IA-98-127, Requests That J Decicco Meet W/S Moore Re FOIA Request on Ams.Listed Info Should Be Addressed
| ML20248L483 | |
| Person / Time | |
|---|---|
| Issue date: | 10/20/1997 |
| From: | Scott Moore NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Decicco J NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| Shared Package | |
| ML20248L474 | List: |
| References | |
| FOIA-98-127 NUDOCS 9806110183 | |
| Download: ML20248L483 (43) | |
Text
{{#Wiki_filter:- _- _ _ - _ _ - - _ _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ 1 . i From: To: Scott Moore f[/ 'i, ~bdC CC D fj g ll,g JXD1 Date: 10/20' 97 3 : 50pm
Subject:
FOIA REQUEST RE: AMS
)
Joe, Please see me re: FOIA request on AMS (in your mailbox). It got sent to RIII and us for a time estimate. RIII's concerned about it .... they thought that l FOIA had been going to try to get the request rescinded, because the fee might not be waived. I told Roy that we (you) would look into it tomorrow, and find l out why we have the request for time estimate. Please get with Mr. Powell tomorrow, and find out:
- 1. Was the fee waived for the requestor? -
N8 l 2. . Did FOIA talk to M.e requestor?g ,W hat was the subject and outcome of those ! discussions? .sr, .- </4. 4 4 4 7' -
- 3. Why was the time estimate sent on to staff (us and RIII) for a reply? . [ ,,..t/ /S.*<M Especially if the FOIA might be dropped? * %.,
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Did FOIA Br. discuss with the requestor NRC's thoughts about trying to 4.
'j make available a list of AMS documents at a public library? With regular i l updates? /';, ,4 ! .., m'wfA 6 m l % ) z as .e ed ft;. ; La
- 5. Did FOIA Br. tell the requestor how many documents are in PDR re: AMS, or send them the list, that may statisfy the requestor's concerns? - A4, o'p. .
A d r-v a-A 5 An. t, u , .. L, u t. ,,L t Thanks for the followup. I told Roy that we would get back to him or John tomorrow, or first thing Wednesday. Once you get answers, you and I can call them back together. Scott I CC: JMP1 i
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P/'// 9 7 m margo n , for error Area residents remain concerned 1 . aboutpotential hazards at AMS 11 11RWE.1.YN , 3) egg' hood of such an acci-dont fa slim. However, thn broblem. l An environmental consultant secording to Cornett. Is nobody I and area citizens havejoined to un. known what would happen in such cover dangers lurking behind *a!!s an avant. He maid atudian Inava en. at Advanced Medical Systems,1000 vironmentalistswanting. London Road. " Credible studiet of plaunihis cat.
. Th3 Collinwood Environmental astrophic relgaets (of cobalt) . . .
Task Force is the brainchild of are needed," Cornett said. "There
.Chesterland resident Larry Cor. is enough of a possibilityfora prob.
nett owner of an environmental lem thatwe need to get the facts " consultingfirm. Hewas hired by an In particular. Cornett ia con-anonymous area businessman wito corned about long term radiation is interested in expanding near the from an accident. Studies he has AMS fact!!ty. The businessman viewed show "that a mNor rs! esse needs Cornett to reveal whether or (cobalt) might render portions of not AMs is detrimental to luture the collinwood area uninhabitable, g development. und people m!ght die if fallou: were . Cornett conducted background not decontaminated. One of our i research into AMS a company that concerns is do they (omelats) even g ones produced cobalt 60 for X ray havco recponsoplanforfollout." g
' machines. His research states that Ccrnett miso said advanced warr.- t 1
in 1907 radioactive cobalt Oo Icaked ingis needed for surrounding prop-into a ecwor. It took 31.5 million to erties. clean up the mees. " Appropriate mosaures are The mess, however. wae not erad- needed to reduce or eliminate icated in the e>es of many peeple, risk," he sold. " Audible alarms . ' Th:re in attu a tnom at AMS be. (ahoult!) be provided within innes I% Q, 5d JIG ,
= Q ' { ,:E Dh[E$
1: lieved to be dangerous. The room vulnerable to significant danger was entombed Years ano because from plausible (silout. Residents E gI - )$,sNS .E gl ! 5 g g ,1i Y I"E radioactive material could not be and businesses should be tralned E] 8* j # h.]
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removed. De whole situstien dis- en how torespond." ' C8 hlg*. .E$ 1" E pleans Ward 10 Councilman Roose-7elt Coats. The Collinwood & Nottingham Vitagee Development Corp. invited - 1 'They need to do a cleanup and Cornett to a November meeting.
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92 jh -1 E{ # s T-they need to seal that vrhole place During the visit, members of the or- E" i 5
. 'off." Coats said, gan!!adon expressed a destre for Tntn tmme around AMs con. more information concerning the j si) 15 h
2l S 2u .f h,g t e:rns Wed 11 Councilman Michael AMS site. About 20 people agreed to y}j$ $$j=~l ,glpg E
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E Polensek. Ele said twice as many form a task force for further invee-
.Ar*_ ins could be using tracks next to4 tigation. .s T ] [. J.6ig g
.tho ftollityin the neer future. Cornett aald an objective of the [' !" 7 "There is a whole leaue with de- task fores is to observe a Jan. 29 railment."he said, emergency drillat the AMS plant. j r
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Polensek's fear is a train will pop "The Jan. 29 exetelse should in- .E k N g,
,pff the tracks. crash through AMS's clude use o(instruments to screen fMII. rupture the entombed room See ERROst. page A3
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i THE PLAIN DEALER SATURDAY,F m.
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Radioact.. .ivi leve. ls~near . pliilt are s e, NRC says NRC como out tien is when we aramenor.s NEIGHBORHOOD IS
""'"'""' "I' * *** *""5' CONTAMINATION. FREE .
The ne(shb6:tood amund the For k dozen years ending in
) old Advanced Medical Systems %7 1991, Advanced Medical Systems
! 'Inc. plant in Oeveland remains v
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D, pacessed histdy radioactive frwo of radioactive contamination F cobalt 60 into saaled elements for hun the troubled firm's handling . radiaHan-tharepy devices at its
! of toxic cobalt 60, nocording to , site at 1060 London Rd. Much of Doh i fedmiresulators. '
p the plant is contaminated with isn't e-In r@ase to concernA Need
.militags of the matenal, cf Which ph. I l i Coun eel b$s of th fe r
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f! A" Sd s " ?a #n'a"d ?t s and local Investigators inspected
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g- M P, N Y M' ' ' " in poem nomes, a park and an industrial i Loension former o In 1991, the Northeast ohto Re. the ws;
" sits in December and enounced H gm i
*% giona1 Sewer DLrtrict traced radi- Th088 8 4 tha results this week- evetens atno cactive contamination.in sewer [* 18D Investigators found no radioac, O I facMas to the lantand accused kd f the NRC of she dy oversight. The ,g3y g tivity m1,ove normallevela cutside 3
/ p met am! Advancd Mal ever-fr
, the company's fenced lot, the y settled their differences in Do' asthey NRC said.Cne spot along a fence ptn l
hv twi as e readings t aver-out the
% ng o me 25 for A j Ikm of the district's costs for de- Streets neighborhood but well below the
' FtAg m ats: conWaHng the M erly Thud level NRCcopoldets safo. Wastawater Treatment Plant and Love r in at Advanced brsry "At this point, we do not feel - IIoly meeting Redeernerat School,1572 7 p.'m. Thursda[Ki- e . .gug. sewers
- f. Doing them ts aDy risk to the residenb pilng Ave.. Cleveland. *I'he NRC got help uith na De. *** h' CI'8I[c," sam Angek a spo aswornan for ga, -
Councilman Michael Polensak said be wun unwpg thoeo whoDepamnent had osmberofinspection Ecalth andfrom au$sn the theMcL Chio gion m o ca in Lisle, nl., a Chi- urged the NRC to study the area. Ceveland nre Department. It . his poe cap su .
"rhat rect 11ty is of grnt con. was the third special investiga. before The agency wi!1 discuss its in- corn to the area,in most cassa be. tion of the ama. Studies in 1985 time."
epection findinen and field ques. cause of fear of the unknown." and 1993 found no cobalt on the tions from neighbors at a public Potensak said. The only time the plant's preparty. , Museum won't give up Balto ' 1, Clown
> BALTO riou .e __ ' ,
,, Q bre it l *Actually, be really sort of be. M N ONto's NtlDg phCC drw a fhIrry of
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v f (4) chemicalaninhy_skal form and the geo- ,Q l' metrical shape of the radioactive _ mate- cific performance requirements (classification rial; numbers). (5) environment in which it is used; and (6) protection afforded the source or source- (i. device combination. Identification 4.3 lladiotoxicity and Solubility. Except as re- The designation according to section 3 shall quired in Section 4.2 radiotoxicity of the radi-onuclide shall be considered only when the be marked on the sealed source or source con-tainer or source holder or accompanying docu-activity of the sealed source exceeds the value ment, shown in Table 3. If the activity exceeds this value, the specifications of the scarce must be considered on an individual basis. If the activity 7. Testing Procedures for Table 1 does not exceed the values shown in Table 3, Table 4 may be used without further consider- .
.I General. "The testing procedures given in .
ation of either radiotoxicity or solubility. this section present acceptable procedures for determining performance classification num-
- 5. Procedure To Establish Classificationbers. All the test environments provide the and Performance Requirements minimum requirements. Procedures which can be demonstrated to be at least equivalent are 5.1. Establish radiotoxicity group from Table 2. also acceptable. All tests, except the temper-ature tests, shall be carried out at ambient tem-5.2 Determine amount of activity allowable perature.
from Table 3. 7.2 Temperature Test ' 5.3 If the desired quantity does not exceed the I allowable quantity of Table 3, an evaluation of 7.2.1 Equipment. The heating or cooling fire, explosion, and corrosion probabilities shall equipment shall have a test zone volume of at be made. If no significant probability with re- least five times the volume of the test specimen. spect to fire, explosion, and corrosion exists, the If a gas or oil-fired furnace is used for the tem-required classification for the source (per- perature test, an oxidizing atmosphere shall be formance requirements) may be taken directly maintained throughout the test. from Table A. If a significant probability does 7.2.2 Procedure. All tests shall be performed exist, the factors listed in 4.2 shall be evaluated in air except in the low temperature test, when with particular attention to the temperature and impact requirements. an atmosphere of carbon dioxide is permitted. All test sources shall be held at the maximum 5.4 If the desired quantity exceeds the allow" (or minimum, for low temperature tests) test able quantity of Table 3, an evaluation of fire, temperature for a period of at least I h. explosion or corrosion probability and a sep- Although Table 1 specifies a low temperature arate evaluation of the specific source usage of -40'C, " dry ice" may be used as the cooling and source design shall be made. material. Thus, the low temperature may ap-proach -75'C. 5.5 After the required classification of the Sources to be subjected to temperatures be-source for the particular application or usage has been established, the performance test con. low ambient shall be cooled to the test temper-ature in less than 45 minutes. ditions can be obtained directly from Table 1. Sources to be enbjectad to temperature above 5.6 Alternatively, the source may be tested, the ambient shall be heated to the test temperature source Class determined from Table 1, and some at least as rapidly as indicated by the follow-suitable application selected from Table 4. ing time-temperature table. Sources of an established classification may be used in any application having less severe ape- ' Part of ,this test for Class 6 is similar in principle f to the heatmg test given in IAEA regulations for the safe transport of radioactive rnaterials.
/
Time Temperature 7.4 Impact Test 8 min 'C 7.4.1 Equipment j amg9 nt This comprises: n y @ (1) A free falling steel hammer which has j 60 750 a flat striking surface,25 mm in diameter with 120 1010 4 the edge rounded to a radius of 3 mm. The cen-ter of gravity of the hammer lies on the axis of For Classes 4,5 and 6, test sources shall also the circle which defines the striking surface, be subjected to a thermal shock test. Either a (2) A steel anvil, the mass of which is at second test source or the source used in the least ten times that of the hammer. It is rigidly temperature test may be used. If the latter is mounted so that it does not deflect during im-used, it shall be evaluated for passage of the pact. It has a flat surface, Inrge enough to take temperature test before it is subjected to the the whole of the source. thermal shock test, (3) For the Class 2 drop test, the steel For the thermal shock test, the source shall plate shall be rigidly mounted so that it will not be heated to the maximum test temperature deflect appreciably during the test. (required for that particular Class) and held at that temperature for at least 15 minutes. 7.4.2 Procedure. Choose the mass of the ham-mer according to the mass specified in Table 1. The test-source shall be transferred, in 15 see-Adjust the drop height to 1 m measured be-onds or less, to water at a maximum temper- tween the top of the source positioned on the ature of 20*C The water shall be flowing at a anvil and the base of the hammer in the release rate of at least ten times the source volume per position. minute, or, if the water is stationary, it shall have a volume of at least twenty times the Position the source so that it offers its most vulnerable area to the hammer. source volume. Drop the hammer onto the source. 7.2.3 Evaluation. Test sources shall be ex- 7.4.3 Drop Test. For the Class 2 drop test, amined visually and subjected to an appr - the test sources shall be dropped so that all priate integrity test such as that described in surfaces are impacted at least once. Appendix A. 7.1.4 Evaluation. Test sources shall be ex-7.3 External Pressure Test amined visually and subjected to an appropriate
; 7.3.1 Equipment. The pressure gauge shall integrity test such as that described in Appen-have been recently calibrated and should have dix A.
a pressure range of at least 10% greater than 7.5 Vibration Test the test pressure. The vacuum gauge must read to a pressure at least as low as 20 kN/m2 ab. 7.5.1 Equipment. A vibrating machine cap-able of producing the specified test conditions. t solute. Different test chambers may be used for the low and high pressure tests. 7.5.2 Procedure. Fix the source securely to i the platform of the vibrating machine so that o 7.3.2 Procedure. Place the test source in the j chamber and expose it to the test pressure for at all times the source will be rigidly in contact with the platform. a two periods of 5 minutes each Return the pres-ft sure to atmospheric between each period. Con- For Classes 2 and 3, subject the source to the duct the low pressure test m air. For the h!gh three complete test cycles for each condition 9 specified. Conduct the test by sweeping through pressure test only water shall be used. all the frequencies m the range at a um. form 7.3.3 Evaluation. Test sources shall be ex- rate from the minimum frequency to the maxi-amined visually and subjected to an appropriate
> Integrity test such as that described in Appen. 'This test is similar in principle to the percussion dix A- tnt ginn jn IAEA, regulations for the safe transport of radioactive materials.
5
mum frequency and return to the minimum fre-quency in 10 minutes, or longer. Test each axis 8 (a)free hardness (b) height 6 from mm; 50 to 60 Rockwell ' C-of the source. A taximum of three axes shall (c) diameter 3 mm; , be used. In addition, continue the test for 30 minutes at each resonance frequency found. (d) lower surface hemispherical. For Class 4, subject the source to three com' The center line of the pin is in alignment ' plete test cycles for each condition specified. with the center of gravity and with the point Conduct the test by sweeping through all the of attachment of the hammer. frequencies in the range at a uniform rate from (2) A hardened steel anvil, rigidly the minimum frequency and return to the mini- { mum frequency in 30 minutes, or longer. Test mounted and with a mass at least ten times each axis 2 that of the hammer. The contact surface be-of the source. A maximum of three tween the source and the anvil is large enough j axes shall be used. In addition, continue the test to prevent deformation of this surface when for 30 minutes at each resonance frequency impact takes place. If necessary, a cradle of f una. suitable form may be interposed between the source and the anvil. 7.5.3 Evaluation. Test sources shall be ex-amined visually and subjected to an appropriate 7.6.2 Procedure. Choose the mass of the ham-integrity test such as described in Appendix A. mer and pin according to the Class as required in Table 1. 7.6 Puncture Test Adjust the drop height to 1 m measured be-7.6.1 Equipment tween the top of the source positioned on the This comprises: anvil and the point of the pin in the release E* "' (1) A hammer, the upper part of which is Position the source so that it offers its most equipped with means of attachment and the vulnerable area to the pin. lower part of which has a pin rigidly fixed to Drop the hammer onto the source. 1 the hammer. The characteristics of this pin are If the source has more than one vulnerable T ' as follows: area, carry o;t the test on each of them. If the dimensions and mass of the source con-cerned do not permit unguided fall, lead the striker to the impact point in a smooth verti-caltube.
"*A ' spherical source has one axis taken at random.
two ax$s: Ne o*f re$o*utYon ndti " $ h 8taS*E7.6.3 Evaluation. The test sources shall be random examined visually and subjected to an appro-in a plane pe pendicular to the axis of revolution. Other sources significant overall dimensions. ave three axes taken parallelpriate to the integrity test such as that described in gppendix A. l 1 1 l $* ) 6
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r (* TABLE 3-Activity Level
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Radionuclides group (from Table 2) Leachable ' Non leachable ' and/or reactive
- and non-reactive '
A O.3 3 hC 30 100 500 300 3000 5000
- Leachable-greater than 0.3 millire arn per giam 6n 100 mi still Jf 0 at 20*C in 48 h.
8 Non.leachable--less than 0.1 milligram per gram in 100 mi atill fisO at 20*C in 48 h. e g,,et;,, reactive in ordinary atmosphere er water (Na, K, U. Ca. metals etc.L T Non-reactive in ordinary atmosphere or water ( AL Au, Co Kr. Ceramica. etc.b Note-In the empiession " milligram per g ra m" the " milligram" refers to th r dissolved or temoved radionuclides, and the "g ra m"
- to the total weight of radioactive material present, not including th'* weight of the capsule.
TAnte 4-Sealed Source Performance Requirements for Typical Usage s Scaled Source Test and Class Sealed Source Uzage Tempe ra- Pres. Vibra- Punc-q% Impact ture sure tion ture Radiography-Ind atrial Unprotected source 4 3 5 1 5 Source in device 4 3 3 1 3 Medical Radiography 3 2 2 Gamma teletherapy 5 3 Gamma gauges (medium and Unprotected source 4 3 3 3 3 high energy) Sourec in device 4 3 2 3 2 Beta gauges and sources for low energy gamma gauges 3 3 2 2 2 or X Ray fluorescence analysis (excluding gas filled sources) Oil Well logging 5 6 5 2 2 Portable moisture and density gauge (including hand held 4 3 3 3 3 1 or dolly traraported) General neutron source application (excluding reactor 4 3 3 2 3 I start-up) l
, Calibration sources-Activity greater than 30 pCi 2 2 2 1 2 Gamma Irradiators ' Categories II, III,1Y 4 3 4 2 4 f., ~ ~ ~ ~ ~
Category I T T T 2 3 i' lon generators ' Chromatography 3 2 2 1 1 (' Static Eliminators 2 2 2 2 2 Smoke Detectors 3 2 2 2 2 e Source-deelee combination may tse tested.
- 1'or the purposes of thia Standard, gamma irradiators have been divided into four distinct categories.
Category I 4 elf-Contained-Dry Source Storare. Category 11 -Panoramic-Dry Source Storage. Category III-Self-Contained-Wet Sourea Storare. Catesory IV-Panoramne-Wet Sou rce Storare. I s 9
L- . L3
*O Yes I did. .
The source is a sealed teletherapy source, and they use it to do on/off radiation leakage tests for teletherapy heads. It is a Model 3802. and in December 1996, it was calibrated for 1200 curies. It is two (2) centimeters long. It'i.s stored presently in the Isotope Shop. (I think it is the same floor as the Hot Cell, the floor above the basement). The source is in a Picker source transfer cask, model 181361, and is suitable for transport to meet DOT regulations. As for the . inspection to verify the inventory.. a firm date has not been established. but MWeber is hopeing to do it in July 1997. That's about it. 1 l t i ___ ._ _ - - - - _ -__ a
p (. LETTER FROM SENATOR GLENN REGARDING ADVANCED MEDICAL SYSTEMS Mr. Beach asked his staff for information on this Congressional letter for today's EDO briefing. They are preparing bullets for Mr. Beach, but said that he would probably not raise the issue during the briefing. INCOMING Senator John Glenn, OH, forwarded a constituent letter to Dennis Rathbun on 10/21/97. The constituent's letter included a FOIA request for NRC, and expressed specific concerns about AMS. Senator Glenn's cover letter just asked NRC to look into the situation as soon as possible and respond to his district office. The Senator did not express any specific concerns, himself. The constituent is Florence Feinberg, on behalf of the Collinwood Village Association in Cleveland, OH. Her FOIA request is 4 pages long and requests large amounts of information on AMS. On the same date that she wrote Senator Glenn (9/29/97), Ms. Feinberg also wrote John Madera, Rlli, a nearly identical letter. When the FOIA/LPDR Branch received the FOIA, they denied Ms. Feinberg's request for a fee waiver, because she did not meet the criteria for a waiver. They forwarded her a list of all AMS documents (hundreds) already publicly available through the public document room. Yesterday, Ms. Feinberg withdrew her FOIA, because Senator Glenn would be getting back to her. Ms. Feinberg's specific concerns, outside the large FOIA request, relate to l NRC not releasing factual information to calm fears; what would happen to the ' contamination in the building if "there's a catastrophe;" and emergency planning and residents' response actions to an emergency. Ms. Feinberg reported that the Collinwood Village Association has contacted a waste management /remediation consultant, Mr. Harry Cornelt, to assist their l
" quest for some data."
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9 In her letter to JMadera, Rlll, Ms. Feinberg noted that the Association had also been in contact with Congressman Stokes and Mayor White.
RESPONSE
IMNS/IMOB had already contacted FOIA/LPDR about the possibility of setting up an LPDR near the AMS site. FOIA/LPDR preferred to provide a listing of hur;dreds of publicly available documents to a local public library and update the listing regularly. Citizens'could select documents from the listing, call NRC's main PDR here, in Washington, D.C., and receive the documents just for the cost of reproduction. A local PDR (essentially, a public access NUDOCS station) already exists at Perry Nuclear Power Plant, within 25 miles of the City of Cleveland.
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The ticket is currently due to NMSS on 11/4/97, and due to EDO on 11/7/97. The key contacts in FOIA/LPDR have been out of the office until this morning. We have been in close contact with Cathy Poland on this. We intend to request a 2-week extension from Blaha on the Congressional response, to allow us to coordinate further with FOIA/LPDR and get the listing of AMS documents to a local public library. We are planning to respond to the Congressional letter by addressing that the FOIA has been withdrawn, and discussing what NRC has done to be { responsive to the City and local citizens' requests. We want to say that we sent a listing of hundreds of AMS documents to a local pubiic library, and they are easily obtained through the PDR. We will also briefly discuss NRC's actions in oversight of AMS. The response should be fairly short: 1-1.5 pages. Next Thursday,11/6/97, IMNS/ Rill /DWM/FOIA/LPDRIOCA/OPA will hold a
" summit meeting" here, at Headquarters, to discuss actions regarding
. AMS, including the strategy plan, AMS' ren.ponse to the DFI, and the City ,
of Cleveland's concerns. ! l l
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T START o in the inspection report, you will see tables and references to the term ! millirem, or millirem per hour, sometimes abbreviated "m" rem or "m" rem per hour. [1st DIAGRAM] The term millirem is a measure to I express the effect of the amount of radiation, similar to measuring in L ' millimeter for distance or milliliters for quantity. The term millirem is , reserved for radiation. I
-[2nd DIAGRAM] The report indicates that the typical background radiation in this area of Cleveland is between 0.010 and 0.015 millirem l per hour. This background radiation co,nsists of naturally occurring L
radioactive material in soil and earth % osmic radiation, and r;atura"y occurring 4adioactive-materia! deposited la-the body. This is similar to
.the background where I live in Maryland. So if you were sitting in your
! back yard enjoying the weather, the natural background radiation from outer space and from naturally radioactive material in the ground would L deliver an amount of radiation of 0.010 to 0.015 millirem in an hour. Someone living here for 24 hours a day, for 365 day a year would L receive between 85 and 130 millirem over the course of that year. This amount of radiation is received in the course of everyday living as natural background. To give you an idea of how this 85 to 130 millirem is in relation to other sources of radiation around us, I have a diagram [3rd DIAGRAM] that
2 gives examples of other sources and levels of millirem doses. Keep in the back of your mind that we all receive somewhere between 85 and 130 millirem a yearjust from natural background from the ground and from cosmic radiation. And remember that the numbers on the this chart are average numbers and may vary a little depending on the circumstances. Starting on the left side of the diagram, there are example of medical x-ray for the arm or the chest (1 millirem and 6 millirem). On this first column you can see that taking a Trans-Atlantic flight, about the distance to the west coast and back, will give a dose of about 3 millirem. That is because at that altitude of plane flight, there is less atmosphere to protect you from cosmic radiation. Looking at the second column, you can see that the average annual medical examinations will add about 55 millirem every year. At the top of the second column you can see the annuallimit for the public. We are required to make sure that when we allow organizations to use radioactive material, that members of the public will not receive more than 100 millirem above natural background from that organization. However, most members of the public do not receive nearly that much from radioactive material users because we ask them to use the material so that the doses are as low as reasonably achievable and as low as possible to their workers and the public.
, I 3
In the third column, you can see that there is an indication that the average annual dose from natural background is somewhere around 360 millirem. But the reading we took indicated 0.010 to 0.015 millirem i per hour that gave 85 to 130 millirem a year for this area. Why the i difference? That is because our meters could not pick up the dose you ' receive from inhaling radon. On the average, members of the public receive about 200 millirem dose just from the natural radon they inhale, which comes from the ground. Add this 200 millirem to the 85 to 130 millirem, and you can see that the dose you and I receive every year is from natural background is around 360 millirem.
.To continue up the scale of radiation dose, in this [4th DIAGRAM]
. remember that these dose are above background radiation. This
' diagram indicates that the occupational limit is 5000 millirem in a year.
That means that people who work with radioactive material at AMS, or even myself, could legally receive 5000 millirem in a year. If you l remember, this is 50 times higher than you are allowed to receive, i
- unless you, too, work with radioactive material in some way. Why the
[' i difference between the public limit and a radiation worker. The ! ' radiation worker accepts the slight increase in risk working around radiation, just like a chemical work or a sky-scraper worker accepts , increased risk in their environment. At 10,000 millirem, you might increase your chance of getting cancer to 1 in 130. As you go up the column,' you can see that radiation effects that are noticeable or -
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identifiable from radiation do not occur until you get around 50,000 millirem in a very short period time, like hours of days. If you spread this 50,000 millirem over years or a lifetime, you would not see these effects. On the right hand column, you can see that effects become more dramatic, like death, that occur at the very large quantities of radiation. These type of doses are not seen except in severe accidents, like what occurred at Chernobyl, where several individuals died because the dose they received were very high. This last diagram [5th DIAGRAM] gives is a quick summary of doses,
.and some indication of risk associated with everyday occurrences. You can see that 360 millirem is a typical annual dose from background, including radon; it's what we receive from just living on this planet.
There are some other typical doses that are received from other activities. The bottom half of this diagram lists some activities that j have a risk a ssociated with them. As you can see, in the aspect of life lost due to these activities, receiving a dose of 360 millirem above the i 360 millirem from background would decrease life expectancy about 18 days; life expectancy lost from smoking or being overweight is q indicated in years. ! l i in conclusion, when reading the report, remember that you are '
5 receiving about 360. millirem a year from natural background, and that ge t the limit that you allowed to receive from AMS in 100 millirem a year above this background, although the dose actually received is much less than 100 mrem because of the idea of as low as reasonably acheievable. END
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f Larry.Comett's concems include the following:
- 1) emergency preparedness for re! ease of fallout caused by train derailment, terrorists using zirconium thermite (what is that?) to vaporize sealed sources, etc.
INFO: Thermite is a compound that mixes " rust" with metallic filings or powder, and when ignited, bums at a very high temperature (iron thermite or aluminum thermite; could not find zirconium thermite). Sometimes used in high school or college chemistry classes as a demonstration!! However, ignition of the thermite need vey high temperature, such as igniting a magnesium ribton with a blow-torch, which could supply enough heat for igniting thermite. Regardless of the method ofignition, the postulated dose from dispersion occurs when the fire bums. This "therrnite" scenario would "possibly" get to the source inside its shielded container, exposing the source to the fire which would disperse some of the exposed source; this is high unlikely (improbable) and the dispersion factor of 0.001 would still be applies. The methodology used for rulemaking considered two points of view: (1) the accident history of fuel cycle and by-product materials; and (2) theoretical calculations of the release and off-site doses of an accident considered to be possible. (the question always arises about trying to create regulations that preclude deliberate acts to violate the regulations; its a never-ending vicious cycle) History of accidents involving by-product , source, special nuclear material, and spent fuel storage, indicate no evidence that an accidental release of radioactive material ever cause even 1% of the EPA's 1 rem protective action guide (accidents surveyed for years 1950 to 1980). The NRC considers a number of possible accidents, requires applicants to evaluate possible accidents, and performs it own analysis of severe accidents to determine whether there is adequate protection of public health and safety. The significant accident were determined to UF8 release, criticality accidents, and fires. For AMS, the fire scenario is used, and the release fractions for fires were larger than other types of I accidents and are used for determining the need for emergency preparedness.
- 2) probability of train derailment - what is the actual probability- he said utilities calculate things like that i do not have the probability of a train derailment, and the adequacy of emergency preparedness is based on a possible accident (i.e., a fire) regardless of the cause of the fire. Train derailment probabilities are most likely (probably) available from a railroad association.
I I _3) inadequate security (in and out of building) 1 1 1 i l
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- 5
- 4) 100 mrem /yr limit - he ciaims this corresponds to a 1% cancer risk, and 1 mrem / year corresponds to a 0.1% risk 4
Risk of fatal cancer- 4 X 10 per rem of exposure (derived from high dose (>50 rem)) 4 4 X 10 cancer death / rem X 0.1 rem / year X 70 years (life expectancy) = 0.0028 cancer deaths or 28 cancers deaths per 10' people Normal cancer deaths is 2000 in 104 people (20 %) Therefore an increase from 2000 to 2028 is about 1% increase (1.4% exactly) However if 0.1 rem / year is 1% increase, 0.01 rem / year would be a .1% increase, and 0.001 rem / year would be a 0.01% increase. I'm not sure what the point of 4)is. Does he wish to decrease the cancer deaths by 28 per year to 0.28 per year? We are then talking about policy on acceptable limits, and rulemaking. Our contention is that 100 mrem per year is a design limit; with ALARA, the population is not receiving 100 mrem per year but something less than that. With low dose and low dose rate, we are not even sure that the cancers are caused by the radiation, or that it would reduce the cancer incidents due to the exposure.
- 5) all NRC licenses in Ohio should not be renewed until proper emergency plans are in place (again, fallout issue with zirconium thermite, etc.)
For all licensees, the question is agt whether they should have any emergency preparedness. The NRC has long required licensees to take steps to reduce the likelihood of serious accidents to a minimallevel, and be prepared to cope with emergencies. It is a question of whether NRC should formally require in regulations formal written state and local govemment plans for coping with serious radiation accidents. The question is not whether State and local govemments should have emergency preparedness capabilities for dealing with radiation accidents. Police and departments, state radiological health departments and other agencies routinely prepare to cope with emergencies that exist. , j The rule for emergency preparedness is intended to assure that there are emergen3;b procedures for mitigating and coping with offsite releases. The requirement is the' require the licensee to be prepared to take practical steps that could, in favorable conditions, reduce the exposure to the public. Even the EPA protection action guidelines indicate that action should be taken to lower I the exposure if the exposure would be likely to exceed 1 rem.
- 6) Exposure from sealed sources inside the AMS facility - especially if AMS brings many sources into the facility in the future I
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e panov p* 4 UNITED STATES
$ r alarms in ne g or oc -g c r plants - in case of s, .
*****/ The licensee has the responsibility to prevent serious accidents, and should that fail, the responsibility for protecting the public near the facility is considered to belong to offsite public safety authority (i.e., the fire department in case of a fire at AMS). This authority would then be expected to notify the public in a manner similar to what is done for truck or rail accidents involving hazardous chemicals.
Most of the exposure from dispersion will occur until the fire is controlled, which will be within a short period of tirne (half hour or so). A waming system would not be provide that much additional time that a notification by the public safety authority could not provide.
- 8) AMS should fully cooperate w/ all local agencies, and alllocal agencies should be allowed to perform unannounced inspections at AMS.
Complying with NRC requirements does not preclude compliance with any other Federal, State, or local requires.
- 9) Inadequate enforcement by NRC - example - $5000 fine to Cleveland Clinic for buming rad waste (??)
The person I talked with in Office of Enforcement indicated that the Cleveland Clinic was fined in December,1996 (they paid in January 1997) a sum of $5000 for deliberate violation of their license (due to limited assets) such as foregoing training, etc. (low risk activities by themselves). The individual I talked with was involved with the case, and does not remember in relating to radioactive waste buming. Not sure what he wants.
- 10) Risk caused to members of the public- he wants numbers per pCi of cobalt-60 ingested, etc.
Dose conversion factor- 220 mrem (TEDE)/microcures inhaled from cobalt- 60 ) or 0.000220 mrem / picocurie inhaled , 27 mrem (TEDE)/ microcurie ingested from cobalt-60 or 0.000027 mrem / picocurie ingested After the dose is calculated, use the risk factor per rem to calutate risk. I l i i __ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ - - - . . - - - - - - - - - - - - - - - - - - - - - - ^
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i 3.m : 4 V f , T **> +4 ? ) .g leor Regulatory Cornmission 92.1201 [ t the presiding officer shall also dismiss lution in an adjudicatory hearing are he proceeding. Interlocutory and must await the end (b) No issue of law or fact shall be of the proceeding, 6algnated for resolution in an adju- 4
' ory hearing unlus the prealding 150 FR 41671, Oct 15,1985, 50 FR 45398. Oct. 31. j fricer determines that: IN '
- 11) There is a genuine and substantial pute of fact which can only be re- i 2,1117 Applicability of other sections, ',
tved with sufficient accuracy by the In proceedings subject to this sub-troduction of evidence in an adju- part, the provisions of subparts A and ]4 Icatory hearing; and G of 10 CFR part 2 are also applicable, b (2)The decision of the Commission is except where inconsistent with the pro- I ely to depend in whole or in part on visions of this subpart. ! b resolution of that dispute. l (c)In rnaking graph a determination (b) of this under Subpart L-informal Hearing Pfo-ecction, the pre' siding officer shall not consider: cedures for AdjudicOtlons in 4 J1) Any issue relating to the design, MOterials Ond Operator Li- I f construction, or operation of any civil- censing Proceedings ; lan nuclear power reactor already 11- ! censed to operate at the siti . or any ci, Mmcr 54 Fit 82"6, Feb. 28,1989, unless , illan nuclear power reactor for which therwino noted. construction permit has been granted 52.1201 Scope of subpart. f, the site, unless the presiding officer determines that any such issue sub. (a) The general rules of this subpart 8 tantially affects the design, construe. govern procedure in any adjudication ! tlon, or operation of the facility or ac. Initiated by a request for a hearing in f livity for which a license application, a proceeding for- e authorization, or amendment to ex- (1) The grant, transfer, renewal, or 11-nd the spent nuclear fuel storage ra- censee-initiated amendment of a mate-ity is being considered; or rials license subject to parts 30, 32
- 2) Any siting or design issue fully through 35, 39, 40, or 70 of this chapter; idered and decided by the Commis- or '
on in connection with the issuance of (2) The grant, renewal, or licensee-
. construction permit or operating li- Initiated amendment of an optrator or '
nae for a civilian nuclear power reac- senior operator license subject to part ' at that site, un1ess (1) such issue re- 55 of this chapter.
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I to from any revision of siting or de- d criteria by the Commission follow- cense (3) The amendment of a Part 50 li-following permanent removal of d such decision; and (11) the presiding cer determines that such issue sub-fuel from the Part 50 facility to an au- S tially affects the design, construc- thorized facility for licensees that have Y' n, or operation of the facility or ac- previously made declarations related y for which a license application, tog permanent cessation of operations g g 7g [ o zation, or amendment to ex-d the spent nuclear fuel storage ra- 6 e e ity is being considered. 6 50.82(aMI). Subpart L hearings for the d) The provisions of paragraph (c) of license termination plan amendment, ; 3 section shall apply only with re. if conducted, must be completed before et to licenses, authorizations, or license term nation. Lendments to licenses or authoriza. (b) Any adjudication regarding, (1) a na applied for under the Atomic En. materials license subject to parts 30,32 Act of 1954, as amended, before through 35, 39, 40, or 70, or an operator mber 31, 2005. or senior operator license subject to
) Unless the presiding officer dis- part 55 that is initiated by a notice of a of all issues and dismisses the hearing issued under $2.104, or (2) a no-eeding, appeals from the presiding tice of proposed action under $2105, or cer's order disposing of issues and a request for hearing under subpart B gnating one or more lesues for reso of 10 CFR part 2 on an order or a civil 117
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May 15.1997 SBfd "The staff should proceed forthwith to require AMS to promptly comply with the license condition requiring remediation of a portion of the London Road interceptor line " License condition 19.F.
"Remediate the London Road Interceptor in the vicinity of the abandoned lateral, as described in letter dated January 27,1995. The remediation activities will be coordinated with the Northeast Ohio Regional Sewer District."
January 27.1995 AMS letter
" Included as part of the remedial action is decontamination of the NORSD interceptor in the vicinity of the abandoned AMS lateral to the levels recommended in NRC Regulatory Guide 1.86."
QFl ooints and resoonses 1.a. Describe the indemnification / hold harmless issue - NEORSD would not permit AMS entry without signed indemnification on file and AMS felt it could not sign it for " obvious legal reasons." 1.b. Describe other issues preventing remediation progress -If no entry authorized, no evaluation available to create a plan or eventually implement one. If no entry authorized, then no way to implement a plan. 1.c. Provide list of correspondence - Much of the communication between AMS and NEORSD was verbal with Dwight Miller. Mr Miller passed away in July 1997. AMS indicated that attached correspondence did not present a complete picture of AMS' action.
- 2. List efforts to establish communication with NEORSD - Attached correspondence. l
}
- 3. State other avenues of remediation - AMS provided only two solutions:(1) AMS Remediate, (2) relinquish responsibility for area pursuant to " Guidelines for Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or Termination of Licenses fer Byproduct, Source, and Special Nuclear Material." (AMS indicated that having NEORSD do work and AMS pay was not an option because AMS would have no management control over services performed in their behalf)
- 4. Provide schedule, actions, and completion dates - Plan and schedule was to be provided shortly after AMS was given permission to enter the lateral. Now, following AMS November 4, 1997 report, AMS requests to amend the license to remove the condition requiring remediation.
1
- 5. Provide next step for proceeaing with remediation - AMS' Table 3 gave planned next steps and initiation times.
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Current Status
- AMS' entry into the interceptor for the purpose of acquiring survey data met the proposed completion date. Entry occurred on October 10,1997 (no samples to be taken for later analysis). A report of the survey was signed by AMS on November 4,1997 and received on November 5,1997.
The November 4,1997, report entitled " Remedial Alternative for the London Road Interceptor in the Vicinity of AMS," gives four options for remediation:
- 1. No action
- 2. Chemical Decontamination
- 3. Structural Decontamination
- 4. Fix in place The report evaluates the short-term risk of each of the options, the long term risk, and the cost evaluation of each option. It also has an ALARA analysis and AMS' selection of their preferred option.
AMS' bases their request (for release) on two NRC documents; (1) 1987 " Guidelines for Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or Termination of Licenses for Byproduct, Source, and Special Nuclear Material", and (2) 10 CFR 20 Subpart E, Radiological Criteria for License Termination. The November 4, report states "It is clear that the "no action" alternative provides the lowest hazard from both a radiological and non-radiological perspective." (p.29) and reenforces the point by indicating that the two referenced NRC documents support "no action". Issues
- 1. How should NRC proceed with AMS' request to release the interceptor?
' 2. If release is not authorized, or analysis / response cannot be completed quick!y, how will NRC staff remain responsive to the Commission's SRM to " proceed forthwith to require AMS to promptly comply"?
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.From: Stephen A. McGuire .(SAM 2)
To: KMR (Ko. - b m >< y , C k % ) Date: Thursday. March 30, 1995 6:00 pm
~Subjecti CRAC2 I believe CRAC2 should be available should you need it, but you may not have to use it. For the accident calculations you would need, it is probably not necessary to run CRAC2. Rather it is probably sufficient to use the equations
'_and. graph on pages 12 and 13 of NUREG-1140. The equation is:
D = DCF x B x X/Q x Q where 0 - dose in rems from internal exposure DCF - a dose conversion factor from ICRP 30 or equivalent publication. The-value for cobalt-60 is 0.22 rems / microcurie inhaled (listed on page 78 of NUREG-ll40.. B = breathing rate, generally 2.66E-4 m3/s X/Q is the atmospheric dispersion factor calculated by CRAC2 and plotted on page 13 of NUREG-1140 Q = the quantify of material released in microcuries. If you would like to discuss this further please call me on Monday at 415-6204. l O N n r+n n o i e tw Y?W_I Y!_?_- _2_ . . . _ _ Q'
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