ML20236S497
| ML20236S497 | |
| Person / Time | |
|---|---|
| Issue date: | 10/01/1997 |
| From: | Jim Hickey NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Seelig C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| Shared Package | |
| ML20236Q363 | List: |
| References | |
| FOIA-98-110 NUDOCS 9807240384 | |
| Download: ML20236S497 (19) | |
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9 ~g g ;a ' yd 'L . . g j. pMEMORANDOM M: .P l T Program' Analysis Branch toe* j..Clau' c
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?[U' 3 Management (DWM) was requested to provide information on the' ~
- v. R , (SDMP) site and the two reactors that were decommissioned by DWM. The attached table Q. ', .1 summarizes the SDMP sites that have been closed out since 1992 and
$ . . ' the information requested by DriPaperiello.' Please' provide the RITS data which shows the L '
- total hours and FTE expended fpr each of these facilities, broken out by NRC Headquarters and
, . Regional employees, for 1990 through 1997.:Please include overtime and compensatory time.
, .. ,., ;'. In addition, please provide the hours and FTE expended for..PA Numbers 232BA,232BAA,
#,2#. ,' . ? 232BAB,' 232BAC, which are not already included in the data for the facilities o
(.' . . ;, list. iri order to meet our Divislo
.. $ deadline, I am requesting that you provide this informatib on y-f,F. W October.17,1997. ' 4 7.
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Progranf, Management, Policy Development
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low-Level Waste and Decommission $1ng
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SUBJECT:
S . . 1D F9R FUTURE BUDGETS ic % f c M b. . , 9,. .:. , qd ,.,** . y ,.^ . , - ~'. . ~ .
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.'I.5,5,'.7 Management (DWM) was requested to provide information on the' costs and Full Time
$W l.2 Equivalents (FTEs) spent on the,close out of each Site Deconimissioning Management Plan
.. , / -. : ; (SDMP)' site and the two' reactors that were decommissioned by DWM. The attached table GS. ' . ' summarizes the SDMP sites that have been closed out since 1992 and the 2 reactors
?gS .; , mentioned in Dr. Paperiello's memorandum! We are requesting your assistance in obtaining i9 : the information requested by Dr[Paperiello.' Please' provide the RITS data which shows the ,
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- s. J' ' , ' total hours and FTE expended for each of these facilities, brpken out by NRC Headquarters and c< Regional employees, for,1990 th. rough 1997. Please include overtime and compensatory time.
,$ ;,,,-- y In addillonlplease provide the hours and FTE e'xpended forPA Numbers 232BA,232BAA, M .: .'l. 232BAB,232BAC, which are not already included in the data for the facilities on the attached
$,', J. list. In order to meet our Divistori deadline, I am requesting that you provide this information by-M.B G October.17,1997. ' 4.
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Dominick Orlandi DV)M/NMSS i g,'M.[ ' ; 301-415-6749 .
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Claudia A. Seelig, Chief a 4 'i-klh$. MEMORANDUMTO: oNO :h. . ,, Progrgg1 Analysis Branch , ,
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'. and Analysis Staff, NMSS , i .
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SUBJECT:
. DATA FOR FUTURE BUDGETS p... 3
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t .. - t In a memorandum from Carl Paperiello, dated June 5,1997, the Division of Waste kJ E.-@'.%.,s.,:
'!b 34y .:M:.Managem. t en .$.' S. 'i. . . .
(DWM) was requ,ested to provide information on the costs and Fulltime
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- p.a%;R, Management Plan pl*H+;, f.y.:.:.,Equiv. .r y +. ale,nts . .
.n (FTEs). spent on the close out of each Site Decommissioning
, ! ph. ex.;M:n:p(SDMP)'alte ...,> and., the).tvio~ reactors'that were decommissioned by DWM. hr.l[ s u $ summarizes . .. . .
' the. '- SDMP site's that have been closed 'out since 1992 and the 2 reac
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mentioned in Dr. Paperiello'.s.m..emorandum w We are requesting your assistance in obtain
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- .hugh 1997. Please include overtin1e and compensatory time.
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.3 i 9.c.M. 9,'x. In addition,,please, r. provide the. hours and FTE cxpended for PA Numbers 232BA,232BAA,
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. [kh $$dBI232BAb, WSch[are rhlready included in the ddta for the facilities on the attached
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As stated
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300HY 10.fd~ fo July 25, 1960 TO: Dr. D. R. spink Corberundua Metals Co. , Akree Ilow York FadM R. J. Augustine, D. E. Barber and G. Boyt libipple Daiversity of Michigan q SURJECT: Resort of the Radielemisal Survers of Operations at the Parkers-burn Plant. May 10 - July 22.1960, and a Recommended Routtae Radiohomical Pronraa. l This report is divided into the following sections: 9 I
- 1. Introduction
- 2. Air Samples
- 3. Water Samples
- 4. Urimelysis
- 5. Gamma Measurements
- 6. Revised Counting Procedure
- 7. Conclusions and Reseamendations i l
, A. Carbiding ,
I S. Chlorination ( l C. separations D. Maintenance \ 2 g E. Geaural Mk[ P i F. Routiae Radielegical Program $ Q 4 % [# . G ' ofg l ) \
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- 1. Introduction The data contained in this report were obtained during less than 100%
l Plant production. Concentrations of radiomativity in air and water saw be expected to inerseas when full production utilising Nigerian ore is achieved. Separattens data were taken when the feed to that system uma only SSE pigeriam tetrachloride. , No data has been obtained during the operation of more than one ableri-aster.
- 2. Air Samples Table 1 is a summmary of air sample data obtained following the install-ation of additional ventilation equipment in the carbide building. All average ,
values are less than MPC except for the drummains operation, the routine for uhteh has not yet been definitely established. The use of the MA respirater will effectively redues the exposure during this operation te less than MpC. A comparison of the data of Table 1 with these of Table 3 of our mome dated March le, 1960, shows that the ventilating equipment and the more sare-fel headling of the earbido and old six has resulted in a redesties of average seneestrations of radioactive material in the air. Off site samples from the seatinuous air semplers loested at the neares' netsh'eers of the plaat indiente air sessentrations of radiomativa esterials 11 below the MPC. Consentrattens of radiomative material in the air of the separations building are all below the occupatiemal Mpc for thorium. A single semple une takaa at each leastion given in Table la azeept for the ErSO 4 filter and tetra-ableride feed locations. The values gives for these latter two loestions are
===N== of two and three saarles respectively. All reported istues are aise based en first sounts of the samplog esasequently, all are hiab estimates.
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Table la AIR 84WLE ETA F5008 SAIIFLES TAEEN IN SEFART10N8 ON 20-8 JULY 1960 Location ges/,el r,, Ostwalk - ErSO 2.7 x 10-12 4 Filter Er804 Filter 1.5 x 10 -12 Feed Filter 9.5 x 10 ~13 Tower, 1st Floor 7.5 x 10~I3
" 2nd " 8.2 x 10" 3
" 3rd " 1.1 x 10- 2
" 4th " 1.4 x 10 -12
" 5th " 1.5 x 10-12 Tet Feed 8.3 x 10 -12 1:0 Drea Change 1.8 x 10-12 1:0E Filter 4.0 x 10 -2 Ef0E Filter 1.1 x 10-12 1:0E Filter 3.3 x 10 -12 Ef Tray Dump 1.1 x 10"II Jt s .OM
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- 5. lister seuslos There appear to be three components of the liquid effluent to the Ohio l River.
These are
- a. surface drainage, which includes eeolant water from the carbide furasse and floor washings, as well as roof dreimage from the
, several buildings. -
- b. Process sewer drainage.
- a. genitary drainage through a septic tank.
l All three of these seaponente combine en plaat property to form the single line which empties in'to the river. Total effluent flow rate is estiasted by Mr. Tuttle to be from 450 to 900 gallons per minute. ,, l gesples taken from the affluent contain a large enount of solida, pr h l inspection of seglas thus far sounted our experience forces us to apply a self-absorption correction faster of le to the unter sample sewating data. This eerrection factor applied to two samples taken during shlerination oper-l ations only and to two samples taken during both separations and ehtorination operations provides an estimate of liquid affluent esseentraties at the river of 4.9 x_ it'_ pe/mi which is apprezimately ten times the My@ for astural thertwa in water. ,\ . l An intensive sauer affluent and river radielegical survey is recommended when the plant achieves full producties on 1991 Nigerias ore. The results of 1 l this survey will help to determine the magnitude of the effluent problem. ( l l 4. Drlasheis i All reported alpha activity asesentrations in urine are well below the Itaimus' permissible primary Exereties Rate (MPUR) of 1.5 a 19-2 dyn/mi which we had recommended in a previous report.
. a (
6 No definite pattern can be recognised from the compilation of data in Table 2 either by work location or with respect to time. Consequently, it is rea - h d that urinalyses not be performed at frequent intervals but be used as a check to demonstrate the absesse of entry of radiomativity into the body. Itissuggestedthaturinalysesbeperformedfollowingadsmonthsof operation. A review of the data vill them enabla daterminaties of an appse-priate interval at skich these analyses should be perfeined, specimens from
, one er two office workers may serve as sentrols for these analyses.
It is considered advisable to include radioactive urinalyses as a part of pre-employenne and terminal physical examinations.
- 5. Osuns Haasuressats F '- -
Gemma radiation measurements tabulated in Table 3 show that a cenelusion of a previous report continues to hold true and film badges as a routine men-itoring teel are unnecessary anywhere in the plant. It is seasidered advisable to begin a samme radiaties los book wherein measurneents can be permsoently recorded. A gamma meseurement on the ErC14 feed tanks indicated nearly backgraned radiation er a not of .01 mr/kr. It is met expoeted that other vessels will give much if any greater readings than this, but measurements ehem14 he made and recorded if film hedges are met to be used. As a matter of Isgsi record it wenid be advisable to monitor with film badges these individuals most exposed, at six month intervals.
- 6. Revised Countina Precedure
{ count the standard seurse et le8 E 29eg c ga,,gh g and record the result in the les book! Any usjer deviaties from the expected standard count indicates
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Table 2 8U80141T OF URINALYSIS DAYA
-2 dpe/al) d /) ONUEE = 1.5 x 10 Report Date Feb. 15 Ilarch 17 June 14 June 27 Position or After Before After Oblorinatiop After llaan Location Carbiding Chlorination and Before Carbiding Carbiding
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- 17 i'19 0 l ~_ 3 I 13 59 i0 3
- h6 23 I 23 0
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@ 4 I 16 74 i 38
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( T-ble 2 (Continued) Report Date Feb. 15 March 17 June 14 June 27 g g Foeition or After Safore After Chierination After h '? ( Hans Location carbiding Chlorination and Before Carbiding Garbiding 61 95 to S 26 t 27 h M o ea t 3o . 6 i _ 4 t 16 o, - M M 17 t is , o 6 g - 4 t 16 66 t 35
- 21 t 23 398 i 99
- 6 i h 13 i 23 21 t 23 o 9
38 t9 2 83 i 42 . 6 17 t 18 - 9 i 20 7 g 124 t 42 o o
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y p 15 t9 1 57 t 30 6 g s2 t 35 17 ts i 1 6 6 3 t is 4 T 16
@ 43 t 26 ,
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6 42 t 27 ao t sa e
- sW W, .. . .
tot 23 o 2 49 t 33
- f@ 15 t 19 26 i 27 6i 13
@ l @ 57 t so 4o t so o
- O 15 t9 1 19 t 19' 22 I7 2 g t6,t 46 M 109 t 4o 46 I 27 6 i 23
- O 2 t 13 6 t 13 o
).
@ (Continued)
Report Date Feb. 15 March 17 June 14 June 27 Position or After Before After Chierination After Location Carbiding Chlorination and Before Carbiding Carbiding f Nans
/ 95 i 38 55 t0 3 66 I 35, ,_* 0 *
-6 57 i 30 23 I 27 9 i93 M 15 i 19 26 i 27 46 i 33 28 23 53 I 35 42 I 27 99 I0 5 17 I 23 *
@ 83 I 35 13 I 23 9 I 39 *
@ 2 I 13 0 31 I 38
~
69 I 33 39 i 40 22 I 27 46 I7 35 I 30 mm 2 I. M
- 1.
- Changes outside limits of error.
- 2. All figures a 10*3 dpe/al.
l
I t r,: Table 3 CARBik BADIATION REAWMIENfs, JULY 22, 1960 (WLORIN&TICE WILDIN) o kN SK4 65
- Leestion Gontainer Filled Mhr Floor ErC1 Container, Top, Center 7-22-60 5.0 First 4
" Top, Side
" 2.0
" Bottom Side
" .76
" Top, Center 7-18-60 .36 a
" Top, Side
" .41 a
" Sotten, side
" .41
" Top, Center 7-14-60 . 21
" Top, Side " .14
" Bottom, side . 21
. .56 First A - Chlorineter I'8 .21 g,,,,4
.56 Sotton
" - .06 Third
. .76 First O b Condoneer Joe . 36 8* * #
a ~ Bottom .66
" - .11 Third 58C1 container, Top, side seing fttled .76 First 4
" Bottom, side " 2.5 k
I
). _
1, s 11 some trouble with the counter, i.e., dirty chamber, dirty center wire electrode, change in high v61tage setting, or malfunction of the electronics. The ulidity of the sausle counts depende en this standard source cheek precedure! saakground should continue to be counted twice a day or after counting
" sloppy" samples and recorded in the leg book. The chamber should be cleased
~
to reduos background below 1 e.p.m. With beekground seumts g3, or gggg,;ig. the background eeust should be subtsneted from the sample eeunt before recordias i the count in the les hoek. Air samples need saly to be counted at approximately 100 hours after collection ( A t = 90-110 hours.) The formulae for saiculating the air activity concentrations are as
, follows:
Einh Vol. Air samplert ue = 2.2 x 10*I' x (not 100 kr. c.p.m.)
~
m1(air) (vel. in cu. ft.) Contiamens 24 kr. gamelers: 1
,00 hr c.s.o.)
I = 2. 5 x 10 *ll x (met l g,g,) __ (ve. .. La eu. ft.)
& g filter h shecid be dry when <eunted. This may require heating them before soenting!
MggLd,333133, should be prepared with care and placed in the plamakets carefully to avoid setting sample material en the outside of the planchet. The final slurry in the plamshot must be dgigg ,dqwly, to avoid hubbling, splatterias, popping, frothing, etc. After drylag, continue to heat the sample to drive off organic vapers, ammonia vapers, ets. game samples may need to be stored in i a dessicator until eeunted! Caleulate the activity of liquid samples by l l using the following formular 1
= 4.5 x 10 x (met 100 kr. c.p.m. )
~~
i
,gg (vol. in mi.)
4
_~,' ( o 12
- 7. Conclusions and Recommendations A. carbidina: Continued care in handling ore, carbide, and old mix coupled with the use of the ventilating equipment will help to keep the air concentrations in the general carbiding area below the MPC. Frampt repair
~
of furasse leaks is essential to maintain low air concentratiems. Respirators j should be worn for any dusty operation er when visible ciends of dust are being generated. Respirators are met required, however, merely to walk through the building, in the locker room, or in the control, room, as long as one stays out of the dust cloud. geassious; effort to keep dust to a minimum is essen-tial for this ares! Protective clothing, consisting of caps, gloves, and coveralls should be worn for all operations involving contact with radioactive material or very dusty conditions. Protective clothing is met necessary when merely walk-ing through the butiding. The following two types of signs should be posted at all entrances to the carbiding areas (1) " Caution - Airborne radioactivity Area" (2) "castion - Radioactive Materiale", la' addition all containers, bias, hoppers, etc., oestaining radioactive ere, eerbida, or old mix should be posted as felless:
" Caution - Radioactive Materials"
- 5. Chlertaaties: In this ares the saaeral air soneantrations are below MFC, except for the dusty operations of drum pulling, feeding carbide,ed 3,elling the bed residue. Respirators should be worn for these operations.
Also, during bed residue pulls the air concentrations in the general chlori-nation area requires wearing of respirators. Continual care in the handling of dusty materials and use of the ventilation equipment is essential for the safe conduct of these operations.
}
i i 13 Coveralis, caps, and gloves should be worn during feeding earbide, tot drum pulling, and bed residue pulls. protective clothing is not required at other times. The two types of signs are required here a (1) " Caution - Airborne Esdioactivity Area" (2) " Caution - Radiomative Materials" All drums, bins, and hoppers containing radiomative material should be posted with: " Caution - Radioactive Materials." C. Separations Buildias: All sir samples indicated no airborne hasard althousk the dusty and fuming operations showed higher concentrations than the others. Respirators need not be generally worn in the area, but it is l resemmended that they be used for the dusty operations or had fume conditions, i.e., feeding tet. Protective slothing (caps, gloves, and coveralls) should be worn to l prevent contamination whenever contact is made with the open systems or there is a possibility of contact with solutions, powders, etc. I I i l The sign " Caution - Radioactive Meterials" is required at all entrances I to the Separations Building and on all precssa vessels, tanks, etc. ( D. Msintoaamso: Air cessentrations for meistemasse operations are met l kneva, but possibly eeuld be high. Coveralis, ears, 31 eves, and roepirators should be worn anytime radiomative material is encountered er the process system is opened. This must be earefally watched!
- 3. General Items
- a. Temporary c' mange shed is met necessary. Tbs 1ecker room in the carbide Building and the change room in the Chierisation Build-ing can be used to change into protective clothing. Emphasis i
f 14 mast be placed, however, en keeping these change reens closa and on providing proper unshing facilities for the workers. ,
- b. There should be a designatedlarea in each building for lumah-ing and me eating should be allowed at other places. The 1emah rooms mast be kept clean and hand washing faegities provided,
- s. The record of eseh man's time in the various areas is new umase-essary since the total plaat is en 1997. Nigerian.
- d. It is ressemanded that work shese be provided in the carbiding operation only. These shoes should reasia at the plant and should met Le were home,
- e. I4beratory personnel should be advised that the semples may con-tain radioactivity and the samples should be handled with care.
- f. All personnel should be advised of the moesssity for elesalisess in working with the radiesetive material. Handveshing after contact with the process stream and especially before eating
'should be required. A shower before poing home is highly resen-mended and should be encouraged.
F. Routine Radielenical Prestes: Table 4 shows a proposed routine radielegical program of sempting and monitoring to be carried out by plant perseenal during operatise with radiesetive meterials. All air samples taken with the Righ Volume sampler should be for a sempling duration of 10 minutes if possible er until the flew rate drops to 18 c.f.m. N. . The off-site sentiameos air samplers should be changed every 43 hours.
'A sewer effteest monitoring program will be set up after the intensive eifluent survey has been assemplished.
The importsmas of recording the results of all sampling and monitoring informaties in a peranaent les book een not be ever-eghasised!
1 I3
. 1 1
~
Table 4 ROUTUE RADIOLOGICAL PROGRAM Air samples: 8E& lagmE . rascosmor Carbide ore and oaka hole 1 per week
. during toeding locker room 1 per week control room 1 per week main floor 1 per week catwalk 1 per week car pulling 1 per car carbide sorting 1 per car drumeing operations 1 per car l
Chlorination feeding carbide i per week trC1 drum pil 1 per week 4 bed residue pull i per residue pull ( general area 1 per week I change room 1 per week l Lunch room 1 per week Separations feeding tot 1 per week Er oxide drumming 1 per week lunch room 1 per week Off-site four directions from continuous plant at nearest neighbor l
( l Table 4 (Continued)" - 4 Laundry Samples: 100 al. of first wash water, 1 per week. Gessa Measuressace: M N ARE& drums or bass of ore 1 per week Osrbida dras of carbids :I 1 per week drwas of old mix 1 per week Chlorination chlorinator 1 per week chlorinator condenser 1 per week drum of bed residue 1 per week drum of tot 1 per week Separations feed storage tank 1 per week feed filter press 1 per week Er raffinate tank i per week Eg raffinate unk 1 per week Er sulfate tank i per week Er OR tank i per week \ drum of M OR 1 per week \,
* \
E g filter press 1 per week Wrinelysis: Reecessaded for all personnel after 6 months of operation with 100% Nigerian ore and as a part of a pre-employment and terminal employment physical asami-nation. R. J. Ausn# tine
.. .. rur
~
GLtI G. Royt Whippl# w Copy: G. Chapman
* .o.. -
G S ._ ~ .~, g . l ((
~.. n.
ei
,, ? .
- October 31, 1978 '/(/ )
i j
~f
( Mr. Jack T. Sutherland . l Chief, Fuel Facility and Material Safety Branch l U.S. Nuclear Regulatory Commission l 101 Marietta Street, N.W. Atlanta, Georgia 30303 l l . l l t
Dear Mr. Sutherland:
1ais will confirm my telephone conversation with John Potter
~
! 4 on October 26, 1978, and is in reply to your letter of October 6, 1978, to Mr. G.R. Couch, concerning the placement of NRC reports in the Public Document Room. We have reviewed the copies of inspection report numbers 78-03, 78-04, 78-05, and 78-06, that you enclosed with your letter, i l and are satisfied that these reports do not contain proprietary { l information. Therefore, we have no objection to these reports j l being placed in the NRC's Public Document Room. ll l l l We appreciate Mr. Potter taking the time to inquire about our j l position on these reports. l Very.truly yours, 1 l tanley A. Thielke I Manager of Industrial Hygiene !. SAT /lmn l cc: J. Potter l F 1 ! AA L...
-78112@f \p .
abrmatica in this record was deleted ~ n accordance with the freedom of information - ~
'~ ""
4 " 3 ' Act, exempli 6 s b ~~ i .. J'_ F0IA- A 78 -l/ L'
~
i
** - tJAr x CFtJTE A. GAf ENWICH. CONNECTICUT 0S830 TELEPHONE (20316?? 3000 CABLES AMAXMET. GAIENW:CH
e a W 8'00, UNITED STATES o NUL; LEAR REGULATORY COMMISSION 4 g (f g REcloN il
, y ',3-
'"* 101 M ARIETTA STREET. N.W.
- / t ATL ANT A, GEORGI A 30303 o, [
gv*...*g In Reply Refer To: OCT 111978 RII:RLW ' SMA-1219 - STB-440 , i AMAX Specialty Metals Corporation
- ATIN: Mr. C. R. Couch, President One Greenwich Plaza Greenwich, Connecticut 06830 Gentlemen:
This refers to the four special inspections conducted by Messrs. R. L. Woodruff and R. A. Brown of this office during the period of July 18, 1978 thru Septembr.r 28, 1978, of activities authorized by NRC License Nos. SHA-1219 and STL-440 for the Washington, West Virginia Facility, and to the discussions of our activities held with L. B. Foster Company representa-tives during the inspecti 1 Areas examined during the , vu ;'on and our findings are discussed in the enclosed inspection reemo dithin these areas, the inspections consisted of environmental sample collections, interviews with personnel, and independent environmental measurements performed by the inspectors. Within the scope of this inspection, no items of noncompliance were disclosed. In accordance with Section 2.790 of the NRC's " Rules of Practice", Part 2, Title'10, Code of Federal Regulations, a copy of this letter and the enclosed inspection report will be placed in the NRC's Public Document Room. If this report contains any information that you (or your contractor) believe to be proprietary, it is necessary that you make a written application within 20 days to this office to withhold such information from public disclosure. Any such application must include a full statement of the reasons on the basis of which it is claimed that the information is proprietary, and should be prepared so that proprietary information identified in the application is contained in a separate part of the document. If we do not hear f rom you in this regard within the specified period, the report will be placed in the Public Document Room. 981420A!!im , i ..~ ~.. : : c : : -W-R y. ::
. . , - - = . , . . - . ., \
l 1
OCT 11 1971
=
I AMAX Specialty Metals Corp. 1' l l Should you have any questions concerning this letter, we will be glad to discuss them with you. Sincerely, e
~
fd Y Jack T. Sutherland, Chief Fuel Facility and Materials Safety Branch
Enclosure:
Inspection Report Nos. 78-03, 78-04, 78-05 and 78-06 cc w/ enc 1: L. B. Foster Company Attn: Mr. H. F. Ford, Vice President Eastern Operations 3169 Holcomb Bridge Road - Suite 210 Atlanta, Georgia 30017 Mr. L. W. Bechtold, Sheriff of Wood County Post Office Box 1076 Parkersburg, West Virginia 26101 Mr. Lee Bettenhausen Region III U. S. Environmental Protection Agency " Curt.is Building 6th and Walnut Streets y Philadelphia, Pennsylvania 19106 k f'.
**
- e *47**",*,., W h g * ,- , , , , , , ,
- -..u- ,g ,
a- . a mnaco, UNITED STATES
- o, NUCLEAR REGULATORY COMMISSION REGloN ll
, y, g 7 g 101 MARIETTA STREET N.W.
*
- ATLANTA, GEOHGI A 30303 s...../ ,,
?
Report No.: 78-03 License No.: SMA-1219 and STB-440
. Licensee: AMAX Specialty Metals, Inc.
P. O. Box 32 Akron, New York 14001 Facility Name: Parkersburg Facility Inspection at: Washington, Vest Virginia Inspection conducted: July 18, 1978 and August 1, 1978 Inspector: R. L. Woodruff Accompanying In torf / Brown Approved by:
' /d N patf J. P. Aotter,' Chief Fuel S cilities and Materials Safety Section Fuel Facility and Materials Safety Branch Inspection Summary Inspection on July 18, 1978 and August 1, 1978 (Report No. 78-03)
Areac Inspectedi Special, announced inspection at the AMAX/ Foster Washington plant to :onduct background radiation measurements at the site area, to collect TLD dosimeters and to interview persons who had formally worked at the site. The inspection involved approximately 30 inspector-hours by the NRC inspectors. Results: No items of noncompliance or deviations were identified. i l i no
- P *S4 40tP" e m=- m 4-d
[ GruJoosy-7 7g,
i l . a t l RII Rpt. No. 78-03 I-I l l DETAILS I Prepared by: - g /heyd/ R. L(roodrulf, Radiatiosf6pecialist Sh/ Date Fuel Facilities and Materials Safety Section Fuel Facility and Materials Safety Branch Dates of Inspect 1 and August 1,1978
- Reviewed by: Il J. P./ Jotter, Chief t.
Fuel (Eacilities and Materials Safety Section Fuel Facility and Materials Safety Branch
- 1. Purpose On July 18, 1978, Richard Woodruff and Robert Brown went to the Washington site above for the purpose of collecting the thermoluminescent dosimeters (TLDs) that had been placed at the facility on May 31, 1978, and to meet with bulldozer operators who reportedly buried various materials at the site during the past several years. On Tuesday, August 1, 1978, R. Woodruff returned to the site for the purpose of evaluating and observing the ATCOR survey.
- 2. Contacts The following persons were contacted during the July 18, 1978, vi s it .
Walter Pavlo, Plant Manager, L. B. Foster Co. Gene Lawson, Spiralweld Division Manager, L. B. Foster Co. Harold Kall, Vice President, AMAX, Inc. R. G. Levesque, ATCOR, Inc. G. L. Williams, ATCOR, Inc. Ron Smith, L. B. Foster Co. . Buck Talbot, Set Excavating Co. Nel Young, Industrial Hygiene, AMAX, Inc. The following persons were contacted during the August 1,1978 visit. W. Pavlo, L. B. Foster, Plant Manager M. Young, AMAX, Industrial Hygenist R. Levesque, ATCOR G. Williams, ATCOR M. Snieckus, ATCOR
-_ , j -. _ .
n 781120o54'l l i __
- h. k' RII Rpt. No. 78-03 1-2
- 0. Sullivan, ATCOR D. Milewski, ATCOR, Project Manager ~
B. DeBord, West Virginia State Health Dept.
- 3. Scope
- On July 18, 1978, brief discussions were held with AMAX/ATCOR people who were conducting the preliminary radiological survey. The discussions were mostly about topics related to the NRC surveys, type of equipment used, and the objectives of the ATCOR surveys and the survey methods they would use. Discussions with L. B. Foster personnel were mostly of a general nature including Foster's plans to move their plant operations to an area free of radioactive and zirconium materials. Mr. Lawson and Mr. Smith furnished a set of blueprints showing the location of a storto sewer , that emptied into the Ohio River. This sewer was established during f the tenure of the Carborundum Metals Co. Inc., at the site. These blueprints have been added to the Region II files. Previous knowledge of the exact location of this sewer had not been revealed to the NRC. It had been previously suggested by Foster personnel that the storm sewer pipe terminated in the ravine close to the settling ponds. Although this pipe was known to exist in the "old fenced area" of the site, it was never considered to be a major problem to the environment or to personnel. The pipe was surveyed thru various " man holes", and water and sediment samples were taken at the " sever outfall" at the Ohio River. These samples (AMW-9 and AMS-29) were sent to DOE /RESL in Idaho Falls, for analysis. The " manhole" survey was performed with the SPA-3A probe and it indicated that some contamination does exist at the
" manhole" just west of the settling ponds. The contribution from natural radioactivity in the brick. liner ,could not be distinguished from any thorium residues, and the AMAX/ATCOR personnel were informed of our findings.
On August 1, 1978, the inspector was told that the survey had been delayed and that the water-jet drilling would not be started until the following Monday, August 7, 1978; and the dry mechanical auger (drilling) work would not be performed until later in the week.
- 4. Interviews
- a. The following persons were contacted by telephone on July 18, 1978, to establish an appointment time for them to " point-out" the
" burial sites" to the NRC inspectors:
~ - -. -- . .. .
- - - - __m
- l RIl Rpt. No. 78-03 I-3 Harvin Eddy, Set Excavating, Vienna, V. V -
6)lh Darrell Drain, former employee of above; . 4 Appointments were made for 6:00 p.m. July 19, 1978, fog the above persons to meet NRC inspectors at the AMAX site. Neither person showed up for the appointment. Further. attempts to contact Mr. Eddy failed. Mr. Drajtn's home phone number was called and his wife stated that he would be working until about 8:00 p.m. I Mr. Buck Talbot, who is a partner of Mr. Eddy, was contacted by f telephone and he agreed to come to the site. Mr. Talbot arrived ~l at the site at 7:00 p.m. and be pointed out/an area between, and ! south of the new buildings where he, Mr. Eddy, Mr. Drain, and a ~ Mr. Fry had buried barrels and other materials over the past nine years. He, could not define the area exactly but be stated that l the barrels had no markings, and that several fires had occurred j during the burials. He further stated that exact burial dates I could be obtained from his files if needed. He stated that the I trenches were up to 20 feet deep and 35 feet wide. ) i
- b. On July 19, the inspectors went to the West Virginia Division of I Radiological Health and briefed Mr. William Aaroe on the NRC /
activities at the AMAX/ Foster site concerning the ongoing activities conducted by ATCOR/AMAX personnel,
- c. On August 1,1978, Mr. Levesque was asked to describe what had been done, in regard to their survey, and what was yet to be done.
He stated that they (ATCOR) had compleed their survey of. the clean areas and had found hot spots from 2 to 5 times background in the sewer manholes, and one area south of the sewer outfall, about 20 feet from the river that was above background levels. A ) sediment sample had been obtained from the sewer outfall catch l tank. Except as noted above this area was considered by ATCOR to -l be free of contamination and suitable for L. B. Foster to move i Mr. Levesque stated that the survey _was their buildings onto. l taking longer to complete than expected; however, they intended to meet the eight weeks deadline. He informed the inspector that l the wet- drilling will be performed by a husband and wife team.that ! have done work for ATCOR at other sites. He said they were aware of the zirconium problems at this site and their names are Chailes and Julia Martin. The " dry" auger drilling was expected to begin later in the week. Mr. Levesque described how the area designated in the survey protocol would be monitored with a Ludlum one inch NaI(TL) scintillation detector and the radiation levels measured with a Reuter-stokes Pressurized Ion Chamber (PIC) instrument. He described how the samples of soil would be monitored in the
?
e i I l RII Rpt. No. 78-03 I-4 t l i field and he stated that 10 percent of the samples would be sent to an independent testing laboratory for radioisotope analysis.
- d. On August 1, 1978, during a discussion, Mr. Pavlo stated that Stephens Construction Company had been contracted to move the steel buildings to the new site and that the Insurance Agency for Stephens Comnany may want a statement that there would be no radiation hazard to the Stephens Company employees. The inspector called the Insurance Co. "S. Byrd Ross Agency",
Parkersburg, W. Va.; 304-485-4475, and informed a Mrs. Mitchell that there should not be a radiation hazard while moving the buildings to the new location. Af ter confering with Mr. Potter by telephone the inspector called Mr. Pavlo and informed him that a NRC representative would be on site frequently and that we did not intend to allow any person to be exposed unnecessarily and to feel free to call the Region II office at any time.
- 5. Inspector Observations
- a. It was observed that ATCOR personnel had established a laboratory in the main office building which consisted of the following equipment:
An Eberline PAC-4S lin-log meter with an alpha probe which would be used for monitoring shoes, clothing, etc., for contamination. An Eberline PS-2 scaler attached to an Eberline RD-13 alpha i sample counter which would be used for smear evaluation. A Reuter-Stokes PIC instrument that would be used to survey environmental radiation levels, as necessary. A Ludlum survey meter equipped with a one inch NaI(TL) crystal that would be used to locate hot spots above background. l An Eberline GM survey meter would also be available.
'All of the above instruments were calibrated by Eberline Instrument Co., Inc. within the past three months and were operable. All persons had been issued R. S. Laudauer Co. , Inc.
film badges and were instructed in the use of the instruments and the nature of the pyrophoric material and potential contamination problems for facilities and to themselves. __ ___ __ _____ _ _ _ _ _ _ _ - _ _ _ _ _ - _ _ _ - _ _ _ _ _ _ _ . _ _ _ - _ . _ _ . _ _ _ _ . _ _ _ _ _ _ _ . . _ _ _ _ _ . _ _ _ _ _ . _ _ _ _ . . _ _ . _ _ _ _ _ _ _ _.___J
~ -
- i Rll Rpt. No. 78-03 I-5 1
Wi i
- b. Much of the area around the new buildings had been marked off in -
25 feet grids. The maximum and averaghtion lev'e-Is had been l recorded from the NaI de survey. ATCOR personnel were currently taking me ements with the PIC instrument in each grid. The measurements were being supervised and the readings i were taken by Mr. Levesque. I, l a.
- c. A NRC Form-3 was posted in the office laboratory. ATCOR employees had been instructed to wash their hands before eating, not to smoke in known pyrophoric material areas, and a paper " runner" was installed on the hallway floor to keep contamination out of the laboratory and other parts of the office building.
- 6. TLD Recovery and Data Summary J l
.On July 18, 1978, the TLD's were recovered after a total exposure time of 1052 hours. Another survey reading was taken with the Eberline SPA-3A scintillation detector. The SPA-3A detector measurements taken on l; July 18, were taken at the position of the TLD locations; whereas, in the previous survey of May 31, 1978, measurements were taken at the PIC J locations. The two measurements were in general agreement with each other; however, some differences were found and these differences are mainly due to hot spots and detector geometry, as it was not always possible to get both the TLD's and the PIC meter in exactly the same locations.
I Attachment A to this report is an updated version of Attachment A from / Report No. 78-02. The PIC reading at location number 31 was erroneous and for this report, the PIC value was adjusted downward to 354 pR/hr to correspond to the maximum digital readout capability of the PIC instrument. The TLD data was converted f rom millirem to microroentgens per hour for comparability with the PIC data". Attachment B is a summary of the PIC and TLD data af ter corrections were made for background radiation. The TLD data were expected to differ from the PIC data because the TLD's represent an integrated exposure over several weeks, and the background exposure rate could vary during any 24 hour period. It is believed that the two sets of l [ data are in general agreement, the dif ferences being due to factors , previously mentioned. It should be noted that location number 6 (U.S. Post Of fice, 26181) - shows a larger TLD reading, which is probably due to the TLD being positioned on an inside concrete block wall during the exposure period, whereas, the PIC reading was taken outside the block building.
~
I { i
RII Rpt. No. 78-03 I-6 Location 23 (Area "t!" at ravine) and location 31 (oil pump, Bldg. C) and location 32 (Northeast Door, Bldg. C) were not in agreement. Again - it is believed that the differences shown are mostly due to geometry and position of the detectors during the measurements. Location number 41 (East fence area) was different mainly because the value had exceeded the PIC instrument digital readout capability. For the purposes of this report, it is believed that the PIC data represents a reasonable evaluation of the environmental radiation levels at the site and with exceptions as noted above, this data is supported by the TLD measurements. f
a ATTACH?fENT A INSTRUMENT AND TLD MEASUREMENTS a
' Measurements were taken at I meter above ground using a pressurized ion chamber - (PIC), and a portable survey meter utilizing a 2 x 2-inch sodium iodide crystal (SPA-3). A TLD was also placed at selected locations one meter above ground.
The PIC readings below are in microroentgens per hour (pR/hr); the SPA-3 read-ings are in counts per minute (cpm), and the TLD readings are in units of microroentgens per hour (pR/hr) and includes the integrated dose from background radiation over the exposure period. The first SPA-3 measurement (second column) corresponds to the PIC measurement, and the SPA-3A readings corresponds to measurements taken at the TLD locations upon removal of the TLDs. This table a contains raw data only. See Attachment B for a summary of data corrected for various background radiation influences. No. LOCATION PIC SPA-3 TLD NO. SPA-3A TLD (pR/hr) (cpm) (cpm) (pR/hr)
- 1. Parking lot, start 10.8 600 N/A 600 Parking lot, stop 11.1 N/A* N/A N/A 137Cs check source surface None 48K N/A 50K
- 2. Secretary Office 11.2 N/A 19 N/A '20.25 i 2.26
- 3. Telephone pole by RR 10.0 900 20 900 21.17 1 2.26
- 4. Well No. 2 9.7 900 21 700 20.69 i 2.01
- 5. Foster Drive and 1 Route 892 11.2 1.1K N/A N/A p l
- 6. U.S. Post Office, 26181 9.6 1.0K Ctl 3 N/A 28.21 1 2.43
- 7. Power pole, Foster Drive 13.2 1.7K 22 1.2K 25.32 1 3.08
- 8. Power pole, parking '
lot 9.5 800 23 700 21.48 1 2.13 j
- 9. Barnsite, Foster Drive 9.0 800 N/A N/A glo.-- Tree near gas,well. 7.2 550 Ctl 4 500 16.94 1 2.07
-18kl W.~O y.
Attachment A l PIC SPA-3 TLD NO. SPA-3A TLD NO. LOCATION ' (pR/hr) (cpm) (cpmT (pR/hrT
- 11. Bldg. at pond 8.5 750 24 700 18.77 i 2.44
- 12. Dirt fill south of '
hay field 23.5 7K 25 4K 38.96 1 7.68
- 13. Ravine bed, boundary 44.8 12K 26 5K 48.31 i 8.13
- 14. Fill dirt, east of #12 8.2 800 42 600 21.48 i 2.22 -
I
- 15. Fill dirt, west of #12 8.0 800 N/A N/A
- 16. NE of Bldg. B, stream 8.8 1K 27 700 19.68 1 1.85
- 27. Dry Stream, east of Bldg. B 9.2 IK 28 IK 21.54 1 2.61
- 18. Southeast boundary 8.9 900 29 800 20.74 1 2.34
- 19. Boundary, SE of -
Bldg. B 8.7 IK 30 IK 19.05 1 2.07
- 20. Boundary, south of Bldg. B 7.9 750 31 600 19.02 1 2.30
- 21. Boundary, east of ~
ravine 9.6 IK 32 IK 20.14 1 2.36
- 22. Area "N" at ravine 50.3 13K N/A
- 23. Area "M" at ravine 63.0 17K 40 14K 108.89 1 15.02
- 24. Area "0" 203 48K N/A N/A
- 25. Area "P" 74.0 22K N/A N/A
- 26. Area "J", south of Bldg. D 63.5 18K N/A N/A
- 27. Pit, Bldg. 13 298 70K N/A F/A
- 28. Bldg. D, 30 ft. from inner ofe 12.7 N/A N/A N/A
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r o , , [ i Attachment A : NO. LOCATION PIC SPA-3 TLD NO. SPA-3A TLD l (pR/hr) lepm) (cpm) (pR/hr)
~
28A. Steel beam, 6 ft. from pit N/A N/A 33 37K , 254.57 1 16.41 l i
- 29. Inner ofc. Bldg. D 9.3 1.1K 34 800 19.59 1 2.13
- 30. Clock area, :dg. C 7.0 500 35 450 16.81 1 2.41
- 31. Oil pump, Bldg. C 354 110K 36 2K 23.95 i 3.17
- 32. Northwest door, Bldg. C 69.0 15K 37 8K ,
52.05 1 8.33
- 33. 50 ft. W of Bldg. C 354 115K N/A N/A I
l 34. Bldg. F, West inside 10.1 1.2K 38 700 17.56 1 1.75 l 35. Trench, Bldg. F, SW corner 19.6 2.5K 39 1.7K 22.26 i 1.89
- 36. Bldg. F, 15 ft west 31.0 7K N/A N/A
- 37. Pond, S.E. corner 8.5 800 43 500 20.76 1 3.57
- 38. West Perimeter 8.2 800 44 600 20.56 1 2.96 i 39. "L" Bldg. site 354 110K N/A N/A i 40. Loading hopper area 111 32K N/A N/A
- 41. East fence area (TLD at 100K reading) 354 200K 45 52K 571.50 1 33.06 -
l 42, 25 ft. East of Tower 267 50K N/A N/A
- 43. North fence, 50 ft.
N of office 216 50K N/A N/A 43A. Window ledge, Office ! Bldg. 17.9 2.5K 46 2.2K 29.76 1 2.80
- 44. North of tower 87.0 20K N/A N/A
- 45. Power pole, NE of office 13.8 ;- 1.8K 47 1.5K 26.09 1 2.04 l
l w_-_-_________-_-_-
4 Attachment A . . , TLD NO. SPA-3A TLD NO. LOCATION PIC SPA-3 (pR/hr) (cpm) (cpm) (pR/hr) ,
- 46. Tree on Hill E of 48 IK 22.48 1 3.14 i Rt. 892 N/A N/A
- 47. . Tree, end of ravine 3.5K 36 18 1 2.63 at hay field 26.5 3.8K 41
- 48. 20' into hay field, from ravine 11.7 N/A N/A N/A
- 49. Tree, 2/3 down ravine 55.86 i 8.33 from S boundary N/A 7.5K 49 7K
- 50. Tree, 1/3 down ravine 49.69 ! 8.14 from S boundary N/A 7.0K 50 6K
- 51. Sheriff Bechtold's 21.15 1 2.49 Office N/A N/A Ct1 5 N/A
*N/A - Not Available or Not Applicable
** - The maximum digital readout capability on the PIC instrument is 354 pR/hr.
*** - Ctl represents a " Control" TLD number.
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g ATTACF. MENT A Yb e PIC AND TLD 1.0 CAT 1055 \ n. 9 9.t. - l 3-l . Aste~ l Ot!bt p /).' _c A !, I
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4 ATTACIDfENT B ,
SUMMARY
OF PIC AND TLD DATA Background areas were setected as location numbers 8, 10, 11, 37 and 38. This selection was based upon the physical location relative to the facility and confirmed by survey meter measurements performed with the SPA-3 and
- SPA-3A sodium iodide crystal detectors. Arithmatic means were calculated for the pressurized ion chamber (PIC) data and for th'e TLD data from the above 5. locations. For the purpose of this report, background values were established as the mean value plus two times the standard deviation for each set of data and rounded up to the nearest 0.1 pR per hour. The PIC back-ground value was established at 10.1 pR per hour, and the TLD background value was established at 23.4 pR/hr. The net values above background are i presented below. Refer to the text of Report 78-03 for further discussion, {
specifically location numbers 6, 23, 31, 32, and 41. j NO. LOCATION PIC TLD NO. TLD (pR/hr.) (pR/hr.)
- 1. Parking lot, start time 0.7 N/A Parking lot, stop time 1.0 N/A 137Cs check source surface N/A N/A
- 2. Secretary Office 1.1 19 BG l
- 3. Telephone pole by RR BG . 20 BG
- 4. Well No. 2 BG 21 BG
- 5. Fester Drive end Route 892 1.1 N/A 1
- 6. U. S. Post Office, 26181 BG Ctl-3 4.9 1
- 7. Power pole, Foster Drive 3.1 22 2.0
- 8. Power pole, parking lot BG 23 BG 4
- 9. Barnsite, Toster Drive BG N/A l
- 10. Tree near gas well BG Ctl-4 BG
- 11. Bldg. at pond BG 24- BG
- 12. Dirt fill south of hay field 13.4 25 15.6 8
e i Attachment B 1 I PIC TLD NO. TLD NO. LOCATION (pR/hr3 (pR/hr.) . Ravine bed, boundary 34.7 26 , 24.9 13. hil dirt, east of #12 BG 42 BG 14.
- 15. Fill dirt, west of #12 BG N/A NE of Bldg. B, stream BG 27 BG 16.
- 17. Dry Stream, east of Bldg. B BG 28 BG
- 18. Southeast boundary BG 29 BG
- 19. Boundary, SE of Bldg. B BG 30 BG
- 20. Boundary, south of Bldg. B BG 31 BG
- 21. Boundary, east of ravine BG 32 BG
- 22. Area "N" at ravine 40.2 N/A
- 23. Area "M" at ravine 52.9 40 85.5
- 24. Area "0" 192.9 N/A
- 25. Area "P" 63.9 N/A
- 26. Area "J", south of Bldg. D 63.4 N/A
- 27. Pit, Bldg. 13 297.9 N/A
- 28. Bldg. D, 30 ft. from inner ofc 2.6 N/A 28A. Steel beam, 6 ft. from pit N/A 33 231.2 29.. Inner office, Bldg. D BG 34 BG
- 30. Clock area, Bldg. C BG 35 BG
- 31. Dil pump, Bldg. C 343.9 36 0.6
- 32. Northwest door, Bldg. C 58.9 37 28.7
'~ 33. '50' feet west of Bldg. C 343.9 N/A
l
. ..ggu_,
6 i l Attachment B l 6: l l NO. LOCATION PIC TLD NO. TLD (pR/hr.) (pR/hr.)
- 34. Bldg. F, west inhide BG 38 BG
~
- 35. Trench, Bldg. F, !;W corner 9.5 39 BG
- 36. Bldg. F, 15 feet west 20.9 N/A
- 37. Pond, S. E. corner BG 43 BG
- 38. West Perimeter BG 44 BG
- 39. "L" building site 343.9 N/A
- 40. Loading hopper anea 100.9 N/A
- 41. East fence area (TLD at i 100K reading) 343.9 45 548.1
- 42. 25 feet East of lower ~256.9 N/A
- 43. North fence, 50 tt. N of ofe 205.9 N/A 43A. Window ledge, of4 ice Bldg. 7.8 46 6.4
- 44. North of tower 66.9 N/A
- 45. Power pole, NE of office 3.7 . 47 2.7
- 46. Tree on Hill E. of Rt. 892 N/A 48 BG
- 47. Tree, end of rav s ne at hay field 16.4 41 12.9 ,
i 48, 20' into hay field, from ravine 1.6 N/A
- 49. Tree, 2/3 down ravine f rom S boundary N/A 49 32.5 I
I 50. Tree,1/3 down i avine f rom S. Boundary BG 50 26.3 l
~
- 51. - - Sherif f Bechtold 's Of fice N/A Ctl-5 BG l
l
, v. , .. - - a Attachment B -
4- . W\ l 3!
*N/A - Not AvaiIable or Not Applicable '
**BG - Backgroun3
***Ct1 represents a " Control" TLD number a
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O g>n atCO UNITED sT ATEs (o, NUCLEAR REGULATORY COMMISSION j [ f ,g REGION ll j {
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Report No.: 78-04 License Nos.: SMA-1219 and STB 440 Licensee: AMAX Specialty Metals, Inc. P. O. Box 32 Akron, New York 14001 Facility Name: Parkersburg Facility Inspection at: Washington, West Virginia Inspection conducted: August 7 to August 11, 1978 and August 28 and 29, 1978 Inspector: R. A. Brown Accompanying Personnel: D. Montgomery J. ter f ,I
/0 k Reviewed by: L J. P. :.ter, Chief Iptf Fuel ilities and Materials Safety Sec. tion I Fuel Facility and Materials Safety Branch Inspection Summary Inspection on August 7-11 and 28-29, 1978: (Report No. 78-04)
Areas Inspected: Special, announced inspection at the AMAX/ Foster Washington plant to observe survey being performed by Atcor Inc. , to collect environmental samples, to evaluate radiation levels in storm drainage system, to provide ground support for EG&G aerial survey and to meet with various media representatives. The inspection involved approximately 96 inspector-hours by three NRC inspectors. Results: No items of noncompliance or deviations were identified. l b
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Program Analysis Branch * .'7, .- . . .
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. . Nhn W!{.N. Nicke , Chief ' '5'[0RIGINAl.SIGNEDBY:)
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SUBJECT:
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' DAT F{R F.UTURE BUDGETS \-
d k:, In s'm ' a Iom b rl"Pa ri lo, dated' June 5,19'97, the Division of Waste
,.$.;' '.' l3 Management (DWM) was requested to provide information on the' costs and Full Time
?,M" k Equivalents (FTEs) spent on the close out of each Site Deconimissioning Management Plan
.,, A . n(SDMP) site and the two reactors that were decommissioned by DWM. The attached table ~
9 ' summarizes the SDMP sites that have been closed out since 1992 and the 2 reactors
. g.5.; , f ; mentioned in Dr. Paperiello's memorandum.' We are requesting your assis
' .. % , l the Information requested by DrJPaperiello.' Please' provide the RITS data which shows the
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- total hours and FTE expended for each of these faellities, broken out by NRC Headquarters and r7 . Regional employees, for 1990 through 1997. Please include overtime and compensatory time. .
i',.7,,l;',.s'J' in addition, please provide the hours and FTE expended for.PA Numbers 232BA,232BAA
,NW '. ll232BAB,' 232BAC, which are not already included in the data for the facilities on the attached 73
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list. lri order to meet our Divisto deadline, I am requesting that you provide this information y;l.w ::.17,1997, (,: u' , s
.q@f I.T':AttschinentPAs
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Contact:
Dominick Orlando, DWM/NMSS
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TICKET:': N9700239 .(Do,not, elose) ~ k l\ DISTRIBUTION: Central lEile? .i.LDPr/f .NMSS r/f RJohnson gg
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.%5 " ' MEMORANDUM To: Claudia A. Seelig. Chief A l j
hb.b.'@ W' '. ,... ;Program Program Analysis Branch
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Management, Policy Development (
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g/s.a;.'i . ** .
.'and Analysis Staff, NMSS . . l
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SUBJECT:
' . . . DATA FOR FUTURE EiUDG'~TS . {
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b #9 d.. ":insummarizes Dr. Paperiello's. memorandum.the SDMP sitesin obtaining that have
..s.. . . . . . . .
mentioned We are requesting your assistance n . w, < * :? r. c.e .. e.: : ,. , . ... .: v wa . .
,h.#fil9 f 9 n,j$; g.tlie. informationo . < w w :< w requested of these facilities, by brokenDr. out byPaperiello. '. Pleas
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.; e total hours and FTE' expended for each NRC Headquarters and
! . '),hk.hR4gional[e'rdi'ohbes,
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Which are not already included in the data for the facilities on tne attached { f'4 232BAB,232.BJ n..
, gh. ofd $[.. > . . , list"In ofds.r toi.
. d DMslon deadline, I am requesting that you provide this information by l 4 e 4,o , . o' October.:17, .1997, ;
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Attachment:
As stated
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Contact:
Dominick Orlando, DWM/NMSS
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