ML20009A190
| ML20009A190 | |
| Person / Time | |
|---|---|
| Site: | Neely Research Reactor |
| Issue date: | 03/07/1979 |
| From: | Kirkland R Neely Research Reactor, ATLANTA, GA |
| To: | |
| Shared Package | |
| ML20009A185 | List: |
| References | |
| NUDOCS 8107090169 | |
| Download: ML20009A190 (7) | |
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197s' GEORGIA INSTITUTE OF TECHNOLOGY SCHOOL OF NUCLEAR ENGINEERING ATLANTA. GEORGI A 30332 FR AMgM. NEELY RUCL3 AR RESE ARCH CENTER 72Lerw o N E: (404)094 3600 a March 7, 1979 U.S. Nuclear Regulatory Co: mission, Region II 101 Parietta Street, N.W. Atlanta, Georgia 30333 Gentlemen: tu-err.:JE: Docket 50-160; License R-97 Pursuant to Section 6.7a of the Technical Specification for our facility license R-97, the following annual report is being sub-citted. Tne.repo" ting period is January 1, 1978 through Dece~.ber 31, 1978 (calander year 1978). Tne disignation of the paragraphs follow the title and order of Section 6.7a of our Technical Speci-fications.
- 1. Operations Sur rj
- a. Changes in Facility Desirn:
- 1. In June 1978, installation was cocpleted on a re-mote send / receive station for the pneumatic trans-fer system H-16. 'Ihe station is located in room 127 of the Nuclear Research Center.
- 2. The operating system of the main airlock doors for the reactor containment building was modified by installing a vacuum supply and control system which functions to assist in deflating the door seals during normal opening and closing.
- b. Performance Characteristics:
During the reporting period, the reactor was operat-ed at power levels up to 5000 Kw using a 17 element core. Fuel perfonwnce has continued to be satis-factory with no known proble:rs.
- c. Changes in Operating Procedures (Safety Related)
A group of Health Physics procedures wae issued and approved on 2-28-78. All the procedures carry a 9000 series nu:ter designation. 8107090169 810630 gDRADOCK 05000160 PDR,
U.S. Nuc1:ar Regulatory Conmission, Region II Page 2 March 7, 1979 Procedures 2002 and 2003, Weekly and Daily Precritical Startup Checklists were m vised to incorporate testing
, of certain radiation monitoring channels.
, Procedure 1502, Fuel Handling In he Com, was revised to more clearly define specific limitatios and restrict-ions.
Procedure 2500, Containrent Building Health Physics Pro-cedums, was rodified tu inccrporate a method of checking for tritium inside the containment building. A new Procedure, No. 3101, was issued to be used when operating certain of the experimental facilities of the reactor,
- d. Results of Surveillance Tests and Inspections h e surveillance tests and inspections of the facility re-quired by the Technical Specifications were performed. Re-cords of each of these tests and inspections are availatle at the site for review,
- e. Changes, Tests and Exceriments Aoproved by USNRC here were no tests or experimnts that required the approval of the USNRC pursuant to 10CFR 50.59 (a).
- f. Changes in Plant Staff and Cornittee Membership h e current plant operating staff is as follows:
Dr. M.V. Davis , Director, Nuclear Research Center Mr. R.S. Kirkland, Reactor Supervisor Mr. R.S. Kirkland, Acting Reactor Engineer Mr. R.M. Boyd, Radiological Safety Officer l R e current organization of the Nuclear Safeguards Comittee is as follows: l Mr. R.M. Boyd Dr. R.N. MacDonald ! Dr. M.V. Davis Dr. D.W. hhrtin Dr. B. Kahn Dr. J.H. Russell j Mr. R.S. Kirkland Dr. J.W. Poston l 2. Power Generation l For the period January 1, 1978 through December 31, 1978, the total power generation of the reactor was 1066 megawatt hours. l r
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U.S. Nuclear Regulatory Commission, Region II Page 3 Ierch 7, 1979 3 Shutdowns During the reporting period there were 18 unscheduled shut-
. downs. These are tabulated in Table I as to the cause and preventive action taken.
- 4. Paintenance (Safety-related systems and corponents)
In January and again in February 1978 the power supply for the area radiation monitors failed. Repair was effected by replacement of several electronic parts. In January,1978, the filter paper drive notor for the nov-ing particulate air monitor (MAP-1) failed and was replaced. The vent system low flow alarm failed to function in June and and again in November, 1978. In June, the mechanical reverent was repaired. In Noverber, a new tercury switch was installed. 5 Changes, Tests and Experiments k'ithout Prior USNRC Approval During the period there were 65 approved experirents for the Georgia Tech Research Reactor. Each of these was evaluated prior to its approval with regard to Section 3.4 of our Technical Speci-fications. Records of each experiment are available at the site for review.
- 6. Radioactive Effluent Releases
- a. Gaseous Effluents:
- 1. Gross Radioactivity Released
- a. Total gross radioactivity - noble gases:
Curies of "lA (only detectable isotope) 197.43
- b. Average normal steady state concentration released out of stack. At 1 M4: 3 0 x 10 s uci/cc 5 M4: 1.8 x 10' uci/cc
- c. Maximum instantaneous concentration released:
4 pci/cc 3 0 x 10 or 472.50 pci/sec
- d. Percent of technical specification limit: 80.8%
- 2. Iodine Release
- a. Tbtal iodine radiocctivity released: None detected.
Minimum detectable reh ase is 400 pCi/yr. 7 - T-w-v vp g y yw -w y-w y- y r-y, r- yve, - y---vw-- w-- -r -, m w w -rrr- - -y
U.S. Nuclear Regulatory Comission, Region II Page 4 March 7, 1979
- b. Percent of technical specification limit: 41.7%
3 Particulate Release
- a. 'Ibtal gross radioactivity (8,y) released: 41901
- b. Gross alpha radioactivity released: 41pCi
- c. 'Ibtal gross radioactivity of nuclides with half-lives greater than eight days: 41pCi
- d. Percent of !?C for particulates with half-lives greater than eight days: 40.01%
- b. Liquid Effluents
- 1. Total gross radioactivity (8,y) released excluding tritium and average concentration:
Total: 96.27 uCi
- Average Concentration: 1.70 X 10 7 pCi/cc before dilution with other Georgia Tech water.
- 2. Maximum concentration radioactivity (8,y) released to un-restricted area: 9.25 x 107 uCi/cc before dilution 3 Total alpha radioactivity released: None detected (mini =r detectability 2 pCi/yr.)
a
- 4. Total volume of liquid waste released: 3 26 x 10 ml l 5 Total volume of dilution water: 6.750 X 2010ml i
- 6. Total radioactivity and concentration re1#ased by nuclide
85,994 uCi Tritium Average cencentration: 2.60 X 104 pCi/cc tritium , 7 Percent of technical specification limit for total j radioactivity from site:
<.01% for gross 8,y e7.cluding tritium f 8.60% for tritium i
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* 'Ihe majority of this is for the laboratory sinks or operations outside
! the mactor containment building and is not necessarily attributable I to reactor operations.
U.S. Nuclear Regulatory Comission, Region II Page 5 March 7, 1979
. 7 Environment Mointoring . a. through d. Environmental monitoring is done with 43 TO's and 30 film badges. See Figure 1. " Environ-mental Manitoring Stations". TLD's are changed on a three renth basis and film badges on a one month bases. The film badges are at 30 of the sa e locations as the TLD's TO Dose rem
- Highest 32 (Station 2)
Iowest 0 (Station 2) Highest Annual Aveg. Radiation Level 8.5 (Station 2)
- e. Fhximum cumulative radiation do e from
- 1. Direct radiation and gaseous effluent: <50 mrer4T.
- 2. Liquid effluents: none or <1% 10CFF20 limits
- 8. Ibtal Occupational Personnel Radiation Exposure For 1978 Two persons received g= eater than 500 eem (one was 780 een).
No persons under the age of 18 years received greater than 10 eem.
*Minirum sensitivity 3 mrem If you have any questions on the above inforration, please contact me.
Sincerely yours, GEORGIA INSTITiTIE OF TEC'EJOID3Y t R.S. Kirkland Reactor Supervisor RSK:1m cc: Members, Nuclear Safeguards Committee L.D. McDowell Sworn t,p and subsc Jbe4 before me this Y day of lbulu 1979
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TABW I GTful UNSCIEDUMD Siilf1DOWIS January 1,1978 - Decenber 31, 1978 Report No. Date Circuit Cause Preventive Action 78-1 3-15-78 Control Air Iow Pressure Sticking soleroid valve Ibnitor system performance; replace valve 78-2 3-16-78 Period #2 (Postive) Operator error Caution operating staff 78-3 4-6-78 Magnet Actuator Anplifier Possible loose connector Replace connector 78-4 4-20-78 Power Trip #1 Spurious Check for faults and monitor performance 78-5 5-5-78 kgnet Actuator Anplifier Possible loose connector Replace connector 78-6 7-13-78 liigh D 0 Enp. (#1) Operator error Caution operating staff 78-7 7-18-78 Period2 Trip #2 (Negative) Spurious Check for faults and nonitor performance 78-8 8-7-78 liigh D20 %np. (#2) Operator error Consider replacenent of channel #2 78-9 8-7-78 Magnet Actuator Anplifier Spurious Check for faults and monitor performance 78-10 8-7-78 liigh D,0 %np. (#2) Operator error See 78-8 :
. 78-11 8-7-78 Power Trip #2 Operator error Caution operating staff 78-12 8-7-78 Period Trip (Negative) Spurious Check for faults and nonitor performance 78-13 8-8-78 Magnet Actuator Amplifier Spurious Check for faults and nonitor performance
- 78-14 8-8-78 Magnet Actuator Anplifier Spurious Check for faults and nonitor performance 78-15 9-20-78 Control Air Iow Pressure Sticking control valve Monitor system performance; change valve 78-16 11-14-78 low Shield Coolant Flow Punp cavitation; low
) tank level Add water to system, repair coil 78-17 12-12-78 Doors Open Spurious Check for faults and monitor performance 78-18 12-18-78 liigh Bismuth Coolant hnp. Mechanical binding in recorder Cleaned contacts and oiled drive mechanism e L -_ ___ ___ _ _ _ _ _ _
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