ML20129E361

Safety Insp Rept 70-0025/85-03 on 850422-26 & 0508.No Violation or Deviation Noted.Major Areas Inspected:Mgt Organization & Controls,Operator Training & Retraining, Radwaste Mgt/Transportation & Environ Protection

ML20129E361
Person / Time
Site:	07000025
Issue date:	05/24/1985
From:	Brock B, Thomas R, Zurakowski P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:
Shared Package
ML20129E341	List: ML20129E338 ML20129E361
References
70-0025-85-03, NUDOCS 8506060452
Download: ML20129E361 (9)

Text

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g' U. S. NUCLEAR-REGULATORY COMMISSION REGION V Re' port No. 70-25/85-03

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' Docket No.

70-25 License No. SNM Sa'feguards Group I i' Licensee: .Rockwell: International Corporation Rocketdyne Division Atomics International 6633 Canoga Avenue Canoga Park, California 91204 Facility Name: Headquarters Site and Santa Susana Field Laboratory Inspection at: Headquarters Site and Santa Susana Field Laboratory' Inspection conddcted: April 22-26'and May'8, 1985 Inspectors: / [I

-B.'L. Brock, Fuel Facilities Inspector Date Signed

@.Zuraknwski, P. 'R.

padru2Ai Radiation Specialist

$/91/7f

--Date Signed I

' Approved By: /5" R. D. Thomas, Chief Dite Signed Nuclear Materials Safety Section Summary:

Insp'ection on April 22-26 and May 8, 1985 (Report No. 70-25/85-03)

' Areas Inspected: A routine announced safety inspection was conducted of. '

management organization,and-controls, operator; training and retraining ~,

,, criticality safety, operations feview, radiation protection, radioactive waste management / transportation, environmental protection,-and emergency-

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preparedness.

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.The' inspection involved a total of 66 hours7.638889e-4 days <br />0.0183 hours <br />1.09127e-4 weeks <br />2.5113e-5 months <br /> onsite by-two regionally. based inspectors. 2 .

Results: No vi31ations or'devlations were identified in the eight areas x inspected. 7 ,' :

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DETAILS C mg g,. _

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1) jPersons' Contacted.

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1*G.1WJ Meyers,;Vice; President,' Atomics International,-Rock'etdyne' t , ' '

. *M.iE.JRealey,'; Director,' Nuclear Safety'and' Licensing' '

4 i*C.' J?Rozas, Director,, Health,_ Safety and Environment ,

I*R.iD.:Barto, Director,? Security-W

, *R.-J.iTuttle,~ Manager, Radiation and Nuclear Safety "

1. , 1*C.-A.' Parker,-Manager,-Technical Training ,

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-I.-N. Stein ~,1M.D.=, Medical' Director . .

L jV.;J.' Schaubert; Manager,1 Nuclear Safety and' Licensing e ,

nW.":R. McCurmin,iManager," Nuclear Operations:

, ;F.(H., Badger / Health and Safety Engineer

!J.<D.; Moore, Health.and Safety. Engineer >

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,  ; ^ 1Q.=Koonf Lead Engineer, Calibration. Quality. Assurance;

'L. E. Rodman, Senior" Fire ProtectionsEngineer:(Emergency. Coordinator)

.~ 0 cJ. A.-Gump, Fire 1 Protection. Engineer ( .' .

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. . , , lR.,M.':Hichlich,' Senior-Staff' Engineer for Training

%DJ Harrison, Staff' Chemical: Engineer V E. :L'.? Babcock, Assistant Manager, Rockwell!In'ternational' Hot Laboratory -

r S. ,M;- Bradbury, . Senior Engineer ,

- ^'  ; "D.: Allen, Staff" Assistant ' +

i# ^ ^ RICutting,iShift Leader ._

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. > y. RH S. Frazier, Member Technical ~ Staffs +

.- w -y,oI,-Greenwall,-Captain,1 Security Department Y '" '

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g C.7 M .: Bower,; Captain,-Security Department; ' -

f JC C:nBliss, Sergeant, Security Department:

R.;F.:Hanabrey,: Electronics Technician s

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• Denotes-those attending the exit meetingi

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I '2. Management Orga'nization and Controlsi , '

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, (' + Section 9 :of NRC License 'SNM-21 incorporates Part-1.of the;1icensee's '

- ' , . application and_ supplements dated October 29 aud December 17,i1982',;and March 2, 7, May 29_and June 12,-1984'as'-license conditions. O ~

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_ ;A. Organizational Structure . .

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Section 11'.3 of the license application' requires certain . -

organizational divisions of responsibility to' provide-a' check and-o, ,

balance syatem'in the :important areas' of plant safety.

O tC , The~insp'ector'sTreview of'the licensee's organizational structure; -

found it' unchanged. Safety functions remain organizationally

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independent of operations. ,

l . - - B. g Procedure Controls " ,

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> "E ~. Section 11.3.4 of the license application requires that changes in c *

-established procedures must be authorized in advance by appropriate ,

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J Theflicensee handlesinformation Notices.without ar specific' ,

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' ' procedure or record (forJfollowup. .The:Information Notices ~are

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reviewed.on receipt byithe;Difector, Nuclear: Safety and Licensing., M

.Theyfare appropriatelys distribut'ed for.actiontas necessary? The

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w ^!adequacylof followup ,on;the Information Notices will be reviewed-gl 4 ~

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N' q< , ,- :Section22.8Lof'thellicensejapplication' requires internal inspectionsJ

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._ The. Criticality (SafeguardsiAdvisorcis conducting the, weekly ^~

rs y- y . inspections n'ormally.done bylthe, Criticality Safeguards Coordinator.

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p' The; Health and Safety Spe'cialist?istbeing. trained to perform this.

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. function LThe criticality Safety 1 oordinato'r also performsathe; "

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M i The Fuels _Committeefconducted its annual inspection'on Januaryf29,y 1985. The ~ findings were minor and appropriate corrective action was-

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<. taken.  !*t 5$h .- ._ , ,

a- . The Isotopes Committee conducted ant inspection 'of the Santa Susana- ,

. .m ~.-. . < Field.; Laboratory on January 22, 1985. They noted the significant ~ ' 9 m -

1 '(50 percent) redu'cti.on in,the mrea/ hour at six feet statistic. 'On- {

January 23, 1985, the'committe'e inspected the-DeSoto Facility and no< ,

'~  ; problems' of' consequence were identified.-

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., No violations were identified.

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.c (3.- H 0perator Training and Retraining

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-Condition 14 of the current license' requires that prior to unsupervisedT~

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work with special nuclear material appropriate formal training shall-be

.g . given:in criticality and/or/ radiation safety. -

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+ During.this' inspection all persons' working in Building 020 who received a g* C , ' , ,*'

fmeasurable' exposure ~during the first quarter of 1985 were cross. checked; '

/ a against the computerized master training record' file ~ maintained by the-

- _E, Training Department!for complianc'e^with training requirementsi .The' _ j .

L,  ?' records indicated that'at least=50 percent of the persons;had'not ,

V ' received'the training. The inspector then went=to BuiMing 020 and cross '

• checked these same people against the. secondary training ~ records _

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imaintained b ,the Administrative Assistant. ;These records-indicated:that ,

t t , all? required training had been given and those persons requiring yearly medicalJexamslas'a prerequisite to using respiratory protectivetequipment ihad received'the examination. The inspector concluded that.the training 1

. records ~ maintained at' Building 020 were up to'date and well maintained.

sy ;However, the master records are not up to date and do not give complete 7 '.informationTabout needed training and medical examinations. - ,

.At-the' exit interview the licensee' agreed to examine this discrepancy and' make-appropriate corrections. This item will be reviewed again during 7' '

the next inspection (85-01-02).

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No violations were identified. -

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4. Criticality Safety

-Section 2.7,of the license application requires that prior to initiating

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a project involving potential hazards, authorization must be obtained from the appropriate Department Director and from designated Safety gg and/or Criticality' Safeguards personnel in the Health, Safety and MM Environmerit Department. g A. Nuclear Criticality Safety Analysis Section 4.1.3 of the license application requires the completion of a Nuclear Safety. Analysis (NSA) for projects involving at least 200 grams of uranium of more than 30 percent enrichment.

An NSA is being prepared for the Fermi fuel decladding project.

Only cold tests (outside the hot cells) are currently underway on cold zirconium rods. The NSA will be reviewed in a subsequent inspection.

The licensee has continued effective control of the "in process" inventory to less than the license limit of 1.0 kg Pu at the E Rockwell International Hot Laboratory.

No violations were identified.

5. Operations Review Section 2.1 of the license application requires the licensee to comply with all the requirements of law, to operate the facilities in a safe and =

efficient manner and within the requirements of all license conditions under which the activities are authorized.

A. Conduct of Operations License Condition 25 requires that the licensee follow the general deconnissioning plan submitted in the. enclosures to the letter dated March 15, 1978.

(1) The licensee has continued to cleanup Building 055. The inspectors observed that the low volume ventilation system that served the glove boxes has been entirely removed. The licensee indicated the removal was completed without incident. The tile floor covering was also removed. See Section 6 for additional details.

(2) The EBR-II decladding operation in the Rockwell International Hot Laboratory (RIHL) was operating normally. The inspectors were able to observe all aspects of the operation including the removal of containeis of solidified liquid waste. The waste handling operation appeared to be conducted in accordance with the licensee's procedures,. license conditions and regulations.

See Section 7 for details.

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4 (3) The neyt RIHL project. involves decladding Fermi fuel rods. The licensee plans to declad the Fermi fuel rods by centerless

, grinding. The U-Zr fines resulting from the grinding operation must be handled carefully since the fines will oxidize exothermically under certain conditions. The licensee reviewed the problem, experimented with the zirconium fines, and established conditions for safe handling of the waste as a stable nonpyrophoric monolith.

B. Housekeaning

.The RIHL basement was toured by the inspectors. They observed the srea to be cleaner and better organized than on previous visits. A basemer.t fire ext.inguisher was relocated closer to the step-off pad in the event it was needed by someone entering the area in an emergency.

No violations were identified.

6. Radiation Protection Protection against radiation ~ hazards-associated with licensed activities is required by 10 CFR Part 20.'

A. TourofFac'ilii.ies During^this; inspection a tour of Buildings 020, 055 and the sanitary sewer holding station was made by the inspectors. Where applicable, portable monitoring equipment, fixed and portable air supplying equipment, stack monitors a'nd criticality alarms were found to be operational,and_ currently calibrated. The one potential problem found,was related to the automatic sewer monitoring device associated with the.sanit'ry a sewer holding station near Building 055. 'Although'the sewer monitor was currently calibrated and appeared to be functioning normally, two lights associated with the automatic transfer. valve that prevents radioactive waste material from being transferred to the sewage processing plant were not indicating correctly. The lights indicated the transfer valve was both open and closed at the same time (It was obviously closed).

The inspectors were assured that each time the monitor is calibrated, the valve' is checked for proper opening and closing and the problem is with the circuit associated with the lights and not the valve. At the exit interview, the licensee agreed to operate the valves in the presence of the inspectors to demonstrate that this emergency backup system functions properly. This item will be reviewed during the next inspection (85-03-01).

During the tour of Building 020 packaging and transfer of solidified EBR-II liquid waste was observed by the inspectors. This item will be discussed further in Section 7, entitled Radioactive Waste Management.

During the tour of Building 055 it was learned that the attempt to clean the two spots on the floor which were discussed in report

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7.""M e" 70.-25/84-05 was partially' successful. One. spot was< decontaminated.

fP ^w; lto background 'while the -second spoti of+ approximately:2rft 2, rea. ding; .gb

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temporary l safety; measure, the spot has been ~ painted overlandisealed. e

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Prior to the' removal of'the; Building 055 ventilation = ducts the.

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"InsideTsurface was wiped and surveyed'where accessible by the:Seniorj , -

. Staff Health Physicist 6 It was found thatialmost:all of th. educt U'+% >

A . :was it background with a high' reading;in one: place'of.425iDPM;

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for disposal as7 radioactive wa'ste.1

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MB Eb'ereadyforlanNRC.over] I check'sometimeafterJanuary1986.Itlis1

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S r .formerly usedfin' Building 055:h'as been resurveye'd by the: licensee; 1 Q'g, OMF (and-foundfagain to be: uncontaminated. The history of its nse'was 4

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~ ; thoroughly ~ researched by the Manager, Radiation and. Nuclear; Safety. <>

W~"2 s  % 'It*was found<that plutonium never made' con' tact with the instrumenti .

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lgl'ovebox'(an~dwasTisolated-from,thespectrometerbya+quartzwindowT

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1. "( ,s 'ih'e,ex'ternal exposure Lrecords o for the: first quarter of -1985 were m SY Rf.c .

examined by,the inspector; -The high quarterly exposure was noted-tol

.be 850; mrem. The downward trend in exposures.appearssto be: .- '

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$?p g TJg'E ^g$  : continuing' with 'a few elevated exposures; caused by'necessary: cell' '

N 7 M re-entries to; survey and repair equipment? (None of'the exposures c '-

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.notedduring}thisinspectionexceededregulatorylimits., m, .-

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,fy'+~ C. -Bioassay Resultsi , - t .

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x quarter'of 1984 and!those available fort the first quarter ofE19852 ,#.

My ^ / Of;the 51 specimens submitted for the-fourth quarter'ofi1984 twoe '

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positive results'for plutonium were reported. -These.were slightly .

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':above the; minimum leveltof detection.'-However,cfollowupibioassays;

' Ed ..Wi idisclosied-that both' individuals were atfthe minimum' level.of ' ,

R M J' E ' detection. :During;the first quarter of 1985 acspecia11 bioassay was ,

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perfor.ned for ari? individual who cut' his; finger while repairing ~al

. gear associated with cell number four. . The< bioassay result was:at

' d p~ 4' n i the.~ minimum l level of de'tection. Immediately after-the' incident'a ,

,i 2_.'v ;1000 second' count of1the, finger using~a Canberra Series 85 .

PM <, , n ;x '3 wP fE T 4 Multichannel 2 analyzer equipped with a Ge-Li detector disclosed no-

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( v,1 Annex;!'B'S of 2th'e curr' e dt' license incorporates guidelines for release of-

, ~1 equipment;and' facilities for unrestricted use. . 10 CFR Part 20.3011to e

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L, TPart20.401) regulates'theidisposal'ofkaste. 10.CFR Part 61 requires: ' ,

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thatLall'~ radioactive waste; prepared:for-disposal is classified in.,

accordance with Section 61255,andimeetsjtheJwaste characteristics

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trequ.irementsJin Section 61.56. Apart 71 regulates the packaging and-

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-transpo"rtationtof radioactive material.

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rocedure for;the safe disposal.of--

Duringfthislinspectionthewrittenp'dingandprocessingofEBR-II' liquid waste generated in' the-declad fuel i

was.again reviewed a'nd the recentichanges, which incorporate the ALARA '

y concept'during actual' handling and packaging in the' hot cell area,-were 3 discussed with'the Staff l Chemical Engin'eer. It was learned that "to

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-date" approximatelyfl00 drums'have been packaged leaving'approximately 0 -

140 yet to be'done.

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The handling'and packaging operation was observed by the inspectors. - It-f.

was found that;the written procedure,was followe'd exactly as the 7

5 operation'proceede'd in a smooth and efficient manner. Each worker seemed" 5 fully aware of the ALARA concepts written _into the procedure.as(the-

' . packaging operation moved from the hot cell into the decontamination roos 7- -

. ;and then into the service gallery. Discussions with the Manager,.

TRadiiti3n and: Nuclear Safety disclosed 'that this well written procedure .

- s Jhas:significantly reduced exposures to persons. involved in this kind'ofr

. work.' -

,M Discussions with the Manager, Nuclear Safety and-licensing d'isclose'd tha't-

. y siace-the'last~ inspection 57 drums of this solidified waste.have.been

' shipped to the~ DOE Disposal' Facility nea'r Richland, Washington.- Although w , these ' shipments are not under NRC jurisdictio'n,' the inspector ' learned ~ -

that the drums arrived'at their destination with'out incident and were-

= " accepted by-DOE Disposal Facility Personnel. 1

'ThesediscussionsalsodisclosedthataPart61in'spectionofsuchL c, w shipments by-NRC is 'not appropriate since .the DOE disposal facilityDis

not a commercial operation and the shipment is'not under.NRC -

' jurisdiction. The: shipments and disposal of such' material are regulated

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by DOE because'the wastes were' generated in DOE sponsored programs.

During this inspection Hallam Canisters containing EBR-II cladding were

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observed in, storage inside hot cell No. 4. The-inspectors learned that

'approxinately sixty of these canisters will be transported to. DOE's

, _ l Nevada Test Site during the last week of May for disposal.

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1* :It is also anticipated-that EBR-II fuel freed in the~decladding-process

, _ ;will be. shipped to Savanna River sometime in June. All of these'

'; ; f shipments will be conducte'd under DOE ' jurisdiction. However,-hot cell

operations. involving these items and onsite shipments to and from e ,' L Building < 020 ' remain under ~NRC jurisdiction. One shipment of EBR-II fuel

a'rriving at Building 020.from the RMDF was observed by~the inspectors.

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.Thstruck'liftTdriverhandledtheIloaIdwith'greatcare.,No_problemswere' ,

C c - encountered 'during-this transfer.' iNo violations. of the licensee'.s '

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Jpracticesfwere noted'during.this? operation.

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.8. ,EnvironmentallProtection . .- .;i ? N / ,~

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1 Title 110;ofz thejCodeofFederalRegulation,Part20.106"Radioantivityin Sd #Y W .

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. 7 EffluentiFto-Uniestricted, Areas"'. requires that licensees / control their

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, . ..- ; exceeding;"the ;11mits rspecifiedfin Appendix B,iTable II of Part 20. 4 ti 3- ,

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iThe licensee's effluent monitoridgLr'eportsifor~1984'~ indicated effluent

. concentsations were within'10_CFR 20; Appendix B-limits. The-licensee's 1

--annualtreportTreflects7afchande3i n~the standard used for making alpha' m' ' ' .9 ,(measurements. The-standard now used'is'better in thatDit;is thick'

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- : relative;to theialpha' particles;mean-free path as in the sample matrix.

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, 'lThe placedL(thin) standard on which previous. measurements.were basedt i ' ' iyielded. low sample results.- Samples-for independent;. analysis-.were taken

" _ from;two of the offsite sampling stations lbp the~NRC inspectors.

,- ,. 1 Measurements,willibe made by bothithe Department of Energy.(DOE) _

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, " Radiological and Environmental Sciences' Laboratory,(RESL);and the NRC-RV:

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Mobile Laboratory. ;The're'ults s will be included 7in a subsequent report;

No violations were identified. -

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, _ - 9. 1 Emergency: Preparedness, *

"~ d.icensbCondition24requiresthelicensee1 tom'intainandexecutethe a l

'"> /rgsponse measuresLof hisLRadiological-Contingency Plan submitted to the

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Coenission on August 28,'1981, and revised-on-March 3, 1982; .

,.Y,, ~ ^ Additionally,1. Appendix A.tothe; Radiological *Contingenc'y Plan statesithat

% fthe' Master Emergency Plan /has~been"approvedTas.part~of theLlicense.

m 77 sA. Emergency Plans, Proce3ures, Facilities.and Equipment- ,

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The licensee's Radiological Contingency Plan.is unchanged. .

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Telephone numbersLon call-lists have been updated-.and.the call' lists were readily1available. The licensee's emergency-equipment vehicle.

, -was being' repaired. A pickup truck was temporarily carrying the

t -emergency equipment. The licensee's medical trailer'(currently s

,;;f t , stationary) was visited. .The' trailer's equipment and housekeeping 7; t', , had been upgraded. Additional medical supplies are'readily '

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,available from the Santa Susana-Field Labo:catory nurse's station (which is1 housed in the Central Security. Station within 1000 yards of the medical trailer.

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- * , iB. -Tests and Drills ,

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" ' The licensee sch'edules and executes < drills with a variety of a v scenarios to assureiemergency-personnel receive a variety of experiences. A'dril1~was held in the RIHL (Building 020) on g6 '

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_ ;fat, t;3@(::l20totfacilitate p.~m. ;the participation of: '

S 5,w Ope.sonnellon(the secondi s hift.'LThi critique of the: drill indicated-7 i,% ~ l". ~

"itihad beenlus'efdlTiii^ identifying areas ;for/ improvement. :The .  ;. 4 ..

Giy 2 ' improvements #are.being implement,ed.' * -The next .drillfis schedule,d' for!

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.mid-May_and the licensee plans tol invite.the participation of'Humana-

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. Hospital Wsst' Hills.2 Th drill?is:still scheduled:to include an- ,

, lambulance trip,from s M e.eSSFL to'Humana Hospital West Hills to- _

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' establish the time'the;hos'pital would have to prepare-for1 receipt,ofi fs > pf N_ -

f a'n"injujed "sadicontaminated patient _. :The. critique ofjthis drill' i

! , .~~'M willbereviewed'wheniavailabl~e!(85f01-05). 1

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A ,p,m#/: M. C. _ Fire Prot'ction e y.

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'h . The inspector verified that: the fire _ extinguisher 7 nspection i tags = in ' . ,

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.,, % > _ ', ,e one area werelnow being fully dated as_in the othersareas.

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,The'results'of_the; inspection:were discussed with the licensee's staff N J'f e f' K identifiediirf Section~'li , s M.,

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'N, + J*~~ the cont'inued effective control of'the-"in process" limit 1 -

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. [ ~_ * (th'e apparent consiheration~given'to ALARA in:tlie~ waste packagingi-4

, , phase:ofJthe.EBR-II decladding' project: ~

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• .the preparation _ underway for assuringithe safe disposal of EU-Zr'-[ #

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_ f E -Y the status of the' Building'055. decontamination effort.

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"? * .the trainingLrecord discrepancy stillrexists though7 training w s.

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V- -current a ~w u

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• - The licensee ag$in' expressed an interest i in, correcting the; training?  % *

, -record' discrepancy. The licenser also indicated that ALARA Qa , .C z H (considerations'.have.been.' emphasized lt employeesCand they have ,

f r 7 contributed s'uggestions'that'effecti reduced doses. in various ' aspects, yofcurrent,

.x operations.

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