ML19309C397
| ML19309C397 | |
| Person / Time | |
|---|---|
| Site: | 05000054 |
| Issue date: | 03/31/1980 |
| From: | UNION CARBIDE CORP. |
| To: | |
| Shared Package | |
| ML19309C395 | List: |
| References | |
| NUDOCS 8004080551 | |
| Download: ML19309C397 (4) | |
Text
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O ANNUAL Rt?0RT FOR 1979 FOR THE UNION CARBIDE NLCLEAR REACTOR (UCNR)
DOCKET 50-54. LICENSE R-81 A. FACILITY MODIFICATION AND MAJOR MAINTENANCE
- 1. A backup 4T system was Installed. This backup unit shares the control room digital readout display installed in 1978 for the original aT digital system. Both primary and backup systems were calibrated.
- 2. A controller was Installed on the stall primary coolant exit valve which allows for remote automatic valve control from the control room.
3 A valve closed alarm circuit was installed on the check valve immediately downstream of the primary pump. This alarm indi-cates in the control room that the check valve has closed as designed when the primary pump is de-energized.
- 4. A new primary resistivity system was installed measuring the resistance of the primary water before and af ter the heat ex-changer. A large difference in readings between the two will set off a le;si alarm Indicating possible seconcary to primary in leakace.
B. PROCEDURE
S MANUAL 1
Amendment No. 14 to License No. R-81 was issued May 17, 1979 and incorporated in the Union Carbide Research Reactor Technical Specifications. A complete revision of our operations procedures manual was thereafter completed to incorporate any changes brought about by the incorporation of the technical specifications. This procedures manual revision and other minor procedures manual changes did not contain any unreviewed safety questions.
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C. ORGANIZATICNAL CHANGES The following 2.s the Union Carbide Corporatica Reactor Mministration Organization.
Vice President Manager Heal th, Safety Nuclear Products R. E. Bol1Inger I I Susiness Manager Nuclear Safeguards Manager Heal tn, Safety Radiochemicals Ccmmittee & Envi ronment Affai rs J. J. McGovern J. J. Agresta, Chm. C. J. Kennerth l
Manager, Nuclear Senior Development Ooera t ions Scientist M. H. Voth K. D. George l I Reactor Project Facili ty Engineer Chief Reactor Engineer Ocerator W. G. Ruzicka H. C. Hart R. A. Strack D.
SUMMARY
OF UNSCHEDULED SHUTDOWNS The following is a listing of all unscheduled shutdowns occurring in 1979 :
Comercial Power Outage . . . 20 Manual Shutdown (Reactor ,
Safety Not Related) .... 1 Shut down to change safety amo l 1 Apparent abnormal AT indication caused l by thermal stratification l
1 Operator error 1
Manual Shutdown (Reactor Safety Related) ...... 1 Manual scram light, no scram action 1 Loss of normal building ventilation 3 Spot on core False Signal ........ 3 Log N 2 Safety .knp 1 1
2 Sample moved close to detector
D.
SUMMARY
OF UNSCHEDULED SHUTDOWNS (Continued)
Equipment Failure . . . . .. 5 Rod Magnet 2 Safety Amp 1 Flapper Switch 1 Guide Tube Lift (faulty switch) 7 Loss of mag. current 1 Loss of 24 Volt Fuse Automatic Safety Action nitiated . ..... . .. 2 Flux probe lift of guide tube 1 Primary pump orime lost, low water level scram in each case a determination of the cause of the shutdown was made and the prescribed corrective action taken. There is a continuing effort made to reduce the number of unscheduled shutdowns within our control by prevent-ative maintenance and equipment replacement.
E. POWER GENERATED Total power generated in 1979 was 40,569 megawatt hours. The reactor was operated on a seven (7) day a week schedule with refueling and maintenance shutdowns about once every two (2) weeks.
F. ROUTINE TESTS CONDUCTED All required routine tests have been performed as scheduled.
G. FUEL Twenty (20) fuel elements containing aluminide (U-Alx) fuel matrix manu-factured by C E R C A (France) were received by the Union Carbide Re-search Reactor in 1979 No fuel was shipped from UCNR during 1979 H. Fif teen members of the Reactor Operations Staff and one Health Physics Technician received exposures in excess of 25% of that allowed or recom-mended in 1979 These doses ranged from 1.26 Rem to 3.58 Rem with the overall average being 1.92 Rem.
No visito. s to the facility received exposures greater than 25% of that allowed or recommended.
- 1. OFFSITE RELEASES OF RA0lATION The following is a summary of the nature and amount of radioactive effluents from the reactor facility released or discharged to the environs determined at or before the point of release or discharge. The summary below is for air and water discharges for the last quarter year of 1979 Technical spec-Ifications for reactor went into effect on 17 September 1979.)
- 1. Air Releases
- a. Noble Gases Isotooe Quantity Released (Curies) 83mKr 99.6 85mKr 279.2 87 Kr 26.8 88 Kr 363 3 133mXe 96.8 133 Xe 3078.9 135mXe 625.3 135 Xe 1749.8 85 Kr 0.4 Total Noble Gas release 6320 Ci Average Concentration of Noble Gases in Stack 3.4 x 10-5 uCI/cc
- b. lodines Isotope Quantity Released (Curies) 125 1 0 30 Ci 131 1 0.14 Ci Average Concentration at Stack 1251 1.6 x 10-9 uCi/cc 131 1 7.2 x 10-10 uCI/cc
- c. Particulate There were some small releases of particulate activity which are being evaluated. These releases are most likely daughter activity of the noble gases.
- 2. Water Releases Total Water Discharged from Site 7.08 x 109 cc Total MicroCuries Released 47.1 uCT Average Concentration Released 6.6 x 10-9 uCi/cc (including background)
Composition of Releases low level unidentified 4-