ML20236T920
| ML20236T920 | |
| Person / Time | |
|---|---|
| Site: | Rhode Island Atomic Energy Commission |
| Issue date: | 07/17/1997 |
| From: | Tehan T RHODE ISLAND, STATE OF |
| To: | Mendonca M NRC (Affiliation Not Assigned) |
| References | |
| NUDOCS 9807290167 | |
| Download: ML20236T920 (21) | |
Text
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M STATE OF RHODE ISL.ND AND PROVIDENCE PLANTATIONS go f /
. RHODE ISLAND ATOMIC ENERGY COMMISSION' Nuclear Science Center South Ferry Road Narragansett, R.I. 02882-1197
- July 17,'1998 Docket No. 50-193
' Mr. Marvin Mendonca, Senior Project Manager Non-Power Reactors, Decommissioning and Environmental Project Directorate Division of Reactor Projects - III/IV/V U.S. Nuclear Regulatory Commission (NRC)
Washington, D.C. 20555
Dear Mr. Mendonca,
This letter and enclosures constitute the annual report required by the RINSC Technical Specifications (Section 6.8A). Enclosure 1 provides reactor operating statistics.
I provides information pertaining to inadvertent reactor shutdowns or scrams. discusses maintenance operations performed during the reporting period. describes changes to the facility carried out under the conditions of Section 50.59 of Chapter 10 of the Code of Federal Regulations. Lastly, enclosure 5 summarizes
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the radiological controls information. If there are any questions regarding this l
information, p ase call me a) 401-789-9391.
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. Terry Te n Director TT:cw
,;Q;J3 Enclosures (5)
Copy to:
T. Dragoun, Region One H. Knickle, Chairman NRSC L
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y ENCLOSURE 2 EMERGENCY SHUTDOWNS AND INADVF.RTENT SCRAMS The following is a listing of the emergency shutdowns and inadvertent scrams, including the reasons, which occurred during the 1997-98 reporting period. This information is required by Technical Specification 6.8.4.b.
DATE HUN #
LOGDOOK/PAGE REASON 7/28/97 7042 46/94 Inadvertent reactor scram caused by the Reactor Operator while atternpting to replace a burned out light bulb in the stop push button of the operating primary pump, thus de-energizing the pump. The loss of flow tripped the scram logic circuitry.
9/3/97 7057 46/111 Inadvertent reactor scram caused a relay in thi reactor 10/21/97 7072 46/130 pool temperature circuitry. He actual pool temperature 12/2/97 7097 47/07 was not near any scram setpoints. A new logic card has 3/10/98 7143 47/56 been ordered for replacement.
10/9/97 7066 46/123 Inadvertent reactor scram caused by Log N high period.
5/27/98 7162 47n9 Instrument malfunction (noise) due to high humidity. He 6/2/98 7164 47/82 reactor was not near criticality. Light in cabinet turned on to dry out instmment.
10/28/97 7077 46/135 Inadvertent reactor scram on a momentary loss of AC 11/24/97 7092 46/149 power. Associated with current weather conditions.
I1/4/97 7081 46/139 Inadvertent reactor scram during a power ascension from 12/9/97 7101 47/11 criticality due to the operator downscaling versus upscaling the wide range power channel. He reactor operators manually change ranges due to past problems with the instruments in automatic mode.
I1/17/97 7090 46/147 Inadvertent reactor scram caused by a switch failure on the coolant channel gate position. The gates, and thus the switches must be in the proper position during operation.
1/6/98 7108 47/19 Inadvertent reactor scram while attempting to shift 10/98 7109 47/20 operating primary pumps during a power ascension.
5/28/98 7163 47/81 Reactor seismic scram initiated by staff as part of the annual emergency / evacuation drill.
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ENCLOSURE 3 MAJOR MAINTENANCE OPERATIONS The following is a listing of the major maintenance operations performed in the 1997-98 reporting period which includes impact upon the safe operation of the reactor and the reasons for the corrective maintenance. This information is required by Technical Specification 6.8.4.c.
- 1. Regulating Blade Repairs On July 2,1997 during a normal reactor checkout it was observed that the regulating blade, while in " manual" would run to the full "in" position if withdrawn to any position. It was discovered that the circuitry had a faulted logic gate and the voltage was not correct. The logic gate was replaced and the voltage changed to the appropriate level by installing resistors. The regulating blade was again operable.
On August 5,1997 during a normal reactor checkout it was observed that the regulating blade, again while in " manual", would run to the full "out" position when the control system was turned on. An inverter chip in the control circuitry was replaced and the regulating blade was made operable prior to the normal reactor start-up.
- 2. Start-up Counter Repairs The RINSC reactor has experienced a number of repeated problems with the startup counter throughout the year. The major problem last reporting period was in-leakage of water into the housing and thus shorting out the instrument and giving erroneous readings. The housing was replaced with a new fabricated aluminum housing which appears to have solved the water problem. However, problems continue to arise with detector failures, electronic problems, etc.
As previously stated, if the start-up counter is inoperable for any reason, the reactor operation is ceased until the unit is returned to service.
- 3. Reactor Makeup Water Demineralized During the week of August 22-26,1997, the makeup water demineralized was taken out of service and replaced with two separate banks of filters and demineralizers. Each bank consists of pre-filters, demineralizers, and post filters to supply water equal to or greater than 1 megohm resistance to the reactor pool.
Y
./
ENCLOSURE 3 (cont)
MAJOR MAINTENANCE OPERATIONS The fill rate is approximately 20 gpm with one bank in service. Normally one bank is lined up to supply water to the pool, however, during abnormal conditions both banks may be lined up in parallel to supply a larger amount of water.
. Water conductivity monitoring is still available to the reactor operator in the control room while local water condition is given by a resistivity light (1 megohm). The banks are serviced by the vendor and are located in a non-radiation area. The RINSC staff no longer has the responsibility of regenerating l
resin with acid and caustic soda, thus removing potential safety hazards.
~ 4. Wide Range Power Instrument (PICO #1) Failure On September 18,1997 during a routine startup, the reactor operator was unable to compensate the power channel instrument (PICO #1). The startup was halted l and the investigation began. After various checks and disassembly, a disconnected cable (compensating voltage) was found. This was not easily.
identifiable due to the fact that the disconnected cable was an added section of cable which was not visible to the staff. Apparently, many years ago the cable g
required lengthening and instead of replacing the entire cable, a short piece was added. The problem was corrected and the instrument operated correctly.
Again, on May 13,1998, the reactor operator was unable to compensate PICO #1.
The instrument was removed from the pool and the compensating voltage cable i
.was not connected to the detector inside the housing. The detector assembly was cleaned up, checked out, and re-installed into the pool. The instrument was then -
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- 5. Primary Pump Oil Seals The RINSC facility, as part of an upgrade to 5 MW, installed two new primaiy l
pumps in the summer of 1996. Since their installation, there has been a slow and i -
steady oil leakage from the bearing housing. After monitoring the pumps over a 6 to 10 month period, the problem did not cease. The RINSC staff thought that perhaps the original oil level was too high and the leakage would stop when the
' level came down slightly. Finally.on December 18,1997, during opening rounds by the reactor operator,it was noticed that there was an excessive amount of oil on the pump base which indicated seal failure. The reactor was not operated and the pump supplier was contacted. The problem was discussed and both pumps received new oil seals.
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7' j
ENCLOSURE 3 (cont)
MAJOR MAINTENANCE OPERATIONS The RINSC staff again monitored the pump seals and leakage and found the problem to be continuing. The pump manufacturer (ITT) was notified and supplied little to no help in the matter, however the pump installers were quite willing to correct the problem. The installers again removed the pump, spray welded the shaft, and turned the shaft down to proper dimensions. The pump was re-installed again, monitored forleakage, and leakage was found.
Currently, the pump installer is working on a plan to manufacture a labyrinth type seal to hopefully cure the problem. Throughout this ordeal, the pump has been used during reactor operations due to the slow leakage of oil. The staff does not anticipated a catastrophic loss of the pump due to this repeated problem.-
- 6. Area Radiation Monitors In December of 1997 new Ludlum radiation monitors were installed to replace the existing monitors which were original equipment. The existing were found to be very difficult to adjust and calibrate and thus were deemed unreliable by the RINSC staff. The new system was installed and checked with a known source at varying distances to ensure proper operation. This entire replacement improved the entire radiation monitoring due to better placement of detectors as well as local readouts which are of great use (ALARA considerations) to the staff when in radiation areas.
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ENCLOSURE 4 FACILITY CHANGES - 10CFR50.59 REVIEW l
The following is a listing and description of 10CFR50.59 evaluations conducted during the 1996-97 reporting period. This information is required by Technical Specification 6.8.4.d.
l NONE THIS REPORTING PERIOD l
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Y ENCLOSURE 5 RADIOLOGICAL CONTROLS
- 1. Environmental Surveys Outside Facility - Technical Specification 6.8.4.e Quarterly TLD badges are deployed outside the reactor building in three separate locations. These locations are not frequented by the general public and therefore occupancy factors may be used to approximate the annual dose. The allowable external dose rates must be below 50 mrem. The doses are shown in the table below.
i LOCATION 3RD QTR 1997 4TH QTR 1997 IST QTR 1998 2ND QTR 1998 Northeast Wall 360 mrem 360 mrem 320 mrem 310 mrem Demin Door 120 mrem 190 mrem 200 mrem 50 mrem Heat Exchanger 30 mrem 50 mrem 20 mrem 0 mrem Door The northeast wall area is in a location where access is limited. Consequently, the j
general public will not frequent this area and appropriate occupancy factors can be used to approximate the annual dose. The dose in this area is due to storage in the reactor room and is present regardless of reactor operation. Assuming that the maximum time a member of the general public would be present in this location is 15 minutes / day. An occupancy factor of 0.01 can be used to obtain an annual I
dose of 13.5 mrem.
The demineralized and heat exchanger doors are restricted areas as well. Access to these two areas is limited and posted with a chain across the driveway.
Assuming that the maximum time a member of the general public would be present in this location is 15 minutes / day. This dose is only present when the reactor is in operation (approx. 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> / day). An occupancy factor of 0.04 can be used to obtain an annual dose of 22.4 mrem (demineralized door) and 4.0 mrem (heat exchanger door).
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- 2. Annual Exposures Exceeding 500 mrem - Technical Specification 6.8.4.f There were no personnel exposures greater than the above limit.
- 3. Radioactive Effluents - Technical Specification 6.8.4.g A.
Gascous effluent concentrations are documented on the Monthly Information Sheets (Form NSC-78) enclosed. The gaseous effluents, primarily Argon-41, are about 3-4% of the maximum permissible concentrations.
7, E,,
s ENCLOSURE 5 (cont)
RADIOLOGICAL CONTROLS B.
Liquid effluent concentrations released to the sewer are documented on the Sewer Disposal Record (Form NSC-52) and/or the Liquid Release (Form NSC-17). The concentrations are well below the monthly sewer limits.
The liquid effluent releases have been reduced considerably because the pool leak water is now being collected and returned to the pool. Below is a summary of the liquid effluents released.
DATE VOLUME ACTIVITY
% OF LIMIT ORIGIN 9/9/97 600 gal 0.25 mci 1.36 %
Pool / Lab Sinks
- Note: The water contains a mixture of isotopes, the principal ones being Cs-137, Sb-124, and H.
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