ML19319D256
| ML19319D256 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 04/13/1973 |
| From: | Albert J, Stewart W FLORIDA POWER CORP. |
| To: | |
| References | |
| RP-1601, NUDOCS 8003130895 | |
| Download: ML19319D256 (34) | |
Text
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ttev. 1 4/26/73
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RADIOLOGICAL CO:; TROL PROCEDURE RP-1601, FLORIDA PO*R.R CORPORATION CRYSTAL RIVER CiIT 3N s
KAbiAttu.N PROTECTION ?'J.NU.*d.
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REVIEb'ED 3Y: Plant Rcvice Cc==.ittea
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APPROVED ~5Y: Nticli.ti Plant' Sune rin:ende:-
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e the foregoing statements and references to comparative generating costs in New England. It has been evident since Cainesville was permitted to intervene in this proceeding that its primary objective has been to convert
' the proceeding into one for determining whether or not this particular reactor (Crystal River Unit No. 3) has any " practical value" as defined by Gainesville and every other similarly situated municipal intervenor in recent Section 104b licensing proceedings. Even if " practical value" as defined by Gainesville, were a. proper matter in thi's proceeding, the in-clusion in the record of the above-quoted statements and material would be improper at this time. Applicant would be denied the right of cross-examination or offering rebuttal evidence to point out the many differences existing between New England and Florida when comparing generating costs-with different types and sizes of generating units.
- 4. The reasons why or the business judgment exercised by Ap-plicant's Management in choosing to build a nuclear facility, as opposed to a conventional generating plant, are immaterial and irrelevant. Such information has no bearing upon any issue over which the Commission has jurisdiction in a 104b licensing proceeding. The Commission has repeatedly stated diat the mere fact that utility companies and reactor manufacturers are willing to accept the business risks involved in constructing and opera-ting a nuclear reactor does not amount to " practical value" within the mean-ing of Section 102 of the Atomic Energy Act of 1954, as amended. (Duke Proceedings - Dockets Nos. 50-269, 50-270, and 50-5287.) The soundness of the Commission's interpretation of "practica; value" is amply illustrated by 'the unforeseen dd, lays and increased costs of Jersey Central Power and Ligne Co.~ and its contractor in the construction of the Oyster Creek reactor.
The Commission can take judicial notice of the experience at Oyster Creek F
.' .. : , p , n P 4 RP-1601 TABLF. OF CCurENTS Section
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, 1.0 INTRODCCTICN . . . . . .......... ... . 1 2.0 ,
RADIATION E)?OSL72 POLICY . . . ..... ... . 2 3.0 RADIATION PROTIC" ION STANDARDS .. ...... . . 3 3.1 DEFI?"ITIONS . . . . ...... ...... .. 3 3.2 OCCU?ATIONAL E}?05L?Z CONTROL . ...... .. 4 3.3 ADMINIS T PATI *w~' E:OGiUP2 CONTROL .... .... 5 3.3.1 E: sternal 6;iation Exposure Limits . ..... 6 3.3.2 Internal Raciation Exposure Li=its . .. ... 6 3.3.3 Total Internal-External Exposure . . ..... 7 3.3.4 Exposure to Visitors . . . . ...... .. . 7 3.3.5 Radiation Exposure at Off-Site Locations . .. 7 3.3.6 Etergency and Special Exposures ...... . 7 4.0 RADIATION EXPOSURE CONTROL . . .. ........ 9 4.1 DESICATION OF ?_2_DIATION CONTROLLED AREA . ... 9 4.2 RESPONSI3ILITY Cr : NnM . . .. ...... 0 4.3 CLASSIFICATICN OF AREAS UITHIN THE FCA . .... ,9 4.3.1 Radiation Area . . .... .. .. ...... 10 4.3.2 High Radiation Area .. . .. ........ 10 4.3.3 Air'corne Radioactivity Area ........ . ,10 4.3.4 Contaminated Area ...... ........ 10 4.3.5 Radioactive Materials Area . ........ . 10 4.4 PERSONNEL 3'0VE}2N! T0/FROM RCA . ........
- 11 4.5 RUIES WITHIN THE RCA . .. . . . . ' . .. .... . 11 4.6 Pf'.vVAL OF EQUIP:2NT FU.0M RCA ........ . 12 4.6.1 Unconditional Release . . .. .. .. .... 12 4.6.2 Conditional Release . . . .. ........ 12 4.7 PROTECTIVE CLOT'4ING , . . . . .... .... . 13 4.8 USE OF PR0iECT VI CLOTHING . . .. .. ..... 13 4.8.1 RCA Entry Procedure . . . .. ..... ... 13 4.8.2 RCA Exit Procedure . . . . . . . . . . ... . 14 4.9 UNCONT!O'INATED ??CTECTIVE CLOTHING . ..... . 14 4.10 LACDEPF.D PROTECTIVE CLO 3ING .. ...... . 14 4.11 ACCESS TO CCNT/22NATED ARIAS . .. ~... .... 15 4.11.1 Entrance to a Contaninated Area . . .. .. . 15 4.11.2 Exit From a Conta=1nated Area .. .. .... 17 4.12 . _ , , , ACCESS TO AIP30P2E CCNT. alp _NATICN MIAS . .. .. 18 4.12.1 '-
Airborne Particulates . . . . ..... ... 18 4.12.2 Caseous Activity Protection . .. .. ....
~ 18 4.13 WORK PEPJ'ITS . . . . . . . . . . .. . . . . . ... 19 -
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-4.13.1- _____ -St endinz ,:ad1.et fon. "'or.k.-hmii; ,_m,.,__m..._19_.........___
4.13.2 Radiation Work Per=its . . . ... .. ...'. 19 O
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- RP-1601 r.
. TABLE. 0F CONTENTS (CONT'D)
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_Section Pace 4.14 4.15 ~. PERSON'!EL DECO?:TAMINATION . ..
PE? SON':EL INJURIES ........ 20 g 4.15.1 . . . . . .. .... .... 20 g 4.15.2 Assignment for Persons Having Skin Breaks .. 20 hinor Injuries . . .. . .
4.15.3 Other Inj uries . ... . . ......... ... 20 1 .
........ 21 5.0 PERS0'.7:EL 3'nNITORING .L';D ACCOC:T.GILITY
,.. .. 22 5.1 SCO?E 5.2 ~ . . . . . . . .. . . .. ........ 22 _.
5.2.1 TYPES OF ?E? SON' EL DOSI1ETER DEVICES TLD Dosite:er .. .... 22 5.2.2 . . ... . . . ........ 22 5.2.3 Fast Neutron Film Dosi=eter .
...... 22 5.2.4 Pocket Dosi=eter . ... . . ..
......... 22 5.3 Miscellaneous Dositeters . .. ...... .. 22 5.3.1 USE OF PERSON'.7L DOSI12TERS ..
Nuclear Plant Employee . . ........ 22 5.3.2-5.3.3 Te=porary E ployees . .... .......... 22 Casual visitors ........ 23 5.3.4 FPC l'anagerent
.. . .... ........ 23 5.4 .. . . .. . . ........ 24
-5.5 WEARING OF PERSO .7;EL DOSI15TERS I
5.6 CA?2 0F DOSIST!E?S . . . .. . . ........ 24 PERSO:C;EL E.GGI ?ERIOD . ........ 24 5.7 .. . . ........ 24 5.8 PFM ON"EL CCILTA!IONAL r..WJSUP.I.... .... 24 5.9 ' RECORDS, Pl?0RTS. A'!3 NOTIFICATION . .
...... 25 5.10 12DICAI. SrRVEII.Lil:CE . ... .
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_ RADIATION PROTECTION ORIENTATION ....... . 25 6.0
_ CONTROL & ACCOCCASILITY OF RADIOACTIVE 26 MATER 6.1 i 6.2 RECEIPT OF RADI0 ACTIVE l'ATERIALS .
....... 26
. 6.3 OFF-SITE SM!?!2NTS OF RADIOACTIVE MATERIALS 26 6.4 SEALED SetRCES . . . . .... . ..
6.5 WASTE GAS ?2LIASIS . . .. . . . ........ 27 WASTE LIOUID ?2LFISES~ ... . . ........ 27 '
6.6 ........ 27
_ SOLID WASTES .
6.7 .. . . ... . . ........ 27 6.8 NEW F1.'EL RECEIPT . . .. ....
SPENT FUEL SMIP!5NT .... .... 27
.. . . . . .. ...... 28 LIST OF FIGURES '
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_FIGtW S Figure 1 h .on ontrolled Area Figure 2 Co..troa Poi.'t .. . ........ ... .. 1 i
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l.0~ INTRODUCTION r
.Th'a Florida Power Corporation is licensed by the Ato:ic Energy Cec =ission to operace'a nuclear pcuer f acility and, together with
- the State of Florida, to possess and use certain other radioactive t-caterials. The icvs require that certain Standards for Protection i Against' Radiation, as set forth in Title 10, Code of Federal Regula-
, tions (10 CFR 20) and Control of Radiation Ha:ards, Chapter 170J-1, of the State.of Florida Statutes, cust be enforced by persons holding such licenses. It is the intent that this Radiatien Protection Manual help teet these require ents by establishing guidelines for the pur-pose of safeguarding the health of all personnel trorking on the plant site and to protect the public outside the boundaries of the facility.
'In no case should any statement in this =anual be construed -tu be less restrictive. ' chan State or lederal Regulations.
Changes or additions to this canual will be necessary to cope with icprovements in Radiation Protection cathods or procedures, or changes in . regulatory requira:ents. Such changes will be posted on plant bulle-tin boards and issued to personnel holding Radiation Protection Manuals.
Occasionally, it will be necessary to icpose te=porary changes not con-sistent with this =anual due to unusual plant operating conditions.
Such changes will be governed by strict ad=inistrative control.
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Page'l RP-1601 Date 1/19/73
..- m 2.0 RADIATIO'; EXPOSt.*?I POLICY .
It is the policy of this plant to keep radiation exposure to personnel as low as possible yet consistent with regulatory 11=its. To accc=-
plish this requires the control procedures contained in this =anual.
It is the dual responsibility of the Che=istry and Radiation Protection Departcent (ChetRad) and each individual to insure that all personnel are cognizant of, and practice, the controls established.
The prirary responsibility for radiation safety rests with the indivi-dual. His attitude toward practicing radiation safety af fects not only hi= but his fc11cv workers as well. It is, therefore, absolutely essen-tial that all concerned work as 'a tea = to assure safe radiation work practices. ,
The supervisor is responsible for seeing that personnel working under his control or direction are aware of, and cc= ply with, radiation safety standards and procedures, and that all work is perfor:ed in
- a safe canner. The Che= Rad Engineer shall be notified i==ediately of any unusual incidents involving radiation or radioactive =aterials, any violation of procedures, or of a possible overerposure which =ay require =edical attention and/or regulatory notification.
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s 3.0 RADIATION PROTECTION STA'!DAPSS
.( 3.1- DEFINITIONS
- a. Restricted Area All areas within a 4400 foot radius (Exclusion Area) from the reactor building.
- b. Nuclear Plant Area The area inside the Nuclear Plant periceter fence.
- Access into the area is controlled for radiological and
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(security purposes through the guardhouse.
- c. Clean Area l
Areas which contain little or no contamination, or i require specific radiological controls. The following l shall apply for a Clean Area: l
- 1. hixedsurfacecontacinationceasuringlessthan 0.25 mrem /hr beta-gac=a and less than 300 dpm alpha,
. as measured by appropriate survey instrument probes.
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- 2. Recovable contamination less than 300 dpm beta-ga==a
. or 30 fra alpha, == dararmined by seear surveys 2
representing approxi=ately 100 en of surface area.*
- d. Radiation Controlled Area That area which may have conta=ination or radiation values !
'in excess of the requirements for a Clean Area. The auxiliary building, reactor building, and Radiation Pro- I tection Service Room, laboratory, and Hot Locker Room j shall be considered Radiation Controlled Areas (RCA) for control purposes (see Figure 1).
- e. Radiation Area I
Any area where the whole body dose could exceed 5 cres in !
any one hour, or in any five consecutive days a dose in l 2xcess of 100 nrem.
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- f. High Radiation Area Any area where the whole body could receive a dose in excess of 100 nrem in an hour.
- g. Contaminated Arca Any area where the secarable centamination is in excess of the values given for a " Clean Arca", e.g. , greater than
- L100 cm2 equals an area ocasuring approxinately 4" x 4" square.
Page 3 .RP-1601 Date 30/31/72
300 dp:/100 cm2 .and 30 dp=/100 c=2 of beta-garma and alpha conta=1 nation, respectively.
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- Airborne Radioactivity Area
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An area where airborne radioactivity exists in concentra-tions in excess of Appendix 3, Table I, Colu=a I of 10 CFR 20 of identified radioisotopes, or 6 x 10-13 pCi/cc of unidentified alpha isotopes, or 3 x 10-9 pC1/cc of I unidentified beta-ga==a isotopes in absence of alpha enitters.
- h. Standine Radiation Work Permit (SRX?) .
A SREP, authorizes entry into the RCA for the purpose of
'doing routine work, to supervise, or to observe, in areas where periodic surveys indicate that exposures to indi-viduals will not exceed 100 =ren in any one week, and that special precautions such as respiratory equiptent are not needed. g
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- 1. Radiation Work Permit (RWP)
A RWP is a form which, when approved, authorizes specific personnel to do work or enter an area that requires special precautions to =inimize a radiological hazard.
- j. Radinnetive Material Area Any area which contains radioactive caterial in excess of 10 times the quantities of caterial specified in 10 CFR 20 Appendix C.
3.2 OCCUPATIONAL EXPOSUF.E CONTROL 3.2.1 In keeping with accepted practice, all radiatica shall be dee:ed undesi-rable and as such any radiation exposure should be cinitized. As previously stated, responsibility for radiation safety rests with the individual, therefore, it is the individual's responsibility to mini-mize his exposure and that of his fellow eeployees.
However,- it should be recognized by each c=ployee that he ray be required to roccive exposures up to the limits prescribed in 10 CFR 20 in order to properly operate and maintain the facility.
Occupational exposure includes radiation from internal and external sources, but does not include radiation exposure from fallout, natural background, or therapeutic and diagnostic medical exposure. E=ployees are . requested to notify the ChenRad Engineer whenever they have been ;
medically exposed to radiation. ; i l
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Page 4 RP-1601 Date 4/26/73 Rev. 3 l
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3.2.2
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Personnel working at the Nuclear Plant shall have on record at the
' k' ChemRad office an updated AEC-4 Exposure Fors and cay receive quar-terly radiation doses _in accordance to the follering table, provided their accu =ulated lifeti=e whole body dose does not exceed 5(N-18),
where "N" equals their age in years on last birthday:
Rees Per Calendar Ouarter
- a. Whole body, including head and trunk, active blood-forning organs, lens of eyes, or gonads 3 recs ',
- b. Hands and forear=s; feet and an'Eles 18.75 rems
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- c. Skin of whole body \ 7.5 re=s i
Those not meeting the 5(N-18) requirements shall not ' exceed 1.25 re=s '
whole body per calendar' quarter.
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i 3.2.3 l
'In no case shall an individual under age 18, or females known or suspected to be pregnant, be per=itted to receive a radiation dose in excess of 125 mres per calcedar quarter.
3.2.4 No individual shall be exposed to airborne concentrations of radio-active caterial in excess of these specified in Appendix B, Table I, of 10 CFR 20, except if the individual is to be exposed other than 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> per week. In that case, a " stay tice" shall be calculated as follows:
I Concentratien given in' Stay Time, hrs /veck = 40 x Appendix B, Table I, 10 CFR 20 Peasured Average Concentration
" Stay tice" will be assessed and evaluated .by Che= Rad supervision.
Under certain conditions, pending AEC approval, the use of respiratory equipment and protective clothing may permit exposure periods in excess of the above. ,
-3.3 AD>f1NISTRATIVE- EX?OSURE CONTROL i 1
l To prevout the overexposure of persennel, it is necessary to establish administrative limits. In sone cases these linits may bc :: ore restric-tive than regulations. Supervisors shall.use these limits in preplanning
-vork involving radioactive ratcrials and radiatien. Careful censideration should be given when individual expecures in excess of the lir.its arc z u_,...
. .; requested. .
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Page 5 RP-1601 Date 10/3.1/72
, 3.3.1 External Radiation Exposure Li=1ts
., a. The taxi =e= veekly (Sunday through Saturday) exposure is 300 cre=s. The Che= Rad Supervisor =ay authorize exposures to 600 crem by use of Fors C12-801.
- b. Requests for exposure greater than 600 crem/vcek will require co=pletica and approval of For= 912-801 by the
\' Nuclear Plant Superintendent. Personnel vill not be
.. allowed to receive =cre than 2 re in any one week, except in cases of special or e=ergency exposures, as
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defined in Paragraph 3.3.6.
.3.2 , Internal Radiarien Excosure Lities
- a. Every effort should be taken to avoid the inhalation or ingestion of airborne activity. Respiratory devices are worn to cinicize internal exposures through inhalation. The following table se==arizes the 40 hour4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> occupancy values of an area with airborne parti-culate activity present:
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\ Unidentified S-y Identified B-y Enitters Etitters i
Mask Not's 3 x 10 9 pCi/cc < than 3?C Required ~
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One-Half 3 x 10-9 to greater than ITC Face 1bsk ,
1.5 x 10-8 but less than 10 >TC Full Face '
1.5 x 10-8 to greater than 10 >TC Mask 1.5 x 10-7 but less than 50 >TC
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, Supplied i.5 x 10-7 50 tTC Air \,
No Entry
- 1 x 10-6 1000 1TC
- Entry cay be granted by approval from AEC.
(Section 20.103,10 CFR 20)
- b. Air respiratory protection shall be worn whenever cutting, velding, or grinding conta=inated caterials, l as prescribed on ENP. 1
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- c. When handling caterials or working in a centaminated j area where the nature of the work nay cause ca airborne ,
radioactivity risk, Scif-f ace tasks shall be worn regard- 1 less of airborne concentrations.
- d. Each person shall have ChenRad personnel check the fit of his rerpiratory device before entering the Airborne Radio-activity Area. CherRad persennel shall not allow an l
1 Page 6 RP-1601 Date 4/26/73 nev. 1
individual to enter such area if cask leaks. A cask may leak if person is not clean shaven or wears glasses.
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( 3. 3.'3 Total Internal-External Excosure Under norcal conditions, regulaticas do not require the calculation of
- a cochined exposure for personnel who have been exposed to both internal and external exposure. This is consistent with NCRP Report No.12.
However, where higher-than-normal internal exposures are encoentered, or where an individual is known to have internally deposited radio-nuclides , medically or otherwise, the ChetRad Engineer cay total internal and external exposures in accordance with NCRP guidelines.
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3.3.4 '
Exposure to Visitors iny personnel within the Nuclear Plant fence and not assigned to the Nuclear Plant percanently shall be considered " visitors" and as such are not to be exposed to radiation in excess of 1.25 rem / quarter.
However, if AEC Form 4 is cocplete; and furnished to the ChetRad Engineer, exposures to 3 r s/ quarter cay be percissible. The Che= Rad Department shall caintain a record of the individual's exposure to radiation incurred during the period of work assign =ent in the facility.
3.3.5 Radiation Exoosure at Off-Site Locations Any individual assigned to Crystal River Nuclear Plant who is to visit another nuclear site where he say be eAvv.ed to radiatica shall ce= ply with the follouing: ;
- a. Notify the ChenRad Engineer prior to departure and immediately upon return.
- b. Wear any personnel monitoring devices issued by the ChenRad Engineer as well as any issued at the site visited. \
- c. Report any dose received to the ChemRad Engineer for inclusion with his cumulative occupational dose.
3.3.6 Emergency and Special Excesures Situations may arise that require the exposure of an individual or group of individuals in excess of their quarterly limits. Such expo-sure is broken down into two categories and is consistent with ICT2 guidelines and AEC guidelines. They are as follows:
- a. Planned Special Exposure A planned special exposure may be juctified only when normal operating techniques are lepractical and doses above the regulatory and administrctive limits cay be encountered. In such a case, an individual may volun-teer to perform the operction and receive up to 12 ren provided:
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1 Page 7 RP-1601 Date 1/39/73
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- 1. Administrative approval of- the Che= Rad Engineer and the !!uclear Plant Superintendent has been granted
- I on Form 912-802; t r
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- 2. The worker's accu =ulated dose does not increase above his radiation bank licit;
- 3. _ In the previous 12 conths he has not had a dose in excess of his quarterly li=its; and i'
- 4. The worker has not previously received a once-in-a-lifeti=e e=ergency dose.
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exposure and followed by _ a written report within 30 days to co= ply with 10 CFR 20.405.
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- b. Emergency Exposure I i
Doses in excess of quarterly limits may occur during an emergency operation, or to rescue an individual whose life is in jeopardy. It is not possible or practical to specify a dose "li=it" since the acceptability of the
- l. dose vill depend on the importance of tha objective. .
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- - Tcr guidance, en c=crgency " hole bndy dn<e of 25 rem is acceptable during an accident or e=erge=cy once-in-a-
', lifetime exposure. If the c=ergency involves .the saving of a hucan life, an absorbed dose up to 100 re has been recognized as an acceptable value. Short-tern physiological and perhaps psychological effects may be
. observed in the range of 50-100 re= whole body, but these are generally short-term effects. ,
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. '.- l 4.0 RADIATION'EXPOSt**E CON ~ROL 4.1
{ DESIGNATION OF RADIATION COSr?OLLED AREA The Radiation Controlled Area (see Definitions, Section 3) includes all- areas within the auxiliary and reactor buildings. A te=porary RCA may be set up in other parts of the plant by barricades, fences,
-etc., with proper posting. A Radiation Controlled Area requires certain adninistrative procedures to regulate traffic for the purpese of protecting all personnel from unnecessary radiation exposure and contamination.
4.2 RESPONSIBILITY OF PERSONNEL The Individual: ,
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It is the responsibility of each individual to obey all rules and procedures, and to report to his supervisor any circumstances where there is doubt as to the correct procedure, or to the safety of the operation.
The Supervisor: '
It is the responsibility of each supervisor to assure that all work within the RCA is done in accordance with approved procedures. It is also his responsibility to inform the ChenRad Supervisor in advance, .
. uhere possible, of any Lepending work to be done in the RCA.
. The ChetRad Supervisor:
It is the responsibility of the ChetRad Supervisor to evaluate radio-logical conditions within the RCA and specify precautionary ceasures to be taken to keep radiation exposures as low as practicable.
4.3 _ CLASSIFICATION OF AREAS WITHIN THE RCA The RCA is shown in Figure 1 and includes the auxiliary and reactor buildings. -Other areas nay tenporarily be designated as Radiation Controlled Areas. All Radiation Controlled Areas shall be conspi-cuously posted as follows:
CAUTION RADIATION CONTROLLED AREA ENTRY BY AUTHORI7.ED PERSOS3EL ONLY
-Within the RCA there nay exist areas that are high in dose rate, con-tain airborne activitics, or are contaninated. Each will be posted in accordance with the particular haanrd.
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- Pano 9 RP-1601 Date 30/a?/72 E- _ _ _ _ _ _ _- - - -
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f 4.3.l' Radiation Area .
," Areas,where the whole body- dose could exceed 5 crem in any one hcur, or 1n any five censecutive days a dose in excess of 100 crem, will be j' posted as follows:
CAUTION RADIATION APIA
_4.3.2 High Radiation Area Any accessible area in which an individual could receive a dose in !
excess of 100 crem in an. hour will be posted as follows:
CAUTION \
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HIGH RADIATION AREA j In addition, all permanent High Radiation Areas shall be barricaded
. within a rigid structure with the gate locked shut to prevent unautho-rized entry. Te=porary areas may use barricades if the duration is anticipated to be less than 30 days.
4.3.3 Airborne Radioactivity Area
_- Any area'in which airborne radioactiva Laterials exist in concentrarinnc in excess of Table I Appendix 3,10 CIR 20, or any area in uhich air-borne concentrations, when averaged over the nu ber of hours in any week during which individuals are in the area, exceed 25% of the a=ounts spe-cified in Appendix B, Table 1, Column 1 of 10 CFR 20, shall be posted as ,
follows:
i CAUTION I AIRBORNE R!.DI0 ACTIVITY AREA j j l \
4.3.4 Conteninated Area Any area in which removable surface conta=ination exceeds 300 dpo/100 c=2 beta-gamma, and/or 30 dpa/100 cm2 alpha shall be posted as follows: '
CAUTION CONTAMINATED AP2A 4.3.5 Radioactive Ms crials' Area
-Each area or room in which licensed caterial is~used or stored, end which contains any radioactive caterici in an arount execeding 10 tines the quantity of such material specified in Appendix C, .10 CFR 20, shall be posted as follows:
CAUTION -
RADIOACTIVE MATERIALS I
Page 10 RP-1601 Date 1/19/73
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4.4 PEPSONNEL MOVE 1'ENT T0/ PROM RCA - THE " CONTROL POIh7" E(~ Entrance and. exit shall always be through a Control Point. The purpose
'. of a Control Point is to insure that personnel are adequately clothed with protective clothing (PC's), as required, have proper personnel monitoring devices, and to prevent the spread of radioactive conta=1-nation upon exiting.
Under nor=al conditiens the Control Point will be at the hallway sepa-rating the ChecRad areas and Hot Locker Room from the Clean Locker Rocs, but excluding the H'ealth Physics offices.
Certain conditions will warrant the establishcont of te=porary Control Points. For instance, a te=perary Control Point will be established between the Clean and Hot SMchina Shops during the cove ent of certain
. equipment into or out of the hot shop; a te=porary Control Point will be established at the dooraay of the drutning area when re=oving dru=s, etc.
It is ecphasized again that radiation and cor.ta=f nation control art each individual's responsibility, and that observance of covement controls through the Control Point and within the RCA is an absolute necessity, i
4.5 RULES WITHIN THE RCA All parsonnel are to observe the following rules while in the RCA. Entry
- into a RCA is controlled by a work permit.
- a. Protective clothing is worn as specified on the Standing Radiation Work Permit or Radiation Work Permit.
- b. Personnel badges and pocket dosimeters shall be worn at all tices. Ine only execption to this rule is the hallway outside the Health Physics office where they ara distributed. Dosimeters shall be reso at periodic intervals and rezeroed before the reading reaches 150 mR.
- c. There shall be no smoking, eating, drinking, or chewing of gum or tobacco in the RCA unless stipu-lated cn the work percits,
- d. Observe step-off pad rules.
- c. Followentrance/ exit rules Iand procedures.
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- f. Do only the work, and in area stipulate'd, as shown on the Radiation Work Permit or Standing Radiction Work Permit. l g'. Exit the RCA CNLY at a Con",rol Point.
. ._]l.-.La%C7 83r arc,a,.,i- 7diately ' {, ,rndictic- ,cnip,*, ,, _ _ _,_. . .
alares and notify the Control Roon.
Page 11 RP-1601 1) ate 1/19/73
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- 1. ' All casual visitors, as defined in Paragraph 5.3.3, shall be escorted by-plant personnel when touring 3
.incide the RCA.
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- j. All radiation, high radiation, airborne radioactivity,- and contaninated areas shall be conspicuously posted and/or batricaded, as applicable, at all tices.
\ k. No caterials shall be removed from the RCA without ChecRad approval. (See Section 4.6 below.)
- 1. Exit doors frc= t'he RCA shall not be used unless used
, as a Control Point. (Doors are nor= ally locked but may
' be opened from inside to permit etergency exit only.)
- m. All work is to be conducted in a practical canner, consistent with taintaining a minimum of radiation exposure to personnel.
- n. The Control Room shall be notified prior to entry and exit of the reactor building and an entry made in the Contain=ent Entry Log whenever the reactor coolant temperature is above 200 F.
4.6 REMOVAL OF EOUIPMENT FROM RCA 4.6.1 finenndi tional Release Equipment may be transferred from the RCA if the following conditions are met:
\
a.. All surfaces are free of recovable conta=ination as determined by alpha-beta and ga==a counting instrucents:
readings are to be less than 300 dp:/100 cn 2beta-ga==a and less than 30 dps/100 en2 alpha, above background.
2 For articles having areas less than 100 cm , the limits shall be less than 300 dpc/ item beta-gacma or 30 dp:/iten alpha, above background.
- b. Dose rate is less than 0.25 crem/hr at one inch, using the E-400 Survey Meter or equivalent.
- c. It is reasonable to assume that no radioactive caterial is inside the equiptent (such as a voltrater, inpact wrench, etc.).
\
4.6.2 Conditional Felease Materials not conforning with the above eay be released conditionally.
These itens will be ~ tagged with a radioactive esterials tag and packaged to prevent the release of contaminatica.
NOTE: Magenta and/or yellow tools shall 50T be recoved fron the RCA for any reason without a clearance pernit.
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RCA protectivo clothing shall not be worn outside of an RCA area.
RP-1601 Date 1/19/73 Par.c 12'
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Except under unusual circu= stances, equiptent to be decenta=inated is the responsibility of the individual or depart =ent re=oving it. Re=o-
/ val is. subject to Che= Rad Depart =ent' approval.
\-
/ ' 4.7 PROTECTIVE CLOTHING
-The purt )se of protective clothing is to protect the individual against conta=in ation; it provides little or no protection against radiation.
Personnel =ay be required to wear the following prot ;tive clothing.
inside*the RCA, depending on work per=it require =ents.
- a. Full Coveralls
- b. Shoe Rubbers
. c. Hood or Cap
- d. Gloves Generally speaking, personnel will be required to wear lab coats when doing work under a Standing Radiation Work Permit and full coveralls, caps, and gloves when working under a Radiation Work Per=it. When wearing full coveralls, personnel are to leave their street clothes in their " clean" lockers. It is advisable to leave all jewelry in the locker before entering the RCA under any condition.
Any personal einching nr nrher ef fects which beco=e contaminated shall be confiscated at the Control Pcint. Atte= pts will be cade to decen-taminate the ite=s. Before re= oval ite=s shall =eet the criteria stated for " unconditional release" in Paragraph 4.6.1.
4.8 USE OF PROTECTIVE CLOTHING The following procedures shall be used by personnel required to wear )
protective clothing in the RCA: 1 l
4.8.1 RCA Entry Procedure
- a. Make all necessary preparations to procure and have approved a Radiation Work Permit, if applicable.
Turn in at Radiation Protection Service Room.
- b. Rc=ove all outer clothing, jewelry, etc. , and store in clean locker if full coveralls are specified.
I
- c. . Exit Clean Locker Room and (1) procure' protective clothing fron-storage shelves and enter Hot Locker l Roon, or (2) enter Hot Locker Room and use PC's
- c. --
__ __, previously stored in hot locker.
l NOTE: PC's arc NOT to be taken into Clean Locker Room. l
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Page'13 RP-1601 Date 1/19/73 I
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- d. Dress in Hot Locker Room. Personnel working in con-taminated areas should tape shut all openings to
{ prevent entry of contacination below clothing.
- e. -Proceed to the Radiation Protection Service Room for special_dositetry recuirerents,-respiratory ecuip-ment, etc., as specified on RWP.
- f. Proceed through Control Point into RCA.
4.8.2- RC'A Exit Procedure Due to the many cocbinations of destination points, type of PC's being worn, etc. , it is not practical to enu=erate all exit proceduras except in very general ter=s.
- s. All personnel exiting from the RCA shall monitor themselves on Monitor No.1. See note below.
I
- b. All personnel exiting the Hot Lo'cker Room to the Clean Area shall conitor the=selves on the Portal Monitor. See note below.
- c. All personnel exiting the Che= Rad area shall conitor.
themselves on Panitor No. 2. .
- c. NOTE: In the event a u:onitor alarns. the individual is expceted to take appropriate cetion. This includes the renoval of clothing, notification of the ChetRad Departcent, and NOT spreading the contamination by entering uncontaminated areas. All contacinated clothing (clothing that is discarded when Monitor No. 1 alar s) shall be placed in_ conta=1nated clothing receptacles.
Personnel having contaminatica on the skin shall take a shower in the hot shower under the super-vision of the ChetRad Department.
4 4.9 UNCONTA'!INATED PROTECTIVE CLOTHING
' Personnel are expected to cooperate in tinicizing laundering because
. water nay have to_be processed through the radwaste system evaporators.
The soap contained in the wash water will cause a solids buildup in the evaporator leading to carryover and techanical problets. Therefore, it is requested that 'unicss protective clothing caures the portal monitor or frisker to alar =, personnel place the clething in their hot locker for reuse. .
, , , , 4.10.... ,
LAUNDERED PROTECTIVE CLOTHING Laundered protective clothing shall be surveyed by the laundry nonitor and placed in the bin for reuse if the reading is less than 1500 cpc.
. , ----- Clothing ;in . excess- of-t.hh-akQ1--(.e d rua..wd-ynQacqgd fpr. r narigd-.c' _ _ _ . ._
one conth, at which tino it shall be resurveyed.
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- Page 14' RP-1601= Date 10/31/72 l
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Clothing reading between 1500-3000 cpc shall be used in highly conta-i, - minated areas only. . Clothing reading greater than 3000 cpm af ter three
\ months holdup shall be discarded as radioactive vaste.
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4.11 ACCESS TO CONTMT!ATED A?EAS - THE "STED-OF7 PAD" It is inevitable that some areas within the RCA vill become conta-J.nated to the extent that it is iceerative that additional censures be taken
\ to prevent its spread to clean areas. This is particularly true of conta=inated floors.
\ Access to any area where the 2 floor has smearable beta-ga-a conta=ination sin excess of 300 dp:/100 cm , or alpha conta=inatien in excess of
\
30 dpe/100 cm 2 , shall be via a step-off pad. Additional protective clothing shall be available at the step-off pad. The contarinated area shall be roped or barricaded and conspicuously posted as "Contaninated Area". At the discretion of the ChenRad Departt.ent, an PS? cay be required to enter a contaminated area if contarination exceeds 1000 dp:/
100 cm2 be t a-ga=a .
4.11.1 Entrance to a Contaminated Area A. Put on plastic suit or other PC's, as required, and shoe covers before stepping on step-off pad. Place each foot on pad when shoe cover is on.
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B. Tape shoe cover to protective clothing, especially when " plastics" are being worn.
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C. Put on gloves and enter:
- 1. Cloth and/or' rubber gloves are ree.uired in all contaminated areas.
- 2. Rubber gloves are required in all wet contaminated areas.
Tape to outside of plastic suit if one is being worn.
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Exit From a Contaminated Area
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. \ A. Recove any plastic PC's before re=oving shoe covers and place in
' \ receptacle provided.
Approach step-off pad. As shoe covers are recoved, place feet OJ
\ step-off pad. DO NOT TOUCH FI.00R ON CONTAMINATED side of step-of f
\ pad. (In tihe event this occurs, place a new shoe cover on foot,
\ assu c it is conta-inted, and wear it to the Che= Rad office where
\ ir vill be checked.) Place discarded shoe covers in receptacle.
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B. While standing on step-off pad, recove one glove and conitor the feet with the hand probe. If the reading is in excess of 300 dpm above background, cover shoes with new shoe covers and report to the Control Point. If feet show no contamination, place on clean side of step-off pad after conitored.
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6 Page 17 RP-1601 Date 10/31/72
1 If you are required to enter a contaninated area, be sure te observe the required procedures. Re:c:ber , contamination con-ig trol is the key to good housekeeping, and all of your fellow
.( workers are depending on you as an individual to keep the
" house" clean.
4
'4.12 ACCESS TO AI?30?2:E CONTAMI'!ATION ADIAS 4.12.1 Airborne Particulates
- It is the responsibility of the individual and his supervisor to notify the ChetRad Deparecent when working around radioactive caterials that may becoce airborne.
Airborne activity areas will be sealed off or barricaded and conspi-cuou, sly posted as such. An RWP will be required to enter an Airborne Activity Area.
Respiratory devices will be required before entry is per=1tted. The type of respirator will be designated by Che= Rad personnel, using the guidelines given on Page 6. Where practical, air sa:ples shall be analyzed periodically with charecal particulate filters while personnel are working within an airborne radioactive area.
Each individual will have been trained in the use of all respiratory equiprent and be thoroughly fa=iliar with their li=itations and check-out procedures in accordance trith the Respiratory Eculptent Manual, RP-1602.
t, Prior to use, the individual shall test the respirator for tightness by covering the air supply ducts and adjusting the harness straps accordingly. A protective hood shall be worn under the mask. While in the airborna. or contaminated area, the wearer should not touch the facepiece with contaminated gloves or recove the rask for conversation
.or visibility. In case of shortness of breath, the individaal may loosen the mask provided he leaves the area immediately.
Used masks shall be decontaninated, sanitized, and checked for defects.
Filter canisters shall be discarded when radiation-levels are higher than 2 mrem /hr on contact. '
4.12.2 Caseous Activity Protection Canister-type face masks of fer no protection against radiogaseous activity. Tritium, krypton-85, xenon, and radiciodine are the prin-ciple gaseous radionuclides with which, we cay have to contend with.
For xenon and krypton-85, the dose to ;the whcle bcdy as determined by an ionization charber (atmospheric pre.ssure) shs'l be the limiting f actor. l If tritium concentration exceeds 5 x 10-5 pCi/ce, supplied m ; r.'sks and plastic protective clothing shall be worn.
.Page 18 RP-1601 1) ate 4/26/73
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If the iodine-131 concentration exceeds 3 x 10-10 pCi/ce, supplied s
\ air masks shall be worn.
4.13 ' ~ WORK PRRMITS $
6
- - In order to raintain. control of personnel radiation exposures, to assure that all personnel are aware of radiological conditions, and to assure awareness of the precautions to be taken, entry into a Radiation Controlled Area requires the use of a Standing Radiation Work Per=it (SRWP) or a Radiation Work Per=it (RWP).
4.13.1 Standine Radiation Vork Permits
'JM SRWP is issued by the Che= Rad Depart ent and permits entry into specific areas of the RCA to observe, supervise, or to do routine work for autho-rized personnel. They cay be issued where periodic radiation surveys show relatively constant radiological conditions within the area of question, and reasonable assurance is given that individuals would not exceed 100 mren in any one week while perfor=ing the required tasks in the area, and that the spread of contacination is unlikely if the require ents sti-pulated on the SPWP are adhered to.
Standing Radiation Work Per=its allow routine tasks such as preventative maintenance on equipment, water sa=pling, and operator duties to be done without the necessity of obtaining a specific Radiation Work Per=it, yet maintaining the radiological safety requirements.
Standing .Maciation work Permits are posted at the Cunttul Pulut and are periodically updated in' accordance with routine radiation surveys.
4.13.2 Radiation Work Permits Radiation Work Pernits authorize seecific individ als to enter areas, or to work on equip =ent, which requires supple =entary ad=inistrative con-trols due to possible changing radiological cenditions during the period the work is being perforced. RWP's are generally required for non-routine work. In lieu of a RWP, the continuous presence of a qualified ChenRad representative may neet the RWP requirecent, provided it does not inter-
. fere with plant operations. The RWP briefly describes the work to be performed, the radiological conditions in the work area, and specifies the protective equipeent and/or eensures to mininize radiation exposures or the spread of contacination.
Radiation Work Permits are initiated by the departrent responsible for the work to be performed. In triplicate, a brief description of the work, the specific area where the work is to be perforced, the indivi-duals who are to do the work, and the estinated ti=e required to do the work are put on the RWP form. The form is then reviewed by the Chet?ad
~Departnant and any special surveys required are perforced to define radiation hazards and special requirements to insure safe verk conditions.
The ChecRad Supervisor will assign a number to the EWP. After his approval, the three forts are taken to the Control Room where the Shif t Supervisor verifics by his signature thct the proposed work vill not interfere with operations. The pink copy is retaf acd in the Centrol Roon,- the white copy
.Page.19 RP-1601 Date 1/19/73
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is given to the Che= Rad Supervisor, and the blue copy accoepanies personnel at the job site. .
Personnel Jhall not deviate from the instructions stated on the R%P, nor shall personnel be added to the RWP (or job) without approval of the ChetRad Supervisor. Should a job extend into another shif t, all interested parties shall be notified for =utual agree =ent provided the working conditions and personnel assign =ent re=ain unchanged, otherwise, a new R%? Eshall be issued.
4.14 PERSONNEL DECO ~r.O'INATION I
All' personnel will conitor the=selves cocpletely for radioactive conta-mination prior to leaving a control point.
+
4.14.1 ,
For skin contamination, decontamination can usually 'ee accomplished
- by pressing tape against the area or washing with seap and water. A
, recheck for conta=1 nation should be made using a tuutd-probe frisker.
!Rewashings =ay be necessary.
l '
l Great care must be taken to avoid breaking the skin, allowing centa=i-
- nation to enter.
I I4.14.2 ,
For more serious contcnination requiring Fi;st Aid, special wash solu-tions, etc., the individual will contact the Che= Rad Supervisor, who will use special decontamination procedures outlined in the Radiation Protection Procedures Manual.
4.15 PERSONNEL INJURIES 4.15.1 Assirneent for Persons Havine Skin Breaks I
- a. The assigncent of persons having skin breaks to work in
-Radiation Controlled Areas should be avoided unless the break can be adequately protected,
- b. Skin breaks will include wounds, open cracks from chapping, luu3 other injuries such as lacerations, ebrasions, punctures, blisters, or burns. Each person is responsible for notifying his supervisor of any skin breaks before working in the RCA.
- c. The supervisor shall be responsible for insuring that any skin. breaks are adequately protected end that attention of
-the break is called to the attention of the Chc= Rad Supervisor.
4.15.2 Miner Injuries l
2e:2;:. - - Jiinor injuries which occur inside the RCA will be treated inmediatelv.
It 'shall be assur:cd that the injury is contaminated. 1he injured Pcge 20 RP-1601
. Date 30/33/72
.s shall leave the RCA in accordance with nor=al exit procedures unless
-!; it . is not practical. - If transferable-conta=ination is not present, he c:ay proceed to the medical rec =. If he is conta=inated but not seriously injured, he should proceed with deconta=ination in the Hot Locker k' ash Area prior to treatment. ,
?
-4.15.3 Other Injuries I Injuries which require the services of a physician or hospital eust be.in *accordance with Section 5 of the plant's E=argency Plan, EP-1201.
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Pag.c 21' RP-1601 Date 1/19/73 '
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'5.0 PERSONNEL MONITORING AND ACCOUNTA3ILITY 5.1 "
- SCOPE
' ' 'A radiation protection program is intended to assure that radiation doses received by personnel are kept as low as possible and do not exceed the prescribed li=its. To acco=plish this, personnel desiteter devicas are
-issued under the supervision of the ChetRad Engineer. These conitoring devices are " read" and the exposures of individuals are kept as perra-nent records. In addition, all personnel entering the Nuclear Plant are issued identification badges. These badges are issued for security and Emergency Plan. accountability purposes. .
5.2 TYPES OF PERSO:YEL DOSIYETER DEVICES .
\
5.2.1 TLD Dosimeter ;
The thermoluninescent dosimeter (TLD) is the official exposure record.
A TLD badge will be issued to each ecployee.of the Nuclear Plant. Peri-odically, the badge will be replaced so the old one can be read. The TLD will give the skin dose (beta) and whole body dose (ga=ca) of the individual for the period.
5.2.2 Fast Neutren Film Desf=eter Fast neutron film is used in areas where neutrons could be present.
. . , nnrm=11v nniv <n rh. v.orene kn41s<,o Two <41- ...a4,- 4, 4.-,..ama as part of the individual's exposure history.
5.2.3 Pocket Dosiceter Self-reading pocket dosimeters are available to give a visual indication of the integrated ga==a dose that an individual has received since it was last zeroed. The reading attained serves as a guide to indicate the exposure only until the official TLD dosi=eter reading is received.
5.2.4 1Escellaneous Desireters I Other types of dosineters are available for specific personnel or for
' limited usage. These include ring badges, filns, pocket chirpers, high range TLD or pocket dosimeters, etc.
5.3 USE OF PERSONNEL DOSIYF.TERS 5 . 3.1. Nuclear Plant Ecolovec A permanently-employed individual of the Nuclear Plant will be issued a TLD hadeo that cust be worn at all times whenever the individual is within the Nuclear Plant perienter fence. The individual will pick up !
his badge at the guardhouse when he arrives for verk and leave it at i the' guardhouse uhen he leaves. It will be kept on a rack rounted inside !
,the guardhouse.- The TLD badge serves two purpeces: (1) his of ficial
- - - - - - - - .radiction exposure -record, and (2) it supolenents the security badge for Energency; Plan accountchility recuire ents. Shruld an individual inal-vertently leave.the site with his badge, he shall notify the guard by phone of the fact so he can be accounted for.
Pace.22- RP-1601 Date 1/19/73 v
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- An individual entering the RCA cust also wear a pocket dosi=eter. Each i individual is assigned a pocket dositeter that is kept on a rack located
\, outside the Che= Rad Service Roo= during periods it is not being used.
\ Upon the initial entry of each day, the individual is to verify that the
. dositeter was rezeroed since his last work period, and if not, notify ChecRad personnel.
\, While of the inside the RCA, TLD badge. Eachthe dositetershould individual should be vorn in check periedically close the proxicity dosi- ,
ceter to verify that it does not exceed 125 tR. If so, it shall be rezeroed by Che= Rad personnel.
(When leaving the RCA, the pocket dosimeter is to be returned to the rack. At the end of each work period Che= Rad personnel will check each dositeter, record readings, and rezero it. Since pocket dositeters are used al adelnistrative zuides by the Che= Rad Department, readings below 10 mR will be neglected and no entry cade on the exposure guidance forcs.
5.3.2 Temocrarv Erelevees i
Temporary ecployees are those individuals who are te=porarily working lat the plant supplementing maintenance personnel.
I Teeporary primary plant caintenance personnel will receive Radiation Protection Orientation (see Section 5.10) and become inticately f amiliar with this manual prior to doing any work inside the RCA. Following this orientation, and upon satisfaction to the Che: Rad Engineer that the individucl is cognirant or RCA rules, tne incivicual vill oe issued a TLD badge and pocket desi 2ter, Subsecuent entries to the plant and RCA will be in accordance with Nuclear Plant e=ployee requirements (Section 5.3.1) for the duration of their tenure at the plant.
Personnel tecporarily assigned to the plant but who are not working inside the RCA will receive an abbreviated indoctrination and will be
. inforced that they cay NOT enter the RCA unescorted and without approval of the ChemRad Supervisor. They will be issued a TIJ) badge but not a pocket dosimeter.
5.3.3 Casual visitors Persons infrequently visiting the Nuclear Plant and not engaged in training, operations , esintenance, etc. , shall be ter=ed " casual" visi-tors. A casual visitor cust,:
a, Be granted entrance to the plant by a responsibic supervisor,
- b. Sign in at the guardhouse.
- c. Be escorted at all times while inside the plant fence, with exception to the walkway between the guardhouse and office lobby ONLY.
A casual visitor may enter the RCA with escort only with appreval frcm a . ChenRad Supervisor.
Page.23 RP-1601 Date 10/31/72 s_
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- 5.3.4 FPC Manacenent-Managecent personnel whose responsibilities include support of plant maintenance, operations, engineering, or canage ent functions cay be given " Nuclear Plant Ecployee" status upon approval of the Nuclear Plant Superintendent. Require ents will be the sa=a but with the following exceptions:
- a. The guard shall notify the office of their visit during normal work hours or the Shift Supervisor during off-hours,
- b. They shall receive per=ission from a ChecRad Supervisor prior to entry into the RCA; escort require =ents shall be at his discretion.
- c. Individuals require reorientation annually to kcap this status.
5.4 WEARING OF ?ERSONNEL DOSIYETERS Personnel dosineters should be worn on the front of the clothing in a visible position. The dositeters should be cevered by no = ore than one layer of clothing if the individual is working in a contaminated area. In all cases, the pocket dosi=eter reading should be periodically checked with an ungloved hand to keep the individual aware of the inte-grated dose.
He should.not allev the dositeter to exceed 150 t2.
5.5 CARE OF DOSIFETEpS Each individual is responsible for preventing damage to his dositeter.
Neither the TLD badge nor the pocket dosineters should be allowed to get vet or conta=1nated. If either gets wet, it should be turned in at the ChenRad office ic=ediately. Each individual is required to
, check his dosimeter for contamination when he leaves the RCA.
Pocket dositeters are subject to damage if dropped. Usually, but not always, they-will go off scale. The ChetRad Department shall be notified immediately if a dosiceter is dropped.
5.6 PERSONNEL BADCE PERIOD Personnel TLD badges will be, processed at regular intervals. The length of the interval will be dependent upon the type of service, for instance, during nornal operations, outages, etc., but will not exceed three months. The personnel badge of any individual vill be processed it c-dintely at any tite an overexposure.is suspected.
l
__. 5 . 7 _ . . , ,, PERSONNEL OCCL?ATIONAL EKDOSURE When any individual nay have been expored to concentrations of radioactive materials, or in cases where it is suspected that radioactive caterials
-may have en te red -the-bodyfappror,riato-bicauav 4.m-f cas-a:.d/c r.-ancr.ia' tests shall be perforced as stipulated in 10 CFR 20.- The deternination
~
of' the individual's exposure shall be based upcn this evaluation.
Par.e 24 RP-1601 Date 10/31/72
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a 5.8 RECORDS, REPORTS, AND NOTIFICATION The ChenRad Engineer shall notify supervisors of the status of exposure
. records of individuals under their supervision. However, individuals
,- - may consult with the Che= Rad Engineer at any ti=e regarding their exposure records. t
_ Upon termination of e= ploy =ent at the Crystal River Nuclear Plant, the
' individual will be furnished a record of his exposure in accordance with 10 CFR 20.403, 5.9 MEDICAL SURVEILI.JSCE All prospective Florida Power Corporation e=ployees cust pass a physical examination given by the }hdical Depart =ent or a Medical Censultant.
This includes cedical history, physical exa=ination, chest x-ray, eye and ear exa=inations , etc. , yearly. In addition to the above, all regular employees who work inside the Nuclear Plant Radiation Controlled Area, or who cay receive more than 500 cre=/ year shall:
- a. Have an initial blood background exanination: R3C, Ng, 'Hecatocrit, W3C, Platelet, Differential, and subsequent analysis as required.
- b. Have tritium urinalysis background ceasure=ent and subsequent analysis as required.
- c. Have whule uudy radiaLion 'oackground ueasurements l 'as required.
An annual physical examination is required on all Nuclear Plant personnel who work or enter the Radiation Controlled Area. Special examinations may be given to individuals whose records indicate he has exceeded the maximum permissible yearly exposure limits.
' Tritium urinalysis ceasurecents and whole body counting will be done routinely on select individuals or groups of individuals as determined by the ChemRad Engineer.
5.10 RADIATION PROTECTION ORIENTATION All new e=ployces shall receive radiation protection orientation prior to their assignment of work in the RCA. Where practically possible, those ceployees will be temporarily assigned to work in the Che Rad Depart cat . prior to reporting -to their regular job assignments. All new enployees shall becoce intimately faciliar with the Radiation Protection ibnual and the Etcrgency. Plan. .
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Temporary employees will be given a general orinetatien lecture on radiation protection practices to enable them to work safely under supervision while in the RCA.
Page 25 RP-1601 Date 10/31/72 l
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\ 6.0 CONTROL A';D ACCot TA3ILITY OF RADIOACTIVE ?'ATERI ALS
-i 6.1 RECEIPT OF PADIOACTIVE l'ATERIALS t
The ChetRad Engineer shall be notified of any imp ling receipt of radioactive catcrials. It is the responsibility of the Che=?.ad Depart-ment, through F?C ad=inistrative procedures and AEC regulations, to docu=ent all radioactive caterials.on the plant site and to perform the following:
- a. Verify package is in ec=pliance with DOT Title 49.173.
k, b. , Test all packages for conta=ination by scear and i
dose surveys.
- c. - Specify suitable controls and procedures to assure safe handling and storage of radioactive =aterials.
! d. To prevent unauthorized persona from having access to
- I licensed caterials, authorized recipienes shall acknowledge by signature receipt of all incoming l
j radioactive caterials.
62 OFF-SITE SHIPPE"TS OF PADI0 ACTIVE 3'ATERI ALS
- It is the responsibility of cognizant supervision te notify the ChenRad -
Engineer of any impending ship cat of rcdioactive natorials. It is the responsibility of the Chenhad ngineer to assure that all shiptent packages are not in violatica of Federal and/or State regulations. The ChemRed Engineer will be guided by Title 49 CFR in deter =ining package parameters. In general, the require =ents governing off-site shipments are as follows: i
~
- a. Smear surveys taken fron each container (af ter filling)
, shall be less than the DOT regulations, which are 2200 dpm/100 cc 2 beta-gamma and 220 dpefl00 cm 2 alpha contamination.
- b. Gamma radiation shall not exceed 200 mrem /hr on the surf ace of the container.
- c. Camma radiation shall not exceed 10 tres/hr at one meter frem each , container.
- d. Each container shall have the proper label affixed.
- c. A shiprent record shall be cade out for all radio-active caterial shipments.
-f. A coeplete snear and dose rate survey shall be cade of the carrier af ter loading is complete. The srear survey shcIl be cade at the point of lor. ding; the dose rate survey shall be cade inside the secondary area or, in the case of a 1crge truck shiprent, at the plant entrance ramp.
Page 26 RP-1601 Date 10/31/72 WW . - - v: , .
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- g. The exposure in the vehicle shall not exceed 2 =Re:/hr at the position of accocpanying personnel.
6.3 SEALED SOURCES All licensed sealed cources, such as calibration sources, shall be leak-tested by .the Che: Rad Departcent in. accordance to applicable regulations at six =enth intervals. Records shall be kept of all
\ t2sts., Sealed source leak-tes". procedures are detailed in radiation protection procedures.
,6.4 UASTE CAS RELEASES
\
- Waste gas releases from the plant are strictly governed by Technical Specification 15.3.9.2 and the Waste Release Procedure in the Radiation Protection Procedures Manual. When it is necessary to release vaste
. gases through either the auxiliary or reactor building vents, a sample of the effluent is obtained. Depending on the isotopes present or the activity, either a gross beta-ga==a or isotopic analysis is per-force d. These results deter =ine all other require =ents such as wind direction or f an dilution flow, necessary to confor=t with Technical Specifications,10 CFR 20, and 10 CFR 50. Percission to perform the release requires the cocpletion of a Waste Gas Release Per=1t approved by the ChetRad Engineer and Nuclear Plant Superinte= dent, or designated alternates . The terns of the release per=it must be adhered to.
5.5 WASTE LIOUID FILEA9FS Waste liquid releases from the plant are strictly governed by Technical Specification 15.3.9.1 and the Waste Palease Procedure in the. Radiation Protection Procedures Manual. Liquid releases are =ade from either the evaporator -condensate storage tank or the laundry su=p. For the forcer, either a. gross beta-gaena analysis or isotopic analysis, plus a tritiu:
analysis, will be nade. For laundry discharge, a gross beta-ga==a
' analysis is performed. \
Before release, a Waste Liquid Release Percit is cocpleted and approved by the ChemRad Engineer. and Nuclear Plant Superintendent, or designcted alte rnates . This release permit specifies what, hoe much, at what ti=e, and other conditions that must be followed during the release.
6.6 SOLID WASTES Solid wastes include rags, paper, lutber, solidified evaporator botto=s, resins, mid filters,_ which are or ray be contc=inared. They are dis-posed of in accordance with Farcgrcph 4.2 and Technical Specification 15.3.9.3. Generally, all solid wastes are shipped out of the state and buried at an AEC-approved burial ground.
6.7 NEW FUEL RECETPT
-The receipt, handling, and ctorace of new fuel asserblics shall be in accordance with the ' provisions of 10 CFR 70, "Special Nuc1 car Materials".
- All handling shall be censistent with the "Speciel ::ucicar ':aterials Handling and Accountability Manual" procedurcs. Nea fuel is surveyed Page 27 RP-1601- Date 10/31/72 s
. r.*.
for radiation and conta=ination. levels prior to or during unpacking and storage.
6.8f -
SPE!:T M:IL SHIP"I?:T s- - k
' p', _, Handling and shipnent of Irradiated spene fuel asse=blies are rigidly controlled by the "Special Nuclear P.aterials Handling and Accountability 11anual" and is governed by the facility license require =ents and a pli-
. cable sections of the AEC and Departrent or Transportation (DOT) rec.:-
lations. Af ter loading has been' cenpleted, the Che=P.ad Depart =cnt_ will survey the transport and packages for radiation and conta=ination levels.
Survey records are kept of all ship ents.
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Page 30 '
RP-MO)
Dr.te 10/3'./72
./ l l STATE OF FIDRIDA )
) SS .
COUNTY OF PINELLAS-)
J. T. Rodgers, being duly sworn, states that he is Asst. Vice President and Nuclear Project 14anager of Florida-Power Corporation; that he is authorized on the part of said Company to sign and file with the Atomic Energy Commission this application and exhibits attached thereto; that he has read all of the statements contained in such application and the exhibits attached thereto and made a part thereof; and that all such statements made and matters set forth therein are true and correct to the best of his knowled6 e, information and telief.
61+.:t ; .
J. T. Rodggra Subscribed and sworn to before me, a Notary Public in and for the State and County above named, this lith day of October,1971.
Thelma R. Maxhimer, Notary Public Notary Public, State of Florida at Large.
My Comiscion E.<pires July 9,1974 (NOTARIAL SEAL)- ,
.