.t 5
-- , - ~'
- 9. Self Explanatory .
10.r. 11. Applica enl/ to exclusive use, cele use, and fuJ1 load chit =ents.'
- 12. All routing inf ormation nunt be specific. ' lou should check ,ti th carrier; tc
- incure routoc you prescrite are appropriate. The carrier 10 recpensible to inforn the Departrent of any changen of routen in South Carolina after departure.
13 thra 21. Self Zxplanatory Certificaticn: Tog'cc o signed
- m. - onlf by an authorized representative er agent of ybbf]Ol' h@ ,
. . , . ~ ..m...,,,
E. I. HATCH NUCLEAR PLANT mm acic son page 1 .m.... we p yy U"O PA4" 1 Georgia Power ed ~~ FIGURE 13 34 M M
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k ~~ 1 1~ 1 See Paqe 1 Georgia Power an 3 r; of 4 (; FIGURE 14 I P.AD10 ACTIVI; Silll311;hT lt ECollO No l'ISS103 f1Altl(Inl oAfr SHlf PLO e nOfA: GEOHGI A POV.En COMPANY P L APJ T E.1. H A I CH IIAXLLY GLOHGIA 31513 UCENSr. NO. fwn U LICE Nnt NO A1T E *ll a nte GHIPfl0 VIA-I'[ MAR K0/DESCRIP TION-
- l'HYSICAL STATk: 0,o'lo O'>ouio Coas Oseccia' rone Otence cuaNTirv Sfd fA ATERIAL-TYPE BY- PRODUCT - 100 TOPE T N .t Nrt nT7 *' mica w Nf c,< s toric rir t;.a i t s i NPL f 1F le! ACitt IT Y t M T f J 1 se a t ,()
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1 v TbANSPORT GnOUP: O' O" '" O'v vi extuar 'Rou o o r PAC A AGING LPECS. HE AL1H PHYSfCS nunVEY RE/ DINGS TAKCfd AFTER MATERIAL 15 CCMPLETCLY PACKAGEO. MAXIMUM RADIATION AT CURF ACC COf4 TACT MR8HH. AT 3 FECT V R /HR. PRINCIPAL EMIOSION: GAMtMA NEUIPON hALPHA LLTA SME AR HESULTS- OPM/100 cm 2 leet A - G AMY Al- OPM/100 cm2I A LPH A) SURVEYCD BY: DATE ! TRAtJSPOnTAiaON { HADIAllON UNITS: FIOSILE CLA;4 /PKG. FIOSILit. CLASS F KG f>HiPME NT l PLACAllD itCOUIRED SHff MENT APPHOVAL j TR ANSPORT A TIUd AND OHiaTING (: ELE ASE THIS 10 TO CCnflFY THAT TFf A00VE NAMED AAT CL ES ARE PAOPLRLY CLA00lTif D, DC0CRIUCD, PACKACtD, MAnkED ANO LADELED AND ARE IfA Pl10PE H CONOlllON 00R TH AN000HTATIOf A, ACCORDING TO THC APPLICARLE DE LULATION3 OF THE DEPT. OF TR AN5PC)AT ATION.
^ OT N MCYliOu OF SHIPMENT k , h2 5 ' ii" (, ' " ('i'\
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, ,j 1 ,, 1, CONTROL AND ACCOUNTABILITY OF RADIOACTIVE MATERIAL A. PURPOSE To define the provisions for the control and accountability of radioactive materials to assure compliance with applicable Federal and State Regulations regarding the possession storage, transfer, and use of byproduct and special nuclear material.
B. SAFETY Observe radiation protection procedures. C. REFERENCES (10 CFR20) (Reg. Guide 7;3) (10 CFR30) D. RESPONSIBILITY
- 1. It is the responsibility of supervision to notify the Counting Room Supervisor or designated alternate of any impending shipment or receipt of radioactive material.
- 2. It is the responsibility of a Laboratory Foreman or designated alternate to approve the shipment and receipt of all radioactive material to and from the plant.
- 3. It is the responsibility of the Counting Room Supervisor or designated alternate to keep an accurate account of all receipts and shipments of radioactive materials, except for special nuclear material (fuel assemblies and in-core l detectors) for which accountability is maintained by the Reactor Engineer.
1 i E. RECEIPT OF RADIOACTIVE MATERIAL
- 1. Upon notification that a radioactive materials shipment is expected, a Laboratory Foreman or his designated alternate will verify that qualified personnel will be present to receive the shipment. If it is necessary to pick up the shipment at the carriers Terminal the foreman v'll be notified when it arrives so he can make every effort to have the package picked up at the earliest possible time.
- 2. Upon receipt of any non-exempt material, component or i equipaent with a radiation warning label attached, the l Health Pb";ics staff will be promptly notified. T;1e Usalth Physics representative must survey theipS*R39 3 %ft 3 bd.YuSN #
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~r u:s if it arrives during normal working hours. If it accives after normal working hours the representative has 18 hours to survey it.
Exempt material should be surveyed at the earliest convenience of the Health Physics staff. The survey will consist of dose rate measurements at 3 feet and at the surface of the package. Also smears will be taken on the outside and the inside of the package. If radiation levels are found on the external surface of the package in excess of 200 mrem per hour, or at three feet from the external surface in excess of 10 mrem'per hour or if there is excessive contamination levels on the external surface ( 22000 dpm/100 cm ), a Laboratory' Foreman or his designated alternate will be notified immediately. If the results are confirmed by the supervisor, he will notify immediately by telephone and telegraph, the final delivering carrier and NRC Region II. All receipts of Radioactive material are to be recorded on Data Package 1, Data Sheet 1 - Radioactive Materials Receipt Log. . F. SHIPMENT OF RADIOACTIVE MATERIAL l
- 1. Prior to transfer or shipment of any material identified as, or suspected of radioactivity or radioactive contamination, the Health Physics staff shall be notified. -A Health <
Physics representative will survey the material or ' equipment, advise as to packaging, labeling and shipment , procedures. The shipment will be remonitored after packaging to insure compliance with all regulations covering such shipments. Refer to HNP-8016, SHIPMENT OF RADIOACTIVE ' MATERIALS. .
- 2. The Health Physics staff will log the transferred material on Data Package 3, Data Sheet 3, of HNP-8017 unless it is radioactive material produced from power plant operation. U i
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- 3. Also, prior to shipment or transfer of radioactive material, i the Health Physics staff will verify that the transferee's l license authorizes the receipt of the type, form, and .r quantity of by product material to be transferred. One of I' the following methods are acceptable for verification.
i a. Obtain and read a current copy of the transferee's j specific license or registration certificate. !
- b. Obtain a written certification from th an ~ that i he is authorized by license or r 46 cate
. to receive the type, form, and q f, roduct material to be transferred, speci 1% t nse or , tigistration number, issuing agency a tion l date. _ l!
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- c. Obtain an oral certification (emergency shipments only) from the transferee containing the information in F.3.
above. The oral certification must be confirmed in writing within 10 days,
- d. See 10 CFR30 para. 30.41 for other methods.
G. LICENSED RADIOACTIVE MATERIAL
- 1. Licensed radioactive material will be handled by or under the supervision of those individuals named in the NRC by-pr> duct material license.
- 2. A complete inventory will be maintained by the Health Physics staff of all licensed radiocctive sources on-site on Data Package 2, Data Sheet 2 and Data Package 4, Data Sheet
- 4. At intervals not to exceed 6 mo. a list of all such sources should be obtained and checked against the source inventory Data Package 2, Data Sheet 2. The Source Continuation Sheet, Data Package 5, Data Sheet 5 should be updated anytime a liquid source is diluted, divided or disposed of. All sources must be accounted for. At no time shall the total quantity of each isotope exceed the quantities specified in the operating license.
The Health Physics staff will assure compliance with provisions of 10 CFR20, 10 CFR30 and any conditions of the byproduct material license.
- 3. Records will be kept of all receipts, transfer, disposal,
- leak tests and other information pertinent to byproduct I
licensed material. Scaled sources shall be leak tested as per HNP-8015.
- 4. Transfer of radioactive materials (except radioLative materials produced from power plant operation) wi.1 be documented on Data Package 3, Data Sheet 3 - Radioactive Materials Transfer Log. All radioactive shipments off site will be documented on Figure 1, HNP-8016.
5. In plant use of sources will be controlled aq, d n HNP-8014. {3 {,{[g, s{ H. NEW FUEL HANDLING AND STORAGE {*s b u ha g .
- 1. The receipt, handling, and storage of new furd h St be in l
accordance with the provisions of 10 CFR70, Special Nuclear l Material. Transfer control and isotopic content records are , l maintained by the Reactor Engineer in accordance with l HNP-9600, SPECIAL NUCLEAR MATERIAL INVENTORY AND TRANSFER, i CONTROL. PEMIQf d
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- 2. All handling operations shall be consistent with approved safety practices relating to the safe handling of special nuclear material.
- 3. A Laboratory Foreman or his designated alternate shall be notified and have the IIealth Physics staf f survey new fuel for radiation and contamination levels upon receipt.
- 4. The new fuel storage vault shall be covered at all times when authorized personnel are not present.
I. SPEtJT FUEL SIIIPMENT
- 1. Tne shipment of spent fuel assemblies will be in accordance with provisions of the facility license and applicable sections of 10 CFR71, Transport of Licensed Material.
- 2. Prior to shipment of spent fuel from the plant site, the Ilealth Physics staff will survey the shipping cask and transport vehicle for radiation and contamination levels.
Records will be maintained for each shipment of expended fuel assemblies. v" O9 t, A. 0W i [U ?T'I?" OA
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