ML19305B795
| ML19305B795 | |
| Person / Time | |
|---|---|
| Site: | 05000077 |
| Issue date: | 01/31/1980 |
| From: | Ebert D, Jordan E, Keene W CATHOLIC UNIV. OF AMERICA, WASHINGTON, DC |
| To: | |
| Shared Package | |
| ML19305B779 | List: |
| References | |
| NUDOCS 8003200397 | |
| Download: ML19305B795 (60) | |
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THE CATHOLIC UNIVERSITY OF AMERICA SCHOOL OF ENGINEERING r ARCHITECTURE MECHANICAL ENGINEERING DEPARTMENT
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1979 ANNUAL REPORT OF NIJCLEAR REACT 0F, ./ERATIONS AGN-201 Nuclear P.eactor, Serial 101 Facility Operating License R-31 Docket 50-77 Janua ry, 1980 Dr. David D. Ebert Reactor Supervisor
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Mr. Varren E. Keene Radiation Safety Officer Dr. Ed.vard D. Jordan Reactor Administrator Dr. Mario Casarella Acting Chairman, Mechanical Engr. , I l 8003200 3 9 7
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l ABSTRACT Y . The 197f Annual Report of Nuclear Operations provides a summary of reactor operating experience, facility maintenance and design changes, surveillance tests, summary of radioactive effluents released to the environment, surveys conducted in and outside the reactor facility, and a summary of radiation exposures received by facility personnel and visitors for the time period January 1, 1979 to December 31, 1979 This report is prepared in accordance with the Technical Specifications of Appendix A, The Catholic University of America Facility Operating License R-31, Docket 50-77, Amendment No.7 issued by the U.S. Nuclear Regulatory Commission on March 12, 1979 i
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A. Reactor Operating Experience
- l. The reactor was brought back into. service at noon on May 9,1979, af ter
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being in the shutdown condition since February 22, 1975 Prior to this event, Dr. David Ebert was issued a Senior Reactor Operator License (SOP-3426) by the Nuclear Regulatory Commission (NRC) on January 17, 1979 The Facili ty Operating License No.R-31 was renewed by the NRC on March 14, 1979 A Reactor Restart Report was prepared and submitted to the NRC on August 9,1979 This
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report is reproduced in Appendix A. - No changes to the facility design or performance characteristics which relate to reactor safety were undertaken'during the reporting period. Routine startup, operating procedures and emergency procedures have been modified considerably from what had existed previously. These procedures were approved by the Reactor Safety Committee prior to restart. Copies of these procedures
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are reproduced in Appendix B. Routine surveillance tests and inspections have been carried out at intervals specified in Appendix C. Resul ts of these surveillance tests and inspections are contained in the Facility Maintenance Log and the Reactor Operations Leg. The reactor has been used almost exclusively as part of a Nuclear Engineering Laboratory course which was offered during the summer and fall semesters of the reporting period. Some of the experiments conducted with the reactor con-I sisted of /M approach to critical, power calibration, control rod calibration, and flux distribution. There were a total of 33 meaningful startups carried out during the reporting period, for a total of 14.6 hours at critical conditions. A monthly tabulation of reactor operation is sho~wn in Table 1. Also' contained.in Table 1 l
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is a listing of scrams, both scheduled and unscheduled. Details are covered in the next section. A routine inspection of reactor operations was made on October 29 & 30, 1979 by C.O. Gallina and K.E. Plu.r.l of the NRC Region I office (Inspection #50-77/79-03). Two minor items of noncompliance regarding posting of notices were identified. These noncompliance items were corrected on
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November 5, 1979
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A concurrent investigation was undertaken by the same two investigators which covered several allegations relating to the operation of the reactor and related radiatio . safety and securi ty programs (Investigation #50-77/79-02). The allegations were part of a petition flied with the NRC on October 3,1979 The results of the investigation indicated that..."of the seven allegations investigated, five were found to be unsubstantiated. The remaining two allegations, while substantiated, involved minimal impact on reactor operations,
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safety and/or security, and did not violate any licensee or NRC requirements. No items of noncompliance or deviations are cited in this report."
- 8. Unscheduled Reactor Shutdowns and Scrams i l
Manual Scrams: There were a total of 18 manual scrams, one of these was
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1. unscheduled. This unscheduled scram occurred when the operator inadvertently brushed gainst the scram button located on the horizontal expanse of the control panel .
- 2. Period Scrams: There were a total of 25 period scrams; all of them were unscheduled. Seven of the 25 were due to operator error, the remaining 18 due to Ins trument mal function, The period meter is a signal differentiating instrument which is connected to the Channel 2 log ammeter. Small fluctuations in the Channel 2 ammeter cause much larger fluctuations in the period meter
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, . , , . - which subsequently caused the 18 period scrams. The problem was traced to a small amount of water leaking into Channel 2 neutron detector housing causing fluctuations in the detector current. When the detector and housing were dried, the large fluctuations disappeared.
3 Channel 1 High Level Trip: There were three high trips on Channel 1. These were all due to operator error by either not changing scales soon enough or changl'ng scales in the wrong di rection.
- 4. Channel 2 Low Level Trip: There were two low level trips on Channel 2.
Both were due to the reasons discussed under period scrams, for large negative fl uc tua t ions. 5 Channel 3 Low Level Trip: There were 11 low level trips on Channel 3 Five were due to operator error by either not changing scales soon enough or changing scales in the wrong direction. The remaining 6 low level trips were due to large fluctuations in the ammeter current. The. source of these fluctua-tions is not clear. It is apparently not due to moisture in the detector housing, however~. The fluctuations come and go unexpectedly, subsequently I making it difficult to locate the cause.
- 6. Channel 3 High L'e vel Trip: There were 4 high level trips on Channel 3 l
Two were due to operator error due to the same reasons given in section 5 The remaining two were due to large current fluctuations as described in section 5 also. C. Preventive and Corrective Maintenance l No major safety. related corrective or preventive maintenance were performed l I since the last Annual Report which would have an ef fect on the safe operation j of the reactor.
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D. Changes Which Affect the Facilities Description None E. Changes to Procedures as Described'Ib the Technical Specifications
- 1. Item 16.6.1.2 - The office of the Executive Vice President and Provost has been separated into two offices, that of the Executive Vice President and separately that of the Provost.
- 2. There has been extensive changes to the following procedures: Routine startup, operation, shutdown and emergency. Copies of these procedures are reproduced in Appendix B.
F. New or Untried Experiments None
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G. Radioactive Effluents -
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- 1. Liquid: None .
- 2. Airborne: None 3 Solid: None
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H. Environmental Radiological Surveys Performed Outside the Facility No radiation surveys were performed outside the Facility during operation. i However, the gamma field at the reactor console during 25 MW operation was 0.3 mr/hr. The gamma field at the nearest outside wall is reduced by a factor of 10 compared to the reactor console. There fo re, it can be concluded that the maximum gamma field at an outside wall would be about 0.03 mr/hr. No neutron radiation would be detected outside the facility, Random wipes of surfaces both inside and-outside the Reactor Room have not detected any loose surface activity above background. I. Radiation Excosure for Staff & Visitors Greater than 100 m REM None
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o TABLE I REACTOR OPERATIONS DATA RUN NUMBER OF NUMBER OF HOURS OF MAX POWER MONTH NUMBER STARTUPS SCRAMS + CRITICAL LEVEL TYPE OPERATION (mW) May 530 1 M 0.3 2 June 531 3 attempts M - -
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532 1 P 0.2 7 -
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~533 1 M 1.5 42
" 40 534 1 3P 0.75 July 535 1 3P,HLi*,LL2,LL3 0.2 5
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536 3 7P,HL1,HL3* 2.0 18
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538 3 4P,3LL3* 1.0 11
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539 1 P 1.0 9 Sept. 540 1 M 0.5 39 Oct. 541 1 M 0.2 35
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542 1 M,LL3* 0.2 40 Nov. 543 1 P*,2LL3,HL3 0.75 40
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544 2 2M,LL2,LL3,HL3 0.5 39
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545 2 2M,LL3 0.5 41
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546 4 M*,3P*,LL3* 2.0 8 Drc. 547 1 M,P,LL3 0.5 40
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548 2 3P*,HL3* 0.5 6.5
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549 1 M,HL1 0.5 40
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550 *5 SM 1.5 14
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M = Hanual Scram , P = Period Scram HL# = High Level Scram on Channel # LL# = Low Level Scram on Channel #
* = Operator Error For example; 2LL3* - means two low level scrams on channel 3, both of which were operator errors.
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The Ca thol i c Universi ty of' Ameri ca School of Engi~ncering & Architecture . Mechanical Engineering Department
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Reactor Restart Report AGN-201 Nuclear Reactor, Serial #101 Facility Operating License R-31 Docket 50-77 August 9,1979 i
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Dr'. David D. Ebert React!or Supervisor
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Mr. Varren E. Keene Radiation Safety Officer Dr. Edward D. Jordan Reactor Adminis trator
- Dr. Yun C. Vhang Chairman, Mechanical Engr. Dept.
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ABSTRACT .
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This report presents the reactor restart procedures and results which verify that the reactor has been restarted and operated in accordance with the Facility Technical Specifications. .
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Backgrounh and Introduction
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- t . The reactor was placed in the shutdown condition on February 22, 1975 and not operated again until May 9,1979 Repair work was initiated on June 15, 1978 by Dr. David Ebert and Mr. Vindsor Dempsey. Dr. Ebert I
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received a Senior. Reactor Operators License ( on January 17.1979 and the Reactor Operating License was extende iother 20 years on March 12, 1979(2) . Re air and necessary paperwork to ve. , and document conformance to the new Technical Specifications was completed on May 8,1979 The reactor was restarted on May 9,1979 following the approved Reactor Restart Procedures (approved by the Reactor Safety Committee).(3) O in the subsequent months following restart,1) a power calibration, 2) 1 control rod calibrations, 3) measurement of k,x and, 4) verification of '
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shut down margins were performed and observed to be both consistent with f. previously determined values and to conform:with the Technical Specifi- ,
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cations.(2) The reactor is now being operated on a routine basis.
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Details ,
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A. Prestartup Maintenance and Surveillance
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The following list presents the prestartup items which were checked
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, 1. ' Shield tank level test and calibration
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- 2. Shield tank temperature test and calibration
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3 Seismic displacerrent test and, calibration
- 4. Thermal column water level check 5 Emergency lighting check
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- 6. Channel I count rate, plateau, safety c,ircuit calibration O 7 Channei 2 levei, period, safety circuit calibration
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- 8. Channel 3 level, and safety circuit calioration
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S. Visual inspection and leakage check ,
- 10. Control rod insertion and scram tihe calibration
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- 11. Reactor scram from loss of electr.I' cal power
- 12. Radiation 5onitoring equipment calibration
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13 Control rod drive inspection, lubrication
- 14. CUA Reactor Safety Committee review of the startup procedure and the operating and emergency procedures
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1 B. Reactor Restart Procedures and Results g REACTOR RESTART PROCEDURES
- 1. . Verify that all the maintenance and tests are in conformance wi th the Tech Specs. and have been car'ried out and documented. .
- 2. Perform I tems 1-9a of the Prestartup Checkout Procedure, but leave the Cd foil inserted in the glory hole position.
l _. . 3 Undertake a 1/H plot as SR #1 is inserted, estimating the critical position l
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of each step.
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- 4. Assuming that the reactor is still subcritical with the SR #1 Inserted, t estimate the subcritical neutron multiplication constant (k) under the l
condi tions that all rods are out of the core (ARO) and the Cd foil inserted. h This k will be - K,5 I- SM where R; is the ratio of the neutron detector ;
. readings of SR #1 out tol-Rt inserted (R y<:1). R; can b'e computed for each detector I
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and applied, and then averaged and appl.ied. A gg is the assumed reactivity worth of SR #1 ( N 0.0125). f.
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S. Ko shod d be less than 0.M. Es number is obtained by O " T ~O'00lb -- '. . . ... i. e + kex - 3(
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This is the ARO shutdown k referenced to 20*C, assuming the Cd has no
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negative reactivi ty worth. If K is not <0 9654, step 6 should not be under-
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taken until the discrepancy is resolved. Return to the ARO condition. Record
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- 6. all three neutron detector readings. Withdraw the Cd foil in approximately
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I inch incremants, performing 1/M calculations at each step. Also, estimate the reactivity worth of the change in cd position using the relation.
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'A.y X (I-kM i-Ro)
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where R is the ratio of detector readings at the initial condition to the O , present posi tion of the Cd. (46 should be less than approximately 0 9654
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otherwise the estimates for SR and CR and/or k are in error. If this is not the case, Step 7 should not be undertaken until the descrepancy is resolved. 7 From the above information, assuming that the Cd foil has been removed, estimate and verify a. that the shutdown margin (wi thout Cd foil) is ?f 2 Io l2. j with the most reactive rod inserted; b. that the estimated k is /,. O . 6 5 7o it., e c; that the reactor will be subcritical with the least reactive SR or CR withdrawn.
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- 4. hu = he + A c.1 l VeiC y ksta- + Agsgi A o.98 a kssa 60.% E O s). t +6 ~ hsg + s (Q + a m
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" kex ~ ksw4 ' - 1 + o. o39 t
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W Wey f O.(G Vo k 4.t.c.O. u 34s.M1 h c). J
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be sAs4iej iC agu * $.cnts akA
- 8. Provided that all the above conditions have been , satisfied or discrepancies resolved,1/M measurements should be undertaken as the SR #1 and 2 are inserted.
Af ter SR #1 has been inserted it should be scrammed according to Prestartup Check 9b. Likewise, af ter SR #1 and 2 have been inserted they should be scrammed
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according to Pres tartup check 9c. .
- 9. Criticality should be achieved at the lowest practical poser level since a power calibration has not been undertaken for 5 years (approximctely id4).
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- 10. As soon as practical af ter the initial criticality, the following tests should be performed:
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- a. Power Calibration *
- b. Control Rod Calibrations -
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- c. Measurement of K
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- d. Verify that.
- 1. Shutdown margin 7f R ic, with the most reactive rod inserted,
- 11. The reactor would be subcritical with the least reactive CR or l
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SR removed. -
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- l II. Reactor Res tart Procedure Results.
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- l. Refer to the operations log
! 2&3 See Appendix A for copies of the appropriate sections of the' ! ! operations log. The pertinent data is put in tabular form in
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Table 1 and plotted in Figure 1.
- 4. - k, ;; 0 79
- 5. k, < 0 9654
- 6. See Table 1 and Figure 1.
Apcd ;; 2.73% ak/k
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k + apcd = 0.82 < 0.9654 7.a) k shut = 0.8173 < 0 9675 - r
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c) Since b) is satisfied, so is c).
- 8. See Table 1 and Figure I and Appendix A 9 SeeTableIandFigure1andEppen,dixA. Criticality achieved at
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approximately 11 nM power on May 9,1979. . -
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_ . Chann61 #1 = 584K cpm /100 cu -
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- Channel #2 = 114% / 100 mW
. Channel #3 = 4.13 x 10'I Amps /100 mW These factors are consistent with those obtained in the past l years of operation.
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. b) Control Rod Calibration Results: . -
The integral rod worth for the fine control rod is given in Figure 2. The total worth of the fine control rod was deternined to be 0.142% ok/k and the dif ferential worth was measured to be
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76 pp/cm in the linear region of the range. The differential rod worth for the coarse control rod was determined to be 607 pp/cm.
%e total worth of the coarse control rod was inferred to be i i
1.14% ak/k. These values are consistent with those obtair.ed in 1
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the past years of oner.' tion.
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- c) k Calculation: *
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The excess reactivity at 20*C which would result if all the
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control and safety rods were inserted was determined to be 0.435% 0# k. This valta is less than the Tech. Spec limit
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of 0.65% ak/k and is consistent with the value obtained I'n
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the past years of operation. i
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s d) 1. The shutdown margin with the most reactive rod inserted I at 20 5*C was determined to be -2.0% ak/k. The choice of
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20.5'c was cho;en becatse . this was the lowes t temperature at which the reactor was operated since May 9,1979 This particular Limiting Condition for Operation r (LCO) therefore O defines the minimum tengerature for operation when the 91oh
'1 hole is empty and the normal material in the Access Ports.
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II. The shut down margin with theleast reactive coarse or
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safety rod removed and the oth'er rods inserted was determined
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to be -0 71% ak/k at 20.5'C. This value is within the limits
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established by the Tech. Specs.
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References .
- 1. Senior Operator License flo. 3426, Docket No.55-6671, January 17, 1973
- 2. Amendr$ent No.7 to the Facility Operating License No.R-31, Docket No.
50-77, March 12,1979 3 CdA Reactor Safety CorEnittee Heeting Hinutes, May 2,1979
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TABLE 1 inverse Mul tiplication Results
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.j Condi tion ' ', 'Date & Page Ch 1 Ch 2 Ch 3 Ave i- cpm 1/M -12 gjg
% 1/M x10 373 nmo
- 1. ARD, Cd in 5/2/79 560 140 1.0 1.0 0.80 0.017 1.0 1.0
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160 0.88
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- 1. ARD, Cd in 5/7/79 562 135 1.0 0.018 1.0 0.80 1.0 1.0
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150 0 90 0.02
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0 90 0 95 0.84 0.88
- 4. SR#1 In, Cd Out " "' '
200 0.68 0.023 0 78 1.15 0 70 0 72 ,
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- 5. SRf1 1 & 2 in, 1 Cd out .' " "
250 0 54 0.04 0.45 0.42 o
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1.90 0.47
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l . ARO , Cd in '5/9/79 565 150 1.0 0.018 ,1. 0 0.85 1.0 1.0 ! 3.h,Cdout " "' 175 0.86 0.018 1.0 0 95 0.89 0 92 I5.SRf1&2'in " " Cd Out 0 52
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290 0.032 0.56 19 0.45 0 51 i 6. SRf1 5 2 in . Cd Out, FR $ at 15 cm " " 300 0 50 0.038 ' O.47 2.0 0.43 0.47
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5 cm " " 320 0.47 0.04 0.45 2.4 0 35 0.42
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- 8. " & CR at 10 cm " "
360 0.42 0.045 0.40
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27 0 31 0 38 e3. " & CR at 15 cm " " 490 0 31 0.073 0.25 4.2 0.20 0.25 10." & CR a t 17 5 cm ' " " 900 0.17 0.12 0.15 70 0.12 0.15 (11." & CR at I 19 0 " " 1650 0.c91 0.25 0 072 13.0 0.065 . 0.076
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- 89*
O - g . . . . yk Run 1 -
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i
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AGil-201 : Serial //101 ,
* * * **
Reactor Op: rations Log *
'.,-
Date J /#4f 77
. .: .. .
- . .
Reactor Opcrator //[ r/ gfn/gg ~ Senior Reactor Operator od/f. g &,6 s t'er;r 7 Reason fo'r 0pcratIon ha -/:./ +/' #d ('* M r T-k'
- Authortzed Experiments y> s A4 S-r7ng C/ A N'/h & N -
. ~ 'Spectal Operating Limitations 2),r -r e ,e.i r e n _ W 1 A n t f ~~
M'N M
'
- Shield Vater Temp *erature /f. g/ (*C) Es timated Excess Reactivi ty (%Ak/h)
-
.
j Prestartop Checklis t
,
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., ,,;;,'
,. -
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<
'l- is
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', 1. All Reactor !!cutron Detectors Vorkingy-' b. . Channel 1: *
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I. High veltage 4/# # (VDC)
# ".
- -
ii. Zero check. Radiation Survey:
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- 2. .
. 111. Calibratcycoo _(cpm) -
..
, ,
lie ter type and number 5??cu-wr F-/J-r2
, , Calibration iv. fl.igh level trip 7.S (%fs) ..
--
//- 3 /f //nme Low level trip /c (%fs) -
, .. . Max. survey reading (p O /.c < m 2 / s vr., C v. it. Operate /94 (cpm) /
Location '72euru Ji1_
,
*
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-
- c. Channel 2.
-
*
- ^" -
*
- l. Low level trip O OO/.f(~tfp) 3 Safety Feature Checks: ,
.
g g , . Fligh level trip /o o (%fp) 111. itigh Cal . rm 7
-
Thermal column scal _ ,
, .
)
'
Hanhole cover scal gy, . Ie ro c h e c k , ~ ;' - Ip)
'
Access p crt fill'ers ins talled t/ , v. Low Cal. ~8Di 'l
. Cd in glory hole 5 - -
vi. Period scr'am t/ M *
. , . Wa ter , temp. swi tc in place t ~"
vil'. Operateg /7 (%fp)
*
.
-
Skirt area OK *
. . . :
. .. .
-
i d ,. Channel 3: -
.. .-
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*
^
Zero chect V .
-
- 4. Area Radiation Moni tor Check. 4 .J'j.
p Calibration check OK V
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. Al a rm s e tpoi n t s 7ma,6,. //y5 /,(- .
;(;y, tog- level trip /d (%fs)
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* *
*
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' l 'v .
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High' levc! trip 59 3 (tfs) . 5 Control Rod Drive Settings Check M y v. Recorder 3K
- . . . . .. . .. . vi., Operatc ,_, ,-~ ) . 3,
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- 6. flearby Persons informed / s
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Rod C'ontrol Interlocks ar.d Scram
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. 9
. M
- A. Checks: '
7 r.cy' in Consolo and Power on -
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- a. Sequence interlocks OK ..
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- b. Safety 1 St. ram OK V .
- 8. Instrument Calibration and Level Trip c. Safety' I cod 2 sc7En 0K
- Sctpoints: - -
- 10. Cd Removet from the Glory llote
- a. flo temporary wiring installe'dg k
~
. 11. Cal cul a te- excess .
,) Co.mpleted by \AS.'De v ApprovedbyJ _,_1
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'
Somor iteactor 0; e: ator f.cviewed liy, CQ g. [ Reactor Supervisor
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Page D S L O
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- ACil-201; Serial #101 'Run f .
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, Ifcactor Operations Lcp ,
Date F/1[~7')
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Reactor (,perator \AJ . Di%Eca. Senior Reactor Operator D. b ' Activi ty _ h/3,v'xlb{a ,w new_ lParkk _,_ _
.. . [, , %_ go$d LL4 Toebh .
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TlHE . DETAILS - '
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- . Page i SGI
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- AGil-201 : Serial #101
- Run #
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Reactor Operations Log Date L. .M
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Reactor Operator W' Shoe h
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Senior Reactor OperatorI) d D. NA b Reason for Operation Mb
* '
- g. k. ,
Authori zed Experiments cd. ek b/ Aqh,[E-r Sk 9 dM8f7J ~ Special Operating Limitations 4%G2
,
C.AA N bv -
.
Shield Water Temp *crature f i.5 (*C) Es timated Excess Reactivi ty (%Ah/k) .
.
- Prestartop theckt ist
. . . - -
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. . . . ?....
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't. All Reactor. Neutron Detectors Vorking V b. Channel 1: . f. -
High voltage 9/ lou (VDC)
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l.
-?'
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Zero checn . / # S93-
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!!:
-
.ty ,-
- 2. . Radiation Survey:
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Heter type and number hb I' (20 *
* '
- 9 (gf )
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Cal ibra tion 1//'3/16 - LM . Kmh
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//m ,
l I vc tr II (%fs) Max. survey rc'ading,ef1. o.1 y;, g gg- (cpm) Loca tion &%$ n-.$)@ w
-
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- c. Channel 2: ' 'i.'? @
'
- I. Lo^a level trip O.cof f(% p)
.3 Safety Featu're Checks / 5
- 11.- Iligh Icvel trip =/0 0 (2,fp)
Thermal column seal / , Cal . 6 (Up)
'
g . Manhole cover seal Access p crt fillers [ installed vy . - .
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lit. di gy,;.Zero checIUDool (Ofp)
- v. Low Cal . O.0I (%fp)
',
-
Cd in glory hole j ' _
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vi. Period scram / (+ce).
' P vii . Opera te fy.OlG%fp)
-
k c OK . '
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. d ,. Char.nel' 3.: _ .
-f;c4pf' ero chef check OKV d
- 4. Arca Radiation Monitor Check Calibration Alarm setpo. int D.7 m /(vi.2)K /00.r,6 ,.iii. Los level trip /o ~(%fs) f [k. '
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i Iv. High' level trip 9 ( (%fs) . - 5 Control Rod Drive Settings Check 75.C v. Recorder OK # vi.',0perateo.9 5f @ ,
.
Nearby Persons Inforced .
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-9 -
Rod Control Interlocks and Scram
. .. ..
.,, .
Checks: Key in Console and Power On v 7 - -
. /
7
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,a. Sequence.nterlocks0)'V i
- b. Safety 1 Scram OK V /~ .
- 8. Instrument Calibration and Level Trip c. Safety I and 2 scram OK Sctpoints: - .
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Cd Removed.from the Glory Hole
/
10.
- c. No temporary wiring insta!!cd
- -
Calculate excess l 11.
.
7
- - - +
g - Completedbfu.g_) '%,b f.- Approved by,_ p3[vt . _ A}
# Senior I;eactor Operm ur
, ,_ ;
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Revicued 'iy w
- b- ,
Mu $ JC"79 f - Reactor Super 7iE r
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Date I /
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een- -m a w< e- e
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h . . . Page i %2
- D AGil-201, Serial #101 Run f -
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Reactor operations to9
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Date.h M l<1
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Reactor operctor W. D[%
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Senior Reactor operator
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Oh. a f "
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Activity $ fta b M -i t. .
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TlHE - DETAILS
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Page # $(E
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i 9 ' AGN-201: Serial #101 , Run / U >b -
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Reactor Operations Log Datef4e4,_@
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Reactor pcrator /
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br/p Nf Seni r Reactor Op,crato /da.,3 fgmt.7 Reason fo'r Operation /A/f n.,f b TrSS .#M N O '
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Authorized Experiments Nmgz:h /[ co/2A,v6 6 /9b7597'77/4 //f/>( O"W
-
'Special Operating Limi tations m
- b. /th;- F M- G [ mwd
,
- Sh,ield Vater Temperaturc h- /7d)"fY(if$ted Excess Reactivity , pp7fg (%Ak/k)
"
, , . % .V 4 * "'
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,46E Pres tar tua Checklis t .
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' {nOctcctors tan'wh'.n
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. :i. ' All Reactor Meutrofi Vorking ! b. . Channel 1: -
O.
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I. High voltageJ yo O _(VDC) ,,'
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* '
N II. Zero check. ' p .gp3gr43,)
.
- 2. Radiation Survey: , .lii . Calibra tey,o b (cpm)
.. . Heter type and nurr.bergm EMlive AA6 Iv. High level trip fff[. (%fs)
" ' ' ' * '
Calibration // 79' /n= z# y,
-
Low level trip f.a Q (%fs)
. Max. survey read,ing , / 5- <>re / g fe vi. Oper.a te /r8 ~{cpal "
Loca t i on ,7)k?G,ift y- 1 4/:27;L * ^L'.
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- c. Channel 2:
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Safety Feature Checks: /
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- M#
3 5 . 11.
, Thermal coluren seal V, .
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. High level trip 2@p,o (%fp)fp)/w iii. High Cal.
Hanhole cover scal __;t/ i .. Zero checkV~ V (%fp).ooof*/o
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-.,., '
Acce.ss p crt filler s tal led v. W Cd. V W'p , w "A Cd in glory hole vi. Period scram , (sec) < Water temp. swi tch .in place
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Skirt area OKy
--
. vii .- Opera te V (tfp) , o/# 7[
, ,
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- d. Channel 3:
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- 4. Arca Radiation Moni to eck' '-
!. Ca b at on check OK
. Alarm se tpo, int .
[i i . -Low ' level trip /d 7 tis) '
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. ' .I' v . High' level trip A7g (%fs) 5 Control Rod Drive Settings Check 7$ $ v. /v
. vi .
- Recorder Opera te OKg~6fs) V ,g'$-k/d
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- 6. Nearby Persons Info,rmed
,
u 9 Rod C'ontrol Interlocks and Scram
- . J- - '
Checks: -
'7 . Key in Console and Power On
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- a. Sco,uence interlocks OK [
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. b. Safety 1 Scram OK / .
. 8 .' instruir.ent Calibration and Level Trip c. Safety' I and 2 scram OK V Sctpoints: -
- a. No ter.iporary wiring installed
' * ' 'Y "
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, 11. Calculate 33 [ ~
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,1 Completed by_ f/'"/> C C Approved by .O.7,h,J __
Reviewed by M J.V , b . k _]_ Reactor Supervisor Dr
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Ope rntle .,s Da ta n b. -
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- 1. Ini tIal- Control Rod Lo.scr l imi t Posi tions: k. wer Limi.t_ Ins trun:cnt ' Readings :. --
Fine control rod /2-a (cm) '~ Chca'rGl' 'l * : MetL((cpm) ki-Coarse control rod _ pop ') (cm) . Channel 2 t'70 %fP) ' Channel 3 y sio-y (amp)
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. 3. Cf.annel ficter Readings from !!cutron Source: N. '
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Channel All Rods Out only Safety Rods in
* *
. #1 (cpm) /C :2fg) .
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#2 (%fp) , g/,r> , g3;3_.
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- 03 (Dep) , 95~X //) ~ ' ' /, gy/6 - / W ,
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ft . Approach to Cri ticali ty /#3 ( Criticality Attained /p-o a
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(Ti rr.e ) .
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- 5. Power, Meter Readings, and Rod Posi tions: ' '
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r.' ' ~ Time Channel'l Channel 2' Channel 3' Fino Control Rod Coarse Control Rod (cpm)' (% power) (amp) (cm) (cm) _ (. C& . 63 F 7. Jksy' 7 / Coo o077 l4
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- 7. Shutdown Check List.
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- b. All rods dcun *%e. f. Recorder Consolestandby and skirt/of doors f locked ..
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APPENDlX B
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-I-AGN-201 DPERATING PROCEDURES
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I. General Rules and Precautions .
- 1. Approval shall be obtained from the Reactor Supervisor prior to reactor operation (the definition of reactor operation is contained in the Facili ty Technical Speci fications) .
- 2. Only personnel authorized by the Reactor Supervisor and holding a current Senior Operator's IIcense at the facility may keep AGN-201 consol'e igni tion swl tch keys. The keys shall not be left at the console during the absence of such persons.
3 The Senior Reactor Operator shall be at the University Building and informed of operations whenever the AGN-201 is not in the shutdown condition (as drfined in the Tech. Specs.) A second person capable of carrying out any prescribed written instructions, instructions of op-erators, and to summon help in the event the licensed operator becomes
- Incapacitated shall be at the University. ,
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- 4. 'During reactor operation, a licensed operator shall remain at the console l and devote his full attention to operation of the reactor. An authorized person not IIcensed as a Reactor Operator or Senior Operator may operate the AGN-201 only while under the direction and in the presence of a IIcensed operator, and with the consent of the Senior Operator present.
5 The available excess reactivity considering all control rods fully , inserted and including the potential reactivity worth of all experiments shall not exceed 0.65% k , referenced to 20*c.
- 6. Changes of core loading, console Instrumentation or safety circuit wiring, safety system settings or Access Port Loading shall be made only with the approval of the Reactor Superviser. Such changes shall be
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2-referred to the Reactor Administrator and the Reactor Safety Committee as specified in the Facility Technical Specifications. 7 The reactor shall not be operated at a steady state power level greater than 100 milli-Vatts, nor shall power level be permi tted to increase at a rate which would produce a stable reactor period of less than 10 seconds.
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- 8. Reactor maintenance shall only be performed by personnel authorized by ,
the Reactor Supervisor. 9 Procedures which involve handling of radioactive isotopes to be produced in the reactor shall be approved by the Radiological Control and Safety Committee prior to the introduction of the samples into the reactor.
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- 10. Personnel dosimetry requirements for access to the control room and reactor room shall be as posted by the Radiological Safety Officer.
- 11. A Reactor Operations Log shall be maintained.
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II. Prestartup Checkout A. Requi rements I. The Pre-Startup Checks shall be performed:
- a. Prior to each day's operation or prior to each operation extending more than one day.
- b. Whenever the reactor is being started following a shutdown period 'of greater than eight hours.
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- c. Whenever the reactor is being s tarted following a complete loss of electrical power.
- 2. The Pre-Startup Checks shall be performed by a licensed operator.
NOTE A trainee may perform the Pre-Startup Checks if accompanied by, and under the direct super-vision of, a licensed operator. In such cases, the trainee and the licensed operator shall sign the completed checklist. , 3 The Pre-Startup Checklist shall be a part of the AGN-201 Reactor, Operations Log and thus maintained as a permanent record. ,
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- 4. The completed Pre-Startup Checklist shall be reviewed and approved by the Senior Operator present prior to critical operation. Tl s checklist shall also be' reviewed by the Reactor Supervisor, but not necessarily prior to startup.
5 Abnormal conditions shall be immediately reported to the Reactor Supervisor and the condition corrected prior to proceeding with the' checkout. I l l
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. B. Procedure NOTE Determine the present reactor condi tion by inspecting tog entries and operational requests. This information may be used as a guide to the status of the reactor as the pre-startup checks are perforced.
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Fill in the required information at the top of the log record the shield tank water temperature.
- 1. Verify that all reactor neutron detectors are operating and appear to be reading approximately the correct values.
- 2. Verify the operation of the portable 3 -y survey meter with a check source, and make a radiation survey around the reactor.
3 Ascertain that the reactor seals (thermal column tank, manhole cover, and control rod access cover) are intact and that the access port fillers are installed, or as indicated by approved changes. Verify that the Cd foil is in the glory hole, the - water temperature and earthquake interlock switches are in place, and there is no unusual conditions in and around the
' reactor and skirt area.
- 4. Using a checksource, veri fy that the Reactor Room Area Moni tor responds to radiation. Check alarm setpoint. (This check need only be performed prior to the first startup of each day).
5 Check the control rod drive voltage settings at the lower center on the back of the console cabinet. Verify the proper settings.
- 6. Inform nearby persons that the reactor will be turned on and started up.
7 Turn reactor Ignition swi tch on. 8.. Instrument Calibration and Level Trip Setpoints:
. a. Check to see that no temporary wires are installed
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- b. Channel I neutron flux monitoring instrument check:
I 1. Check proper settir.g of the high voltage II. Zero Check; Place the ZERO-0PERATE-CAL swi tch to zero and check zero level. Adjust if necessary. Ill . With the RANGE SWITCH at IOK, place the ZERO-OPERATE- l CAL Switch to CAL and observe the meter reading at 3600 CPM + 2%. Adjust if necessary. IV. With the TIME CONSTANT at 40 seconds, place the RANGE SWITCH to 2.5K and observe the CHANNEL 1 HIGH
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LEVEL TRIP at 90-95% fs. Return the Range Swi tch to 10K. Reset the level trip.
- v. Reset the Channel i Low Level trip and return the ZERO-OPERATE-CAL swi tch to OPERATE. Observe the ,
1 CHANNEL I LOW LEVEL TRIP at > 12% f.s. (corres ponds
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to > 120 CPM on 1 K s'cale) . vi. With the TlHE CONSTANT at 10 the RANGE SWITCH at 250 and the XERO-OPERATE-CAL swi tch in OPERATE, record
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the Channel 1 neutron level and compare with previous shutdown readings. Reset all scram trips. C. Channel 2 neutron flux monitoring instrument and reactor period l
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circuit check:
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I. Place the operate-cal switch to the Low Cal position. Reduce the meter reading using the Low Cat adjust screw until a low level trip is obtained. Adjust trip level If necessary. Reset scram trip. II . Place the operate-cal switch to the High Cal posi tion. Increase the meter reading using the Hish Cal adjust screw until a high level trip is obtained. Adjust the trip level if necessary. Reset scram trip. III .PI' ace the operate-cal swi tch to the Hig'h Ca1 'posi tion. Observe the meter reading at the valve recorded from the most recent instrumer.; calibration. Adjust if necessary. iv. Place the operate-cal swi tch to the ground position. The meter reading should be 0.0001 % power.
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- v. Place the operate-cal swi tch to the Low Cal pos tion.
Observe the meter reading at the value recorded from the most recent instrument calibration. Adjust if necessary. vi. Press the Period Test button and verify that a period scram is initiated at 10 sec. Adjust if necessary. vil. Return to Operate, record the channel 2 neutron level and compare with previous shutdown readings. D. Chiannel 3 neutron flux monitoring instrument check: I. . Disconnect the neutron detector input signal and correct the Positive Current Source to the input Jack on the front of the instrument. Energize the current source and allow at least 15 minutes for warm up. Depress the zero check button and verify the meter zero. Adjust if necessary. II. With channel 3 selected to the range, adjust the input current to amps and verify meter reading at the calibrated point i 2% of full scale. Change the channel 3 Range Selector swi tch to amps and verify the reading at amps 1 2% of full scale. Reduce the test current to approximately amps. III. With channel 3 Range Switch at the posi tion, reset all scram trips. Slowly decrease the input current until the channel 3 Low Level Trip actuates. Verify the trip level at 5 - 10% fs. i IV. With the channel 3 Range Switch at reset all ~ scram trips. 1
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Slowly increase the input current until the channel 3 High l Level Trip actuates. Verify the trip level at 90 - 95% fs.
- v. Position the Varian Recorder selector switch to channel 3 Check the recorder zero and full scale reading by varying the channel 3 ' Input current. Adjust the recorder if necessary, vi. Disconnect the Positive Current Source from the channel 3 input Jack and re-connect the channel 3 detector input signal.
Reset all scram trips and record the channel 3 neutron level. Compare with previous shutdown readings. Deenergize the Positive Current Source and store the test cable.
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NOTE If there is reason to believe that any of 'the flux monitoring Ins tru-ments are not operating properly or are in 'of calibration, the Reactor Supervisor should be inforced and the condition corrected before proceeding. G. Rod Control Interlocks and Scram Checks: .
- a. Reset all scram trips. Observe that the Interlock OK and Scram Interlock open lights function properly as the Interlocks line is interrupted by the trip reset swi tches. Observe that the DOWN limit lights and ENGAGED lights are energized. Depress the MAGNETS ON push button and energize the latch magnets.
Test the sequence Interlocks by attempting to first insert the Coarse Rod and then the No. 2 Safety Rod (should not operate).
- b. Insert SAFETY No. I to its UP limit, carefully observing the neutron flux monitoring instruments for proper " operation.
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Initiate a CHANNEL 3 HIGH LEVEL SCRAM by switching the Channel 3 RANGE SELECTOR to a lower settin'g, observing the SAFETY No.1 is fully withdrawn from the core as indicated by proper operation of the ENGAGED, UP and DOWN limit lights.
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l The ENGAGED light should deenergize and
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- the magnet carriage reaches the DOWN limit.
! If the ENGAGED light re-energizes at an Intermediate posi tion, i t may Indicate the Safety Rod has not been completely withdrawn
. from the core. If this does occur, the Reactor Supervisor shall be notified and corrective action taken before proceeding.
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- c. Reset all scram'alarcs and re-energize the latch magnets.
Insert SAFETY-1 and SAFETY-2 to their UP limits, carefully observing the neutron flux moni toring instruments for proper opera tion. Initiate a MANUAL scram and verify that both rods are fully wi thdrawn from the core as in step G.b. above.
- 10. Remove the Cd foil from the Glory Hole.
II. Using the most recent values for the AGN negative temperature coefficient, determine the available excess reactivity for the existing reactor conditions where:
% Ak 5- = (Excess % ak5- referenced to 20*C, glory hole empty) 1 (% bh *C)(*C above or below 20*C) 1(% -h glory hole loading)
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-- (% ak5- installed experiments other than glory hole).
The Pre-startup checklist will then be reviewed and approved by the Senior Reactor Operator prior to cri tical operation.
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- III. Reactor S tartup
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A. Initial Conditions
- l. Reactor operation has been authorized by the Reactor Supervisor.
- 2. The available excess ' reactivity considering all control and I
safety rods fully inserted and including the potential reactivity Ak worth of all experiments is less than 0.65) g. 3 All safety system Instrumentation is operable.
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- 4. The reactor neutron flux level is greater than 120 CPM on channel 1.
5 The shield tank water temperature is greater than 15*C.
- 6. The reactor pre-startup checkoff has been satisfactorily completed and approved within the guidelines of Operating Procedure No.II.
- 7. Flux monitoring instrument readings corresponding to full licensed reactor power are posted at the AGN-201 console.
- 8. The seismic displacement interlock is operational within the limitations of the facili ty technical specifications.
- 9 The console ke; switch is turned on and reactor power is energized.
- 10. The control and safety rods are at their fully withdrawn position.
- 11. All scram trips and the Interlock I.ine are reset.
- B. Precautions
- 1. To avoid an inadvertent scram, the ranges for chan.iel 1 and channel 3 should be changed when readings have reached slightly greater than mid-scale.
- 2. The reactivity addition rate shall be limited such that the neutron level is not permitted to increase at a rate which would result in a stable period of less than 10 seconds.
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. 3 If abnormal neutron flux levels or instrument operation is observed at any time during the startup, a manual scram shall be initiated and the Reactor Supervisor immediately notified.
The startup shall not proceed until the abonormality is resolved and corrected. h C. Procedure 4, 1. Check the four DOWN limit lights and the four ENGAGED lights ON.
- Depress the Magnets On pushbutton to energize the control and safety rod magnets. Observe the MAGNETS ON light energized.
NOTE The ENGAGED light for the FINE Control Rod has no
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meaning since the rod is not carried by a magnet.
- 2. Record the rod position and flux monitoring instrument readings.
i 3 Insert the Safety Rods, first No. I and then No. 2, to their UP l I limits. During rod insertion, carefully. monitor the flux level ! Instruments to ascertain that Instrument operation and neutron flux level behavior is normal . Observe the rod position windows Illuminated when Safety No. 2 reaches i ts UP limit. ) l
- 4. Record the flux monitoring instrument readings for each channel 1 l
and determine the ratio of Safety Rods UP readings to the readings' ~ l recorded in step C.3 above. Compare with data obtained on l previous startups to accertain proper flux level and ins trument behavior.
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- NOTE If an Estimated Critical Position (ECP) has been calculated to pre-position the Fine Rod at other than i 15 cm, or to preposition the Coarse Rod and achieve cri ticali ty using the Fine Rod, omit steps 5 and 6
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and proceed with steps 7a and b.
- 5. Insert the Fine Rod to 15 cm (near the center of its operating range).
- 6. Insert the Coarse Rod in slow speed to achieve criticality.
7 Applicable to startups for which an ECP has been calculated: '
- a. Insert the Fine Rod (Coarse Rod) to the pre-determined position. j
- b. Insert the Coarse Rod (Fine Rod) to approximately 2-3 cm. below the caluclated critical position and allow instrument readings to stabili ze. Then continue Coarse Rod (Fine Rod) insertion to achieve criticali ty.
- 8. When cri ticality is suspected, withdraw the neutron source and establish a constant neutron level (infinite period) at the
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desired power level. 9 Record rod posi tions, flux moni toring instrument readings and reactor period. These readings should be compared with previous cri tical data and/or the calculated ECP (if applicable) to verify proper reactor operation.
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IV. Cri tical Operation .,
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A. Precautions
- 1. Observe precautions lis ted in Operating Procedure .No.I.
- 2. The Coarse Rod worth us about 1.2-1.4 % , the Fine Rod t
worth about .15 .32 % $. B. Procedure
- 1. Normal Operation
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- a. The reactor is in general controlled with the Fine Control Rod. This is nost easily done using slow speed; however,
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the speed and control rod selected is at the discretion of the operator and will depend upon operator experience and ability. -
- b. If criticality is being maintained wi th the Fine Rod at less than 8 cm., the Coarse Rod should normally be withdrawn such that the Fine Rod may be inserted to an operating posi tion. In the range of 10 - 20 cm.
- c. If criticality is being maintained with the Fine Rod inserted more than 22 cm., the Coarse Rod should be inserted such that i the Fine Rod may be withdrawn to an operating position in the range of 10 - 20 cm.
- d. The 1inear micromicroammeter (channel 3) should normally provide the most sensitive Indication of changes of power level; however, it should be frequently cross-checked with channels 1 and 2.
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- 2. Power Level Changes
'a . Power Level may be increased by insertion of elther the Fine of Coarse Control Rod depending upon the desired reactor period. Normally, the neutron flux is steadled at the new power level by manipulation of the Fine Rod.
- b. Power Level may be decreased by wi thdrawal of either the Fine or Coarse Control Rod. Normally, the neutron flux is steadled at the new power level by manipulation of the Fine Rod.
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- c. If moderator or fuel is inserted into the reactor, or if an absorber is withdrawn, the reactivity will increase. The control rod (s) should be withdrawn and withdrawal coordinated with the insertI6n of approved material such that mininal perturbations to power level are incurred. Such an evolution requires that the potential reactivity worth of the control rods and the material to be inserted be known. If the neutron flux level increases at a rate faster than can be compensated for by control rod withdrawal, a Manual Scram shall be immediately ini tiated.
- d. If an absorber is inserted or moderator is removed, the reactivity will be negative. It is not necessary to follow this change with a control rod; however, if it is desired to maintain a given power level, then control rods should be inserted as necessary and Rod movement coordinated with the negative reactivity insertion, created by the approved material, in order to minimize power level perturbations.
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V. Reactor Shutdown A. Shutdown Procedure
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- 1. To perform either a normal or emmergency shutdcwn, depress the red SCRAM button on the motor control panel, i 2. Observe the following:
- a. Scram alarm Indicator light and bel ENERG1 ZED.
- b. Magnets ON lamp DEENERGlZED.
- c. Engaged lamps OEENERGlZED.*
- d. Up Ilmit lamps remain ENERGlZED.*
[ e. Neutron level decreasing.
- f. Negative reactor period.
- g. Coarse and Fine Rod digital position indicators returning to zero centimeters, (indicates magnet carriages are being driven down).
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The engaged lamps will remain deenergized and the UP limit lamps remain energized until the magnet carriages have been driven to their lower limi t. At the lower limi t, i the Engaged larps and DOWN limit lamps should
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energize, and the UP limit lamp should de-
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energize. 3 Monitor the decreasing neutron flux level by changing the Range
, Selector swi tches for channels 1 and 3 l
- 4. If the reactor is 'not to be immediately re-started, or if the console is to be lef t unattended, carry out the Shutdown Check- l off procedure.
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15 - L - B. Shutdown Checkof f Procedure
- 1. When all reds are fully withdrawn and the magnet carriages have been returned to their DOWN limit, deenergize reactor power by depressing the STOP button on the console.
- 2. Lock and remove the key from the console key switch.
3 Record the stable neutron flux level for Channels I, 2, and 3 Place the strip chart recorder to Standby.
- 4. Install and lo'ck the Cadmium shutdown rod into the Glory Hole.
I 5 Check the reactor skirt door's and console doors locked, and announce that the " Reactor is secured" to nearby persons. NOTE The neutron flux monitoring instruments and area radiation monitoring systems
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Page # AGN-2M : Serial #101 Run # Reactor j'.ations Log Date Reactor Operator Senior Reactor Operator Reason for Operation Authorized Experiments Special Operating Limitations Shield Water Temperature (*C) Estimated Excess Reactivity (%Ak/k) Prestartuo Checklist
- 1. All Reactor Neutron Detectors Working b. Channel 1: -
- 1. High voltage (VDC)
- 2. Radiation Survey: II. Zero check
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1 brat n I. I trip (%fs) Max. survey reading v. L w level trip (%fs) vi. Operate (cpm) Loca tion
- c. Channel 2:
- 1. Low level trip (%fp) 3 Safety Feature Checks: '
li. High level trip (%fp) emal column seal Manhole cover seal 111. High Cal. (%fp)
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Access pcrt fillers installed iv. Zero check (%fp) . Cd in glory hole v. Cal. (%fp) Vater temp. switch in place vi. Period scram (sec) Skirt area OK vil . Operate - (%fp)
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- d. Channel 3:
- 4. Area Radiation Monitor Check Alarm setpoint - {. Ca b t on check OK
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111. Low level trip' (%fs) Iv. High level trip (Ofs) 5 Control Rod Drive Settings Check v. Recorder OK vi. Opera te (%fs)
- 6. Nearby Persons Informed 9 Rod Control Interlocks and Scram
. Checks:
7 Key in Consolc and Power On
- a. Sequence interlocks OK
- b. Safety 1 Scram OK
- 8. Instrument Calibration and Level Trip c. Safety I and 2 scram OK Setpoints:
- a. No temporary wiring Installed 10. Cd Removed from the Glory Hole k
II. Calculate excess Completed by Approved by Senior Reactor Operator Reviewed by , Reactor Supervisor Date
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Page # AGN-201: Serial #101 Run # Reactor Operations Log Date Reactor Operator Senior Reactor Operator Activi ty
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MW TIME DETAILS
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o Operations Data i ' 1. Initial Control Rod Lower Limit Positions: 2. Power Limit Instrument Readings : Fiae control rod (cm) Channel 1 (cpm) Coarse control rod
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(cm) Channel 2 (%fp) > Channel 3 (amp) j~ 3. Channel Meter Readings from Neutron Source: , Channel All Rods Out Only Safety Rods in
#1 (cpm) i
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#2 (%fp)
#3 (amp) i,
- 4. Approach to Cri ticality Criticality Attained
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(Time) (Time) j 5. Power, Meter Readings, and Rod Positions: i ' Time Channel'1 Channel 2 Channel 3 Fine Con' trol Rod Coarse Control Rod 4 (cpm)- (% power) (amp) (cm) (cm) i l
i i i ! 4 l ! ! ! ( i < l . i
- 6. Remarks:
, Time 1 i l
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{ 7. Shutdown Check List. j a. Hanner e. Recorder standby /off j b. All. rods down f. Console and skirt doors locked
- c. Console power of f g. Keys returned to SRO
~ d. Cd in glory hole
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Time _, _ .' a b cld e f g' Ch 1(CPM) Ch 2 (%fp) Ch 3 (amps) Initial $
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j . VI. Logs and Records l l
- 1. The Reactor Operations Log shall be a comprehensive record of
- AGN-201 operations including:
- a. Pre-startup Checkof f data.
- b. Reactor startup and cri tical data. ..
- c. Power level changes.
- d. Reactor shutdowns and shutdown data,
- e. Experiments performed wi th the reactor,
- f. Installation and removal of Jumpers and/or temporary changes to reactor safety' circui try.
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- g. Reportable occurrences as defined in the faci 11ty's Technical Speci fica tions .
- h. Rod wort.h and other reactivity measurements.
- i. Principal maintenance operations including installation and removal of fuel elements and control rods.
J. Completion of tests and operations specified as Surveillance Requirements in' the facIIIty's Technical Specifications.
- k. Completion of radiation and contamination surveys.
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- 2. Format s
[ a. The Reactor Operations Log shall be maintained in a binder I and will normally consist of two sides of one data sheet.
- b. Normally, the three sheets will comprise the log for one day's entries. However, if more than one pre-startup checkoff is required; if insufficient space is available for the required Instrument readings or shutdown checklists; if additional i space is needed for remarks or entries required when the f , reactor is not in operation then the appropriate sheets may be added as necessary.
- c. Pages in the log shall be numbered consecutively and properly dated.
3 Log Entries
- a. Log entries shall be legible, and shall be made in ink.
- b. Erasures are not permi tted. If an error I.s made, a line will be drawn through the erroneous entry and Initialled by the
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person making the correction.
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- c. An asterisk (*) placed in the left hand margin will be used to denote a log entry for an unplanned reactor scram.
- d. Entries shall be made to properly document the information of j l
Items listed in A.1 above and in the case of A.I.g. Repor table i 1 Occurrences, sufficient Information must be recorded to i 1 administratively recons truct and evaluate the cause of the occurrence. j 1
- e. The log will be signed by the Reactor Operator and Senior Operator upon relief, and at the end of their operating shif t.
- f. Steady state instrument readings and rod positions shall be recorded following each power level change or once each hour, whichever occurs first.
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- l 4. Disposition
- a. The Reactor Operations Log will normally be maintained at the AGN-201 console. When the number of pages in the binder becomes excessive, completed logs may be removed from (ne bin
( binder and retained in a file by the Reactor Supervisor. I
- b. Retention of completed Reactor Operations Logs shall be in accordance wi th the facili ty's Technical Specifications.
- 5 Review
- a. The Reactor Operations Log shall be reviewed by the on-
' ; coming Reactor Operator and Senior Operator prior to the '
first reactor startup of the day or prior to relieving,
! whichever is applicable.
i l l B. Preventive Maintenance and Surveillance Log l l 1. A log containing the resul ts of the most recent Surveillance - I Activities as required by the facility's Technical Specifications j and data from routine tests and inspections required by the AGN-
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201 Maintenance and S torage Man,ual shall normally be maintained in the Control Room as directed by the Reactor Supervisor. Superseded records will be maintained in a file by the Reactor Supervisor for as long as required by the Technical Specifications. C. Radiation and Contamination Surveys -
- 1. Copies of completed radiation and contamination surveys of the AGN-201 facility shall be maintained as specified in the University's Radiological Controls Manual, and for as long as specified in the Technical Specifications.
D. O thers
- 1. Additional records shall be maintained as required by the facility's Technical Specifications.
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AGN-201 EMERGENCY PROCEDURES
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I. Reactor Scram A. Precautions ,
- 1. If an unintentional reactor scram occurs, the reactor should
- not be restarted until the cause of the scram is known and corrected.
- 2. If the cause of scram is not known or if maintenance is required
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to correct the cause, the Reactor Supervisor should be immediately i n formed. B. Procedure
- 1. Carry out the norrel Reactor Shutdown Procedure.
NOTE in addition to the shutdown requirements, 5, the Shutdewn Checkof f proced'ure shall . be performed if:
- a. The cause of the scram is not immediately known and/or cannot be immediately corrected.
- b. The cause of the scram was Instrument
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failure. (see Energency Procedure II)
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- c. The cause of scram was complete loss
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of electrical power, (see Emergency , l Procedure III).
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- 2. Determine the origin of the scram by observing the Scram /
Chassis annunciator lights and initiate the necessary corrective l action. l l
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f . II. Instrumentation Failure A. Precautions
- 1. Reactor startup shall not be attempted unless all three neutron flux monitoring channels are operating properly.
- 2. A channel of the neutron flux monitoring instruments may only be bypassed as provided for in the facility Technical Specifications
, and wi th approval of the Reactor Supervisor.
3 Following corrective maintenance on a neutron flux moni toring channel, as a minimum, the applicable portion of the Pre-startup Checkoff shall be performed to verify proper operation prior to reactor startup.
- 4. If corrective action involves neutron detector replacement or maintenance, a power calibration should be performed as soon as practical following the next reactor startup.
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. B. Procedure
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- 1. If the channel fault results in a reactor scram or if more than one instrument is suspected of abnormal operation: l l
- a. Shutdown the reactor and carry out the procedures of i l
Emergency Procedure I, Reactor Scram.
- b. Immediately notify the Reactor Supervisor,
- c. Initiate action to locate and correct the channel faul t.
- 2. If a channel facult does not result in a reactor scram or if abnormal operation is suspected:
- a. Immediately notify the Reactor Supervisor.
- b. If necessary, reactor operation may continue'within the provisions of the facility Technical Specifications and if approved by the Reactor Supervisor,
- c. Shutdown the reactor as soon as practical and ini tiate action to locate and correct the channel faul t.
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III. Loss of Electrical Power , A. Precautions
- 1. The AGN-201 is provided wi th two 115 vol t I.c power connections:
- a. Reactor Control Pover, providing electrical power to the i rod control circui try and the rod latch magnets.
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- b. Instrument Power, providing electrical power to the neutron flux monitoring channels, safety channels, and recorder.
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Loss of el ther power source, or both, will result in a reactor scram. However, loss of Reactor Control Power will prevent magnet carriage return to. the DOWN limi t until power can be restored and the console key switch again turned ON.
- 2. If the neutron flux troni toring instruments have been deenergizad,
! and a complete Pre-Startup Checkoff is not otherwise required, applicable portions of that procedure shall be performed to
, verify proper operation of the instruments and their associated
- trips prior to reactor startup.
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- B. Procedure
- 1. Complete Loss of Electrical Power
- a. Ensure that the Emergency Lights are operating properly.
, b. If Reactor Control Power can be immediately restored:
(1) Reenergize the conscie and verify that the reactor is
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shutdown by performing the normal Shutdown and Shutdown
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(2) Notify the Reactor Supervisor. .l l c. If Reactor Control Power cannot be imediately restored: l l .(1) Conduct a gamma radiation survey around the reactor to verify that the reactor is shutdown. f (2) Perform the Shutdown Checkoff proceduro to the maximum extent poss ible.
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4-(3) Immediately notify the Reactor Supervisor.
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(4) When Reactor Control Power can be restored, re-energize
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the console and perform the norrel Shutdown procedure.
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- d. Perform a complete Pre-startup Checkoff prior to the first reactor startup following restoration of electrical power.
- 2. Partial loss of Electrical Power
- a. If only Reactor Control Power is lost, the flux moni toring channels have not been dee,ergized, and power can be immediately restored:
(1) Restore Reactor Control Power, energize the console and verify that the reactor is shutdown.
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(2) If reactor operation is to be continued, the Shutdown Checkoff need not be performed and startup may be performed using the normal startup procedures.
- b. If only , Instrument Power is lost and power can be immediately j restored: i
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(1) Perform the nornal Shutdown and Shutdown Checkoff. (2) Restore Instrument Power. (3) If a complete Pre-startup Checkoff is not otherwise i
' required, perform applicable portions of prestartup
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procedure to verify proper operation of the Instruments and their associated trips prior to reactor startup.
- c. If either Reactor Control Power or Instrument Power, or both, cannot be immediately res tored, carry out step B.I of this ,
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IV. Control Rod Sys tem Malfunction
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> A. Precautions
- 1. If reactivity control of the AGN-201 is lost, the reactor shall i be immediately shutdown and shall remain shutdown until the I control facult is corrected.
- 2. in the extremely unlikely event that more than one control rod becomes s tuck at other than the fully withdrawn posi tion.
reactor shutdown should be assured by Cadmium loading of the Glory Hole. The amount of Cadmium inserted shall be equal to l 1 or greater than the totai reactivity worth of all the rods that I are stuck. i 3 A reactor startup shall not be attempted with a stuck control or safety rod. B. P rocedure
- 1. Failure of the FINE ROD to respond to control switch positions (IN or OUT'
- a. Alternately withdraw and insert the COARSE ROD to ascertain
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proper operation and to verify that reactivity control is
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- 1. If Coarse Rod control is normal'and continued reactor )
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operation is necessary, the reactor may continue to be ) operated upon approval of the Reactor Supervisor. I
. 1 However., the reactor should be shutdcwn as soon as l practical and the abnormality corre'cted.
- 2. If Coarse Rod operation is not normal, carry cut step ;
B.2 below.
- 2. Failure of the CDARSE ROD to respond to control switch posi tions (IN or OUT)
- a. Immediately shutdown the reactor and perform a Shutdown Checkoff.
- b. Inform the Reactor Supervisor and initiate action to locate and correct the sys tem faul t.
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3 Dropped Rod (Safety-1, Safety-2, or Coarse Rod)
- a. Immediately shutdown the reactor and perform the Shutdown Checkoff.
- b. Notify the Reactor Supervisor.
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- 4. Stuck Rod
- a. Immediately shutdown the reactor and perform a Shut down Checkoff.
- b. Inform the Reactor Supervisor.
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V. Reactivity Excursions and/or High Radiation A. Precautions
- 1. In the very improbable event of an uncontrolled nuclear excursion there is extremely little chance that at least one of the instrument scrams will not shut the reactor down. However, the
, reactor, in a very fast runaway, will actually shut itself down by its negative temperature coefficient. The occurrence of such , an incident will be indicated by a reactor scram and actuation
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of the automatic high radiation and evacuation alarm.
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- 2. If sufficient energy is released during the reactivity excursion to melt the Thermal Fuse, the lower reactor core half will drop approximately two inches and separate the assembly into two sub-critical masses. Subsequent startup will not be possible.
! 3 If an alarm from the Area Gamma Monitor (no reactivity excursion) is suspected as being the resul t of monitoring instrument mal-function, the alarm should be treated as valid until the absence of a radiation hazard is verified.
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B. Procedure
- 1. Positive Reactivity Excursion with no Apparent High Radiation levels
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- a. If a positive reactivity excursion results in a power level greater than 100 milli Watts but less than the scram setpoint, immediately withdraw the Coarse Control Rod to reduce power to 100 milli. Vatts or less.
- b. If a positive reactivi ty excursion occurs at a rate such that Coarse Control Rod withdrawal is insufficient compensation, or if the origin of the power level increase is unknown, immedia tely scram the reactor in accordance with the Shutdown Procedures.
Further operation of the reactor will not be permitted until approved by the Reactor Supervisor and the Reactor Administrator.
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- 2. Abnormal Reactivity Excursion and High Radiation Levels
- a. Immediately scram the reactor, push the Stop button, and remove the console key.
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- b. Carry out procedures delinated in the General Emergency
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Procedures as described in the final Safety Analysis Report. 3 Area Gamma Moni tor Alarm (No reactivi ty excursion)
- a. If operating, shutdown the reactor in accordance with the .
Shutdown Procedures.
- b. Evacuate all pe'rsonnel from the Reactor Room.
- c. Immediately notify the Radiation Safety Office, the Reactor l l
Supervisor, and the Reactor Administrator.
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- d. Conduct a radiation survey of the Reactor Room and, if !
applicable, the Centrol Room to determine the source of radi a tion .
- e. Further access to the affected area should be restricted until
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- authorized by the Radiation, Safety Office.
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, APPENDIX C
.. AGN 201 SURVEILLANCE SCHEDULE Quarterly Q.l. Shield tar.k water level channel check q.2. Shield tank water temperature channel check q.'3. Seismic displacement channel check Q.4. Emergency lighting check Semi-Annual SA.1. Thermal column water level check SA.2. Power calibration Annual A.I. Shield tank water level calibration A.2. Shield tank water temperature e-Sration A.3. Seismic displacement calibratic A.4. Visual Inspection; shield tank leakage check A.S. Safety and control rod scram time and insertion rate measurement A.6. Channel I count rate, plateau, safety circuit calibration
- A.7. Channel 2 level, period and safety circuit calibration A.S. Channel 3 level and safety circuit calibration
. A.9. Reactivity Heasurements
. a. Safety and control rod reactivity worths
- b. Total excess reactivity
- c. Shutdown margin
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- d. Maximum reactivity addition rate A.10. Reactor scram from loss of electrical power A.II. Radiation monitoring equipment calibration -
B i- Annual BA.I. Control rod drive assembly inspection BA.2. Visual inspection of the shield tank
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AGN 201 SURVEILLANCE DOCUMENTATION Quarterly item Date Checked initials Documentation Location Q.l. . Q.2. , 4 3. Q.4. . .
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AGN 201 SURVEILLANCE DOCUMENTATION
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Semi-Annual item Date Checked initials Documentation Location SA.I. SA.2.
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AGN 201 SURVElLLANCE DOCUMENTATION Annual
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Item Date Checked initials Documentation Location 5 A.I. . ! A.2. A.3 A.4. . , , 'A.5. A.6. i A.7.
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l AGN 201 SURVElLLANCE DOCUMENTATION )
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Bi-Annual l Item Date Checked initials Documentation Location l BA.I. BA.2.
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