ML20132H050
| ML20132H050 | |
| Person / Time | |
|---|---|
| Site: | Purdue University |
| Issue date: | 12/31/1984 |
| From: | Stansberry E PURDUE UNIV., WEST LAFAYETTE, IN |
| To: | |
| Shared Package | |
| ML20132H016 | List: |
| References | |
| NUDOCS 9612270122 | |
| Download: ML20132H050 (7) | |
Text
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3 SCHOOL OF NUCLEAR ENGINEERING Purdue University West Lafayette, Indiana 47907 e
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9 REPORT ON REACTOR OPE 1ATIONS For the Period January 1, 1934 to December 31, 1984 PURDUE UNIVERSITY REACTOR-1 .
r PURDUE UNIVERSITY West La f aye t t e , Indiana 47907 March 1985 Prepared by Eldon R. Stansberry l
Reactor Supervisor I
I
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- 1. INTRODUCTION This report is submitted to meet the requirements set f orth in 10 CFR 50.59 and the technical specif ications of the Purdue Univer-si ty Reactor (PU R-1 ) f or the period January 1,1984 to December 31, 1984.
The total number of visliors f or the reporti nq pt. . .. , os 681 per sons. This nunber incl uded 67 tour groups end s3 visits f cr the purpose of mai ntenance or surveil l ance tests.
- 2. PL ANT DESIGN AND ' OPERATIONAL . CHANGES
. 1 2 1 Facility Desig: Chances There were no design changes to the f acil ity in 1984.
2.2 Performance Cheeseteristics Operations of the PUFF 1 f acil ity continued satisf actorily dur-ing 1984. During the annual Inspecti on of the f uel pl ates no change codi d be identif ied. A visual inspection of the surf aces of two represe ntativ e f uel pl ates f or ev idence of corrosi on or def ects, and the measuring of the thickness of the pl ates with a micrometer to ver i f y the i ntegr i ty of the cl addi ng w as i ncl uded i n the i nspecti on. Fuel perf ormance continued satisf actory during the year, l
2.1 Channes la Ooerating Procedures Concernino Saf ety of Facilltv Ooerations No changer, in the operating procedures of th e f acil Ity were made during 1984 2.1 Results.R1 .SurveliIance lgsts,and insoections 2.4 1 Reactivl,bt Limits !
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l The reactiv ity worths of the control rods were de term i r.c d
- to be as f ol l ows
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2 Shim-saf ety #1 - 5.02%
Shim-saf ety #2 -
2.67%
Regul ati ng Rod -
0.25%
Using control rod worth curves that were checked f ol l ow ing 1 control rod I nspections, the excess was cal cul ated to be 0.49%.
On the basis of these val ues the shutdown margin was cal cul ated to be 7.45%.
The control rods were inspected on thy 21, 1984 and no evi-dence of change or deterioration was indicated.
No experiment was pl aced in the reactor pool during 'the year that would require the determination of its reactiv ity dur-ing the initial critical ity following its installation.
2.4.2 Reactor Safety Systems Each reactor saf ety system had a channel test perf ormed on
- it during the prestartup check, prov ided the shutdown exceed 8
. hours or if the system was repaired or de-energized.
Each reactor saf ety system had a channel check perf ormed at time interval s of less than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during operation.
On July 5,1984 the electronic cal ibration of al l saf ety channel s was compl eted.
The irradiation of a gol d f oil f or a power cal ibration was made on May 25, 1984. No si gn i f icant ch ange was i dent i f ied f rom th i s cal ibrati on.
The radiation area monitors and the continuous air moni tor were checke d f or normal operation during the prestartup check that precedes each run. Cal ibration of the radiation area moni-tor s was completed on January 31 and August 31 during 1984 and the cal ibration of, the continuous air monitor was compl eted on bbrch 30 and September 28 during 1984.
The rod drop times were measured on May 22, 1984 f ol l ow ing the control rod I nspect i ons. The rod drop times f ell betwoon 511 and 542 mil l iseconds. These val ues are consi stent with past measur ements and are well within the specification iimits 9
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of 1'Second.
l 2.1.1 Primarv Coolant Svstem l The weekly' measurements of the pH of the primary cool ant f eel between 5.0 and 6.4 during 1984, which are within specif i-cation i lmits of 5.5 + 1.0.
Conductiv ity of the' primary cool ant was measured during the prestartup f or each run and never exceeded 1.32 micromhos-cm -
during the year. This represents a resi stiv ity of more than 750,000 ohm /cm which exceeds the l ower l ir. it of 330,000 ohm /cm ar. glven in the specif ications.
'The height of water above the core was 13 feet or greater f or each reactor run according to the prestartup check i ists f or the year. The specif icaticin of 13 feet of water was al w ay s -
either met or sxceeded.
Personnel f rom Radiol ogical Control collected and analyzed
. month l y sampl es of the primary cool ant f or gross al pha and beta act iv i ty. No act iv I ty of ei ther ki nd w as i dent i f ied i n the sam-pies which would indicate no f ailure of the f uel pl ates.
2 1 1 Containment Val ues of the negative pressure in the reactor room were recorded weekly. Readings between 0.065 and 0.15 inches of water exceeded the minimum of 0.05 incher req ui red by the speci f icati ons.
San i-annual ly the inl et and outl et dampers are checked along w Ith the ai r condi ti oner f or proper operation. These checks were made on April 27 and October 29,'1984.
Fuel plates were visually inspected and measured f or thick-ness on May 21, 1984. No indication of change was identif led in the cl adding. The surf ace condition of f uel pl ate #4-3-73 was i denti f ied as bei ng unchanged.
2.1.5. Exoeriments 1
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i The mass of .the singly encapsulated samples and the flux of l
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the reactor are such that the complete release of all gaseous, !
particul ate, and vol atil e omnponents of the ?sampl es woul d res'ul t I i n . 6oses in excess of 10% of th'e equivU'ent annual doses as !
., stated .i n 10 CFR 20.
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No samples of unknown composition or that required doubl e ;
i , encapsul ation were. submitted f or irradi ation. . l i
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I 21 Changos, Tests juuj Exoeriments Reauf ring Commission Author i z rt- !
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.. i, No changes, or experiments which required authorization from j l the' 0anmission pursuant to 10 CFR 50.59 (a) were pref ormed during l- 1984 -
2.6 Changes.1D Facilitv Staff ;
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( - No changes in the.f acil ity staf f occurred in -1984 'l
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- 3. POWER GENERATION )
Operation of the FUFF1 during 1984 consisted of 32 runs which !
generated - 547,594 watt-minutes of energy and covered an integrated ,
running time of 86.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, i i
- 4. UNSCHEDULED SHUTDOWNS During 1984 there was Just one un sch edul ed sh utdow n. This l* ' sh ut dow n was caused when the magnet power dropped more than normal
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as the pow er i ncr ease d, causi ng rel ease of the control rod.
In str umentati on does dri f t but this was the f irst i de nti f ied j instance of prenature lovering of the magnet current. It has not
! boon observed si nce.
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- 5. MAINTENANCE No mr.l ntena nce beyond the us ual routI ne malntenance was requi red f n 1984.
- 6. CHANGES, TESTS.6BD EXPERIMENTS No changes, tests or experiment s were carried out w ithout frior Commission approv al pursuant to the requiranents of 10 CFR S. 50.59 (b).
- 7. RADIOACTIVE EFFt_UENT REl EASES No measurabl e amounts of radioactive ef fl uents were rel eased I to the env irons bey ond our of f ective control, as measured at or
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prior to the point of such rel ease. i
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