ML20216D343
| ML20216D343 | |
| Person / Time | |
|---|---|
| Site: | 05000131 |
| Issue date: | 03/29/1998 |
| From: | Phillips J DEPT. OF VETERANS AFFAIRS MEDICAL CENTER, OMAHA |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 636-151, NUDOCS 9804150260 | |
| Download: ML20216D343 (5) | |
Text
T DEPARTMENT OF VETERANS AFFAIRS Medical Center 4101 Woolworth Avenue Omaha NE 68105 March 29,1998 In Reply Refer To:
636/151 l
- U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 l
l SUBJ: 10 CFR 50.59 Annual Report 1
REF: License R-57 Docket #50-131 l
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The following report is submitted for the period January 1,1997 to December 31,1997 l
in accordance with Paragraph 50.59, Title 10, Code of Federal Regulations.
1 (a) The Radiation Protection Program (ALARA) has been rewritten into a single l
document. The program provides guidance on training, surveillance, and l
management responsibility for the use of radioactive materials.
(b) The quarterly fuel element inspections indicate nothing out of the ordinary. All elements appear to be in good condition. Annual inspection of the facility control rods found the rods to be in good condition. The reactor was power calibrated in accordance with the SOP. Both neutron detectors were within four percent of l
the thermally calibrated value. They were adjusted to match the calibrated value. The control rods were calibrated using the integral method. The total excess reactivity was determined to be $0.89, which is in compliance with TS 3.2(2). The shut down margin was $2.38 meeting the requirement stated in TS l
3.2(1). Time of Flight measurements show full rod inscrtion times no greater than 0.5 seconds for any of the three control rods. This is less than the limitation established in TS 3.3.1.
The NM-1000 system was inspected by a representative from Sorrento Electronics (formerly a subdivision of General Atomics)in November. The facility has had a history of period trips due to noise spikes. It was determined that the noise problems were occurring form the ground-side of the hospital power system.
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i U. S. Nuclear Regulatory Commission i
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Tabulation showing the energy generated by the reactor:
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Month Total KW-Hr January 339.3 February 498.6 March 1,002.3 April 87.3 May 222.9 j
June 252.1 July 308.1 l
August 328.8 l
September 0
l October 0
l November 273.1 December 76.2 l
Total 1996 3388.7 l
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During 1997 there were 11 unscheduled shutdowns:
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On Jan.10, a high level scram occurred when a sample was inserted into the pneumatic tube (PnT). The reactor had been allowed to run at 95%. When samples are introduced into the PnT, there can be an increase of 2-3% in power due to increased moderation. This occurs from a lessening of the void coefficient. The NM-1000 being a digital system will report and scram on any l
digitized reading reaching 100% of licensed power.
l ii. On Jan.13, a period scram occurred during a spike in the hospital power supply.
l iii. On Feb. 27, there were two period scrams due to noise spikes during approach j
to power. The reactor neutron detection systems are extremely sensitive. At the lower ranges in power, noise spikes can produce spurious period tripe. Since l
the second period trip occurred during the initial rise of the shim rod, the shim rod "up" switch was cleaned.
iv. On Mar.10, a period scram occurred during a spike in the hospital power supply.
v.
On Mar.13, a period scram occurred just after raising the safety rod to the full-out position. In response the rod drive switches and slide wires were inspected and cleaned. The safety rod drive components were checked and cleaned. The safety rod was again raisea. Another period scram occurred when the rod was approximately halfway out. The NM-1000 was inspected and the grounding plug
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U. S. Nuclear Regulatory Commission was tightened to insure a proper ground connection. Power traces at source level showed near rhythmic pulses of half a decade occurring about every 9 minutes. These pulses were also intermixed with smaller pulses. Tha reactor facility's electrical power is junctioned through NBW1 (NDP-1 BLDG #17A BKR#13). The NM-1000 uses breaker #32, the reactor console including the power to the NM-1000 recorder is on breaker #37. Traces at source level were taken of the following situations: (1) breaker #36 was turned off; (2) the NM-1000's two power cords were plugged in through breaker #23; (3) the power cord to the recorder was plugged into breaker #32; (4) the NM-1000 power received through a Voltrol Stabilizer (Type #T-57585); and (5) the recorder power through the same stabilizer. There was little change in the traces due to these changes. On Mar.14, a trace was performed and no spikes were present.
The reactor was put into operation. The matter is being studied further.
vi. On July 11, two period scrams occurred due to noise pulses in the hospital power supply.
vii. On July 14, period scram occurred from a short produced by a dirty reg. rod magnet down switch. The switch was cleaned. The rod drives were also j
inspected to make sure there was not a short due to the magnets power wire.
viii. On July 15, period scram due to a spike produced from a dirty shim rod switch.
The switch was inspected and cleaned, ix. On Sept.18, period scram due to noise spike in hospital power supply.
x.
On Nov.12, scram due to noise spike in hospital power supply resulted in a period trip.
4.
Corrective safety related maintenance performed this reporting period is as follows:
i.
On Sept.17,1997 during conduction of the daily reactor checklist, it was observed that the period scram reset light was on. Even after resetting the switch the scram indicator continued to switch to a scram mode. Upon inspection of the period channel, two vacuum tubes were found to be inoperable.
As a result, the OA2 and 12AU7A vacuum tubes were replaced. The period scram reset to normal.
- 11. Replaced safety, shim and reg. up and down switches (S6-S11). Replaced scram reset switches (S4, SS).
iii. Removed redundant wiring and Action Pak MDL used for previous recorder.
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iv. Some Scram indicator lights were changed. Below is a table of the current l
configuration-l Scram Console scram resat indicator l
NM PER PER l
NM HIGH REC i
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% POWER
% POWER HV HV i
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Replaced 7-2M127 diodes for HV supply to in-line GM.
i 5(a) There were no changes to the facility during 1997 as it is described in the SAR.
(b) The Committee reviewed a revised copy of the Radiation Protection Program (ALARA). Upon review the program was approved. It was also determined that the program does not constitute an unreviewed safety question as defined in 10CFR50.
l (c) There were no new or untried experiments or tests performed during the reporting period that are not described in the Safety Analysis Report.
6.
As mentioned above, the facility Radiation Protection Program (RPP) was rewritten to make it more clear and concise. Tha Reactor Safeguards Committee determined that the changes made in the RPP do not constitute an l
unreviewed safety question as specified in 10 CFR50.59.
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Summery of radioactive effluents released or discharged beyond the effective control of the license:
(a) Liquid-none (b) Airborne - 4 mci (c) Solid - none 8.
During 1997 there were no outside environmental radiological surveys performed.
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l Currently the reactor facility is without a Scientific Director. The permanent funding for this l
position is currently being sought from VA Headquarters.
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l The Reactor Facility continues to be utilized for medical research with emphasis on the I
current health needs of the veteran. The facility also continues to be used by the Fort Calhoun Nuclear Power Station as a part of their operator-training program, f
JOHN J. PHILLIPS Director l
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