ML20087P019
| ML20087P019 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 01/13/1984 |
| From: | Nix H, Sorrell E GEORGIA POWER CO. |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| GM-84-41, PROC-840113, NUDOCS 8404050372 | |
| Download: ML20087P019 (80) | |
Text
{{#Wiki_filter:- GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PROCEDURE East'e Classification And Manifest Reporting All Type Waste
-- PROCEDURE TITLE HNP-8038 PROCEDURE NUMBER Lab -
RESPONSIBLE SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( ) _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .r________________. APPROVED APPROVED - REV. DESCRIPTION DEPT. GENERAL DATE MANAGER MANA O New Procedure
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- Date: Signature: Date:
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SAFETY RELATED ( PROCEDURE CHANGES MODE OF OPERATION OR IN AS DESCRIBED IN FSAR: ( ) Yes ( ) No
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PROCEDURE INVOLVES:
) An unreviewed Safety Quest' n ( ) Tech. Specs. ( ) A condition
( not addressed in FSAR ( ) None of these (See back for Safety Evaluation if required). Attach copy of procedure to this form. ' REASON FOR EOUEST iNMR hhCL d\DCt i s in o ok
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PRB RECOMMENDS APPROVAL:(/Yes ( )No PRB Secretary
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l 1 appeevvat PROCEDURt NO HNP-8038 See Title Page E. I. HATCH NUCLEAR PLANT . .,3.u o
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WASTE CLASSIFICATION AND MANIFEST REPORTING ALL TYPE., WASTE A. PURPOSE To detail the steps necessary to classify all types of radioactive waste in accordance with the requirements of 10 CFR 61.55 and to identify manifest reporting requirements in accordance with 10 CFR 20.311. This procedure should be used for wastes that are not adequately addressed by the classification and manifest reporting procedures for resin and DAW shipments (Procedures HNP-8036 and HNP-8037). B. REFERENCES
- 1. 10 CFR 20, Standards for Protection Against Radiation.
- 2. 10.CFR 61, Licensing Requirements for Land Disposal of-Radioactive Material. .
- 3. HNP-8016, Shipment of Radioactive Material.
- 4. HNP-8036, Waste Classification and Manifest Reporting, Resin Shipments.
- 5. HNP-8037 Waste Classification and Manifest Reporting, DAW (Compacted and Non-Compacted Trash).
C. DEFINITIONS 1.- TRU - Alpha emitting transuranic nuclides with half-lives greater than 5 years (in particular - Pu-238, Pu-239, Pu-240, Am-241, Pu-242, Cm-243 and Cm-244).
- 2. - Principal gamma emitter - any radionuclide of plant origin identified by gamma spectroscopy and contributing 3> 1% of the total identifiable gamma activity for the waste under consideration.
D. PRECAUTIONS
- 1. If the shipment includes multiple containers with differing waste composition, separate analysis for each different type waste should be performed for waste classification and manifest reporting. A single analysis may be used for multiple containers of the same type waste provided the container composition (i.e., radiondclide concentration or distribution) is considered the same.
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- 2. Recc dure HNP-8037 should be used for waste that can be
- characterized as DAW - compacted and non-compacted trash.
Procedure HNP CO36 should be used for resin shipments. E. DATA SHEET 1 GUIDANCE
- 1. Determine the waste container (s) that are to be included in the waste shipment.
- 2. For each waste container complete the initial identification material as listed on Data Package 1, Data Sheet 1. Record the container (s) identification number, type container, type waste and the measured dose rate @ 1 meter, if available.
NOTE For some type containers it may not be feasible to measure an unshielded dose rate prior to loading in the shipping cask. A dose rate @ , 1 meter is not required by this procedure unless" " a dose rate to curie content conversion is to be used for determining the total activity of the container. s
- 3. Identify the method to be used for determining radionuclide distribution. Priority should be given to use of a representative sample of the container contents for nuclide quantification. However, if it is not feasible to collect such a sample, nuclide distribution can be based on a smear of the container contents, plant area smears, or other methods as directed by the Lab Foreman (or designated alternate). For irradiated components special directions are provided in Procedural Steps G.1 through G.S.
- 4. Depending on the method to be used for determining record either the concentration radionujlidedistribution, (uCi/cm , as determined by gamma spectroscopy) or ralative activity (uCi, or similar equivalent units) for all principal gamma emitters using the entries under Columns #1 and #2 on Data Sheet 1. The blank entries in Column #1 may be used to record radionuclides that are identified but are not specifically listed on the Data Sheet 1 entries.
- 5. Total the Column #1 and #2 entries to determine Subtotals #1 i I
and #2 for either the concentration or relative activity.
- 6. Using the entries under Column #3, calculate the concentrations or relative activity, as appropriate, for the ;
s correlated radionuclides. Multiply the previously-determined concentration or relative activity of the scaling nu-clide, as listed, by the scaling factor (SW): the pro SITis the correlated radionuclide concentration a relative i l activity. l ! l
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- @W Generic scaling nuclides and conservative scaling factors have been included in the Column #3 and #4 entries. However, it may be more appropriate to select scaling factors based on the type waste. If other than generic SF are to be used, cross through the generic value and insert the appropriate value. H-3 and C-14 are not correlated to any other radionuclides.
The concentrations and relative activities listed under Column #3 for these nuclides are conservative, generic values. The Lab Supervisor (or designated alternate) will determine if other than the generic SF values.or generic H-3 or C-14 values should be used. Technical bases for selection of scaling factors (if other than the generic values) shall be documented on Data Sheet 1 (or by an accomp.anying attachment). . NOTE If the waste consists of irradiated components, use of scaling factors is inappropriate. Special analysis, as performed in Procedural Steps G.1 - G.6, shall be used for determining radionuclide concentrations. Procedural steps, as addressed below, which are inappropriate for classifying activated metals need not be performed. Unless trace quantities of H-3, Tc-99 and I-129 are known to exist in the activated metals (either by radio-chemical analysis or material composition), these nuclides should be reported as not present on the manifest. If available, a radiochemical analysis _. of a representative sample of the activated metals shall be used for determining radionuclide composition and shall be given priority over Procedural Steps G.1 - i G.6. l
- 7. Similarily for Column #4, calculate the correlated concentration .or relative activity of TRU, Pu-241 and Cm-242, as indicated by multiplying the measured Cs-137 concentration by the designated scaling Factor (SF).
- 8. Calculate Subtotal #3 by adding the Column #3 entries, Subtotal #4 by adding the Column #4 entries.
- 9. Determine the total concentration or total relative activity
( (GRAND TOTAL) by summing Subtotals #1, #2, #3 and #4. Circle the appropriate units (uCi/cm 3 or Re.lative. g i y .
I 1 PROGOupt NO ! HNP-8038 See Title Page E. l. HATCH NUCLEAR PLANT *csc~ w 0 om . See Title Page GeorgiaPower 4 of 1S
- 10. Por each nuclide as identified or correlated above,
- determine its fractional abundance by dividing its concentration or relative activity by the GRAND TOTAL -
(either concentration or relative activity, respectively). The quotient is the fractional abundance for the nuclide.
- 11. The Total Activity for each waste container shall be calculated by either Method #1.1 or Method #1.2 as delineated on Data Sheet 1 and as described below. Method
#1.1 should be used for single or multiple containers with the radioactive material content based on concentration.
Method #1.2 should be used for single or multiple containers with the radioactive material content based on a dose rate to millicurie content conversion.
- a. Method #1.1 For each container enter its identification, the GRAND TOTAL (concentration, as determined above), and the ,
container volume (or volume of waste, as appropriat'e) (ft3). Perferm the multiplication as listed to determine the Total Container Activity (mci). Sum the Total Container Activity for all containers to
' determine the TOTAL MILLICURIES for the waste shipment.
- b. Method #1.2 Enter each container's identification. Based on the measured dose rate @ 1 meter, determine the container activity for the principal gamma emitters using Procedural Steps H.1 - H.6 (or computerized dose conversion code). Determine the gamma fractional
- j. abundance by adding the Subtotals #1 and #2 for fractional abundance. Divide the total Gamma Activity
- by the Fractional Abundance; the quotient is the Total Container Activity. Sum all containers to determine the TOTAL MILLICURIES.
- 12. Calculate the TOTAL MILLICURIES of H-3, C-14, Tc-99 and I-129 for all containers as indicated on Data Sheet 1 by multiplying the nuclide Fractional Abundance by the TOTAL MILLICURIES.
~
l 13. .If the dose rate @ 1 meter does not exceed ^100 mR/hr for a 55-gal. drum container or 500 mR/hr for a 4X4X6 box (or i similar dimension box), the waste is catagorically CLASS A. ' l Otherwise, Data Sheet 2 should be used.to determine WASTE L CLASS. N i l
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- 14. Mr t e dose rate is used to determine WASTE CLASS, enter the
- WASTE CLASS as A for each applicable container on the initial identification material, Data Sheet 1. Otherwise, proceed to Procedure Section F, DATA SHEET 2_GUIGANCE.
- 15. Provide completed Data Sheet 1 (and Data Sheet 2, if applicable) to the Lab Foreman (or designated alternate).
- 16. The Lab Foreman (or designated alternate) will review the calculations and waste class determination of Data Sheets 1 and 2. If satisfactory, the Lab Foreman (or designated alternate) will sign and date the data sheets.
- 17. The Lab Foreman (or designated alternate) shall complete Data Package 1, Data Sheet 3, GA/GC Check List. A "N/A" entry shall be recorded for any item on Data Sheet 3 that is not applicable to the type waste being evaluated. Any designated "No" response shall be explained on the data' sheet (or by an accompanying attachment). ,
- 18. The completed data sheet (s) shall be provided to the Lab Supervisor (or designated alternate) for review. The Lab Supervisor will sign and date Data Sheet 3, GA/QC Check List.
- 19. All completed data sheets shall be included in the station records for the waste shipment.
F. DATA SHEET 2 GUIDANCE
- 1. If Data Package 1, Data Sheet 2 is to be used for determining WASTE CLASS, transfer the radionuclide concentrations from Data Sheet i for each radionuclide or radionuclide grouping to appropriate entries on Data Sheet
- 2. If concentrations have not been identified on Data Sheet 1, calculate the concentration for each nuclide. Divide the Total Container Activity (mci) by the container volume (ft3);
multiply by the nuclide fractional abundange; and multiply by 0.035 to convert from mci /ft3 to uCi/ W . It will be necessary to evaluate each container separately (i.e., a separate Data Sheet 2 for each container).
- 2. The concentrations (and corresponding limits) for all nuclides are expressed as uCi/an3 , except for TRU, Pu-241 and Cm-242 for which the units are nCi/g. Therefore, the l concentrations for TRU, Pu-241 and Cm-242 shall be converted l f rom uCi/cm3 to nCi/g prior to entry on Data Sheet 2 by dividing by the. density of the waste (g/cm9 ) and multiplying by 103 (nCi per uCi).
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- 3. Prrform the required calculations to determine waste class.
After dividing each radionuclide concentration by the 10 CFR 61 limit (as included on Data Sheet 2), determine the " sum of fractions" for each column.
- 4. Waste class is determined per the guidance included on Data Sheet 2.
- 5. Enter the WASTE CLASS; sign and date Data Sheet 2.
- 6. Return to Procedural Step E.15.
G. IRRADIATED COMPONENTS GUIDANCE NOTE - If the material to be disposed of consists of irradiated materials, it is necessary to account for.the presence of C-14, Ni-59, Ni-63 and Nb-94, *
- within the activated metal. This analysis is required only for metals that have been exposed to a neutron flux of'>1d7 neutrons / anl -sec (i.e.,
any materials located outside the sacrificial shield need not be evaluated for activated metals).
- 1. For the metals under evaluation, determine the chemical 1 composition and density (example: stainless steel #304 -
0.08% carbon, 0.1% cobalt, 10% nickel, 0.016% niobium at a density of 8 g/an3).
- 2. - Determine the averge neutron flux in the area of the core where the material was located.
- 3. Determine the total time of exposure. For conservation,
- periods of shutdown may be excluded. The net full power days of exposure in conjunction with the neutron flux at full power may be used.
- 4. Based on the above information and the activation data in Table 1, calculate the concentration of C-14, Ni-59, Ni-63 and Nb-94 using the equation:
A=2.7X10-U*f*CI*N*(1 - (exp -)( t)) l where: A = concentration of the radionuclide in the activated metal (uCi/cm 8 ) b = average (or full power)
\_
thermal( neutron to which the metal was exposed flup) an ~1 - sec
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' (7 = thermal neutron cross section of the target nuclide (cm ., from Table 1) 2 l N, = target nuclide density (atoms /cm@) ;
N = (density of metal) * (target nuclide abundance) l (g/ mole)
- 6.025E + 23 (atoms / mole) .
)(=radionuclide(A) decay constant (sec, from Table 1) 5 t = total time of exposure (sec) 2.7 X 10-5= conversion f actor (uCi per disintegration per sec)
- 5. As directed by the Lab Foreman (or designated alternative) determine the concentration of Co-60 in the activated metal.
based on either a calculation (correlating.Co-60 to a measured dose rate for the metal) or an activation , calculation (using the equation in step F.4 and data in
- Table 1).
M j It can be conservatively assumed that Co-60 < accounts for all remaining activity (i.e., l all activity attributing to the dose rate from . 1' the metal). Other radionuclides may be present due to neutron activation analysis or external contamination; however, because of.either pro-
! duction rates or radioactive decay, the overall contribution of these nuclides (in both abundance and radiation dose contribution) relative to Co-60 will be minor.
- 6. Return to Procedural Step E.4 for completion of waste classification and manifest reporting using the radionuclide concentrations as determined above.
H.- DETERMINATION OF WASTE CONTAIfER MILLICURIE CONTENT BASED E PEASURED DOSE RATE
- 1. Identify.the waste. container (s) .to be evaluated, container weight or waste density, and the measured dose rate at 1 meter (from exterior' surface of container).
M 4 If multiple dose rate measures are recorded, average should beall usedvalues to determine for calculating the value'th6 g I.III the cankainer millicurie content.
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- 2. Fdentify the average gamma energy of the radionuclide
- distribution for the waste. If unavailable, a conservative average energy of 0.7 Mev may be used. (Considering the normal radibnuclide distribution at nuclear power rcactors, use of 0.7 Mev average gamma energy will overestimate actual container content.)
- 3. Determine the appropriate set of curves for relating dose rate to millicurie content -- Figure 1 for 55-gal. drum or Figure a for a 4X4X6 box.
- 4. Based on the average gamma energy, determine the specific curve from either Figure 1 or 2, as appropriate. For conservation, if the average gamma energy is between any of the designated energies, use the lower energy curve for determining the value of C. If the average gamma energy exceeds the maximum designated gamma energy curve, use the maximum energy curve.
- 5. The total container gamma activity of the container is calculated by the following equation:
G = DR
- C s
i where: G = total radioactive material content for gamma emitting radionuclides for the container (4X4X6 box or 55 gal. drum) (mC1) DR = dose rate measured at 1 meter from container exterior surface-(mR/hr) C = conversion factor from Figure i for a 55 gal. drum container or from Figure
- 2 for a 4X4X6 box container (or similar capacity container) (mci per mR/hr 9 1 meter)
I 6. If the density (or weight) of the container exceeds the l bounds of the curves in either Figure 1 or 2, .the value of C ! may be approximated by taking the ratio of the actual container density (or weight) to the maximum value of the , curve. This ratio should be multiplied by the maximum.value j of the curve to determine the value of C. l \ I t J NL SET . l
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. 10 CFR 61 NUCLIDES NEUTRON ACTIVATED METALS
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TARGET NUCLIDE g/ mole
~
Nuclide Decay Nuclide Natural Thermal Neutron Constant (1) ~3hndance Cross Section# C-14 3.8E-12 sec
-I C-13 1.li% 13 0.9 i O.2 mb Ni-59' 2.9E-13 sec~ Ni-58 67.9% 58 4.4 i O.4 b Ni -63 2.2E-10 sec-I Ni-62 3.66% 62 15 1 2 b Nb-94 1.1E-12 se c-I Nb-93 100% 93 O.15 i O.1 b (Nb-94m)
, 1.15 i O.05 b (Nb-94)
- (1.3 b, total) ,
, , f Co-60 4.2E-09 sec-I Co-59 100% 59 19.9 i O.9 b (Co-60m)
- 17 1 2 b (Co-60)
(37 b, total)
- 1) Cross section units are expressed as barns (b) or millibarns (mb).
A barn equals 10-M cm1 4
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FIGURE 2 Dose Rate to Millicurie Content Conversion 4X4X6 LSA- Box Coatsiner . _ . . _ _ . . . . . _ . _ . . _ . :.. - . . _ _ . . y Densigy _I T -!.~-- ~~
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A LW MMJCtDV E.1. HATCH NUCLEAR PLANT " -s sa See Title Page " " "
- vet O See Title Page 12 f 18 l
PROCEDtJRE DATA PACHACE I
~
DOCUPENT NO: HPF-E, ' 11-1 SERIAL NO: ROO-PFL NO: RTYPE: C15.14 XREF: TOTAL SHEETS: 7 . i FREQUENCY: COPPLETED BY: DATE COMPLETED: I HAVE REVIEWED THIS DATA PACHACE FOR COPPLETENESS AND AGAINST ACCEPTANCE CRITERIA IN ACCCRDANCE WITH W -830. ACCEPTABLE tJNACCEPTABLE REVIEWED DY: DATE REVIEWED: REMARKS: Page 1 of 7
,HPF-SO38 ROO ' ~
FIGURE 3 Page 1 of 7
%(g
apesaow an, 8540GEOudt NO
" -8038 E. l. HATCH NUCLEAR PLANT See Title Page at m ~ w
~
~
See Title Page Geo iaPower A 13 of 18 b
. gATA PAcxAcE 1 OATA 9EET 1 WASTE CLASSIFICATIG4 e 4 - .
4
- 2" O C1 3 :
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6 u~uu s e s d Page 2 of 7 HNP-8038 000 l \.. l FIGURE 3 j Sg i Page 2 of 7 t I l l l l l
i l
%W AL PACT.EOvaE NO
- E.1. HATCH NUCLEAR PLANT HNP-8038 see Title e g. av.sm .
OAYE l See Title Page GeorgiaPower d ~~ 14 of 18 I
%e DATA PACKAGE 1 (cont.)
DATA SHEET 1 (cont.> o CALCULATIGe CF CORRELATE RA010baJCLIDES --..........................
.........................._- ...Colm # 3---- = - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
Cope Relative reactional (uci/ M.) or gg31y1Lt eg3ggggngg, SE-03 H-3 e SE-04 C-14 *
.N-63 = _
e 4E-02 = LCo-603 - (F) *
* *E-Og .
Sr-30 * (F) LCs-137) Tc-19 e
- X-04 *
(Co-137) (F) 1-129 e
- 1E-05 m (Co-137) (F) e Suttotal #3
== = -...........
......C o lumn #4-- --
Conc Relatsve Fractional ( uc t / ed.t or Activity stusaggggg, e . * %-03
- TRO (Cs-137) (F)
Pu-241 =
- X-02 m (Cs-137) (F)
- Cm-242 *
- 2E-04 e ECs-137) (F)
=
Subtotal e4 Page 3 of 7
;- WP-8038 ROO FIGURE 3 Page 3 of 7 4 L gy l
aW5euvat -w E. I. HATCH NUCLEAR PLANT HNP-8038 See Title Page ainse. w cara o See Title Page 15 of 18 b DATA PACKAGE 1 (Cont.t OATA 9EET 1 (Cont.) (ETERMIPGATICM CF TOTAL. ACTIVITY - - - - - - - - - - - - - - - - - - - - - - - -
=- .-.---..-----.----
uC6/cm 3 t t -
- or t
CRAPO TOTM. * (Suetotat map (Suetotal e33 iCustotat *** Ret. astavat, (Suetotal ets e M141 CRafe TOTag. *
- Converoson
- Total Container Container t uc t / ens, volume n!gete (*to'
- 31. _Fgggg., Adugg.1L=Gn.
ljggni;sgugg
*
- 28.3 *
*
- 28.3 * .
*
- 29.3 *
*
- 28.3 *
*
- 28.3 *
*
- 28.3 *
*
- 28.3 =
*
- 28.3
- TOTAL MILLICt.fttr3 PdTMI) e 1.2 ,
Total Y Actavsty - Y Feae. Abun.ance
- Totat Container Containee (Suetatal et si 27 A.gggy 'Ma p Idents f acSMSS
. e TOTAs. n!LLICtst!C3 (H-3 Frec. Abun, p
- tTOTM. MILLICURfC3) e mCs TUTAs. 6+ 3 =
- tTOTAL MILLICURfCSI = <t 7074. C-t* * (C.14 Frac. Aeun.)
* (TOTAL. "" LICUR!rSt = mC4 Totas. Tc. M e (Tc-99 Frac. Atun.3 707 % I tM e t1-129 Frac. Atun.p
- tTOTAL MILLicisttr31 = mC4 teASTE CLASS 1FICATICH
==-................... .............
.o .e t e- ne. ., .o.e cate ., te, SmCJes .
o.t. chest 2 othee. ,pecter Criteria for Waste Classification Gased on Dose
'de s t e is <:ategorically CLASG A if dose rates measured at 1 mater to not etCowd 100 mR/hr for a 55-gal. drtan :en ta.r.e r o r '*C0 sv1/ ',r isr a
*e446 Contatner (0-35 bot), or similar : pacity Container.
i l l Page 4 of 7'
. Hre-8033 R00 FIGURE 3 %
Page 4 of 7 J I IT l l
e app 40 vat enOCEDupe NO E. l. HATCH NUCLEAR PLANT WP-8038 See Title Page aem m ~0 a*re o See Title Page 16 of 18 b DATA PACMAGE 1 (cont.)
. QATA 94EET 2 WASTE CLASSIFICATION WGtH9EET
/
Mar & F1tacTftze .10 CPW Et TasLK 1 LINffs **
. .e Nuctase Wats Ente 1e Class A Class c
.f...r. .
e ......~. 8.0 e C-te ucs/cm . 0.8 = uCs/ce' = 8.0 e = 80.0 C
- t t"I uCa#CmI
- 22.0 e . 220.0 e Nt.s9' No-94 uCa/cm 3 0 02 e -
0.J e Tc-99 uCa/cm3 .- 03 e - 3. 0 e 1-123 uCa/cm3 0 00e e . 0.08 e TIru (TL/2 >s ret aca/g .- 10 0 = - 100.0
- Pu-det aCa/g . 390 0
- 3s00. * -
Co-ded acarg 2000. = - Je t 04 e a >l 7 > enaccepteele s e of Feactaens I" l= ' fee turnet
......-...... .......... S.se & memcTftse - to CFut SWR.. 2.
.. LIMITS...
Unste e4 Class C Nuclade Entera Class A Class S .......... . ......
- 700.0 N/A Tatat uCs/cm 3 e N/A tT3/84 9 res 3 N/A N/A M-3 uCa/cm - 40.0 m 700.0
- N/A N/A Co-60 uCs/cm3 . e 700. e N1-63 8 uC4/cm3 . 3.s a 70.0
* !s.O e a 700.0 e - TOOO. e N1 63 uC6/Cm3
- 7000.
- se-90 uCs/cm3 . 0.04 e - 150.0 e 1.0 e - 44.0 = - 4600. e Cs-127 ucs/ col -
swa et reactmens l= 7 f ) le l 8
.m e.. e
......... ........ . . . . . . roe nues.a.. . . . . .
The waste classification as determined by the highest class for which the ' sum of fractions
- does not exceed 1.
If the " sum of f ractions* f or Table 1. Class A 41. waste class 5 determined by highest column of Table 2 with " sum of fraction"( 1. If
- sum of fraction
- of Table 1, Class A ts > 1 but Class C 41.
waste is Class C, provsded Table 2, Class C
- sum of f ractton"< 1.
If " sum of f ractions* of Table 1, Class C> 1 or if " sum of f raction* of Table 2, Class C >1, waste not suitable for burtal. i
' Units are uCi/cmd for all nuclides ex cept TRU, Pu-241 and Cm-242 for which the units are nCi/g.
1 In activated metals only. l WASTC CLACS: Technician: Date: l Lab Foreman: Cate: Page 5 of 7
. ,lFN5-8038 ROO FIGURE 3 ; %( ggy Page 5 of 7
APPRQvAt PMCLEOudt No HNP-8038 see Title page E. I. HATCH NUCLEAR PLANT +.se u 1 See Title Page GeorgiaPower A P-17 of 18
%e DATA PACHACE i (cont.)
QATA SPEET 3 QA/QC CFECM L13I WASTE Ct.ASSIFICATION APO MANIFEST REPCNITING Shipment #: L4111 ElA11 YE3 W
- 1. Has waste been properly classified? Data Sheet 1 (and Data Sheet 2, if applicable) completed?
- 2. Has waste container been labeled CLASS A. CLASS B, or CLASS C?
h!!!11.313 hili 1X_She r a e t e e i s t i s1 YES t!Q
- 1. Has proper waste container been selected (Class A *
- carbon steel, Class 8 or C- HIC)? .
- 2. If HIC used, has User Checklist been completed?
- 3. Verify proper dewatering of resins ((1Z water).
- 4. If any liquids have been included, has sufficient absorbant been added to absorb twice the volume of the liquid? Absorbed liquids are not acceptable at Barnwell.
- 5. For waste contatning oils, does the designated burial site allow for receipt of waste containing os1? Waste contatning oils cannot be shipped to Barnwell. For Class 8 or C waste in a HIC, osis cannot exceed 0.5%.
- 6. Have void spaces been reduced to extent practical?
- 7. For shipments to Barnwell. the site criteria for
- required use of HTC is 1 uC1/cm3 long lived activity (i.e., Subtotals #2, #3, and #4, Data Sheet 1).
Page G of 7
, ,',HNP-3033 ROO FIGURE 3 Page 6 of 7 .1 % Al SET
PHOCEDURL PeO HNP-8038 E. l. HATCH NUCLEAR PLANT , , , , _ See Title Page e Title Page GeorgiaPower d - 1, 1, b DATA PACKAGE 1 (cont.1 DATA SFEET 3 ( conM WASTE CLASSIFICATICN AFC MANIFEST REPORTING Manifest Reoorti"2 Ma !!Q
- 1. Have the total millicurie quantities of H-3. C-14, Tc-99 and I-129 been determined and included on Manifest?
- 2. Have a,ll principal gamma emitters and gli correlated radtonucitdes been included on manifest? Barnwell site criteria require reporting correlated abundances of TRU, Pu-241 and Cm-242.
- 3. Verify accounting for at least 99% of total activity by individual radionuclide identification. ,
- 4. Verify identification of Waste Class.
- 5. Verify correct physical description of waste.
- 6. Verify total volume of waste (same as used for determining millicurie content; if different explain below).
- 7. Verify correct chemical form.
- 3. Verify exclusion of chelating agents (if> O.1%,
chelating agents must be tdentified). Date: Lab Foreman:_ Lab Supervisor: Date: Page 7 of 7 HNP-3033 900 FIGURE 3 #A%AtIT Page 7 of 7
r t GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PROCEDURE _Op3 ration of the Bartlett Nuclear Mixing _ Unit
-- PROCEDURE TITLE HNP-8044 PROCEDURE NUMBER Lab RESPONSI LE SECTION SAFETY RELATED ( X ) NON " M RELTTED ( )
APPROVED APPROVED REV. DESCRIPTION DEPT. GENERAL DATE MANAGER ER O . _ New _ _ _Procedure
.hQg q,,' _ _ _ _ _ _ _ _ ..j J_;a<f_.
. v ._-__-___
a % t m _3-
g3 %t.
'e y bY ter, PRTen stE REVIEW REGLEST SEET k CF / '
FOR PEW PROCEDURES
/[M h I' -
PROCEDt.RE NO. M- [~ / REN t:sicu BY sDEPARTMENT MANAGER APPROVAL * [~ Date: Name: - Date: g[$ignature: j l' t l :b % l2 -/V t' 5 O l lEllfb3
/4:sy -
/
NON-SAFETY RELATED ( ) SAFETY RELATED ( PROCEDURE CHANGES MODE OF OPERATION OR INTENT..AS DESCRIBED IN FSAR: ( ) Yes ( -f No PROCEDURE INVOLVES: ( ) A condition
) An unreviewed Safety Question- ( ) Tech. Specs.
( not addressed in FSAR ( v r'None of these (See bacl< for Safety Evaluation if required). Attach copy of procedure to this form. 1
/
a ( REASON FOR REQUEST !'< ' c
. /c f
/, . > &S ,
,? .
2s r
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PRB RECOMMENDS APPROVAL:( )Yes ( )No m b _ _ _ _ PRS Secretary 33-24o . PRB Number Oate
t l r
. SAFETY EVALUATION j s
U __ d
-- M This ornendure anae nnt ennetitieto an tinraviawad ca#ary niiactinn ae avnlained )i below. -
- 1. TAs ornhability of neciteranco and the -nneonnancoe nf an accident a
ne malfunctinn of antiinmant imnnr+=nt tn e n f a tv a re nnt incroacad above those analy7pd in the FRAR due to tnic nrnendiere hoe =trea the orncedggg dont nnt change the nitrnnep ne oprformanen n# the system. L.,The nnstibility nf an accident nr malf).uletinn nf a diffarant tyna _than analy7ad in the NAR dnu nne caeul e frnm thie nrnendura hacainen the eyetam coennnde and ie nnarated ac hafnen the n rnendeira 1 ,,Iha margia nf enfaty ac daf4nad in +ha Tarhn4rm1 Cnar4#4r3+4nne a ie MnI radif f ad Af f a IM *b4e nrnPAMitra ar S t t e n tha n t*M e nNi n es Mnar si M + changa any limi+ad enfatya yetam ea++4nne wh 4 rh unf t1 A 211mu s safety limit en ha avrandad nr M 1nw 2 14mit4nn ennd4*4nn far __ nna ra ti nn e en ha avenadad me e+2 tad in Technieml <nar4ffgat4nne
= .. _
i l _. . _ _ _ - -- - l : l \ . l a. .=_
'b &
1 .
6 - PROCEQu a t NO aPPRCvat 1
" -8 44 4 See Title Page E. I. HATCH NUCLEAR PLANT % ,,su,, %
e Title Page GeorgiaPower d -- 2 fa 6 E. OPERATf0N
- 1. This syste$ is designed to be used with a 55 gallon D.O.T.
; specificatio'n 17 H drums.
- 2. Hydraulic system is incorporated for raising and lowering the mixing blade and is operated from the control panel.
- 3. Switch on power at the control panel (indication light ! should be on).
- 4. Engage electric motor switch (indication lighc should be on).
- 5. To raise mixing blade, engage "up" switch.
- 6. To lower mixing blade, engage "down" switch.
f
- 7. To turn mixing blade, engage " forward" switch
~
- a. Blade should turn freely.
- b. Psi gauge should read approx. 350 psi and flow control meter set at 3.
EE Unit is not electrically designed to mix in
> the reverse mode.
- 8. Oil line on sight glass should be in line with black i indicator line or within 2 inches for operation.
- 9. During operation, the speed of the mixing blade may be increased by unlocking the flow control meter knob and rod
- moved up scale. The vortex in the liquid waste should be maintained as long as possible to give a good homogeneous i mixture.
I f I j "NWRL gy 1
i GEORGIA POWER COMPANY i HATCH NUCLEAR PLANT . PROCEDURE Waste Classification and Manifest Reporting DAW (Comgacted and Non-Compacted Trash
, PROCEDURE TITLE .
HNP-8037 PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( ) APPROVED APPROVED REV. DESCRIPTION DEPT. GENERAL DATE MANAGER ER O New Procedure ._h______________gg __y,
- _ _ _ _ _ ..s.___________________.. _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ..________
- _ _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .r________________. . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .________
i i
. _ _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . .______:_________a________
inassa i se t HNP 3 1 I I I r 9 I (
, i
~ N' '
& k%%
~
l
% 14 SEET & CF o- PROCEIMIE REVIEks NE(R.EET
- FGt PEW PROCEIMIES PROCEDtJtE NO. i+P- %3"7 RErm=~imu BY utrART& MANAGER APPROVAL I' Name: Date: Signature: Date:
b .
~
Uh -E -M ,
- /
SAFETY RELATED ( ) NCN-SAFETY RELATED ( ) _ , AS DESCRIBED IN FSAR: PROCEDt.RE CHANGES MODE ( ) OF YesOPERATION OR Iy( ) No PROCEDURE INVOLVES: ( ) An unreviewed Safety Questp' n ( ) Tech. Specs. ( ) A condition not addressed in FSAR ( 4 None of these (See back for Safety Evaluation if required). Attach copy of procedure to this form. REASON FOR REGtKST si\ % ss M tt o iRO&1 1 h O (> A
~
i DM iA t \6 BC: R C).2ll 01w l& C.E b .
>A a J.e.e 1 to.,. a h malay fanws% ,saqgp
_ Yff$[~ PRB RECOMMENDS APPROVAL:( es ( )No PRB Secretary I "I /.2 ,A / E3 PRB Number . Date 1+P-9 massa i se t 4.
1 b
'a aJ l f
~
f,$4 !4 - T . .- .
- L^NTY EVas t ETICN ,_
I.
=
t w g . av nl a i ned I r
""oceinn me -
*"f**V j nnt ennetit"to an "nrai " *d -
This nrocedura dnat _ t belnw. of an accident __ 1
"*The nrnhahirity nf necurronce and the ennconnancoe l
**f**? ""* "^* I"""a"'ad -
imnnetant in ne mal functinn nf anifinment ___ due tn thic nrneadnea haeanea ahova thnte _ analyred in the MAD - nnt changa tha nurnata nr narfnmanca nf '%m - the nrnendure anat RVttOM- _ M OM - ne malfunctinn af a diffarant tyna
?- ,Jhp nnetibility mf an accident nnt vaen1* fenm thie nenrad""aShar$"** Y 6k'D than analvtad in the MAD MS Anne A0+ ex iiLN&@N hy
- - .a. , .
~~~
", b. is frCC.ecAuTE ,
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- MAP Mf. h h & MMO A flF&
$fO O f e nPn[O ll PO BOO Sit P O
( nb IO IIeO _ .rh_a n n. o a n.u 14m4 tad enf0+u . ev.e+Om e O *
- 4 an. e 'h4ch "a"1d $110"
- O O (j @ Y @ O O OYfOO O .
nnowatinne tn ha avenadad me etated 4n TOehnics1 CnOe4 f 4
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^""o " % -8037 See Title Page E. l. HATCH NUCLEAR PLANT ou,se o j O
ee Title Page GeorgiaPower d ~ ~ 1 of 1A WASTE CLASSIFICATION AND MANIFEST REPORTING
< DAW (COMPACTED AND NON-COMPAC it-u TRASH)
A. PURPOSE To detail the steps necessary to classify radioactive waste (DAW shipment - compacted and non-compacted trash) in accordance with the requirements of 10 CFR 61.55 and to identify manifest reporting requirements in accordance with 10 CFR 20.311. B. REFERENCES
- 1. 10 CFR 20, Standards for Protection Against Radiation
- 2. 10 CFR 61, Licensing Requirements for Land Disposal of Radioactive Waste.
- 3. HNP-8016, Shipment of Radioactive Material C. DEFINITIONS
- 1. TRU - Alpha emitting transuranics with half-lives greater than 5 years (in particular - Pu-238, Pu-239, Pu-240, Pu-242, Am-241, Cm-243 and Cm-244).
- 2. Principal gamma emitter - Any radionuclide of plant origin identifiable by gamma spectroscopy and contributing >1% of the total identifiable gamma activity for the waste under consideration.
D. PRECAUTIONS If the shipment includes multiple containers with differing waste composition, separate analysis for each different type waste should be performed. A single analysis may be used for multiple containers of the same type waste provided the container composition (i.e., radionuclide distribution) is considered the same. E. DATA SHEET 1 GUIDANCE
- 1. Determine the DAW containers that are to be included in the waste shipment.
- 2. For each container complete the initial identification information on Data Package 1, Data Sheet 1. The same data l
sheet may be used to record multiple containers provided
~
each container represents a common type waste and storage time interval. Enter the container (s) identification, container weight (lbs), dose rate (s) @ 1 meter, storage time (s), type waste and type container. gens t set (
i e " " WP-8037 See Title Page E. l. HATCH NUCLEAR PLANT _ ee Title Page GeorgiaPower d 2 of 14
- 3. If the maximum dose rate @ 1 meter is <C100 mR/hr for a
< 55-gal. drum' container or <( 500 mR/hr f or a 4X4X6 box container (or similar capacity container), the waste is categorically Class A. If the dose rate exceeds the above, contact the Lab Foreman (or designated alternative). It may be necessary to open the container; identify and remove the item (s) contributing to the unacceptably high dose rate.
NOTE DAW shipments cannot ekceed the Class A limits. Exceeding these limits requires the packaging of the items in a "High Integrity Container."
- 4. Determine the appropriate radionuclide distribution to be used for calculating the individual radionuclide fractional abundance and curie inventory of the container (s). The Generic Distribution (appropriately decay corrected) should be used for all DAW unless the waste is known to be ,
substantially different in radionuclide composition (i . e. , a change of more than a factor of 10 in relative activities or fractional abundances of the principal gamma emitters).
- 5. If other than the Generic Distribution is required, take a special sample (i.e., smear of the container contents of special plant area smears) and have analyzed by gamma spectroscopy to determine relative activity of the principal gamma emitters. Use Data Package 1, Data Sheet 2 for determining fractional abundance. Refer to Data Sheet 2 Guidance for details (Procedural Steps F.1 - F.9).
- 6. If using a Special Distribution (as determined by Procedural Steps F.1 - F.11), calculate the weighted gamma energy for each nuclide by multiplying the fractional abundance of the nuclide by its average gamma energy. Sum all weighted gamma energies to determine the average gamma energy for the distribution. This average gamma energy is used to calculate the container millicurie inventory (based on the I curves in Figure 1 or Figure 2, if used for determination).
l
- 7. Determine the radioactive material content of the container (s), in millicuries, for the principal gamma emitters by the following steps (or a computerized dose conversion code). Enter the results on Data Sheet 1.
- a. For each waste container (s) to be evaluated, identify the container weight or waste density, and the measured dose rate at 1 meter (from exterior surface of container).- As recorded on Data Sheet 1.
maun t set l l
PROCEDuRt NO wunovg HNP-8037 See Title Page E. I. HATCH NUCLEAR PLANT aevew w
~
~~
See Title Page Geo biaPower A 3 of 14 NOTE If multiple dose rate measures have been recorded, average all values to determine the value that should be used for calculating the container millicurie content.
- b. Identify the average gamma energy of the radionuclide distribution for the waste (from Data Sheet 1). If unavailable, a conservative average energy of 0.8 Mev may be used. (Considering the normal radionuclide distribution at nuclear power reactors, use of a O.8 Mev_ average gamma energy will overestimate actual container content.)
- c. Determine the appropriate set of curves for relating dose rate to millicurie content -- Figure 1 for 55-gal.
drum or Figure 2 for a 4X4X6 box.
- d. Based on the average gamma energy, determine the specific curve from either Figure 1 or 2, as appropriate. For conservation, if the average gamma energy is between any of the designated energies, use the lower energy curve for determining the value of C.
If the average gamma energy exceeds the maximum designated gamma energy curve, use the maximum energy curve.
- e. The total container gamma activity of the container is calculated by the following equation:
G = DR
- C where: G = total radioactive material content for gamma emitting radionuclides for the container (4X4X6 box or 55-gal.
drum) (mci) l DR = dose rate measured at 1 meter from I container exterior sur' face (mR/hr) I C = conversion factor from Figure 1 for a 55-gal. drum container or from Figure 2 for a 4X4X6 box container (or similar capacity container) (mci per mR/hr @ l meter) l maun t set
'""* " % -8037 See Title Page E. I. HATCH NUCLEAR PLANT _
oare , See Title Page GeorgiaPower " " 4 of 14 i
- f. If the density (or weight) of the container exceeds the
, bounds of the curves in either Figure 1 o r 2, the value of C may be approximated by taking the ratio of the !
actual container density (or weight) to the maximum value of the curve. This ratio should be multiplied by
. the maximum value of the curve to determine the value of C.
- 8. Calculate the Total Activity (mci) for each container using the entries on the data sheet to correct for the presence of the non-gamma emitting radionuclides. The Total Activity is determined by dividing the Total Y Activity by the gamma fractional abundance ( hi - Fraction). The quotient is the Total Activity (mci) for the container.
- 9. Sum the Total Activities for all containers to determine the TOTAL MILLICURIES, which is the total millicuries of all waste containers being evaluated.
- 10. Calculate the total H-3, C-14, Tc-99 and I-129 inventory (mci) for the shipment using the appropriate entries on Data Sheet 1 by multiplying nuclide fractional abundance by TOTAL MILLICURIES (mci). The generic fractional abundances for H-3 and C-14 have been included as default values; the Tc-99 and I-129 fractional abundances should be taken from the radionuclide distribution - Generic or Special.
- 11. Record Waste Class and identify bases for determination under the Waste Classification and Manifest Reporting, Data Sheet 1. Criteria for classification are provided on the data sheet.
- 12. If Waste Class exceeds Class A (i.e., Class 8 or C), contact Lab Foreman (or designated alternative). Class B or C waste requires packaging and shipment in a "High Integrity Container" (HIC).
l
- 13. Sign and date the completed Data Sheet 1. Provide completed Data Sheet 1 (and Data Sheet 2, if applicable) to the Lab Foreman (or designated alternate).
- 14. The Lab Foreman (or designated alternate) will review the calculations and waste class determination of Data Sheet 1 and Data Sheet 2, if applicable. If satisfactory, the Lab Foreman (or designated alternate) will sign and date the data sheets.
saum i set ,
- "" %-8037 See Title Page E. l. HATCH NUCLEAR PLANT _
o ee Title Page GeorgiaPower 5 oe 14
- 15. The Lab Foreman (or designated alternate) shall complete
< Data Package 1, Data Sheet 3, GA/GC Check List. A "N/A" entry shall be recorded for any item on Data Sheet 3 that is not applicable to the type waste being evaluated. Any designated "No" response shall be explained on the data sheet (or by an accompanying attachment).
- 16. The completed data sheets shall be provided to the Lab Supervisor (or designated alternate) for review. The Lab Supervisor (or designa ted alternate) will sign and date Data Sheet 3, GA/GC Check List.
- 17. All completed Data Sheets 1, 2 and 3 shall be included in the station records for the waste shipment.
F. DATA SHEET 2_ GUIDANCE NOTE Data Package 1, Data Sheet 2 is used to determine the correlated concentration of - the non gamma emitting radionuclides. These procedural steps need only be completed if a Special Distribution (i.e., other than the Generic Distribution) is used to quantify the radionuclide content of the container (s).
- 1. Enter the identification of each container to be addressed by the Special Distribution.
2.- Based on a gamma spectrum analysis of a special sample (e.g., smear of the container contents of special plant area smears) determine the distribution of the principal gamma emitters (relative activity).
- 3. Enter the relative activity of the principal gamma emitters in Columns #1 and #2 on Data Sheet 2. The blank entries in Column #1 may be used to record radionuclides that are identified but not specifically listed.
l 4. Total Columns #1 and #2 to determine Subtotals #1 and #2, respectively. ! 5. Determine the relative activity of the correlated ( radionuclides in Columns #3 and #4 by multiplying the relative activity of the scaling radionuclide by the designated scaling factor (SF). The fractional abundances for H-3 and C-14 should be taken directly from the Generic Distribution unless special analysis have been performed to quantify these nuclides. samutset
-e
~ " W -8037 See Title Page E.1. HATCH NUCLEAR PLANT --
o ee Title Page GeorgiaPower d ~ ~ 6 o# 14 NOTE The generic DAW scaling nuclides and scaling factors (SF) are listed for each correlated radionuclide on Data Sheet 2. If scaling nuclides or scaling factors other than the generic are required to be used due to partic-ulars of the waste, cross through the generic value and insert appropriate value. The Lab Supervisor (or designated alternative) will determine if other than generic scaling nuclides and scaling factor values should be used. Tech-nical bases for selection of scaling factors (if other.than the generic DAW values) shall be documented on Data Sheet 2 (or by an accompanying attachment).
- 6. Determine Subtotal #3 by summing the Column #3 entries, Subtotal #4 by summing the Column #4 entries.
- 7. Sum the Subtotals #1, #2, #3 and #4 to determine the Total Relative Activity.
- 8. To determine the Fractional Abundance for each radionuclide, divide its relative activity by the Total Relative Activity. The quotient is the Fractional Abundance.
- 9. Enter these Fractional Abundances on Data Sheet i under Special Distribution.
- 10. Sum the Fractional Abundances of the gamma emitters on Data Sheet 1. Sum all Fractional Abundances to verify accounting for all activity (i.e., 100% i 1%).
- 11. Sign and date the completed Data Sheet 2. Return to Procedural Step E.6 for completion of the waste classification and shipping manifest reporting.
l mana l set
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See Title Page Georgia power FIGURE 2 Dose Rate to Millicurie Content Conversion AX4X6 LSA Box
=2p r :: a -- -
FAvengi.jrs .rwrt""-r*=[.:r' cent.siner'Densigy __:_. =. . . ;. .; . _ . _ ___; ";. = 2 ._: = = . . . .
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* ^ ' " " W -8037 See Title Page E. I. HATCH NUCLEAR PLANT m,n -
o 7eeritieege GeorgiaPower d ~ ~ s or 14 PROCEDURE DATA PACMAGE DOCUMENT NO: HNP-8037-l
, - SERIAL NO: ROO-
~
ffL NO:
. RTYPE: G15.14 XREF:
TOTAL SHEETS: 6 FREQUENCY: COffLCTED BY: DATE COMPLCTED: I HAVE REVIEWCD THIG DATA PACHAGE FOR COMPLCTENESS AND AGAINCT ACCEPTANCE CRITERIA IN ACCCRDANCE' WITH FSP-830. ACCEPTADLE UNACCEPTABLE REVIEWED DY: DATE REVIEWED: REMARHG: Page 1 of 6 l p. HNP-8037 ROO j FIGURE 3 - Page 1 of 6 l massa i set
I . 1 i W WAL PROGtDuitD -8037 See Title Page E. l. HATCH NUCLEAR PLANT Ntv%Ue req o QAft See Title Page GeorgiaPower ~ ~ 10 og a DATA PA G A_C Q QATA SHEET 1 WASTE CLASSIFICATION - DAW Storage T6me Shepment Not Conta6 nee testeht Dese Rate e I meter (mentns)__ Technacsans__ jiha.I fmR/hrt Oates ljantificati gn 8 05 tes Type Containert 55 gal, drum other, specafr e compacted traen Type saastet non-comp. trash other. specafy generic values enter nuttedes en Radtenucl 6de oestettuttent spectet stant area seeses Data Sheet 2 to , smear of contaaner contents determans frac. abun., other, specafy Y* RActoP4JCL10C OISTRIBUTIOi-.......---. __.
.__ GPECIA4.'
cDER1C 0tSTR1SUT10N' O!STRIBUTICP4 1 - 3 Veers P4JCL10E avc.V 43 Months 3 Months - t vr. frac. eesghted frac. esghted frac. eesghted frac. esenghted abun. _enerar DERcv enecer abun. eneear aggn. enerar (Movt anun. s -04 ---- 5E-04 --~ x.04 .... 4E-04 ---- 4E-04 ~~ g.3 .... JE-04 --- 4E-04 --- C-14 ---- .E-04 ~~ 0.044 0.04 0.03 0.02 mn-54 0.04 0.05 0.04 ~~ ~ ~ ~ *~* Ca-58 0.18 0.01 0.002 ---- 0.53 1.32 0.2e 0.70 0.36 0.00 *"- co-60 2.50 0.007 --- 0.012 --- ng.63 ---- 0.005 ~~ 0.25 0.20 0.11 In-65 0.57 0.53 0.30 0.44 0.006 --
---- 0.o03 --- 0.003 ----
Sr-10 **~ **~- Zr-95 0.73 0.01 0.007 ~~-
- - ~ SE-05 --
--~
Tc-91 --- 2E-05 --~ X 05 -~~
---- 6E-04 --~ 0.001 1-123 --- SE-04 0.00 0.053 0.08 ce-t34 1.55 0.04 0.06 0.05 0.16 0.00 0.57 0.07 0.04 0.00 0.05 ---
co-137 0.001 ---- 0.001 ---- TRu * ---- 7E-04 - -- 0.004 ----
--~
0.002 ---- - Pu-241 --- 0.002 --~
--- SE-06 - - * ~
~~
1E-06 ~~ SC-06 cm-242 ~~ canom FRAC. 0.3e4 0.373 tyr TOTAs. 0.990 1.63 (Mewl 1.15 1 32 bEtGHTEDV DERcY 4The fractional abundance for the Generic Distributton as based on a nominal once every two years special radiochemical analysis Of selected plant smears for all radionuclides as needed for 10 CFR 61 waste classification. 1For Special Dietribution, use the Scaling Factors of Data Sheet 3 to determine the fractional abundance of the non-gamma emitting radionuclides. For H-3 and C-14 generic OAW fractional abundances have been included. Due to the insigntfacant contribution Of these radionuclides to waste classification, having to perform special evaluations or corrections are not required. These generte fractional abundances have been factored into the conservative waste classificattan criterta for CAW. Page 3 of 6
- p. HNP-8037 ROO FIGURE _3 Page 2 of 6 massa i set
- 8 37 See Title Page E. l. HATCH NUCLEAR PLANT "" "
o om See Title Page GeorgiaPower uaa DATA PACXACE 1 (cont 1 DATA SHEET 1 (cont.) DETERMINATION OF TOTAL ACTIVITY a Total Actavity (mC&) Total s Activsty EmC1) i g - Fraction Container Identsfjcation ................._.... mci TOTAL MILLICtst!E3 e mC4
= SE-04 (frac. abun.) ** _ TOTAL
( MILLICtJt!ES) mci Total H.3 _ (TOTAL Mit.LICtJRIES) e
. Total C-14
- 4E-03 terac. abun.) (TOTAL MILLICtJt!ES) = mci *
- Total Tc-99 * (frac. abun.) * = mCA .;f -
_ (frac. anun.) * (TOTM. MILL 1Ctst1ES) Total I-129 = WASTE CLASSIFICATION APO MANIFEST REPORTING As determined by: dose rate 4 1 meter /.5o04100 ndt/hr ndt/hr (0-25(SS-gal. bos) drum) M Ct.AC3 other, specify CRITERIA FOR WASTE CLASSIFICATION GASED ON DOSE RATE Waste ss categorically CLASS A if dose rate measured at 1 meter from unshielded container does not exched 100 mR/hr for a 55-gal. drum or (DOT 17 container) and 500 mR/hr for a 4X4X6 container (B-P.S box) similar capacsty container. NOTE: If the dose rate exceeds the above guidelines, contact Lab Foreman for guidance. Waste may exceed Class A; additional analysis may be needed or container contents examined. Compacted and non-compacted trash may not be shipped as Class B or C unless packaged in a HIC. MANIFECT REPORTING:
- 1. List all radionuclides as recorded in the Generic Distribution or Special Distribution.
- 2. The total' activity (mCL) in the waste shipment for H-3.
C-14 Tc-99 and I-109 must be included on mansfest. ! Page 3 of 6 j ,p ., , Hrf-8037 ROO FIGURE 3 Page 3 of 6 massaiset
,r Nat enactouD-8037 I see ntle,Page E. l. HATCH NUCLEAR PLANT atvare w 0
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DATA PACMAGE 1 (cont.) CATA GHEET a CALCt1ATION OF CORRELATED RADICNUCidQES - QAW
/ /
Chapment at Containee Identsescatson / / TeChngggang
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oates a CAPE 94 SPf*CTRt.PI ANat.YGIS Or GPCCIAL Cart *t C . . . . . . . . .......... ....
. . . . . . . . . . . . . . . . . . . . . . . . . . . .* . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Column e2 Col 6mn 91 to CrR C1 NuC14 des Radtonucasdes .eath T1/2
...........................I*4. 5 vr. ...........
ret. actavsty frac. abun.I Pet. actsvaty frac. 4 tun.1 .-- -*- -- -* -- Co -E0 mn-54 - Co-58 Cs 137 2n-65 Cs-134 *
- Subtotet ,,
Co-l** . og a Guttotat et . . CALCt.A.AT!aN 0" CORRELATED RActoP4JCLIDC FRACTICPAAL. AOLFOANCCS Column e3 Column e4 relatsve frac, rotative' frac.% activity, asun.1 actavsty atun.
= SC-04 H.3f
*C 04 TRu e
- 7-03 =
C-14' ." (Cs-137) (Cr) N t -63 *
- 2E*oc e (Co-Got 17) ge.90 . * *E-02
- Pu -241 *
- JC -02 e tcs tJ7) (Gr3 (Cs.137 ) (7)
Tt-13 = -
- 3C-04 i (Co 13F8 (7)
- g.123 *
- 3 C -OS = Cm-242 = . CC 04 *
(Cs 1373 (71 (Co-1379 (73 Subtotal e3 Guttotal e4
~
+ t T'o' tat Relative Actavstr = t Guetotat e3 Suetotet e4
._._.........Suttotal 4
_ _ - - - et...Guttetal
. 82 Relative activity is the activity of a radionuclide as determined by a gamma spectrum analysis of a smear sample (or other type special sample) or by use of scaling factors for non-gamma emitting radionuclides. .
i Fractional abundance is determined by dividing each
' radionucitde's realt..e activity by the Total Relative Activity The quotient is the fractional abundance.
(as determined above7.
/- %
IUnless special analy3is have been performed for~H-3 and C-14,'the generic fractional abandances may be used w&thent ancurring j , signtficant error. , Page 4 of G p, Fff2-8037 ROO i
- a FIGURE 3
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P80CE DU
-so37 See Title Page E. l. HATCH NUCLEAR PLANT m,n -
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see Title Page GeorgiaPower 13 ,, n DATA PACHAGE 1 (cent.) DATA SFEET 3 QA/QC CHECM LIST WASTE CLASSIFICATICN APO MANICEST REPORTING Weste C1gis Shipment #:
%G $
- 1. Has waste been properly classified? ' Data Sheet 1 (and Data Sheet 2, if applicable) completed?
- 2. Has waste container been labeled CLASS A, CLASS B,-
- or CLASS C?
Waste Stability Chgracteristics YG @
- 1. Has proper waste container been selected (Class A
- carbon steel. Class B or C- HIC)? .
- 2. If HIC used, has User Checklist been completed? ,
- 3. Verify proper dewatering of resins ( 4.1% water).
4 If any liquids have been included, has sufficient absorbant been added to absorb twice the volume of the liquad? Absorbed liquids are not acceptable at Garnwell.
- 5. For weste containing osis, does the designated burial site allow for receipt of waste contatning oil? Waste containing otis cannot be shipped to Barnwell. For Class 8 or C waste in a HIC, oils cannot exceed 0.5%.
- 6. Have void spaces been reduced to extent practical'
- 7. For shipments to Barnwell, the site criteria for required use of HIC is 71 uCi/cmI long lived activity ( i. e. , Oub to tals #2, #3, and #4, Data Sheet 1).
l i l . Page5ofj, .
- W -8037 ROO FIGURE 3 Page 5 of 6 sassa i set
~ " " M -8037 see Title Page E. l. HATCH NUCLEAR PLANT .t..,..
g QAft See Title Page GeorgiaPower ~ ~ 14 or 14 d DATA PACHACE 1 fcent.) DATA 9EET 3 ( cont. ) WASTE CLASSIFICATICN APO PWWIFEST REPCRTING Mggifest Reporting ECS $
- 1. Have the total millicurie quantities of H-3, C-14, Tc-99 and 1-129 been determined and included on Manifest?
- 2. , Have gli principal gamma emitters and gli correlated radionuclides been included on manifest? Barnwell site criteria require res. rting correlated abundances of TRU, Pu-241 and Cm-242.
- 3. Verify accounting for at least 99% of total activity by individual radionuclide identification. .
- 4. Verify identification of Weste Class.
- 5. Verify correct physical description of waste.
- 6. Verify total volume of waste (same as used for determining millicurie content; if different esplain below).
- 7. Verify correct chemical form.
- 8. Verify exclusion of chelating agents (i+ > O.1%,
chelating agents must be identified). Cab Foreman: Date: Lab Gupervisor: Date: i 1 l l l t l Page 6 of 6 w -sO37 ROO l , FIGURE 3 Page 6 of 6 gangalset i 1
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GEORGIA POWER COPPANY HATCH MJCLEAR PLANT PROCEDL.RE Radiolocical Work Practices
. PROCEDURE TITLE Mf-8042 PROCEDLRE NUPEER Lab RESPONSIBLE SECTION GefETY RELATED ( X) NON-SAFETY RELATED ( )
APPROVED APPROVED REV. DESCRIPTION DEPT. GEhERAL DATE MANAGER _ _ _ _ _ _ . . _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ ..________ ____ _. ._ L___________. . _ _ _ O New Procedure
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. _ . . PROCEDURE CHANCES MODE OF OPERATION OR I S DESCPIDED IN FSAR:
.( ) Yes ( . N.o . . .
- nocsouns TNvatvES:
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( ) An unreviewed Safety Guesti ) Tech. Specs. not addressed in FSAR ( None of these (See back foe Safety Evalu. tion if required). ,,,. , , o
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See Title Page 1 of 7 l RADInt M ICAL WORK PRACTICES A. P_QR1 0Sg To make available to the general employee a brief set of general guidelines to be used for certain radiological work situations. . G. REFEREEE,3 10 C.F.R. 20, " Standards for Protection Against Radiation" C. GAFETY
- 1. Observe all radiation protection procedures.
- 2. Observe safety rules contained in SAFETY, Section O.
D. WORK PRACTICES The following work practices have been selected for all GPC Hatch employees to be familiar with.
- 1. itg}IVIDUAL RESPONS1gILITIES Observe the following when working in radiation control areas:
- a. E_x,o o sure: Don't get exposure you don't need.
(1) Obey promptly "stop-work" and " evacuate" orders of
. Health Physics and Operations personnel.
(2) Obey posted, oral, and written Health Physics instructions and procedures, including instructions on Radiation Work Permits. (3) Wear TLD and self-reading dosimeter where required by signs or by Health Physics personnel. Immedi-ately report unexpected exposure and a lost or offscale dosimeter to the Health Physics Department. Do not tamper with dosimetry in any manner. (4) Keep track of personal radiation exposure status and avoid exceeding exposure limits. Adminis-trative limits are whole body 2.5 Rem / quarter; skin 7.5 Rem / quarter; extremities 18.75 Rem / quarter.
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See Title Page E. I. HATCH NUCLEAR PLANT wnm> =o can O See Title Page 2 of 7 (5) Remain in as low a radiation area as practicable to accomplish work. (6) Do not loiter in radiation areas. (7) Notify Health Physics personnel of faulty or ' alarming radiation protection equipment. (8) Notify dosimetry personnel upon returning to the site after medical administration of radiophar-maceuticals. (9) Ensure that your actsvities do not create radiological problems for others and be alert for the possibilities that the activities of others may change the radiological conditions to which you are exposed. (10) Do not enter any areas with radiological hazards such as high radiation areas, airborne radioactivity areas unless you have been trained and are qualified to deal with the situation in a safe manner.
- b. Contamination: Do not carry radioactive materials home with you.
(1) Do not smoke, eat, drink, or chew in Radiation -
Controlled areas.
(2) Properly wear protective clothing and respiratory protection wherever required by signs or Health Physics personnel.
(3) Remove protective clothing and respiratory protection properly to minimize spread of contamination.
(4) Perform frisking properly. Assume that you are contaminated. Whole body frisking is required when leaving contaminated areas when protective l
clothing has been worn.
(5) For a known or possible radioactive spill, minimize its spread and notify Health Physics personnel promptly.
(6) Do not unnecessarily touch a contaminated surface or allow clothing, tools, or other equipment,to do so. m ,.
4 g =o can O
See Title Page 3 of 7 (7) Material must be surveyed after leaving a
, . radiation control area. Contaminated items must be bagged (as practical), labeled, and stored properly.
(8) Report the presence of open wounds to Health Physics and medical personnel prior to working in -- areas where radioactive contamination exists and immediately if a wound occurs while in such an area. (9) Minimum protective clothing dress for contaminated areas is: (a) Cloth shoe covers (b) Rubber shoe covers (c) Cotton gloves (d) Rubber gloves (10) Tools, equipment, trash, or any material leaving the operating buildings must be surveyed by HP prior to exit. (11) Do not step in puddles.
- c. Radioactive Weste: Minimize the waste that is generated.
(1) Limit the amount of material that has to be decontaminated or disposed of as radioactive waste. This can be accomplished by minimizing the amount of waste taken into the controlled zone, limiting the use of water when using it on contaminated surfaces, separating clean and contaminated trash and performing all jobs in a manner that generates as little radweste as
. possible.
(2) Read the label on trash and laundry drums. Place items in the proper container.
- d. Sianificance of Violatina Standards (1) Violation of procedural standards concerning radiation protection will be documented on the Radiological Deficiency Report (RDR) and brought to the attention of the person's supervisor. It is up to the supervisor to take action to assure this problem is solved. Action taken should then be reported back to H.P.
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See Title Page 4 of 7 Any flagrant violation will be documented on the (2)
< - Radiological Occurrence Report (Rm ) and brought to the person's Dept. Head attention. A copy of i
the Rm will also go to Plant Management. A response is expected from the Dept. Head as to the resolution of the problem. In addition, Plant Management has the discretion to delegate the severity of discipline to the person who has been recognized as continuously violating radiation protection procedures.
- 2. ALARA AS LOW _AS REASONABLY ACHIEVAE g
- a. Obiective The objective of the ALARA program is to maintain all
! personnel exposures, both internal and external, at the lowest practical level. This will be accomplished through good radiation protection planning along with a firm management connaitment to ALARA.
- b. Employee Responsibilitigg (1) Know your current whole body dose.
(2) Cooperate fully with W personnel in all matters. (3) Comply with plant directives, standard operating procedures, and warning signs or barriers that concern radiation and contamination control. (4) Knowing principal radiation sources and exposure ' rates on the job site as defined by W. (5) Properly using the exposure reduction tools and methods available. (6) Discuss exposure reduction ideas with W and supervisory personnel. I
- c. ALARA Guidelines (1) Minimize time spent in Radiation Areas.
(2) Increase the distance between yourself and the radiation source. (3) Use shielding to reduce your exposure. f D sp*u Q :l, W . e
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' O wm See Title Page 5 of 7 Plan all radiation work. '
(4) (5) Practice on mockups when available so you can do your work in a radiological environment in less time.
- 3. HAPOLING RADI0 ACTIVELY CONTAMINATED MATERIALS
- a. Previously contaminated materials, such as tools and equipment which could not be completely decontaminated, should be reused whenever possible for work in contaminated areas.
- b. Health Physics must be notified prior to removing
- material from contaminated areas.
- c. In as much as practical, contaminated materials or potentially contaminated materials must be placed in containers or in yellow plastic bags or wrapping material prior to being transferred from a contaminated area. Health Physics may specify special requirements such as the use of double plastic bags, use of shielded containers, or special precautions while handling the material.
- d. All containers or plastic wrappings should be properly sealed to prevent the spread of contamination.
Containers or wrappings should be open only when work is actually in progress that involves the container or wrapped material.
- e. Anyone observing damaged or torn containers / wrappings of radioactive materials should notify Health Physics immediately.
I
- f. Materials removed from contaminated areas shall be I handled as radioactive until monitored by Health Physics. Based upon monitoring results, non-contaminated materials will be released by Health Physics. Contaminated materials will be tagged by
!. Health Physics, indicating the radiation and contamination levels, and will be handled as radioactive material.
- g. Health Physics must be notified prior to contaminated material being moved from one contaminated area to 1
another contaminated area.
- h. Personnel should always minimize their exposure and
?
prevent the spread of contamination when handling i contaminated materials.
,g .
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mg PROCEDUM NQ.
" -8
- See Title Page E. I. HATCH NUCLEAR PLANT *dwa
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See Title Page O @O 6 of 7
' i. Yellow plastic indicates the item is radioactive or
, . radioactively contaminated material. Yellow plastic bags, tubing, and wrapping should be used only with radioactive materials or systems. Non-radioactive applications are not permitted.
- 4. RADIOACTIVE SPILLS
- a. Stop the spill: If the spill is from a system which may have more material (either airborne particulate radioactivity or fluids) to leak out, promptly stop the leak if possible. If the spill is from an overturned container, try to set it upright if the contents have not all escaped. The amount of time spent stopping a difficult leak should depend upon the radiation levels involved, the possibility of inhaling airborne radioactivity from the spill, and the consequences of not making a prompt closure.
If the spill is minor (for example, a small amount of water with low radioactivity spilled on a smooth surface), immediately cover the spill with the most convenient absorbent material available, such as absorbent paper or rags to soak up the liquid. After the spill is covered, follow steps b and c below as necessary to keep the spill under control.
- b. Protect Others: Other personnel who may become contaminateo by the spill or who may be able to help control it should be warned immediately. Call Health
, Physics personnel and the Control Room and give them the location and description of what has happened.
Keep unnecessary personnel away from the area affected by the spill to minimize spread of contamination. This action may require closing doors and verbally warning approaching personnel.
- c. P
,rotect Yourself: Move to the edge of the affected area, taking care to minimize spread of contamination.
It may be advisable to step outside the room where a spill occurred and close the door. Remain at the edge of the area until Health. Physics personnel advise otherwise.
- d. Follow Instructions: Follow instructions of Health Physics personnel, your department supervisor, or instructions given over the speaker system. -
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- 5. ' PROCEDURE FOR HIGH AIR 80RfE ACTIVITY Stop all work which might be causing the
- a. Stop Work:
airborne activity. For example, grinding or welding on contaminated components may be the source of the airborne radioactivity. You may be unable to determine the cause. Therefore, you and all other personnel in the area should stop work and leave.
- b. Protect Others: Other personnel who may be exposed to airborne activity or who may be able to help control it should be warned immediately. Call Health Physics and the Control Room and give them your location and describe what has happened.
- c. Protect Yourself: Move out of the affected area. If possible, step outside the area and close the door.
Put on a respirator if available.
- d. Follow Instructions: Follow instructions of Health Physics personnel, your department supervisor, or instructions given over the speaker system.
- 6. PROCEDURE FOR AN AREA RADIATION MONITOR (MtM) ALgf3
- a. Stop Work: Stop all work and leave the area immediately.
- b. Protect Others: Other personnel who may be exposed to high radiation should be told to leave the area immediately. Keep the unnecessary personnel away from the area. Call Health Physics personnel and the Control Room and give them your location and describe what has happened. This action may require closing doors and verbally warning approaching personnel.
- c. Protect Yourself: Leave the area. When you think you are out of the affected area, read your dosimeter. If the reading is 3/4 scale or greater, notify Health Physics of this fact.
- d. E_ollow Instructions: Follow instructions of Health Physics personnel, your department supervisor, or instructions given over the speaker system.
i Y- d
,p4 .D umann. 4xl 77 r
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PROCEDURE Waste Classification and Manifest Reporting Resin Shi Ements PROCEDURE TITLE HNP-8036 PROCEDURE NUMBER Lab RESPONSIOLE SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( ) APPROVED APPROVED REV. DESCRIPTION DEPT. GENERAL DATE MANAGER MANA ER O New Procedure - __ __--- -_ . p,y -. d--8.lh-i _gb-4.hM-_-_W-e.m-_-_.
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PROCEDL5tE rey 1Bf REEEEST SSE.T k (F l thdh O PROCEIXRE NO. HNP- Db REN -*rm.u BY ut:rARTriafT Pt*,.*GER APPROVAL. I~ Date: Signature: Date: Name: . QQ Q /
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SAFETY RELATED ( NCN-SAFETY REL ATED (d PROCEDURE CHANCES MOCE OF OPERATICN CNt INTENT, AS DESCRIBED IN FSAR: ( ) Yes ( d No . PROCEDURE INVOLVES:
) An unreviewed Safety Quest' n ( ) Tech. Specs. ( ) A condition
( not addressed in FSAR ( V) None of these (See back for Safety Evaluation if required). Attach copy of procedure to this form. REASON FOR REGtEST A 'h rulI' t w wvrrf;%sw + .G w # z /-f % '
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e PRB RECOMMEN)S APPROVAL:( es ( )No PRB Secretary g3-t87 /.l s /- D PRS Number Date y9 NANML SET -
SAFETY EVALUATICN This ornEndura dnet nnt ennefituta an unraviawad cafaty nuaetinn ae avnlained _' belnw.
- 1. iThe ernhability nf neencranea and the enneannaneae nf an accidant f
ne malfunctinn nf anninment imnnetant tn cafatv ara nnt ineramend ahnva those analyvad in the FRAR due to this nrneadura haeanes the orneadura dnae nnt channo the nurnnte nr nerfomanca of .t.he CLTW I system. L,Ihe nnstibility of an accident nr malfunctinn nf a differant tuna than analv7ad in the MAD dnae nne caenit fene thfe nenendues haeanca O'it fIe c erk%tte CADe C-
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't . Tha marnim nf emfaty me def4ned in +ha Tarkn4rm1 enar4#4g+4ane _,,
-f ie nnt raduced Ana en thic nenraA..ca harmnea tha n ar aA. . . Aa ,
na+ 2 anno h any 14mitad e n f a t,u c,uetam e n + + 4 nn, e. wh4rh unn1A_ 211au m enfaty limit en ha aveandad nr 211nw 2 14m4+4nn ,.nnd4+4nn fne nnaratinne en ha avesaded me etated in Tachniem1 Cnar4f4estinne e egeo. -. M6 eng. m 4. 9 M- M- - 1 t emb I -_.. _ - _ . -_. l Hi@-9 NANMLSET - e
PROCEDUHt **O HNP-8036 See Title Pag, E. l. HATCH NUCLEAR PLANT aen.o O , l
)
own g o
~~
See Title Page Georgia Power al 1 ,, 10 WASTE CLASSIFICATION AND MANIFEST REPORTING RESIN SHIPMENTS A. PURPOSg To detail the steps necessary to classify radioactive waste resin shipments in accordance with the requirements of 10 CFR 61.55 and to identify manifest reporting requirements in accordance with 10 CFR 20.311. B. REFERENCES
- 1. 10 CFR 20, Standards for Protection Against Radiation.
- 2. 10 CFR 61, Licensing Requirements for Land Disposal of Radioactive Waste.
- 3. HAP-8016, Shipment of Radioactive Material.
C. DEF_I_NITIONS
- 1. TRU - Alpha emitting transuranic nuclides with half-lives greater than 5 yr. (in particular - Pu-238, Pu-239, Pu-240,. .
Am-241, Pu-242, Cm-243 and Cm-244).
- 2. Principle gamma emitters - any radionuclide of plant origin identified by gamma spectroscopy and contributing > 1% of the total identifiable gamma activity for the waste under consideration.
D. PRECAUTIONS If the shipment includes multiple containers with differing waste composition, separate analysis for each different type waste should be performed. A single analysis may be used for multiple containers of the same type waste provided the container composition (i.e., radionuclide. distribution) is considered the same. E. DATA SHEET 1 GUIDANCE
- 1. Obtain results of gamma spectrum analysis of the resin sample for the resin shipment that has been collected and analyzed per Procedure HNP-8016.
- 2. Enter the sample identification information and the results of the gamma spectrum analysis on Data Package 1, Data Sheet
- 1. Record the measured concentration for each principal gamma emitter in the designated entries in Column #1 and
#2. The blank entries in Column #1 may be used to record radionuclides that are identified but not specifically
( listed. j 1 NM SET - l -
APPHyvat PHOLIDuHt NU HNP-8036 See Title Page E. l. HATCH NUCLEAR PLANT _
- o. ,,
O See Title Page GeorgiaPower " ~" a o , 10
- 3. Total the radionuclide concentration for Column #1 and #2
, entries to determine Subtotals #1 and #2.
- 4. Using the entries under Column #3, calculate the concentrations of the correlated radionuclides. Multiply the previously determined concentration of the scaling radionuclide, as listed, by the scaling factor (SF); the product is the correlated radionuclida concentration.
ES16 Generic scaling nuclides and generic resin scaling factors (SF) have been included in the Column #3 and #4 entries. If other than generic scaling nuclides or SF are to be used, cross through the generic value and insert the appropriate value. The Lab Supervisor (or designated alternate) will determine if other than the generic values should be used. H-3 and C-14 are not correlated to any other radionuclides. The concentrations listed under Column #3 for these nuclides are conservative, generic values. Technical bases for selection of scaling factors (if other than he generic fesin values) shall be documented on ata Sheet 1 by an accompanying attachment) K?> )(or NOTE The generic scaling factors will normally be updated yearly or once every two years as ap-propriate for the particular type of waste and activity levels. S. Similarly for Column #4, calculate the correlated concentration of TRU, Pu-241 and Cm-242, as indicated, by multiplying the measured Cs-137 concentration by the designated scaling factor (SF). These correlated concentrations shall be multiplied by 1.25 X 103 to convert from uCi/cm3 to nCi/g (based on a dewatered resin density of l 0.8 g/cm3 ) for use in comparison with the waste l classification limits on Qata Sheet 2). M & h t) Calculate Subtotal #3 by adding the Column #3 entries, G. Subtotal #4 by adding the Column #4 entries. I
- 7. Determine the total radionuclide concentration (GRAND TOTAL) by summing Subtotals #1, #2, #3 and #4.
ENEAL MT -
~ " HN P-8036 See Title Page E. l. HATCH NUCLEAR PLANT _
o ee Title Page GeorgiaPower A ~~ 3 of to
- 8. For each nuclide as identified or correlated above, determine its fractional abundance by dividing its concentration (uCi/cm I ) by the GRAND TOTAL. The quotient is the fractional abundance for the nuclide.
- 9. Determine the TOTAL MILLICURIES (total activity, in millicuries, of the shipment) by multiplying the GRAND TOTAL concentration by the volume of the waste (which may be less than the container size but in no case larger) and a conversion factor of 28.3 (cm3 /ft1
- mci /uC1).
- 10. Similarly, determine the total activity (millicuries) of the shipment for the nuclides H-3, C-14, Tc-99 and I-129.
(Total activity of these radionuclides must be included on the shipping manifest.) F. DATA SHEET 2_ GUIDANCE p
- 1. Transfer the radionuclide concentrationsfromkDataSheet1) for each radionuclide or radionuclide grouping to appropriate entries on Data Package 1, Data Sheet 2.
- 2. The concentrations (and corresponding limits) for all nuclides are expressed as uC1/cm3, e x cep t f o r TRU, P u-241 and Cm-242 for which the units are nCi/g. Therefore, the concentrations for TRU, Pu-241 and Cm-242 that should be used are those under the heading Conc. (nCi/g) from Data Sheet 1} g
- 3. Perform the required calculations to determine waste class.
After dividing each radionuclide concentration by the 10 CFR 61 limit (as included ong)ata Sheet 2), determine the " sum of fractions" for each column g g
- 4. Waste class is determined per the guidance included on (Data A
Sheet 2) M M 4I Nbg S. i Enter the WASTE CLASS; 4 % IsignanddatdDataSheeth 6. d@ Provide completed Qata Sheets 1 and 2) to the Lab Foreman (or l designated alternate), wil1[N i
- 7. The Lab Foreman (or designated alternate) review the calculations and waste class determination of'(Data Sheets 1 and 2). If satisfactory, the Lab Foreman (or designated alternate) will sign and date the data sheets.
E M SET . -
~~~ %-w
" -8 36 See Title page E. l. HATCH NUCLEAR PLANT RtvibON NU vm O
~~
See Title Page GeorgiaPower . ,, 10
- 8. The Lab Foreman (or designated alternate) shall complete
, Data Package 1, Data Sheet 3, GA/GC Check List. A "N/A" entry shall be recorded for any item of Data Sheet 3 that is not applicable to the type waste being evaluated. Any designated "No" response shall be explained on the data sheet (or by an accompanying attachment).
- 9. The completed data sheets shall be provided to the Lab Supervisor (or designated alternate) for review. The Lab Supervisor (or designated alternate) will sign and date Data Sheet 3, GA/GC Check List.
- 10. All completed Data Sheets 1, 2, and 3 shall be included in the station records for the waste shipment.
I i I 0
APP *euv4 6'WAADU8*t 'wu
" -8 36 See Title Page E. l. HATCH NUCLEAR PLANT . ,, %
i part
- " ~
See Title Page GeorgiaPower s o, 10 PROCEDURE DATA PACHAGE coCUMENT NO: HNP-gQ]Q-1 SERIAL NO: ROO-
- MPL NO:
RTYPC: 915 14 . XREF: TOTAL GHCETS: 6 FREQUENCY: COMPLCTED BY: DATE COMPLETCD: I flAVC RCVICWCD THIG DATA PACHACC FOR COMPLETENCG3 AND AGAINGT ACCEPTANCE CRITERIA IN ACCORDANCE WITH FtO-830. ACCEPTADLC UNACCEPTARLE RCVICWCD DY: DATE REVICWC : RCMARMG: .__. Page 1os6 HNP-SO36 ROO FIGURE 1 Page 1 of G 34sML MT -
l mm mtov* w
" -8 36 See Title Page E. l. HATCH NUCLEAR PLANT m.w w l Oatt 0 -
1
~
See Title Page eO@b NM s of to QATA PACMAGE_1 DATA 9EET 1 WASTE CLASSIFICATION - RE310 Sample Identification: Shspment # Type Waste: Technicaan: Volume of Shipment: ft Date: GAPPIA SPECTRtJM ANALYSIS RADIONUCLIDES Column #1 Column #2 Radionuclides wath T 1/a ( 5 yr. 10 CFR 61 Nuclides Conc. Fractional Conc. Fractional 1MGi/C'3 ) OkMH$Anit_ (uCi/cm3 ) Akungangg, Cr-51 Co-60 Mn-54 Cs-137 Fe+S3 , Co-58 Subtatal Zn-SS #2 Cs-134 Ce-144 Subtatal
#1 CALCtLATION OF CORRELATCD RADIONUCLIDES Column #3 Conc. Fractional (uC1/cm3 ) Akundance_
H-3 = = 4E C-14 " = = SE-04 Ni-63 = (Co-60)
- 4E-02 (SF) =
Sr-00 = (Cs-137)
- CE-03 (SF) =
- Tc-09 = (Cs-137)
- IE-04 (SF) =
I-129 = _ (Cs-137)
- IE-OS (GF) =
S9btotal #3 = ! Page 2 of E l FNP-SO36 ROO FIGURE 1 Page 2 of 6 EM SET . -
w --
" -8 36 See Title Pa9e E. I. HATCH NUCLEAR PLANT RtwsSauce seO I
om o l
-o See Title Page Georgia Pbwer 7 ,, 10 QATA PACHAGE 1 (cont.)
QAJA_ AggT 1 (contd M Tg_qugg1ElgATION - RESIN CALCULATION OF CORRELATED RAOIONUCLIDES (con *t) Column #4 Conc.
- Conversion = Conc. Fractional
, igCi/cmI) _Essior (nCi/o) A_jtyngaric e _
TRU =_____
- 2E-04 =
- 1.25 a 10 I =
(Cs=137) (GF) 1.23 a 100
* = =
Pu-241a
- CE-03 =
(Cs-137) (SF)
- I =
Cm-242=
- 7E-OS = 1.25 x IO (Cs-137) (GF)
=
Gubtotal #4 DETERMINATION OF TOTAL ACTIVITY GRAr0 TOTAL = + t + = uCa/cmI (Gubtot (Subtot (Gubtot (Subtot
#1) #2) #3) #4)
* *'OTAL ft3 (vol. of waste)
- 28.3 = mci MILLICURIES = _uca/cm3*
GRAND TOTAL Total H-3 =4C-04 uCa/cmI * ,__Ftl (vol of waste)
- 28.3 a mci To ta ', C -14
. 65C-04 uCa/cmI* ftI (vol. of waste)
- 23.3 = mci Total Tc M = uCL/cmI* ftI (vol. of waste)
- 23.3 = mci Total I-129 = uCi/cm 3
- Ft3 (vol. of waste)
- 23.3 =_ mci Page 3 of G HNP-SO36 ROO FIGURE 1 Page 3 of 6 M SET ,
) ., um *RGtC W W HNP-80%
see Tiue Page E. l. HATCH NUCLEAR PLANT %V4KJN NO Datg See Title Page GeorgiaPbwer d -a ~ 8 of to QATA PACKAGE _1 (cont.1
, QATA SIEE U WASTE CQ QSIFICATION WCRHSHEET
- I i
............................i.I.ggi.E1L1.".1.I.2........................
sJe 7 NActtrne - no Cm s.. . .... unste e4 Class C
% I Cate Class A
...s16de
-. 4... ..s..r...I
.... 6..........................
f e.0
- C.14 uC6/cm 3 6 0.3 e 0.3
- 6 3.0 fs.19 ucs/cm 6 e o.ce
- 3 123 uCt/cm3 s 0.00s =
- nC6/g 9 10.0 e t 100.0 TMt ef t/2>l ret e _ t 3500.
- 4 350.0 Pu Co-a24.a 4 aca/g cC u e e a00o. . e x e o* . ,.
>l se of reactiset 48 '* 28 7 l* u.na,t.t
. . .. ee.tet t e g1 y T Ngc7ttNI 10 C M gl.,.l.e.gLE 2 LIMIT 2...
Untes e9 CIdSS C
%cl de CatF Clett A Clast e
......a..'....
. .. ...F....
uC6/cm 3 3 700.0
- N/A N/A Total til/2 ) s yet N/A uC4/cm 8 1 40.0
- N/A H3 N/A N/A Co 60 vCa/ce' 8 700.0 e f 70.o
- 8 700. e N s .6 3 WCs/ce' 8 3. S e
- 190.0
- e 7000. e er.90 uC6/ce' # 0.04 *
**.o Co.ast uC6/cm5 t s.o e e = t =600. .
se es reestmeas l* ; l* 7 l*
...et .e for turnal The waste classificatton is determtned by the highest class for whtCh the " sum of fractions
- does not exceed 1.
If the " sum of fractsons' for Table 1. Class A 41, waste class as determined by highest column of Table 2 with " sum of f ractton"(1. If .* sum of f raction" of Table 1. Class A is > 1 but Class C 41, waste is Class C, provided Table 2. Class C
- sum of f raction" (1.
If " sum of fractions" of Table L. Class C > 1 or if " sum of l Fraction
- of Table 2. Class C >1. waste not suitable for burtal.
Iunsts for all nuclides are uCi/cm3 except for TRU. Pu.241 and Cm iba for which the untts are t'Ci/g. f I WASTE CLASS: __ Technician: Date: l l l Lab Foreman: Date: Page 4 of 6 HP-GO36 ROO FIGURE 1 Page 4 of 6 EAAML SET -
amom """'* HNP-8036 See Title Page E. l. HATCH NUCLEAR PLANT ..w w 0 ee Title Page GeorgiaPbwer d *
- 9 or 10 DATA PACT (AGE _1 (contd QATA GHEET 3 WASTE CLASSIFICATION APO MANIFEST R @ TINfg Weste Cla13 Shapment #:
%EE ,W
_ .1. Has waste been properly classified? Data Sheet 1 tand Data Sheet 2, if applicable) completed?
- 2. Has waste container been labeled CLASS A, CLASS 0, or CLASS C?
WA 112.2.til!111tY ChiriLieristics 1ES !!Q
- 1. Has proper weste contaaner been selected (Class A
- carbon steel, Class 0 or C- HIC)?
- 2. If HIC used, has User Checklist been completed?
- 3. Verify proper dewatering of resans ( 412 water).
- 4. If any liquids have been included, has sufficient absorbant been added to absorb twsce the volume of the liquid? Absorbed liquids are not acceptable at Barnwell.
- 5. For waste containing oils, does the designated burial site allow for receipt of waste containing oil? Waste containing oils cannot be shipped to Barnwell. For Class 0 or C waste in a HIC, osis cannot onceed 0.5%.
- 6. Have void spaces been reduced to estent practical?
- 7. For shipments to Darnwell, the site crateria for required use of HIC is> 1 uC A/cm3 long lived activity (i.e., Subtotals #2, #3, and #4, Data
. Sheet 1).
Page 5 of 6 m ~8036 Roo FIGURE 1 Page 5 of 6 M RT ~
-- -so36 see Title Page E. l. HATCH NUCLEAR PLANT * .w .
g See Title Page GeorgiaPower ~ ~ 10 ,, io DATA PACHAQE 1.(cont.) QATA SFEET 3 (SEH1d WASTE C(MSIFICATIQN APO MANIFEST REPCRTING DADif est Reoortino III 'dQ
~ 1. Have the total millicurie quantaties of H-3, C-14, Tc-73 and 1-129 been determined and included on
- Mansfest?
, 2. Have g n principal gamma emstters and gli .. ..
corrstated radionuclides been included on mansfestS Barnwell site criteria require reporting correlated aDundances of TRU, Pu-241 and Cm-242. __ 3. Verify accounting for at least 73% of total activity by individual radionuclide identification. 4 Verify identification of Weste Class.
- 5. Verify correct physical description of waste.
- 6. Verify total volume of waste (same as used for determining millicurie content; if different explain below).
- 7. Verify correct chemical form.
- 8. Verif y exclusion of chelating agents (if >O.1%,
chelating agents must be identified). Lab Foreman: Da* 3: Lab Supervisor: Date: __ f Page 6 of 6 w -sO36 'ROO l FIGURE 1-
- Page 6 of 6 BAML SET '
GEORGIA POWER COPPANY HATCH M.JCLEAR PLANT PROCEDURE Charcoal and Particulate Sampling Of Gaseous Effluents Under Emeroency Conditions-PROCEDURE TITLE 4 hbp-4830 1 PROCEDURE NUPEER l,3b RESPONSIBLE SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( )
#- APPROVED APPROVED REV. DESCRIPTION DEPT. GEbERAL DATE MANAGER 2 Pages 1, 2, 3&4 .- . _ _ _ . . _ _ _ _ , . . _ _ _ _ _ _ _ _ _ _ _ _ . __ ___. w_.
_____ ___. t_ ___ _ _ _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .._____ ______ ___4________________. .. ___ . _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .._____ ______ __. 4________________. .________ l l 1 _ _ _ . . .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . ._ ___ ______ ___ r_______________... .________ 1 1 _ _ _ _ _ _ . . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ..________________ 9________________. ._____ __ _ _ _ _ _ _ .. ____... _________ . .________________ r____________.___. .__ _ __ r_ . ___ . . _ _ . _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . r_____________ . . _ ____
. . . , _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . ._________ . p_ _______ . __.,________
4 7 wj, t q 4 j 6, y
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1. WI ') FROCEDJRE REVISIGJ REGUEST 1
~-
9 gw- . . . * *: .' , 5 PROCEDJ E NC. H'P _d[d8 __ SHEET 1 OF
. Revision No. / ___
e t REGUg gD_bV _
/DEFAGTMENT W AD AT' RO'w'A*g Name: Date: gnature: Date:
l'
$ff,(/) [
___ji q $$ / 12-l6 O _
- REVISION ('HANGE3 MODE OF CF ERATION OR INTENT AS DESCRIBED IN FEAR:
( M No
-t ". ( ) Yes I!
If CHANGE IN'wCLVES: ( ) An unreviewest Safety Guestion ( ) Tech. Specs. ( M Neithee l (Eee tack for Safety Evaluation if required). '
. PRESENT STATUS: h fety Related ( Non-Safety Related ( )
The above Safety /Non-Safeiy Status has changed ( ) Yes to Attach marl <ed up copy of procedure to this form. REASON FOR REGUEST:_ , M - 9 t/ 3 (JrdCe_Mcty/ P,/t / / w
/
i - -- i
, DESCRIPTION OF CHANCES: Ifi /fLi ;ho e St : Q . l f"c.-tti pig stl f Mc/
[.) /'e# by GefjeJLT _ 7:: !
~
Z*. ' . - > !. * - ) .: .,~ ? ,e - rs
/
<<ji)j lb }l4l 4 ,.
g ).- ' A .,';.*: -- k'
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f ' PRB RECOMM NDS APPROUAL: (')Ves ( )No PRB Secretary 83-233 u,,.c u PRO Number Date HNP-9 t l
,,5
- 7,
,;gtr 7 0 i
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;n St_F_TTV A_/.iLUATIC_N_ =
l f
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2 e revi'sion of this procedure does not constitute an unreviewed safstv nuene ton as *wnlaintd. _ belmi;_ _ _ . . . ,
- t. The nrobability .gl_RSSRIanGS and lht SJ2H110. u_ences of an agg.i.denI..__ _ _ _ ,
. . a .
. nr am1 funeeio ,,,.g(_eauipment_imgariant to the 1sLLtFI ILIA 09.C.1.DEIA.aj3d ,,,
nhnva ebase analy, gad in the ELM dge to these channas because_Ihe__,___ r.vi*4an dn** noe eb'"oe - *h* ?"YPD12 QI geefamm_nce of thg_gy,31gh___ .. I ~t .~t.- i , ,.s. nn. 4hu.it.y_at.an.acc.ident. or e 1f mcc. tan _au.3msraat me =
.t 3 e s ,., , ,, 21,r , . A ' 4 n ek. reAn an.= nne v =nie frem ehf* Changs because J
t ek. eyeram_noemanae and <gt_opormeed n= hefnre the change. j _ ew. Tarknient__speciffestions L ;5. ,,.,4,, n r e _, 7,. ev 2e A . f 4 ., ,, A 4, _ _.4 r nne . A , , e gd, A , , . en eb4s rav4=4+n heemstem *he *evisfon does not
; _ % a =ay 14 'ead; *]Fary systa, a e e i n g .rh 4 ch yeu i d _ m i t og_a_c gf,e ty litrit e, wo evr..A.A n, en 211rb m 14-4eing ennatrinn fnr eneration eg_h,e
.,,,...; A n= n e a e e d.,Maghnf.ggLS,,73 gi,f_(g a e ion s f, *
// , J..,6 rf n'e'n
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p_=# _ . , _ g t [ - ___M_ l _ -D_D_.D_.M-_ k I s __= e m___ __ __ _.h_e_.D ___ HNP-9 R. . . : , 3 .y-.. . -. . _. .
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kNdW Ir ,=gg , treur. . w.y-- w v 7 , m 2
- -o HPP-4830 See Title Page E. l. HATCH NUCLEAR PLANT oo om 2 See Title Page 1 of 4 CHARCOAL APO PARTICtLATE SAPPLING
, OF GASEOUS EFFLtKNTS UNDER EPERGENCY CorOITIONS A. PURPOSE To provide a detailed procedure for sampling gaseous effluent ~for l Iodine and Particulates during a Site or General Emergency.
B. REFER,jN_G]}
- 1. HPP-7600, HNP-7129 C. SAFETY 4 l
- 1. Due to the high dose rates and contamination levels which are to be expected with this kind of an accident, dry runs of sampling techniques should be performed before doing actual sampling. ,
- 2. Laboratory supe'evision shall be consulted on all activities associated with sampling and counting any material obtained for post-accident analysis.
- 3. All attempts to get samples will be followed with the most restrictive H.P. practices. Constant H.P. monitoring will be provided and adhered to. A minimum of two persons will be required while getting the sample.
- 4. These sample points are high and hard to get locations. Be
, aware of the danger of falling.
- 5. Be aware of time it would take to retreat and which is the best and fastest way down.
D. SPECIAL EQUIPPENT I
- 1. Sample shields previously placed at sample points.
- 2. Special lowering device to lower samples from top of Reactor Bldg. and from the stack sample station.
- 3. Hoods in lab with shisiding which to unload sample behind.
- 4. Special counting shield for charcoal and particulate.
- 5. Cart or truck to bring sample from Stack to Lab.
- 6. High range dosimeter, TLD's, Finger Rings, Pc's, Polybags, and air packs for H.P. purposes.
p;r ~~- .~
'W5
- 7. Remote tools to open sample holders. P.
~
h. W S00 3'
_ .mam o HNP-4830 See Title Page E. ! HATCH NUCLEAR PLANT = ve= =o Daft See Title Page b 2 of 4 E. SAPPLING REACTOR OUILDING VENTS l
- 1. Load a spare cnarcoal and particulate holder with a Cesco Charcoal Cartridge anc a 5 micron millipore filter. If available substitute a Silver Zeolite Cartridge for the charcoal. Obtain a plastic bag large enough to hold holder.
, 2. Notify Health Physics you are ready and you need a person to survey for you. Put on the protective clothing required for the R.W.P.
- 3. One technician proceeds to Unit I Reactor Building by using Reactor Building elevator or stairs and ladders from the Turbine B14g. roof, taking radiation surveys as you go. If dose rate is above SR/hr retreat. The second technician goes to the area where the sample is to be lowered with cart and awaits the lowering of the sample.
- 4. One technician proceeds to the appropriate Unit I'or Unit ,II vent.
- 5. Assure that the previously placed shielded sample carrier and apparatus to lower sample is available. Place' plastic bag into shield.
- 6. Survey current sample line and holder. Assume 1 minute to remove holder and replace holder. If dose will be above 1 and 1/4 Rem to whole body or 7 and 1/2 Rem to extremities do l not remove holder.
- 7. . Very quickly and with constant monitoring, disconnect the present sample holder and place in shield.- Connect spare holder in place. Note time sample was removed.
- 8. Lower shield over side of Reactor Building to ground.
- 9. The other technician removes the sample from the shield and places it in the lead pig on the cart and brings the cart to the lab for counting.
F. SAMPLING MAIN STACK
- 1. Load spare sample holder as per E.1 of this procedure. l
- 2. Notify Health Physics you are ready and need a person to l survey for you. Put on the protective clothing required on I the R.W.P.
1 3 ,--- v -- .- 1 + t__
~ . - >
HNP-4830 See Title Page E. l. HATCH NUCLEAR PLANT unuw w we 2 I See Title Page 3 of 4
- 3. One technician proceeds to main stack and up the outside
, stairs to the sample room taking radiation surveys as he goes. If dose rate is above 5 R/hr. retreat. The second technician waits with sample cart at base of main stack for the sample to be lowered.
- 4. Assure that previously placed shielded sample carrier an'd apparatus to lower sample is available. Place plastic bag into shield.
- 5. With a teletector , survey current sample line and holder.
Assume 4 minutes to remove holder and replace holder. If dose will be above 1 and 1/4 Rem to whole body or 7 and 1/2 l Rem to exfremities do not remove hcider.
- 6. Very quickly climb to clatform where sample is located.
With constant H.P. monitoring disconnect the present sample holder and place in shield. Note time sample was removed. Connect spare sample holder in place. ,
- 7. Lower bucket to floor and then to ground, where waiting technician is ready to place sample in shielded cart and proceed to Lab for counting.
G. SAMPLE PREPARATIONS APO COUNTING l
- 1. Take sample from shield and place behind shield in hood.
- 2. Unscrew two halves and take out particulate and charcoal filters.
- 3. Place particulate in a petri dish and wrap dish with plastic.
- 4. If sample is too hot to count on GeLi, place sample in special shield and counting holder. The holder is half a lead brick with an indention to hold the petri dish. The brick will have a 1/2 inch hole thru it at the center of-the l brick. The top of the holder i.s another half brick.
l S. Count particulate filter and calculate particulate releases l using procedure FN)-7600 and 7129.
- 6. Place the charcoal from G.2 in special holder for purging. l Blow air very slowly thru filter. Try to get all gases released to go up hood and not out into Lab.
l _JZIE If Silver Zeolite is used, the purge is not necessary.
- 7. When dose rate on filter quits dropping, s ig"**= y y-4 g -{
- t. - *
- . l Q meen set ,
l y-
~ --
" -*830 See Title Page E.1. HATCH NUCLEAR PLANT . . .
oun 2
~ ^ -
See Title Pags GeorgiaPower 4 ,, 4
- 8. Wrap charcoal in plastic. IF sample is tou hot to count,
< place sample in special shield and counting holder. The holder is similar to one in G.4. l
- 9. Count charcoal filter and calculate release as per FNP-7129 and 7600
- 10. If counting room is not habitable, mobile labs should be on site.
- 11. If no Lab is available, send sample to outside vendor specified by Lab Supervisor for analysis.
H. DISPOSAL '- g cmg Keep samples in the fume hood behind lead bricks until proper disposal methods are arranged. , i l l W.~~. g v 3 s f, Y t
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50-321/366 Ilatch MEMORANDUM FOR: Chief, Document Management Branch, TIDC FROM: Director, Divison of Rules and Records, ADM
SUBJECT:
REVIEW 0F UTILITY EMERGENCY PLAN DOCUMENTATION The submitter of the attached document'has expressed no desire to withhold any information contained therein. Therefore, this material may now be made publicly available.
/
p J. M. Felton, Director
/ Division of Rules and Recoros Office of Administration l
Attachment:
As stated 1 i d
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l i Georgia Power Company l Poet Office Box 436 i Bexley, Georgte 31513 Telephone 912 367-7781 912 537-9444 m Edwin 1. Hatch Nuclear Plant January 13, 1984 GM-84-41 PLANT E. 1. HATCH Emergency Implementing Procedures Docket Nos. 50-321/50-366 United States Nuclear Regulatory Commission Director of Nuclear Reactor Regulation Washington, DC 20555 Gentlemen: Pursuant to Appendix E Section V of 10 CFR 50, ylease find enclosed ten-(10) copies of the latest revisions to the Plant E. I. Hatch Emergency procedures. Three copies of these procedures are also being forwarded to the Region II office in Atlanta, Georgia. [
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