ML20092M011

Rept of Facility Changes,Aug 1969 to Jul 1970

ML20092M011
Person / Time
Site:	05000172
Issue date:	07/31/1970
From:	Amend F LOCKHEED AIRCRAFT CORP.
To:	US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML20092L085	List: ML20092L280 ML20092L999 ML20092M006 ML20092M011 ML20092M117 ML20092M144 ML20092M168 ML20092M188 ML20092M376
References
FOIA-91-233 LGD-301154, NUDOCS 9202270109
Download: ML20092M011 (13)

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• Gl;OltGI A CO31 PANY A DiV IS ICh OF L OC 8.kt t D A l.C. A FT C O.PCe a 9 sok M ARicTTA. GEORGIA Soo6o

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SUBJECT:

Report of Facilities ChanEes for License R.66, Docket No. 50-172 fue C7 T0: United States Atccic Energy Ccant eeton Division of Reactor Licet. min 6 Washington, D. C. 20545 FEFERENCE: (A) Amendment No. 9 to Faciliwi License R-86 dated March 11, 1969 ENOLOSLCE: (a) Report of Facilities Changes, August 1,1@

through July 31, 1970

1. Enclosure (a) is submitted in compliance with Section 50 59 (b) of Part 50, Title 10, CFR, and with Faragraph 4.E(4) of Reference (A) license.

LOCKEEED-GEORGIA COMPANY ff$ '

F. L. Amend, Acting Manager Reactor Operations and Nuclear Safety Departcent FLA:fe F. L. Amend, under oath, states that the above and attached statements are true to the best of bic knowledge and belief.

Subscribed and evorn to before me this M day of Se a b A,,, ,17(0, at Dawsonville, Georgia.

Slilhg  % b NOT ARY FUM10, C.EOt01A STATE AT LARGE

'% MY COVN;t51oN EAPikt$ MAY 23,1972

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1. CGRENT STATUC - GliL Locliaad har recently ar.norce:' the intention cf reducirc the level of ~

setivi ty at tne Georgie Nu: lear Laboratories to caretaker otatus. The recetor !uei var rezcved fr:r. the REE on July ?), 1970, with no future

*rt. tion planned.

Although fev crcanitst'Onni che.nces have been announced to date, it is an-ticipated snat e any chantet vill be c.ade in the near future. Lockheed hat

• plied for e.n ecendnent to license B-36 to percit ovnerchip but r.ot o;er-stion of the RER. .

ParaEraph 5.0 reporte the orcanizaticnal status on July 31,17/0.

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2. IRRADIATION EXPERIMENTC 2.1 0FIEFAL -

The entire operation of the RD during the period AuCust 1,19 69, throuch July 31, 1770, is su-rsrised in the table below:

Unscheduled ,

Tire Shutdowns-Startups Operated MW-Brs Scrams Other Neutron Eadiography 122 67 bro 25 min 150.15- 3 0 Foils 2 3 hre 27 tin 42 0 -0 IFIC-W: 3 1 br -37 min .76 0 0

• NASA 7 3 bre 4 min k.45 0 0 Beacter Checkout 2 1 hr 2h rein 3.07 0 0 5 77 hrs 156.85 3 3 There vere no tectc involving the use of cryogenic caterials or the lithium

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hydride shield.

• 2.2- NEU 30N RADIOGRAPHY The tea =-tube used throughout the reporting period was as described in Paragraph 13. of Ref. A. letter. The only change 'in the test equipment was the addition of a retractable cassette holder which provided a ceans for changing test specimens vithout working in close proximity to the beam tute. Tne cassette holder was provided with an interlock with the reactor lift controls to disable the reactor lift except when che holder is in the fully retracted position.

. Inchheed was granted an amend:ent to license A-66 on April 22, 1970, which per itted personnel access to the reactor building under.certain conditions while the reactor vae operating. '!he' amendment vas sou6ht to facilitate the efficient production of large numbers of neutron radiographs without a re-actor-shutdown. Ibis type operation has not caterialised ad there has been no personnel entry to the outside area within the exclusion fence while. the reacter was operating.

Approxir.ately 70% of the operetion for radio 6raphy vas a continuation of de-velopment vork previously described. The remaining 306) was vork done under contract te various custeters and consisted primarily of radiographing sr.all explosive devices. The aggreEate weight of, explocives (TNT equivalent) involved-in a' single exposure has not exceeded 30 grace.

2 3 IFSC 'aTT One test was conducted for Lcchheed Misciles and Cpace Co:pany and consisted entirely of the irradiation of electronic components.

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2. 4 NAEA One test was conducted for the purpose of calibratic6 detectors vhich vere _

developed at the GeorEin Nuclear I4boratories under contract to NASA.

25 REACTOR CTICKCUT The reactor was operated on two occasions to observe reactor systems per-fomcnce following periods of reactor systems maintenance.

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3. SCRAMS AfiD UNSCHEIULED SilUTIOVNS

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Sree scrats occurred durird the period August 1,1969, through July 31, 1T0. There vere no other unscheduled shutdowns.

• ate Scram Occurred

. Indiention Cause February 20 Felay Scram - Malfunction of f 3 Safety (3ree Occurrences) Instrument Trouble Channel Converter resuit-in6 in a shift of the scram set point.

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k. REACTOR & AUXII.IARY SYSTDG MAINTENANCE .

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k.1 FJJffCR MAINTENANCE me reactor was shut dovn for six work days during the period June 10 throu6h June 17, igrTO, to investigate and correct a condition which caused number .one control rod to stick in the extrece lowered position. he con ' ,

dition vas first observed durin6 the performance of routine rod drop time measurecents on June 10. It vas necessary to unload the reactor core and disassectie the reactor to the extent that the grid and scrac damper vere recoved from the pressure vessel to perfdm the necessary maintenance.

me cause of the rod _ sticking vas apparently the presence of a thin deposi,t of corresion product in the close tolerance cylindrical section of the scram - ,

da::pe r. Bis section of each of the four dampers was rienned usits a vire brush and cylinder hone. No foreign materials were observed other than particulate tatter vtich forced a white cloud in the pool during the clean

• ire operstion. There vas no evidence of datage to the scram dacper or the control rod shell. '.

After the cleaning operation, nur:ber one control rod shell was inserted into and withdrawn fro: nu::hr one position of the scram darper through approx-imately 40 cycles with no sticking.

Red dre; and scrar tires censured after. reactor reassembly were normal.

k.2 DT.GENCY GENEPJ,TO?.

On March L,197C, the a.utecatic start features of the FTR eeergency diesel Eenerater vere functier. ally checked by simulating a pover failure. We diesel etsine started but the generator load breaker failed to close to pick up the lead. The reactor was not operating at the time. he AEC was ad-vised of this failure by Ref. B. letter.-

All ether rytters tainter.ernce was -considered routine.

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5. C.%53E IN CRCANIZATION f.1 O'" OSCAICEATION le foll:ving title char.ces vithin the GNL organization vere announced in Jr.e, 17'0:

Free To Eclear Froducts Manager Nuclear 145 oratory Director Eclent E;'dptent nr.d lateratory Eyste .s Division Nuclear Dupport .

Nelear/ Electronic Cyste:r Division Nuclear laboratory Operationr Eclear Aerospace Dimio:. Nuclear Aerospace Engineering Feactor Operations r.nd Nuclee. Safety nov report tc the Asr.ociate Director, helear Support. The ehr.ntes do not affect the f anction or the line organi-tation cf either af these EToups.

All experitental procrats art conducted by either Nuclear laboratory Opera-tions or Nuclear Aerospace Er.giceerin6 Tne Eeactor Operations Group has t.een reduced to five persons including three licensed Operators and tvo licensed Senior Operators.

52 EEACICE SAFEn* CCt0 CITE Cne ne:ter of the Safety Cec. ittee not in the operating line organization was replaced in May,1070, due to an organizationni change.

Another cetter he.s recently lef t the Co:pany and has been replaced by his Alterr. ate Cone.ittee Me:ter.

5.3 IlJ5T FRO"ECUCN A:O F;J.'C E'h3I!EERING 2ere he.ve keer no char.ges in -he function and activities of thece organita-tians.

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6. FE OFEP), TING PROCEIURES The procedure chteget listed have been revieved and dpproved by the Reac-ter Safety Cor. ittee:

Froeedu e Change PD 14 - Red *.'ithdraval Rates New procedure - to require that con-trol rod withdraval rates be ceasured at least cuarterly.

PS l'$ - Startup of Ret:tcr Include check of e:er6er.cy generator Auxiliary Syrte:r control settings. Incorporute chand,es pen.itted by Chan6e No. 7 to Technical Opecifications of License R-86 F5109 - Shift Superviecrs Incorporate chan6e in key control.

Check Sheet Incorporate changes permitted by Change No. 7 to License R-66 RER IM - Nuclear Startup Eewritten to exclude extraneous cate-rial and to better define F.C. vith-draval limitations.

TE M - Reactor Shutdova Rewritten to cover In-Pool operatics.

RER 51k - E ergency Generator - New Procedure - to require a function-Functional Check

. al check of the emergency Eenerator aute::stic start features quarterly.

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- 7. FACILITY CHA!CES .

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'Ibere vere r.o chances to the facility other than the additice of the re-tractatle ca. stet e holder iiteursed in Para 6raph 22.

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6. ENVIS0? MEN'AL MONITORI1O 3.1 SC11 S/FPLE EER*LTC D.trins *.he report period surface samples vere collected in each of four eencentric ringe around the Radiation Effects Reactor at distances of 50, 125, 250 snd SCC feet. We results shown are an average of the activity in UC/OM for the sa ples in each ring. ,

A. (SC ft') E. (125 ft) C. (250 ft) D. (500 ft) 3rd Quarter - 1969 19 0 x 10-i 6.4 x 10-5 5.6 x 10-5 4.1 x 10-5

!.th Qusrter - 1969 26.3 x 10*5 12.2 x 10-5 5 9.0 x 10-5 ist Quarter - 1970 21.7 x 1C-f 12.6 x 10-5 11 9 xx 10 9,1 10-5 5 2nd Quarter - 19'70 28.6 x 10-5 13 3 x 10-5 8.7 x 10-5 6.3 6.8 xx 10-10 5' 6.2 f.CHVATED SCIL TRA!!SPCP.T Fricary nethods fer activated soil tranrport are by airborne diepersion and vater run-off. '

6.2.1 Airborne Dispercion Airborne activit- results reflect the average monthly gmos activity in par-ticulate e.ir sr.:ples te. ken continuously at the REF approximately 140 feet fro: the reac' or building and at the CEF meterological tover, which reptv-seats the control sample. Results are shovn in Arc /ce.

REF CEF Aucust - 1969 1.25 x 10-12 * * '12 September - 1969 .69 x 10-12 '

-12 October - 1969 99 x 10-12 '50

• 0-12 Nove:ber - 1969 ,.72 x 10-12 '3g 10-12 December - 1569 .77 x 10-12 38 10-12 vanuary - 1970 .64 x 10-12 35 x 1 -12 February - 1570 .% x 10-12 x 10-12 Rsrch - 1770 1.06 x 10-12 .Sfx10 April - 1970 2.24 x 10-12 g ,

May - 1770 3 35 x 10-12 2.'02 x 10-12 June - 19'70 2 * ~c o

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• July - 1970 1,72 x 10-12 ,

0'-12 S.2.2 su-race Water Transport Tr.e -activated scil transport via surface vnter run-off 1s determined by con-tinuously sarplirg the Etovah Eiver water upstrear and downstream from the reactor. The centhl;' averages of the gross activity for these sarples are shevn in .te /ML.

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.For cocparison,~ activity or rain vnter collected at the CEF e shown. ,

Period - Upstream Downstream -4*m CEPs Rain' M -

AuSust -.1969 3,3 x lo-8 3 5 x 10-8 6.5 x 10 Septecber -:1969- 3 9 x 10-8 8 8 october -11969 3,5 x lo-8 6.o 2 9 xx 10- 10 8 7 3 x 10 8- -

November - 1969 8 3 2 x 10-0 g,1 8.0 x 10-x lo 8 .

December - 1969 2. 2 x 10 8 4.2 x 10-8 12.5 x 10-8 January - 1Wo 2.0 x 10 8 3.o x 10-8 , 12.o x 10-8 February - 1$rfo 3 0 x 10 8 8 8 March - 197o 2.S x lo*8 -

4.1 x 10 8 6.h 9.5 xx 10- 10 8 April - 1M o 2.6 2.2 xx10-10 8 2 2.2 7 xx lo-lo 8 14.4 x 10-8

_ May - igrto 3 7 x lo-88 3,9 x 10-8 8-10.8 x 10 8

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June - 1970 8 4 July - 1970 19x1o8 2.5 x 10- 2.2 2.2 x x 10 lo-8 11.k 7 4 xx 10 lo- 8

-83 VmCATION .

Vegatation sa:::ples .taken quarterly are avera6ed for the report period _ and are shows for "on-site" and "off-site" in >>.c/GM.

on-Site Off-Bite 13 2 x 10-5 24.h x 10~5 t

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RDUENCES:

A. LAC, Ga. Co. , ltr to AM, dtd 2 October,1969, Sutj.: Feport of Tacilities Changes for License R-86, Ibeket No. 50-172, icd /2E,S017 E. LAO, Ga. Co.,1tr to AEC, dtd 12 May, ISTIO, Subj.: Radiation Effects Peactor, Docket No. 50-172.

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